L-MT-16-021, Changes to the Emergency Plan, Revision 47

Changes to the Emergency Plan, Revision 47

ML16120A350
Person / Time
Site:	Monticello
Issue date:	04/29/2016
From:	Gardner P Northern States Power Co, Xcel Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-MT-16-021
Download: ML16120A350 (126)

Text

(l Xcel Energy Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 April 29, 2016 L-MT-16-021 10 CFR 50.54(q)(5) 10 CFR 72.44(f)

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License No. DPR-22 Changes to the Monticello Nuclear Generating Plant (MNGP) Emergency Plan Pursuant to 10 CFR 50.54(q)(5) and 10 CFR 72.44(f), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy, submits a summary of changes to the MNGP Emergency Plan as Enclosure 1. The new revision to the Emergency Plan is provided in . The Emergency Plan changes have been reviewed and do not result in a reduction in the effectiveness of the Emergency Plan.

Summary of Commitments There are no new commitments and no revisions to existing commitments in this letter.

~~4 Peter A. Gardner Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company- Minnesota Enclosures (2) cc: Emergency Response Coordinator, Region Ill, USNRC (with Enclosures)

Resident Inspector, MNGP, USNRC (with Enclosure 1)

Administrator, Region Ill, USNRC (w/o Enclosures)

Chief, Plant Support Branch, Division of Reactor Safety, Region Ill, USNRC (with Enclosure 1)

Director, Division of Spent Fuel Management, Office of Nuclear Material Safety and Safeguards (with Enclosure 1)

ENCLOSURE 1 Monticello Nuclear Generating Plant Summary of Changes - 10 CFR 50.54(q)(5)

Description (Executive Summary)

The Emergency Plan is being revised as described below:

• To explicitly list the Backup Emergency Operating Facilities (EOFs) and capabilities as identified in the 2015 Emergency Preparedness (EP) Focused Self-Assessment Report.

• To reflect a transfer of assigned responsibilities based on MN Statute Chapter 12, regarding responsibility for overall protection of the general public and providing logistical support (food, water, shelter, etc.) during an emergency

• To remove a misleading asterisk next to the 30 minute Core/Thermal Hydraulics responder in Table 1 and clarify that requirement for the position to be augmented within 30 minutes

• Spelled out the acronym SAMG as Severe Accident Management Guidelines when first referenced in the document (considered an editorial change which does not require further evaluation)

• Corrected references to applicable Emergency Plan Sections in Appendix B which had changed during previous revisions and not been updated accordingly (considered an editorial change which does not require further evaluation)

Review of the above changes concluded that none of them result in a reduction in effectiveness of the Emergency Plan.

Change (1)

==

Description:==

During the 2015 EP Focused Self-Assessment, it was identified that the Monticello Nuclear Generating Plant (MNGP) Emergency Plan does not explicitly list facilities or capabilities of the Backup EOF as is currently identified for the primary EOF.Section IV.E.8.c of Appendix E provides performance-based criteria applicable to EOFs. The functions that the EOF has to address include the capability to obtain and display plant data and radiological information for each unit or plant that the facility serves. Section 7.1.5 is being revised to clearly identify these capabilities to be consistent with the EOF section.

Doc ID or (Procedure Number) I Revision Number: E-Pian I 47 Document

Title:

Emergency Plan Licensing/Basis Affected:

• App. E., Sec. IV, E. S.c. Provides performance based criteria applicable to all EOFs.

• NSIR/DPR-ISG-01, Interim Staff Guidance, Emergency Planning for Nuclear Power Plants

• 10 CFR 50.47 Page 1 of 4

Evaluation Determination Regulatory Compliance Basis:

This change updates the description of Back-up EOF facilities and capabilities to reflect the requirements for EOFs found in NSIR/DPR-ISG-01, Interim Staff Guidance, Emergency Planning for Nuclear Power Plants, with the exception of the following:

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

This item was not included based upon this facility being a backup. The Safety Evaluation Report (SER) approval for the Backup EOF does not require any specific staffing and activation time frames applicable for inclusion in the Emergency Plan.

Emergency Plan Effectiveness Basis:

The Back-up EOF facilities and capabilities being added to Revision 47 of the Emergency Plan were all present prior to the revision. No changes in the operational characteristics of the Back-up EOF were made as a result of clarifying the performance expectations. There is no reduction in effectiveness to the Emergency Plan.

Change (2)

==

Description:==

It was identified during an annual Emergency Plan review that the reference to the Area Civil Defense Groups and the State Emergency Services Mobile Support Area VI is no longer valid due to MN Statute Chapter 12 being enacted, which abolished these organizations. Although the responsibilities that were assigned to these sub-organizations were transferred over to the Minnesota Department of Public safety, MNGP's Emergency Plan was not updated accordingly.

Doc ID or {Procedure Number) I Revision Number: E-Pian /47 Document

Title:

Emergency Plan Licensing/Basis Affected:

• 10CFR50.47

• NUREG-0654-FEMA-REP-1, Rev 1 Evaluation Determination Regulatory Compliance Basis:

This change corrects an outdated reference to Area Civil Defense groups, an organization that was abolished under state law when Statute-Chapter 12 was enacted. The responsibilities for emergency response that were previously assigned to this organization were maintained and transferred over to the Minnesota Department of Public Safety. This assignment of responsibilities is supported by the current Letter of Agreement (LOA) on file between the State of Minnesota, Department of Public Safety, Division of Homeland Security and Emergency Management (HSEM), and Northern States Power Company-Minnesota for the Prairie Island and Monticello Nuclear Generating Plants. The LOA contains a direct reference to the Minnesota Emergency Operations Plan, as stated under the section titled "Responsibilities of HSEM":

"Coordinate and provide for the functions and responsibilities that are outlined in the most current version of the Minnesota Emergency Operations Plan (MEOP), the Hostile Action Based Supplement and the State of Minnesota Governor's Executive Order assigning emergency responsibilities to state agencies." Within the MEOP, Annex F "Health and Safety Protection" documents a summary of responsibilities with each of the Page 2 of 4

State of Minnesota sub-agencies listed. Per this annex, the Department of Public Safety is responsible for the below items, where P=Primary, C= Coordination and S=Support:

P: Overall coordination of state agency activities during the response and recovery phases of a public health emergency, including those incidents/accidents that result from the use and transport of hazardous materials (chemical and radiological), infectious agents (biological) as weapons of mass destruction, and nuclear generating plant incidents.

P: When requested, make hazardous materials chemical assessment teams and emergency response teams available to local authorities.

C: Overall responsibility for coordination of animal health protection, during an incident/accident that results from the use of hazardous materials (chemical and radiological), infectious agents (biological),

and nuclear generating plant incidents.

S: When needed, assure the provision of life and safety support (food, water, sanitation) in the mass sheltering and mass feeding of victims.

Emergency Plan Effectiveness Basis:

This change is being made to correct the responsibility assignments within the Emergency Plan based on the elimination of Area Civil Defense Groups under Minnesota statutes. The correction aligns with the current LOA on file with the State of Minnesota and the Minnesota Emergency Operations Plan. All of the responsibilities that were assigned to Area Civil Defense Groups are still maintained and have not been eliminated. This change is not a reduction in effectiveness of the Emergency Plan.

Change (3)

==

Description:==

During an Emergency Plan revision in 2012, an asterisk was added to Table 1 next to the 30-minute Core/Thermal Hydraulics responder. The note that pertains to all asterisked position states "May be provided by shift personnel assigned other functions." The justification was that this made it clearer that the Core/Thermal Hydraulics role can be performed by an on-shift personnel until a 30-minute responder arrives. The current E-Pian change will remove a misleading asterisk next to the 30 minute Core/Thermal Hydraulics responder in Table 1, to regain clarity that the position does indeed need to be augmented within 30 minutes and is not a collateral duty of an on-shift position not requiring augmentation.

Doc ID or (Procedure Number) I Revision Number: E-Pian I 47 Document

Title:

Emergency Plan Licensing/Basis Affected:

• 10 CFR 50.47

• 10 CFR 50 Appendix E, Sec. IV

• A.2-002 (Monticello On-Shift Staffing Analysis), Revision 0 and Revision 1 Evaluation Determination Regulatory Compliance Basis:

This change as described clarifies the requirement for the Core/Thermal Hydraulics position to be augmented within 30 minutes by someone other than an on-shift person. This clarification will eliminate Page 3 of 4

potential misinterpretations of the requirement and ensure future regulatory compliance regarding staffing of the site's Emergency Response Organization and established positions.

Emergency Plan Effectiveness Basis:

This revision to the Emergency Plan will clear up potential confusion regarding the staffing requirements of the Core/Thermal Hydraulics position. It removes the possible misinterpretation that the positon can be covered by an on-shift person performing another role and clarifies the requirement for the position to be augmented within 30 minutes. Removal of the asterisk does not change the total 30 minute responders identified in the table, which remains at nine. This change is not a reduction in effectiveness of the Emergency Plan.

Page 4 of 4

ENCLOSURE 2 Monticello Nuclear Generating Plant Emergency Plan, Revision 47 120 pages follow

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 1 of 120 Approval: PCR 01481745 INFORMATION USE Procedure should be available, but NOT necessarily at the work location.

Procedure may be performed from memory.

User remains responsible for procedure adherence.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 2 of 120 TABLE OF CONTENTS SECTION PAGE 1.0 DEFINITIONS AND ABBREVIATIONS ........................................................................... 3 2.0 SCOPE AND APPLICABILITY ........................................................................................ 5 3.0

SUMMARY

OF EMERGENCY PLAN ............................................................................. 6 4.0 EMERGENCY CLASSIFICATION SYSTEM ................................................................... 7 5.0 ORGANIZATIONAL CONTROL OF EMERGENCIES .................................................... 9 6.0 EMERGENCY MEASURES .......................................................................................... 35 7.0 EMERGENCY FACILITIES AND EQUIPMENT ............................................................ 56 8.0 MAINTAINING EMERGENCY PREPAREDNESS ........................................................ 87 9.0 RECOVERY .................................................................................................................. 91 10.0 APPENDIX A ................................................................................................................ 93 11.0 APPENDIX B ................................................................................................................ 97 12.0 ANNEX A .................................................................................................................... 105 13.0 FIGURES .................................................................................................................... 110 Figure 13.1 MONTICELLO PLANT EMERGENCY ORGANIZATION ............................. 110 Figure 13.2 INTERFACE BETWEEN FUNCTIONAL AREAS OF EMERGENCY ACTIVITY ..................................................................................................... 111 Figure 13.3 INTERFACE BETWEEN FUNCTIONAL AREAS OF EMERGENCY ACTIVITY DURING HOSTILE ACTION BASED EVENTS ........................... 112 Figure 13.4 HEALTH PHYSICS GROUP ORGANIZATION ............................................ 113 Figure 13.5 PLAN VIEW OF TECHNICAL SUPPORT CENTER, BACK-UP OPERATIONAL SUPPORT CENTER .......................................................... 114 Figure 13.6 PLAN VIEW OF THE EMERGENCY OPERATIONS FACILITY ................... 115 Figure 13.7 DIRECT DEDICATED TELEPHONES (HOT LINES) ................................... 116 Figure 13.8 PLAN VIEW OF OPERATIONAL SUPPORT CENTER ................................ 118 Figure 13.9

SUMMARY

OF SIGNIFICANT CHANGES ................................................... 120

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 3 of 120 1.0 DEFINITIONS AND ABBREVIATIONS 1.1 Assessment Action - Actions taken during or after an accident to obtain and process information necessary to make decisions regarding emergency measures.

1.2 Committed Dose Equivalent (CDE) refers to the dose received over the 50 year period following an intake of radioactive materials.

1.3 Committed Effective Dose Equivalent (CEDE) is the sum of the products of the weighted factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent to these organs or tissue.

1.4 Corrective Actions - Emergency measures taken to terminate an emergency situation at or near the source in order to prevent or minimize a radioactive release, e.g., shutting down equipment, firefighting, repair and damage control, etc.

1.5 Effective dose equivalent (EDE) is the sum of the product of the absorbed dose in tissue, quality factors, and all other necessary modifying factors at the location of interest.

1.6 Emergency Action Level (EAL) - A predetermined, site-specific, observable threshold for a plant Initiating Condition that places the plant in a given emergency class. An EAL can be: an instrument reading; an equipment status indicator; a measurable parameter (on-site or off-site); a discrete, observable event; results of an analyses; entry into specific emergency operating procedures; or another phenomenon which, if it occurs, indicates entry into a particular emergency class.

1.7 Emergency Director (ED) - The Plant Manager or his designee. This individual has overall responsibility and authority for managing the emergency effort within the plant. The ED will also manage efforts external to the plant until relieved of those responsibilities by the Emergency Manager.

1.8 Emergency Manager (EM) - This person is responsible to direct the overall MNGP emergency response effort. The EM will assume control of the Emergency Operations Facility and direct NSPM Emergency response efforts.

1.9 EOF - Emergency Operations Facility 1.10 Emergency Planning Zones - A defined area around the plant to facilitate emergency planning by state and local authorities, to assure that prompt and effective actions are taken to protect the public in the event of a release of radioactive material. It is defined for:

Plume Exposure Pathway - A 10 mile radius around the plant where the principal exposure source is: (1) whole body exposure to gamma radiation from the plume and from deposited material; and (2) inhalation exposure from the passing radioactive plume (Short Term Exposure).

Ingestion Exposure Pathway - A 50 mile radius around the plant where the principal exposure would be from the ingestion of contaminated water or foods such as milk or fresh vegetables (Long Term Exposure).

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 4 of 120 1.11 ERDS - Emergency Response Data System 1.12 Emergency Worker - Any individual who has an essential mission within or outside the plume exposure pathway emergency planning zone to protect the health and safety of the public who could be exposed to ionizing radiation from the plume or from its deposition. Some examples of emergency workers are: radiation monitoring personnel; traffic control personnel; evacuation vehicle drivers; fire and rescue personnel, including ambulance crews; medical facilities personnel; emergency operations center personnel; personnel carrying out backup alerting procedures; and essential services or utility personnel.

1.13 FTS - Federal Telephone System 1.14 Initiating Condition (IC) - One of a predetermined subset of nuclear power plant conditions when either the potential exists for a radiological emergency, or such an emergency has occurred.

1.15 Northern States Power Company - Minnesota (NSPM) - is the operator of the Monticello Nuclear Generating Plant.

1.16 OSC - Operational Support Center 1.17 PASS - Post-Accident Sampling System 1.18 Protective Actions - Emergency measures taken before or after a release of radioactive materials in order to prevent or minimize radiological exposures to the population.

1.19 Protective Action Guides (PAG) - Projected dose to individuals that warrants protective action prior to and/or following a radioactive release.

1.20 REC - Radiological Emergency Coordinator 1.21 Recovery Actions - Actions taken after an emergency to restore the plant to normal.

1.22 SEC - Shift Emergency Communicator 1.23 TSC - Technical Support Center 1.24 Total Effective Dose Equivalent (TEDE) is the sum of EDE and CEDE.

1.25 Xcel Energy is the owner of the Monticello Nuclear Generating Plant.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 5 of 120 2.0 SCOPE AND APPLICABILITY In accordance with license conditions, 10CFR Part 50, and NRC Regulatory guidance, the Northern States Power Company - Minnesota (NSPM) has developed and implemented an emergency response plan for the Monticello Nuclear Generating Plant (MNGP) and a joint off-site plan for the MNGP and the Prairie Island Nuclear Generating Plant. Xcel Energys wholly owned subsidiary NSPM operates the Monticello Nuclear Generating Plant. As asset owner, Xcel Energy retains all owner obligations.

In any emergency situation at Monticello, the initial response would be made by the site staff and, if needed, by local support agencies. It is expected that the initial response would have to extend for a period of hours, by which time the site staff would be augmented by other segments of the overall NSPM emergency response organization.

Once all centers are activated and the emergency organization is at full strength, the scope of the plant staff response will be reduced to the immediate plant site activities. This plan covers the actions and responsibilities of the Monticello plant staff and the local off-site support agencies.

The plan is directed toward the following areas:

2.1 Organization and actions within the plant to control and limit the consequences of an accident.

2.2 Organization and actions controlling site and initial off-site activities in the event of an uncontrolled release of radioactive material. This includes notification of and coordination with required off-site support agencies.

2.3 Identifying and evaluating the consequences of accidents that may occur and affect the safety of public and plant personnel.

2.4 Describing the protective action levels and actions that are required to protect the public and plant personnel in the event of an accident.

2.5 Considerations necessary for the purposes of re-entry and recovery.

2.6 Arrangements required for medical support in the event of injury.

2.7 The training necessary to assure adequate response to emergencies.

2.8 Notification systems used to notify the public in the event of an incident involving or potential of involving an off-site release.

The Emergency Plan is dependent upon the Emergency Plan Implementing Procedures for implementation. The procedures are the activating mechanism for the State Plan, which in turn activates the local government and service support agencies. Finally, the procedures reference standing plant operating, radiological control and security procedures in defining the plants response to the spectrum of emergency situations.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 6 of 120 3.0

SUMMARY

OF EMERGENCY PLAN Abnormal events, both realized and potential, requiring emergency preparedness response are classified into four classes of Emergency Action Levels. The four levels of emergency classes, in increasing order of severity are:

(1) Notification of Unusual Event (2) Alert (3) Site Area Emergency (4) General Emergency Each class requires specific immediate actions on the part of the plant staff in order to protect the public, plant personnel and property. As the severity level of the emergency increases, so does the response of the off-site agencies, in order to protect the public.

The lowest class (least severe) is the Notification of Unusual Event. This classification will be handled by plant personnel, with advisory notification to local and state authorities. The Alert Classification requires prompt notification of local and state authorities, which will place their various organizations in the standby mode. In both the Notification of Unusual Event and the Alert Classification, the plant staff is expected to restore the situation to normal without further or minimum involvement of off-site authorities. The two higher severity classes, the Site Area and the General Emergency, (the General Emergency being the most severe), require prompt notification of off-site authorities with immediate involvement of those organizations to assess the emergency situation and to implement the required protective actions for the general public.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 7 of 120 4.0 EMERGENCY CLASSIFICATION SYSTEM Emergency situations are classified according to severity, taking into consideration potential as well as actual events in process. Monticello Nuclear Generating Plant has and 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 has been exceeded. Upon identification of the appropriate emergency classification level the emergency condition will be promptly declared. The four standardized classifications are as follows:

1. Notification of Unusual Event (UE)

2. Alert

3. Site Area Emergency (SAE)

4. General Emergency (GE)

The rationale connecting the four action levels is to provide a mechanism for timely notification of events which could lead to significant consequences given subsequent operator error or equipment failure or which might be indicative of more serious conditions which are not yet fully realized. It should be noted that various events could require a graded scale of response. A minor incident could increase in severity and advance to the next class of emergency. For some events, the condition may be corrected before a classification has been made. In general, the following guidance applies. Classify the event as indicated and terminate the emergency once assessment shows that there were no consequences from the event and other termination criteria are met. For example, a momentary event, such as an ATWS or an earthquake, requires declaration even though the condition may have been resolved by the time the declaration is made.

The process of assessing and classifying an event as a specific type of emergency requires a broad knowledge of integrated plant instrumentation and response to various transients. The various Initiating Conditions (IC) for each emergency class are specified in Annex A of this plan. Annex A also includes the detailed set of Emergency Action Levels (EAL) applicable to the Monticello Nuclear Generating Plant. The EALs are the plant-specific indications, conditions, or instrument readings that are utilized to classify emergency conditions at the plant and were developed using the EAL development methodology found in NEI 99-01, Revision 4.

The ICs and EALs are grouped into the following symptom-based, event based, and barrier-based recognition categories.

R - Abnormal Rad Levels/Radiological Effluent C - Cold Shutdown/Refueling System Malfunction E - Independent Spent Fuel Storage Installations F - Fission Product Barrier Degradation H - Hazards S - System Malfunction

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 8 of 120 Following is a brief description of each emergency classification and its associated response level.

4.1 Notification of 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 has been initiated. No releases of radioactive material requiring off-site response or monitoring are expected unless further degradation of safety systems occurs.

The purpose of the Unusual Event emergency class is to (1) have the operating staff come to a state of readiness from the standpoint of emergency response in the event the handling of the initiating condition needs to be escalated to a more severe emergency class, and (2) provide for systematic handling of Unusual Events information and its related decision-making.

4.2 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 HOSTILE ACTION. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.

Alerts are the lowest level where emergency off-site response may be anticipated.

The purpose of the alert emergency class is to (1) assure emergency personnel are readily available to respond if the situation becomes more serious or to perform confirmatory radiation monitoring if required, (2) provide off-site authorities current status information, and (3) provide for activation of the TSC, OSC, and EOF or backup EOF.

4.3 Site Area Emergency Events are in process 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 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 Protective Action Guideline exposure levels beyond the site boundary.

The purpose of the site area emergency classification is to (1) assure that response centers are staffed; (2) assure that monitoring teams are dispatched; (3) assure that personnel required for evacuation of near-site areas are at duty stations if the situation becomes more serious, and (4) provide current information for and consultation with off-site authorities and public.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 9 of 120 4.4 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 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.

The purpose of the general emergency classification is to (1) initiate predetermined protective actions for the public, (2) provide continuous assessment of information from licensee and off-site measurements, (3) initiate additional measures as indicated by actual or potential releases, and (4) provide current information for and consultation with off-site authorities and public.

5.0 ORGANIZATIONAL CONTROL OF EMERGENCIES 5.1 Normal Site Organization 5.1.1 Site Management Organization The normal site organization is comprised of the plant organization and several other site support organizations. Each organizational area has a report directly to the Site Vice President or provides on-site functional support to the Site Vice President with an indirect reporting responsibility to the Site Vice President. These organizational areas include:

Plant (including Operations, Production Planning, Maintenance, Radiation Protection, Chemistry, and Human Performance and Safety).

Performance Assessment Business Support (including Document Control, Administrative Support, Emergency Preparedness, Accounting/Finance)

Training Nuclear Security Nuclear Oversight Information Technology Supply Chain Regulatory Affairs/Licensing Engineering (including Plant and Systems, Design, and Programs)

Human Resources Projects Responsibilities and authority of the various functional groups and individual positions are delineated in MNGP Administrative Directives.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 10 of 120 5.1.2 Shift Organization 5.1.2.1 Operations The Shift Manager holds a Senior Reactor Operator license and is the senior member of the Operations shift organization.

The Shift Manager has the responsibility and authority to direct operating activities of the plant IAW applicable regulations and procedures. The Shift Manager maintains the broadest perspective of operational conditions affecting plant safety and serves as or provides oversight of the technical advisor to the Control Room Supervisor and Control Room operations crew.

The Control Room Supervisor holds a Senior Reactor Operator license and reports to the Shift Manager. The Control Room Supervisor has the responsibility to supervise operating activities of the plant in accordance with applicable regulations and procedures under the direction of the Shift Manager.

A third SRO is qualified to support the shift manager in evaluation of off normal conditions.

Licensed Operators assigned to the Control Room perform plant manipulations and take direction from the Control Room Supervisor.

Auxiliary Operators outside the Control Room manipulate plant equipment and generally take direction from the Lead Plant Equipment and Control Room Operator or the Control Room Supervisor.

5.1.2.2 Fire Brigade The plant Fire Brigade is staffed by qualified Operators, Chemistry and Radiation Protection Technicians. The Fire Brigade is maintained in accordance with 4 AWI-08.01.01 (FIRE PREVENTION PRACTICES).

5.1.2.3 Radiation Protection Two Radiation Protection Technicians are assigned to each operating shift. The normal responsibilities of a shift Radiation Protection Technician are conducting routine and special radiological surveys, operation of plant Count Room equipment, access control and Radiation Work Permit preparation.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 11 of 120 5.1.2.4 Chemistry One Chemistry Technician is assigned to each operating shift.

The normal responsibilities of the shift Chemistry Technician are conducting routine and special chemistry sampling and analysis and operation of the plant Chemistry Lab.

5.1.2.5 Security (Shift Emergency Communicator)

Security personnel perform duties in accordance with the Security Plan. In addition, Security personnel on each shift are normally assigned the responsibility of primary Shift Emergency Communicator (SEC). As SEC, Security personnel perform emergency and non-emergency communications as directed by the Shift Manager. If dedicated Security personnel are not available to perform this function, other SEC qualified personnel may also be assigned responsibility of primary SEC.

5.1.3 Minimum Shift Staffing Minimum shift staffing SHALL be as indicated in Table 1, Minimum Shift Staffing And Capability For Additions For Nuclear Power Plant Emergencies.

5.1.4 Onshift Staffing Analysis The Onshift Staffing Analysis, A.2-002, provides the supporting documentation for developing the onshift staffing levels as indicated in Table 1, Minimum Shift Staffing and Capability for Additions for Nuclear Power.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 12 of 120 5.2 Emergency Organization and Responsibilities Under emergency conditions the organization of the site staff is altered to simplify communications channels and make more efficient use of personnel resources (refer to Figure 13.1, Monticello Plant Emergency Organization). The Monticello Emergency Response Organization (ERO) consists of various groups which staff the site Emergency Response Facilities including the Technical Support Center, Operational Support Center and Emergency Operations Facility (or backup EOF if necessary). Functional responsibilities of the various groups are described in this section. A detailed description of individual position responsibilities and leadership designations for the various groups is contained in Emergency Plan Implementing Procedure A.2-001 (EMERGENCY ORGANIZATION). A detailed description of personnel assignments is found in Form 5790-001-01 (EMERGENCY RESPONSE ORGANIZATION).

5.2.1 Technical Support Center Emergency Organization The Technical Support Center ERO consists of a Coordination and Direction Group and six subordinate groups. Each group is represented at the command table in the Technical Support Center.

When a transition point (Primary Containment flooding is required) in the Emergency Operating Procedures (EOPs) is reached, the duty Shift Manager and Operations Group Leader will make a joint decision to transition from the EOPs to the Severe Accident Management Guidelines (SAMGs). At this point, the Operations Group Leader would inform the TSC that they have relieved the duty Shift Manager as the Decision Maker.

The Decision Maker is designated to assess and select the strategies to be implemented. When using the SAMGs, the Operations Group Leader will act as the Decision Maker.

At the same time an Accident Management Team (AMT) is formed to utilize the SAMGs. The AMT is comprised of the following ERO positions; Operations Group Leader, Assistant Operations Group Leader, Engineering Coordinator, Nuclear Engineer, SPDS Operator, Trending Individual. AMT members are the Decision Maker and Evaluators. Evaluators are responsible for assessing control parameters, plant status, system status and EOP/SAMG actions and develop potential strategies that may be utilized to mitigate an event.

5.2.1.1 Direction and Control The Direction and Control Group consists of the Plant Manager and other senior plant management personnel designated by the Plant Manager. Designated members of this group staff the Emergency Director position in the TSC. Qualified Shift Managers are also included in this group and function as the interim Emergency Director during the initial stages of an emergency until relieved by a designated Emergency Director.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 13 of 120 The Emergency Director is responsible for overall emergency direction and control until relieved of that responsibility by the Emergency Manager at the EOF. Initially, the Shift Manager assumes the role of Emergency Director until relieved by a designated Emergency Director. The Emergency Director has the authority and responsibility to unilaterally initiate emergency response actions including making off-site protective action recommendations to authorities responsible for implementing off-site emergency measures.

Functional responsibilities of the Emergency Director include:

Recommend off-site protective measures. This responsibility may not be delegated and is relinquished to the Emergency Manager when the EOF is activated and staffed.

Overall direction and control of the Technical Support Center personnel and activities.

Ensure 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> coverage of key Emergency Response Organization positions in the TSC and OSC and continuity of personnel and material resources.

Make decisions regarding plant emergency response facility habitability including on-site protective actions (including KI use), personnel monitoring and evacuations.

Approval of emergency radiation exposures in excess of normal limits.

Communications with utility and off-site Emergency Response Organizations. EOF assumes responsibility for communications with off-site agencies when activated and staffed.

When the EOF is activated and the Emergency Manager position is staffed, the overall direction and control responsibility is transferred from the Emergency Director to the Emergency Manager. The Emergency Director retains authority and responsibility for decisions immediately affecting the plant including direction of plant emergency response and on-site protective measures.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 14 of 120 5.2.1.2 Radiation Protection and Chemistry Groups The Radiation Protection and Chemistry Groups consists of the Radiological Emergency Coordinator (REC) and members of the Radiation Protection and Chemistry Groups. The REC reports to the Emergency Director and is staffed by Radiation Protection and Chemistry Manager designees. The group is divided into three sections:

Monitoring Section Chemistry Section Off-site Dose Projection The Radiological Emergency Coordinator is the group leader and responsible for coordination of all on-site Radiation Protection and Chemistry emergency response activities.

The Monitoring Section consists of the Monitoring Section Leader, and members of the plant Radiation Protection/Chemistry staff and other NSPM personnel with demonstrated experience in radiation protection.

Responsibilities of the Monitoring Section include on-site radiological surveys, in-plant surveys, personnel exposure control, access control, and initial off-site radiological monitoring.

The Chemistry Section consists of the Chemistry Section Leader and members of the plant Chemistry staff.

Responsibilities of the Chemistry Section include chemistry sampling and analysis, plant and EOF Count Room operation, PASS sampling and core damage assessment, if necessary.

Chemistry personnel also function as off-site Dose Projection Specialists.

Off-site dose projection is performed by a Dose Projection Specialist. The Dose Projection Specialist positions are staffed by qualified personnel trained in off-site dose projection. The Dose Projection Specialist responsibilities include off-site dose projections, monitoring current and forecast meteorological information and providing off-site dose projection results to the REC or RPSS.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 15 of 120 5.2.1.3 Support Group The Support Group is staffed by members of the site Business Support Group, Supply Chain, and others designated by site management. The Support Group Leader reports to the Emergency Director and is responsible for on-site logistics support, emergency document control, print and drawing retrieval, administrative services, emergency procurement and warehouse support. The Support Group Leader is also responsible to coordinate the establishment of 24-hour ERO shift schedules as requested by the Emergency Director.

5.2.1.4 Operations Group The Operations Group consists of the Operations Group Leader and all members of the Operations staff including the duty operating crew, off-duty Shift Managers, Control Room Supervisors and all Operators. The Operations Group Leader is staffed by Shift Operation Manager designees and includes off-duty Shift Managers and Control Room Supervisors that report to the Emergency Director. The Operations Group Leader serves as the primary link between the TSC and Control Room for the purpose of providing technical and operational advice and support to the duty Control Room operating staff.

When a transition point (Primary Containment flooding is required) in the EOPs is reached, the duty Shift Manager and Operations Group Leader will make a joint decision to transition from the EOPs to the Severe Accident Management Guidelines (SAMGs). At this point, the Operations Group Leader would inform the TSC that they have relieved the duty Shift Manager as the Decision Maker. The Decision Maker is designated to assess and select the strategies to be implemented. When using the SAMGs, the Operations Group Leader will act as the Decision Maker and directs actions as specified in the SAMGs.

The Assistant Operations Group Leader is a member of the Accident Management Team (AMT). The Assistant Operations Group Leaders primary responsibility is to recommend actions to the Operations Group Leader based on the SAMGs.

The Assistant Operations Group Leader is an off-duty Shift Manager or Control Room Supervisor.

In addition, the Operations Group provides off-duty personnel to staff and support the Operational Support Center (OSC).

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 16 of 120 5.2.1.5 Engineering Group The Engineering Group consists of the Engineering Group Leader and members of the site Engineering Group. The Engineering Group Leader position is staffed by Director, Site Engineering designees and reports to the Emergency Director.

The Engineering Group Leader is responsible for overall direction of Engineering Group activities and assessment. The Engineering Coordinator reports to the Engineering Group Leader until the SAMGs are entered. When using the SAMGs the Engineering Coordinator becomes a member of the Accident Management Team (AMT) and reports to the Operations Group Leader. Responsibilities of the Engineering Coordinator include engineering evaluation of the event, assessment of inoperable systems or system components, development of accident mitigation strategies and parameter trending and analysis.

5.2.1.6 Maintenance Group The Maintenance Group consists of the Maintenance Group Leader and members of the Mechanical and Electrical Maintenance Groups including Instrument and Control and designated personnel capable of performing emergency tasks.

The Maintenance Group Leader position is staffed by Maintenance Manager designees and reports to the Emergency Director. The Maintenance Group Leader is responsible for the overall direction of corrective actions including damage control and emergency repairs to systems, components or equipment. The OSC Coordinator reports to the Maintenance Group Leader and is responsible for the coordination of emergency repair activities initiated out of the OSC.

5.2.1.7 Security Group The Security Group consists of the Security Group Leader, Security Lieutenant/SEC and members of the plant Security force. The Security Group Leader position is staffed by the Security Manager or designee and reports to the Emergency Director. The Security Group Leader is responsible for the direction and coordination of security emergency activities including personnel accountability, evacuation of on-site areas and site traffic control and access. The duty Shift Emergency Communicator reports to the Emergency Director (Shift Manager) and is responsible for making or assisting with initial off-site notification. The duty Shift Emergency Communicator may be a qualified SEC from other departments.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 17 of 120 5.2.1.8 Emergency Communications Group The Communications Group consists of the Lead Emergency Communicator and qualified Emergency Communicators from various site groups. Designated personnel are qualified to staff emergency communicator positions in the TSC, OSC, EOF and Control Room. Responsibilities of the Emergency Communicators include emergency notifications to off-site authorities, transmission of Emergency Follow-up Messages and other required information to off-site authorities, intra-utility communications and communications links between site emergency response facilities.

5.2.2 Operational Support Center Emergency Organization The OSC Emergency Response Organization includes personnel from Maintenance, Operations, Production Planning, Radiation Protection and Chemistry.

5.2.2.1 Coordination and Direction The OSC Coordinator is responsible for coordination of all OSC activities including dispatching repair teams, personnel accountability in the OSC and OSC habitability. The OSC Coordinator position is staffed by experienced Maintenance, Production Planning, or Operations personnel and reports to the Maintenance Group Leader.

5.2.2.2 Mechanical Maintenance The Mechanical Maintenance Group consists of Machinists, Steamfitter - Welders, Riggers and Repairmen from the plant Maintenance Department, as well as designated personnel capable of performing emergency tasks. They are responsible for emergency repair activities under the direction of the OSC Coordinator.

5.2.2.3 Electrical Maintenance The Electrical Maintenance Group consists of the Electrical Maintenance Supervisor and Station Electricians from the plant Maintenance Department, as well as designated personnel capable of performing emergency tasks. They are responsible for emergency repair activities under the direction of the OSC Coordinator.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 18 of 120 5.2.2.4 Instrument & Control The I&C Group consists of the I&C Maintenance Supervisor and I&C Specialists from the plant Maintenance Department, as well as designated personnel capable of performing emergency tasks. They are responsible for emergency repairs under the direction of the OSC Coordinator.

5.2.2.5 Radiation Protection The Radiation Protection Group consists of the Radiation Protection Coordinator, Radiation Protection Technicians, Chemistry Technicians, and other NSPM personnel with radiation protection/chemistry experience and personnel designated and trained to perform on-site, out of plant and off-site radiological monitoring surveys. Radiation protection responsibilities include: OSC RP support, staffing Main Access Control, in-plant emergency team support, in-plant and out-plant radiological surveys, Emergency Response Center habitability, off-site environmental monitoring, Assembly Point staffing and Fire Brigade support (as necessary).

5.2.2.6 Operations The Operations Group consists of available non-duty Shift Managers, Control Room Supervisors, Operators and other personnel reporting to the Operations Manager. Their responsibilities include OSC operations support, in-plant emergency teams, augment the duty Control Room staff (as necessary) and Fire Brigade support (as necessary).

5.2.3 EOF Emergency Organization The EOF Emergency Organization consists of a Direction and Control Group and four subordinate groups. The EOF Emergency Organization is staffed by personnel from the NSPM organization.

5.2.3.1 Direction and Control The Direction and Control Group consists of Site Senior Management personnel. Designated members of this group staff the Emergency Manager position in the EOF. The Emergency Manager is responsible for overall direction and control of the utilities emergency response effort. The Emergency Manager relieves the Emergency Director of the following responsibilities:

Off-site dose projections and coordination and direction of off-site radiological monitoring teams.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 19 of 120 Declaration of new emergency classifications (the Control Room and Emergency Director retain the primary responsibility for re-classification and make recommendations to the Emergency Manager who has the responsibility to declare the new emergency class).

Communications with off-site authorities including Federal, State, and local authorities and Xcel Energy/NSPM executive management.

In addition, the Emergency Manager assumes the authority and responsibility to provide protective action recommendations to authorities responsible for implementing off-site emergency measures. Other responsibilities of the Emergency Manager include:

Coordinate the emergency response efforts of other utility personnel assisting the site organization.

Obtain and coordinate the services of outside consultants and vendors.

Advise Xcel Energy/NSPM executive management on matters related to emergency response efforts and needed resources to support the effort.

5.2.3.2 Technical Support Group The EOF Technical Support Group consists of select personnel from various site groups. The Technical Support Supervisor is staffed by senior site personnel and reports to the Emergency Manager. The Technical Support Group is responsible for trending critical parameters, engineering evaluation in support of the TSC Engineering Group, technical assessment and advising the Emergency Manager on technical matters related to the event.

5.2.3.3 Radiation Protection Support Group The Radiation Protection Support Group is staffed by Radiation Protection Technicians, Chemistry Technicians, and other NSPM personnel with radiation protection (chemistry) experience and personnel designated and trained to perform on-site, out of plant and off-site radiological monitoring surveys.

The Radiation Protection Support Supervisor position is staffed by NSPM personnel with demonstrated experience in radiation protection and reports to the Emergency Manager. The Radiation Protection Support Group includes plant Chemistry personnel for off-site dose projection and EOF Count Room operation and designated personnel who function as sample

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 20 of 120 couriers and drivers for off-site radiological monitoring teams.

Radiation Protection Support Group responsibilities include:

Direction and coordination of the utility off-site radiological monitoring teams.

Off-site dose projection.

EOF Count Room activation and operation.

EOF habitability, personnel monitoring and decontamination (as necessary).

Communications with State Emergency Operation Center personnel on matters related to dose projections and off-site protective action recommendations.

Staffing the Health Physics Network (HPN) and communications with the NRC (as necessary).

The Radiation Protection Support Supervisor advises the Emergency Manager on matters related to actual or potential radiological impact on the environment, off-site protective action recommendations, and EOF habitability.

5.2.3.4 EOF General Staff, Logistics, and Support Group The EOF general staff consists of the EOF Coordinator, off-site communicators, administrative and logistics support personnel.

The EOF Coordinator position is staffed by designated NSPM personnel and reports to the Emergency Manager. The EOF Coordinator is responsible for activation and operation of the EOF and assists the Emergency Manager with administrative duties.

The off-site communicators, EOF Security Coordinator, Agency Liaison and Administrative Staff report to the EOF Coordinator.

The off-site communicators are responsible for communications with Federal, State and Local authorities as directed by the Emergency Manager.

The Administrative Staff is responsible for emergency document control, recording and document distribution in the EOF.

The off-site Agency Liaison is responsible to serve as the initial interface with off-site (Non-MNGP/NSPM) Emergency Organizations (e.g. NRC Incident Response Team) responding to the EOF.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 21 of 120 The EOF Security Group is staffed by personnel from the Site Security Group. The EOF Security Coordinator reports to the EOF Coordinator. Responsibilities of EOF Security include EOF access, dosimetry issuance to EOF personnel and Fitness-for-duty assessment (if required during off-hours activations).

5.3 Emergency Response Organization Augmentation The Emergency Response Organization augmentation goals are outlined in Table 1.

The augmentation of each functional area and the methods used to accomplish ERO augmentation are described in this section.

5.3.1 ERO Augmentation Description and Goals 5.3.1.1 Plant Operations and Operational Assessment The duty Operations crew retains the responsibility for plant operation throughout an emergency situation. When in Severe Accident Management Guidelines (SAMGs) the duty operations staff implements the actions as directed by the SAMGs.

Non-duty Operations personnel in the TSC and OSC will augment the duty Operations staff.

The responsibilities of the non-duty Operations personnel include operational assessment, under the direction of the Emergency Director in the TSC, and support of emergency repair and corrective action efforts in the OSC including Fire Brigade support.

When a transition point (Primary Containment flooding is required) in the EOPs is reached, the duty Shift Manager and Operations Group Leader will make a joint decision to transition from the EOPs to the SAMGs. At this point, the Operations Group Leader would inform the TSC that they have relieved the duty Shift Manager as the Decision Maker. The Decision Maker is designated to assess and select the strategies to be implemented. When using the SAMGs, the Operations Group Leader will act as the Decision Maker and direct control room response as specified in the SAMGs. The Assistant Operations Group Leader is a member of the Accident Management Team (AMT).

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 22 of 120 5.3.1.2 Emergency Direction and Control The duty Shift Manager initially assumes the duties and responsibilities of the Emergency Director until relieved by a designated Emergency Director. Once relieved, the duty Shift Managers primary focus returns to overall coordination of emergency response activities of the duty Operations crew.

The Emergency Director assumes overall responsibility for the utility emergency response activities until relieved by the Emergency Manager. For non-security related events, the Emergency Manager should take over responsibilities in about 60 minutes from the declaration of an emergency, at the Primary EOF. Once relieved, the Emergency Directors primary focus is on plant operation and overall direction of plant emergency response activities in plant emergency response facilities including the on-site Assembly Point. The Emergency Manager assumes overall authority and responsibility for the utilitys emergency response activities from the Emergency Director and retains this authority until the event is terminated or the transition to recovery is complete.

5.3.1.3 Notification and Communications The Shift Emergency Communicator (SEC) is responsible for the performance of initial emergency notifications to the State, counties, NRC and other off-site and utility support organizations. The duty SEC will be augmented within approximately 30 minutes with one additional Emergency Communicator and within 60 minutes with two more Emergency Communicators. In about 60 minutes, the EOF should assume responsibility for communications with off-site authorities.

5.3.1.4 Radiological Assessment and Protective Actions The Shift Radiation Protection Technician is responsible for initial radiological assessment including in-plant radiological surveys. The shift Chemistry Technician is responsible for initial chemistry sampling, sample analysis, and off-site dose projection operation if required.

The Shift Radiation Protection Technician will be augmented by three additional Radiation Protection personnel within approximately 30 minutes and four more Radiation Protection personnel within approximately 60 minutes. The responsibilities of these additional Radiation Protection personnel include in-plant surveys, access control, and off-site radiological monitoring.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 23 of 120 In addition, a qualified Radiological Emergency Coordinator (REC) will augment the shift RP staff within approximately 30 minutes. The REC is responsible for overall coordination of the Radiation Protection and Chemistry Groups emergency response activities.

The Shift Chemistry Technician will be augmented with one additional Chemist within approximately 60 minutes.

The plant Radiation Protection staff will be augmented by Radiation Protection Technicians from the Prairie Island Nuclear Plant within approximately three hours.

Responsibilities of sister plant Rad Prot Technicians include off-site radiological monitoring and sampling under the direction of the Radiation Protection Support Supervisor and Emergency Manager at the EOF.

5.3.1.5 Engineering and Technical Support Technical support for the shift Operations staff is initially provided by the duty Shift Manager or Shift Technical Advisor (when staffed separately on-shift). The plant Engineering and Operations staff will provide additional technical support personnel, knowledgeable in the areas of nuclear core/thermal hydraulics, electrical, and mechanical engineering.

Augmentation in this area includes the addition of the core/thermal hydraulics position within about 30 minutes and two more members of the TSC Engineering Staff within approximately one hour. The TSC Engineering Staff is responsible to provide technical support to the Control Room staff under the direction of the Emergency Director.

Specific individuals from the TSC Engineering Staff are also members of an Accident Management Team (AMT). They will evaluate parameters used within the SAMGs.

5.3.1.6 Repair and Corrective Actions The duty Operations crew is initially responsible for any emergency repair and corrective actions that may be immediately required prior to ERO augmentation. After augmentation, repair and corrective actions are the responsibility of the Maintenance Group under the direction of the Emergency Director. The Maintenance Group consists of mechanical and electrical maintenance personnel including instrument and control technicians, as well as designated personnel capable of performing emergency tasks. Personnel from these groups report to the OSC where they are assigned corrective action tasks by the OSC Coordinator.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 24 of 120 Augmentation in the maintenance area includes the addition of one mechanical maintenance person within about 60 minutes, one I&C Group member within about 30 minutes and two electrical maintenance personnel, one within about 30 minutes and the other within 60 minutes.

5.3.1.7 Firefighting A shift fire brigade trained and equipped for fire fighting ensures adequate manual fire fighting capability for all areas of the plant containing structures, systems or components important to safety.

Firefighting is the responsibility of the shift Fire Brigade. The shift Fire Brigade may be augmented by non-duty, Fire Brigade qualified, personnel available from the OSC. Additional support for the Fire Brigade is also available from the local Fire Departments upon request.

5.3.1.8 Rescue Operations and First Aid The shift Fire Brigade is initially responsible for any immediate search and rescue operations or medical emergency response that may be required. After ERO augmentation, additional support for search and rescue and medical emergency response is available from the OSC staff under the direction of the OSC Coordinator.

5.3.1.9 Site Access Control, Accountability and Security Site access, personnel accountability, coordination of evacuees and on-site traffic control are the responsibilities of the site Security Group. Augmentation of the on-duty, shift Security Force will be as directed by the Emergency Director and Security Group Leader.

5.3.1.10 Administrative and Logistics Support The Support Group is responsible for administrative support, document control and logistics in the on-site emergency response facilities.

5.3.1.11 Environmental Monitoring Support The site Radiation Protection/Chemistry Group is responsible to coordinate post-accident environs monitoring with the REMP contractor.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 25 of 120 5.3.2 Augmentation Methods In order to ensure the goals of Table 1 (Minimum Shift Staffing and Capability for Additions for Nuclear Power Plant Emergencies ) can be achieved, two methods have been developed for the notification of site emergency response personnel. The methods include an Emergency Response Organization (ERO) Pager Network and automatic callout system for select site groups such as Business Support, Operations, Maintenance, Radiation Protection, and Chemistry.

The ERO Pager Network consists of a commercial pager system which provides coverage to an area of approximately 75 mile radius of Minneapolis. This area includes both the Monticello and Prairie Island nuclear sites. The system may be accessed via commercial telephone and has primary and backup telephone numbers. Designated ERO personnel carry ERO pagers. This group includes:

Emergency Directors TSC Group Leaders TSC Engineering Staff Emergency Communicators Radiation Protection/Chemistry personnel Operations Shift Managers Maintenance Supervision and Engineers Support Group personnel Emergency Managers EOF Technical Engineering personnel EOF Radiation Protection Support personnel Each pager in the network may be activated individually and all pagers in the network may be activated by one telephone (group) call.

To supplement the Pager Network, an automated callout system is utilized for site groups, including Operations, Maintenance, Support Group, Radiation Protection/Chemistry. The ERO roster utilized by the automated callout system is reviewed and updated quarterly.

Whether contacted by pager or other means, ERO personnel are instructed to respond immediately to the event.

If an emergency has been declared based on a security event or security threat, onsite MNGP ERO personnel may be instructed to duck and cover until the threat has passed or, if safe, report to an alternate near site location to standby for activation of their respective facility. ERO members

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 26 of 120 who are off-site will be instructed to report to the EOF. They will not be instructed to staff the affected facilities until it is safe to do so.

5.4 Augmentation of On-Site Emergency Organization 5.4.1 Licensee Headquarters Support This augmentation capability is completely described in the Off-site Nuclear Emergency Plan. The purpose of this capability is to support the plant and EOF in as many areas as is practical. Such areas include: Government Agency Interface, Logistics Support, Technical Analysis, News Media Interface, Xcel Energy and NSPM Executive Management Interface.

5.4.2 Local Support Services 5.4.2.1 Monticello Fire Department The Monticello Fire Department will provide fire and rescue assistance upon request in the event of a fire at the plant and Hostile Action Based (HAB) event. The Monticello Fire Department will be the lead fire agency for all emergencies in the City of Monticello. For a HAB event, the fire department will deploy a representative to the Incident Command Post dependent upon type, location, and scope of the incident, once scene safety is established. The MNGP Fire Brigade Leader will work with the Fire Department Leader to provide local coordination of fire fighting and non-fire fighting activities. Non-fire fighting tasks may include actions such as spraying water to contain radiological releases or directing water to plant locations for refilling/cooling purposes. In all cases, such operations may begin only when the radiological and security threats are mitigated to insure the safety of both plant personnel and fire fighters.

The City of Monticello has agreements in place to call upon resources of other agencies to assist in the response to a HAB event. The Monticello Fire Department will coordinate with other local fire departments to the extent necessary and consistent with the plans. If the fire department requires assistance to respond to an event at MNGP, including an HAB event, the Monticello Fire Department will be supplemented by resources available pursuant to the North Suburban Mutual Aid Agreement and the Minnesota Fire and Rescue Mutual Aid Plan.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 27 of 120 5.4.2.2 CentraCare Health Monticello CentraCare Health Monticello, also referred to as local hospital, serves as the principal off-site medical facility for initial treatment of radiation complicated injury or illness. In addition, North Memorial Hospital (in Minneapolis) has been designated as the definitive care center for injuries or illness that require services/facilities that the local hospital is unable to provide. Emergency procedures have been established at both hospitals and training of hospital personnel is accomplished periodically.

A complete description of local medical support services may be found in the Off-site Nuclear Emergency Plan.

5.4.2.3 Burlington Northern and Santa Fe Railway The Burlington Northern and Santa Fe Railway Dispatcher will stop and re-route trains away from the plant site, if necessary.

5.4.2.4 Ambulance Service There are two ambulance services that are available to provide service to the Monticello Nuclear Generating Plant.

CentraCare Health ambulance service will provide ambulatory services and be the lead Emergency Medical Service (EMS) agency for all emergencies at MNGP. For a Hostile Action Based (HAB) event, CentraCare Health ambulance service will deploy a representative to the Incident Command Post dependent upon type, location, and scope of the incident, once scene safety is established. The CentraCare Health representative will work under the direction and control of the Incident Commander, which shall be either the Wright County Sheriff's Office or Monticello Fire Department, dependent on the type of incident.

CentraCare Health ambulance service may utilize mutual aid to supplement their response. This mutual aid includes the relationships with CentraCare-St. Cloud Hospital and North Memorial Medical Center. If the response to an emergency, including a HAB event, requires additional resources, CentraCare Health will engage the resources of its affiliate, CentraCare-St. Cloud Hospital as needed and as available.

A complete description of response capabilities, organizational resources, activation plans, designations of emergency operations centers and letters of agreement for the organizations mentioned above are available in the Minnesota Emergency Operations Plan.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 28 of 120 5.4.2.5 Local Law Enforcement For a HAB event, Wright County Sheriff's Office will set up an Incident Command Post (ICP) near the site. The pre-designated ICP location(s) have been identified; however, selection will depend on the incident. The Wright County Sheriff's Office maintains the list of potential ICP sites and will be responsible for designating the site during a response and notifying the other agencies responding to the location. The Incident Command Post should be responsible for tracking resources and personnel at or near the site.

Unified Command will be established and includes the Wright and Sherburne Counties, state, federal and utility personnel.

For a HAB event, communication will be established between the Incident Commander and plant security and operations as soon as possible. The Wright County Sheriff's Office Tactical Response Team will be the lead tactical response operations group coordinator and coordinate the tactical law enforcement response with Command. If the response to an emergency, including a HAB event, requires additional resources, Wright County and the Sheriff have agreements in place to call upon the resources of neighboring law enforcement and emergency response service providers to assist. Wright County Sheriff's Office may request tactical team resources as needed from:

Minnesota State Patrol Special Response Team, Sherburne County ERT, and FBI SWAT.

The initial hostile action response goals are:

Maintain vital plant systems to prevent a release of radioactive materials, protection of on-site workforce, neutralizing the adversaries and restoring plant operating conditions.

Law enforcement tactical operational priorities include:

Securing a perimeter around the site, immediate containment of vital areas, sweep and securing of vital areas, safe movement of critical workers on the site, neutralizing adversaries, protection/evacuation of the on-site workforce, sweep of protected area and owner controlled area.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 29 of 120 Sherburne County will support the ICP with a Sherburne County Sheriff's Representative. If the response to an emergency, including a HAB event, requires additional resources, Sherburne County Sheriff's Department and Sherburne County Emergency Services have agreements in place to call upon the resources of neighboring law enforcement and emergency response service providers to assist.

5.5 Coordination with Participating Government Agencies Appropriate State and Local government emergency plans have been developed in support of the Monticello emergency preparedness effort. Figure 13.2, Interface Between Functional Areas of Emergency Activity, shows the interface relationships between functional areas of emergency activity. Figure 13.3, Interface Between Functional Areas of Emergency Activity During Hostile Action Based Events, illustrates the interface relationships between on-site and off-site functional areas of emergency response during events requiring use of an off-site Incident Command Post.

5.5.1 Minnesota Department of Public Safety The Minnesota Department of Public Safety has the responsibility for notification and coordination of state agencies in the event of a major emergency at Monticello. In the event of an emergency situation at the plant, the State Emergency Operations Center is activated and the Minnesota Duty Officer will immediately call the Department of Health, Governors Office, and other state agencies with emergency assignments to coordinate the implementation of any emergency procedures. The state agencies responsible for emergency procedures have established a system of 24-hour communications.

The state agencies and local government agencies are responsible for protecting the general public and providing logistical support such as food, temporary quarters, water, and sanitary facilities in the event that evacuation and isolation is required.

5.5.2 Minnesota Health Department The Minnesota Department of Health (MDH) is responsible for providing radiological expertise in the State Emergency Operations Center in conjunction with the Department of Public Safety.

The Minnesota Department of Health will interpret data and participate in recommending protective actions to the Governors Authorized Representative.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 30 of 120 5.5.3 Wright County Sheriff In the event of an accident the Sheriff of Wright County will notify all necessary civil support groups in Wright County. The sheriff or designee is also responsible for protection of the general public and can provide personnel and equipment for evacuation, relocation and isolation of affected areas.

5.5.4 Monticello Radiological Emergency Preparedness The Monticello Radiological Emergency Preparedness has the responsibility for coordination of city populace in the event of a major emergency that affects the city of Monticello.

5.5.5 U.S. Department of Energy Protection for the general public is provided through the Nuclear/Radiological Incident Annex of the National Response Framework.

Under this plan, individual DOE officers are assigned geographic responsibilities for incidents occurring in their region. Their immediate objective is to rapidly dispatch a team of specialists to the incident site and assist the state in evaluating the hazard. The DOE will then provide the materials and equipment to counteract and control any acute hazard, and establish communications with local authorities.

5.5.6 Sherburne County Sheriff In the event of an accident, the Sheriff of Sherburne County will notify all necessary civil support groups in Sherburne County. The sheriff or designee is also responsible for protection of the general public and can provide personnel and equipment for evacuation, relocation and isolation of affected areas.

5.5.7 Minnesota State Patrol The State Patrol may assist with the protection of the general public by providing personnel and equipment to re-route traffic in the event of a general emergency. Plans have been made for re-routing federal and state highways. Signs and equipment required for re-routing will be stored in the areas where they would be needed to facilitate highway closings.

5.5.8 Minnesota Department of Transportation Assist the State Patrol in blocking and re-routing traffic around the plant site. The Minnesota Department of Transportation has the necessary personnel, vehicles, signals, and barriers for establishing and maintaining detour routes.

5.5.9 City of Minneapolis Water Department The Water Department can shut off water intakes, if necessary.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 31 of 120 5.5.10 City of St. Paul Water Department The Water Department can shut off water intakes, if necessary.

A complete description of response capabilities, organizational resources, activation plans, designations of emergency operations centers and letters of agreement for the organizations mentioned above are available in the Minnesota Emergency Operations Plan.

5.6 Coordination with Other Participating Agencies 5.6.1 Institute Of Nuclear Power Operations (INPO)

INPO will coordinate requests from other utility INPO members and participants. They will notify NEI and EPRI of events, maintain an emergency resource capability and information on industry assistance capabilities, coordinate the delivery of persons and materials under its Nuclear Power Plant and Transportation Agreements, and provide member communications to facilitate the flow of technical information about the emergency.

5.6.2 Pooled Equipment Inventory Company (PEICo)

Southern Nuclear Services, llC ("SNS"), as agent for Pooled Equipment Inventory Company (PEICo) will support the Monticello emergency preparedness effort for withdrawal of PIM Pass Cask D24AElOIAOOl &

A002. The emergency contact list of the PIM Program Manager's Organization is provided in the LOA in the event there is a need to withdraw the subject equipment.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 32 of 120 Table 1 MINIMUM SHIFT STAFFING AND CAPABILITY FOR ADDITIONS FOR NUCLEAR POWER PLANT EMERGENCIES Capability for Additions Position Title or On 30 60 Major Functional Area Major Tasks Expertise Shift min min Plant Operations and Shift Manager 1 --- ---

Assessment of Control Room Supv 1 --- ---

Operational Aspects SRO 1 --- ---

Nuclear Lead 1 --- ---

PE&RO (RO)

Nuclear PE&RO 2 --- ---

Nuclear Asst. PEO 3 --- ---

Emergency Direction Emergency Director 1* --- ---

and Control (Shift Manager until relieved)

Notification/ Notify licensee, Shift Emerg 1 --- ---

Communication Local, State, and Communicator Federal personnel &

agencies Maintain Emergency --- 1 2 Communications Communicators Radiological Accident Emergency Emergency --- --- 1 Assessment and Operations Facility Manager Support of Operational Coordinate EOF prior EOF Coord --- 1 ---

Accident Assessment to arrival of Emergency Manager Off-Site Dose Radiological --- 1 ---

Assessment Emergency Coord Off-Site Surveys Radiation Protection --- 1 1 On-Site (out-of-plant) 1 1 In-Plant Surveys 2 --- 1 Chemistry/Radio- Chemistry 1 1 Chemistry

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 33 of 120 Table 1 MINIMUM SHIFT STAFFING AND CAPABILITY FOR ADDITIONS FOR NUCLEAR POWER PLANT EMERGENCIES (CONTD)

Capability for Additions Position Title or On 30 60 Major Functional Area Major Tasks Expertise Shift min min Plant System Technical Support Technical Advisors 1* --- ---

Engineering, Repair and Core/Thermal Hyd. --- 1 ---

Corrective actions Electrical --- --- 1 Mechanical --- --- 1 Repair & Corrective Mech Maint 1* --- 1 Actions Elec Maint 1* 1 1 I&C --- 1 ---

Protective Actions Radiation Protection Radiation Protection 2* 1 1 (In-Plant) a. Access Control

b. HP Coverage for response actions

c. Personnel monitoring

d. Dosimetry Fire Fighting Fire Brigade per Local 4 AWI-08.01.01 Support Rescue Operations and 2* Local First Aid Support Site Access Control and Security, Security Force All per Personnel Accountability Communications, Security Plan Personnel Accountability 13 9 12

• May be provided by shift personnel assigned other functions.

I I MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 34 of 120 Table 2 MONTICELLO PLANT ERO RESPONSIBILITY MATRIX p - PRIMARY RESPONSIBILITY S - SECONDARY RESPONSIBILITY COMMAND/ p p CONTROL NOTIFICATION/

COMMUNICATION s s p s PLANT OPERATIONS p s p p s TECHNICAL SUPPORT s p s p PROTECTIVE ACTIONS ON-SITE s s p p PERSONNEL ACCOUNTABILITY s s p ACCIDENT ASSESSMENT s s p s OFF-SITE DOSE PROJECTION s p p CONTAMINATION/

RADIATION CONTROL s p p DAMAGE CONTROL s p s p s PROTECTIVE ACTIONS p OFF-SITE RECOMMENDATIONS SEARCH & RESCUE/

FIRST AID s s p s p ACCESS CONTROL s p p p RECOVERY OPERATIONS s s s s p s s CHEMISTRY/

RADIOCHEMISTRY s p p LOGISTICS SUPPORT s p p FIRE FIGHTING s p s p s

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 35 of 120 6.0 EMERGENCY MEASURES 6.1 Summary of Responses For each of the four emergency classifications discussed in Section 4.0 certain generic emergency response actions are required to be taken by the site Emergency Response Organization. These generic emergency response actions are in addition to those actions specific to the type of emergency. This section summarizes the generic emergency response actions.

6.1.1 Notification of Unusual Event 6.1.1.1 Promptly inform State and Local off-site authorities of the nature of the emergency condition.

6.1.1.2 Inform the NRC of the Unusual Event.

6.1.1.3 Augment on-shift resources as necessary.

6.1.1.4 Assess and respond to the off-normal condition.

6.1.1.5 Terminate the Unusual Event with notification to the State and Local off-site authorities and the NRC.

OR 6.1.1.6 Escalate to a more severe emergency class.

6.1.2 Alert 6.1.2.1 Promptly inform the State and Local off-site authorities of the Alert and the nature of the emergency condition.

6.1.2.2 Augment on-shift resources by activating the Technical Support Center (TSC), Operational Support Center (OSC), and Emergency Operations Facility (EOF) or Back-up EOF 6.1.2.3 Notify the NRC of the Alert.

6.1.2.4 Establish the Emergency Response Data System (ERDS) communication link with the NRC.

6.1.2.5 Assess and respond to the emergency condition.

6.1.2.6 Dispatch on-site and off-site radiological survey teams and associated communications as necessary.

6.1.2.7 Provide periodic plant status updates to off-site authorities (Follow-up Messages).

6.1.2.8 Provide periodic meteorological assessments to off-site authorities and, if releases are occurring, estimates for actual releases.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 36 of 120 6.1.2.9 Terminate the Alert with notification to the State and Local off-site authorities and the NRC.

OR 6.1.2.10 Escalate to a more severe emergency class.

6.1.3 Site Area Emergency 6.1.3.1 Promptly inform the State and Local off-site authorities of the Site Area Emergency and the nature of the emergency condition.

6.1.3.2 Augment on-shift resources by activating the Technical Support Center (TSC), Operational Support Center (OSC) and Emergency Operations Facility (EOF) or Back-up EOF.

6.1.3.3 Notify the NRC of the Site Area Emergency.

6.1.3.4 Establish the ERDS communication link with the NRC.

6.1.3.5 Assess and respond to the emergency condition.

6.1.3.6 If radiological and environmental conditions permit evacuate on-site, non-essential personnel.

6.1.3.7 Dispatch on-site and off-site radiological survey teams and associated communications as necessary.

6.1.3.8 Provide a dedicated individual for plant status updates to off-site authorities.

6.1.3.9 Make utility senior technical and management staff available for consultation with the NRC and State on a periodic basis.

6.1.3.10 Provide meteorological data and dose estimates to off-site authorities for actual releases via a dedicated individual or automated transmission.

6.1.3.11 Provide release data and dose projections based on available plant condition information and foreseeable contingencies.

6.1.3.12 Terminate the Site Area Emergency with notification to the State and Local off-site authorities and the NRC.

OR 6.1.3.13 Enter Recovery with notification to the State and Local off-site authorities and the NRC.

OR 6.1.3.14 Escalate to a General Emergency.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 37 of 120 6.1.4 General Emergency 6.1.4.1 Promptly inform the State and Local off-site authorities of the General Emergency and the nature of the emergency condition.

6.1.4.2 Make off-site protective action recommendations to State and Local authorities based on actual or potential plant conditions and radiological releases.

6.1.4.3 Augment on-shift resources by activating the Technical Support Center (TSC), Operational Support Center (OSC) and Emergency Operations Facility (EOF) or Back-up EOF.

6.1.4.4 Notify the NRC of the General Emergency.

6.1.4.5 Establish the ERDS communication link with the NRC.

6.1.4.6 Assess and respond to the emergency condition.

6.1.4.7 If radiological and environmental conditions permit evacuate on-site, non-essential personnel.

6.1.4.8 Dispatch on-site and off-site radiological survey teams and associated communications.

6.1.4.9 Provide a dedicated individual for plant status updates to off-site authorities.

6.1.4.10 Make utility senior technical and management staff available for consultation with the NRC and State on a periodic basis.

6.1.4.11 Provide meteorological data and dose estimates to off-site authorities for actual releases via a dedicated individual or automated transmission.

6.1.4.12 Provide release data and dose projections based on available plant condition information and foreseeable contingencies.

6.1.4.13 Enter Recovery with notification to the State and Local off-site authorities and the NRC.

6.2 Emergency Response Activation 6.2.1 Notification Scheme In the event an emergency classification is declared procedures and systems are in place to facilitate timely activation of the site Emergency Response Organization and notification of State and Local authorities, Federal agencies and the general public within the 10 mile EPZ. This section describes the notification methods and processes used to activate on-site and off-site emergency response.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 38 of 120 6.2.1.1 Activation of the On-Site ERO When an abnormal condition is identified by the shift operating staff the duty Control Room Supervisor and Shift Manager are notified. An assessment of the safety significance of the event is performed and a determination of the emergency classification made using the Emergency Action Levels (EALs) contained in the Emergency Plan Implementing Procedures.

Upon declaring an emergency condition, the duty Shift Manager is responsible for implementation of the Emergency Plan and assumes the role of Emergency Director. The Shift Manager directs the completion of the necessary emergency notifications including the on-site Emergency Response Organization.

When directed, the Shift Emergency Communicator notifies the site Emergency Response Organization. During normal working hours, ERO notification is made using the plant public address system. During non-working hours, ERO notification is made using the ERO Pager Network and automated callout system. The detailed instructions for ERO notification are contained in the implementing procedures and associated forms and call-lists.

6.2.1.2 State and Local Authorities and NRC Under the direction of the Shift Manager (Emergency Director) the Shift Emergency Communicator will notify State and Local authorities and the NRC using commercial telephone and the FTS Emergency Notification System (ENS) respectively.

Notification procedures are contained in the Emergency Plan Implementing Procedures and associated forms.

A security threat to MNGP requires an accelerated notification to the NRC immediately after notification to state and local authorities. The goal is to initiate the accelerated call within about 15 minutes of discovery of an imminent threat or attack against the station. This implements the requirements of SA-05-02, Safeguards Advisory for Operating Power Reactors, January 26, 2005.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 39 of 120 In addition to the initial notifications, provisions are included in the Emergency Plan Implementing Procedures for follow-up notifications to State authorities which contain the following information (if it is known and appropriate):

6.2.1.2.1 Location of the incident, name and telephone number of the caller; 6.2.1.2.2 Date and time of the incident; 6.2.1.2.3 Emergency classification; 6.2.1.2.4 Type of actual or potential release and estimated release duration/impact times; 6.2.1.2.5 Estimate of quantity of radioactive material released or being released and the release point; 6.2.1.2.6 Estimates of relative quantities and concentration of noble gases, iodines and particulates; 6.2.1.2.7 Meteorological conditions; 6.2.1.2.8 Actual or projected dose rates at the site boundary and integrated dose at the site boundary; 6.2.1.2.9 Projected dose rates and integrated dose at projected peak and at about 2, 5 and 10 miles, including affected sectors; 6.2.1.2.10 Estimates of any surface radioactive contamination on-site or off-site; 6.2.1.2.11 Licensee emergency response actions underway; 6.2.1.2.12 Recommended emergency actions including protective measures; 6.2.1.2.13 Request for any needed on-site support by off-site organizations.

6.2.1.2.14 Prognosis for worsening or termination of the event based on plant information.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 40 of 120 6.2.1.3 Off-site Emergency Response Organization Notification and activation of the Off-site Emergency Response Organization is accomplished by the Shift Emergency Communicator per the site ERO notification procedures. The ERO notification procedures support the notification of select Xcel Energy/NSPM management and technical personnel who staff the Joint Information Center (JIC).

6.2.1.4 General Public The decision to notify the general public will be made by State or Local authorities based on information and recommendations provided by the MNGP. The Emergency Director is initially responsible for recommendations involving notification of the general public and is relieved of this responsibility by the Emergency Manager.

Notification of the general public is accomplished through Local Authorities use of the Public Alert and Notification System (ANS), and Emergency Alert System (EAS) auto dialing telephone systems. The State or Local authorities are responsible for activation of these systems and the information provided to the public. See Section 7.7 for additional information.

6.2.2 Emergency Action Levels (EALs)

The Emergency Action Levels (EALs) for each of the four emergency classifications are outlined in the Initiating Conditions in Annex A. These Emergency Action Levels are also identified for each Initiating Condition in the Emergency Plan Implementing Procedures. State and Local authorities are notified for all four emergency classifications and will activate the appropriate elements of their respective emergency plans based on information provided in the notification from the utility.

6.2.3 Authentication Communications made for the purpose of notifying off-site authorities of an emergency will be authenticated before the initiation of their emergency response actions. The methods used for authentication are developed and mutually agreed to by the utility and off-site authorities and are located in the off-site plans.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 41 of 120 6.3 Assessment Actions 6.3.1 Determining Magnitude of Release The magnitude of releases and release rates from normal pathways (e.g.,

Stack and Reactor Building vent) are determined using installed plant instrumentation. Installed side-stream isokinetic samplers and wide-range radiation monitors normally monitor plant effluent releases, and would be the primary method used in an emergency. Portable hand held radiation instruments are used in the event the installed monitors become inoperable.

Releases from other than normal pathways (e.g., hard pipe containment vent) will be estimated either from installed plant instrumentation or from a determination of the amount of activity available for release plus the particulars of the release path. Field measurements will be used to assist in the assessment effort by making physical measurements of dose rates and airborne, liquid and surface contamination. Field measurements are primarily the responsibility of the Radiation Protection Support Group, headquartered at the EOF, and under the direction of the Emergency Manager.

6.3.2 Off-Site Dose Projection The primary means of performing dose projections is RASCAL (Radiological Assessment System for Consequence Analysis) using the Unified RASCAL Interface(URI).

URI provides a site specific overlay on RASCAL meteorological, dispersion, and dose assessment models for all required input for emergency dose assessment as well as reports and plume graphics. Using URI, the user does not interact with any part of the original RASCAL input or output screens. Meteorological and effluent data from process monitors and meteorological instruments located at the plant site is entered into RASCAL using URI. This data is available from one central location to be used by the Dose Projection Specialist for entry into the dose projection software.

The URI code supports three modes of operation: Rapid Assessment, Detailed Assessment, and Sum Assessment.

6.3.2.1 Rapid Assessment This mode is intended for use as an aid to supporting decision-makers during the initial phases of a rapidly evolving incident. It is useful for quickly providing estimates of offsite dose projections relative to established Protective Action Guideline (PAG) exposure levels in support of initial protective action decision-making making but limits options in order to simplify the assessment.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 42 of 120 6.3.2.2 Detailed Assessment This mode provides a user-interface to produce more deliberate and comprehensive offsite dose projections than those produced by the Rapid Assessment option. It supports development of refined off-site dose projections based on changing plant status and/or meteorological conditions or field monitoring and sampling results.

6.3.2.3 Sum Assessment This mode permits the user to add archived data from previously completed dose assessments into a single report characterizing multiple concurrent releases. It is an additive process, producing a composite report and is solely for concurrent releases rather than integration of an entire event.

The URI supports expected emergency effluent dose assessment changes such as summing of multiple release/multiple source events and assessment to 50 miles.

The URI program can be run from computer stations located in the Control Room, TSC, EOF, and the Back-up EOF. Independent battery powered laptop computers are available in the TSC, EOF and Back-up EOF.

The Radiological Emergency Coordinator has the capability to estimate the total off-site population dose (manrem) received during a release. The off-site dose assessment computer will supply the projected dose rates or doses (whole body and thyroid) at various distances. Field Team radiation survey results may also be used to determine the off-site dose rates.

Population distribution charts comprised of the sectors and distances from the plant are available. The Radiological Emergency Coordinator will determine the applicable doses or dose rates in the sectors and calculate the estimated total population dose by referring to the population totals in the sectors of interest.

6.3.3 Field Radiation Surveys The task of field radiation surveillance will be accomplished by several teams under the supervision of Emergency Operations Facility (EOF) personnel. Initially, plant staff personnel will be responsible for on-site as well as off-site monitoring. As the organization is augmented, plant personnel from Prairie Island Nuclear Generating Plant (PINGP) will take over the off-site surveys. The EOF will be the central point for receipt and analysis of all off-site field monitoring data.

Survey teams will normally be composed of 2 individuals each, at least one of whom SHALL be trained in radiological field monitoring. Each team SHALL be equipped with appropriate monitoring equipment, including dose rate instruments, air sampling equipment and sample collection media and

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 43 of 120 containers. This equipment has the capability to detect and measure radioiodine concentrations in the air as low as 1x10-7 µCi/cc under field conditions. Monticello Nuclear Generating Plant monitoring teams SHALL perform necessary off-site monitoring until the PINGP off-site monitoring teams arrive and assume off-site monitoring responsibility. The estimated deployment time for monitoring teams composed of Monticello Nuclear Generating Plant personnel is 60 minutes.

6.4 Corrective Actions 6.4.1 Fire Control The Fire Brigade, which is composed entirely of plant personnel, is fully equipped, trained and capable of dealing with fire emergencies. At the direction of the Emergency Director and the Brigade Leader, the Fire Brigade will be deployed as necessary.

6.4.2 Repair and Damage Control The repair and damage control functions are assigned to the Maintenance Group. Personnel are assigned according to the skills they possess so that the team is capable of coping with the emergency situation. Repair and damage control team members are selected from available personnel.

6.5 Protective Actions 6.5.1 Protective Cover, Evacuation, Personnel Accountability In the course of an emergency situation where there is an actual or potential release of radioactive material to the environs in excess of normal operating levels, an assessment of projected exposure to persons on-site and off-site will be made. The result of this assessment will be a determining factor for implementing protective actions.

6.5.1.1 Plant Site During the course of an emergency, the REC is responsible for on-site monitoring operations. The on-site monitoring procedures contain criteria for initiating evacuations of various degrees. In all cases of elevated radiation levels or in potentially hazardous situations, non-essential personnel will be evacuated from affected areas of the plant. A plant evacuation is required at the Site Area Emergency level, radiological and environmental conditions permitting. The plant evacuation includes the owner-controlled area outside of the Protected Area.

A personnel accounting process is part of a plant or site evacuation. A system using the plant security computer and individual Security I.D. badges enables the Emergency Director to account for all personnel within the Protected Area in 30 minutes or less. Card readers are located at the TSC, Security

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 44 of 120 Access Facility and Access Control to expedite the process.

Backup methods are also available in case of a computer malfunction.

Personnel within the plant are notified of an evacuation by the plant Public Address (PA) system. A warning tone and voice instructions are part of the procedure. Time required for this process is less than 5 minutes from decision to evacuate.

Personnel outside of the plant buildings are notified by the plant evacuation siren, which is located atop the Reactor Building.

The siren initiation is simultaneous with the PA system alarm.

After the accounting process is completed, Security personnel are dispatched to ensure that all personnel in the Owner-Controlled Area outside the Protected Area have been notified. This process should be completed within 60 minutes of the start of the evacuation.

In the event of a Site Area or General Emergency, the following actions will be taken:

6.5.1.1.1 All plant employees not having emergency assignments at the site and having been cleared of radioactive contamination, will be directed to proceed to the Emergency Operations Facility, a designated off-site assembly point or sent home; 6.5.1.1.2 All working and non-working visitors and contractor and construction personnel, having been cleared of radioactive contamination, will be directed to leave the site, unless requested otherwise by the Emergency Director; 6.5.1.1.3 Persons who may be within the restricted area but outside the security fence, will be directed to proceed to the designated assembly point for accountability and radioactive contamination check before being directed to leave the site.

6.5.1.1.4 Persons who are not cleared of radioactive contamination following a plant evacuation will be decontaminated at a location on the plant site, at an off-site assembly point, or at a County Emergency Worker Monitoring and Decontamination Facility.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 45 of 120 6.5.1.2 Onsite Protective Actions for Hostile Action Events 6.5.1.2.1 Onsite Protective Actions designed for protection of personnel as described in Section 6.5.1.1 may be inappropriate for a Hostile Action Event. Alternate actions as described in NSIR/DRP-ISG-01 Section IV.F have been developed and proceduralized.

6.5.1.3 Off-Site Public Actions planned to protect the off-site public and criteria for their implementation are described in the MINNESOTA EMERGENCY OPERATIONS PLAN.

Initiation of protective actions for off-site areas is the responsibility of the State of Minnesota. Prior to the EOF being activated, the Emergency Director will make recommendations for protective actions if it is determined that they are necessary.

Recommendations will be directed to the State EOC and will come directly from the Emergency Director. If the State EOC is not activated and it is determined by MNGP that immediate protective actions should be initiated at the Local level, the recommendation will be made directly to the Local authorities.

When the EOF is activated, the protective action recommendation function will normally be transferred to the Emergency Manager.

The current issue of the Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA 400-R-92)

SHALL be used as a basis for recommendations for protective actions for the off-site public; however, more conservative protective actions based on discussions with the State may be recommended in the course of an emergency. Protective action recommendations SHALL also be consistent with the guidance of the U.S. Food and Drug Administrations, Department of Health and Human Services document titled Accidental Radioactive Contamination of Human Food and Animal Feeds: Recommendations for State and Local Agencies, August, 1998.

Tables 3, 4, 5 and 6 provide guidelines and action levels to be used in the formulation of protective action recommendations.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 46 of 120 6.5.2 Routes for Site Evacuation Evacuation of personnel from the site SHALL be accomplished in personal private vehicles and augmented by MNGP vehicles when necessary and available. Personnel are to proceed to the designated assembly area as directed by traffic control personnel.

6.5.2.1 Monticello Service Center Assembly Area -

118 Dundas Road, Monticello, Minnesota 6.5.2.2 Xcel Energy Sherburne County Generating Plant (Sherco) -

13999 Industrial Blvd, Becker, Minnesota 6.5.3 Evacuation Time Estimates (ETE) - Plume Exposure EPZ Time estimates for evacuation of the plume exposure EPZ are referenced in an appendix to the Off-site Nuclear Emergency Plan and in the Plant Emergency Plan Implementing Procedure for making off-site protective action recommendations. MNGP and the State of Minnesota use the ETE to develop pre-determined protective action recommendations.

6.5.4 Use of On-Site Protective Equipment and Supplies 6.5.4.1 Respiratory Protection and Protective Clothing In an emergency situation, the protection afforded by individual respiratory equipment must be weighed against the negative aspects of its use. In the case where a respirator may lead to additional external exposure because of the inherent difficulties of working while wearing a respirator, it may be prudent to forego the respirator in favor of a lower total dose to the individual.

In general the use of protective clothing and respiratory protection equipment will be governed by existing Radiation Protection Procedures. The Radiological Emergency Coordinator will make decisions on the use of this equipment during emergency situations.

A supply of protective clothing is stored in the TSC.

A very limited supply of this equipment is stored at each assembly point. Large supplies of respiratory equipment are stored at the plant access control area and protective clothing will normally be available in the warehouse located outside the security fence.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 47 of 120 6.5.4.2 Thyroid Prophylaxis A supply of potassium iodide (KI) will be maintained at the Technical Support Center and the Emergency Operations Facility. Each of these locations will have a minimum of 200 boxes, each of which contain a 10-day supply of KI at recommended dosages for one person. In the event that an individual is expected to receive a dose to the thyroid in excess of 25 Rem (due to radioiodine uptake), the use of KI as a blocking agent may be recommended. KI will not be made available to off-site personnel under this plan.

6.5.5 Emergency Exposure Control 6.5.5.1 Exposure Limits Although an emergency situation transcends the normal requirements of limiting exposure, there are suggested levels for exposure to be accepted in emergencies. Immediate re-entry may be necessary to account for missing personnel or to secure vital equipment. Additional exposure for this purpose must be approved by the Emergency Director based on the following criteria and the guidelines in Table 6:

6.5.5.1.1 In order to avoid restricting actions that may be necessary to save lives or protect the health and safety of the public, it SHALL be the discretion of the Emergency Director that determines the amount of exposure that will be permitted in order to perform the emergency mission. However, the dose resulting from emergency exposure should be limited to 25 REM for life-saving activities and the protection of large populations. Individuals undertaking any emergency operation in which the dose will exceed 25 REM to the whole body should do so only on a voluntary basis and with full awareness of the risk involved (EPA-400).

6.5.5.1.2 In situations where protecting valuable property is involved, the dose resulting from emergency exposure should be limited to 10 REM (EPA-400).

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 48 of 120 6.5.5.2 Exposure Control Under emergency conditions, exposure control would be implemented in accordance with the Emergency Plan Implementing Procedure A.2-401 (EMERGENCY EXPOSURE CONTROL).

Each person entering the controlled area would be required to wear a permanent record device (TLD) and a direct reading dosimeter or an electronic dosimeter.

The responsibility for maintaining exposure control for site activities rests with the Radiological Emergency Coordinator and the Radiation Protection Group. With this responsibility would be the option of establishing Access Control at alternate locations on site if the primary access control facility becomes uninhabitable. In this event, the access control function would be relocated to an alternate location within the Administration Building, Security Access Facility or the EOF. In any case, strict exposure control of all individuals passing through the access point would be maintained on a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> basis.

In order to enhance the exposure control process and to provide dosimetry for an expanded number of people, a dosimetry vendor would be called upon to expedite the shipment of extra dosimetry devices and to supply personnel and instrumentation for on-site appraisal of exposures.

It must be noted, however, that every effort will be made to keep the exposures of plant staff personnel and off-site emergency personnel below the limits for normal operations.

6.5.6 Contamination Control Measures 6.5.6.1 Plant Site The Radiation Protection Group is responsible for preventing or minimizing direct or subsequent ingestion exposure to radioactive materials deposited on the ground or other surfaces. Personnel, material and equipment will be checked at the main access control point. Decontamination will be effected when needed and when practical. Equipment which cannot be decontaminated will remain within the Radiological Controlled Area or be controlled through a conditional release process.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 49 of 120 The site guidelines for release of equipment to a clean area are no detectable licensed radioactive material above background, using the following criteria:

6.5.6.1.1 A.Use of a counting system that meets a minimum detection sensitivity of 1000 dpm/100cm2 beta/gamma provided that this equates to an MDA no higher than 20 dpm/100cm2 alpha based on 10CFR61 plant beta to alpha ratios.

6.5.6.1.2 B.Using a frisker type instrument to conduct a direct frisk survey with no reproducible counts above background provided background is

< 200 cpm.

Should any normally clean areas become contaminated in excess of 20 dpm/100 cm2 alpha or 1000 dpm/100 cm2 beta-gamma (as determined by smear tests), they SHALL be barricaded or roped and posted as a Contaminated Area, per normal plant procedures. Such areas SHALL be decontaminated as soon as practical. Access to such areas which lie outside the protected area will be controlled by plant security until properly decontaminated and cleared.

Under emergency conditions, the Radiological Emergency Coordinator has the option of implementing emergency guidelines for contamination control which are in excess of normal limits.

The Radiation Protection Group is responsible for controlling all food and water supplies at the plant during an emergency.

Whenever an evacuation due to radiological condition occurs, all food and water supplies within the evacuated area will be considered contaminated and measures will be taken to prevent their use.

Before any water or food may be consumed, the Radiation Protection Group must verify that the water/food is not contaminated and the area in which it is consumed is less than detectable using normal contamination survey methods.

Random samples of water/food SHALL be analyzed for contamination on a periodic basis.

6.5.6.2 Off-Site Areas Protective actions planned for persons in off-site areas and criteria for their implementation are described in the MINNESOTA EMERGENCY OPERATIONS PLAN.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 50 of 120 6.6 Aid to Affected Personnel In case of an accident or emergency, protection of personnel from radioactive contamination and exposure is the responsibility of the Radiation Protection Group.

The highest priority for medical treatment of radiation injuries are personnel suspected of receiving 25 rem or more of penetrating radiation to the whole body.

The order of medical treatment will be:

A. Immediate care of serious injuries B. Decontamination of personnel C. Care of other injuries D. Determining any internal contaminations through bioassays and whole body counts.

E. Follow-up treatment 6.6.1 Decontamination and First Aid 6.6.1.1 Decontamination As soon as practical, attempts SHALL be made to decontaminate individuals found to be contaminated. First aid or removal from a hazardous environment, however, SHALL take precedence over decontamination actions. Precautions will be taken to prevent the spread of contamination to other parts of the body. Particular attention will be paid to open wounds in order to prevent internal contamination.

Contamination monitoring will be accomplished using thin-window GM pancake-type probes for maximum sensitivity.

Each assembly area where decontamination may be conducted is equipped with one or more of these instruments.

The primary decontamination facility is located in the plant Access Control Area. Two showers and a large sink, plus various other supplies are provided for this express purpose. If the primary facility is not accessible, decontamination kits are also provided in the emergency supplies for the EOF and off-site Assembly Points. Decontamination operations at an Assembly Point would be on a small scale due to limited resources. If necessary, contaminated personnel at an Assembly Point will be placed in protective clothing and transported to an adequate facility.

The decontamination kits contain the equipment and materials necessary for small scale personnel decontamination operations. Decontamination materials are made available for use at Access Control, EOF, and Off-Site Assembly Points to deal with various skin contamination.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 51 of 120 The waste generated in decontamination operations will be retained for proper disposal.

6.6.1.2 First Aid Fire Brigade personnel receive first aid training (Red Cross Multi-Media or equivalent) on a periodic basis. The level of skills is sufficient for the time it takes for off-site medical personnel to arrive.

6.6.2 Medical Transportation Arrangements for transportation of radiologically contaminated casualties have been made with local hospitals Ambulance Service. The personnel at the service receive radiological training from MNGP Training Staff members on a regular basis. The procedure for handling contaminated personnel includes protective measures for equipment as well as the ambulance service personnel.

6.6.3 Medical Treatment The Monticello Nuclear Generating Plant has made arrangements for medical services with a local hospital located approximately five miles from the plant in Monticello. In addition, this hospital has established a transfer agreement with North Memorial Hospital for backup assistance should it be necessary for either radiological support or to care for large numbers of patients.

Injured personnel who must be moved to the local hospital while in a contaminated condition SHALL be accompanied by personnel who are qualified in radiological monitoring who will stay in attendance and maintain radiological control until decontamination is satisfactorily completed.

The person escorting the patient will take along survey instruments. In addition, TLD badges, pocket dosimeters, survey instruments and other supplies and protective equipment for hospital employees are available at the hospital.

The patient will be put in a separate room and this will be considered a Contaminated Area. Upon release of the patient from the room, it SHALL be sealed until decontaminated and cleared by Radiation Protection. All hospital equipment in the room will be surveyed and decontaminated to site guidelines for release of equipment to a clean area before being released.

If deemed necessary patients may be sent to the North Memorial Hospital for radiological studies, or other reasons. This arrangement is formalized in a transfer agreement between these two hospitals and outlined in the Off-site Nuclear Emergency Plan, Section entitled EMERGENCY MEDICAL PLAN.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 52 of 120 Table 3 EPA GUIDELINES FOR RECOMMENDED PROTECTIVE ACTIONS (WHOLE BODY AND THYROID DOSE FROM EXPOSURE TO A GASEOUS PLUME)

Projected Does (REM) to the Population Recommended Actions Comments Whole Body <1 (TEDE) No planned protective actions.

Thyroid <5 (CDE) Monitor environmental radiation levels.

Skin <50 (CDE)

Whole Body >1 (TEDE) Evacuate unless constraints make it Shelter if evacuation Thyroid >5 (CDE) impractical. Monitor environmental were not immediately Skin >50 (CDE) radiation levels. Control access. possible.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 53 of 120 Table 4 RECOMMENDED DERIVED INTERVENTION LEVEL (DIL) OR CRITERION FOR EACH RADIONUCLIDE GROUP (A), (B)

All Components of the Diet Radionuclide Group (Bg/kg) (pci/kg)

Sr-90 160 4300 I-131 170 4600 Cs-134 &Cs-137 1200 32,000 Pu-238 + Pu-239 + Am-241 2 54 Ru-103 + Ru-106(c) C3 + C6 < 1 C3 + C6 <1 6800 450 180,000 12,000 Notes:

(a) The DIL for each radionuclide group (except for Ru-103 + Ru-106) is applied independently. Each DIL applies to the sum of the concentrations of the radionuclides in the group at the time of measurement.

(b) Applicable to foods as prepared for consumption. For dried or concentrated products such as powdered milk or concentrated juices, adjust by a factor appropriate to reconstitution, and assume the reconstitution water is not contaminated. For spices, which are consumed in very small quantities, use a dilution factor of 10.

(c) Due to the large difference in DILs for Ru-103 and Ru-106, the individual concentrations of Ru-103 and Ru-106 are divided by their respective DILs and then summed. The sum must be less than one. C3 and C6 are the concentrations, at the time of measurement, for Ru-103 and Ru-106, respectively.

(d) Reference U.S. Food and Drug Administrations, Department of Health and Human Services document titled Accidental Radioactive Contamination of Human Food and Animal Feeds: Recommendations for State and Local Agencies, August 1998, for further discussion of this table.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 54 of 120 Table 5 RECOMMENDED PROTECTIVE ACTIONS Accident Phase Exposure Pathway Example of Actions to be Recommended EARLY Inhalation of gases, Evacuation, shelter, Access Control, (EMERGENCY) radioiodine or respiratory protection, prophylaxis (thyroid PHASE (NOTE 1) particulate protection)

(0 to 4 days)* Direct whole body Evacuation, shelter, Access Control exposure INTERMEDIATE Ingestion of Milk Take cows off pasture, prevent cows from PHASE (NOTE 2) drinking surface water, discard contaminated milk, or divert to stored products such as cheese Ingestion of fruits and Wash all produce, or impound produce, vegetables delay harvest until approved, substitute uncontaminated produce Ingestion of water Cut off contaminated supplies, substitute from other sources, filter, demineralize (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to 30 Whole body exposure Relocation, decontamination, Access Control days)* an inhalation LATE PHASE Ingestion of food and Decontamination, condemnation, or (NOTE 3) water contaminated destruction of food, deep plowing, from the soil either by condemnation or alternate use of land resuspension or uptake through roots (over 30 days) Whole body exposure Relocation, Access Control, from deposition decontamination, fixing of contamination, material or inhalation deep plowing of resuspended material NOTE 1 Early Phase - Time period from the onset of major release and subsequent plume exposure periods up to 4 days.

NOTE 2 Intermediate Phase - Time period of moderate continuous release with plume exposure and contamination of environment.

NOTE 3 Late Phase Recovery period

• Typical Pst - Accident Time Periods

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 55 of 120 Table 6 EMERGENCY EXPOSURE GUIDELINES EXPOSURE LIMIT1 EMERGENCY COMMENTS 5 REM (TEDE)(2)(3) All emergency activities This dose limit applies when a lower dose is not practicable through application of ALARA practices.

(2)(3) 10 REM (TEDE) Protection of valuable This dose limit applies when a lower property dose is not practicable through application of ALARA practices.

(2)(3) 25 REM (TEDE) Life saving or protection This dose limit applies when a lower of large populations dose is not practicable through application of ALARA practices.

(2)(3)

> 25 REM (TEDE) Life saving or protection Doses in excess of 25 REM should be of large populations on a voluntary basis to persons fully aware of the risks involved.

NOTE 1: Dose limits for emergency workers and activities are based on EPA 400-R-92-001, May 1992.

NOTE 2: Sum of external effective dose equivalent and committed effective dose equivalent to non-pregnant adults from external exposure and intake during the duration of an emergency.

NOTE 3: Exposure to the lens of the eye should be limited to 3 times the value listed and doses to the skin and extremities should be limited to 10 times the value listed.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 56 of 120 7.0 EMERGENCY FACILITIES AND EQUIPMENT 7.1 Emergency Response Centers Plan views of the Technical Support Center, Back-up Operations Support Center, Emergency Operations Facility (EOF) and Operations Support Center (OSC) as described below, are shown in Figures 13.5, 13.6, and 13.8.

7.1.1 Technical Support Center The Technical Support Center (TSC) serves as a center outside of the Control Room that acts in support of the command and control function.

Plant status and diagnostic information will be available at this location for use by technical and management personnel in support of reactor command and control functions. The Emergency Director resides in the TSC when activated.

The TSC is located on the first level of the Plant Engineering Building (PEB). The TSC has approximately 5700 sq ft of floor space and is within the controlled ventilation boundary of the Emergency Ventilation System (EVS). This system is independent of the Emergency Filtration Train System (EFT) which serves the Control Room.

An emergency equipment locker located in the TSC contains protective, anti-contamination clothing for TSC personnel.

7.1.2 Operations Support Center The Operational Support Center (OSC) serves as the facility to which Mechanical, Electrical and I&C maintenance personnel report in an emergency. In addition to maintenance personnel, off-duty Operations personnel also report to the OSC. The OSC functions as the staging area from which emergency teams are dispatched, by the TSC or Control Room, to undertake emergency corrective actions.

The primary OSC is located on the first and second levels of the Plant Administration Building within the Outage Control Center, PAB2 conference room, I&C offices, Operations Department Break Room and Plant Lunch Room. The primary OSC is a dedicated facility which serves as a maintenance support area and conference room during normal operation.

The primary OSC is outside a filtered ventilation boundary.

The Back-up OSC is located within the TSC shell structure in the east end of the TSC. The Back-up OSC is located within the EVS controlled ventilation boundary. The Back-up OSC is activated if the primary OSC becomes uninhabitable or as other circumstances dictate.

Emergency equipment lockers, located in the primary OSC, contain protective anti-contamination clothing for OSC emergency team personnel.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 57 of 120 7.1.3 Emergency Operations Facility In the event of an Alert, Site Area Emergency, or a General Emergency, the Emergency Operations Facility (EOF) will be activated. The EOF serves as a center for evaluation and coordination of off-site activities related to the emergency. Additionally, the facility will be the base of operations for environmental surveillance and communications with supporting operations.

The Emergency Manager is in charge of the EOF.

The EOF is located within the site Training Center, 1 mile south by southeast of the plant (approximately 5 minutes driving time). It was designed primarily as a training facility and also in accordance with NUREG 0696. In the event the EOF is needed, it is capable of prompt conversion from a training facility to an Emergency Response Facility.

The EOF will be activated and staffed by Site ERO personnel. On activation, the first personnel will arrive within 30 minutes, with complete activation in approximately one hour. The Emergency Plan Implementing Procedures describe the functions, equipment and personnel responsibilities more fully.

The EOF will also provide office space, trailer space and communications hook-ups for NRC Incident Response Teams, vendors, and technical support contractors. Media personnel may be assembled in the Training Center Multi-Purpose Room or other designated waiting area. The JIC will be the main point of contact for the media to obtain information regarding the emergency.

The EOF has facilities and capabilities for:

Management of overall licensee emergency response, Coordination of radiological and environmental assessment, Determination of recommended public protective actions, Notification of offsite agencies, 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, Obtaining and displaying key plant data and radiological information, and Analyzing plant technical information and providing technical briefings on event conditions and prognosis to licensee staff and offsite agency responders.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 58 of 120 7.1.4 Alternative Facilities In the case of Hostile Action Events activation of onsite Emergency Response Facilities may be unsafe. Alternative Response Facilities have been developed to allow onsite ERO personnel to muster is a location near the site but away from any onsite hostile activity. The alternative facility selected for Monticello is the EOF/Training Building described in Section 7.1.3. This facility is accessible in the event of an onsite Hostile Action and provides the ability to perform the following functions:

Communication with the Control Room and onsite Security Forces Notification of offsite Emergency Response Organizations Engineering Assessment Activities including damage control team preparation and planning.

7.1.5 Back-up EOF In the event the primary EOF becomes uninhabitable during a real emergency, the functions of the EOF would be transferred to the Back-up EOF.

The Back-up EOF is located at the Xcel Energy corporate office in downtown Minneapolis, 45 miles southeast of plant.

The Back-up EOF has facilities and capabilities for:

Management of overall licensee emergency response, Coordination of radiological and environmental assessment Determination of recommended public protective actions Notification of offsite agencies Coordination of event, plant, and response information provided to public information staff for dissemination to the media and public, Coordination of emergency response activities with Federal, State, and local agencies, Obtaining and displaying key plant data and radiological information, and Analyzing plant technical information and providing technical briefings on event conditions and prognosis to licensee staff and offsite agency responders.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 59 of 120 7.1.6 Assembly Points In the event of a plant evacuation, the On-Site Assembly Point (or an Off-Site Assembly Point, as appropriate) will be activated. The function of the assembly point is to provide a center for personnel accountability and radiological contamination screening along with any other immediately necessary actions.

The On-Site Assembly Point is located approximately 1000 feet south of the plant, within the Site Administration Building . The location of the Off-Site Assembly Point is dependent upon the nature of the emergency conditions.

Its location will be announced over the public address system when announcement of evacuation is made.

7.1.7 Access Control The Primary Access Control Point is located in the lower level of the Plant Administration Building. This is the primary entry/exit point from the Radiologically Controlled Area.

An alternate Access Control Point will be located in the Administration Building, Security Access Facility, or at a point designated by the ED, if the Primary Access Control Point becomes uninhabitable due to high radiation or high airborne levels.

7.1.8 Sign-in Boards for ERO Assignments The boards are used to make speedy personnel duty assignments during the initial stage of an emergency, to insure that qualified personnel fill the positions in the ERO, and insure that the more important positions in the ERO are filled first.

The board consists of a layout of the Emergency Response Organization.

Under the board is a list of the individuals who are qualified to fill that position.

The boards are located in each facility. Personnel who have key positions within those facilities have the responsibility of checking the boards when it is announced that ERO personnel are to report to their duty stations. The boards are reviewed and updated quarterly.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 60 of 120 7.2 Communications Systems 7.2.1 Normal On-Site Communications Normal on-site communications is provided by the plant telephone system which has a maximum capacity of 36,000 lines and 12,000 trunks. The telephone system processing equipment located in the Plant Administration Building telephone room and the Plant Engineering Building communication room is powered by UPS/battery backed non-1E instrument buses.

Portions of the system are also provided with an alternative power source from lighting panels backed by the non-1E Diesel Generator. Telephone system components at remote locations are powered from lighting panels backed by stand-alone UPSs.

The plant PA System may also be used for in-plant communications. The PA System is powered by normal plant power, backed up by uninterruptible power.

Portable radios are used for communications between individuals and base stations located in the Control Room, TSC, EOF, and Security Building.

7.2.2 Normal Off-Site Communications Normal off-site communications is provided by the following telephone circuits:

7.2.2.1 46 two way ISDN trunks (TDS Telecom) 7.2.2.2 46 two way ISDN trunks to Minneapolis (Dial 8 access) 7.2.2.3 23 ISDN trunks to the Monticello Training Center 7.2.3 Alternate Off-Site Communications 7.2.3.1 Radio Receiver/Transmitter An alternate method for communications is provided by an AC powered radio transceiver with control consoles located in the TSC, Control Room and EOF.

From either console, communications may be established with the EOF, Sherburne and Wright County Sheriffs, Plant Security, Operations and Radiation Protection portable radios, and the Xcel Energy System Control Center.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 61 of 120 7.2.3.2 Emergency Response Organization Pager Network An ERO Pager Network is utilized for notification of site Emergency Response Organization members. The system consists of a commercial pager network with independent, transmitters. Transmitters are located in various areas from St.

Cloud to Red Wing. Each pager group has a primary and back-up telephone number which are from separate trunk lines, which further increases accessibility. Each transmitter is installed with a back-up power supply (battery or diesel).

7.2.3.3 Direct Dedicated Telephones Direct dedicated telephones as described below are diagrammed in Figure 13.7.

7.2.3.3.1 Three dedicated lines exist between the TSC and the EOF.

7.2.3.3.2 Site FTS System - this dedicated telephone network connects the plant site with the NRC Operations Center. Site extensions are located in the Control Room, TSC, Duty Shift Manager Office and Site NRC Office. Site extensions include ENS, HPN, and various other extensions connecting to the NRC Operations Center.

7.2.3.3.3 EOF FTS System - this dedicated telephone network connects the EOF with the NRC Operations Center. EOF extensions are located in the EOF and adjoining classrooms.

EOF extensions include ENS, HPN and various other extensions connecting to the NRC Operations Center.

7.2.3.3.4 An automatic-ringing line exists between the TSC and the State EOC.

7.2.3.3.5 Two dedicated lines exists between the EOF and the Back-up EOF.

7.2.3.3.6 An auto ring line exists between the EOF and the State EOC.

7.2.3.3.7 Four dedicated Federal Telephone System (FTS) lines exists in both the EOF and TSC to connect the NRC incident response team with the NRC Operations Center.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 62 of 120 7.2.3.3.8 Two dedicated cellular phones providing back-up communications for Field Teams.

7.2.3.4 Radio Links Radio links exist for communications between the Minnesota Division of Homeland Security and Emergency Management and the Control Room, TSC , EOF, and Back-up EOF at the plant site.

7.2.3.5 Emergency Response Data System ERDS is a direct near real-time electronic data link between the plants on-site computer system and the NRC Operations Center that provides for the automated transmission of a limited data set of selected parameters. The ERDS supplements the existing voice transmission over the FTS-ENS.

7.2.4 Emergency Communications Matrix Tables 7 and 8 depict the different communications media by which emergency centers pass information, and give primary and alternate contacts for centers where appropriate.

7.2.5 Testing Testing of the various communications links is accomplished in two ways.

7.2.5.1 Each month a communications test is conducted in accordance with a surveillance procedure (1225).

7.2.5.2 Drills involving communications equipment are conducted on a regular basis to assure operability.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 63 of 120 7.3 Assessment Facilities The plant instrumentation and monitors perform indicating, recording and protective functions. The regulating systems provide the ability to regulate the plant safely from shutdown to full power and to monitor and maintain key variables such as reactor power, flow, temperature and radioactivity levels within predetermined safe limits during both steady state and plant transients. Plant instrumentation and control systems also provide means to cope with abnormal operating conditions. The control and display of information of these various systems are centralized in the main Control Room. This instrumentation would provide the basis for initiation of protective systems.

7.3.1 On-Site Systems and Equipment 7.3.1.1 Safety Parameter Display System (SPDS)

The Safety Parameter Display System (SPDS) is designed to provide plant operators with a concise display of critical plant parameters as an aid in implementation of the plant Emergency Operating Procedures (EOPs). The Monticello SPDS System is based on plant Emergency Operating Procedures (EOPs) and General Electric (GE) generic Emergency Response Information System (ERIS). SPDS displays are available in the Work Execution Center Office, Duty Shift Manager Office, Technical Support Center (TSC), Emergency Operations Facility (EOF) and throughout the Control Room.

SPDS information is presented to the operator via color graphic computer systems. Operator interface to the color graphics computer system is via keyboards, color monitors, and printer/plotters. Input data from plant sensors is gathered via the Data Acquisition System (DAS) and independently transmitted to the computer systems. Identical DAS data is maintained on both process computers for purposes of redundancy in the event one computer fails. Signals are processed through various algorithms such as signal range checking, limit checking, averaging, logical manipulations and validation. The results are then transmitted to the color graphic display computers where the data is transformed into the SPDS displays.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 64 of 120 The SPDS displays can be classified into two categories, Top-Level and Lower-Level displays. In general, Top-Level displays provide information on several control parameters, both current and historical. The Lower-Level displays are designed to augment the Top-Level displays by providing more detail or background on specific items contained in the Top-Level displays. The overall SPDS display structure is as follows:

7.3.1.1.1 Top Level SPDS Displays

1. Critical Plant Variables The CPV display provides the status of all critical plant parameters including RPV level, pressure, reactor power, drywell pressure and temperature, torus pressure, temperature and level, and radioactive release rate information.

2. Reactor Pressure Vessel Control The RPV display provides detailed status and control parameter information including RPV water level, RPV pressure, reactor power and RPV temperature.

3. Containment Control This display provides specific information regarding containment control including drywell pressure and temperature and torus water level, temperature and pressure.

4. Radiation Control The Radiation Monitor displays provide detailed information on Reactor/Turbine and Radwaste Building area radiation monitors and plant process monitors.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 65 of 120 7.3.1.1.2 Lower-Level SPDS Displays

1. Trend Plot Displays Trend plot displays support the RPV and Containment Control displays by providing detailed parameter trend plots of those displays.

2. Two Dimensional Plot Displays The 2-D plot displays provide plant specific two dimensional limits in an x-y format and are identical to the curves used in the EOPs.

3. Validation Displays The Validation displays are used to display how a parameter is determined.

In addition, Menu Displays are provided to assist the user in selection of individual displays from applicable display types.

SPDS menus include, Reactor Menu, Trend Plot Menu, 2-D Menu and Validation Menu.

The SPDS displays are designed with common display characteristics for ease of understanding. Data is displayed according to defined conventions for use of color, shape, format, alarm and validation processing.

A display color coding scheme is used to aid the operator in prioritizing information and recognizing off-normal conditions.

In addition, displays provide indication of both validated parameter and process limit status. Status windows are also provided to alert the operator when approaching or exceeding a critical parameter limit (EOP entry condition).

Two SPDS Terminals are available in the Technical Support Center for use during emergency conditions and for system development during normal operation. One terminal is utilized by the Radiation Protection Group for display of plant radiological conditions and process monitor status. The second terminal is located in the Technical Engineering area of the TSC and is used for plant parameter analysis and trending under the direction of the Engineering Group Leader.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 66 of 120 7.3.1.2 Geophysical Phenomena Monitors 7.3.1.2.1 Seismic Monitoring System The Seismic Monitoring System is made up of three independent sensing systems: the peak-recording accelerometers, the seismic-switch-activated annunciator system and the accelerograph recording system. The peak-recording accelerometers and the sensors for the accelerograph system (force-balance accelerometers) are located in the drywell, on the refueling floor and in the seismic shed (located to the north of the number 2 warehouse). Seismic switches for the annunciator system are also located in the seismic shed. The seismic trigger which initiates the accelerograph is located in the number 12 125 VDC Battery Room.

Each of the peak-recording accelerometers is a self-contained unit. The sensing mechanism is a permanent magnet stylus attached to the end of a torsional accelerometer. Low frequency accelerations cause the magnet to erase pre-recorded lines on a small (approximately 1/4 inch square) piece of magnetic tape. Each peak recording accelerometer unit contains three torsional accelerometers and magnetic tapes - one each for longitudinal, transverse, and vertical accelerations.

The magnetic tapes can be removed from the accelerometers, developed and evaluated by plant personnel for a rapid determination of the severity of a seismic disturbance.

The Control Room annunciator 6-C-08 (EARTHQUAKE) is initiated by either seismic switch of the Seismic Annunciator System or the seismic trigger of the accelerograph recording system. In addition to this, each of the seismic switches has its own alarm. The first of these is the alarm 6-C-13 (OPERATIONAL BASIS EARTHQUAKE (OBE))

which annunciates when its switch senses an acceleration > .03 g. The second alarm is the 6-C-18 (DESIGN BASIS EARTHQUAKE

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 67 of 120 (DBE)), which annunciates when its switch senses an acceleration >.06g. These two switches do not activate the accelerograph recording system.

The accelerograph recording system gives a more detailed record of a disturbance than the peak recording accelerometers - it records accelerations in three directions (longitudinal, transverse, and vertical, as above) from each of the three sensor locations on magnetic tape cartridges located in the Control Room. This system has five major components: a trigger, three sensors, and the recording and control units. When the trigger (located in the No. 12 125 VDC Battery Room) senses the beginning of a seismic disturbance, (an acceleration > .01 g), it will start the accelerograph recorders and also triggers the earthquake event alarm 6-C-08 in the Control Room.

A summary of the Seismic Monitoring Equipment is provided in Table 9.

7.3.1.2.2 Meteorological Monitoring System The purpose of the meteorological monitoring system is to monitor and determine atmospheric dilution and dispersion parameters for the Monticello Plant site.

The meteorological monitoring system consists of two instrumented towers, associated signal transmission and processing equipment, two AC power sources, and battery backup power supplies.

The primary meteorological tower facility is located on the plant site southeast of the Reactor Building. It consists of a guyed 100m tower with six instrumentation booms located in pairs at 10m, 43m, and 100m.

At each height one boom is reserved for A-train instrumentation and the other boom is reserved for B-train instrumentation. Two independent elevator systems are installed on the tower allowing each division of equipment to operate independently so maintenance may be

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 68 of 120 performed without taking the full system out of service.

Instrumentation consists of wind speed and direction sensors along with aspirated temperature sensors. One sensor of each type is mounted at each location for each train for a total of six instruments of each type. Two precipitation monitors, one for each train, are located at the base of the tower. Data is communicated wirelessly from the tower to a receiver inside the Plant Administration Building.

Instrumentation is AC powered and is run on UPS backed power designed to last for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

A second meteorological tower is located approximately 3/4 mile from the Reactor Building and is adjacent to the EOF. This tower is a 30 meter self-supported tower with an instrument elevator which lifts single train wind speed and wind direction sensor to the 22 meter elevation. Signal transmission lines from the wind sensor to the associated junction box are surge protected and the tower is grounded.

Signals from the tower are fed to an instrument processor rack located inside the EOF and provide the third source of wind speed and wind direction data.

Meteorological data from the 100 meter tower is collected every 5 seconds, averaged every minute and 15 minutes, and stored in raw data files. The data is available on the Process Computer System in the Plant Control Room, TSC, and the EOF.

Meteorological data from the 30 meter tower is collected every second and averaged every minute and 15 minutes. The data is available on the Process Computer System in the Plant Control Room, TSC, and the EOF.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 69 of 120 Some meteorological data is provided as digital averages in the Control Room. Displays of current and 15 minute running average meteorological data from both sensor trains on the 100 meter tower and 30 meter tower are simultaneously available on computer terminals in both the TSC and EOF.

The Meteorological Data Collection software includes data quality control tests which flag questionable or bad data to the user. Plant Chemistry personnel access hourly averaged data on a daily basis and review the data for reasonableness in accordance with plant Chemistry Department procedures. Plant I&C personnel perform a monthly surveillance test on the 100 meter tower and annual instrument calibrations on both towers in accordance with the plant surveillance program. System problems are corrected through the plant Work Order process.

In addition to the site meteorological monitoring system, regional meteorological data is available through the National Weather Service by commercial telephone. National Oceanic and Atmospheric Administration (NOAA)

Weather Alert radios are also installed in the Control Room, TSC and EOF to provide warning of adverse weather.

7.3.1.3 Radiological Monitors 7.3.1.3.1 Process Radiation Monitoring System The function of the process radiation monitoring system is to provide a continuous monitoring and readout of the radioactivity of all process lines and vents that can release radioactivity directly to the environs. In addition, this system also continuously measures, indicates and records the radioactivity concentration levels of in-plant process streams and vents. A list of the plant process monitors is provided in Table 11.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 70 of 120 7.3.1.3.2 Area Radiation Monitoring System A list of the Area Radiation Monitors is provided in Table 12.

The functions of the Area Radiation Monitoring System are:

1. Warn of excessive gamma radiation levels in areas where nuclear fuel is stored or handled.

2. Provide operating personnel with a continuous indication in the main Control Room of gamma radiation levels at selected locations within the various plant buildings.

3. Contribute supervisory information to the Control Room so that correct decisions may be made with respect to deployment of personnel in the event of a radiation incident.

4. Assist in the detection of unauthorized or inadvertent movement of radioactive material in the plant including the radwaste area.

5. Supplement other systems including Process Radiation Monitoring, Leak Detection, etc., in detecting abnormal migrations of radioactive material in or from the process streams.

6. Provide local alarms at key points where a substantial change in radiation level might be of immediate importance to personnel frequenting the area.

7. Maintain a permanent record of the radiation levels in the areas being monitored.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 71 of 120 7.3.1.4 Process Monitors 7.3.1.4.1 There are many instruments in the plant which may be used to assess the many potential conditions that the plant may experience.

These instruments may be used individually or in groups of indicators to assess a certain situation. There is no specific indication that in itself can correctly identify an emergency condition 100% of the time. Therefore, the operators must utilize their general knowledge along with the guidelines provided in Emergency Plan Implementing Procedure A.2-101 (CLASSIFICATION OF EMERGENCIES) to analyze process indications. Specific process monitors of reactor systems which are used during various plant emergencies are discussed in Section 4.0, Emergency Classification System. In addition, a summary of the types of measured parameters in the Control Room is provided in Table 13, Instruments Available for Monitoring Major Systems.

7.3.1.4.2 Reactor Protection System The Reactor Protection System is designed to prevent, in conjunction with the Primary Containment and Containment Isolation Systems, the release of radioactive materials in excess of the guidelines of 10CFR50.67, and to prevent fuel damage as a consequence of single operator error or single equipment failure.

When specified limits have been exceeded, the Reactor Protection System initiates a reactor scram.

7.3.1.4.3 Primary Containment Isolation System The purpose of the Primary Containment Isolation System is to prevent the release of radioactive materials in excess of the guidelines of 10CFR50.67 by isolating the reactor vessel and closing containment where required following an accident.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 72 of 120 7.3.1.5 Containment Radiation Monitor There are two containment radiation monitors which have ion chamber detectors and a response range of 100 to 108 R/hr.

The detectors are located at approximately the midline of the drywell and separated to enhance the redundant feature of the system. As safety monitors, they satisfy 1E requirements and are qualified under LOCA conditions to IEEE 323-1974. The detectors are encased in steel to protect them from containment sprays and high temperatures.

In the event of a large release of radioactivity to the containment atmosphere, the containment monitors can be used to estimate the amount of activity available for release from containment.

7.3.1.6 Fire Detection Devices 7.3.1.6.1 Early Warning Fire Detectors Fire detectors (smoke, heat, and flame) are located in most areas of the plant. The detectors in each area initiate an alarm locally and in the Control Room upon detecting either combustion or a failure in the detector system.

Detectors in certain areas of the plant will activate their respective sprinkler systems.

7.3.1.6.2 HAD (Heat Activated Device)

The HAD System utilizes the heat from a fire to operate a pneumatic system to either sound alarms or automatically initiate a deluge or sprinkler system. The HAD System is used in conjunction with the building siding deluge, the cooling tower deluges, the recirculation MG set deluges, and the lube oil reservoir deluge.

These systems can also be operated locally.

7.3.1.6.3 LHD (Linear Heat Detection)

The LHD utilizes a Protectowire linear heat fire detection system and is capable of initiating an alarm once its rated activation temperature is reached.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 73 of 120 7.3.1.7 Post-Accident Sample System The Post-Accident Sample System (PASS) was designed to provide a means of assessing core damage during and after a loss-of-coolant accident. The facility is located outside of secondary containment to enhance accessibility. Local shielding and area radiation monitoring are also provided to protect the operator.

The capabilities of the system include:

7.3.1.7.1 Large and small volume liquid coolant samples from jet pumps A and B and RHR pumps A and B;

7.3.1.7.2 Gas samples from drywell and torus.

7.3.2 Facilities and Equipment for Off-Site Monitoring 7.3.2.1 Geophysical Phenomena Monitors In the event that a seismic disturbance is indicated by on-site detection equipment, plant procedures require the operator to confirm the validity and intensity of the disturbance by contacting an off-site source. The list of off-site sources includes:

7.3.2.1.1 Prairie Island Nuclear Plant (Located near Red Wing, Minnesota);

7.3.2.1.2 National Earthquake Information Service (Golden, Colorado) 7.3.2.2 Radiological Monitors The Monticello off-site radiation monitoring program includes TLD stations which are located in the general areas of the site boundary, in an outer ring, in special interest areas, and in control stations, many miles from the plant. Also included in the program is a group of air monitoring stations positioned on the site boundary and in the city of Monticello. The program, known as the Radiological Environmental Monitoring Program, is administered at the Site.

7.3.2.3 Laboratory Facilities In the event that the lab facilities on-site become unusable or overloaded, back-up facilities are available. The chemistry labs at Prairie Island are available for chemical analysis work. For radiochemical analysis, the back-up countroom at the EOF is equipped with a computer-based multi-channel analyzer and gross beta counting equipment. The counting facilities at Prairie Island are also available, if needed.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 74 of 120 7.4 Protective Facilities and Equipment 7.4.1 Assembly Points In the event of a Site Area or General Emergency, the Site Administration Building (SAB) is designated as the assembly point for evacuated personnel. The SAB is located approximately 1000 feet south of the plant.

This structure offers cover from fallout, but does not have special ventilation or shielding properties. It has the capacity to handle the number of people expected to report there. An emergency equipment locker at the assembly point contains a supply of emergency equipment and protective clothing.

The Receiving Warehouse has been identified as an alternate assembly point for specific events. This facility may be used to relocate and assemble and account for non-essential personnel during security threats.

7.4.2 Emergency Operations Facility (EOF)

The EOF is located approximately 1 mile southeast of the plant and is activated at the Alert, Site Area or General Emergency classification. The EOF is contained within the site Training Center which houses the Training Staff, administrative offices and Control Room Simulator.

The EOF was designed and constructed IAW NUREG 0696 and is a concrete structure which contains sufficient shielding (for the EOF section of the building) to provide a protection factor of 5. The EOF portion of the building is served by two independent off-site power sources for reliability.

The building ventilation system includes an emergency mode which provides filtered air to pressurize the EOF through a high efficiency particulate absolute (HEPA) filtration system. The layout of the building entrances and exits were also designed to facilitate emergency operations.

Radiological monitoring of the EOF is provided by air sampling and Dosimeter Area Radiation Monitor (DARM) which may be supplemented with radiological surveys by the EOF Radiation Protection Staff.

Extensive communications equipment is installed to provide primary and back-up methods of communicating with plant Emergency Response Facilities, utility headquarters, off-site agencies and utility Field Monitoring teams. Critical plant parameter data is available in the EOF through the plant Safety Parameter Display System (SPDS).

Meteorological data is provided by the ERIS system. Off site dose projection is provided by RASCAL.

7.4.3 Back-up EOF The Back-up EOF is located at the Xcel Energy corporate office in downtown Minneapolis, 45 miles southeast of the plant.

In the event the primary EOF became uninhabitable during a real emergency, the functions of the EOF would be transferred to the Back-up EOF.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 75 of 120 Extensive communications equipment is installed to provide primary and back-up methods of communicating with plant emergency Response Facilities, off-site agencies and utility Field Monitoring teams. Critical plant parameter data is available in the Back-up EOF through the plant Safety Parameter Display System (SPDS). Meteorological data is provided and displayed by the ERIS system. Off site dose projection is provided by RASCAL.

7.4.4 Emergency Kits Table 14 lists the location and general contents of emergency kits to be used in response to an emergency at the Monticello Plant.

7.5 First Aid and Medical Supplies 7.5.1 First Aid Center A decon shower and first aid supplies are located in the Main Access Control area in the lower level of the Plant Administration Building.

Immediate and temporary care may be given to a victim in this area. If the injury involves contamination that cannot be removed without causing further injury, steps will be taken to minimize the spread of contamination until medical assistance arrives or until the victim has been transported to the hospital.

7.5.2 First Aid Kits First Aid kits are located in the Fire Brigade Room at Main Access Control, Work Execution Center and various other areas on the plant site.

Stretchers and shock blankets are located on each level of the Containment Building, Turbine Building and Main Access Control.

7.6 Damage Control Equipment and Supplies 7.6.1 Firefighting Equipment A full line of fire fighting equipment and supplies is available for damage control operations. The equipment is stored in the Fire Brigade Room adjacent to the Main Access Control area in addition to various areas within the plant for easy access and quick response to fires.

7.6.2 Spill and Leak Control Equipment Spill and leak control equipment includes electric and gas driven pumps, various patching supplies and welding equipment. This equipment is available in the warehouse along with machine shop facilities for response to a wide variety of problems.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 76 of 120 7.7 Public Alert and Notification System (ANS)

Within the Plume Exposure Emergency Planning Zone (EPZ) there exists provisions for alerting and providing notification to the public. The state and local authorities are responsible for activation of this system.

The ANS system consists of a primary and backup activation and monitoring of outdoor warning sirens, primary and backup initiation of the Emergency Alert System (EAS), primary and backup initiation of the Integrated Public Alert and Warning System (IPAWS), county auto-dial notification systems for special populations and backup routes by siren contour and by subarea.

Emergency Planning Visitor Guides are available for distribution in all recreational areas to advise transient populations of the action they should take in the event of an accident at the MNGP. Annual Emergency Planning Guides are distributed to all residential and business addresses within the 10-mile EPZ and contain information for the public to use in the event they hear sirens or EAS Messages over the local radio system.

Activation of the ANS begins with a protective action recommendation (PAR) of evacuation or sheltering by the MNGP Emergency Director/Manager. The Minnesota Division of Homeland Security and Emergency Management (HSEM) is responsible for coordinating the recommendation and making it a decision with appropriate approvals Sherburne and Wright Counties and assigning siren activation times and EAS activation times. The Sherburne and Wright County Sheriff's Offices are responsible for activation of the outdoor warning sirens.

The system consists of 106 sirens. The 106 sirens provide 100% coverage of the populated area within the 10-mile EPZ. In the event that a siren is not working, effective areas are alerted through the use of emergency warning vehicles operated by local sheriff departments in accordance with the Sherburne and Wright Counties' plans.

Additional, detailed information about the ANS system, including system design, siren coverage analysis, testing schedules, and an evaluation of the current system is found in the Alert and Notification System Design Report.

7.8 Emergency Alert System Auto Dialing Telephone Systems To further ensure prompt notification, auto-dialing systems are used to notify various commercial, institutional, and education facilities in the 10 mile zone. These locations may harbor large groups of people during all or part of a day. Auto dialing systems will be activated by the local counties.

7.9 Mapping 10 mile EPZ maps are periodically updated to reflect population and geo-physical changes.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 77 of 120 Table 7 MONTICELLO NUCLEAR GENERATING PLANT COMMUNICATIONS MATRIX X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X MNGP Security X X X X X Incident Command Post X X X X X X PLANNING & ASSESSMENT X X X X X X X X X X X X X X X X X X X X X X X

X STATE PATROL X

X X

X X X X X X X X Xcel ENERGY SYSTEM DISP X X X X X X X X MNGP-PINGP MONITORING TEAMS X X X X

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 78 of 120 Table 8 COMMUNICATIONS CONTACTS CONTACT LOCATION PRIMARY ALTERNATE Control Room Shift Manager Control Room Supervisor EOF and Back-up EOF Emergency Manager EOF Coordinator Minnesota Division of Emergency Duty Officer Duty Officer Management Minnesota Planning and Planning Chief State Duty Officer Assessment Center Wright Country Sheriff Sheriff Dispatcher Sherburne Country Sheriff Sheriff Dispatcher Monticello Civil Defense Monticello CD Driver Sheriff Dispatcher Minnesota State Patrol (St. Cloud) Captain Dispatcher Monticello City Hall Mayor City Administrator Monticello F. D. Sheriff Dispatcher NRC HPN NRC - Operations Center Region III Lisle NRC ENS NRC - Operations Center Region III Lisle Table 9 SEISMIC MONITORING INSTRUMENTATION LOCATION DESCRIPTION ACTUATING DEVICE SETPOINT 6-C-08 Earthquake Accelerograph Trigger .01 g OR OBE Alarm Module .03 g OR DBE Alarm Module .06 g 6-C-13 Operational Basis OBE Alarm Module .03 g Earthquake 6-C-18 Design Basis DBE Alarm Module .06 g Earthquake

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 79 of 120 Table 10 ON-SITE METEOROLOGICAL MONITORING INSTRUMENTATION SENSOR LOCATION SYSTEM PARAMETER (METERS) INDICATOR LOCATIONS 100 meter WIND SPEED 10 Single train (A or B) 5 minute Tower 43 average data available on the Met 100 Recorder in the Control Room.

15 minute average data is available on computer terminals in the TSC and EOF.

WIND DIRECTION 10 Single train (A or B) 5 minute 43 average data available on the Met 100 Recorder in the Control Room.

15 minute average data is available on computer terminals in the TSC and EOF.

TEMPERATURE 10 Current and 15 minute average 43 data (both A&B) from 100 meter 100 tower available in the TSC and EOF on computer terminals.

TEMPERATURE 43 100 30 meter WIND SPEED 22 Current data available on any Tower WIND DIRECTION 22 plant process computer terminal display.

Back-up Sources of Meteorological Data Data Source Location Method National Weather Service MSP Airport and Commercial Telephone and Chanhassen, MN website NOAA Weather Alert Radio Regional Alert Radio in TSC and EOF

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 80 of 120 Table 11 PROCESS RADIATION MONITORS NUMBER OF INDICATOR MONITOR DETECTORS LOCATIONS INDICATOR RANGE Main Steam Line Radiation Monitor 4 Panel C-02, C-10 1 - 106 mrem/hr Off-gas Pretreatment Rad Monitor 2 Panel C-02, C-10 1 - 106 mrem/hr Flux Tilt Monitor 1 Panel C-02, C-10 0 - 125 units Stack WRGM 2 Panel C-257 100 - 1012 µCi/Sec Panel C-258 Reactor Building Vent WRGM 2 Panel C-257 100 - 1012 µCi/Sec Panel C-258 Fuel Pool Monitor 2 Panel C-10 0.1 - 1000 mrem/hr Reactor Building Exhause Plenum 2 Panel C-02, C-10 .01 - 100 mrem/hr Monitor Process Liquid:

Radwaste Liquid Effluent Monitor 1 Panel C-10 10 106 CPS Service Water Effluent Monitor 1 Panel C-02, C-10 10 106 CPS RBCCW Radiation Monitor 1 Panel C-02, C-10 10 106 CPS Discharge Canal Rad Monitor 2 Panel C-02, C-10 10 106 CPS Turbine Building Normal Waste 2 Panel C-02, C-10 10 - 106 CPM Sump Radiation Monitor Drywell CAM Monitor 1 Panel C-02 10 - 106 CPM Control Room Radiation 2 Panel C-257 10 104 mrem/hr Panel C-258 Sewer Lift Station 1 Panel C-249 10 - 107 CPM Hard Pipe Vent 1 Panel C-289B 10 104 mrem/hr Continuous Air Monitors

1. Primary OSC

2. TSC

3. SJAE Room (Condensate Pump Area)

4. 951 Turbine Floor East

5. 1027 Reactor Building

6. Recombiner Building (TB RR Access)

7. Off-gas Storage Building

8. 962 Reactor Building (CUPR Vent)

9. 962 RX Building East (Samples Stm Chase)

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 81 of 120 Table 12 AREA RADIATION MONITORS PANEL C-11 SENSOR SENSOR RANGE STA. AREA LOCATION (MR/HR)

BUILDING A-1 Reactor Refuel Floor 0.1 - 1000 A-2 Reactor Refuel Floor (High Range) 1.0 - 10,000 A-3 Reactor Refuel Floor West Stairway 0.1 - 1000 A-4 Reactor 1001 Source Storage 0.1 - 1000 A-5 Reactor 1001 Fuel Pool Room 0.1 - 1000 A-6 Reactor 1001 Decon Equipment Area 0.1 - 1000 A-7 Reactor 985 Chem Sample Area 0.1 - 1000 A-8 Reactor 962 Cleanup System Access 0.1 - 1000 A-9 Reactor 962 Reactor Building East 0.1 - 1000 A-10 Reactor 935 East CRD Module Area 0.1 - 1000 A-11 Reactor 935 West CRD Module Area 0.1 - 1000 A-12 Reactor 935 TIP Drive 0.1 - 1000 A-13 Reactor TIP Cubicle 1.0 - 10,000 A-14 Reactor HPCI Turbine Area 0.1 - 1000 A-15 Reactor 896 Radwaste Drain Tank Room 0.1 - 1000 A-16 Reactor RCIC Pump Area 0.1 - 1000 A-17 Reactor A RHR Room 0.1 - 1000 A-18 Reactor B RHR Room 0.1 - 1000 A-19 Office Chemistry Lab 0.1 - 1000 A-20 Office Control Room (Low Range) 0.01 - 100 A-21 Office Control Room (High Range) 1.0 - 10,000 B-1 Turbine Operating Floor (North Wall) 1.0 - 10,000 B-2 Turbine Shield Wall 0.1 - 1000 B-3 Turbine Condensate Demin Operating 0.1 - 1000 Area B-4 Turbine MVP Room 0.1 - 1000 B-5 Turbine Feedwater Pump Area 0.1 - 1000 C-1 Radwaste Radwaste Control Room 0.1 - 1000 C-3 Radwaste Conveyor Operating Aisle 0.1 - 1000 D-1 13.8kV Switchgear 13.8kV Switchgear Room 0.1 - 1000 Room

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 82 of 120 Table 12 AREA RADIATION MONITORS (CONTD)

PANEL C-252 &

C-11 SENSOR SENSOR RANGE STA. AREA LOCATION (MR/HR)

BUILDING E-1 Recombiner Instrument Room 0.1 - 1000 E-2 Recombiner Pump Room 0.1 - 1000 F-1 Gas Storage Foyer (Low Range) 0.1 - 1000 F-2 Gas Storage Foyer (High Range) 100 - 1,000,000 PANEL C-257 &

C-258 SENSOR SENSOR RANGE STA. AREA LOCATION (MR/HR)

BUILDING Reactor Containment 100 - 108 R/HR

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 83 of 120 Table 13 INSTRUMENTS AVAILABLE FOR MONITORING MAJOR SYSTEMS Measured Indicator Parameter Type of Readout Range Location

1. Source Range

a. Neutron Level Log Scale Indicator, 10-1 to 106 CPS System Cabinets Recorder, Annunciator Main Control Panels

b. Reactor Period Linear Scale Indicator, -100 to 10 Sec System Cabinets Annunciator Main Control Panels

2. Intermediate Range

a. Neutron Level Digital Bargraph 0 to 125 (units) System Cabinets Display, Recorder, Main Control Annunciator Panels

3. Power Range

a. Neutron Level Linear Scale Indicator, 0 to 125% System Cabinets Recorder, Annunciator Main Control Panels

4. Reactor Coolant Range

a. Recirc Loop Linear Scale Indicator, 0 to 600°F Main Control Temperature Computer Printout Panels

b. Reactor Pressure Linear Indicator, 0 to 1500 PSIG Main Control Recorder, Computer Panels Printout, Annunciator

c. Core Flow Linear Scale 0 to 80 x 106 Main Control LB/HR Panels

d. Circ Flow Linear Indicator, 0 to 35 x 103 Main Control Recorder, Computer GPM Panels Printout

e. Jet Pump Flow Linear Scale Indicator, 0 to 44 x 106 Main Control Computer Printout LB/HR Panels

5. Main Steam

a. Steam Line Flow Linear Indicator 0 to 2.5 x 106 Main Control LB/HR Panels

b. Total Steam Flow Linear Scale Recorder 0 to 10 x 106 Main Control LBS/HR Panels

c. Main Steam Line Linear Scale Indicator, 900 to 1000 psig Main Control Pressure Computer Printout (on C-07) Panels 0 to 1200 psig (on C-03)

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 84 of 120 Table 13 INSTRUMENTS AVAILABLE FOR MONITORING MAJOR SYSTEMS (CONTD)

Measured Indicator Parameter Type of Readout Range Location

6. Containment

a. Pressure Linear Scale -2 to +3 psig Main Control Recorder, Computer recorder Panels Printout, Annunciator 0-80 psig recorder 0 to +250 psig recorder

b. Torus Pressure Linear Scale Recorder -2 to +3 psig Main Control Panels

c. Torus Level Linear Scale Indicator -15 to 15 Main Control

-8 to 14 Panels recorder (in Linear Feet)

d. Torus Water Digital Indicator, 30° - 240°F Main Control Temperature Annunciator Panels

e. N2 Makeup Flow Linear Scale 0 - 2 SCFM Main Control Recorder, Annunciator Panels

f. N2 Purge Flow Linear Scale Indicator 0 - 5000 SCFM Main Control Panels

g. Drywell Sumps Level Recorder 0 - 14 Main Control Panels

h. Drywell Cooling Indicator Lights Stby/Off/On System Cabinet Fans Control Panels

7. Station Electric

a. Busses 15 and 16 Linear Scale Indicator, 0-5250 AC Volts Main Control 4.16 KV Bus Annunciators Panels Voltage

b. Breaker Positions Indicator Lights Open/Closed Main Control Panels

c. Amperage Linear Scale Various Main Control Indicators Panels

d. Generator Output Linear Scale 0 to 800 MW Main Control Recorder, Indicator, 0 to 700 MW Panels Computer Printout

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 85 of 120 Table 13 INSTRUMENTS AVAILABLE FOR MONITORING MAJOR SYSTEMS (CONTD)

Measured Indicator Parameter Type of Readout Range Location

8. Feedwater Condensate

a. Feedwater Linear Scale Recorder 32 to 430°F Main Control Temperature Panels

b. Condensate Linear Scale Indicator 0 to 500 psig Main Control Header Pressure Panels

c. Feedwater Linear Scale Indicator 0 to 2000 psig Main Control Discharge Pres and Recorder Panels

d. Feedwater Flow Linear Scale Indicator 0 to 5 x 106 Main Control LB/HR Panels

e. Total Feedwater Linear Scale Recorder 0 to 10 x 106 Main Control Flow LB/HR Panels

9. Condenser Systems

a. Condenser Linear Scale 0 to 30 HG Vac Main Control Vacuum Recorder, Annunciator Panels

b. Hotwell Level Linear Scale -15 to +15 Main Control Recorder, Annunciator Panels

c. CST Level Linear Scale Indicator 5 to 30 Main Control Panels

10. ECCS Systems

a. LPCI, Core Spray Indicator Light ----

Pump Status

b. LPCI Flow Square Root Scale 0 to 10,000 GPM Main Control Recorder, Indicator Panels

c. Core Spray Flow Square Root Scale 0 to 5000 GPM Main Control Indicator Panels

d. LPCI Core Spray Indicator Lights ---- Main Control Valve Positions Computer Printout Panels

e. ADS Valve Indicator Lights ---- Main Control Positions Annunciator Panels

f. ADS Discharge Linear Scale 0 to 600°F System Temperature Recorder, Annunciator Temperature Recorder

g. HPCI Flow Linear Scale Indicator 0 to 3500 GPM Main Control Panel

11. Decay Heat Removal System

a. RCIC Flow Linear Scale Indicator/ 0 to 500 GPM Main Control Controller Panel

b. LPCI Mode of RHR (see above)

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 86 of 120 Table 14 EMERGENCY KITS LOCATION GENERAL CONTENTS Site Administration Building Protective Clothing & Equipment Assembly Point Radiological Monitoring Equipment Emergency Supplies Personnel Decontamination Supplies First Aid Kit Control Room & Work Execution Center Protective Clothing & Equipment Radiological Monitoring Equipment Communications Equipment Toxic Chemical Monitoring Equipment Emergency Supplies First Aid Kits Access Control Protective Clothing & Equipment Radiological Monitoring Equipment Personnel Decontamination Equipment First Aid Kits Technical Support Center Radiological Monitoring Equipment Communications Equipment Emergency Supplies Emergency Operations Facility Protective Clothing & Equipment Radiological Monitoring Equipment Communications Equipment Personnel Decontamination Equipment Emergency Supplies First Aid Kit Emergency Vehicle & Vehicles for Emergency Use (2)

Equipment Storage Facility Radiological Monitoring Equipment Protective Clothing & Equipment Communications Equipment Emergency Supplies Monticello Plant Security Access Facility Protective Clothing & Equipment (Ambulance/Fire E Kit) Dosimetry CentraCare Health Monticello Protective Clothing & Equipment

& North Memorial Hospital Radiological Monitoring Equipment Personnel Decontamination Equipment Emergency Supplies

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 87 of 120 8.0 MAINTAINING EMERGENCY PREPAREDNESS 8.1 Organizational Preparedness 8.1.1 Emergency Response Organization Training Training of ERO personnel is controlled by the EP Training Program Description (TPD). The requirements for training in the TPD are based on a graded approach to the systematic approach to training.

Off-site Emergency Preparedness Coordinators will make provisions for the training of those off-site organizations who may be called upon to provide assistance in the event of an emergency.

8.1.2 Drills, Exercises and Tests The Off-site Nuclear Emergency Plan contains the specific requirements for the conduct of required drills and exercises.

The conduct of periodic drills and exercises are the responsibility of the Monticello Business Support Group in accordance with the Emergency Preparedness Drill & Exercise Manual, which includes:

8.1.2.1 An exercise which tests the integrated capability and basic elements of the Emergency Plan SHALL be conducted every 2 years. This exercise may be included in the full participation biennial exercise which tests the off-site state and local emergency plans.

8.1.2.2 In order to ensure that adequate emergency response capabilities are maintained during the interval between biennial exercises, drills SHALL be conducted including at least one drill involving a combination of some of the principal functional areas of the on-site emergency response capabilities. The principal functional areas of emergency response include activities such as management and coordination of emergency response, accident assessment, protective action decision making, and plant system repair and corrective actions. During these drills, activation of all of the Emergency Plans response facilities (TSC, OSC, and EOF) is not necessary, opportunities to consider accident management strategies may be provided, supervised instruction is permitted, operating staff may have the opportunity to resolve problems (success paths) rather than have controllers intervene, and the drills may focus on on-site training objectives.

8.1.2.3 A medical emergency drill, involving response to and transport of a simulated contaminated, injured individual, which provides for off-site support agency participation, SHALL be conducted annually.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 88 of 120 8.1.2.4 Health Physics Drills which involve response to and analysis of simulated elevated airborne or liquid samples and direct radiation measurements in the environment SHALL be conducted semi-annually. These drills may be performed as stand alone Health Physics Drills or included as part of other drills or exercises.

8.1.2.4.1 The analysis of in-plant liquid samples (with actual elevated radiation levels) including the use of the Post Accident Sampling System (PASS) will be included in biennial chemistry training/walkthroughs and may be performed in conjunction with full scale exercises/drills or Health Physics drills.

8.1.2.4.2 Radiological monitoring drills which include the collection and analysis of environmental samples for the purpose of ground deposition assessment SHALL be conducted annually and may be performed as stand alone Health Physics Drills or included as part of other drills or exercises.

8.1.2.5 Fire Drills SHALL be conducted in accordance with applicable Plant Administrative Control Directives.

8.1.2.6 In addition to drills and exercises, periodic tests are conducted to ensure an adequate state of emergency preparedness is maintained. These tests include:

8.1.2.6.1 Communications tests with State and Local government agencies, local law enforcement, and off-site facilities within the plume EPZ are conducted monthly in accordance with plant Surveillance 1225.

8.1.2.6.2 Communications tests with the NRC via the Emergency Notification System (ENS ) and Health Physics Network (HPN) are conducted monthly in accordance with Surveillance 1225.

8.1.2.6.3 Emergency Response Organization Augmentation tests are conducted quarterly in accordance with plant Surveillance 1317.

8.1.2.6.4 The Public Alert Notification System (ANS) is tested weekly in accordance with plant Surveillance Test 1359.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 89 of 120 8.1.2.6.5 The Annual Performance Review for the ANS is conducted in accordance with plant Surveillance 1408.

8.1.2.6.6 The Emergency Alert System Auto Dialing Telephone Systems are tested by Sherburne County and Wright County staff. Completion of the testing and system maintenance is verified on a semi-annual basis in accordance with plant Surveillance 1410.

8.1.2.6.7 The ERDS communication link is tested on a quarterly basis in accordance with plant Surveillance 1416.

8.2 Planning 8.2.1 Responsibility The overall responsibility for radiological emergency response planning rests with NSPM management.

At the site level the Site Vice President, Monticello Site has overall authority and responsibility for the Monticello Emergency Plan and Emergency Plan Implementing Procedures. The Site Emergency Planners are responsible for the development and updating of the Emergency Plan and coordination of the plan with off-site emergency response plans.

8.2.2 Review and Updating of the Emergency Plan The Monticello Emergency Plan SHALL be reviewed and certified to be current on an annual basis in accordance with the Off-site Nuclear Emergency Plan. Other reviews of the Emergency Plan and Implementing Procedures will be performed as required by Technical Specifications.

Annual revisions to the Emergency Plan are conducted in accordance with Surveillance Procedure 1406 and may be based on the following:

8.2.2.1 Lessons learned during drills and exercises and industry lessons learned.

8.2.2.2 Changes in the normal plant or Emergency Response Organization structures.

8.2.2.3 Modifications to plant systems, components or instrumentation.

8.2.2.4 Changes in the functions or responsibilities of supporting agencies and organizations.

8.2.2.5 Lessons learned from real emergency plan activations.

8.2.2.6 Changes in State or Federal regulations.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 90 of 120 Changes to the Emergency Plan SHALL be reviewed and approved in accordance with plant Technical Specifications and applicable Administrative Control Directives. Distribution of controlled copies of the Emergency Plan SHALL be performed in accordance with applicable MNGP document control procedures.

In addition to the annual review, all Emergency Plan Implementing Procedures containing telephone numbers are reviewed at least quarterly to verify the correct numbers in accordance with Surveillance Procedure 1240.

8.3 Maintenance and Inventory of Emergency Equipment and Supplies 8.3.1 Equipment and Supplies Inventory Emergency Equipment and supplies SHALL be inventoried at least quarterly in accordance with plant Surveillance Procedure 1102.

8.3.2 Instrument and Facilities Functional Check Key emergency response equipment and instrumentation located in the Technical Support Center and Emergency Operation Facility is tested monthly in accordance with plant Surveillance Test 1230.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 91 of 120 9.0 RECOVERY 9.1 General Approach In general, the site organization will be responsible for the short term recovery, that is recovery from an emergency condition in which no core damage or serious release of radioactivity to the environment has occurred.

If it is clear that a high potential exists for core damage or a serious release of radioactivity to the environment has occurred, a Recovery Phase will be activated to provide for the long-term recovery actions and for establishing support arrangements.

Before reoccupying buildings after an emergency, certain recovery criteria must be satisfied:

There must be assurance that the problem encountered is solved and that the same incident cannot immediately recur; The normally occupied areas must be free of significant contamination; Radiation areas and High Radiation areas must be properly defined; Airborne radioactivity must be eliminated or controlled.

9.2 Investigation of Incidents All incidents SHALL be investigated by qualified plant staff personnel and reported to the Plant Operations Review Committee, Management and Safety Review Committee (MSRC) and the NRC in accordance with guidelines for reportable events which are set forth in the Administrative Control Directives and the Technical Specifications.

9.3 Recovery Procedures All recovery operations SHALL be performed in accordance with written procedures.

These procedures SHALL include the following activities:

Investigation of the course of the incident.

Investigation of plant conditions following an accident.

Repair and restoration of facilities.

Testing and startup of restored facilities.

Methods for determining the extent of radioactive contamination and general protective measures to be taken for personnel performing recovery operations are established in site Radiation Protection Procedures.

Written procedures for recovery of the facility from the specific post accident conditions will be prepared by qualified plant staff members and submitted to the Plant Operations Review Committee. The Plant Operations Review Committee approval of all such procedures is required prior to their initiation.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 92 of 120 9.4 Criteria for Resumption of Operation If the plant is shutdown as the result of an emergency, it will be restarted only when:

The conditions which caused the emergency are corrected.

The cause of the emergency is understood.

Restoration, repair and testing is completed as required.

No unreviewed safety questions exist.

All conditions of the license and technical specifications are satisfied.

9.5 Long Term Recovery If extensive plant damage exists and contamination of plant or site environs has occurred, then a Recovery Phase will be required.

Activation of the Recovery Phase will take place in an incremental manner as the functions change from operational to engineering/construction. The decision to activate the Recovery Phase will be made by Site Management. The Recovery Manager will be selected from several qualified designees who are members of the site organization. The Emergency Manager and the Emergency Director will share responsibility at least during the early part of the Recovery Phase.

If a transition to the Recovery Phase becomes necessary, the site engineering/construction oriented staff would provide the nucleus of the organization responsible to carry out the Recovery Phase.

The plant staff would be augmented as required by specialists from the site organization and the NSPM/Xcel Energy corporate office. These speciality areas include Engineering Services, Licensing Administration, Maintenance, Quality Assurance, Communications and Security personnel. In addition, appropriate assistance would be secured from the Architect-Engineer and the Technical Support Services vendor organizations. This support could be broadened as required by consultant help from the several organizations familiar with the MNGP and organization. The overall organizations envisioned for a substantial Recovery Phase would be a blend of site staff and appropriate vendor and consultant personnel. On a prior basis it is counter productive to define in detail the extensive organization that might be involved in a sizable Recovery Phase because of the unlimited variation of conditions that could result from plant emergencies. However, the nucleus organization has been identified together with guidelines on how the organization might be expanded to meet the requirements demanded at the time.

When the Emergency Manager and Emergency Director agree that the emergency condition has been terminated, a complete transfer of the responsibilities for off-site support may be made to the Recovery Organization. The EOF will then become the Recovery Center and will function as Command Center for the Recovery Organization activation and implementation in accordance with applicable Emergency Plan Implementing Procedures.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 93 of 120 10.0 APPENDIX A Plan Section Procedure No. Procedure Title Reference 000 Series Organization A.2-001 Emergency Organization 5.1, 5.2, 5.3 100 Series Activation A.2-101 Classification of Emergencies 4.0, 6.2.2, Annex A A.2-102 Notification of an Unusual Event (NUE) 4.1, 6.1.1, Annex A A.2-103 Alert 4.2, 6.1.2, Annex A A.2-104 Site Area Emergency 4.3, 6.1.3, Annex A A.2-105 General Emergency 4.4, 6.1.4, Annex A A.2-106 Activation And Operation of the TSC 5.2.1, 7.1.1 A.2-107 Activation And Operation of the OSC 5.2.2, 7.1.2 A.2-108 Access Control During Emergencies 7.1.6 A.2-109 Activation and Operation of the Back-Up OSC 7.1.2 A.2-110 Response to a Security Threat 5.3.2 A.2-111 Activation of Alternative Facilities During a Security 7.1.4 Event 200 Series Assessment A.2-201 On-Site Protective Action 6.3.2, 6.5 A.2-202 Off-Site Monitoring During an Emergency 6.3 A.2-203 Radioactive Liquid Releases 6.3 A.2-204 Off-Site Protective Action Recommendations 6.5.1.2 A.2-205 Personnel Accountability 6.5.1, 7.1.5 A.2-206 Work Control During Emergencies 5.3.1.6, 6.4.2 A.2-208 Core Damage Assessment 7.3.1.5 A.2-209 Responsibilities of the Radiological Emergency Coordinator 5.2.1.2 A.2-210 Engineering Support in the TSC 5.2.1.5 A.2-213 Responsibilities of the Emergency Director 5.2.1.1

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 94 of 120 10.0 APPENDIX A (CONTD)

Plan Section Procedure No. Procedure Title Reference 300 Series Protective Actions A.2-301 Emergency Evacuation 6.5.1, 6.5.2 A.2-302 Activation of the Assembly Points 6.5.1, 7.1.5 A.2-303 Search and Rescue 5.3.1.8 A.2-304 Thyroid Prophylaxis (Potassium Iodide Use) 6.5.4.2 400 Series Radiological Surveillance and Control A.2-401 Emergency Exposure Control 6.5.5 A.2-402 On-Site Radiological Monitoring 6.5.6, 6.3 A.2-404 Emergency Air Sampling and Analysis 6.3 A.2-405 Release Rate Determinations 6.3.1 A.2-406 Off-Site Dose Projection 6.3.2 A.2-407 Personnel & Vehicle Monitoring And 6.5.1 Decontamination A.2-408 Sample Coordination During Emergencies 6.3 A.2-409 Self-Contained Breathing Apparatus (SCBA) Use 6.5.4.1 During an Emergency A.2-410 Out-of-Plant Surveys 6.3.3 A.2-411 Establishment of a Secondary Access Control 7.1.6 Point A.2-412 Reactor Coolant Sample Obtained from Reactor Sample Station 7.3.1.7 A.2-413 Small Volume Liquid Sample Obtained at the Post Accident Sampling System 7.3.1.7 A.2-414 Large Volume Liquid Sample Obtained at Post Accident Sampling System 7.3.1.7 A.2-415 Containment Gas Sample Obtained at Post Accident Sampling System 7.3.1.7 A.2-417 Draining the Trap, Sump and Collector of Post Accident Sampling System 7.3.1.7

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 95 of 120 10.0 APPENDIX A (CONTD)

Plan Section Procedure No. Procedure Title Reference A.2-418 Post Accident Sampling Station Demin Water Tank Fill Procedure 7.3.1.7 A.2-419 Containment Atmosphere Sample Obtained from Reactor Sample Station 7.3.1.7 A.2-420 Containment Atmosphere Radiochemical Analysis 7.3.1.7 A.2-422 Stack Iodine/Particulate Sampling and Analysis 6.3.1 A.2-423 Reactor Building Vents Iodine/Particulate Sampling

& Analysis 6.3.1 A.2-424 EOF Count Room Procedures 7.3.2.3 500 Series Communications and Documentation A.2-501 Communications During an Emergency 7.2 A.2-502 Record Keeping During an Emergency ---

A.2-504 Emergency Communicator Duties in the TSC And OSC 5.2.1.8 600 Series Re-Entry and Recovery A.2-601 Re-Entry 9.1 A.2-602 Event Termination or Recovery 9.5 700 Series Emergency Preparedness A.2-701 PANS System False Activation or Failure ---

A.2-702 Response to an Emergency at Prairie Island ---

A.2-703 Response to Off-Site Situations Involving Radioactive Material ---

800 Series EOF Procedures A.2-801 Responsibilities of the Emergency Manager 5.2.3.1, 7.1.3 A.2-802 Activation and Operation of the EOF 5.2.3.4, 7.1.3 A.2-803 Emergency Communications at the EOF 5.2.3, 7.1.3 A.2-804 EOF Support and Logistics 5.2.3.4, 7.1.3 A.2-805 Technical Support in the EOF 5.2.3.2, 7.1.3

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 96 of 120 10.0 APPENDIX A (CONTD)

Plan Section Procedure No. Procedure Title Reference A.2-806 Radiation Protection Support in the EOF 5.2.3.3, 7.1.3 A.2-807 Off-Site Dose Assessment and Protective Action Recommendations 5.2.3.3, 7.1.3 A.2-808 Radiological Monitoring and Control at the EOF 5.2.3.4, 7.1.3 A.2-809 EOF Security 5.2.3.4, 7.1.3 A.2-810 Transfer to the Backup EOF 7.4.3 A.2-811 Event Termination or Recovery in the EOF 9.0 A.2-812 Off-site Agency Liaison at the EOF 5.2.3.4, 7.1.3

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 97 of 120 11.0 APPENDIX B NUREG-0654 Section Emergency Plan Section A. Assignment of Responsibility 1.a. 5.4 & 5.5 1.b. 5.4 & 5.5 1.c. Figure 13.2, Figure 13.3 1.d. 5.2 1.e. 5.1 & 5.2 2.a. State/Local Plans 2.b. State/Local Plans 3 Off-Site Plan 4 5.2, 5.2.1.3 B. On-Site Emergency Organization 1 5.1.2 2 5.2.1.1, 5.3.1.2 3 5.3.1.2 4 5.2, 5.2.1.1, 5.3.1.2 5 5.2, 5.3.1 & 5.3.2, Table 1 6 Figure 13.2, Figure 13.3 7 5.2.3, Off-site Plan 7.a. 5.2.3, Off-site Plan 7.b. 5.2.3, Off-site Plan 7.c. 5.2.3, Off-site Plan 7.d. 5.2.3, Off-site Plan 8 Off-site Plan & 5.4 9 5.4.2

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 98 of 120 11.0 APPENDIX B (CONTD)

NUREG-0654 Section Emergency Plan Section C. Emergency Response Support and Resources 1.a. 5.2.3.1 1.b. Off-site Plan 1.c. Off-site Plan 2.a. State/Local Plans 2.b. Off-site Plan 3 7.3.2.3 Off-site Plan 4 Off-site Plan D. Emergency Classification System 1 Section 4.0, Annex A 2 Section 4.0, Annex A 3 State/Local Plans 4 State/Local Plans E. Emergency Classification System 1 6.2.1.2, 6.2.3 2 6.2.1.1 3 6.2.1.2 4.a. 6.2.1.2.1 4.b. 6.2.1.2.2 4.c. 6.2.1.2.3 4.d. 6.2.1.2.4 4.e. 6.2.1.2.5 4.f. 6.2.1.2.6 4.g. 6.2.1.2.7 4.h. 6.2.1.2.8 4.i. 6.2.1.2.9 4.j. 6.2.1.2.10 4.k. 6.2.1.2.11

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 99 of 120 11.0 APPENDIX B (CONTD)

NUREG-0654 Section Emergency Plan Section 4.l. 6.2.1.2.12 4.m. 6.2.1.2.13 4.n. 6.2.1.2.14 5 State/Local Plans 6 6.2.1.4 7 6.5.1.3, State/Local Plans F. Emergency Communications 1.a. 7.2 1.b. 7.2 1.c. 7.2 1.d. 7.2, 7.2.3.3 1.e. 6.2, 7.2.3.2 1.f. 7.2, 7.2.3.3 2 7.2.2 3 7.2.5 G. Public Education and Information 1 Off-site Plan 2 Off-site Plan 3.a. Off-site Plan 3.b. 7.1.3 Off-site Plan 4.a. Off-site Plan 4.b. Off-site Plan 4.c. Off-site Plan 5 Off-site Plan

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 100 of 120 11.0 APPENDIX B (CONTD)

NUREG-0654 Section Emergency Plan Section H. Emergency Facilities and Equipment 1 7.1.1, 7.1.2 2 7.1.3 3 State/Local Plans 4 6.2.1.1 5 Table 9 through Table 13 5.a. 7.3.1.2, Table 9 and Table 10 5.b. 7.3.1.3, Table 11 and Table 12 5.c. 7.3.1.4, Table 13 5.d. 7.3.1.6 6.a. 7.3.2.1 6.b. 7.3.2.2 6.c. 7.3.2.3 7 7.4.4, Table 14 8 7.3.1.2.2 9 7.1.2 10 8.3.1 11 Table 14 12 7.3.2.3 I. Accident Assessment 1 4.0, Table 9 through Table 13 2 6.3, 7.3 3.a. 6.3.1 3.b. 6.3.1 4 6.3.2 5 7.3.1.2.2, Table 10 6 6.3.1, 6.3.2

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 101 of 120 11.0 APPENDIX B (CONTD)

NUREG-0654 Section Emergency Plan Section 7 6.3.3 8 6.3.2, 6.3.3 9 6.3.3 10 6.3.2 11 State Plan J. Protective Response 1.a. 6.5.1 1.b. 6.5.1 1.c. 6.5.1 1.d. 6.5.1.1 2 6.5.2 3 6.5.1.1 4 6.5.1.1 5 6.5.1.1 6.a. 6.5.4 6.b. 6.5.4 6.c. 6.5.4.2 7 6.5.1.2 8 6.5.3 9 State/Local Plan 10.a. Off-site Plan 10.b. Off-site Plan 10.c. 7.7 and 7.8 10.d. State/Local Plan 10.e. State/Local Plan 10.f. State/Local Plan 10.g. State/Local Plan 10.h. State/Local Plan

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 102 of 120 11.0 APPENDIX B (CONTD)

NUREG-0654 Section Emergency Plan Section 10.i. State/Local Plan 10.j. State/Local Plan 10.k. State/Local Plan 10.l. State/Local Plan 10.m. 6.5.1.2, Table 3 thru Table 6, State/Local 11 State/Local 12 State/Local K. Radiological Exposure Control 1.a. 6.6 & Table 6 1.b. 6.6 & Table 6 1.c. 6.6 & Table 6 1.d. 6.6 & Table 6 1.e. 6.6 & Table 6 1.f. 6.6 & Table 6 1.g. 6.6 & Table 6 2 6.5.5 3.a. 6.5.5.2 3.b. 6.5.5 4 State/Local Plans 5.a. 6.6.1 5.b. 6.6.1 6.a. 6.5.6.1 6.b. 6.5.6 6.c. 6.5.6.1 7 6.1.1.1

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 103 of 120 11.0 APPENDIX B (CONTD)

NUREG-0654 Section Emergency Plan Section L. Medical and Public Health Support 1 6.6.2, 6.6.3 2 6.6.1.2 3 State Plan 4 5.4.2, 6.6.2 M. Recovery and Re-entry Planning and Post Accident Operations 1 9.0 2 9.0 3 9.0, Off-site Plan 4 6.3.2 N. Exercises and Drills 1.a. 8.1.2.1 1.b. 8.1.2 2.a. 8.1.2.6 2.b. 8.1.2.5 2.c. 8.1.2.3 2.d. 8.1.2.2 2.e. 8.1.2.4 3.a. 8.1.2 3.b. 8.1.2 3.c. 8.1.2 3.d. 8.1.2 3.e. 8.1.2 3.f. 8.1.2 4 8.1.2 5 8.1.2

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 104 of 120 11.0 APPENDIX B (CONTD)

NUREG-0654 Section Emergency Plan Section O. Radiological Emergency Response Training 1 8.1.1 & Off-site Plan 1.a. 8.1.1 & Off-site Plan 1.b. 8.1.1 & State/Local Plans 2 8.1.2 3 6.6.1.2 & Off-site Plan 4.a. 8.1.1 & Off-site Plan 4.b. 8.1.1 & Off-site Plan 4.c. 8.1.1 & Off-site Plan 4.d. 8.1.1 & Off-site Plan 4.e. 8.1.1 & Off-site Plan 4.f. 8.1.1 & Off-site Plan 4.g. 8.1.1 & Off-site Plan 4.h. 8.1.1 & Off-site Plan 4.i. 8.1.1 & Off-site Plan 4.j. 8.1.1 & Off-site Plan 5 8.1.1 & Off-site Plan P. Responsibility for the Planning Effort: Development, Periodic Review and Distribution of Emergency Plans 1 Off-site Plan 2 8.2.1 3 8.2.1 4 8.2.2 5 8.2.2 6 8.2.2 7 Appendix A 8 Appendix B, Table of Contents 9 Off-site Plan 10 8.2.2

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 105 of 120 12.0 ANNEX A MNGP EMERGENCY ACTION LEVELS AND APPLICABLE DEFINITIONS Emergency Action Levels The site specific Emergency Action Levels are contained in Form 5790-101-02 (MONTICELLO NUCLEAR GENERATING PLANT EMERGENCY ACTION LEVEL MATRIX). These EALs are based on NEI 99-01, Revision 4, and Security ICs and EALs from NEI 99-01, Revision 5.

Emergency Plan Implementing Procedure A.2-101 (CLASSIFICATION OF EMERGENCIES) requires use of Form 5790-101-02.

I I MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 106 of 120 12.0 FIGURE Annex A-1 Monticello Nuclear Generating Plant Emergency Action Level Matrix Left half of Page 1 of Form 5790-101-02

~l~~~ftil~l~i GENERAL EMERGENCY I SITE AREA EMERGENCY I ALERT I UNUSUAL EVENT I 1110 1 Ot'kb Oou ltesuiUrog from an Act laM o r lmmi!Mnt lltiiNH of ItS! Oftllll Dose bsulllng from ~n Aetu.ill or~lll llt ele- ol ItA I Ai'r1 UNPl.ANNEOII..N H ol ~eooS Of Llquld iii ~IICIIYitylo 11M ltul Any UNPLANNED llleiNSe o f OHeOUS Of Liquid lllidOKtMiy to the o .......s lbdl....,llvlty b.ce.<ls 1000 mltltm TI!OE or i1000 mit..,. G.io.M OUs lbdkwctMI ~ b c - s 100 m lt.m TEDE. or 500 IRII:..., EnYir-o.....- 1~ ExcM <k 200 11m . . IIMOfiU!e Dou C*UI..Ion Envlronmenl lhill Exc-*Y...., n .... the Ofh.il* Do!t* C*=UI.tllon fhrl!rold Cot! fof lh* Act!a! or l"rojKted Ournlon of thellefNse ltlyrold COl! for tiM Actual or Pro)KMO 0\nUon of the ll:e!Nse MinUii! LimlfO! lS.nuln OI L~ M~nuiiUmit:fOI &O itllinYI H OIL~r Utlrtg ActiMI MI I -Oiagy Note* lfOoM11S6eMment reS~.~tsare*~a~ble *tne tJmeol Note lldo5ell~results are.-vaQt.leatltletl.meol 0 RA1 .1 I 1 I 2 I 3 I

• I 5 I DEF I 0 RU1.1 I 1 I 2 I 3 I

• I 5 I OEF I

<l<<:laraboro. the clnSificatlon should be bawd Ql"j RG 1 2 rtstNd r:l dedaratJon. toe clawlficabon ~be bt!Md on RS1 2 m.tead of VAUO reading on arry effluent I'T'()flltor tha,t ex~ 200 tirrlet> VALl) reacting on &nf effluerc morvtor that t')(ceeds two ttmes RS1 1 'M'Iile necewary dedlratioos should not be ~ed ll'lo9lli:'lg the alarm setporn established bV a CU'rent radioactMty RG11 'lloNeMCeSNI~<Ieclarabons.tlouldi'KltbeOelayedawaibng t"'-lltt. tl'le~n;wwmenttho\.lld be initi;Jited lco~ inor<lef retUb, thedoMa'loW~tholild be in~ted/oompleoteol;;f in~ lhe alarm setpolnt establ1s.hed by' a current radioactNrty to<ietet"rnne lfthec:ln.5oific..oon tho~o~ld be w~uel"(lyncWate<l !Odetefmne fthe~~bontho\111::1 bewbwquently ~ated chcharge permit for 15 m~nlies or longer discharge permt lor 60 mrutes or longer 0 RG1 .1 I 1 I 2 I 3 I 4 I 5 I DEF I 0 RS1.1 I 1 I 2 I 3 I 4 I 5 I DEF I VALID read11"Q on any of the follOWing rad!atJOn morutors lhal VALID readi!"Q on any of the lolloN*ng radiatiOn monrtors that 0 AA1 .2 I 1 I 2 I 3 I 4 I 5 I DEF I 0 RU1.2 I 1 I 2 I 3 I 4 I 5 I DEF I e'll;ceeds or es expiKted to exoeed the read*ng ~n for ~ S exceeds or *sexpected to exceed the readirg a.hoWn lor 15 VALID readtng on q d the loiiOWtf"G radiatiOn monitors that VALV reading on q of the following radiat1011 morvtors that fY'li!"UesoriOOQel' IT"'Illtes or IOnQef ex<::eede. the re&ang Shown for 15 l'nlrute& or IO!'Ot'f ~ceea& the reaot!ll Shown for 60 mr..tes or lOnger Mo11tor GE Monttor SAE Montor Alert Monttor UE

~~uentMorvtor 21E91JCtlseC ~ ~uertMorilof 21E81-1CIIsec ~luentMonilor 1 46E7 "Qisec* ~uentMontor 7.3E51-1Cifsec (Ch AorB) (ChAorB) (Ch AorB) (ChAorB)

RB Vent Emuerl: Monitor 1.5E8 .,.Qisec RB Vent E ffluent Mor1tor 1.5E7 "Qisec RBVeni: EmuertMonll.or RB Vent Effluent Mo11tor 216E4 .,.Cilsec c_...,

Ofhltelt ~

(ChAor8) (ChAocB) (ChAorB)

2. 1 6E6~

(ChAorB) l.iSWQ l.iSI.Ii<l ~ LW<I SeNteewater NIA St'Ntcewater NIA ServteeWater 31,400cps Servtce water 314 cps Discharge Canal Morwtor NIA Dtscharge canal Montor NIA Discharge Canal Monitor 93,000 cps Discharge Garel Mo11tor 930 cpt5 TBNWS NIA TBNWS NIA TEr-1\NS OOOOOOcom- TEr-M'S 37 752 com 0 R01 2 I 1 I 2 I 3 I 4 I 5 I DEF I 0 RS1.2 I 1 I 2 I 3 I 4 I 6 I DEF I 0 AA1 3 I 1 I 2 I 3 I 4 I 6 I DEF I o RU13 I 1 I 2 I 3 I ,. I 5 j oe=l Dose assessment USII'g actua I meteorologt tndtcates doseS Dose assessment USifll actual meteorology tndicates ooses Conftrmed safl'llle analysts for gaseous. or Nq:.id re ~ase Confirmed saflllle analy&IS for gaseous or ltqi.Jid release GREATER THAN 1000 ~emTEOEor 5000~em thyroid GREATER THAN 100 mRem T EOE or 500 mRem tJ'¥rotd CCE if'ldc.ates concer<<ratJOn& or release rates, wtth a release II"'Cicates (l()(l()enttatJOI"S. or release rates, Wttrt a release cl.l"ahJn ol 15 ITWJ.Jtes or lorqer, 1n excess d 200 tunesOOCM dura!Jon of 60 ll'W'lUtes or longer, 111 excess d two 111nes OOCM COE at or beyOild the Me bt:::ulclary atort::teyondtnes.ttebo\.ndary 0 RG1.3 I 1 I 2 I 3 I 4 I 5 I DEF Fiek:l survey results indicate dosed ..,;I"'Cbw d:lse rate~

I 0 RS1.3 I 1 I 2 I 3 I 4 I 6 I OEF I Fll"ld suvey reSIJI:s llldteate closed WlOdow dose rates lmt exceeding 1000 mRemtu expected to contii'I.Je !of more than exoeedtrg 100 ~emlhr expected to conttrue for more than

• 40 bmes OOCM calculated lml one hour, at or teyof"KI the site bot.. o:b ry one h:t1.1, at or beyond the site boundary ** 48 tlfllK OOCM catcUated ~mt OR OR A bnormal Ma!y$1S Of field wvey sarrpes IndiCate thyroid COE of 5000 m:<:em for one hou' of tnhalat:Jon. at or beyond the sne bounda~

Analy&t!l of field 5\XVey sample!lltldtcate thyrOid COE Of 500 mRem for one hol.l of lftlalation, at or beyond the srte

"""""~ ltAl Dani*Oe ~ lffadlale d ~ wt er LOU Ol Wat.. Le ..... ~ HM Of -

IteM In I ' - Unc:-rlrlg 0111 lflldllltiMI f uel OUI$1(1to the l'tNdqf VUMI TabW R*1 A~as Requir ing lnfrequW~t Acc.ss 0 RA2.1 I 1 I 2 I 3 I 4 I 5 I DEF I 0 RU2.1 I 1 I 2 I 3 I 4 5 I OEF I A VALID ala rm or readtllJ on al?( of the followtrg radiat1011 VALl) indlcahonoi i.JI'ICOI'tJ'olled water levellowen llJ In the Monitor reactor rel~ ingcavrty, spent fuel pool, or fuel transl eJ canal Alternate Sht.tdown Panel t;,vsurvey

"""'"~ with a~ irraGated fuel as.5ef'l"bb.es rematf'lirO covered by water Montor Alam'V'Tnp as ndlcated b( any of the followt!"(l Cable SpreadllJ Room Turbine Building (excluding t;,vsurvey b>,'survey

~; ~~~~~=~~ Unexpected Spert Fuel F:w k:Jw water level alarm Vttual ob6ervat101"1 of an uncontrolled water I~ drop A-3 1027 RB WStatrway below a fuel pool sklrtmef st.Xge tarf< Inlet T url:ttne operatii"IQ dec!<) B-2 TG FRONT STANDARD (951') RM*17-452A Reactor Butldlf"9 VenblatiOil ct:teervatJOil of water leakage tnto the Qoywel or the reactor ExhaUSI Pleoom Mootor Ch A B-3COOOENSATE OEM IN OPERATING bulding from piping penetrattonS surrOI.XIdng the drywel RM-17-4528 Reactor Bulldtrg Venblat1011 26mRIIY B-491 1 TURB ELDG MVP ROOM ExhaU'SI Plerun Monrtor Ch B AND RM-17-453AFue! Fool RadlationMonll.orCh A 50 mR/tY Any UNPlANNED VAllO Area Radl3bon Monttor reaclllJ nse B-5FEEOVVATER PlJMP AAEA(911') RM-17*4538 Fuel Pool Radl.!ltton Monitor Ch B 50 mRihr as Indicated I;Jj any of the followtng General Reactor Butldi"tg A-1 1027 RX BLDG LON RANGE A*1 1027 RB NE Low Areas (exdudi~ normally A*2 1027 RB N HrJh A-31027 RXBLOOWSTAIRWAY Hxl<ed hi!tt radar"') A-3 1027 R8WS1atrway A*5 1001 RX BLDG Fl.EL PCX:X.. ROOM RM-17-453A orBfiJe!Pool MonconngSystem A-7985 RX BL.OGCHEM SAMPLE AREA A-8 962 RX EI...OG tofiN OUTSIDE RVvCtJ ROOM o Ru2.2 l 1 I 2 I 3 I 4 I 5 l oe=l Any UNPlANNED VAllO Area Radiation Montbr readirg nses A-9 962 RX EI...OO EAST t'Ja factorof1{l)()overnormal"levels A*10 EAST CR0 MODULE AREA ' Normal leYef5 a m be con$1defed a5 the htghest reading in !he pnt

~four houfsexclvdinglhecurrentpeakvalue A-11 \o\oEST CRD MCX>ULE AREA A-1 2935 RX BlOGNE TIP DRIVE AREA A-14 HPCI TURBINE AREA A-15 896 RX BlDG DRAIN TANK ROOM A*16 RCIC EQUIPMENT AREA A-17 EAST COOE SPRAY & RHR AREA A-18 Vv'EST CORE SPRAY & RHR AREA HU t N~lur~ ..0 0.5lruo;tl.,. PtleflomeN Aff..:t ~ 11M 1'1-PitO TI!CTI:O ..ItEA 0 HA1 .1 I 1 I 2 I 3 I 4 I 6 I DEF I 0 HU1.1 I 1 I 2 I 3 I 4 I 5 I DEF I Se1&mic event GREATER THAN c:,erattng Basi& Earthqua~e Earthqua ~e felt In p!ar( as tneicated by (OBE) as indicated by' Amunctalor OPERATIONAl BASIS Consensus of Cortrol Room operator.;. on d~

EARTHQUAKE (6-C-13) receM!d AND 0 HA1 .2 I 1 I 2 I 3 I 4 I 5 I DEF I 0 Anr'J..trootor EAA1HOJAKE !6-C-08) rect'!Ved HU1.2 I 1 I 2 I 3 I 4 I 5 I OEF I Tornado or hi\1lwinds GREATER "THAN 100 rTV~witt"ln plant PROTECTED AREA boundary and r~ng tn VISIBlE Report b( ~ant persornel d tom.!IO;) or hrJh Winds GREATER DAMAGE to a"i ~nt structt.Xes.l equtpmenl (Table H-1) or THAN 100 mph within piarc PROTECTED AREA boi.X1dary Control Room irtdic::at1011 of degltded petformance d tho6e D HU1.3 I 1 I 2 I 3 I 4 I 5 I OEF I systems. VehiCle Ct"c.t$h 111to piar<< &tn.ICCI..Ke&. or &y$tem& Wllhtn ptar<<

0 HA1 .3 I 1 I 2 I 3 I 4 I 5 I DEF I PROTECTED AREA bOI.Xldary VehiCle crash wrthin p!a r<< PROTECTED AREA t:x>trdary end 0 HU1.4 I 1 I 2 I 3 I 4 I 5 I DEF I resUbng 111 VISIBlE DAM AGE to afli plant s1Juctures01 Report b( ptarc persomel dan ln211"111Ctpated EXPLOSION ecp..lipnert therein (Ta ble H-1) or Control Room lfldic:atJon eX wtti'W'I plant PROTECTED AREA DOI..tldary restJttng In degraded pertormanoe of ti"'I&e systerrtS VISIELE DAMAGE to permanert structt.Xe or equpment None None 0 HA1 .4 I 1 I 2 I 3 I 4 I 5 I DEF I u HU1.6 I 1 I 2 I 3 I 4 I 6 I OEF I Turb ne fa i~Xe-geoerated mts&lles resJI 111 any VISIBLE Report d turbine f&~t.Xe re&ulttng in castng penetratiOn or DAMAGE to or penetration ola"f plant areas (Table H--1) damage to t t.rlline Of generator sea fs 0 HA1 .5 I 1 I 2 I 3 I 4 I 5 I DEF I 0 HU1.5 I 1 I 2 I 3 I 4 I 5 I OEF I Lhcontrolled flooding tn areas (Table H-1) of the plant that Uncontrolled ftoodin;;tln areas (Table H*1) dlhe plant that has re&I.Ats In degraded s.afety system performance as tndicated tn the potential to affect safety related equtpmenl needed for the the conlrol room or that creates trd.Jstrial safety haza rds. (e g , CU'rert oper8lt!ll mooe.

e1ectoc Shock) tNt prech.ldes aocess neoessary to operate or I'T'()flll()r aafety equtpment o Huu l 1 I 2 I 3 I ,. Is j oe=!

~of the following htgl liver le~~el or low river level o HA1 .e I 1 I 2 I 3 I 4 I 5 I DEF I occurrences a!Tecttng the p!art PROTECTED AREA Either d the lolowtng OOCU"en::es Wlthlrt plant PROTECTED River level GREAT ER THAN 918 n~

AREA bOI..f'IOary and re&l#:tng 1n VISI BlE DAMAGE to ~11 Rtver level L ESS THAN 902 4 ei n sti'UC(IJres contatll!"(l eq\llprner1 ~ssa.'Y lor safe Shutdown.

or has caused damage as evte~erad 1:J! Control Room trtdicallOn d deg~ petformance d those S'(Sieml Rrver ~el GREATER THAN 919 It el OR Rtver level LESS ll-IAN 900 5 n el H..U fll'tl! or EXPLOSION .. ffecting the ()pe< ~blllly of 1'1- S.Nty HU1 fllti!'Mihin Pl'tOTECTI!D A !'tEA llound.ory Not Eo:bngul...,_d OMII'IIn SYtttons l'tfQI.Ii"d 10 hldsh or thlnt.,_ S life Shutdown 1SMonul:esoi0.1Ktion 0 HA2.1 I 1 I 2 I 3 I 4 I 5 I DEF I 0 HU2.1 I 1 I 2 I 3 I 4 I 5 I OEJ" I FIRE or EXPL.OSIOI\Itn any ollt'te followtng areas (Table H-1) FtRE tn bU11dti"'Q'S or areas OOf'IIIQI..IOO&IO any Table H-1 area None None not exongu!Shedwrthin 15 rnntJ:e$ cl control room nobficetlon AND or venficallon d a control room alarm Affected system parameter tndlcatJons show degraded performance or plan! pefSO~ report VISIB..E DAMAGE to permanent structt.Xes or equpment w tthin the speeif1ed area HU ll'te tuw C.I To~Ot ...Sf)l'ly.:l.lol'lll, ot Fl.iOTIITIIIbt* GUH o..rn..:l Detriment*ltoNonn~Op..-illl onoltr**l'l-0 HA3.1 I 1 I 2 I 3 I

• I 5 I DEF I 0 HU3.1 I 1 I 2 I 3 I

• I 5 I DEF I Report or detedton of toxiC or a~iar<< gases within or Report or detediOil of IDxc, asptr(Xiant or namrnable gases oortJguous to a VITAL AREA (Table H*1) n concentrattons that that has or could enter the stle area bour'Kiary lf1 amounts that may result 111 an auro~phefe IM MEDIATELY DANGEROUS can affect NORMAl PlANT OPERATIO'\IS None None TO UFE ANO HEALTH (IDI...H) a HU3.2 I 1 I 2 I 3 I 4 I 5 l oe=l 0 HA3.2 I 1 I 2 I 3 I 4 I 5 I DEF I Report t7r' L..ocal, Courty or State Offictal!llor evacuaHon or Report or detectiOn Ofga&e$ 111 concentration GREATER aheltering of srte persomel based on an offsite eveot THAN the Lov.'ER FLA MMABl.ITY U M IT W11h111 or conllgu:JUS to a VITAL AREA (Table H*1)

~11t0STI L I! ACTION l'tiSUIIIng lll LOUOII'ny slut ConlrOI Ollhe HU.f Cootlrm e<l SI!CUI'tiTY CON CliTION Of Tnreal: W!1ICfl tnattiJIK ll

,~.., Pot-iiiOeg<~lnth* L*.,.Ioi S~etyotth* I'IM~t a HG1. 1 I 1 I 2 I 3 I 4 I s I oeF I 0 H$4.1 I 1 I 2 I 3 I 4 I 6 I OEF I 0 HA4.1 I 1 I 2 I 3 I 4 I 5 I DEF I D HU4.1 I 1 I 2 I 3 I 4 I 5 I OEF I A HOSTILE ACTION has occurred such that plant per-some! A HOSTIL E ACTION is OOCU"nrg or has OCCI.Xfed within the A HOSTILE ACTION IS OOCUTI!"(l or ~S oocurred wtthtnlhe A SECURITY CONOIT IQ'\1 thai 00es NOT trrVOIVt! II HOSTILE are u~bioe 10 operate equipment requtred to ma1r1a1n safety Plart PROTECTED AREA as reponed 17,' the Sect.Xtty Shft OMoJER CONTRQLED AREA a s reported 17,' the Secu"fy ACTION as reported bj the SecU1ty SMt S~r IL1rct10ns Supervtsor Stilt Supervisor o HU4.2 I 1 I 2 I 3 I 4 I 5 l oe=l 0 HG1.2 I 1 I 2 I 3 I 4 I 5 I DEF I 0 HA4.2 I 1 I 2 I 3 I 4 I 5 I DEF I A a edible MNGP wciXlty threal notlficatOO A HOSTILE ACTION has caused laitt.Xe of Spert Fuel CoollflQ A validated nottl.cation from NRC cA an awkner allad< th'eat Systems a I'd IMMINEF'ff fuel damage IS likely fora lrestfy off. within 30 m tnlies cA the stte loaded reactor OOI'e tn pool o HU4.3 I 1 I 2 I 3 I 4 I 5 l oe=l A validated notification from NRC prcNidtng trtormatton dan atrcraft threat C*nnot 8e EJiabli$hed a HS2.1 I 1 I 2 I 3 I 4 I 5 I DEF I 0 HA5.1 I 1 I 2 I 3 I 4 I 5 I DEF I None Control room evacuatiOn has been ll"lll.tated None Entry ir1o C 4-C, Sh.Jtdo.vn OJ:stde ltle Cortrot Room, for AND oortrOiroomevacuatJon Control of the plant cannot be establi~hed per C .4..C, StllAdown Qui:Si()e the ContrOl Room, wth1n 10 mint.Aes t-;02 Othef Condltlons EldMtng Which Nllhe Judgment of !he Emlfgency HUOtherCondltlortsE..stlngwtlkhln lhe Judgmentof lhe Em..-genc:y OH-.,;tor w~"""' DKI*OIII<m of U.n..- ill l!m..-tlfi!Cy DH-Mior W*n - 0.<.1....-~ol Slt* Arn Emt<g*n<Y 0 HG2.1 I 1 I 2 I 3 I 4 I 5 I OEF I 0 HS3.1 I 1 I 2 I 3 I 4 I 5 I OEF I 0 HAS.1 I 1 I 2 I 3 I

• I 5 I DEF I 0 HU5.1 I 1 I 2 I 3 I

• I 5 I OEF I Oher cordtt1011s e xist whiCh Wtlhe judgment of the Emergency Other cordllona ex.tSI wt-.ch tn the judgmert eX the Emergency other coOOrhons exiSt which tn the _iudgment of the Efl"lefgenc:y Other conditiOns exist whch in the Judgnert of the Emergency Director indicate that events are tn prooess or have oocured Dtrector todicate that evenls are n p-oc:ess or have occurred Director tndicate ltlat events are In p-ooess or haVe OCCI..fl'ed Dtrector tndicate that evern are in p-ooess or have occurred Vlttich 1rrvoNe actual or trrmtnent ~ubE.t artaal core degadaltOn wtld'l trwotve actual Of kkely map flltkxes of plant fi..OCtlons whiCh 111Yolve actual or ~kely potential substantial degradat1011 whch indicate a potenbal del7lldallon of the le'llel of safety of or melting with potertiat for loss of COrfaJrment lflte!Jily needed for protedkm d the pubic. Any re~ases ere not d the level of safety d the plant An( releases are ele"pected ID the plant No releases of rad'oactive matenal requnng ormte Releases can be renonaljy e

• pected to e xceed EPA expected to res.Ut N1 exp>>Ure levels whiCh exceeo EPA be ~mtled to small fracttoos ol the EPA Protecbve Acbon response or ITIOI'IItori~ are expec:ted I.Xlless fu'ther Protective Action Gudeline e:w;po~ure levefs offsite lor more Protective Acbon Gl.ldeltne exposu-e levels beyond the ~ite GutdeNne expotl,J'e levelt; de!Jadatton d satfe!y &ystetrl$ OO:::UI$

than lhe tmmedate $1!e area

"""""~

0 ~~~ ~~J~s ;nJ~ ~klJJ;&}(£~!~&T 3 BOUNOARY

~l'lhquake None None None To.-radoStrtke Q E U1 .2 I 1 I 2 I 3 I .. I 5 I DEF I Aoctdenlcondittonsaflecttng aloadedcasio; C0 ~'£1.ENT~Y AocidentaiTr*nsfefCas-lr.Orop

~;!mllion in !te !JOO!d! b~n! Olr~Ji.~&Jtes 0

1oM ot lo;tded fuel&b'age QJ$11. CONANEMENT BOUNOARY

I I MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 107 of 120 12.0 FIGURE Annex A-1 Monticello Nuclear Generating Plant Emergency Action Level Matrix (Contd)

Right half of Page 1 of Form 5790-101-02

~ii~iiiiii:iiiiiiiii~ii:i:ii~i! GENERAL EMERGENCY I SITE AREA EMERGENCY I ALERT I UNUSUAL EVENT I M*!<<t:t!+!*!*!o!-,!<<t!t!*!o~

N1 LC4t ofAIOfhlltl"o-tndloH ofNMOniiM AC~to JA$AC l'o_C..,...,. IOttMOlllalllu$MtrM~CHtott.lnglot ..-r .U1lott of. . Ollllllt '"-"to t:....-allunM lorOitlATIII TKAN U l!llswtlll . ._ sourctfafOitL\TI!II TMAJI15ftllldM IUdllhll~ny.a.IOIUI Unglebll.... -*tr-*ln.aallonba.r:~

0 SG11 I 1 I 2 I 3 I I 0 SS1.1 I 1 I 2 I 3 I 0 SAS1 I 1 I 2 I 3 I I 0 SU11 I 1 I 2 I 3 I I Loss of offSite power to Essenllal busses 15 and 16 Loss of otrsite power to Easenbal bus.ses 15 <rod 16. AC power capability to Essert~l busses 15 and 16 reduced to LossofolfSJte power to Essert*al t:xAses 15 and 16for AND AND or1)' one or the follow!OQ SOI.M'ces IOf GREATER THAN 15 GREAT ER THAN 15 mm!J:es Faiure af 11 EmerverJCY Diesel Generator <rod 12 Emeorgency OK!sel rrirUes Fabe of 11 Emergency Diesel Generator and 12 Em~ C)eseJ AND Generator IOsuppfypoweriO Essenlialbus;!es 15 and 16. - 1R transformer, Genemtor to supply IXJWef to Essential busses 15 Wid 16 Essential buS&eS 15 and 16 are powered by thew respectNe AND - 2R transformer AND F1n1u-e to restore I)Oo'ler to at least one Esser1.al bus, 1!5 or 16,

• 1AR transformer Emergen:y Diesel Generators E 1ther of the following (a or b) wrthn 15 mnUes from the !Jrre of loss of both offsrte and - 11 EOG

a. Restorat100 of at least one Essential bus wlhin 4 hou"s onsrte AC power

• 12EDG is.DQlli kely AND OR Ar.f additiOnal s ingle fa ilure Will reSlit in station txackol.t.

b Cont*rung degradatiOn of core cooling based on Fission Product Barner morut.Ofing as indicated by RPV o s53.1 I 1 I 2 I 3 lev~ILESS THAN-126 1n {TAF)

Loss o fal vital OC power based on LESS THAN 1 06 VDC on the 125 VOC ma in distnbt.C:ion busses for GREATER THAN 15ITllrU:es 0

MZP......cltt.e"-~l,.....,.c~.,A-*

SG2.1 1 2 I

.."""-*Cooi..

I<<MitMAI MMu.! k-~1 -NOT...._II'III MIIIft..ll tM--..IIf .. b-~*

I I C..

o N2 , ......." - - ' ............ * ,....., ......_....._ .c-....... t. . . .

s52.1

-~,_._

.._.._~_...._.

I 1 I 2

.... o.... ......... ...-.. .... ......

I

......,W.MOT'-sflll I c IAl:P-...of"'-'kw ......... a,_~----..-c-...

SA2.1

• ~ ...........

.... ._~

I 1 I 2 I

a._ _ ._....

I

.. t--

O.,.e""-',....._.,.........,.._

a An a l..lomattc scram (trip) failed to sN.JtdoWn the reac1or lndlcation(s) exist that automatiC and manual scram were NOT lndicalton(s) eXIst that a Reactor PJO(ectlon System setpoirt AND SI..(:;C;eSS!"U in tedlX:ing p:JWer to LESS THAf'.l 4% was exceeded b lndcation(s) exist that all marual scram actions were not AND successfU in redtclng power to LESS THAN 4% RPS automatic scram didDQlreduce power to lESS THAN 4%

AND A ND c Either of the folow.ng ex1st 01 have ow.xred due to Art{ of the follOWing opera tOI" act100s m soocessfi.A in reducing None continued po.ver generation !XJWer to LESS THAN 4%

• RPV level canrot be restored and maintan--.ed GREATER

• manual scram pusht:Utons THAN OR EQUAl T0*1491n

• mode swrtch to sht.tdown

• l ndication(s) ex1st that heat removal is extremely

• M:ernale Rod lllRrtiOn (ARI) challerJJE!d as indcated "f Torus terf1)eratL.-e and RP-1 pressu-e cannot be mairtained LESS THAN Heat C<IP<~C*tv L1mt (C !>-1200 fig M, SPOS 78)

SUZI~Io~hhqulred~Wit'*'Tectnc.. llpKI!Ic.ellon ln..... IO None o ss.t.1 I 1 I 2 I 3 I Heal capecity LirTIII CI..M! (C.5*1200 fig M and SPOS 78)

I None

~~~*~~~~~~~~~~----L*

0 SU2.1 ~-: 1 I 2 I 3 I Planl is no1 brougtt to req11red operat.ng mode within

"""'""' IAA UMII'LAMMI!OLoss ot*-orMklltr trst-Annundellonor Ted"w'lieal Speciflcat iOI'IS LCO ActiOn Staternert Time lnclc.M6onln C-101111- WMh Dlw 11) e IIOMI'ICAIIIT

.

.-.:~~=.:..or(l)eon.-.,...,~

o sse1 I 1 I 2 I 3 I I 0 SA4.1 I 1 I 2 I 3 I 0 SU3.1 I 1 I 2 I 3 I Loss of most or a ll annuncaators assoc~ated wrth safety Uf\PLANNED loss of most 01 all annullC'ators 01 IndiCators UNPlA~ED loss of most or all ani'U"IC.ators or indicators systems on control room panels COO, C04, C05, C06C, C08 asSOCiated w1th safety systems lor GREATER THAN 15 assooatedwrth safetysystemsfOIGREATER THAN 15 m:ru:es on COI"1r01 room panels C03, C04. COS, C06C, ros, C20, C24 and C259 rTVnl..le s on control room panels C03, a:J4, COS, CXJ6C, <XI6, lAM. I None AND C20, C24 and C259. C20 C24ANDC259 c-SIGNIFK::ANT TRANSIENT in progess AND .UI UIIII"LAIIIMIRI Loss of All OnsiM or OffiiM c-.Nc:Mionl AND E11t~ of the follOWing (a or b)

Compensatory fiOI'WIIIatmng Indications are U"laVai la~e a A SIGNIFICANT TRANSIENT 1$ rn progress 0 SU61 I 1 I 2 I 3 I I OR Loss of all Table C-1 OflSite corrrm..n cations capabll*ty AND affectirg the ability to perform rOOine operatklns b . Comi)Msat<<y non-alaiTT"Iing indications are unavailable.

lndlcaiK>m needed to montor the ability to s.hl.( down the react01, maJntaJnthe core cooled, maintain the react01 coolant 0 SU6.2 I 1 I 2 I 3 I I I system 1ntact, and ma*nta*n conta1nmen1 irtact a re unava ilable Loss of all Table C-2 offstte commt.ncat10ns capability 0 SU4.1 I 1 I 2 I 3 I Oflgas Pretreatrrer1 RadiatiOn Monrtor (RM-17-150A and B)

'""""" None None None hi!11 radia tion alarm (4*A*12) reoeived indicating fuel clad d egradatiOO O SU4.2 I 1 1 2 I 3 )

Coolant sample act*vrty GREATER THAN 0 2 11CiJgm dOSe eqUvalen1 1*131

• u~IIIC* L.-..

0 SU51 I 1 I 2 I 3 I Unident ified or pressure boundary leakage GREATER THAN None None None 10 gprn OSU5.2 I 1 1 2 I 31 Identified leakage GREA TER THAN 25 g:rn None None None 0 SU81 I I 3 I All UNF'l..ANNEO extended posrtive period observed on nuclear instnmematlon

~ FO t.t 0 FS1.1 0 FA1.1 0 F U1.1 Loss of ANY Two Bamers AND L oss 01 Potential Loss of Thnd Loss 01 A:)ter11al Loss of A NY Two Bamers (Table F*1) ANY Loss or ANY Poter1ial Loss of EITHER Fuel Clad OR RCS ANY loss or AN'( Potential Loss ofContaurnent {Table F*1)

Barrler(TableF*1) (TableF*1)

Table F-1 FISSION PRODUCT BARRIER MATRIX NOTES 1 The logiC used for these n ltJatmg condrt100s reflects the folloWing con&lderallons The Fuel Clad Barrier and the RCS Barrier ar e Wi!I!1Jted more heavfy than the Conta llmenl Barner. UE ICs associated wrth RCS and Fuel C lad Barriers are adctessed under System MalflllCtion ICs..

At the Srte Area E~gency level, there must be some ability to dynarrically assess how far present condibons are f rom the threshold for a Gene-ral Emergency For exa~Jl)ie, if Fuel Clad and RCS Barrier "loss' EALs exJsted, that, rn addition to o lfs1te OOse assessmer1s, W(I(Jid reql.ll"e oor11nual assessments of rad10aC!Jve II"M!ntOf)' a nd containment irtegrty. Alternatively, 11 both Fuel Oad and RCS Barrier "P\::Itert1al Loss' EAL.s existed, the Emergency Director wolid haVe more a ssurance that there was ro immedate need to escalate to a General E ~gency.

The ability to escalate to higher eiTIE!fgency classes as an event deteriorates must be maintained. F01 example, RCS leakage steadily ilcreastng woi.Jd represert an increastng fiSk to pubic healltl and safety.

2 F1SstOn Proruct Barner ICs must be capable of address.ng event dyna.ITllcs Thus, ltle EAL Reference Table F* l states that itm11nert (i e., with1n 2 hoi.Xs) Loss 01 PotentJa l Loss stoUid result in a clasSification as if the affected threshold(s) are a lready exceeded, partiCIJaft)' for the ~r emergency classes Fuel Cladding Barrier Reactor Coolant System Barrier Primary Containment Barrier 0 Loss 0 Potential Loss 0 Loss 0 Potential Loss 0 Loss 0 Potential Loss

1. f?t1!J\'W P>olg!QI Acc!IYrty I ftYf'l f?t!marv CooJaru ActiYY l cvet 0 1. ~ 0 1.~

" '~ 0 1~

0 0 1 Coolant Activity GREATE R THAN Not Awlicable Ofywell Pressure GRE ATER THAN Not Applicable Rapid uoexplained decre ase n Orywell Pressure 56 PSIG and 300 11Cilgm 1*131 dose equivalent 1 84 ps~g NOT caiJSed by a loss of ctrywell presSU"e fOllowing irwt.al IncreaSing ON Cooling OR OR GREATERTHANOREOUAL TO Orywen pressae response not 6% hydrogen and GREATER THAN consiStent Wllh LOCA. ooodl10ns OR EQUAL TO 5% oxygen in

• nQcat*ng conta1rmen1 breach Orywell Of TOfUS 0 2. Reactor \'esse! Water t eye! 0 2. Reactor Vessel Water eye! l 0 2. Reactor Vessel water Level jcoi22JR~e~act~n~ry~e~,..;;jiiM!~t;;;er:i;tfYf~l- -t<0,.-;2;:-.R~e~*~~Q[~V~e~....

~wo;>ti<i<<LLOieve!iOj~~ 0 2. RejtCt()[ V essel water Leyel Level L ESS THAN *149 in Level LESS THAN *126 in (TAF) Level LESS THAN

• 126 in. {TAF) Not AppliCable Not Applicable Pmnary contaiYnent flooding reqUred Fission Product (MSCR'M.)

0 3~ a 3. ~ o 3 (;NMT IM'MIOO Ea1'~ rt or e.tpass o 3 CNMT hiQill'loo f:@c or fttpasa Urnolable Main Steamline Break as RCS leakage GREATER THAN 50 FaillJ"eofbolhvatves in art(one l1ne Not Applicable M""ldrcated by the faiiLK~ of both !PTl inside aywe* to close ANO<bwnstream pathway f-- - - - - - - - -- -

MSIVs in a ny one hne to close ANO OR to the ertv'Jrormert extsts EITHER Un solable pnmary system leakage OR High MSL flow or h9"1 steam outside ctrywell as indicated "f lr1eo!lonal Primary containment tlJ1ne-l temperatlle ann.Jnciators Any Secondary Conlairrnent area venting r1 progess per EOPs OR lemperalllre GREATER THAN ma;.r OR Oned repor1 of steam release normal (C > 1300Tat>le W)

OR Unlsolable pomary system leakage ANI Secondary Cor1arrv nen1 outside ~I as ind1eated hV area radiation GREATER THAN A"'! Secondary oonta~rrnent a rea max normal (C5*1300 Table X) temperatlJ'e GREATER T HAN max safe (C.5-1300 Table W)

OR A"'! Secondary oonta~rment a rea radiationGREATERTHAN max safe (C.S..1300TableX) 0 3. prvwe!! Racyttoo Mgortgnoo }-;c<JJJ3!!lriwr!:§'~'R~od!a§'non>il!r!M.2ioo!iltorl!iirnw-J o 4 Dryyu:nRamaroo Mgmtorm Cont:a1rmer1 H1!1J Range Bad I'" NQc Applicable Conta1nmen1 High Range Rad morwtor reading GREATER T HAN monitor reading GREATER THAN 1.5E3Rihr 65R!IY 0 4. ~ 04~ 0 5.~ 0 5~

Not AppliCable No!Appl>oable Not .Appicable NotAJ.1)11Cabie 0 6 Emergency Director JtJdcrmeot a 5. Emergency Q!res;tor tuooment 0 6. frnergeooy P,recror **dQmert 0 6. Emergency Director hmment a 6 Emergency O.rea.x ' trirr'r!ftrf o 6 Ememeocy Djrect9f ll!l!Jmell Art( condibon 11'"1 the opfliOn of the An( condioon 1n the op~nion of the Ally condrt10n in the op1Aon of the Any conditiOn in ltle opnon of the A~ condition in the opinion of the An( conditKJn in t he opn100 of the Emergency Director that inQcates Emergency Director that indicates Emergency Director that 100cates Emergency Director that indiCates Emergency Director that indiCates Emergency OirectOf that indicat es l oss or Potential Loss of the Fuel l oss 01 Potential l oss of the Fuel Loss or Polent~al Loss of lhe RCS Loss or Potenlial Loss of t he RCS Loss or Poter1~1 Loss of the Loss o r Potenlial Loss of the C~Barner C lad Barrier Ba rr~r Barner COnta1nmeot Barrier Conlainment Barrier Tabl* H*1 EAL Class ification A r* as T.,._ C-1 Ons. . Corrmuntca~tloM Sysi!Mns Reactor Bldg Comnerc1allelephones HR:! Bldg Plari: telephOnes Tubne- Bidg Portable ra dios Conlrol & AdiTllniStratiOI'l Bldg Plart page system 0.~ Generator Bldg 0.~ Fuel 011 Transfer House EFT Bldg Tallie C-2 Ol'htte Conwnuntc.tloM Systems l ntake Stru:t.ure Corrrnercial telephones 1

Security Blilding FTS Phone System 1  !

Secunty D.esel Generator Buld1ng Radio Rece*vefiTransmtter

~

Nai*I: TMHbuildings . . cnlyODrnoderedwhen cllost/tftl9peo-MU2.t . HAl.tend~2 *~

Modes 1, 2, 3 ~

MONTICELLO NUCLEAR GENERATING PLANT 5790-101-02

~ EMERGENCY ACTION LEVEL MATRIX Revisio n 10 Modes: IT] [TI [TI L!J [!] I DEF I Page 1 of2 Power Operation Startup Hot ShutdOIMI Cold Shutdown R~fueling Defueled Approval: ~

I I MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 108 of 120 12.0 FIGURE Annex A-1 Monticello Nuclear Generating Plant Emergency Action Level Matrix (Contd)

Left half of Page 2 of Form 5790-101-02

~:~:~:~:~:~:~:~~:~~:~:~:~:!

~::::::::::::::::::::::::::::::::~

GENERAL EMERGENCY I SITE AREA EMERGENCY I ALERT I UNUSUAL EVENT I 11:0 1 Offsltt Don ltKUIIIng from.-. Ac!Ua!CM' lmminenll lt...iiW ot Oll'sltt Oose ~HUlling *om in ActUIII Of """**- ~ti tHe of

!.~.:~~~:=~~s:.=~==:~-:.~~~~r. ~U1 :n~~~':!:.~=~~=~:.=.~~!:~=!~:

~ 11 c;.,....,. lt..:lo.clhtly beNds 1000 mlllom TI!DI! or 54100 mltwn G KI'OUS lbdlo~lvlly EXCM<I'i 100 ml f - T1!.01: Of ~mit'"' AA1 lhyroldCDe:fort,.Actv*or Pro)M:tf<l Owllllon oi i:M ~MM Thrl"old Cot! lo< lh* Ac:tU'III Of Plojld..:l O..Mionoftht ~* - 1111.-.uiii LimllfO<Uflllinii"Of Long.r Ill__,. Umll for flO lllinuln Of Longer UsklgAciWIMIIIOfOio.gy fiQte* lf doMH~I~iillll! ~*~bjoe *tt~eiJmeof Note- lfOow*-rnenl tet<.~bilre*v*Q,~ at the timed a RA1.1 I 1 I 2 I 3 I 4 I 5 I DEF I a RU1 .1 I 1 I 2 I 3 I 4 I 5 I oeF I

<ieeli1r;Jlon,ltlecl*~*tlon~ld be bil~onRG12~~r;J Qecfilflllbon.ltle ci"Wbt1011 ~ld be bneQ onR$12 i~d VAUD reading on a"¥ etf!uert montor that exceeds 200 times VALID reading on artt effluent moN!or tturt e Kceeds two limes RG1 1 V'.tlilenecnNry dedarabonsshouldnotbe~yed.-rting RS1 1 'M'nle necftNJY Oeclwlltion$ thJukl no1 be Oel1ye<;l I"'Mtiting r~lta,thecknoeas~-.houldbe n rtL;oted/00<11lletedrn Qfclec raulta, the dOM n~ 5houkl be irutiil;ile<l/ eompleWd in ordef the alarm selpolnt establiShed by a currert radioact~i ty the alarm setpo1rt establ~ ~ a w rent radioactiVIty

!Qd~rni,.,.if tn*clns.ificll:.on~ldbew~~:,~..,~ W detemroe li the c~ifieaOon thoukl be ~uently~l*ted chcharge perrnit for 15 min.Jtesor loogef discharge permit f or 60 minl.tes or larger a Rau l 1 I 2 I 3 I .- Is ! oeF! Q RS1.1 I 1 I 2 I 3 I 4 I 5 I DEF I VALID reading on af'¥ cA tnelollo.vtng rad.aUon rmnitors that VALI Oreacllngon any olthe folk:PN.ng rad.abon morMtors lhat 0 RA1.2 I 1 I 2 I 3 I 4 I 5 I DEF I 0 RU1.2 I 1 I 2 I 3 I 4 I 5 I OEF I exceed&orisexpectedto eiCceedthe readirg shown for 15 exceeds o r IS expected to exoeed the reading shown for 15 VAUD readir-G on anv o1 the folowng rad1a11on montors that VALID reading on artt of the follow1rg radiaHon montors that mtru~es or torger mlluesork:w'1Qer excee<~s the re ad1ng Shown for 15mrues. Of lOnger e)(~ the reading Shown fOf 60 ITllf'llAes. or k>nger Monitor GE Mon1tor SAE M ontor Alert Monitor UE

~ ~

Stack Emuent Mor11tor 2 .1e9 ~cnec Stack Emuent Monrtor (ChAorB) (CtlAor8) 21E81-1Ctl!ec

~uentMoN!or 146E7 }ICilse<:' ~uent Monitor 7 3E5 J.1C ilsec RB Vert Eftluern Morvtor 1.5E8 ...Qisec RB VertEffiuent Monrtor 1.5E7 "Qisec (ChAOf"B) (ChAorB)

~llelt.-1 (ChAorB) (CtlAorS) RB Vel1 Etnuel1 MoMor 2 16E6 }ICilse<: RB Vert Emuent Monitor 2. 16E 4 "CWec c-~ l.JOi.jg (ChAOfB) (ChAorB)

LW<I Serv~ceWater NIA Service Water NIA I..I!Wl<l J.iOl.lg Oscharge cared Monrtor NIA Dtsctlarge Canal Monitor NIA ~ce~ec 31400cps. SeMce- Water 314 cps TBNWS NIA TBNWS NIA Discharge canal Mol"lltor 93 000 cps. O.Charge canal Monitor 930 CfJ5 T BM\'5 900 000 cpm TBN'M5 37 752 cpm a RG1 .2 I 1 I 2 I 3 I " I s I DEF I 0 RS12I 1 I 2 I 3 I 4 I 5 IDEF I

[)ose a ssessmen~ using actual meteorolOgy tndlcates doses Dose as.sessmert uSIIll actUSII meteorOlogy indicates do6es 0 RA1.3 I 1 I 2 I 3 I 4 I 5 I DEF I 0 RU1 3 I 1 I 2 I 3 I 4 I 5 I OEF I GREATER THAN 1000 rrRem TEDE or 50Xl rrfiem thyroid GREATER THAN 100 mRem T EOE or 500 rrRem thyi'Oid CCE Confirmed sample ana~Sis for gaseous o r liQuid release Corilrmed sall"f.'leanalysis ror gaseous or liquid release CDE at or beyond the s~e boundal)' at or beyond the s1te bolndary indicates coooertrallons Of release rates, With a release Kldicates ooooertratJont or re~se rates, with a release clrratklnof 60 mirJJtesor longer, in excess ol two limes a:x;M I I I I I I OEF I RSU I I I I I IDEF I W"at10nol15 rnm.i:E'$ or longef, lll e Kcess ol200hmes OOCM

J RG1 ,3 1 2 3 4 5 0 1 2 3 4 5 Field survey resUts indicate clo11ed W1ndow dose rat es e><oeedng 1000 rrRem'tw expected to oort1nue fOf more than Field Sl.f\leY results indicate dosed v.indow <Dose rates exceeding 100 rrRem'tw expected to oont1nue fOf 1'1"10fe than one hotx, at or beyond the site boundary one hour, at or beyond the s1te boundary * -40 bmes CXX:M calcuiated limt OR OR ** 48 tfnes OOCM calcUated ~ml AnalySis of field Sl.f\leY saf1l)le& indicate thyrOid ca::: oi501Xl Are~ o f neld 5\IVeY sarrl)les Indicate tt.,.rotd COE ot 500 mRem for one hou- ol inhalation, Bl o r beyond the srte mRem for one hou of 1nhala!J011 at Of beyond tre Site Abnormal Releilse

""""""' tx>undo'Y Effluen1 ltA2 o.n.g. toh..tllllltd~utlor Lon atW~* L.wollhliiiHii* Of Wll

~-=: In m.Uncovll1ng oflrndllllltoel ~ut>l Outsldt m. ~nctOf 0 RA2.1 I 1 I 2 I 3 I 4 I 5 I DEF I 0 RU21 I 1 I 2 I 3 I 4 I 5 I DEF I A VALID alarm Of reading on any d the foiiCPNJng rad~anon VALID ln<icationof l.riCOOi rolledwater level lowec*ng n the tTIOilltors reactor refue~r"G cavrty, spent fuel pool, o r fue! transfer canal With atllffill<iated fuel a ssemblies rema1nir"9 covered t1)' wateJ Morutor AlarnvTrip as *ndicate<li)jarrydthefOIIo<ooflnQ A:~ ~~;~=~~~ Unexpected Spert Fuel Pool ION water level alarm V~ OO&ervat10n of an unoontrofled water level drop A-3 1f127 RBW SI:a11Way 100"""" belOW a fuel pool s.ltinYner wge tank lf"llet RM-17-452A Reactor Buld*fll VertJ.Iabon 26m""'

• Observation of water leakage 11110 the liywell 01 the reactor Exhaust P leru-n Mor"litOf 0"1 A building from PIPII'Q penetrations surOUndlf'IQ the ciyweM R M-17 -4528 Reactor Build*ng Verttlabon Exhaust Pleru-n MonitOf 0"1 B AND RM-H -453A Fuel Pool RadiatiOn MontorCh A 50 mRihr Artt UNPLANNED VALID Area RadiatiOn Morrtor reading rise RM*17-4538Fuel Pool Rad1at10n Mon-torChB 50 mR.hv asindicated~ af¥ olthe f011owtng A- 1 1027 R8NELo.v A*21027 RBN HIQh None None

• A.J 1027 RBWStairway

• RM-17-453Aor BWPootMonrtoringSystem a RU2.2 ( 1 I 2 I 3 I 4 I 5 loeFI Artt UNPLANNED VALID Area RadiatiOn Morttof reading nses t:y a f.actor oi1000(J<Ier normal* le'llels

" lolormallevMe*nbeeon~e<lutt.l"llghnt rNdirlgintMp.5t twenly-lour hou~e-.;eb;:l*ngtheeunent pco*k v~

HU1 NOIIurol - O.~lru~tln Pllotnomtn~ AII"K bng 11"1* Plonl PlfOTECTEOA~EA.

a HA 1.1 I 1 I 2 I 3 I 4 I 5 I oeF I a HU1 .1 I 1 I 2 I 3 I 4 I 5 I oeF I SeiSmiC evert GREATER THAN Operat1ng BaSIS Earthquake Earthquake lett 11'1 ptant as indicated t:¥ (OBE) as indicated ~ ANUlCialor OPERAT IONAL BASIS Consensus of Control Room operators on duty EARTHOJAKE (6.C.13) rteeiYed AND a HA 1.2 I 1 I 2 I 3 I 4 I 5 I DEF I a HU1.2 AnrlJoclator EARTHQUAKE {6-C-081 receiVed I 1 I 2 I 3 I 4 I 5 I oeF I Tornado or t41 wnd& GREATER THA/11100 l"fl)h Wll.hn plant PROTECTED AREA boundary and resiA*fl!n VISIBlE Report t1)' ~rt persomel of tornado or hig'l Wlrdi. GREATER DAMAGE to any plant structaes leq.Jpmeflt (Table H-1)or THAN 100 mph Wlthlll plart PROTECTED AREA boun:tary Control Room *f'!Ckatoo of degraded perlormance ol th06e a Hut.3 I 1 I 2 I 3 I 4 I 5 I oeF I systems VetiiCie crash ll'llo pant stn.dtxes or system& within pl3nt 0 HA1.3 I 1 I 2 I 3 I 4 I 5 I DEF I PROTECTED AREA boundary Vehicle CBSh Wilhlfl plart PROTECTED AREA boundary and a HU1 .4 I 1 I 2 I 3 I

• I 5 I oeF I resulting 11 VISIBLE DAMAGE to Btl( part struciUres o r Re port b'f' part personnel Ofan um rt1C1paled EXA..OSIOI">>

eqi.JII)ffiel"'l ther~n (Table H*1) orCortrOI Room indication of Within plant PROTECTED AREA boundary rewltng 1n degraded pedorrna rce of those systems VISIBLE DAMAGE topermanentstn.dtXe Of eq.Jpnert None None 0 HA1.4 I 1 I 2 I 3 I 4 I 5 I DEF I 0 HU1 .5 I 1 ( 2 I 3 I 4 I 5 I OEF I Tu-tline failure-generated rnsSJies reS\Jllll any VIS IBLE Report oft..-blne fa ilure reSIAI:*r"G 1n C3Sing penelratoo or DAMAGE to or penetratiOn a al'fr' plart areas (Table H-1) da1T\21ge to tne or generator seals a HAu I 1 I 2 I 3 I 4 I 5 I DEF I a HU1 .s I 1 I 2 I 3 I 4 I 5 I oeF I Uooortroled IIOodrlQ in areas (Table H-1) or me p4art that l)ncor(rolle<l H()()(jirg in areas (Tabte H ~)of the p~Mtthat h&'S results n degaded safety system performance a s 1nckated 111 the potential to affect safety r~ated ecp.~pment needed lor 1t1e the oortrol room or that creates.ltiC1JstriaJ safety hazards (e g, ctXrert operatii"IQ fOOde elecbic 1-hock) lhat precludes access necessary to operate or tTIOnrtor safety eQUipment 0 HU1.7 I 1 I 2 I 3 I 4 I 5 I OEF I a HA1.s I 1 I 2 I 3 I 4 I 5 I DEFI A"'J of the fOIIOwlf"lQ high rive r level or bw nver level ooconerw:::es affecting the plait PROTECTED AREA Eithef Of the followlllQ OOCU"eoces w1thm pla rt PROTECTED Rwer level GREATER THAN 918ft el AREA boundary and resullfll in VISIB..E DAMAGE to part

• RJYer level LESS THAN 902.4 ft el strl.du"es oon1a m1ng ec,.Jipnerl necessary for safe sht.tOOwn, or has caused damage~ eVIdence<!~ Corcrol Room indicatJOil Ofdegaded performance ol those systems Rrver leveiGREATERTHAN919rtel OR Rrver ~ LESS THAN 900 5 tt el t1A2 ,I~[ Of U ,LOSIOH -'!Mcllng tllot 0p<<<<Millyol fl'lar<< hlery HU2 Fl~f Withln , ~OTtC TEOA~EA 8oundilf)' Hot h llngo.ts lltd Wllllln

~" 'M$1f*q..>~* ..t*o h* ~bll$111)0 *~"~' s...r, Shuldo- 1 ~MN.... uor O.I* ( IIOh 0 HA2.1 I 1 I 2 I 3 I 4 I 5 I DEF I a HU2.1 I 1 I 2 I 3 I 4 I 5 I oeF I

~"* Of FIRE or EXPlOSION in &f¥ ol the f olowlng areas (Table H -1) FIRE in buildings or areas cont9Jous to Btl( Table H-1 area Explosion None None not extirrgUished within 15 mnutes of cortrol room notifiCation AND or ver*fica t*on of 11 control room alarm.

Affected syst em pa ra meteJ 1ndicabons show degraded perf()fi"Tl;,noe or planl per$01lnel report VISIBLE DAMAGE to permanent sltuctures Of eqUipmert w.ttun the speafied area

os. n,rnm..,.

t~Ef~~i~~~~~i~~::'Fi~::~~:

HUl lt.... 01 ToKit . A~pi>Jr-.;lanl . or Ga w~ OM~~>~td Oeulmentolto HOfmol ~1atlon ofi:M 1'1-0 HA3.1 I 1 I 2 I 3 I 4 I 5 I DEF I 0 HU3.1 I 1 ( 2 I 3 I 4 I 5 I DEF I Report <X detectoo or tOl<IC Of &~1art gases within <X Report or detecoon Of tox.c, a~lart Of flammable gases contrguous to a V tTALAREA(Ta blf! H-1) 111 concentratiOOS tturt that has 01 could e rteJ the Site area boun:tary m amourts that may result in an atmosphere IMMEDIA TELY DANGEROUS can affect ~ M AL PI....ANT Cf>ERATION$

None None TO LIFE AND HEAL TH (IOI...H)

!J HU3.2 I 1 I 2 I 3 I 4 I 5 IDEFI 0 HA3.2 I 1 I 2 I 3 I 4 I 5 I DEF I Report b'f' Loca~ Courty or state OffiCials for evacuaton or Report or detectiCIII Of gases 1n ooooertrahon GREAT ER shenering cl site persomel b8sed on a n offSite evert THJV.J the LONER FLAMMABILITY LIMIT Wll.hn or oont9UOU6 to a VITAL AREA (Table H.1)

HG1 HO$llLE AC"nOH ~.suR~ kl Loss of ,..,vsk~ CorMrol oflht HM HOSTILE AC"nOH Wn.hkl tlw OWHE~ CONT~OL LEOA~EA or Hu.t Coniii!Md SECU~I TY COHOi llON or TIY*a~ Whkll lndlu t .s a

~a.::lllly. Alfi:>Ofl~ An~k ThtUI Pol.!llla!DI>grad.iltiOnlnm* UvMOI ~I..yorln* PIJMII:.

0 HG1 .1 I 1 I 2 I 3 I 4 I 5 I DEF I 0 HSC.1 I 1 I 2 I 3 I 4 I 5 I DEF I 0 HA4.1 I 1 I 2 I 3 I 4 I 5 I DEF I !J HU4.1 I 1 I 2 I 3 I 4 I 5 I OEF I A HOSTILE ACTION has occwed wch tMt ~rt pef6()f"t)tl A HOSTILE ACTION IS OCCU"nng Of hn OC(;Urred Within the A HOSTILE ACTION IS occurring or has OCCU"red Within the A SEClRITY CONDtTION that does NOT lnvot.le a HOSTl.E are ...nable to operate eq ..11pment reqUired to ma11"U1n safety Plant PROTECTED AREA as reported t1r' the Security Shin CNVNER CONTRO..LEO AREA as reported t1y' the Secu rity ACTIOO ~reported bV the SectXily Shift SUpervisor f\Jnctions S~ISOr Shift Supervisor a HU4.2 ( 1 I 2 I 3 I 4 I 5 loeFI

I HG1 .2 I 1 I 2 I 3 I 4 I 5 I DEF I 0 HA4.21 1 I 2 I 3 I 4 I 5 I DEFI A cre<lble MNGP sectxty threat notification A HOSTILE ACTION has caused fa1I1Xe of Spent Fuel Cooi!Og A validated not1flca tion from NRC Of an a r11ner attack threat

&{st em& and IMM INENT fuel damage IS blolely for a ffes.hly 01'1* Wltl'lln 30 m.ntAes o1 the srte loadedreactorcoreinpool 0 HU4.3 I 1 I 2 I 3 I 4 I 5 IDEFI A validated notJficat*on from NRC pr()llfl()rg informaoon Of an a*rcraftthreat I I I I I I DEF I

..... I I I I I DEF I 0 HS2.1 1 2 3 4 5 0 HA5.1 I 1 2 3 4 5 con1101 None Cortrol room evacuatiOn has been Initiated None Entry into C 4-C Stn.t<Xlwn Ot.cside the Cortrol Room, lor AND oonuOI room e¥acoatoo Cortrol of the plart cannot be establi!.hed per C .4-C Sh.Jtdown o.tside the Cort¥01 Room, w ~hn 10 ITllni.Aes HG201tt.Condltlons E~ lsllng Which l nlhl~ ofl llot Emergency H$3 Olher Condlllons Eldstlng wtokh 1r1 tllot Judgmenl of lh* Emtrgenc:y DI,.<.!Of W** - O.C I~*~tlon ofG-ral EmlfQIOn<v Dlr.,;tOf Warronl o.d*OIIkm or Sll* Afu £merg"""~

I HG2.1 I 1 I 2 I 3 I 4 I 5 I OEF I 0 HS3.1 I 1 I 2 I 3 I 4 I 5 I OEF I 0 HAe.1 I 1 I 2 I 3 I 4 I 5 I DEF I a HU5.1 I 1 I 2 I 3 I 4 I 5 I oeF I ether conditions exiSt which 111 the JI.Dgnent a the Emergency Other cond1I1011S exist ......nch in the judgment of the Emergency Olher coo01Jons exrst ¥otiich 1n the~ ol the Emergef"ICY Othel oondltons e:..ISt which 1n the~ o f the Emergency Diredof indicat e that events are in process or have occurred Director indicate that evt!nts are 1n process o r have occured Director 1ndicate that events are m p-ooess or have ooourred Director 1n<1cate that~ a re m p-ocess or have OOC!.fled which involve l!tCtual or irTmlnert s\bstartJal core degad211boo which 1nvotve actual or ~kefy m!IJOf fa1k.fes of pant !Uf""d:10ns which Involve actua l or likely potential SJ.bstartial degradation whiCh indicate a potential degadatiCIII of the level of safety c1 or melting Wllh pot ential for loss ot conta1nmert integrity needed for prorectJOil o f the pWIIC Any releases are oot ol the ~of safety of the plant My releases are expected to the pant No re ~ases ol radioactiVe matena1 recp.~rlllQ oti"Site Releases can be reasonably expected to exceed EPA expected to rest.it 111 exposure ~els whiCh exceed E PA be ~miled t o small fractiOnS of the E P A Protective .1\ction response or morltonrg are expected unless futher Pro tectr.te Ac1JOI1 Guideline exposu-e levels offsite f or more Protective Acllon Gudel1ne exposu-e levefs beyond the srte GJ!del*ne exposiSe ~Is degradatiOn o1 safety sys:cems. OCCIXS than the immediate ~te area tx>undo'Y None None None

I I MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 109 of 120 12.0 FIGURE Annex A-1 Monticello Nuclear Generating Plant Emergency Action Level Matrix (Contd)

Right half of Page 2 of Form 5790-101-02

!llllllllllllllllllllllllllllllll~ GENERAL EMERGENCY I SITE AREA EMERGENCY I ALERT I UNUSUAL EVENT I

!*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*!

~

0 CA 3.1 I I

_. I CA3 L-ti AI Otfsb~ lfiCILOMoi .U elftth AC~-~o I 4 I 5 I OEF I CUS L-a eu;.~*~..

of A.II Oiftll* ~ to ! ....,. . .... for OII!ATP: TMAll I

• I sI I -

Loss d oft'..s.te poNer 1o Essential busses 15 and 16 loss of oft-lite power to Essential bus.so&S 15and 16 for GREATER A ND ~ 15 mn.rtes Faii!Je d 11 Ernergeooy Diesel GeneraiOf and 12 Emergency AND Diesel Generator to supply poNer 1o EsSoefltlal busses 15 and Alleastooe Euential bua, 15or 16, ispa.yered t,.. its 16

....... emergency <le6t'l generator AND None None Faii!Je to restore power to at leas.! one Es.sertaal bus, 1501" 16, CU7 UJIIOI,.ANNI:D Lon of ~ DC'"-' for QIIIATI:II TMAN U wrthln 15 m.-.u:es from the time ollossof both offslte and onsite AC power 0 CU7.1 I I 4 I s I I UNPLANNED loU 01 '<rita! DC pcmtr to ~ured 125 VDC bu~S ba$ed on LESS THAN 111 VOC bus wltaQe ndicatx:m.

A ND Fatl<.re to restore powe r t o a t least one reqllred 125 VDC bus wlth1n 15 rnrutes from the tune of loss C01 LOf.* of ffi'Y I-ory A~PVII Ciid .......-v .....

C~Ctl. . . . . . . . . ln-.... MIIP\Itt ln . . II:N

[I

J CG1.1 ::;:c=:~=:ID*:::I I J*DI=:: J 0 CS11 I I 4 I 0 CA1 1 I 4 I I 1 Los:& of RPV II'!Vertory as indicated by une>epiane<:l rise lf'l W th Secondary Coruirmerc ll!:t establl$hed LOB& of RCS invertory as tndicated bof RPV level LESS THAN dryweg floor Of e~pnert d ran SUrfl> tevet a RPV i1Yellloty as indicated by RPV le~ LESS THAN -53 in -47 11'1 A ND OR

2. RPV Level b. RPv level carnot be monnored for GREATER THAN 30 0 CA 1.2 I I 4 I I a LESS TKAN-126 1!'1. (T~)forGREATERTHAN 30 mlnuteswlflamof RPV In~eniOI')' as Indica-ted b)' elttler LOS$ ol RCS invenlory as lf"l(lcated bof U""lt'XPained \eVeol rise in mnct~

• Unexpau"led level nse lf'l dryWell ftOOf or eqUipment drywelt noor or eq..11pmert draun sumps.

OR dransufll)& A ND

b. camot be montored with lnc:l lcation d core ...-.covery for Erraoc Source Range Montor lndlcatiOI'I.

RCS level cannot be monitored for GREATER THAN 15 GREATER THAN 30 rYln\Aes as evidenced by l!lf¥ of the 0 C S1 .2 I I I I 4 I I mrues.

fOllOw!~ W th Secondary cortanmert e&U~bli&hed

• Errabc Sou-oe Rarge Mon1or irdcatoon a RPV l"'vento.-y as indiCiteel by RPV le~ LESS THAN -126 10.

• Refueling:Roorradia\Jonle... GREATERTHAN3 R.tlr (TAF)

A ND OR 3 . lnd1C8t101'1 of CONTAINMENT challenged as inclcated by b RPol level (;tl n ~bemoniiOfl)dforGREATE RTHAN30 any of lhe follow\rg minutes'Mtl a los.sofRPVirrterttol)o asindicatedt)'Jeittler GREATER THAN OR EQUAL TO 6% hydrogen and - Urlexplamed level nse .n drywell nOOf or eQUipment GREATER THAN OR EQUAL TO 5% oxygen in pnmary d t8rl$Urfl)$

corta inmert Errabc Source Range MoMor lndicat10r1 Dtywe* pressu-e above 56 p&ig CSZLGM fll ffiiY~.......,.~C..O.., ItMI ...._..~ C Ul ~IO a...fti~ I......_, _,,,..,.... , ...... .IIPY Itt._..Fwl .. . . ffiiY Secondary oont~nment rot established T wo or more Rea ctor 8J1kling a reas exceed Max Safe Ra<iatJon Levels (C 5*1300, Table X) o cs2.t [I::;r;:=;:~:::::::.c:::~!;*gi;::::J W lh Secondary Cortairmert J!l1 establiShed 0 CA2.1 .~~:;:r:=;:~:::::r:::::::r1~sg1;:J Loss ot RPV ~ventory a s indicated by R PV level LESS a cu2.1 1c.:;:~;;:::I::I=II:::*o1:;~

UNPLANNED RCS level lOwering below the RPv Range ror a RPV i'IYOO!ory as indicated by RPV le~ LESS THAN -53 in. THAN -47 in GREATER THAN OR EOJAL TO 15 rlllnl.les OR b RPV level cai'I'IOI be morutOI'ed wJth lrdicatiOI'I of core 0 CA22 I I 5 I I 0 CU2.2 I[ =r==:~=I=II:::*0 1=]

~"~~b'larry-d thefOIIOWirg Loss Of RPV invertory as indicated t:lV unexp11!11ned level nse 11'1 Loss o f RPV Inventory as llldcated by u nexplauned level nse ll dryweu floor or eq.11pmen1 dra1n sumps. d rywell noor or equpment ch*n s.umps

• ErratiC Source Range Monitor IOdicahon.

• Rt!'uelng FIOorraa.atton levet3 GREATER THAN 3 Rlhr. A ND AND Cold SCI I I I l s i I RPV level camot be moritored fa GREATER THAN 15 o c s2.2 1 R PV level ca nnot te montored mn..tes W th Seoondary Coi'UII'IITiert e&IKI!Ist\ed

""'"""- a RPVnventoryasindicaled by RP\t' le~ LESS THAN -125 in.

(TAF)

OR b RPV level cai'I'IOI be morutore-d with lrdcat1011 of core

~ ItS t'VIdeoced b'/ 8rry' d the fOII()Mrg

- ErratiC Soul"ce Range MonilOI' .ndicatlon

• Reluei(Jg Fklorr&diation 11!1..-e!s GREATER THAN 3 RJtn .

.._.doNI 0

eM lnllbllly 10 * ..,.... ,.... In Cold CA...1 I I 4 I 5 wftl lrr . ..... , .... In I 0 Ctw '*"LANNeD Lon ofO.C., HMIIIII-CU4 1

'""I-"'h!lo""' I 4 I

¥1111Capibltly . .hlll. . .tod 5 I I W.th SecondaJY Conta irmen. and RCS 1rtegr1ty ~ An UNPLANNED evert reslAts 1n RCS temperature exceeding established an UNPLANNED evert results lf1 RCS temperatU"e 212degees F exceedii'IQ 212 degrees F 0 CU4 2 I I 4 I 5 I I

'Note. U on RCS ~'~.eat rfo!TI(W.ol *"Y5tem ** in operatiOtl...ch*n th;. time- Loss dan RCS temperatiSe and RPV level indlcat()n fOf frame ondRCS~ r.. ,.~ing rll'd~~tn.. EAL 11' not GREATER Tl-iAN 15 mn..tes appk:Clle No ne None O CA4.2 j j 4 l s j W.th Secondary Contair"meft estati1s hed fiLl! RCS ntegnty Qat esta til&hed Of RCS inverltory rec:I!Xled an UNPLANNED evert results in RCS teJ'I'l)eratiJe exoeed1~ 212 oegrees F lor GREATER TKAN 20 rT'InUte&'

a CA4 .3 [I::::~;:=:~=:IO*;:J:IJ*OI=]

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D.esel Fuel 0.1 Transter House B-3CONOENSATE OEM IN OPERATif'o.G ERBidg T* IM C.2 Ofbttll ComnunigUons Systenw; B---4 91 1 TURB BL0G MVP ROOM Intake Structure Corrrnerc~a l telephones B-5 FEECY.'ATER PUMP AREA (911')

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MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 110 of 120 13.0 FIGURES Figure 13.1 MONTICELLO PLANT EMERGENCY ORGANIZATION EMERGENCY DIRECTOR SHIFT EMERGENCY COMMUNICATOR ENGINEERING SUPPORT RADIOLOGICAL SECURITY GROUP GROUP EMERGENCY GROUP LEADER LEADER COORDINATOR LEADER SUPPORT HEALTH SECURITY ENGINEERING GROUP PHYSICS GROUP GROUP OPERATIONS MAINTENANCE GROUP GROUP LEADER LEADER TECHNICAL ADVISOR OSC COORDINATOR OPERATIONS GROUP I&C ELECTRICAL &

GROUP MECHANICAL GROUP

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 111 of 120 Figure 13.2 INTERFACE BETWEEN FUNCTIONAL AREAS OF EMERGENCY ACTIVITY NSPM EXECUTIVE MANAGEMENT (JIC)

EMERGENCY MANAGER (EOF)

NRC EMERGENCY DIRECTOR (TSC)

OSC LOCAL SUPPORT SERVICES Fire Department County Sheriffs Ambulance Service CentraCare Health STATE EOC Monticello WRIGHT SHERBURNE STATE COUNTY COUNTY FEDERAL AGENCIES EOC EOC AGENCIES LOCAL GOVERNMENT Initial lines Lines after EOF is staffed

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 112 of 120 Figure 13.3 INTERFACE BETWEEN FUNCTIONAL AREAS OF EMERGENCY ACTIVITY DURING HOSTILE ACTION BASED EVENTS Federal Agencies MN State Police County Sheriff Fire Ambulance Law NSPM Departments Services Enforcement Executive Management Incident Joint Commander Information (ICP) Center CentraCare Monticello Health Emergency ICP Monticello Manager Federal Liasons (EOF) Agencies Utility Minnesota State NRC Liaison State EOC Agencies Security Monticello Liaison Control Room Wright Sherburne County County EOC EOC Local Government Direct Interface

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 113 of 120 Figure 13.4 HEALTH PHYSICS GROUP ORGANIZATION EMERGENCY EMERGENCY DIRECTOR MANAGER RADIATION RADIOLOGICAL PROTECTION EMERGENCY SUPPORT COORDINATOR SUPERVISOR Dose Projection Dose Projection Specialist Specialist CHEMISTRY MONITORING SECTION F/T COMM EOF CR SECTION CHEM TECH LEADER LEADER CHEM RPC F/T COMM OFF-SITE COORD MONITORING TEAMS CHEM RP OFF-SITE GROUP GROUP MONITORING TEAMS Continuous interface between EOF & TSC Command chain for TSC and EOF

I I MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 114 of 120 Figure 13.5 PLAN VIEW OF TECHNICAL SUPPORT CENTER, BACK-UP OPERATIONAL SUPPORT CENTER

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I I MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 115 of 120 Figure 13.6 PLAN VIEW OF THE EMERGENCY OPERATIONS FACILITY TRAINING TRAINING ROOM 11 ROOM 12 RECEIVING TRAINING ROOM 10 COUNT ROOM EXAM ROOM COMMUNICATIONS ROOM OFFICE TRAINING EOF COMMAND ROOM 9 CENTER DOSE ASSESSMENT TRAINING ROOM 14

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MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 116 of 120 Figure 13.7 DIRECT DEDICATED TELEPHONES (HOT LINES)

MONTICELLO TELEPHONE NETWORK (Primary Communications Link) 1 NRC CONTROL NRC OPERATION ROOM OPERATION CENTER 14 CENTER 1 7 1a 7a 2 5 3 BACK-UP TSC EOF EOF 9

8 6 4 12a 12 STATE 11 EOF 13a 11a 10a NRC NRC OPERATION OPERATION CENTER CENTER Number Name Stations 1 Emergency Notification System 5 station FTS line between the Control (ENS) Room, TSC, NRC Conference Room in TSC, NRC Office, and NRC Operations Center.

1a ENS (EOF) 3 station FTS line between the EOF, EOF NRC work area, and NRC Operations Center.

2 EOF - TSC 1 (EM-ED) 2 station line between the EOF (EM) and TSC (ED).

3 EOF TSC 2 (RPSS-REC) 2 station line between the EOF (RPSS) and TSC (REC).

4 EOF - MN. State EOC (1) 3 station auto ring hotline between the EOF and the Minnesota State EOC. Either station can activate the circuit.

5 EOF - Back-Up EOF 1 2 station line between the EOF and the Back-Up EOF.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 117 of 120 Figure 13.7 DIRECT DEDICATED TELEPHONES (HOT LINES) (CONTD) 6 EOF - Back-Up EOF 2 2 station line between technical support (Tech Support) groups at the EOF and the Back-Up EOF.

7 Health Physics Network (HPN) 4 station FTS line between the TSC, TSC Health Physics Room, NRC Conference Room in TSC, and NRC Operations Center.

7a HPN 3 station FTS line between the EOF, EOF NRC work area and NRC Operation Center.

8 TSC - MN State EOC (1) 2 station auto ring hotline between the TSC and the Minnesota State EOC. Either station can activate the circuit.

9 EOF - TSC 3 2 station line between the Technical Support (Tech Support) groups at the EOF and the TSC.

10a Management 2 Station FTS line between EOF and NRC Counterpart Link (DSO/STL) Operations Center 11 Protective Measures 2 station FTS line between NRC protective Counterpart measures personnel at the site and NRC Operations Center.

11a Protective Measures 2 station FTS line at the EOF between NRC Counterpart Link (PMCL) protective measures personnel at the EOF and NRC Operations Center.

12 Reactor Safety 2 station FTS line between NRC reactor Counterpart Link (RSCL) safety personnel at the site and NRC Operations Center.

12a Reactor Safety 2 station FTS line at the EOF between NRC Counterpart Link (RSCL) reactor safety personnel at the EOF and NRC Operations Center.

13a Local Area Network (LAN) 2 Station FTS line between EOF and NRC Operations Center 14 Emergency Response Data ERDS VPN channel link over which raw System (ERDS) reactor process data is transmitted from the site.

(1) Auto-Ring Hotlines (Dedicated Private Lines). The interconnection of two or more telephones, which automatically ring the circuit when the telephone is removed from its cradle. This service can be provided intra-facility, intra-city, or inter-city. This is a full-period circuit which is available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day with no limit to its use.

I I MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 118 of 120 Figure 13.8 PLAN VIEW OF OPERATIONAL SUPPORT CENTER PAB 1st Floor OSC Assembly Areas n

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MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 120 of 120 Figure 13.9

SUMMARY

OF SIGNIFICANT CHANGES Section Change and Reason for Change 5.5.1, Update to reflect the changes made in 1996 under state law 5.5.8 (deleted) when MN Statute-Chapter 12 was enacted. Responsibilities for the items listed in previous section 5.5.1 now fall under State and local agencies. State Emergency Services Mobile Support Area VI was abolished.

7.1.5 Update to include description of Back-up EOF capabilities.

Table 1 Removed asterisk next to Core/Thermal Hyd. 30 min responder Throughout Minor editorial and reference corrections

(l Xcel Energy Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 April 29, 2016 L-MT-16-021 10 CFR 50.54(q)(5) 10 CFR 72.44(f)

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License No. DPR-22 Changes to the Monticello Nuclear Generating Plant (MNGP) Emergency Plan Pursuant to 10 CFR 50.54(q)(5) and 10 CFR 72.44(f), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy, submits a summary of changes to the MNGP Emergency Plan as Enclosure 1. The new revision to the Emergency Plan is provided in . The Emergency Plan changes have been reviewed and do not result in a reduction in the effectiveness of the Emergency Plan.

Summary of Commitments There are no new commitments and no revisions to existing commitments in this letter.

~~4 Peter A. Gardner Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company- Minnesota Enclosures (2) cc: Emergency Response Coordinator, Region Ill, USNRC (with Enclosures)

Resident Inspector, MNGP, USNRC (with Enclosure 1)

Administrator, Region Ill, USNRC (w/o Enclosures)

Chief, Plant Support Branch, Division of Reactor Safety, Region Ill, USNRC (with Enclosure 1)

Director, Division of Spent Fuel Management, Office of Nuclear Material Safety and Safeguards (with Enclosure 1)

ENCLOSURE 1 Monticello Nuclear Generating Plant Summary of Changes - 10 CFR 50.54(q)(5)

Description (Executive Summary)

The Emergency Plan is being revised as described below:

• To explicitly list the Backup Emergency Operating Facilities (EOFs) and capabilities as identified in the 2015 Emergency Preparedness (EP) Focused Self-Assessment Report.

• To reflect a transfer of assigned responsibilities based on MN Statute Chapter 12, regarding responsibility for overall protection of the general public and providing logistical support (food, water, shelter, etc.) during an emergency

• To remove a misleading asterisk next to the 30 minute Core/Thermal Hydraulics responder in Table 1 and clarify that requirement for the position to be augmented within 30 minutes

• Spelled out the acronym SAMG as Severe Accident Management Guidelines when first referenced in the document (considered an editorial change which does not require further evaluation)

• Corrected references to applicable Emergency Plan Sections in Appendix B which had changed during previous revisions and not been updated accordingly (considered an editorial change which does not require further evaluation)

Review of the above changes concluded that none of them result in a reduction in effectiveness of the Emergency Plan.

Change (1)

==

Description:==

During the 2015 EP Focused Self-Assessment, it was identified that the Monticello Nuclear Generating Plant (MNGP) Emergency Plan does not explicitly list facilities or capabilities of the Backup EOF as is currently identified for the primary EOF.Section IV.E.8.c of Appendix E provides performance-based criteria applicable to EOFs. The functions that the EOF has to address include the capability to obtain and display plant data and radiological information for each unit or plant that the facility serves. Section 7.1.5 is being revised to clearly identify these capabilities to be consistent with the EOF section.

Doc ID or (Procedure Number) I Revision Number: E-Pian I 47 Document

Title:

Emergency Plan Licensing/Basis Affected:

• App. E., Sec. IV, E. S.c. Provides performance based criteria applicable to all EOFs.

• NSIR/DPR-ISG-01, Interim Staff Guidance, Emergency Planning for Nuclear Power Plants

• 10 CFR 50.47 Page 1 of 4

Evaluation Determination Regulatory Compliance Basis:

This change updates the description of Back-up EOF facilities and capabilities to reflect the requirements for EOFs found in NSIR/DPR-ISG-01, Interim Staff Guidance, Emergency Planning for Nuclear Power Plants, with the exception of the following:

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

This item was not included based upon this facility being a backup. The Safety Evaluation Report (SER) approval for the Backup EOF does not require any specific staffing and activation time frames applicable for inclusion in the Emergency Plan.

Emergency Plan Effectiveness Basis:

The Back-up EOF facilities and capabilities being added to Revision 47 of the Emergency Plan were all present prior to the revision. No changes in the operational characteristics of the Back-up EOF were made as a result of clarifying the performance expectations. There is no reduction in effectiveness to the Emergency Plan.

Change (2)

==

Description:==

It was identified during an annual Emergency Plan review that the reference to the Area Civil Defense Groups and the State Emergency Services Mobile Support Area VI is no longer valid due to MN Statute Chapter 12 being enacted, which abolished these organizations. Although the responsibilities that were assigned to these sub-organizations were transferred over to the Minnesota Department of Public safety, MNGP's Emergency Plan was not updated accordingly.

Doc ID or {Procedure Number) I Revision Number: E-Pian /47 Document

Title:

Emergency Plan Licensing/Basis Affected:

• 10CFR50.47

• NUREG-0654-FEMA-REP-1, Rev 1 Evaluation Determination Regulatory Compliance Basis:

This change corrects an outdated reference to Area Civil Defense groups, an organization that was abolished under state law when Statute-Chapter 12 was enacted. The responsibilities for emergency response that were previously assigned to this organization were maintained and transferred over to the Minnesota Department of Public Safety. This assignment of responsibilities is supported by the current Letter of Agreement (LOA) on file between the State of Minnesota, Department of Public Safety, Division of Homeland Security and Emergency Management (HSEM), and Northern States Power Company-Minnesota for the Prairie Island and Monticello Nuclear Generating Plants. The LOA contains a direct reference to the Minnesota Emergency Operations Plan, as stated under the section titled "Responsibilities of HSEM":

"Coordinate and provide for the functions and responsibilities that are outlined in the most current version of the Minnesota Emergency Operations Plan (MEOP), the Hostile Action Based Supplement and the State of Minnesota Governor's Executive Order assigning emergency responsibilities to state agencies." Within the MEOP, Annex F "Health and Safety Protection" documents a summary of responsibilities with each of the Page 2 of 4

State of Minnesota sub-agencies listed. Per this annex, the Department of Public Safety is responsible for the below items, where P=Primary, C= Coordination and S=Support:

P: Overall coordination of state agency activities during the response and recovery phases of a public health emergency, including those incidents/accidents that result from the use and transport of hazardous materials (chemical and radiological), infectious agents (biological) as weapons of mass destruction, and nuclear generating plant incidents.

P: When requested, make hazardous materials chemical assessment teams and emergency response teams available to local authorities.

C: Overall responsibility for coordination of animal health protection, during an incident/accident that results from the use of hazardous materials (chemical and radiological), infectious agents (biological),

and nuclear generating plant incidents.

S: When needed, assure the provision of life and safety support (food, water, sanitation) in the mass sheltering and mass feeding of victims.

Emergency Plan Effectiveness Basis:

This change is being made to correct the responsibility assignments within the Emergency Plan based on the elimination of Area Civil Defense Groups under Minnesota statutes. The correction aligns with the current LOA on file with the State of Minnesota and the Minnesota Emergency Operations Plan. All of the responsibilities that were assigned to Area Civil Defense Groups are still maintained and have not been eliminated. This change is not a reduction in effectiveness of the Emergency Plan.

Change (3)

==

Description:==

During an Emergency Plan revision in 2012, an asterisk was added to Table 1 next to the 30-minute Core/Thermal Hydraulics responder. The note that pertains to all asterisked position states "May be provided by shift personnel assigned other functions." The justification was that this made it clearer that the Core/Thermal Hydraulics role can be performed by an on-shift personnel until a 30-minute responder arrives. The current E-Pian change will remove a misleading asterisk next to the 30 minute Core/Thermal Hydraulics responder in Table 1, to regain clarity that the position does indeed need to be augmented within 30 minutes and is not a collateral duty of an on-shift position not requiring augmentation.

Doc ID or (Procedure Number) I Revision Number: E-Pian I 47 Document

Title:

Emergency Plan Licensing/Basis Affected:

• 10 CFR 50.47

• 10 CFR 50 Appendix E, Sec. IV

• A.2-002 (Monticello On-Shift Staffing Analysis), Revision 0 and Revision 1 Evaluation Determination Regulatory Compliance Basis:

This change as described clarifies the requirement for the Core/Thermal Hydraulics position to be augmented within 30 minutes by someone other than an on-shift person. This clarification will eliminate Page 3 of 4

potential misinterpretations of the requirement and ensure future regulatory compliance regarding staffing of the site's Emergency Response Organization and established positions.

Emergency Plan Effectiveness Basis:

This revision to the Emergency Plan will clear up potential confusion regarding the staffing requirements of the Core/Thermal Hydraulics position. It removes the possible misinterpretation that the positon can be covered by an on-shift person performing another role and clarifies the requirement for the position to be augmented within 30 minutes. Removal of the asterisk does not change the total 30 minute responders identified in the table, which remains at nine. This change is not a reduction in effectiveness of the Emergency Plan.

Page 4 of 4

ENCLOSURE 2 Monticello Nuclear Generating Plant Emergency Plan, Revision 47 120 pages follow

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 1 of 120 Approval: PCR 01481745 INFORMATION USE Procedure should be available, but NOT necessarily at the work location.

Procedure may be performed from memory.

User remains responsible for procedure adherence.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 2 of 120 TABLE OF CONTENTS SECTION PAGE 1.0 DEFINITIONS AND ABBREVIATIONS ........................................................................... 3 2.0 SCOPE AND APPLICABILITY ........................................................................................ 5 3.0

SUMMARY

OF EMERGENCY PLAN ............................................................................. 6 4.0 EMERGENCY CLASSIFICATION SYSTEM ................................................................... 7 5.0 ORGANIZATIONAL CONTROL OF EMERGENCIES .................................................... 9 6.0 EMERGENCY MEASURES .......................................................................................... 35 7.0 EMERGENCY FACILITIES AND EQUIPMENT ............................................................ 56 8.0 MAINTAINING EMERGENCY PREPAREDNESS ........................................................ 87 9.0 RECOVERY .................................................................................................................. 91 10.0 APPENDIX A ................................................................................................................ 93 11.0 APPENDIX B ................................................................................................................ 97 12.0 ANNEX A .................................................................................................................... 105 13.0 FIGURES .................................................................................................................... 110 Figure 13.1 MONTICELLO PLANT EMERGENCY ORGANIZATION ............................. 110 Figure 13.2 INTERFACE BETWEEN FUNCTIONAL AREAS OF EMERGENCY ACTIVITY ..................................................................................................... 111 Figure 13.3 INTERFACE BETWEEN FUNCTIONAL AREAS OF EMERGENCY ACTIVITY DURING HOSTILE ACTION BASED EVENTS ........................... 112 Figure 13.4 HEALTH PHYSICS GROUP ORGANIZATION ............................................ 113 Figure 13.5 PLAN VIEW OF TECHNICAL SUPPORT CENTER, BACK-UP OPERATIONAL SUPPORT CENTER .......................................................... 114 Figure 13.6 PLAN VIEW OF THE EMERGENCY OPERATIONS FACILITY ................... 115 Figure 13.7 DIRECT DEDICATED TELEPHONES (HOT LINES) ................................... 116 Figure 13.8 PLAN VIEW OF OPERATIONAL SUPPORT CENTER ................................ 118 Figure 13.9

SUMMARY

OF SIGNIFICANT CHANGES ................................................... 120

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 3 of 120 1.0 DEFINITIONS AND ABBREVIATIONS 1.1 Assessment Action - Actions taken during or after an accident to obtain and process information necessary to make decisions regarding emergency measures.

1.2 Committed Dose Equivalent (CDE) refers to the dose received over the 50 year period following an intake of radioactive materials.

1.3 Committed Effective Dose Equivalent (CEDE) is the sum of the products of the weighted factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent to these organs or tissue.

1.4 Corrective Actions - Emergency measures taken to terminate an emergency situation at or near the source in order to prevent or minimize a radioactive release, e.g., shutting down equipment, firefighting, repair and damage control, etc.

1.5 Effective dose equivalent (EDE) is the sum of the product of the absorbed dose in tissue, quality factors, and all other necessary modifying factors at the location of interest.

1.6 Emergency Action Level (EAL) - A predetermined, site-specific, observable threshold for a plant Initiating Condition that places the plant in a given emergency class. An EAL can be: an instrument reading; an equipment status indicator; a measurable parameter (on-site or off-site); a discrete, observable event; results of an analyses; entry into specific emergency operating procedures; or another phenomenon which, if it occurs, indicates entry into a particular emergency class.

1.7 Emergency Director (ED) - The Plant Manager or his designee. This individual has overall responsibility and authority for managing the emergency effort within the plant. The ED will also manage efforts external to the plant until relieved of those responsibilities by the Emergency Manager.

1.8 Emergency Manager (EM) - This person is responsible to direct the overall MNGP emergency response effort. The EM will assume control of the Emergency Operations Facility and direct NSPM Emergency response efforts.

1.9 EOF - Emergency Operations Facility 1.10 Emergency Planning Zones - A defined area around the plant to facilitate emergency planning by state and local authorities, to assure that prompt and effective actions are taken to protect the public in the event of a release of radioactive material. It is defined for:

Plume Exposure Pathway - A 10 mile radius around the plant where the principal exposure source is: (1) whole body exposure to gamma radiation from the plume and from deposited material; and (2) inhalation exposure from the passing radioactive plume (Short Term Exposure).

Ingestion Exposure Pathway - A 50 mile radius around the plant where the principal exposure would be from the ingestion of contaminated water or foods such as milk or fresh vegetables (Long Term Exposure).

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 4 of 120 1.11 ERDS - Emergency Response Data System 1.12 Emergency Worker - Any individual who has an essential mission within or outside the plume exposure pathway emergency planning zone to protect the health and safety of the public who could be exposed to ionizing radiation from the plume or from its deposition. Some examples of emergency workers are: radiation monitoring personnel; traffic control personnel; evacuation vehicle drivers; fire and rescue personnel, including ambulance crews; medical facilities personnel; emergency operations center personnel; personnel carrying out backup alerting procedures; and essential services or utility personnel.

1.13 FTS - Federal Telephone System 1.14 Initiating Condition (IC) - One of a predetermined subset of nuclear power plant conditions when either the potential exists for a radiological emergency, or such an emergency has occurred.

1.15 Northern States Power Company - Minnesota (NSPM) - is the operator of the Monticello Nuclear Generating Plant.

1.16 OSC - Operational Support Center 1.17 PASS - Post-Accident Sampling System 1.18 Protective Actions - Emergency measures taken before or after a release of radioactive materials in order to prevent or minimize radiological exposures to the population.

1.19 Protective Action Guides (PAG) - Projected dose to individuals that warrants protective action prior to and/or following a radioactive release.

1.20 REC - Radiological Emergency Coordinator 1.21 Recovery Actions - Actions taken after an emergency to restore the plant to normal.

1.22 SEC - Shift Emergency Communicator 1.23 TSC - Technical Support Center 1.24 Total Effective Dose Equivalent (TEDE) is the sum of EDE and CEDE.

1.25 Xcel Energy is the owner of the Monticello Nuclear Generating Plant.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 5 of 120 2.0 SCOPE AND APPLICABILITY In accordance with license conditions, 10CFR Part 50, and NRC Regulatory guidance, the Northern States Power Company - Minnesota (NSPM) has developed and implemented an emergency response plan for the Monticello Nuclear Generating Plant (MNGP) and a joint off-site plan for the MNGP and the Prairie Island Nuclear Generating Plant. Xcel Energys wholly owned subsidiary NSPM operates the Monticello Nuclear Generating Plant. As asset owner, Xcel Energy retains all owner obligations.

In any emergency situation at Monticello, the initial response would be made by the site staff and, if needed, by local support agencies. It is expected that the initial response would have to extend for a period of hours, by which time the site staff would be augmented by other segments of the overall NSPM emergency response organization.

Once all centers are activated and the emergency organization is at full strength, the scope of the plant staff response will be reduced to the immediate plant site activities. This plan covers the actions and responsibilities of the Monticello plant staff and the local off-site support agencies.

The plan is directed toward the following areas:

2.1 Organization and actions within the plant to control and limit the consequences of an accident.

2.2 Organization and actions controlling site and initial off-site activities in the event of an uncontrolled release of radioactive material. This includes notification of and coordination with required off-site support agencies.

2.3 Identifying and evaluating the consequences of accidents that may occur and affect the safety of public and plant personnel.

2.4 Describing the protective action levels and actions that are required to protect the public and plant personnel in the event of an accident.

2.5 Considerations necessary for the purposes of re-entry and recovery.

2.6 Arrangements required for medical support in the event of injury.

2.7 The training necessary to assure adequate response to emergencies.

2.8 Notification systems used to notify the public in the event of an incident involving or potential of involving an off-site release.

The Emergency Plan is dependent upon the Emergency Plan Implementing Procedures for implementation. The procedures are the activating mechanism for the State Plan, which in turn activates the local government and service support agencies. Finally, the procedures reference standing plant operating, radiological control and security procedures in defining the plants response to the spectrum of emergency situations.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 6 of 120 3.0

SUMMARY

OF EMERGENCY PLAN Abnormal events, both realized and potential, requiring emergency preparedness response are classified into four classes of Emergency Action Levels. The four levels of emergency classes, in increasing order of severity are:

(1) Notification of Unusual Event (2) Alert (3) Site Area Emergency (4) General Emergency Each class requires specific immediate actions on the part of the plant staff in order to protect the public, plant personnel and property. As the severity level of the emergency increases, so does the response of the off-site agencies, in order to protect the public.

The lowest class (least severe) is the Notification of Unusual Event. This classification will be handled by plant personnel, with advisory notification to local and state authorities. The Alert Classification requires prompt notification of local and state authorities, which will place their various organizations in the standby mode. In both the Notification of Unusual Event and the Alert Classification, the plant staff is expected to restore the situation to normal without further or minimum involvement of off-site authorities. The two higher severity classes, the Site Area and the General Emergency, (the General Emergency being the most severe), require prompt notification of off-site authorities with immediate involvement of those organizations to assess the emergency situation and to implement the required protective actions for the general public.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 7 of 120 4.0 EMERGENCY CLASSIFICATION SYSTEM Emergency situations are classified according to severity, taking into consideration potential as well as actual events in process. Monticello Nuclear Generating Plant has and 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 has been exceeded. Upon identification of the appropriate emergency classification level the emergency condition will be promptly declared. The four standardized classifications are as follows:

1. Notification of Unusual Event (UE)

2. Alert

3. Site Area Emergency (SAE)

4. General Emergency (GE)

The rationale connecting the four action levels is to provide a mechanism for timely notification of events which could lead to significant consequences given subsequent operator error or equipment failure or which might be indicative of more serious conditions which are not yet fully realized. It should be noted that various events could require a graded scale of response. A minor incident could increase in severity and advance to the next class of emergency. For some events, the condition may be corrected before a classification has been made. In general, the following guidance applies. Classify the event as indicated and terminate the emergency once assessment shows that there were no consequences from the event and other termination criteria are met. For example, a momentary event, such as an ATWS or an earthquake, requires declaration even though the condition may have been resolved by the time the declaration is made.

The process of assessing and classifying an event as a specific type of emergency requires a broad knowledge of integrated plant instrumentation and response to various transients. The various Initiating Conditions (IC) for each emergency class are specified in Annex A of this plan. Annex A also includes the detailed set of Emergency Action Levels (EAL) applicable to the Monticello Nuclear Generating Plant. The EALs are the plant-specific indications, conditions, or instrument readings that are utilized to classify emergency conditions at the plant and were developed using the EAL development methodology found in NEI 99-01, Revision 4.

The ICs and EALs are grouped into the following symptom-based, event based, and barrier-based recognition categories.

R - Abnormal Rad Levels/Radiological Effluent C - Cold Shutdown/Refueling System Malfunction E - Independent Spent Fuel Storage Installations F - Fission Product Barrier Degradation H - Hazards S - System Malfunction

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 8 of 120 Following is a brief description of each emergency classification and its associated response level.

4.1 Notification of 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 has been initiated. No releases of radioactive material requiring off-site response or monitoring are expected unless further degradation of safety systems occurs.

The purpose of the Unusual Event emergency class is to (1) have the operating staff come to a state of readiness from the standpoint of emergency response in the event the handling of the initiating condition needs to be escalated to a more severe emergency class, and (2) provide for systematic handling of Unusual Events information and its related decision-making.

4.2 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 HOSTILE ACTION. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.

Alerts are the lowest level where emergency off-site response may be anticipated.

The purpose of the alert emergency class is to (1) assure emergency personnel are readily available to respond if the situation becomes more serious or to perform confirmatory radiation monitoring if required, (2) provide off-site authorities current status information, and (3) provide for activation of the TSC, OSC, and EOF or backup EOF.

4.3 Site Area Emergency Events are in process 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 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 Protective Action Guideline exposure levels beyond the site boundary.

The purpose of the site area emergency classification is to (1) assure that response centers are staffed; (2) assure that monitoring teams are dispatched; (3) assure that personnel required for evacuation of near-site areas are at duty stations if the situation becomes more serious, and (4) provide current information for and consultation with off-site authorities and public.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 9 of 120 4.4 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 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.

The purpose of the general emergency classification is to (1) initiate predetermined protective actions for the public, (2) provide continuous assessment of information from licensee and off-site measurements, (3) initiate additional measures as indicated by actual or potential releases, and (4) provide current information for and consultation with off-site authorities and public.

5.0 ORGANIZATIONAL CONTROL OF EMERGENCIES 5.1 Normal Site Organization 5.1.1 Site Management Organization The normal site organization is comprised of the plant organization and several other site support organizations. Each organizational area has a report directly to the Site Vice President or provides on-site functional support to the Site Vice President with an indirect reporting responsibility to the Site Vice President. These organizational areas include:

Plant (including Operations, Production Planning, Maintenance, Radiation Protection, Chemistry, and Human Performance and Safety).

Performance Assessment Business Support (including Document Control, Administrative Support, Emergency Preparedness, Accounting/Finance)

Training Nuclear Security Nuclear Oversight Information Technology Supply Chain Regulatory Affairs/Licensing Engineering (including Plant and Systems, Design, and Programs)

Human Resources Projects Responsibilities and authority of the various functional groups and individual positions are delineated in MNGP Administrative Directives.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 10 of 120 5.1.2 Shift Organization 5.1.2.1 Operations The Shift Manager holds a Senior Reactor Operator license and is the senior member of the Operations shift organization.

The Shift Manager has the responsibility and authority to direct operating activities of the plant IAW applicable regulations and procedures. The Shift Manager maintains the broadest perspective of operational conditions affecting plant safety and serves as or provides oversight of the technical advisor to the Control Room Supervisor and Control Room operations crew.

The Control Room Supervisor holds a Senior Reactor Operator license and reports to the Shift Manager. The Control Room Supervisor has the responsibility to supervise operating activities of the plant in accordance with applicable regulations and procedures under the direction of the Shift Manager.

A third SRO is qualified to support the shift manager in evaluation of off normal conditions.

Licensed Operators assigned to the Control Room perform plant manipulations and take direction from the Control Room Supervisor.

Auxiliary Operators outside the Control Room manipulate plant equipment and generally take direction from the Lead Plant Equipment and Control Room Operator or the Control Room Supervisor.

5.1.2.2 Fire Brigade The plant Fire Brigade is staffed by qualified Operators, Chemistry and Radiation Protection Technicians. The Fire Brigade is maintained in accordance with 4 AWI-08.01.01 (FIRE PREVENTION PRACTICES).

5.1.2.3 Radiation Protection Two Radiation Protection Technicians are assigned to each operating shift. The normal responsibilities of a shift Radiation Protection Technician are conducting routine and special radiological surveys, operation of plant Count Room equipment, access control and Radiation Work Permit preparation.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 11 of 120 5.1.2.4 Chemistry One Chemistry Technician is assigned to each operating shift.

The normal responsibilities of the shift Chemistry Technician are conducting routine and special chemistry sampling and analysis and operation of the plant Chemistry Lab.

5.1.2.5 Security (Shift Emergency Communicator)

Security personnel perform duties in accordance with the Security Plan. In addition, Security personnel on each shift are normally assigned the responsibility of primary Shift Emergency Communicator (SEC). As SEC, Security personnel perform emergency and non-emergency communications as directed by the Shift Manager. If dedicated Security personnel are not available to perform this function, other SEC qualified personnel may also be assigned responsibility of primary SEC.

5.1.3 Minimum Shift Staffing Minimum shift staffing SHALL be as indicated in Table 1, Minimum Shift Staffing And Capability For Additions For Nuclear Power Plant Emergencies.

5.1.4 Onshift Staffing Analysis The Onshift Staffing Analysis, A.2-002, provides the supporting documentation for developing the onshift staffing levels as indicated in Table 1, Minimum Shift Staffing and Capability for Additions for Nuclear Power.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 12 of 120 5.2 Emergency Organization and Responsibilities Under emergency conditions the organization of the site staff is altered to simplify communications channels and make more efficient use of personnel resources (refer to Figure 13.1, Monticello Plant Emergency Organization). The Monticello Emergency Response Organization (ERO) consists of various groups which staff the site Emergency Response Facilities including the Technical Support Center, Operational Support Center and Emergency Operations Facility (or backup EOF if necessary). Functional responsibilities of the various groups are described in this section. A detailed description of individual position responsibilities and leadership designations for the various groups is contained in Emergency Plan Implementing Procedure A.2-001 (EMERGENCY ORGANIZATION). A detailed description of personnel assignments is found in Form 5790-001-01 (EMERGENCY RESPONSE ORGANIZATION).

5.2.1 Technical Support Center Emergency Organization The Technical Support Center ERO consists of a Coordination and Direction Group and six subordinate groups. Each group is represented at the command table in the Technical Support Center.

When a transition point (Primary Containment flooding is required) in the Emergency Operating Procedures (EOPs) is reached, the duty Shift Manager and Operations Group Leader will make a joint decision to transition from the EOPs to the Severe Accident Management Guidelines (SAMGs). At this point, the Operations Group Leader would inform the TSC that they have relieved the duty Shift Manager as the Decision Maker.

The Decision Maker is designated to assess and select the strategies to be implemented. When using the SAMGs, the Operations Group Leader will act as the Decision Maker.

At the same time an Accident Management Team (AMT) is formed to utilize the SAMGs. The AMT is comprised of the following ERO positions; Operations Group Leader, Assistant Operations Group Leader, Engineering Coordinator, Nuclear Engineer, SPDS Operator, Trending Individual. AMT members are the Decision Maker and Evaluators. Evaluators are responsible for assessing control parameters, plant status, system status and EOP/SAMG actions and develop potential strategies that may be utilized to mitigate an event.

5.2.1.1 Direction and Control The Direction and Control Group consists of the Plant Manager and other senior plant management personnel designated by the Plant Manager. Designated members of this group staff the Emergency Director position in the TSC. Qualified Shift Managers are also included in this group and function as the interim Emergency Director during the initial stages of an emergency until relieved by a designated Emergency Director.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 13 of 120 The Emergency Director is responsible for overall emergency direction and control until relieved of that responsibility by the Emergency Manager at the EOF. Initially, the Shift Manager assumes the role of Emergency Director until relieved by a designated Emergency Director. The Emergency Director has the authority and responsibility to unilaterally initiate emergency response actions including making off-site protective action recommendations to authorities responsible for implementing off-site emergency measures.

Functional responsibilities of the Emergency Director include:

Recommend off-site protective measures. This responsibility may not be delegated and is relinquished to the Emergency Manager when the EOF is activated and staffed.

Overall direction and control of the Technical Support Center personnel and activities.

Ensure 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> coverage of key Emergency Response Organization positions in the TSC and OSC and continuity of personnel and material resources.

Make decisions regarding plant emergency response facility habitability including on-site protective actions (including KI use), personnel monitoring and evacuations.

Approval of emergency radiation exposures in excess of normal limits.

Communications with utility and off-site Emergency Response Organizations. EOF assumes responsibility for communications with off-site agencies when activated and staffed.

When the EOF is activated and the Emergency Manager position is staffed, the overall direction and control responsibility is transferred from the Emergency Director to the Emergency Manager. The Emergency Director retains authority and responsibility for decisions immediately affecting the plant including direction of plant emergency response and on-site protective measures.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 14 of 120 5.2.1.2 Radiation Protection and Chemistry Groups The Radiation Protection and Chemistry Groups consists of the Radiological Emergency Coordinator (REC) and members of the Radiation Protection and Chemistry Groups. The REC reports to the Emergency Director and is staffed by Radiation Protection and Chemistry Manager designees. The group is divided into three sections:

Monitoring Section Chemistry Section Off-site Dose Projection The Radiological Emergency Coordinator is the group leader and responsible for coordination of all on-site Radiation Protection and Chemistry emergency response activities.

The Monitoring Section consists of the Monitoring Section Leader, and members of the plant Radiation Protection/Chemistry staff and other NSPM personnel with demonstrated experience in radiation protection.

Responsibilities of the Monitoring Section include on-site radiological surveys, in-plant surveys, personnel exposure control, access control, and initial off-site radiological monitoring.

The Chemistry Section consists of the Chemistry Section Leader and members of the plant Chemistry staff.

Responsibilities of the Chemistry Section include chemistry sampling and analysis, plant and EOF Count Room operation, PASS sampling and core damage assessment, if necessary.

Chemistry personnel also function as off-site Dose Projection Specialists.

Off-site dose projection is performed by a Dose Projection Specialist. The Dose Projection Specialist positions are staffed by qualified personnel trained in off-site dose projection. The Dose Projection Specialist responsibilities include off-site dose projections, monitoring current and forecast meteorological information and providing off-site dose projection results to the REC or RPSS.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 15 of 120 5.2.1.3 Support Group The Support Group is staffed by members of the site Business Support Group, Supply Chain, and others designated by site management. The Support Group Leader reports to the Emergency Director and is responsible for on-site logistics support, emergency document control, print and drawing retrieval, administrative services, emergency procurement and warehouse support. The Support Group Leader is also responsible to coordinate the establishment of 24-hour ERO shift schedules as requested by the Emergency Director.

5.2.1.4 Operations Group The Operations Group consists of the Operations Group Leader and all members of the Operations staff including the duty operating crew, off-duty Shift Managers, Control Room Supervisors and all Operators. The Operations Group Leader is staffed by Shift Operation Manager designees and includes off-duty Shift Managers and Control Room Supervisors that report to the Emergency Director. The Operations Group Leader serves as the primary link between the TSC and Control Room for the purpose of providing technical and operational advice and support to the duty Control Room operating staff.

When a transition point (Primary Containment flooding is required) in the EOPs is reached, the duty Shift Manager and Operations Group Leader will make a joint decision to transition from the EOPs to the Severe Accident Management Guidelines (SAMGs). At this point, the Operations Group Leader would inform the TSC that they have relieved the duty Shift Manager as the Decision Maker. The Decision Maker is designated to assess and select the strategies to be implemented. When using the SAMGs, the Operations Group Leader will act as the Decision Maker and directs actions as specified in the SAMGs.

The Assistant Operations Group Leader is a member of the Accident Management Team (AMT). The Assistant Operations Group Leaders primary responsibility is to recommend actions to the Operations Group Leader based on the SAMGs.

The Assistant Operations Group Leader is an off-duty Shift Manager or Control Room Supervisor.

In addition, the Operations Group provides off-duty personnel to staff and support the Operational Support Center (OSC).

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 16 of 120 5.2.1.5 Engineering Group The Engineering Group consists of the Engineering Group Leader and members of the site Engineering Group. The Engineering Group Leader position is staffed by Director, Site Engineering designees and reports to the Emergency Director.

The Engineering Group Leader is responsible for overall direction of Engineering Group activities and assessment. The Engineering Coordinator reports to the Engineering Group Leader until the SAMGs are entered. When using the SAMGs the Engineering Coordinator becomes a member of the Accident Management Team (AMT) and reports to the Operations Group Leader. Responsibilities of the Engineering Coordinator include engineering evaluation of the event, assessment of inoperable systems or system components, development of accident mitigation strategies and parameter trending and analysis.

5.2.1.6 Maintenance Group The Maintenance Group consists of the Maintenance Group Leader and members of the Mechanical and Electrical Maintenance Groups including Instrument and Control and designated personnel capable of performing emergency tasks.

The Maintenance Group Leader position is staffed by Maintenance Manager designees and reports to the Emergency Director. The Maintenance Group Leader is responsible for the overall direction of corrective actions including damage control and emergency repairs to systems, components or equipment. The OSC Coordinator reports to the Maintenance Group Leader and is responsible for the coordination of emergency repair activities initiated out of the OSC.

5.2.1.7 Security Group The Security Group consists of the Security Group Leader, Security Lieutenant/SEC and members of the plant Security force. The Security Group Leader position is staffed by the Security Manager or designee and reports to the Emergency Director. The Security Group Leader is responsible for the direction and coordination of security emergency activities including personnel accountability, evacuation of on-site areas and site traffic control and access. The duty Shift Emergency Communicator reports to the Emergency Director (Shift Manager) and is responsible for making or assisting with initial off-site notification. The duty Shift Emergency Communicator may be a qualified SEC from other departments.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 17 of 120 5.2.1.8 Emergency Communications Group The Communications Group consists of the Lead Emergency Communicator and qualified Emergency Communicators from various site groups. Designated personnel are qualified to staff emergency communicator positions in the TSC, OSC, EOF and Control Room. Responsibilities of the Emergency Communicators include emergency notifications to off-site authorities, transmission of Emergency Follow-up Messages and other required information to off-site authorities, intra-utility communications and communications links between site emergency response facilities.

5.2.2 Operational Support Center Emergency Organization The OSC Emergency Response Organization includes personnel from Maintenance, Operations, Production Planning, Radiation Protection and Chemistry.

5.2.2.1 Coordination and Direction The OSC Coordinator is responsible for coordination of all OSC activities including dispatching repair teams, personnel accountability in the OSC and OSC habitability. The OSC Coordinator position is staffed by experienced Maintenance, Production Planning, or Operations personnel and reports to the Maintenance Group Leader.

5.2.2.2 Mechanical Maintenance The Mechanical Maintenance Group consists of Machinists, Steamfitter - Welders, Riggers and Repairmen from the plant Maintenance Department, as well as designated personnel capable of performing emergency tasks. They are responsible for emergency repair activities under the direction of the OSC Coordinator.

5.2.2.3 Electrical Maintenance The Electrical Maintenance Group consists of the Electrical Maintenance Supervisor and Station Electricians from the plant Maintenance Department, as well as designated personnel capable of performing emergency tasks. They are responsible for emergency repair activities under the direction of the OSC Coordinator.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 18 of 120 5.2.2.4 Instrument & Control The I&C Group consists of the I&C Maintenance Supervisor and I&C Specialists from the plant Maintenance Department, as well as designated personnel capable of performing emergency tasks. They are responsible for emergency repairs under the direction of the OSC Coordinator.

5.2.2.5 Radiation Protection The Radiation Protection Group consists of the Radiation Protection Coordinator, Radiation Protection Technicians, Chemistry Technicians, and other NSPM personnel with radiation protection/chemistry experience and personnel designated and trained to perform on-site, out of plant and off-site radiological monitoring surveys. Radiation protection responsibilities include: OSC RP support, staffing Main Access Control, in-plant emergency team support, in-plant and out-plant radiological surveys, Emergency Response Center habitability, off-site environmental monitoring, Assembly Point staffing and Fire Brigade support (as necessary).

5.2.2.6 Operations The Operations Group consists of available non-duty Shift Managers, Control Room Supervisors, Operators and other personnel reporting to the Operations Manager. Their responsibilities include OSC operations support, in-plant emergency teams, augment the duty Control Room staff (as necessary) and Fire Brigade support (as necessary).

5.2.3 EOF Emergency Organization The EOF Emergency Organization consists of a Direction and Control Group and four subordinate groups. The EOF Emergency Organization is staffed by personnel from the NSPM organization.

5.2.3.1 Direction and Control The Direction and Control Group consists of Site Senior Management personnel. Designated members of this group staff the Emergency Manager position in the EOF. The Emergency Manager is responsible for overall direction and control of the utilities emergency response effort. The Emergency Manager relieves the Emergency Director of the following responsibilities:

Off-site dose projections and coordination and direction of off-site radiological monitoring teams.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 19 of 120 Declaration of new emergency classifications (the Control Room and Emergency Director retain the primary responsibility for re-classification and make recommendations to the Emergency Manager who has the responsibility to declare the new emergency class).

Communications with off-site authorities including Federal, State, and local authorities and Xcel Energy/NSPM executive management.

In addition, the Emergency Manager assumes the authority and responsibility to provide protective action recommendations to authorities responsible for implementing off-site emergency measures. Other responsibilities of the Emergency Manager include:

Coordinate the emergency response efforts of other utility personnel assisting the site organization.

Obtain and coordinate the services of outside consultants and vendors.

Advise Xcel Energy/NSPM executive management on matters related to emergency response efforts and needed resources to support the effort.

5.2.3.2 Technical Support Group The EOF Technical Support Group consists of select personnel from various site groups. The Technical Support Supervisor is staffed by senior site personnel and reports to the Emergency Manager. The Technical Support Group is responsible for trending critical parameters, engineering evaluation in support of the TSC Engineering Group, technical assessment and advising the Emergency Manager on technical matters related to the event.

5.2.3.3 Radiation Protection Support Group The Radiation Protection Support Group is staffed by Radiation Protection Technicians, Chemistry Technicians, and other NSPM personnel with radiation protection (chemistry) experience and personnel designated and trained to perform on-site, out of plant and off-site radiological monitoring surveys.

The Radiation Protection Support Supervisor position is staffed by NSPM personnel with demonstrated experience in radiation protection and reports to the Emergency Manager. The Radiation Protection Support Group includes plant Chemistry personnel for off-site dose projection and EOF Count Room operation and designated personnel who function as sample

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 20 of 120 couriers and drivers for off-site radiological monitoring teams.

Radiation Protection Support Group responsibilities include:

Direction and coordination of the utility off-site radiological monitoring teams.

Off-site dose projection.

EOF Count Room activation and operation.

EOF habitability, personnel monitoring and decontamination (as necessary).

Communications with State Emergency Operation Center personnel on matters related to dose projections and off-site protective action recommendations.

Staffing the Health Physics Network (HPN) and communications with the NRC (as necessary).

The Radiation Protection Support Supervisor advises the Emergency Manager on matters related to actual or potential radiological impact on the environment, off-site protective action recommendations, and EOF habitability.

5.2.3.4 EOF General Staff, Logistics, and Support Group The EOF general staff consists of the EOF Coordinator, off-site communicators, administrative and logistics support personnel.

The EOF Coordinator position is staffed by designated NSPM personnel and reports to the Emergency Manager. The EOF Coordinator is responsible for activation and operation of the EOF and assists the Emergency Manager with administrative duties.

The off-site communicators, EOF Security Coordinator, Agency Liaison and Administrative Staff report to the EOF Coordinator.

The off-site communicators are responsible for communications with Federal, State and Local authorities as directed by the Emergency Manager.

The Administrative Staff is responsible for emergency document control, recording and document distribution in the EOF.

The off-site Agency Liaison is responsible to serve as the initial interface with off-site (Non-MNGP/NSPM) Emergency Organizations (e.g. NRC Incident Response Team) responding to the EOF.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 21 of 120 The EOF Security Group is staffed by personnel from the Site Security Group. The EOF Security Coordinator reports to the EOF Coordinator. Responsibilities of EOF Security include EOF access, dosimetry issuance to EOF personnel and Fitness-for-duty assessment (if required during off-hours activations).

5.3 Emergency Response Organization Augmentation The Emergency Response Organization augmentation goals are outlined in Table 1.

The augmentation of each functional area and the methods used to accomplish ERO augmentation are described in this section.

5.3.1 ERO Augmentation Description and Goals 5.3.1.1 Plant Operations and Operational Assessment The duty Operations crew retains the responsibility for plant operation throughout an emergency situation. When in Severe Accident Management Guidelines (SAMGs) the duty operations staff implements the actions as directed by the SAMGs.

Non-duty Operations personnel in the TSC and OSC will augment the duty Operations staff.

The responsibilities of the non-duty Operations personnel include operational assessment, under the direction of the Emergency Director in the TSC, and support of emergency repair and corrective action efforts in the OSC including Fire Brigade support.

When a transition point (Primary Containment flooding is required) in the EOPs is reached, the duty Shift Manager and Operations Group Leader will make a joint decision to transition from the EOPs to the SAMGs. At this point, the Operations Group Leader would inform the TSC that they have relieved the duty Shift Manager as the Decision Maker. The Decision Maker is designated to assess and select the strategies to be implemented. When using the SAMGs, the Operations Group Leader will act as the Decision Maker and direct control room response as specified in the SAMGs. The Assistant Operations Group Leader is a member of the Accident Management Team (AMT).

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 22 of 120 5.3.1.2 Emergency Direction and Control The duty Shift Manager initially assumes the duties and responsibilities of the Emergency Director until relieved by a designated Emergency Director. Once relieved, the duty Shift Managers primary focus returns to overall coordination of emergency response activities of the duty Operations crew.

The Emergency Director assumes overall responsibility for the utility emergency response activities until relieved by the Emergency Manager. For non-security related events, the Emergency Manager should take over responsibilities in about 60 minutes from the declaration of an emergency, at the Primary EOF. Once relieved, the Emergency Directors primary focus is on plant operation and overall direction of plant emergency response activities in plant emergency response facilities including the on-site Assembly Point. The Emergency Manager assumes overall authority and responsibility for the utilitys emergency response activities from the Emergency Director and retains this authority until the event is terminated or the transition to recovery is complete.

5.3.1.3 Notification and Communications The Shift Emergency Communicator (SEC) is responsible for the performance of initial emergency notifications to the State, counties, NRC and other off-site and utility support organizations. The duty SEC will be augmented within approximately 30 minutes with one additional Emergency Communicator and within 60 minutes with two more Emergency Communicators. In about 60 minutes, the EOF should assume responsibility for communications with off-site authorities.

5.3.1.4 Radiological Assessment and Protective Actions The Shift Radiation Protection Technician is responsible for initial radiological assessment including in-plant radiological surveys. The shift Chemistry Technician is responsible for initial chemistry sampling, sample analysis, and off-site dose projection operation if required.

The Shift Radiation Protection Technician will be augmented by three additional Radiation Protection personnel within approximately 30 minutes and four more Radiation Protection personnel within approximately 60 minutes. The responsibilities of these additional Radiation Protection personnel include in-plant surveys, access control, and off-site radiological monitoring.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 23 of 120 In addition, a qualified Radiological Emergency Coordinator (REC) will augment the shift RP staff within approximately 30 minutes. The REC is responsible for overall coordination of the Radiation Protection and Chemistry Groups emergency response activities.

The Shift Chemistry Technician will be augmented with one additional Chemist within approximately 60 minutes.

The plant Radiation Protection staff will be augmented by Radiation Protection Technicians from the Prairie Island Nuclear Plant within approximately three hours.

Responsibilities of sister plant Rad Prot Technicians include off-site radiological monitoring and sampling under the direction of the Radiation Protection Support Supervisor and Emergency Manager at the EOF.

5.3.1.5 Engineering and Technical Support Technical support for the shift Operations staff is initially provided by the duty Shift Manager or Shift Technical Advisor (when staffed separately on-shift). The plant Engineering and Operations staff will provide additional technical support personnel, knowledgeable in the areas of nuclear core/thermal hydraulics, electrical, and mechanical engineering.

Augmentation in this area includes the addition of the core/thermal hydraulics position within about 30 minutes and two more members of the TSC Engineering Staff within approximately one hour. The TSC Engineering Staff is responsible to provide technical support to the Control Room staff under the direction of the Emergency Director.

Specific individuals from the TSC Engineering Staff are also members of an Accident Management Team (AMT). They will evaluate parameters used within the SAMGs.

5.3.1.6 Repair and Corrective Actions The duty Operations crew is initially responsible for any emergency repair and corrective actions that may be immediately required prior to ERO augmentation. After augmentation, repair and corrective actions are the responsibility of the Maintenance Group under the direction of the Emergency Director. The Maintenance Group consists of mechanical and electrical maintenance personnel including instrument and control technicians, as well as designated personnel capable of performing emergency tasks. Personnel from these groups report to the OSC where they are assigned corrective action tasks by the OSC Coordinator.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 24 of 120 Augmentation in the maintenance area includes the addition of one mechanical maintenance person within about 60 minutes, one I&C Group member within about 30 minutes and two electrical maintenance personnel, one within about 30 minutes and the other within 60 minutes.

5.3.1.7 Firefighting A shift fire brigade trained and equipped for fire fighting ensures adequate manual fire fighting capability for all areas of the plant containing structures, systems or components important to safety.

Firefighting is the responsibility of the shift Fire Brigade. The shift Fire Brigade may be augmented by non-duty, Fire Brigade qualified, personnel available from the OSC. Additional support for the Fire Brigade is also available from the local Fire Departments upon request.

5.3.1.8 Rescue Operations and First Aid The shift Fire Brigade is initially responsible for any immediate search and rescue operations or medical emergency response that may be required. After ERO augmentation, additional support for search and rescue and medical emergency response is available from the OSC staff under the direction of the OSC Coordinator.

5.3.1.9 Site Access Control, Accountability and Security Site access, personnel accountability, coordination of evacuees and on-site traffic control are the responsibilities of the site Security Group. Augmentation of the on-duty, shift Security Force will be as directed by the Emergency Director and Security Group Leader.

5.3.1.10 Administrative and Logistics Support The Support Group is responsible for administrative support, document control and logistics in the on-site emergency response facilities.

5.3.1.11 Environmental Monitoring Support The site Radiation Protection/Chemistry Group is responsible to coordinate post-accident environs monitoring with the REMP contractor.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 25 of 120 5.3.2 Augmentation Methods In order to ensure the goals of Table 1 (Minimum Shift Staffing and Capability for Additions for Nuclear Power Plant Emergencies ) can be achieved, two methods have been developed for the notification of site emergency response personnel. The methods include an Emergency Response Organization (ERO) Pager Network and automatic callout system for select site groups such as Business Support, Operations, Maintenance, Radiation Protection, and Chemistry.

The ERO Pager Network consists of a commercial pager system which provides coverage to an area of approximately 75 mile radius of Minneapolis. This area includes both the Monticello and Prairie Island nuclear sites. The system may be accessed via commercial telephone and has primary and backup telephone numbers. Designated ERO personnel carry ERO pagers. This group includes:

Emergency Directors TSC Group Leaders TSC Engineering Staff Emergency Communicators Radiation Protection/Chemistry personnel Operations Shift Managers Maintenance Supervision and Engineers Support Group personnel Emergency Managers EOF Technical Engineering personnel EOF Radiation Protection Support personnel Each pager in the network may be activated individually and all pagers in the network may be activated by one telephone (group) call.

To supplement the Pager Network, an automated callout system is utilized for site groups, including Operations, Maintenance, Support Group, Radiation Protection/Chemistry. The ERO roster utilized by the automated callout system is reviewed and updated quarterly.

Whether contacted by pager or other means, ERO personnel are instructed to respond immediately to the event.

If an emergency has been declared based on a security event or security threat, onsite MNGP ERO personnel may be instructed to duck and cover until the threat has passed or, if safe, report to an alternate near site location to standby for activation of their respective facility. ERO members

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 26 of 120 who are off-site will be instructed to report to the EOF. They will not be instructed to staff the affected facilities until it is safe to do so.

5.4 Augmentation of On-Site Emergency Organization 5.4.1 Licensee Headquarters Support This augmentation capability is completely described in the Off-site Nuclear Emergency Plan. The purpose of this capability is to support the plant and EOF in as many areas as is practical. Such areas include: Government Agency Interface, Logistics Support, Technical Analysis, News Media Interface, Xcel Energy and NSPM Executive Management Interface.

5.4.2 Local Support Services 5.4.2.1 Monticello Fire Department The Monticello Fire Department will provide fire and rescue assistance upon request in the event of a fire at the plant and Hostile Action Based (HAB) event. The Monticello Fire Department will be the lead fire agency for all emergencies in the City of Monticello. For a HAB event, the fire department will deploy a representative to the Incident Command Post dependent upon type, location, and scope of the incident, once scene safety is established. The MNGP Fire Brigade Leader will work with the Fire Department Leader to provide local coordination of fire fighting and non-fire fighting activities. Non-fire fighting tasks may include actions such as spraying water to contain radiological releases or directing water to plant locations for refilling/cooling purposes. In all cases, such operations may begin only when the radiological and security threats are mitigated to insure the safety of both plant personnel and fire fighters.

The City of Monticello has agreements in place to call upon resources of other agencies to assist in the response to a HAB event. The Monticello Fire Department will coordinate with other local fire departments to the extent necessary and consistent with the plans. If the fire department requires assistance to respond to an event at MNGP, including an HAB event, the Monticello Fire Department will be supplemented by resources available pursuant to the North Suburban Mutual Aid Agreement and the Minnesota Fire and Rescue Mutual Aid Plan.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 27 of 120 5.4.2.2 CentraCare Health Monticello CentraCare Health Monticello, also referred to as local hospital, serves as the principal off-site medical facility for initial treatment of radiation complicated injury or illness. In addition, North Memorial Hospital (in Minneapolis) has been designated as the definitive care center for injuries or illness that require services/facilities that the local hospital is unable to provide. Emergency procedures have been established at both hospitals and training of hospital personnel is accomplished periodically.

A complete description of local medical support services may be found in the Off-site Nuclear Emergency Plan.

5.4.2.3 Burlington Northern and Santa Fe Railway The Burlington Northern and Santa Fe Railway Dispatcher will stop and re-route trains away from the plant site, if necessary.

5.4.2.4 Ambulance Service There are two ambulance services that are available to provide service to the Monticello Nuclear Generating Plant.

CentraCare Health ambulance service will provide ambulatory services and be the lead Emergency Medical Service (EMS) agency for all emergencies at MNGP. For a Hostile Action Based (HAB) event, CentraCare Health ambulance service will deploy a representative to the Incident Command Post dependent upon type, location, and scope of the incident, once scene safety is established. The CentraCare Health representative will work under the direction and control of the Incident Commander, which shall be either the Wright County Sheriff's Office or Monticello Fire Department, dependent on the type of incident.

CentraCare Health ambulance service may utilize mutual aid to supplement their response. This mutual aid includes the relationships with CentraCare-St. Cloud Hospital and North Memorial Medical Center. If the response to an emergency, including a HAB event, requires additional resources, CentraCare Health will engage the resources of its affiliate, CentraCare-St. Cloud Hospital as needed and as available.

A complete description of response capabilities, organizational resources, activation plans, designations of emergency operations centers and letters of agreement for the organizations mentioned above are available in the Minnesota Emergency Operations Plan.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 28 of 120 5.4.2.5 Local Law Enforcement For a HAB event, Wright County Sheriff's Office will set up an Incident Command Post (ICP) near the site. The pre-designated ICP location(s) have been identified; however, selection will depend on the incident. The Wright County Sheriff's Office maintains the list of potential ICP sites and will be responsible for designating the site during a response and notifying the other agencies responding to the location. The Incident Command Post should be responsible for tracking resources and personnel at or near the site.

Unified Command will be established and includes the Wright and Sherburne Counties, state, federal and utility personnel.

For a HAB event, communication will be established between the Incident Commander and plant security and operations as soon as possible. The Wright County Sheriff's Office Tactical Response Team will be the lead tactical response operations group coordinator and coordinate the tactical law enforcement response with Command. If the response to an emergency, including a HAB event, requires additional resources, Wright County and the Sheriff have agreements in place to call upon the resources of neighboring law enforcement and emergency response service providers to assist. Wright County Sheriff's Office may request tactical team resources as needed from:

Minnesota State Patrol Special Response Team, Sherburne County ERT, and FBI SWAT.

The initial hostile action response goals are:

Maintain vital plant systems to prevent a release of radioactive materials, protection of on-site workforce, neutralizing the adversaries and restoring plant operating conditions.

Law enforcement tactical operational priorities include:

Securing a perimeter around the site, immediate containment of vital areas, sweep and securing of vital areas, safe movement of critical workers on the site, neutralizing adversaries, protection/evacuation of the on-site workforce, sweep of protected area and owner controlled area.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 29 of 120 Sherburne County will support the ICP with a Sherburne County Sheriff's Representative. If the response to an emergency, including a HAB event, requires additional resources, Sherburne County Sheriff's Department and Sherburne County Emergency Services have agreements in place to call upon the resources of neighboring law enforcement and emergency response service providers to assist.

5.5 Coordination with Participating Government Agencies Appropriate State and Local government emergency plans have been developed in support of the Monticello emergency preparedness effort. Figure 13.2, Interface Between Functional Areas of Emergency Activity, shows the interface relationships between functional areas of emergency activity. Figure 13.3, Interface Between Functional Areas of Emergency Activity During Hostile Action Based Events, illustrates the interface relationships between on-site and off-site functional areas of emergency response during events requiring use of an off-site Incident Command Post.

5.5.1 Minnesota Department of Public Safety The Minnesota Department of Public Safety has the responsibility for notification and coordination of state agencies in the event of a major emergency at Monticello. In the event of an emergency situation at the plant, the State Emergency Operations Center is activated and the Minnesota Duty Officer will immediately call the Department of Health, Governors Office, and other state agencies with emergency assignments to coordinate the implementation of any emergency procedures. The state agencies responsible for emergency procedures have established a system of 24-hour communications.

The state agencies and local government agencies are responsible for protecting the general public and providing logistical support such as food, temporary quarters, water, and sanitary facilities in the event that evacuation and isolation is required.

5.5.2 Minnesota Health Department The Minnesota Department of Health (MDH) is responsible for providing radiological expertise in the State Emergency Operations Center in conjunction with the Department of Public Safety.

The Minnesota Department of Health will interpret data and participate in recommending protective actions to the Governors Authorized Representative.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 30 of 120 5.5.3 Wright County Sheriff In the event of an accident the Sheriff of Wright County will notify all necessary civil support groups in Wright County. The sheriff or designee is also responsible for protection of the general public and can provide personnel and equipment for evacuation, relocation and isolation of affected areas.

5.5.4 Monticello Radiological Emergency Preparedness The Monticello Radiological Emergency Preparedness has the responsibility for coordination of city populace in the event of a major emergency that affects the city of Monticello.

5.5.5 U.S. Department of Energy Protection for the general public is provided through the Nuclear/Radiological Incident Annex of the National Response Framework.

Under this plan, individual DOE officers are assigned geographic responsibilities for incidents occurring in their region. Their immediate objective is to rapidly dispatch a team of specialists to the incident site and assist the state in evaluating the hazard. The DOE will then provide the materials and equipment to counteract and control any acute hazard, and establish communications with local authorities.

5.5.6 Sherburne County Sheriff In the event of an accident, the Sheriff of Sherburne County will notify all necessary civil support groups in Sherburne County. The sheriff or designee is also responsible for protection of the general public and can provide personnel and equipment for evacuation, relocation and isolation of affected areas.

5.5.7 Minnesota State Patrol The State Patrol may assist with the protection of the general public by providing personnel and equipment to re-route traffic in the event of a general emergency. Plans have been made for re-routing federal and state highways. Signs and equipment required for re-routing will be stored in the areas where they would be needed to facilitate highway closings.

5.5.8 Minnesota Department of Transportation Assist the State Patrol in blocking and re-routing traffic around the plant site. The Minnesota Department of Transportation has the necessary personnel, vehicles, signals, and barriers for establishing and maintaining detour routes.

5.5.9 City of Minneapolis Water Department The Water Department can shut off water intakes, if necessary.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 31 of 120 5.5.10 City of St. Paul Water Department The Water Department can shut off water intakes, if necessary.

A complete description of response capabilities, organizational resources, activation plans, designations of emergency operations centers and letters of agreement for the organizations mentioned above are available in the Minnesota Emergency Operations Plan.

5.6 Coordination with Other Participating Agencies 5.6.1 Institute Of Nuclear Power Operations (INPO)

INPO will coordinate requests from other utility INPO members and participants. They will notify NEI and EPRI of events, maintain an emergency resource capability and information on industry assistance capabilities, coordinate the delivery of persons and materials under its Nuclear Power Plant and Transportation Agreements, and provide member communications to facilitate the flow of technical information about the emergency.

5.6.2 Pooled Equipment Inventory Company (PEICo)

Southern Nuclear Services, llC ("SNS"), as agent for Pooled Equipment Inventory Company (PEICo) will support the Monticello emergency preparedness effort for withdrawal of PIM Pass Cask D24AElOIAOOl &

A002. The emergency contact list of the PIM Program Manager's Organization is provided in the LOA in the event there is a need to withdraw the subject equipment.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 32 of 120 Table 1 MINIMUM SHIFT STAFFING AND CAPABILITY FOR ADDITIONS FOR NUCLEAR POWER PLANT EMERGENCIES Capability for Additions Position Title or On 30 60 Major Functional Area Major Tasks Expertise Shift min min Plant Operations and Shift Manager 1 --- ---

Assessment of Control Room Supv 1 --- ---

Operational Aspects SRO 1 --- ---

Nuclear Lead 1 --- ---

PE&RO (RO)

Nuclear PE&RO 2 --- ---

Nuclear Asst. PEO 3 --- ---

Emergency Direction Emergency Director 1* --- ---

and Control (Shift Manager until relieved)

Notification/ Notify licensee, Shift Emerg 1 --- ---

Communication Local, State, and Communicator Federal personnel &

agencies Maintain Emergency --- 1 2 Communications Communicators Radiological Accident Emergency Emergency --- --- 1 Assessment and Operations Facility Manager Support of Operational Coordinate EOF prior EOF Coord --- 1 ---

Accident Assessment to arrival of Emergency Manager Off-Site Dose Radiological --- 1 ---

Assessment Emergency Coord Off-Site Surveys Radiation Protection --- 1 1 On-Site (out-of-plant) 1 1 In-Plant Surveys 2 --- 1 Chemistry/Radio- Chemistry 1 1 Chemistry

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 33 of 120 Table 1 MINIMUM SHIFT STAFFING AND CAPABILITY FOR ADDITIONS FOR NUCLEAR POWER PLANT EMERGENCIES (CONTD)

Capability for Additions Position Title or On 30 60 Major Functional Area Major Tasks Expertise Shift min min Plant System Technical Support Technical Advisors 1* --- ---

Engineering, Repair and Core/Thermal Hyd. --- 1 ---

Corrective actions Electrical --- --- 1 Mechanical --- --- 1 Repair & Corrective Mech Maint 1* --- 1 Actions Elec Maint 1* 1 1 I&C --- 1 ---

Protective Actions Radiation Protection Radiation Protection 2* 1 1 (In-Plant) a. Access Control

b. HP Coverage for response actions

c. Personnel monitoring

d. Dosimetry Fire Fighting Fire Brigade per Local 4 AWI-08.01.01 Support Rescue Operations and 2* Local First Aid Support Site Access Control and Security, Security Force All per Personnel Accountability Communications, Security Plan Personnel Accountability 13 9 12

• May be provided by shift personnel assigned other functions.

I I MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 34 of 120 Table 2 MONTICELLO PLANT ERO RESPONSIBILITY MATRIX p - PRIMARY RESPONSIBILITY S - SECONDARY RESPONSIBILITY COMMAND/ p p CONTROL NOTIFICATION/

COMMUNICATION s s p s PLANT OPERATIONS p s p p s TECHNICAL SUPPORT s p s p PROTECTIVE ACTIONS ON-SITE s s p p PERSONNEL ACCOUNTABILITY s s p ACCIDENT ASSESSMENT s s p s OFF-SITE DOSE PROJECTION s p p CONTAMINATION/

RADIATION CONTROL s p p DAMAGE CONTROL s p s p s PROTECTIVE ACTIONS p OFF-SITE RECOMMENDATIONS SEARCH & RESCUE/

FIRST AID s s p s p ACCESS CONTROL s p p p RECOVERY OPERATIONS s s s s p s s CHEMISTRY/

RADIOCHEMISTRY s p p LOGISTICS SUPPORT s p p FIRE FIGHTING s p s p s

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 35 of 120 6.0 EMERGENCY MEASURES 6.1 Summary of Responses For each of the four emergency classifications discussed in Section 4.0 certain generic emergency response actions are required to be taken by the site Emergency Response Organization. These generic emergency response actions are in addition to those actions specific to the type of emergency. This section summarizes the generic emergency response actions.

6.1.1 Notification of Unusual Event 6.1.1.1 Promptly inform State and Local off-site authorities of the nature of the emergency condition.

6.1.1.2 Inform the NRC of the Unusual Event.

6.1.1.3 Augment on-shift resources as necessary.

6.1.1.4 Assess and respond to the off-normal condition.

6.1.1.5 Terminate the Unusual Event with notification to the State and Local off-site authorities and the NRC.

OR 6.1.1.6 Escalate to a more severe emergency class.

6.1.2 Alert 6.1.2.1 Promptly inform the State and Local off-site authorities of the Alert and the nature of the emergency condition.

6.1.2.2 Augment on-shift resources by activating the Technical Support Center (TSC), Operational Support Center (OSC), and Emergency Operations Facility (EOF) or Back-up EOF 6.1.2.3 Notify the NRC of the Alert.

6.1.2.4 Establish the Emergency Response Data System (ERDS) communication link with the NRC.

6.1.2.5 Assess and respond to the emergency condition.

6.1.2.6 Dispatch on-site and off-site radiological survey teams and associated communications as necessary.

6.1.2.7 Provide periodic plant status updates to off-site authorities (Follow-up Messages).

6.1.2.8 Provide periodic meteorological assessments to off-site authorities and, if releases are occurring, estimates for actual releases.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 36 of 120 6.1.2.9 Terminate the Alert with notification to the State and Local off-site authorities and the NRC.

OR 6.1.2.10 Escalate to a more severe emergency class.

6.1.3 Site Area Emergency 6.1.3.1 Promptly inform the State and Local off-site authorities of the Site Area Emergency and the nature of the emergency condition.

6.1.3.2 Augment on-shift resources by activating the Technical Support Center (TSC), Operational Support Center (OSC) and Emergency Operations Facility (EOF) or Back-up EOF.

6.1.3.3 Notify the NRC of the Site Area Emergency.

6.1.3.4 Establish the ERDS communication link with the NRC.

6.1.3.5 Assess and respond to the emergency condition.

6.1.3.6 If radiological and environmental conditions permit evacuate on-site, non-essential personnel.

6.1.3.7 Dispatch on-site and off-site radiological survey teams and associated communications as necessary.

6.1.3.8 Provide a dedicated individual for plant status updates to off-site authorities.

6.1.3.9 Make utility senior technical and management staff available for consultation with the NRC and State on a periodic basis.

6.1.3.10 Provide meteorological data and dose estimates to off-site authorities for actual releases via a dedicated individual or automated transmission.

6.1.3.11 Provide release data and dose projections based on available plant condition information and foreseeable contingencies.

6.1.3.12 Terminate the Site Area Emergency with notification to the State and Local off-site authorities and the NRC.

OR 6.1.3.13 Enter Recovery with notification to the State and Local off-site authorities and the NRC.

OR 6.1.3.14 Escalate to a General Emergency.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 37 of 120 6.1.4 General Emergency 6.1.4.1 Promptly inform the State and Local off-site authorities of the General Emergency and the nature of the emergency condition.

6.1.4.2 Make off-site protective action recommendations to State and Local authorities based on actual or potential plant conditions and radiological releases.

6.1.4.3 Augment on-shift resources by activating the Technical Support Center (TSC), Operational Support Center (OSC) and Emergency Operations Facility (EOF) or Back-up EOF.

6.1.4.4 Notify the NRC of the General Emergency.

6.1.4.5 Establish the ERDS communication link with the NRC.

6.1.4.6 Assess and respond to the emergency condition.

6.1.4.7 If radiological and environmental conditions permit evacuate on-site, non-essential personnel.

6.1.4.8 Dispatch on-site and off-site radiological survey teams and associated communications.

6.1.4.9 Provide a dedicated individual for plant status updates to off-site authorities.

6.1.4.10 Make utility senior technical and management staff available for consultation with the NRC and State on a periodic basis.

6.1.4.11 Provide meteorological data and dose estimates to off-site authorities for actual releases via a dedicated individual or automated transmission.

6.1.4.12 Provide release data and dose projections based on available plant condition information and foreseeable contingencies.

6.1.4.13 Enter Recovery with notification to the State and Local off-site authorities and the NRC.

6.2 Emergency Response Activation 6.2.1 Notification Scheme In the event an emergency classification is declared procedures and systems are in place to facilitate timely activation of the site Emergency Response Organization and notification of State and Local authorities, Federal agencies and the general public within the 10 mile EPZ. This section describes the notification methods and processes used to activate on-site and off-site emergency response.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 38 of 120 6.2.1.1 Activation of the On-Site ERO When an abnormal condition is identified by the shift operating staff the duty Control Room Supervisor and Shift Manager are notified. An assessment of the safety significance of the event is performed and a determination of the emergency classification made using the Emergency Action Levels (EALs) contained in the Emergency Plan Implementing Procedures.

Upon declaring an emergency condition, the duty Shift Manager is responsible for implementation of the Emergency Plan and assumes the role of Emergency Director. The Shift Manager directs the completion of the necessary emergency notifications including the on-site Emergency Response Organization.

When directed, the Shift Emergency Communicator notifies the site Emergency Response Organization. During normal working hours, ERO notification is made using the plant public address system. During non-working hours, ERO notification is made using the ERO Pager Network and automated callout system. The detailed instructions for ERO notification are contained in the implementing procedures and associated forms and call-lists.

6.2.1.2 State and Local Authorities and NRC Under the direction of the Shift Manager (Emergency Director) the Shift Emergency Communicator will notify State and Local authorities and the NRC using commercial telephone and the FTS Emergency Notification System (ENS) respectively.

Notification procedures are contained in the Emergency Plan Implementing Procedures and associated forms.

A security threat to MNGP requires an accelerated notification to the NRC immediately after notification to state and local authorities. The goal is to initiate the accelerated call within about 15 minutes of discovery of an imminent threat or attack against the station. This implements the requirements of SA-05-02, Safeguards Advisory for Operating Power Reactors, January 26, 2005.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 39 of 120 In addition to the initial notifications, provisions are included in the Emergency Plan Implementing Procedures for follow-up notifications to State authorities which contain the following information (if it is known and appropriate):

6.2.1.2.1 Location of the incident, name and telephone number of the caller; 6.2.1.2.2 Date and time of the incident; 6.2.1.2.3 Emergency classification; 6.2.1.2.4 Type of actual or potential release and estimated release duration/impact times; 6.2.1.2.5 Estimate of quantity of radioactive material released or being released and the release point; 6.2.1.2.6 Estimates of relative quantities and concentration of noble gases, iodines and particulates; 6.2.1.2.7 Meteorological conditions; 6.2.1.2.8 Actual or projected dose rates at the site boundary and integrated dose at the site boundary; 6.2.1.2.9 Projected dose rates and integrated dose at projected peak and at about 2, 5 and 10 miles, including affected sectors; 6.2.1.2.10 Estimates of any surface radioactive contamination on-site or off-site; 6.2.1.2.11 Licensee emergency response actions underway; 6.2.1.2.12 Recommended emergency actions including protective measures; 6.2.1.2.13 Request for any needed on-site support by off-site organizations.

6.2.1.2.14 Prognosis for worsening or termination of the event based on plant information.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 40 of 120 6.2.1.3 Off-site Emergency Response Organization Notification and activation of the Off-site Emergency Response Organization is accomplished by the Shift Emergency Communicator per the site ERO notification procedures. The ERO notification procedures support the notification of select Xcel Energy/NSPM management and technical personnel who staff the Joint Information Center (JIC).

6.2.1.4 General Public The decision to notify the general public will be made by State or Local authorities based on information and recommendations provided by the MNGP. The Emergency Director is initially responsible for recommendations involving notification of the general public and is relieved of this responsibility by the Emergency Manager.

Notification of the general public is accomplished through Local Authorities use of the Public Alert and Notification System (ANS), and Emergency Alert System (EAS) auto dialing telephone systems. The State or Local authorities are responsible for activation of these systems and the information provided to the public. See Section 7.7 for additional information.

6.2.2 Emergency Action Levels (EALs)

The Emergency Action Levels (EALs) for each of the four emergency classifications are outlined in the Initiating Conditions in Annex A. These Emergency Action Levels are also identified for each Initiating Condition in the Emergency Plan Implementing Procedures. State and Local authorities are notified for all four emergency classifications and will activate the appropriate elements of their respective emergency plans based on information provided in the notification from the utility.

6.2.3 Authentication Communications made for the purpose of notifying off-site authorities of an emergency will be authenticated before the initiation of their emergency response actions. The methods used for authentication are developed and mutually agreed to by the utility and off-site authorities and are located in the off-site plans.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 41 of 120 6.3 Assessment Actions 6.3.1 Determining Magnitude of Release The magnitude of releases and release rates from normal pathways (e.g.,

Stack and Reactor Building vent) are determined using installed plant instrumentation. Installed side-stream isokinetic samplers and wide-range radiation monitors normally monitor plant effluent releases, and would be the primary method used in an emergency. Portable hand held radiation instruments are used in the event the installed monitors become inoperable.

Releases from other than normal pathways (e.g., hard pipe containment vent) will be estimated either from installed plant instrumentation or from a determination of the amount of activity available for release plus the particulars of the release path. Field measurements will be used to assist in the assessment effort by making physical measurements of dose rates and airborne, liquid and surface contamination. Field measurements are primarily the responsibility of the Radiation Protection Support Group, headquartered at the EOF, and under the direction of the Emergency Manager.

6.3.2 Off-Site Dose Projection The primary means of performing dose projections is RASCAL (Radiological Assessment System for Consequence Analysis) using the Unified RASCAL Interface(URI).

URI provides a site specific overlay on RASCAL meteorological, dispersion, and dose assessment models for all required input for emergency dose assessment as well as reports and plume graphics. Using URI, the user does not interact with any part of the original RASCAL input or output screens. Meteorological and effluent data from process monitors and meteorological instruments located at the plant site is entered into RASCAL using URI. This data is available from one central location to be used by the Dose Projection Specialist for entry into the dose projection software.

The URI code supports three modes of operation: Rapid Assessment, Detailed Assessment, and Sum Assessment.

6.3.2.1 Rapid Assessment This mode is intended for use as an aid to supporting decision-makers during the initial phases of a rapidly evolving incident. It is useful for quickly providing estimates of offsite dose projections relative to established Protective Action Guideline (PAG) exposure levels in support of initial protective action decision-making making but limits options in order to simplify the assessment.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 42 of 120 6.3.2.2 Detailed Assessment This mode provides a user-interface to produce more deliberate and comprehensive offsite dose projections than those produced by the Rapid Assessment option. It supports development of refined off-site dose projections based on changing plant status and/or meteorological conditions or field monitoring and sampling results.

6.3.2.3 Sum Assessment This mode permits the user to add archived data from previously completed dose assessments into a single report characterizing multiple concurrent releases. It is an additive process, producing a composite report and is solely for concurrent releases rather than integration of an entire event.

The URI supports expected emergency effluent dose assessment changes such as summing of multiple release/multiple source events and assessment to 50 miles.

The URI program can be run from computer stations located in the Control Room, TSC, EOF, and the Back-up EOF. Independent battery powered laptop computers are available in the TSC, EOF and Back-up EOF.

The Radiological Emergency Coordinator has the capability to estimate the total off-site population dose (manrem) received during a release. The off-site dose assessment computer will supply the projected dose rates or doses (whole body and thyroid) at various distances. Field Team radiation survey results may also be used to determine the off-site dose rates.

Population distribution charts comprised of the sectors and distances from the plant are available. The Radiological Emergency Coordinator will determine the applicable doses or dose rates in the sectors and calculate the estimated total population dose by referring to the population totals in the sectors of interest.

6.3.3 Field Radiation Surveys The task of field radiation surveillance will be accomplished by several teams under the supervision of Emergency Operations Facility (EOF) personnel. Initially, plant staff personnel will be responsible for on-site as well as off-site monitoring. As the organization is augmented, plant personnel from Prairie Island Nuclear Generating Plant (PINGP) will take over the off-site surveys. The EOF will be the central point for receipt and analysis of all off-site field monitoring data.

Survey teams will normally be composed of 2 individuals each, at least one of whom SHALL be trained in radiological field monitoring. Each team SHALL be equipped with appropriate monitoring equipment, including dose rate instruments, air sampling equipment and sample collection media and

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 43 of 120 containers. This equipment has the capability to detect and measure radioiodine concentrations in the air as low as 1x10-7 µCi/cc under field conditions. Monticello Nuclear Generating Plant monitoring teams SHALL perform necessary off-site monitoring until the PINGP off-site monitoring teams arrive and assume off-site monitoring responsibility. The estimated deployment time for monitoring teams composed of Monticello Nuclear Generating Plant personnel is 60 minutes.

6.4 Corrective Actions 6.4.1 Fire Control The Fire Brigade, which is composed entirely of plant personnel, is fully equipped, trained and capable of dealing with fire emergencies. At the direction of the Emergency Director and the Brigade Leader, the Fire Brigade will be deployed as necessary.

6.4.2 Repair and Damage Control The repair and damage control functions are assigned to the Maintenance Group. Personnel are assigned according to the skills they possess so that the team is capable of coping with the emergency situation. Repair and damage control team members are selected from available personnel.

6.5 Protective Actions 6.5.1 Protective Cover, Evacuation, Personnel Accountability In the course of an emergency situation where there is an actual or potential release of radioactive material to the environs in excess of normal operating levels, an assessment of projected exposure to persons on-site and off-site will be made. The result of this assessment will be a determining factor for implementing protective actions.

6.5.1.1 Plant Site During the course of an emergency, the REC is responsible for on-site monitoring operations. The on-site monitoring procedures contain criteria for initiating evacuations of various degrees. In all cases of elevated radiation levels or in potentially hazardous situations, non-essential personnel will be evacuated from affected areas of the plant. A plant evacuation is required at the Site Area Emergency level, radiological and environmental conditions permitting. The plant evacuation includes the owner-controlled area outside of the Protected Area.

A personnel accounting process is part of a plant or site evacuation. A system using the plant security computer and individual Security I.D. badges enables the Emergency Director to account for all personnel within the Protected Area in 30 minutes or less. Card readers are located at the TSC, Security

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 44 of 120 Access Facility and Access Control to expedite the process.

Backup methods are also available in case of a computer malfunction.

Personnel within the plant are notified of an evacuation by the plant Public Address (PA) system. A warning tone and voice instructions are part of the procedure. Time required for this process is less than 5 minutes from decision to evacuate.

Personnel outside of the plant buildings are notified by the plant evacuation siren, which is located atop the Reactor Building.

The siren initiation is simultaneous with the PA system alarm.

After the accounting process is completed, Security personnel are dispatched to ensure that all personnel in the Owner-Controlled Area outside the Protected Area have been notified. This process should be completed within 60 minutes of the start of the evacuation.

In the event of a Site Area or General Emergency, the following actions will be taken:

6.5.1.1.1 All plant employees not having emergency assignments at the site and having been cleared of radioactive contamination, will be directed to proceed to the Emergency Operations Facility, a designated off-site assembly point or sent home; 6.5.1.1.2 All working and non-working visitors and contractor and construction personnel, having been cleared of radioactive contamination, will be directed to leave the site, unless requested otherwise by the Emergency Director; 6.5.1.1.3 Persons who may be within the restricted area but outside the security fence, will be directed to proceed to the designated assembly point for accountability and radioactive contamination check before being directed to leave the site.

6.5.1.1.4 Persons who are not cleared of radioactive contamination following a plant evacuation will be decontaminated at a location on the plant site, at an off-site assembly point, or at a County Emergency Worker Monitoring and Decontamination Facility.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 45 of 120 6.5.1.2 Onsite Protective Actions for Hostile Action Events 6.5.1.2.1 Onsite Protective Actions designed for protection of personnel as described in Section 6.5.1.1 may be inappropriate for a Hostile Action Event. Alternate actions as described in NSIR/DRP-ISG-01 Section IV.F have been developed and proceduralized.

6.5.1.3 Off-Site Public Actions planned to protect the off-site public and criteria for their implementation are described in the MINNESOTA EMERGENCY OPERATIONS PLAN.

Initiation of protective actions for off-site areas is the responsibility of the State of Minnesota. Prior to the EOF being activated, the Emergency Director will make recommendations for protective actions if it is determined that they are necessary.

Recommendations will be directed to the State EOC and will come directly from the Emergency Director. If the State EOC is not activated and it is determined by MNGP that immediate protective actions should be initiated at the Local level, the recommendation will be made directly to the Local authorities.

When the EOF is activated, the protective action recommendation function will normally be transferred to the Emergency Manager.

The current issue of the Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA 400-R-92)

SHALL be used as a basis for recommendations for protective actions for the off-site public; however, more conservative protective actions based on discussions with the State may be recommended in the course of an emergency. Protective action recommendations SHALL also be consistent with the guidance of the U.S. Food and Drug Administrations, Department of Health and Human Services document titled Accidental Radioactive Contamination of Human Food and Animal Feeds: Recommendations for State and Local Agencies, August, 1998.

Tables 3, 4, 5 and 6 provide guidelines and action levels to be used in the formulation of protective action recommendations.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 46 of 120 6.5.2 Routes for Site Evacuation Evacuation of personnel from the site SHALL be accomplished in personal private vehicles and augmented by MNGP vehicles when necessary and available. Personnel are to proceed to the designated assembly area as directed by traffic control personnel.

6.5.2.1 Monticello Service Center Assembly Area -

118 Dundas Road, Monticello, Minnesota 6.5.2.2 Xcel Energy Sherburne County Generating Plant (Sherco) -

13999 Industrial Blvd, Becker, Minnesota 6.5.3 Evacuation Time Estimates (ETE) - Plume Exposure EPZ Time estimates for evacuation of the plume exposure EPZ are referenced in an appendix to the Off-site Nuclear Emergency Plan and in the Plant Emergency Plan Implementing Procedure for making off-site protective action recommendations. MNGP and the State of Minnesota use the ETE to develop pre-determined protective action recommendations.

6.5.4 Use of On-Site Protective Equipment and Supplies 6.5.4.1 Respiratory Protection and Protective Clothing In an emergency situation, the protection afforded by individual respiratory equipment must be weighed against the negative aspects of its use. In the case where a respirator may lead to additional external exposure because of the inherent difficulties of working while wearing a respirator, it may be prudent to forego the respirator in favor of a lower total dose to the individual.

In general the use of protective clothing and respiratory protection equipment will be governed by existing Radiation Protection Procedures. The Radiological Emergency Coordinator will make decisions on the use of this equipment during emergency situations.

A supply of protective clothing is stored in the TSC.

A very limited supply of this equipment is stored at each assembly point. Large supplies of respiratory equipment are stored at the plant access control area and protective clothing will normally be available in the warehouse located outside the security fence.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 47 of 120 6.5.4.2 Thyroid Prophylaxis A supply of potassium iodide (KI) will be maintained at the Technical Support Center and the Emergency Operations Facility. Each of these locations will have a minimum of 200 boxes, each of which contain a 10-day supply of KI at recommended dosages for one person. In the event that an individual is expected to receive a dose to the thyroid in excess of 25 Rem (due to radioiodine uptake), the use of KI as a blocking agent may be recommended. KI will not be made available to off-site personnel under this plan.

6.5.5 Emergency Exposure Control 6.5.5.1 Exposure Limits Although an emergency situation transcends the normal requirements of limiting exposure, there are suggested levels for exposure to be accepted in emergencies. Immediate re-entry may be necessary to account for missing personnel or to secure vital equipment. Additional exposure for this purpose must be approved by the Emergency Director based on the following criteria and the guidelines in Table 6:

6.5.5.1.1 In order to avoid restricting actions that may be necessary to save lives or protect the health and safety of the public, it SHALL be the discretion of the Emergency Director that determines the amount of exposure that will be permitted in order to perform the emergency mission. However, the dose resulting from emergency exposure should be limited to 25 REM for life-saving activities and the protection of large populations. Individuals undertaking any emergency operation in which the dose will exceed 25 REM to the whole body should do so only on a voluntary basis and with full awareness of the risk involved (EPA-400).

6.5.5.1.2 In situations where protecting valuable property is involved, the dose resulting from emergency exposure should be limited to 10 REM (EPA-400).

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 48 of 120 6.5.5.2 Exposure Control Under emergency conditions, exposure control would be implemented in accordance with the Emergency Plan Implementing Procedure A.2-401 (EMERGENCY EXPOSURE CONTROL).

Each person entering the controlled area would be required to wear a permanent record device (TLD) and a direct reading dosimeter or an electronic dosimeter.

The responsibility for maintaining exposure control for site activities rests with the Radiological Emergency Coordinator and the Radiation Protection Group. With this responsibility would be the option of establishing Access Control at alternate locations on site if the primary access control facility becomes uninhabitable. In this event, the access control function would be relocated to an alternate location within the Administration Building, Security Access Facility or the EOF. In any case, strict exposure control of all individuals passing through the access point would be maintained on a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> basis.

In order to enhance the exposure control process and to provide dosimetry for an expanded number of people, a dosimetry vendor would be called upon to expedite the shipment of extra dosimetry devices and to supply personnel and instrumentation for on-site appraisal of exposures.

It must be noted, however, that every effort will be made to keep the exposures of plant staff personnel and off-site emergency personnel below the limits for normal operations.

6.5.6 Contamination Control Measures 6.5.6.1 Plant Site The Radiation Protection Group is responsible for preventing or minimizing direct or subsequent ingestion exposure to radioactive materials deposited on the ground or other surfaces. Personnel, material and equipment will be checked at the main access control point. Decontamination will be effected when needed and when practical. Equipment which cannot be decontaminated will remain within the Radiological Controlled Area or be controlled through a conditional release process.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 49 of 120 The site guidelines for release of equipment to a clean area are no detectable licensed radioactive material above background, using the following criteria:

6.5.6.1.1 A.Use of a counting system that meets a minimum detection sensitivity of 1000 dpm/100cm2 beta/gamma provided that this equates to an MDA no higher than 20 dpm/100cm2 alpha based on 10CFR61 plant beta to alpha ratios.

6.5.6.1.2 B.Using a frisker type instrument to conduct a direct frisk survey with no reproducible counts above background provided background is

< 200 cpm.

Should any normally clean areas become contaminated in excess of 20 dpm/100 cm2 alpha or 1000 dpm/100 cm2 beta-gamma (as determined by smear tests), they SHALL be barricaded or roped and posted as a Contaminated Area, per normal plant procedures. Such areas SHALL be decontaminated as soon as practical. Access to such areas which lie outside the protected area will be controlled by plant security until properly decontaminated and cleared.

Under emergency conditions, the Radiological Emergency Coordinator has the option of implementing emergency guidelines for contamination control which are in excess of normal limits.

The Radiation Protection Group is responsible for controlling all food and water supplies at the plant during an emergency.

Whenever an evacuation due to radiological condition occurs, all food and water supplies within the evacuated area will be considered contaminated and measures will be taken to prevent their use.

Before any water or food may be consumed, the Radiation Protection Group must verify that the water/food is not contaminated and the area in which it is consumed is less than detectable using normal contamination survey methods.

Random samples of water/food SHALL be analyzed for contamination on a periodic basis.

6.5.6.2 Off-Site Areas Protective actions planned for persons in off-site areas and criteria for their implementation are described in the MINNESOTA EMERGENCY OPERATIONS PLAN.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 50 of 120 6.6 Aid to Affected Personnel In case of an accident or emergency, protection of personnel from radioactive contamination and exposure is the responsibility of the Radiation Protection Group.

The highest priority for medical treatment of radiation injuries are personnel suspected of receiving 25 rem or more of penetrating radiation to the whole body.

The order of medical treatment will be:

A. Immediate care of serious injuries B. Decontamination of personnel C. Care of other injuries D. Determining any internal contaminations through bioassays and whole body counts.

E. Follow-up treatment 6.6.1 Decontamination and First Aid 6.6.1.1 Decontamination As soon as practical, attempts SHALL be made to decontaminate individuals found to be contaminated. First aid or removal from a hazardous environment, however, SHALL take precedence over decontamination actions. Precautions will be taken to prevent the spread of contamination to other parts of the body. Particular attention will be paid to open wounds in order to prevent internal contamination.

Contamination monitoring will be accomplished using thin-window GM pancake-type probes for maximum sensitivity.

Each assembly area where decontamination may be conducted is equipped with one or more of these instruments.

The primary decontamination facility is located in the plant Access Control Area. Two showers and a large sink, plus various other supplies are provided for this express purpose. If the primary facility is not accessible, decontamination kits are also provided in the emergency supplies for the EOF and off-site Assembly Points. Decontamination operations at an Assembly Point would be on a small scale due to limited resources. If necessary, contaminated personnel at an Assembly Point will be placed in protective clothing and transported to an adequate facility.

The decontamination kits contain the equipment and materials necessary for small scale personnel decontamination operations. Decontamination materials are made available for use at Access Control, EOF, and Off-Site Assembly Points to deal with various skin contamination.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 51 of 120 The waste generated in decontamination operations will be retained for proper disposal.

6.6.1.2 First Aid Fire Brigade personnel receive first aid training (Red Cross Multi-Media or equivalent) on a periodic basis. The level of skills is sufficient for the time it takes for off-site medical personnel to arrive.

6.6.2 Medical Transportation Arrangements for transportation of radiologically contaminated casualties have been made with local hospitals Ambulance Service. The personnel at the service receive radiological training from MNGP Training Staff members on a regular basis. The procedure for handling contaminated personnel includes protective measures for equipment as well as the ambulance service personnel.

6.6.3 Medical Treatment The Monticello Nuclear Generating Plant has made arrangements for medical services with a local hospital located approximately five miles from the plant in Monticello. In addition, this hospital has established a transfer agreement with North Memorial Hospital for backup assistance should it be necessary for either radiological support or to care for large numbers of patients.

Injured personnel who must be moved to the local hospital while in a contaminated condition SHALL be accompanied by personnel who are qualified in radiological monitoring who will stay in attendance and maintain radiological control until decontamination is satisfactorily completed.

The person escorting the patient will take along survey instruments. In addition, TLD badges, pocket dosimeters, survey instruments and other supplies and protective equipment for hospital employees are available at the hospital.

The patient will be put in a separate room and this will be considered a Contaminated Area. Upon release of the patient from the room, it SHALL be sealed until decontaminated and cleared by Radiation Protection. All hospital equipment in the room will be surveyed and decontaminated to site guidelines for release of equipment to a clean area before being released.

If deemed necessary patients may be sent to the North Memorial Hospital for radiological studies, or other reasons. This arrangement is formalized in a transfer agreement between these two hospitals and outlined in the Off-site Nuclear Emergency Plan, Section entitled EMERGENCY MEDICAL PLAN.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 52 of 120 Table 3 EPA GUIDELINES FOR RECOMMENDED PROTECTIVE ACTIONS (WHOLE BODY AND THYROID DOSE FROM EXPOSURE TO A GASEOUS PLUME)

Projected Does (REM) to the Population Recommended Actions Comments Whole Body <1 (TEDE) No planned protective actions.

Thyroid <5 (CDE) Monitor environmental radiation levels.

Skin <50 (CDE)

Whole Body >1 (TEDE) Evacuate unless constraints make it Shelter if evacuation Thyroid >5 (CDE) impractical. Monitor environmental were not immediately Skin >50 (CDE) radiation levels. Control access. possible.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 53 of 120 Table 4 RECOMMENDED DERIVED INTERVENTION LEVEL (DIL) OR CRITERION FOR EACH RADIONUCLIDE GROUP (A), (B)

All Components of the Diet Radionuclide Group (Bg/kg) (pci/kg)

Sr-90 160 4300 I-131 170 4600 Cs-134 &Cs-137 1200 32,000 Pu-238 + Pu-239 + Am-241 2 54 Ru-103 + Ru-106(c) C3 + C6 < 1 C3 + C6 <1 6800 450 180,000 12,000 Notes:

(a) The DIL for each radionuclide group (except for Ru-103 + Ru-106) is applied independently. Each DIL applies to the sum of the concentrations of the radionuclides in the group at the time of measurement.

(b) Applicable to foods as prepared for consumption. For dried or concentrated products such as powdered milk or concentrated juices, adjust by a factor appropriate to reconstitution, and assume the reconstitution water is not contaminated. For spices, which are consumed in very small quantities, use a dilution factor of 10.

(c) Due to the large difference in DILs for Ru-103 and Ru-106, the individual concentrations of Ru-103 and Ru-106 are divided by their respective DILs and then summed. The sum must be less than one. C3 and C6 are the concentrations, at the time of measurement, for Ru-103 and Ru-106, respectively.

(d) Reference U.S. Food and Drug Administrations, Department of Health and Human Services document titled Accidental Radioactive Contamination of Human Food and Animal Feeds: Recommendations for State and Local Agencies, August 1998, for further discussion of this table.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 54 of 120 Table 5 RECOMMENDED PROTECTIVE ACTIONS Accident Phase Exposure Pathway Example of Actions to be Recommended EARLY Inhalation of gases, Evacuation, shelter, Access Control, (EMERGENCY) radioiodine or respiratory protection, prophylaxis (thyroid PHASE (NOTE 1) particulate protection)

(0 to 4 days)* Direct whole body Evacuation, shelter, Access Control exposure INTERMEDIATE Ingestion of Milk Take cows off pasture, prevent cows from PHASE (NOTE 2) drinking surface water, discard contaminated milk, or divert to stored products such as cheese Ingestion of fruits and Wash all produce, or impound produce, vegetables delay harvest until approved, substitute uncontaminated produce Ingestion of water Cut off contaminated supplies, substitute from other sources, filter, demineralize (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to 30 Whole body exposure Relocation, decontamination, Access Control days)* an inhalation LATE PHASE Ingestion of food and Decontamination, condemnation, or (NOTE 3) water contaminated destruction of food, deep plowing, from the soil either by condemnation or alternate use of land resuspension or uptake through roots (over 30 days) Whole body exposure Relocation, Access Control, from deposition decontamination, fixing of contamination, material or inhalation deep plowing of resuspended material NOTE 1 Early Phase - Time period from the onset of major release and subsequent plume exposure periods up to 4 days.

NOTE 2 Intermediate Phase - Time period of moderate continuous release with plume exposure and contamination of environment.

NOTE 3 Late Phase Recovery period

• Typical Pst - Accident Time Periods

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 55 of 120 Table 6 EMERGENCY EXPOSURE GUIDELINES EXPOSURE LIMIT1 EMERGENCY COMMENTS 5 REM (TEDE)(2)(3) All emergency activities This dose limit applies when a lower dose is not practicable through application of ALARA practices.

(2)(3) 10 REM (TEDE) Protection of valuable This dose limit applies when a lower property dose is not practicable through application of ALARA practices.

(2)(3) 25 REM (TEDE) Life saving or protection This dose limit applies when a lower of large populations dose is not practicable through application of ALARA practices.

(2)(3)

> 25 REM (TEDE) Life saving or protection Doses in excess of 25 REM should be of large populations on a voluntary basis to persons fully aware of the risks involved.

NOTE 1: Dose limits for emergency workers and activities are based on EPA 400-R-92-001, May 1992.

NOTE 2: Sum of external effective dose equivalent and committed effective dose equivalent to non-pregnant adults from external exposure and intake during the duration of an emergency.

NOTE 3: Exposure to the lens of the eye should be limited to 3 times the value listed and doses to the skin and extremities should be limited to 10 times the value listed.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 56 of 120 7.0 EMERGENCY FACILITIES AND EQUIPMENT 7.1 Emergency Response Centers Plan views of the Technical Support Center, Back-up Operations Support Center, Emergency Operations Facility (EOF) and Operations Support Center (OSC) as described below, are shown in Figures 13.5, 13.6, and 13.8.

7.1.1 Technical Support Center The Technical Support Center (TSC) serves as a center outside of the Control Room that acts in support of the command and control function.

Plant status and diagnostic information will be available at this location for use by technical and management personnel in support of reactor command and control functions. The Emergency Director resides in the TSC when activated.

The TSC is located on the first level of the Plant Engineering Building (PEB). The TSC has approximately 5700 sq ft of floor space and is within the controlled ventilation boundary of the Emergency Ventilation System (EVS). This system is independent of the Emergency Filtration Train System (EFT) which serves the Control Room.

An emergency equipment locker located in the TSC contains protective, anti-contamination clothing for TSC personnel.

7.1.2 Operations Support Center The Operational Support Center (OSC) serves as the facility to which Mechanical, Electrical and I&C maintenance personnel report in an emergency. In addition to maintenance personnel, off-duty Operations personnel also report to the OSC. The OSC functions as the staging area from which emergency teams are dispatched, by the TSC or Control Room, to undertake emergency corrective actions.

The primary OSC is located on the first and second levels of the Plant Administration Building within the Outage Control Center, PAB2 conference room, I&C offices, Operations Department Break Room and Plant Lunch Room. The primary OSC is a dedicated facility which serves as a maintenance support area and conference room during normal operation.

The primary OSC is outside a filtered ventilation boundary.

The Back-up OSC is located within the TSC shell structure in the east end of the TSC. The Back-up OSC is located within the EVS controlled ventilation boundary. The Back-up OSC is activated if the primary OSC becomes uninhabitable or as other circumstances dictate.

Emergency equipment lockers, located in the primary OSC, contain protective anti-contamination clothing for OSC emergency team personnel.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 57 of 120 7.1.3 Emergency Operations Facility In the event of an Alert, Site Area Emergency, or a General Emergency, the Emergency Operations Facility (EOF) will be activated. The EOF serves as a center for evaluation and coordination of off-site activities related to the emergency. Additionally, the facility will be the base of operations for environmental surveillance and communications with supporting operations.

The Emergency Manager is in charge of the EOF.

The EOF is located within the site Training Center, 1 mile south by southeast of the plant (approximately 5 minutes driving time). It was designed primarily as a training facility and also in accordance with NUREG 0696. In the event the EOF is needed, it is capable of prompt conversion from a training facility to an Emergency Response Facility.

The EOF will be activated and staffed by Site ERO personnel. On activation, the first personnel will arrive within 30 minutes, with complete activation in approximately one hour. The Emergency Plan Implementing Procedures describe the functions, equipment and personnel responsibilities more fully.

The EOF will also provide office space, trailer space and communications hook-ups for NRC Incident Response Teams, vendors, and technical support contractors. Media personnel may be assembled in the Training Center Multi-Purpose Room or other designated waiting area. The JIC will be the main point of contact for the media to obtain information regarding the emergency.

The EOF has facilities and capabilities for:

Management of overall licensee emergency response, Coordination of radiological and environmental assessment, Determination of recommended public protective actions, Notification of offsite agencies, 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, Obtaining and displaying key plant data and radiological information, and Analyzing plant technical information and providing technical briefings on event conditions and prognosis to licensee staff and offsite agency responders.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 58 of 120 7.1.4 Alternative Facilities In the case of Hostile Action Events activation of onsite Emergency Response Facilities may be unsafe. Alternative Response Facilities have been developed to allow onsite ERO personnel to muster is a location near the site but away from any onsite hostile activity. The alternative facility selected for Monticello is the EOF/Training Building described in Section 7.1.3. This facility is accessible in the event of an onsite Hostile Action and provides the ability to perform the following functions:

Communication with the Control Room and onsite Security Forces Notification of offsite Emergency Response Organizations Engineering Assessment Activities including damage control team preparation and planning.

7.1.5 Back-up EOF In the event the primary EOF becomes uninhabitable during a real emergency, the functions of the EOF would be transferred to the Back-up EOF.

The Back-up EOF is located at the Xcel Energy corporate office in downtown Minneapolis, 45 miles southeast of plant.

The Back-up EOF has facilities and capabilities for:

Management of overall licensee emergency response, Coordination of radiological and environmental assessment Determination of recommended public protective actions Notification of offsite agencies Coordination of event, plant, and response information provided to public information staff for dissemination to the media and public, Coordination of emergency response activities with Federal, State, and local agencies, Obtaining and displaying key plant data and radiological information, and Analyzing plant technical information and providing technical briefings on event conditions and prognosis to licensee staff and offsite agency responders.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 59 of 120 7.1.6 Assembly Points In the event of a plant evacuation, the On-Site Assembly Point (or an Off-Site Assembly Point, as appropriate) will be activated. The function of the assembly point is to provide a center for personnel accountability and radiological contamination screening along with any other immediately necessary actions.

The On-Site Assembly Point is located approximately 1000 feet south of the plant, within the Site Administration Building . The location of the Off-Site Assembly Point is dependent upon the nature of the emergency conditions.

Its location will be announced over the public address system when announcement of evacuation is made.

7.1.7 Access Control The Primary Access Control Point is located in the lower level of the Plant Administration Building. This is the primary entry/exit point from the Radiologically Controlled Area.

An alternate Access Control Point will be located in the Administration Building, Security Access Facility, or at a point designated by the ED, if the Primary Access Control Point becomes uninhabitable due to high radiation or high airborne levels.

7.1.8 Sign-in Boards for ERO Assignments The boards are used to make speedy personnel duty assignments during the initial stage of an emergency, to insure that qualified personnel fill the positions in the ERO, and insure that the more important positions in the ERO are filled first.

The board consists of a layout of the Emergency Response Organization.

Under the board is a list of the individuals who are qualified to fill that position.

The boards are located in each facility. Personnel who have key positions within those facilities have the responsibility of checking the boards when it is announced that ERO personnel are to report to their duty stations. The boards are reviewed and updated quarterly.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 60 of 120 7.2 Communications Systems 7.2.1 Normal On-Site Communications Normal on-site communications is provided by the plant telephone system which has a maximum capacity of 36,000 lines and 12,000 trunks. The telephone system processing equipment located in the Plant Administration Building telephone room and the Plant Engineering Building communication room is powered by UPS/battery backed non-1E instrument buses.

Portions of the system are also provided with an alternative power source from lighting panels backed by the non-1E Diesel Generator. Telephone system components at remote locations are powered from lighting panels backed by stand-alone UPSs.

The plant PA System may also be used for in-plant communications. The PA System is powered by normal plant power, backed up by uninterruptible power.

Portable radios are used for communications between individuals and base stations located in the Control Room, TSC, EOF, and Security Building.

7.2.2 Normal Off-Site Communications Normal off-site communications is provided by the following telephone circuits:

7.2.2.1 46 two way ISDN trunks (TDS Telecom) 7.2.2.2 46 two way ISDN trunks to Minneapolis (Dial 8 access) 7.2.2.3 23 ISDN trunks to the Monticello Training Center 7.2.3 Alternate Off-Site Communications 7.2.3.1 Radio Receiver/Transmitter An alternate method for communications is provided by an AC powered radio transceiver with control consoles located in the TSC, Control Room and EOF.

From either console, communications may be established with the EOF, Sherburne and Wright County Sheriffs, Plant Security, Operations and Radiation Protection portable radios, and the Xcel Energy System Control Center.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 61 of 120 7.2.3.2 Emergency Response Organization Pager Network An ERO Pager Network is utilized for notification of site Emergency Response Organization members. The system consists of a commercial pager network with independent, transmitters. Transmitters are located in various areas from St.

Cloud to Red Wing. Each pager group has a primary and back-up telephone number which are from separate trunk lines, which further increases accessibility. Each transmitter is installed with a back-up power supply (battery or diesel).

7.2.3.3 Direct Dedicated Telephones Direct dedicated telephones as described below are diagrammed in Figure 13.7.

7.2.3.3.1 Three dedicated lines exist between the TSC and the EOF.

7.2.3.3.2 Site FTS System - this dedicated telephone network connects the plant site with the NRC Operations Center. Site extensions are located in the Control Room, TSC, Duty Shift Manager Office and Site NRC Office. Site extensions include ENS, HPN, and various other extensions connecting to the NRC Operations Center.

7.2.3.3.3 EOF FTS System - this dedicated telephone network connects the EOF with the NRC Operations Center. EOF extensions are located in the EOF and adjoining classrooms.

EOF extensions include ENS, HPN and various other extensions connecting to the NRC Operations Center.

7.2.3.3.4 An automatic-ringing line exists between the TSC and the State EOC.

7.2.3.3.5 Two dedicated lines exists between the EOF and the Back-up EOF.

7.2.3.3.6 An auto ring line exists between the EOF and the State EOC.

7.2.3.3.7 Four dedicated Federal Telephone System (FTS) lines exists in both the EOF and TSC to connect the NRC incident response team with the NRC Operations Center.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 62 of 120 7.2.3.3.8 Two dedicated cellular phones providing back-up communications for Field Teams.

7.2.3.4 Radio Links Radio links exist for communications between the Minnesota Division of Homeland Security and Emergency Management and the Control Room, TSC , EOF, and Back-up EOF at the plant site.

7.2.3.5 Emergency Response Data System ERDS is a direct near real-time electronic data link between the plants on-site computer system and the NRC Operations Center that provides for the automated transmission of a limited data set of selected parameters. The ERDS supplements the existing voice transmission over the FTS-ENS.

7.2.4 Emergency Communications Matrix Tables 7 and 8 depict the different communications media by which emergency centers pass information, and give primary and alternate contacts for centers where appropriate.

7.2.5 Testing Testing of the various communications links is accomplished in two ways.

7.2.5.1 Each month a communications test is conducted in accordance with a surveillance procedure (1225).

7.2.5.2 Drills involving communications equipment are conducted on a regular basis to assure operability.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 63 of 120 7.3 Assessment Facilities The plant instrumentation and monitors perform indicating, recording and protective functions. The regulating systems provide the ability to regulate the plant safely from shutdown to full power and to monitor and maintain key variables such as reactor power, flow, temperature and radioactivity levels within predetermined safe limits during both steady state and plant transients. Plant instrumentation and control systems also provide means to cope with abnormal operating conditions. The control and display of information of these various systems are centralized in the main Control Room. This instrumentation would provide the basis for initiation of protective systems.

7.3.1 On-Site Systems and Equipment 7.3.1.1 Safety Parameter Display System (SPDS)

The Safety Parameter Display System (SPDS) is designed to provide plant operators with a concise display of critical plant parameters as an aid in implementation of the plant Emergency Operating Procedures (EOPs). The Monticello SPDS System is based on plant Emergency Operating Procedures (EOPs) and General Electric (GE) generic Emergency Response Information System (ERIS). SPDS displays are available in the Work Execution Center Office, Duty Shift Manager Office, Technical Support Center (TSC), Emergency Operations Facility (EOF) and throughout the Control Room.

SPDS information is presented to the operator via color graphic computer systems. Operator interface to the color graphics computer system is via keyboards, color monitors, and printer/plotters. Input data from plant sensors is gathered via the Data Acquisition System (DAS) and independently transmitted to the computer systems. Identical DAS data is maintained on both process computers for purposes of redundancy in the event one computer fails. Signals are processed through various algorithms such as signal range checking, limit checking, averaging, logical manipulations and validation. The results are then transmitted to the color graphic display computers where the data is transformed into the SPDS displays.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 64 of 120 The SPDS displays can be classified into two categories, Top-Level and Lower-Level displays. In general, Top-Level displays provide information on several control parameters, both current and historical. The Lower-Level displays are designed to augment the Top-Level displays by providing more detail or background on specific items contained in the Top-Level displays. The overall SPDS display structure is as follows:

7.3.1.1.1 Top Level SPDS Displays

1. Critical Plant Variables The CPV display provides the status of all critical plant parameters including RPV level, pressure, reactor power, drywell pressure and temperature, torus pressure, temperature and level, and radioactive release rate information.

2. Reactor Pressure Vessel Control The RPV display provides detailed status and control parameter information including RPV water level, RPV pressure, reactor power and RPV temperature.

3. Containment Control This display provides specific information regarding containment control including drywell pressure and temperature and torus water level, temperature and pressure.

4. Radiation Control The Radiation Monitor displays provide detailed information on Reactor/Turbine and Radwaste Building area radiation monitors and plant process monitors.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 65 of 120 7.3.1.1.2 Lower-Level SPDS Displays

1. Trend Plot Displays Trend plot displays support the RPV and Containment Control displays by providing detailed parameter trend plots of those displays.

2. Two Dimensional Plot Displays The 2-D plot displays provide plant specific two dimensional limits in an x-y format and are identical to the curves used in the EOPs.

3. Validation Displays The Validation displays are used to display how a parameter is determined.

In addition, Menu Displays are provided to assist the user in selection of individual displays from applicable display types.

SPDS menus include, Reactor Menu, Trend Plot Menu, 2-D Menu and Validation Menu.

The SPDS displays are designed with common display characteristics for ease of understanding. Data is displayed according to defined conventions for use of color, shape, format, alarm and validation processing.

A display color coding scheme is used to aid the operator in prioritizing information and recognizing off-normal conditions.

In addition, displays provide indication of both validated parameter and process limit status. Status windows are also provided to alert the operator when approaching or exceeding a critical parameter limit (EOP entry condition).

Two SPDS Terminals are available in the Technical Support Center for use during emergency conditions and for system development during normal operation. One terminal is utilized by the Radiation Protection Group for display of plant radiological conditions and process monitor status. The second terminal is located in the Technical Engineering area of the TSC and is used for plant parameter analysis and trending under the direction of the Engineering Group Leader.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 66 of 120 7.3.1.2 Geophysical Phenomena Monitors 7.3.1.2.1 Seismic Monitoring System The Seismic Monitoring System is made up of three independent sensing systems: the peak-recording accelerometers, the seismic-switch-activated annunciator system and the accelerograph recording system. The peak-recording accelerometers and the sensors for the accelerograph system (force-balance accelerometers) are located in the drywell, on the refueling floor and in the seismic shed (located to the north of the number 2 warehouse). Seismic switches for the annunciator system are also located in the seismic shed. The seismic trigger which initiates the accelerograph is located in the number 12 125 VDC Battery Room.

Each of the peak-recording accelerometers is a self-contained unit. The sensing mechanism is a permanent magnet stylus attached to the end of a torsional accelerometer. Low frequency accelerations cause the magnet to erase pre-recorded lines on a small (approximately 1/4 inch square) piece of magnetic tape. Each peak recording accelerometer unit contains three torsional accelerometers and magnetic tapes - one each for longitudinal, transverse, and vertical accelerations.

The magnetic tapes can be removed from the accelerometers, developed and evaluated by plant personnel for a rapid determination of the severity of a seismic disturbance.

The Control Room annunciator 6-C-08 (EARTHQUAKE) is initiated by either seismic switch of the Seismic Annunciator System or the seismic trigger of the accelerograph recording system. In addition to this, each of the seismic switches has its own alarm. The first of these is the alarm 6-C-13 (OPERATIONAL BASIS EARTHQUAKE (OBE))

which annunciates when its switch senses an acceleration > .03 g. The second alarm is the 6-C-18 (DESIGN BASIS EARTHQUAKE

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 67 of 120 (DBE)), which annunciates when its switch senses an acceleration >.06g. These two switches do not activate the accelerograph recording system.

The accelerograph recording system gives a more detailed record of a disturbance than the peak recording accelerometers - it records accelerations in three directions (longitudinal, transverse, and vertical, as above) from each of the three sensor locations on magnetic tape cartridges located in the Control Room. This system has five major components: a trigger, three sensors, and the recording and control units. When the trigger (located in the No. 12 125 VDC Battery Room) senses the beginning of a seismic disturbance, (an acceleration > .01 g), it will start the accelerograph recorders and also triggers the earthquake event alarm 6-C-08 in the Control Room.

A summary of the Seismic Monitoring Equipment is provided in Table 9.

7.3.1.2.2 Meteorological Monitoring System The purpose of the meteorological monitoring system is to monitor and determine atmospheric dilution and dispersion parameters for the Monticello Plant site.

The meteorological monitoring system consists of two instrumented towers, associated signal transmission and processing equipment, two AC power sources, and battery backup power supplies.

The primary meteorological tower facility is located on the plant site southeast of the Reactor Building. It consists of a guyed 100m tower with six instrumentation booms located in pairs at 10m, 43m, and 100m.

At each height one boom is reserved for A-train instrumentation and the other boom is reserved for B-train instrumentation. Two independent elevator systems are installed on the tower allowing each division of equipment to operate independently so maintenance may be

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 68 of 120 performed without taking the full system out of service.

Instrumentation consists of wind speed and direction sensors along with aspirated temperature sensors. One sensor of each type is mounted at each location for each train for a total of six instruments of each type. Two precipitation monitors, one for each train, are located at the base of the tower. Data is communicated wirelessly from the tower to a receiver inside the Plant Administration Building.

Instrumentation is AC powered and is run on UPS backed power designed to last for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

A second meteorological tower is located approximately 3/4 mile from the Reactor Building and is adjacent to the EOF. This tower is a 30 meter self-supported tower with an instrument elevator which lifts single train wind speed and wind direction sensor to the 22 meter elevation. Signal transmission lines from the wind sensor to the associated junction box are surge protected and the tower is grounded.

Signals from the tower are fed to an instrument processor rack located inside the EOF and provide the third source of wind speed and wind direction data.

Meteorological data from the 100 meter tower is collected every 5 seconds, averaged every minute and 15 minutes, and stored in raw data files. The data is available on the Process Computer System in the Plant Control Room, TSC, and the EOF.

Meteorological data from the 30 meter tower is collected every second and averaged every minute and 15 minutes. The data is available on the Process Computer System in the Plant Control Room, TSC, and the EOF.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 69 of 120 Some meteorological data is provided as digital averages in the Control Room. Displays of current and 15 minute running average meteorological data from both sensor trains on the 100 meter tower and 30 meter tower are simultaneously available on computer terminals in both the TSC and EOF.

The Meteorological Data Collection software includes data quality control tests which flag questionable or bad data to the user. Plant Chemistry personnel access hourly averaged data on a daily basis and review the data for reasonableness in accordance with plant Chemistry Department procedures. Plant I&C personnel perform a monthly surveillance test on the 100 meter tower and annual instrument calibrations on both towers in accordance with the plant surveillance program. System problems are corrected through the plant Work Order process.

In addition to the site meteorological monitoring system, regional meteorological data is available through the National Weather Service by commercial telephone. National Oceanic and Atmospheric Administration (NOAA)

Weather Alert radios are also installed in the Control Room, TSC and EOF to provide warning of adverse weather.

7.3.1.3 Radiological Monitors 7.3.1.3.1 Process Radiation Monitoring System The function of the process radiation monitoring system is to provide a continuous monitoring and readout of the radioactivity of all process lines and vents that can release radioactivity directly to the environs. In addition, this system also continuously measures, indicates and records the radioactivity concentration levels of in-plant process streams and vents. A list of the plant process monitors is provided in Table 11.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 70 of 120 7.3.1.3.2 Area Radiation Monitoring System A list of the Area Radiation Monitors is provided in Table 12.

The functions of the Area Radiation Monitoring System are:

1. Warn of excessive gamma radiation levels in areas where nuclear fuel is stored or handled.

2. Provide operating personnel with a continuous indication in the main Control Room of gamma radiation levels at selected locations within the various plant buildings.

3. Contribute supervisory information to the Control Room so that correct decisions may be made with respect to deployment of personnel in the event of a radiation incident.

4. Assist in the detection of unauthorized or inadvertent movement of radioactive material in the plant including the radwaste area.

5. Supplement other systems including Process Radiation Monitoring, Leak Detection, etc., in detecting abnormal migrations of radioactive material in or from the process streams.

6. Provide local alarms at key points where a substantial change in radiation level might be of immediate importance to personnel frequenting the area.

7. Maintain a permanent record of the radiation levels in the areas being monitored.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 71 of 120 7.3.1.4 Process Monitors 7.3.1.4.1 There are many instruments in the plant which may be used to assess the many potential conditions that the plant may experience.

These instruments may be used individually or in groups of indicators to assess a certain situation. There is no specific indication that in itself can correctly identify an emergency condition 100% of the time. Therefore, the operators must utilize their general knowledge along with the guidelines provided in Emergency Plan Implementing Procedure A.2-101 (CLASSIFICATION OF EMERGENCIES) to analyze process indications. Specific process monitors of reactor systems which are used during various plant emergencies are discussed in Section 4.0, Emergency Classification System. In addition, a summary of the types of measured parameters in the Control Room is provided in Table 13, Instruments Available for Monitoring Major Systems.

7.3.1.4.2 Reactor Protection System The Reactor Protection System is designed to prevent, in conjunction with the Primary Containment and Containment Isolation Systems, the release of radioactive materials in excess of the guidelines of 10CFR50.67, and to prevent fuel damage as a consequence of single operator error or single equipment failure.

When specified limits have been exceeded, the Reactor Protection System initiates a reactor scram.

7.3.1.4.3 Primary Containment Isolation System The purpose of the Primary Containment Isolation System is to prevent the release of radioactive materials in excess of the guidelines of 10CFR50.67 by isolating the reactor vessel and closing containment where required following an accident.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 72 of 120 7.3.1.5 Containment Radiation Monitor There are two containment radiation monitors which have ion chamber detectors and a response range of 100 to 108 R/hr.

The detectors are located at approximately the midline of the drywell and separated to enhance the redundant feature of the system. As safety monitors, they satisfy 1E requirements and are qualified under LOCA conditions to IEEE 323-1974. The detectors are encased in steel to protect them from containment sprays and high temperatures.

In the event of a large release of radioactivity to the containment atmosphere, the containment monitors can be used to estimate the amount of activity available for release from containment.

7.3.1.6 Fire Detection Devices 7.3.1.6.1 Early Warning Fire Detectors Fire detectors (smoke, heat, and flame) are located in most areas of the plant. The detectors in each area initiate an alarm locally and in the Control Room upon detecting either combustion or a failure in the detector system.

Detectors in certain areas of the plant will activate their respective sprinkler systems.

7.3.1.6.2 HAD (Heat Activated Device)

The HAD System utilizes the heat from a fire to operate a pneumatic system to either sound alarms or automatically initiate a deluge or sprinkler system. The HAD System is used in conjunction with the building siding deluge, the cooling tower deluges, the recirculation MG set deluges, and the lube oil reservoir deluge.

These systems can also be operated locally.

7.3.1.6.3 LHD (Linear Heat Detection)

The LHD utilizes a Protectowire linear heat fire detection system and is capable of initiating an alarm once its rated activation temperature is reached.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 73 of 120 7.3.1.7 Post-Accident Sample System The Post-Accident Sample System (PASS) was designed to provide a means of assessing core damage during and after a loss-of-coolant accident. The facility is located outside of secondary containment to enhance accessibility. Local shielding and area radiation monitoring are also provided to protect the operator.

The capabilities of the system include:

7.3.1.7.1 Large and small volume liquid coolant samples from jet pumps A and B and RHR pumps A and B;

7.3.1.7.2 Gas samples from drywell and torus.

7.3.2 Facilities and Equipment for Off-Site Monitoring 7.3.2.1 Geophysical Phenomena Monitors In the event that a seismic disturbance is indicated by on-site detection equipment, plant procedures require the operator to confirm the validity and intensity of the disturbance by contacting an off-site source. The list of off-site sources includes:

7.3.2.1.1 Prairie Island Nuclear Plant (Located near Red Wing, Minnesota);

7.3.2.1.2 National Earthquake Information Service (Golden, Colorado) 7.3.2.2 Radiological Monitors The Monticello off-site radiation monitoring program includes TLD stations which are located in the general areas of the site boundary, in an outer ring, in special interest areas, and in control stations, many miles from the plant. Also included in the program is a group of air monitoring stations positioned on the site boundary and in the city of Monticello. The program, known as the Radiological Environmental Monitoring Program, is administered at the Site.

7.3.2.3 Laboratory Facilities In the event that the lab facilities on-site become unusable or overloaded, back-up facilities are available. The chemistry labs at Prairie Island are available for chemical analysis work. For radiochemical analysis, the back-up countroom at the EOF is equipped with a computer-based multi-channel analyzer and gross beta counting equipment. The counting facilities at Prairie Island are also available, if needed.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 74 of 120 7.4 Protective Facilities and Equipment 7.4.1 Assembly Points In the event of a Site Area or General Emergency, the Site Administration Building (SAB) is designated as the assembly point for evacuated personnel. The SAB is located approximately 1000 feet south of the plant.

This structure offers cover from fallout, but does not have special ventilation or shielding properties. It has the capacity to handle the number of people expected to report there. An emergency equipment locker at the assembly point contains a supply of emergency equipment and protective clothing.

The Receiving Warehouse has been identified as an alternate assembly point for specific events. This facility may be used to relocate and assemble and account for non-essential personnel during security threats.

7.4.2 Emergency Operations Facility (EOF)

The EOF is located approximately 1 mile southeast of the plant and is activated at the Alert, Site Area or General Emergency classification. The EOF is contained within the site Training Center which houses the Training Staff, administrative offices and Control Room Simulator.

The EOF was designed and constructed IAW NUREG 0696 and is a concrete structure which contains sufficient shielding (for the EOF section of the building) to provide a protection factor of 5. The EOF portion of the building is served by two independent off-site power sources for reliability.

The building ventilation system includes an emergency mode which provides filtered air to pressurize the EOF through a high efficiency particulate absolute (HEPA) filtration system. The layout of the building entrances and exits were also designed to facilitate emergency operations.

Radiological monitoring of the EOF is provided by air sampling and Dosimeter Area Radiation Monitor (DARM) which may be supplemented with radiological surveys by the EOF Radiation Protection Staff.

Extensive communications equipment is installed to provide primary and back-up methods of communicating with plant Emergency Response Facilities, utility headquarters, off-site agencies and utility Field Monitoring teams. Critical plant parameter data is available in the EOF through the plant Safety Parameter Display System (SPDS).

Meteorological data is provided by the ERIS system. Off site dose projection is provided by RASCAL.

7.4.3 Back-up EOF The Back-up EOF is located at the Xcel Energy corporate office in downtown Minneapolis, 45 miles southeast of the plant.

In the event the primary EOF became uninhabitable during a real emergency, the functions of the EOF would be transferred to the Back-up EOF.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 75 of 120 Extensive communications equipment is installed to provide primary and back-up methods of communicating with plant emergency Response Facilities, off-site agencies and utility Field Monitoring teams. Critical plant parameter data is available in the Back-up EOF through the plant Safety Parameter Display System (SPDS). Meteorological data is provided and displayed by the ERIS system. Off site dose projection is provided by RASCAL.

7.4.4 Emergency Kits Table 14 lists the location and general contents of emergency kits to be used in response to an emergency at the Monticello Plant.

7.5 First Aid and Medical Supplies 7.5.1 First Aid Center A decon shower and first aid supplies are located in the Main Access Control area in the lower level of the Plant Administration Building.

Immediate and temporary care may be given to a victim in this area. If the injury involves contamination that cannot be removed without causing further injury, steps will be taken to minimize the spread of contamination until medical assistance arrives or until the victim has been transported to the hospital.

7.5.2 First Aid Kits First Aid kits are located in the Fire Brigade Room at Main Access Control, Work Execution Center and various other areas on the plant site.

Stretchers and shock blankets are located on each level of the Containment Building, Turbine Building and Main Access Control.

7.6 Damage Control Equipment and Supplies 7.6.1 Firefighting Equipment A full line of fire fighting equipment and supplies is available for damage control operations. The equipment is stored in the Fire Brigade Room adjacent to the Main Access Control area in addition to various areas within the plant for easy access and quick response to fires.

7.6.2 Spill and Leak Control Equipment Spill and leak control equipment includes electric and gas driven pumps, various patching supplies and welding equipment. This equipment is available in the warehouse along with machine shop facilities for response to a wide variety of problems.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 76 of 120 7.7 Public Alert and Notification System (ANS)

Within the Plume Exposure Emergency Planning Zone (EPZ) there exists provisions for alerting and providing notification to the public. The state and local authorities are responsible for activation of this system.

The ANS system consists of a primary and backup activation and monitoring of outdoor warning sirens, primary and backup initiation of the Emergency Alert System (EAS), primary and backup initiation of the Integrated Public Alert and Warning System (IPAWS), county auto-dial notification systems for special populations and backup routes by siren contour and by subarea.

Emergency Planning Visitor Guides are available for distribution in all recreational areas to advise transient populations of the action they should take in the event of an accident at the MNGP. Annual Emergency Planning Guides are distributed to all residential and business addresses within the 10-mile EPZ and contain information for the public to use in the event they hear sirens or EAS Messages over the local radio system.

Activation of the ANS begins with a protective action recommendation (PAR) of evacuation or sheltering by the MNGP Emergency Director/Manager. The Minnesota Division of Homeland Security and Emergency Management (HSEM) is responsible for coordinating the recommendation and making it a decision with appropriate approvals Sherburne and Wright Counties and assigning siren activation times and EAS activation times. The Sherburne and Wright County Sheriff's Offices are responsible for activation of the outdoor warning sirens.

The system consists of 106 sirens. The 106 sirens provide 100% coverage of the populated area within the 10-mile EPZ. In the event that a siren is not working, effective areas are alerted through the use of emergency warning vehicles operated by local sheriff departments in accordance with the Sherburne and Wright Counties' plans.

Additional, detailed information about the ANS system, including system design, siren coverage analysis, testing schedules, and an evaluation of the current system is found in the Alert and Notification System Design Report.

7.8 Emergency Alert System Auto Dialing Telephone Systems To further ensure prompt notification, auto-dialing systems are used to notify various commercial, institutional, and education facilities in the 10 mile zone. These locations may harbor large groups of people during all or part of a day. Auto dialing systems will be activated by the local counties.

7.9 Mapping 10 mile EPZ maps are periodically updated to reflect population and geo-physical changes.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 77 of 120 Table 7 MONTICELLO NUCLEAR GENERATING PLANT COMMUNICATIONS MATRIX X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X MNGP Security X X X X X Incident Command Post X X X X X X PLANNING & ASSESSMENT X X X X X X X X X X X X X X X X X X X X X X X

X STATE PATROL X

X X

X X X X X X X X Xcel ENERGY SYSTEM DISP X X X X X X X X MNGP-PINGP MONITORING TEAMS X X X X

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 78 of 120 Table 8 COMMUNICATIONS CONTACTS CONTACT LOCATION PRIMARY ALTERNATE Control Room Shift Manager Control Room Supervisor EOF and Back-up EOF Emergency Manager EOF Coordinator Minnesota Division of Emergency Duty Officer Duty Officer Management Minnesota Planning and Planning Chief State Duty Officer Assessment Center Wright Country Sheriff Sheriff Dispatcher Sherburne Country Sheriff Sheriff Dispatcher Monticello Civil Defense Monticello CD Driver Sheriff Dispatcher Minnesota State Patrol (St. Cloud) Captain Dispatcher Monticello City Hall Mayor City Administrator Monticello F. D. Sheriff Dispatcher NRC HPN NRC - Operations Center Region III Lisle NRC ENS NRC - Operations Center Region III Lisle Table 9 SEISMIC MONITORING INSTRUMENTATION LOCATION DESCRIPTION ACTUATING DEVICE SETPOINT 6-C-08 Earthquake Accelerograph Trigger .01 g OR OBE Alarm Module .03 g OR DBE Alarm Module .06 g 6-C-13 Operational Basis OBE Alarm Module .03 g Earthquake 6-C-18 Design Basis DBE Alarm Module .06 g Earthquake

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 79 of 120 Table 10 ON-SITE METEOROLOGICAL MONITORING INSTRUMENTATION SENSOR LOCATION SYSTEM PARAMETER (METERS) INDICATOR LOCATIONS 100 meter WIND SPEED 10 Single train (A or B) 5 minute Tower 43 average data available on the Met 100 Recorder in the Control Room.

15 minute average data is available on computer terminals in the TSC and EOF.

WIND DIRECTION 10 Single train (A or B) 5 minute 43 average data available on the Met 100 Recorder in the Control Room.

15 minute average data is available on computer terminals in the TSC and EOF.

TEMPERATURE 10 Current and 15 minute average 43 data (both A&B) from 100 meter 100 tower available in the TSC and EOF on computer terminals.

TEMPERATURE 43 100 30 meter WIND SPEED 22 Current data available on any Tower WIND DIRECTION 22 plant process computer terminal display.

Back-up Sources of Meteorological Data Data Source Location Method National Weather Service MSP Airport and Commercial Telephone and Chanhassen, MN website NOAA Weather Alert Radio Regional Alert Radio in TSC and EOF

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 80 of 120 Table 11 PROCESS RADIATION MONITORS NUMBER OF INDICATOR MONITOR DETECTORS LOCATIONS INDICATOR RANGE Main Steam Line Radiation Monitor 4 Panel C-02, C-10 1 - 106 mrem/hr Off-gas Pretreatment Rad Monitor 2 Panel C-02, C-10 1 - 106 mrem/hr Flux Tilt Monitor 1 Panel C-02, C-10 0 - 125 units Stack WRGM 2 Panel C-257 100 - 1012 µCi/Sec Panel C-258 Reactor Building Vent WRGM 2 Panel C-257 100 - 1012 µCi/Sec Panel C-258 Fuel Pool Monitor 2 Panel C-10 0.1 - 1000 mrem/hr Reactor Building Exhause Plenum 2 Panel C-02, C-10 .01 - 100 mrem/hr Monitor Process Liquid:

Radwaste Liquid Effluent Monitor 1 Panel C-10 10 106 CPS Service Water Effluent Monitor 1 Panel C-02, C-10 10 106 CPS RBCCW Radiation Monitor 1 Panel C-02, C-10 10 106 CPS Discharge Canal Rad Monitor 2 Panel C-02, C-10 10 106 CPS Turbine Building Normal Waste 2 Panel C-02, C-10 10 - 106 CPM Sump Radiation Monitor Drywell CAM Monitor 1 Panel C-02 10 - 106 CPM Control Room Radiation 2 Panel C-257 10 104 mrem/hr Panel C-258 Sewer Lift Station 1 Panel C-249 10 - 107 CPM Hard Pipe Vent 1 Panel C-289B 10 104 mrem/hr Continuous Air Monitors

1. Primary OSC

2. TSC

3. SJAE Room (Condensate Pump Area)

4. 951 Turbine Floor East

5. 1027 Reactor Building

6. Recombiner Building (TB RR Access)

7. Off-gas Storage Building

8. 962 Reactor Building (CUPR Vent)

9. 962 RX Building East (Samples Stm Chase)

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 81 of 120 Table 12 AREA RADIATION MONITORS PANEL C-11 SENSOR SENSOR RANGE STA. AREA LOCATION (MR/HR)

BUILDING A-1 Reactor Refuel Floor 0.1 - 1000 A-2 Reactor Refuel Floor (High Range) 1.0 - 10,000 A-3 Reactor Refuel Floor West Stairway 0.1 - 1000 A-4 Reactor 1001 Source Storage 0.1 - 1000 A-5 Reactor 1001 Fuel Pool Room 0.1 - 1000 A-6 Reactor 1001 Decon Equipment Area 0.1 - 1000 A-7 Reactor 985 Chem Sample Area 0.1 - 1000 A-8 Reactor 962 Cleanup System Access 0.1 - 1000 A-9 Reactor 962 Reactor Building East 0.1 - 1000 A-10 Reactor 935 East CRD Module Area 0.1 - 1000 A-11 Reactor 935 West CRD Module Area 0.1 - 1000 A-12 Reactor 935 TIP Drive 0.1 - 1000 A-13 Reactor TIP Cubicle 1.0 - 10,000 A-14 Reactor HPCI Turbine Area 0.1 - 1000 A-15 Reactor 896 Radwaste Drain Tank Room 0.1 - 1000 A-16 Reactor RCIC Pump Area 0.1 - 1000 A-17 Reactor A RHR Room 0.1 - 1000 A-18 Reactor B RHR Room 0.1 - 1000 A-19 Office Chemistry Lab 0.1 - 1000 A-20 Office Control Room (Low Range) 0.01 - 100 A-21 Office Control Room (High Range) 1.0 - 10,000 B-1 Turbine Operating Floor (North Wall) 1.0 - 10,000 B-2 Turbine Shield Wall 0.1 - 1000 B-3 Turbine Condensate Demin Operating 0.1 - 1000 Area B-4 Turbine MVP Room 0.1 - 1000 B-5 Turbine Feedwater Pump Area 0.1 - 1000 C-1 Radwaste Radwaste Control Room 0.1 - 1000 C-3 Radwaste Conveyor Operating Aisle 0.1 - 1000 D-1 13.8kV Switchgear 13.8kV Switchgear Room 0.1 - 1000 Room

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 82 of 120 Table 12 AREA RADIATION MONITORS (CONTD)

PANEL C-252 &

C-11 SENSOR SENSOR RANGE STA. AREA LOCATION (MR/HR)

BUILDING E-1 Recombiner Instrument Room 0.1 - 1000 E-2 Recombiner Pump Room 0.1 - 1000 F-1 Gas Storage Foyer (Low Range) 0.1 - 1000 F-2 Gas Storage Foyer (High Range) 100 - 1,000,000 PANEL C-257 &

C-258 SENSOR SENSOR RANGE STA. AREA LOCATION (MR/HR)

BUILDING Reactor Containment 100 - 108 R/HR

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 83 of 120 Table 13 INSTRUMENTS AVAILABLE FOR MONITORING MAJOR SYSTEMS Measured Indicator Parameter Type of Readout Range Location

1. Source Range

a. Neutron Level Log Scale Indicator, 10-1 to 106 CPS System Cabinets Recorder, Annunciator Main Control Panels

b. Reactor Period Linear Scale Indicator, -100 to 10 Sec System Cabinets Annunciator Main Control Panels

2. Intermediate Range

a. Neutron Level Digital Bargraph 0 to 125 (units) System Cabinets Display, Recorder, Main Control Annunciator Panels

3. Power Range

a. Neutron Level Linear Scale Indicator, 0 to 125% System Cabinets Recorder, Annunciator Main Control Panels

4. Reactor Coolant Range

a. Recirc Loop Linear Scale Indicator, 0 to 600°F Main Control Temperature Computer Printout Panels

b. Reactor Pressure Linear Indicator, 0 to 1500 PSIG Main Control Recorder, Computer Panels Printout, Annunciator

c. Core Flow Linear Scale 0 to 80 x 106 Main Control LB/HR Panels

d. Circ Flow Linear Indicator, 0 to 35 x 103 Main Control Recorder, Computer GPM Panels Printout

e. Jet Pump Flow Linear Scale Indicator, 0 to 44 x 106 Main Control Computer Printout LB/HR Panels

5. Main Steam

a. Steam Line Flow Linear Indicator 0 to 2.5 x 106 Main Control LB/HR Panels

b. Total Steam Flow Linear Scale Recorder 0 to 10 x 106 Main Control LBS/HR Panels

c. Main Steam Line Linear Scale Indicator, 900 to 1000 psig Main Control Pressure Computer Printout (on C-07) Panels 0 to 1200 psig (on C-03)

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 84 of 120 Table 13 INSTRUMENTS AVAILABLE FOR MONITORING MAJOR SYSTEMS (CONTD)

Measured Indicator Parameter Type of Readout Range Location

6. Containment

a. Pressure Linear Scale -2 to +3 psig Main Control Recorder, Computer recorder Panels Printout, Annunciator 0-80 psig recorder 0 to +250 psig recorder

b. Torus Pressure Linear Scale Recorder -2 to +3 psig Main Control Panels

c. Torus Level Linear Scale Indicator -15 to 15 Main Control

-8 to 14 Panels recorder (in Linear Feet)

d. Torus Water Digital Indicator, 30° - 240°F Main Control Temperature Annunciator Panels

e. N2 Makeup Flow Linear Scale 0 - 2 SCFM Main Control Recorder, Annunciator Panels

f. N2 Purge Flow Linear Scale Indicator 0 - 5000 SCFM Main Control Panels

g. Drywell Sumps Level Recorder 0 - 14 Main Control Panels

h. Drywell Cooling Indicator Lights Stby/Off/On System Cabinet Fans Control Panels

7. Station Electric

a. Busses 15 and 16 Linear Scale Indicator, 0-5250 AC Volts Main Control 4.16 KV Bus Annunciators Panels Voltage

b. Breaker Positions Indicator Lights Open/Closed Main Control Panels

c. Amperage Linear Scale Various Main Control Indicators Panels

d. Generator Output Linear Scale 0 to 800 MW Main Control Recorder, Indicator, 0 to 700 MW Panels Computer Printout

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 85 of 120 Table 13 INSTRUMENTS AVAILABLE FOR MONITORING MAJOR SYSTEMS (CONTD)

Measured Indicator Parameter Type of Readout Range Location

8. Feedwater Condensate

a. Feedwater Linear Scale Recorder 32 to 430°F Main Control Temperature Panels

b. Condensate Linear Scale Indicator 0 to 500 psig Main Control Header Pressure Panels

c. Feedwater Linear Scale Indicator 0 to 2000 psig Main Control Discharge Pres and Recorder Panels

d. Feedwater Flow Linear Scale Indicator 0 to 5 x 106 Main Control LB/HR Panels

e. Total Feedwater Linear Scale Recorder 0 to 10 x 106 Main Control Flow LB/HR Panels

9. Condenser Systems

a. Condenser Linear Scale 0 to 30 HG Vac Main Control Vacuum Recorder, Annunciator Panels

b. Hotwell Level Linear Scale -15 to +15 Main Control Recorder, Annunciator Panels

c. CST Level Linear Scale Indicator 5 to 30 Main Control Panels

10. ECCS Systems

a. LPCI, Core Spray Indicator Light ----

Pump Status

b. LPCI Flow Square Root Scale 0 to 10,000 GPM Main Control Recorder, Indicator Panels

c. Core Spray Flow Square Root Scale 0 to 5000 GPM Main Control Indicator Panels

d. LPCI Core Spray Indicator Lights ---- Main Control Valve Positions Computer Printout Panels

e. ADS Valve Indicator Lights ---- Main Control Positions Annunciator Panels

f. ADS Discharge Linear Scale 0 to 600°F System Temperature Recorder, Annunciator Temperature Recorder

g. HPCI Flow Linear Scale Indicator 0 to 3500 GPM Main Control Panel

11. Decay Heat Removal System

a. RCIC Flow Linear Scale Indicator/ 0 to 500 GPM Main Control Controller Panel

b. LPCI Mode of RHR (see above)

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 86 of 120 Table 14 EMERGENCY KITS LOCATION GENERAL CONTENTS Site Administration Building Protective Clothing & Equipment Assembly Point Radiological Monitoring Equipment Emergency Supplies Personnel Decontamination Supplies First Aid Kit Control Room & Work Execution Center Protective Clothing & Equipment Radiological Monitoring Equipment Communications Equipment Toxic Chemical Monitoring Equipment Emergency Supplies First Aid Kits Access Control Protective Clothing & Equipment Radiological Monitoring Equipment Personnel Decontamination Equipment First Aid Kits Technical Support Center Radiological Monitoring Equipment Communications Equipment Emergency Supplies Emergency Operations Facility Protective Clothing & Equipment Radiological Monitoring Equipment Communications Equipment Personnel Decontamination Equipment Emergency Supplies First Aid Kit Emergency Vehicle & Vehicles for Emergency Use (2)

Equipment Storage Facility Radiological Monitoring Equipment Protective Clothing & Equipment Communications Equipment Emergency Supplies Monticello Plant Security Access Facility Protective Clothing & Equipment (Ambulance/Fire E Kit) Dosimetry CentraCare Health Monticello Protective Clothing & Equipment

& North Memorial Hospital Radiological Monitoring Equipment Personnel Decontamination Equipment Emergency Supplies

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 87 of 120 8.0 MAINTAINING EMERGENCY PREPAREDNESS 8.1 Organizational Preparedness 8.1.1 Emergency Response Organization Training Training of ERO personnel is controlled by the EP Training Program Description (TPD). The requirements for training in the TPD are based on a graded approach to the systematic approach to training.

Off-site Emergency Preparedness Coordinators will make provisions for the training of those off-site organizations who may be called upon to provide assistance in the event of an emergency.

8.1.2 Drills, Exercises and Tests The Off-site Nuclear Emergency Plan contains the specific requirements for the conduct of required drills and exercises.

The conduct of periodic drills and exercises are the responsibility of the Monticello Business Support Group in accordance with the Emergency Preparedness Drill & Exercise Manual, which includes:

8.1.2.1 An exercise which tests the integrated capability and basic elements of the Emergency Plan SHALL be conducted every 2 years. This exercise may be included in the full participation biennial exercise which tests the off-site state and local emergency plans.

8.1.2.2 In order to ensure that adequate emergency response capabilities are maintained during the interval between biennial exercises, drills SHALL be conducted including at least one drill involving a combination of some of the principal functional areas of the on-site emergency response capabilities. The principal functional areas of emergency response include activities such as management and coordination of emergency response, accident assessment, protective action decision making, and plant system repair and corrective actions. During these drills, activation of all of the Emergency Plans response facilities (TSC, OSC, and EOF) is not necessary, opportunities to consider accident management strategies may be provided, supervised instruction is permitted, operating staff may have the opportunity to resolve problems (success paths) rather than have controllers intervene, and the drills may focus on on-site training objectives.

8.1.2.3 A medical emergency drill, involving response to and transport of a simulated contaminated, injured individual, which provides for off-site support agency participation, SHALL be conducted annually.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 88 of 120 8.1.2.4 Health Physics Drills which involve response to and analysis of simulated elevated airborne or liquid samples and direct radiation measurements in the environment SHALL be conducted semi-annually. These drills may be performed as stand alone Health Physics Drills or included as part of other drills or exercises.

8.1.2.4.1 The analysis of in-plant liquid samples (with actual elevated radiation levels) including the use of the Post Accident Sampling System (PASS) will be included in biennial chemistry training/walkthroughs and may be performed in conjunction with full scale exercises/drills or Health Physics drills.

8.1.2.4.2 Radiological monitoring drills which include the collection and analysis of environmental samples for the purpose of ground deposition assessment SHALL be conducted annually and may be performed as stand alone Health Physics Drills or included as part of other drills or exercises.

8.1.2.5 Fire Drills SHALL be conducted in accordance with applicable Plant Administrative Control Directives.

8.1.2.6 In addition to drills and exercises, periodic tests are conducted to ensure an adequate state of emergency preparedness is maintained. These tests include:

8.1.2.6.1 Communications tests with State and Local government agencies, local law enforcement, and off-site facilities within the plume EPZ are conducted monthly in accordance with plant Surveillance 1225.

8.1.2.6.2 Communications tests with the NRC via the Emergency Notification System (ENS ) and Health Physics Network (HPN) are conducted monthly in accordance with Surveillance 1225.

8.1.2.6.3 Emergency Response Organization Augmentation tests are conducted quarterly in accordance with plant Surveillance 1317.

8.1.2.6.4 The Public Alert Notification System (ANS) is tested weekly in accordance with plant Surveillance Test 1359.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 89 of 120 8.1.2.6.5 The Annual Performance Review for the ANS is conducted in accordance with plant Surveillance 1408.

8.1.2.6.6 The Emergency Alert System Auto Dialing Telephone Systems are tested by Sherburne County and Wright County staff. Completion of the testing and system maintenance is verified on a semi-annual basis in accordance with plant Surveillance 1410.

8.1.2.6.7 The ERDS communication link is tested on a quarterly basis in accordance with plant Surveillance 1416.

8.2 Planning 8.2.1 Responsibility The overall responsibility for radiological emergency response planning rests with NSPM management.

At the site level the Site Vice President, Monticello Site has overall authority and responsibility for the Monticello Emergency Plan and Emergency Plan Implementing Procedures. The Site Emergency Planners are responsible for the development and updating of the Emergency Plan and coordination of the plan with off-site emergency response plans.

8.2.2 Review and Updating of the Emergency Plan The Monticello Emergency Plan SHALL be reviewed and certified to be current on an annual basis in accordance with the Off-site Nuclear Emergency Plan. Other reviews of the Emergency Plan and Implementing Procedures will be performed as required by Technical Specifications.

Annual revisions to the Emergency Plan are conducted in accordance with Surveillance Procedure 1406 and may be based on the following:

8.2.2.1 Lessons learned during drills and exercises and industry lessons learned.

8.2.2.2 Changes in the normal plant or Emergency Response Organization structures.

8.2.2.3 Modifications to plant systems, components or instrumentation.

8.2.2.4 Changes in the functions or responsibilities of supporting agencies and organizations.

8.2.2.5 Lessons learned from real emergency plan activations.

8.2.2.6 Changes in State or Federal regulations.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 90 of 120 Changes to the Emergency Plan SHALL be reviewed and approved in accordance with plant Technical Specifications and applicable Administrative Control Directives. Distribution of controlled copies of the Emergency Plan SHALL be performed in accordance with applicable MNGP document control procedures.

In addition to the annual review, all Emergency Plan Implementing Procedures containing telephone numbers are reviewed at least quarterly to verify the correct numbers in accordance with Surveillance Procedure 1240.

8.3 Maintenance and Inventory of Emergency Equipment and Supplies 8.3.1 Equipment and Supplies Inventory Emergency Equipment and supplies SHALL be inventoried at least quarterly in accordance with plant Surveillance Procedure 1102.

8.3.2 Instrument and Facilities Functional Check Key emergency response equipment and instrumentation located in the Technical Support Center and Emergency Operation Facility is tested monthly in accordance with plant Surveillance Test 1230.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 91 of 120 9.0 RECOVERY 9.1 General Approach In general, the site organization will be responsible for the short term recovery, that is recovery from an emergency condition in which no core damage or serious release of radioactivity to the environment has occurred.

If it is clear that a high potential exists for core damage or a serious release of radioactivity to the environment has occurred, a Recovery Phase will be activated to provide for the long-term recovery actions and for establishing support arrangements.

Before reoccupying buildings after an emergency, certain recovery criteria must be satisfied:

There must be assurance that the problem encountered is solved and that the same incident cannot immediately recur; The normally occupied areas must be free of significant contamination; Radiation areas and High Radiation areas must be properly defined; Airborne radioactivity must be eliminated or controlled.

9.2 Investigation of Incidents All incidents SHALL be investigated by qualified plant staff personnel and reported to the Plant Operations Review Committee, Management and Safety Review Committee (MSRC) and the NRC in accordance with guidelines for reportable events which are set forth in the Administrative Control Directives and the Technical Specifications.

9.3 Recovery Procedures All recovery operations SHALL be performed in accordance with written procedures.

These procedures SHALL include the following activities:

Investigation of the course of the incident.

Investigation of plant conditions following an accident.

Repair and restoration of facilities.

Testing and startup of restored facilities.

Methods for determining the extent of radioactive contamination and general protective measures to be taken for personnel performing recovery operations are established in site Radiation Protection Procedures.

Written procedures for recovery of the facility from the specific post accident conditions will be prepared by qualified plant staff members and submitted to the Plant Operations Review Committee. The Plant Operations Review Committee approval of all such procedures is required prior to their initiation.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 92 of 120 9.4 Criteria for Resumption of Operation If the plant is shutdown as the result of an emergency, it will be restarted only when:

The conditions which caused the emergency are corrected.

The cause of the emergency is understood.

Restoration, repair and testing is completed as required.

No unreviewed safety questions exist.

All conditions of the license and technical specifications are satisfied.

9.5 Long Term Recovery If extensive plant damage exists and contamination of plant or site environs has occurred, then a Recovery Phase will be required.

Activation of the Recovery Phase will take place in an incremental manner as the functions change from operational to engineering/construction. The decision to activate the Recovery Phase will be made by Site Management. The Recovery Manager will be selected from several qualified designees who are members of the site organization. The Emergency Manager and the Emergency Director will share responsibility at least during the early part of the Recovery Phase.

If a transition to the Recovery Phase becomes necessary, the site engineering/construction oriented staff would provide the nucleus of the organization responsible to carry out the Recovery Phase.

The plant staff would be augmented as required by specialists from the site organization and the NSPM/Xcel Energy corporate office. These speciality areas include Engineering Services, Licensing Administration, Maintenance, Quality Assurance, Communications and Security personnel. In addition, appropriate assistance would be secured from the Architect-Engineer and the Technical Support Services vendor organizations. This support could be broadened as required by consultant help from the several organizations familiar with the MNGP and organization. The overall organizations envisioned for a substantial Recovery Phase would be a blend of site staff and appropriate vendor and consultant personnel. On a prior basis it is counter productive to define in detail the extensive organization that might be involved in a sizable Recovery Phase because of the unlimited variation of conditions that could result from plant emergencies. However, the nucleus organization has been identified together with guidelines on how the organization might be expanded to meet the requirements demanded at the time.

When the Emergency Manager and Emergency Director agree that the emergency condition has been terminated, a complete transfer of the responsibilities for off-site support may be made to the Recovery Organization. The EOF will then become the Recovery Center and will function as Command Center for the Recovery Organization activation and implementation in accordance with applicable Emergency Plan Implementing Procedures.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 93 of 120 10.0 APPENDIX A Plan Section Procedure No. Procedure Title Reference 000 Series Organization A.2-001 Emergency Organization 5.1, 5.2, 5.3 100 Series Activation A.2-101 Classification of Emergencies 4.0, 6.2.2, Annex A A.2-102 Notification of an Unusual Event (NUE) 4.1, 6.1.1, Annex A A.2-103 Alert 4.2, 6.1.2, Annex A A.2-104 Site Area Emergency 4.3, 6.1.3, Annex A A.2-105 General Emergency 4.4, 6.1.4, Annex A A.2-106 Activation And Operation of the TSC 5.2.1, 7.1.1 A.2-107 Activation And Operation of the OSC 5.2.2, 7.1.2 A.2-108 Access Control During Emergencies 7.1.6 A.2-109 Activation and Operation of the Back-Up OSC 7.1.2 A.2-110 Response to a Security Threat 5.3.2 A.2-111 Activation of Alternative Facilities During a Security 7.1.4 Event 200 Series Assessment A.2-201 On-Site Protective Action 6.3.2, 6.5 A.2-202 Off-Site Monitoring During an Emergency 6.3 A.2-203 Radioactive Liquid Releases 6.3 A.2-204 Off-Site Protective Action Recommendations 6.5.1.2 A.2-205 Personnel Accountability 6.5.1, 7.1.5 A.2-206 Work Control During Emergencies 5.3.1.6, 6.4.2 A.2-208 Core Damage Assessment 7.3.1.5 A.2-209 Responsibilities of the Radiological Emergency Coordinator 5.2.1.2 A.2-210 Engineering Support in the TSC 5.2.1.5 A.2-213 Responsibilities of the Emergency Director 5.2.1.1

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 94 of 120 10.0 APPENDIX A (CONTD)

Plan Section Procedure No. Procedure Title Reference 300 Series Protective Actions A.2-301 Emergency Evacuation 6.5.1, 6.5.2 A.2-302 Activation of the Assembly Points 6.5.1, 7.1.5 A.2-303 Search and Rescue 5.3.1.8 A.2-304 Thyroid Prophylaxis (Potassium Iodide Use) 6.5.4.2 400 Series Radiological Surveillance and Control A.2-401 Emergency Exposure Control 6.5.5 A.2-402 On-Site Radiological Monitoring 6.5.6, 6.3 A.2-404 Emergency Air Sampling and Analysis 6.3 A.2-405 Release Rate Determinations 6.3.1 A.2-406 Off-Site Dose Projection 6.3.2 A.2-407 Personnel & Vehicle Monitoring And 6.5.1 Decontamination A.2-408 Sample Coordination During Emergencies 6.3 A.2-409 Self-Contained Breathing Apparatus (SCBA) Use 6.5.4.1 During an Emergency A.2-410 Out-of-Plant Surveys 6.3.3 A.2-411 Establishment of a Secondary Access Control 7.1.6 Point A.2-412 Reactor Coolant Sample Obtained from Reactor Sample Station 7.3.1.7 A.2-413 Small Volume Liquid Sample Obtained at the Post Accident Sampling System 7.3.1.7 A.2-414 Large Volume Liquid Sample Obtained at Post Accident Sampling System 7.3.1.7 A.2-415 Containment Gas Sample Obtained at Post Accident Sampling System 7.3.1.7 A.2-417 Draining the Trap, Sump and Collector of Post Accident Sampling System 7.3.1.7

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 95 of 120 10.0 APPENDIX A (CONTD)

Plan Section Procedure No. Procedure Title Reference A.2-418 Post Accident Sampling Station Demin Water Tank Fill Procedure 7.3.1.7 A.2-419 Containment Atmosphere Sample Obtained from Reactor Sample Station 7.3.1.7 A.2-420 Containment Atmosphere Radiochemical Analysis 7.3.1.7 A.2-422 Stack Iodine/Particulate Sampling and Analysis 6.3.1 A.2-423 Reactor Building Vents Iodine/Particulate Sampling

& Analysis 6.3.1 A.2-424 EOF Count Room Procedures 7.3.2.3 500 Series Communications and Documentation A.2-501 Communications During an Emergency 7.2 A.2-502 Record Keeping During an Emergency ---

A.2-504 Emergency Communicator Duties in the TSC And OSC 5.2.1.8 600 Series Re-Entry and Recovery A.2-601 Re-Entry 9.1 A.2-602 Event Termination or Recovery 9.5 700 Series Emergency Preparedness A.2-701 PANS System False Activation or Failure ---

A.2-702 Response to an Emergency at Prairie Island ---

A.2-703 Response to Off-Site Situations Involving Radioactive Material ---

800 Series EOF Procedures A.2-801 Responsibilities of the Emergency Manager 5.2.3.1, 7.1.3 A.2-802 Activation and Operation of the EOF 5.2.3.4, 7.1.3 A.2-803 Emergency Communications at the EOF 5.2.3, 7.1.3 A.2-804 EOF Support and Logistics 5.2.3.4, 7.1.3 A.2-805 Technical Support in the EOF 5.2.3.2, 7.1.3

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 96 of 120 10.0 APPENDIX A (CONTD)

Plan Section Procedure No. Procedure Title Reference A.2-806 Radiation Protection Support in the EOF 5.2.3.3, 7.1.3 A.2-807 Off-Site Dose Assessment and Protective Action Recommendations 5.2.3.3, 7.1.3 A.2-808 Radiological Monitoring and Control at the EOF 5.2.3.4, 7.1.3 A.2-809 EOF Security 5.2.3.4, 7.1.3 A.2-810 Transfer to the Backup EOF 7.4.3 A.2-811 Event Termination or Recovery in the EOF 9.0 A.2-812 Off-site Agency Liaison at the EOF 5.2.3.4, 7.1.3

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 97 of 120 11.0 APPENDIX B NUREG-0654 Section Emergency Plan Section A. Assignment of Responsibility 1.a. 5.4 & 5.5 1.b. 5.4 & 5.5 1.c. Figure 13.2, Figure 13.3 1.d. 5.2 1.e. 5.1 & 5.2 2.a. State/Local Plans 2.b. State/Local Plans 3 Off-Site Plan 4 5.2, 5.2.1.3 B. On-Site Emergency Organization 1 5.1.2 2 5.2.1.1, 5.3.1.2 3 5.3.1.2 4 5.2, 5.2.1.1, 5.3.1.2 5 5.2, 5.3.1 & 5.3.2, Table 1 6 Figure 13.2, Figure 13.3 7 5.2.3, Off-site Plan 7.a. 5.2.3, Off-site Plan 7.b. 5.2.3, Off-site Plan 7.c. 5.2.3, Off-site Plan 7.d. 5.2.3, Off-site Plan 8 Off-site Plan & 5.4 9 5.4.2

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 98 of 120 11.0 APPENDIX B (CONTD)

NUREG-0654 Section Emergency Plan Section C. Emergency Response Support and Resources 1.a. 5.2.3.1 1.b. Off-site Plan 1.c. Off-site Plan 2.a. State/Local Plans 2.b. Off-site Plan 3 7.3.2.3 Off-site Plan 4 Off-site Plan D. Emergency Classification System 1 Section 4.0, Annex A 2 Section 4.0, Annex A 3 State/Local Plans 4 State/Local Plans E. Emergency Classification System 1 6.2.1.2, 6.2.3 2 6.2.1.1 3 6.2.1.2 4.a. 6.2.1.2.1 4.b. 6.2.1.2.2 4.c. 6.2.1.2.3 4.d. 6.2.1.2.4 4.e. 6.2.1.2.5 4.f. 6.2.1.2.6 4.g. 6.2.1.2.7 4.h. 6.2.1.2.8 4.i. 6.2.1.2.9 4.j. 6.2.1.2.10 4.k. 6.2.1.2.11

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 99 of 120 11.0 APPENDIX B (CONTD)

NUREG-0654 Section Emergency Plan Section 4.l. 6.2.1.2.12 4.m. 6.2.1.2.13 4.n. 6.2.1.2.14 5 State/Local Plans 6 6.2.1.4 7 6.5.1.3, State/Local Plans F. Emergency Communications 1.a. 7.2 1.b. 7.2 1.c. 7.2 1.d. 7.2, 7.2.3.3 1.e. 6.2, 7.2.3.2 1.f. 7.2, 7.2.3.3 2 7.2.2 3 7.2.5 G. Public Education and Information 1 Off-site Plan 2 Off-site Plan 3.a. Off-site Plan 3.b. 7.1.3 Off-site Plan 4.a. Off-site Plan 4.b. Off-site Plan 4.c. Off-site Plan 5 Off-site Plan

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 100 of 120 11.0 APPENDIX B (CONTD)

NUREG-0654 Section Emergency Plan Section H. Emergency Facilities and Equipment 1 7.1.1, 7.1.2 2 7.1.3 3 State/Local Plans 4 6.2.1.1 5 Table 9 through Table 13 5.a. 7.3.1.2, Table 9 and Table 10 5.b. 7.3.1.3, Table 11 and Table 12 5.c. 7.3.1.4, Table 13 5.d. 7.3.1.6 6.a. 7.3.2.1 6.b. 7.3.2.2 6.c. 7.3.2.3 7 7.4.4, Table 14 8 7.3.1.2.2 9 7.1.2 10 8.3.1 11 Table 14 12 7.3.2.3 I. Accident Assessment 1 4.0, Table 9 through Table 13 2 6.3, 7.3 3.a. 6.3.1 3.b. 6.3.1 4 6.3.2 5 7.3.1.2.2, Table 10 6 6.3.1, 6.3.2

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 101 of 120 11.0 APPENDIX B (CONTD)

NUREG-0654 Section Emergency Plan Section 7 6.3.3 8 6.3.2, 6.3.3 9 6.3.3 10 6.3.2 11 State Plan J. Protective Response 1.a. 6.5.1 1.b. 6.5.1 1.c. 6.5.1 1.d. 6.5.1.1 2 6.5.2 3 6.5.1.1 4 6.5.1.1 5 6.5.1.1 6.a. 6.5.4 6.b. 6.5.4 6.c. 6.5.4.2 7 6.5.1.2 8 6.5.3 9 State/Local Plan 10.a. Off-site Plan 10.b. Off-site Plan 10.c. 7.7 and 7.8 10.d. State/Local Plan 10.e. State/Local Plan 10.f. State/Local Plan 10.g. State/Local Plan 10.h. State/Local Plan

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 102 of 120 11.0 APPENDIX B (CONTD)

NUREG-0654 Section Emergency Plan Section 10.i. State/Local Plan 10.j. State/Local Plan 10.k. State/Local Plan 10.l. State/Local Plan 10.m. 6.5.1.2, Table 3 thru Table 6, State/Local 11 State/Local 12 State/Local K. Radiological Exposure Control 1.a. 6.6 & Table 6 1.b. 6.6 & Table 6 1.c. 6.6 & Table 6 1.d. 6.6 & Table 6 1.e. 6.6 & Table 6 1.f. 6.6 & Table 6 1.g. 6.6 & Table 6 2 6.5.5 3.a. 6.5.5.2 3.b. 6.5.5 4 State/Local Plans 5.a. 6.6.1 5.b. 6.6.1 6.a. 6.5.6.1 6.b. 6.5.6 6.c. 6.5.6.1 7 6.1.1.1

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 103 of 120 11.0 APPENDIX B (CONTD)

NUREG-0654 Section Emergency Plan Section L. Medical and Public Health Support 1 6.6.2, 6.6.3 2 6.6.1.2 3 State Plan 4 5.4.2, 6.6.2 M. Recovery and Re-entry Planning and Post Accident Operations 1 9.0 2 9.0 3 9.0, Off-site Plan 4 6.3.2 N. Exercises and Drills 1.a. 8.1.2.1 1.b. 8.1.2 2.a. 8.1.2.6 2.b. 8.1.2.5 2.c. 8.1.2.3 2.d. 8.1.2.2 2.e. 8.1.2.4 3.a. 8.1.2 3.b. 8.1.2 3.c. 8.1.2 3.d. 8.1.2 3.e. 8.1.2 3.f. 8.1.2 4 8.1.2 5 8.1.2

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 104 of 120 11.0 APPENDIX B (CONTD)

NUREG-0654 Section Emergency Plan Section O. Radiological Emergency Response Training 1 8.1.1 & Off-site Plan 1.a. 8.1.1 & Off-site Plan 1.b. 8.1.1 & State/Local Plans 2 8.1.2 3 6.6.1.2 & Off-site Plan 4.a. 8.1.1 & Off-site Plan 4.b. 8.1.1 & Off-site Plan 4.c. 8.1.1 & Off-site Plan 4.d. 8.1.1 & Off-site Plan 4.e. 8.1.1 & Off-site Plan 4.f. 8.1.1 & Off-site Plan 4.g. 8.1.1 & Off-site Plan 4.h. 8.1.1 & Off-site Plan 4.i. 8.1.1 & Off-site Plan 4.j. 8.1.1 & Off-site Plan 5 8.1.1 & Off-site Plan P. Responsibility for the Planning Effort: Development, Periodic Review and Distribution of Emergency Plans 1 Off-site Plan 2 8.2.1 3 8.2.1 4 8.2.2 5 8.2.2 6 8.2.2 7 Appendix A 8 Appendix B, Table of Contents 9 Off-site Plan 10 8.2.2

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 105 of 120 12.0 ANNEX A MNGP EMERGENCY ACTION LEVELS AND APPLICABLE DEFINITIONS Emergency Action Levels The site specific Emergency Action Levels are contained in Form 5790-101-02 (MONTICELLO NUCLEAR GENERATING PLANT EMERGENCY ACTION LEVEL MATRIX). These EALs are based on NEI 99-01, Revision 4, and Security ICs and EALs from NEI 99-01, Revision 5.

Emergency Plan Implementing Procedure A.2-101 (CLASSIFICATION OF EMERGENCIES) requires use of Form 5790-101-02.

I I MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 106 of 120 12.0 FIGURE Annex A-1 Monticello Nuclear Generating Plant Emergency Action Level Matrix Left half of Page 1 of Form 5790-101-02

~l~~~ftil~l~i GENERAL EMERGENCY I SITE AREA EMERGENCY I ALERT I UNUSUAL EVENT I 1110 1 Ot'kb Oou ltesuiUrog from an Act laM o r lmmi!Mnt lltiiNH of ItS! Oftllll Dose bsulllng from ~n Aetu.ill or~lll llt ele- ol ItA I Ai'r1 UNPl.ANNEOII..N H ol ~eooS Of Llquld iii ~IICIIYitylo 11M ltul Any UNPLANNED llleiNSe o f OHeOUS Of Liquid lllidOKtMiy to the o .......s lbdl....,llvlty b.ce.<ls 1000 mltltm TI!OE or i1000 mit..,. G.io.M OUs lbdkwctMI ~ b c - s 100 m lt.m TEDE. or 500 IRII:..., EnYir-o.....- 1~ ExcM <k 200 11m . . IIMOfiU!e Dou C*UI..Ion Envlronmenl lhill Exc-*Y...., n .... the Ofh.il* Do!t* C*=UI.tllon fhrl!rold Cot! fof lh* Act!a! or l"rojKted Ournlon of thellefNse ltlyrold COl! for tiM Actual or Pro)KMO 0\nUon of the ll:e!Nse MinUii! LimlfO! lS.nuln OI L~ M~nuiiUmit:fOI &O itllinYI H OIL~r Utlrtg ActiMI MI I -Oiagy Note* lfOoM11S6eMment reS~.~tsare*~a~ble *tne tJmeol Note lldo5ell~results are.-vaQt.leatltletl.meol 0 RA1 .1 I 1 I 2 I 3 I

• I 5 I DEF I 0 RU1.1 I 1 I 2 I 3 I

• I 5 I OEF I

<l<<:laraboro. the clnSificatlon should be bawd Ql"j RG 1 2 rtstNd r:l dedaratJon. toe clawlficabon ~be bt!Md on RS1 2 m.tead of VAUO reading on arry effluent I'T'()flltor tha,t ex~ 200 tirrlet> VALl) reacting on &nf effluerc morvtor that t')(ceeds two ttmes RS1 1 'M'Iile necewary dedlratioos should not be ~ed ll'lo9lli:'lg the alarm setporn established bV a CU'rent radioactMty RG11 'lloNeMCeSNI~<Ieclarabons.tlouldi'KltbeOelayedawaibng t"'-lltt. tl'le~n;wwmenttho\.lld be initi;Jited lco~ inor<lef retUb, thedoMa'loW~tholild be in~ted/oompleoteol;;f in~ lhe alarm setpolnt establ1s.hed by' a current radioactNrty to<ietet"rnne lfthec:ln.5oific..oon tho~o~ld be w~uel"(lyncWate<l !Odetefmne fthe~~bontho\111::1 bewbwquently ~ated chcharge permit for 15 m~nlies or longer discharge permt lor 60 mrutes or longer 0 RG1 .1 I 1 I 2 I 3 I 4 I 5 I DEF I 0 RS1.1 I 1 I 2 I 3 I 4 I 5 I DEF I VALID read11"Q on any of the follOWing rad!atJOn morutors lhal VALID readi!"Q on any of the lolloN*ng radiatiOn monrtors that 0 AA1 .2 I 1 I 2 I 3 I 4 I 5 I DEF I 0 RU1.2 I 1 I 2 I 3 I 4 I 5 I DEF I e'll;ceeds or es expiKted to exoeed the read*ng ~n for ~ S exceeds or *sexpected to exceed the readirg a.hoWn lor 15 VALID readtng on q d the loiiOWtf"G radiatiOn monitors that VALV reading on q of the following radiat1011 morvtors that fY'li!"UesoriOOQel' IT"'Illtes or IOnQef ex<::eede. the re&ang Shown for 15 l'nlrute& or IO!'Ot'f ~ceea& the reaot!ll Shown for 60 mr..tes or lOnger Mo11tor GE Monttor SAE Montor Alert Monttor UE

~~uentMorvtor 21E91JCtlseC ~ ~uertMorilof 21E81-1CIIsec ~luentMonilor 1 46E7 "Qisec* ~uentMontor 7.3E51-1Cifsec (Ch AorB) (ChAorB) (Ch AorB) (ChAorB)

RB Vent Emuerl: Monitor 1.5E8 .,.Qisec RB Vent E ffluent Mor1tor 1.5E7 "Qisec RBVeni: EmuertMonll.or RB Vent Effluent Mo11tor 216E4 .,.Cilsec c_...,

Ofhltelt ~

(ChAor8) (ChAocB) (ChAorB)

2. 1 6E6~

(ChAorB) l.iSWQ l.iSI.Ii<l ~ LW<I SeNteewater NIA St'Ntcewater NIA ServteeWater 31,400cps Servtce water 314 cps Discharge Canal Morwtor NIA Dtscharge canal Montor NIA Discharge Canal Monitor 93,000 cps Discharge Garel Mo11tor 930 cpt5 TBNWS NIA TBNWS NIA TEr-1\NS OOOOOOcom- TEr-M'S 37 752 com 0 R01 2 I 1 I 2 I 3 I 4 I 5 I DEF I 0 RS1.2 I 1 I 2 I 3 I 4 I 6 I DEF I 0 AA1 3 I 1 I 2 I 3 I 4 I 6 I DEF I o RU13 I 1 I 2 I 3 I ,. I 5 j oe=l Dose assessment USII'g actua I meteorologt tndtcates doseS Dose assessment USifll actual meteorology tndicates ooses Conftrmed safl'llle analysts for gaseous. or Nq:.id re ~ase Confirmed saflllle analy&IS for gaseous or ltqi.Jid release GREATER THAN 1000 ~emTEOEor 5000~em thyroid GREATER THAN 100 mRem T EOE or 500 mRem tJ'¥rotd CCE if'ldc.ates concer<<ratJOn& or release rates, wtth a release II"'Cicates (l()(l()enttatJOI"S. or release rates, Wttrt a release cl.l"ahJn ol 15 ITWJ.Jtes or lorqer, 1n excess d 200 tunesOOCM dura!Jon of 60 ll'W'lUtes or longer, 111 excess d two 111nes OOCM COE at or beyOild the Me bt:::ulclary atort::teyondtnes.ttebo\.ndary 0 RG1.3 I 1 I 2 I 3 I 4 I 5 I DEF Fiek:l survey results indicate dosed ..,;I"'Cbw d:lse rate~

I 0 RS1.3 I 1 I 2 I 3 I 4 I 6 I OEF I Fll"ld suvey reSIJI:s llldteate closed WlOdow dose rates lmt exceeding 1000 mRemtu expected to contii'I.Je !of more than exoeedtrg 100 ~emlhr expected to conttrue for more than

• 40 bmes OOCM calculated lml one hour, at or teyof"KI the site bot.. o:b ry one h:t1.1, at or beyond the site boundary ** 48 tlfllK OOCM catcUated ~mt OR OR A bnormal Ma!y$1S Of field wvey sarrpes IndiCate thyroid COE of 5000 m:<:em for one hou' of tnhalat:Jon. at or beyond the sne bounda~

Analy&t!l of field 5\XVey sample!lltldtcate thyrOid COE Of 500 mRem for one hol.l of lftlalation, at or beyond the srte

"""""~ ltAl Dani*Oe ~ lffadlale d ~ wt er LOU Ol Wat.. Le ..... ~ HM Of -

IteM In I ' - Unc:-rlrlg 0111 lflldllltiMI f uel OUI$1(1to the l'tNdqf VUMI TabW R*1 A~as Requir ing lnfrequW~t Acc.ss 0 RA2.1 I 1 I 2 I 3 I 4 I 5 I DEF I 0 RU2.1 I 1 I 2 I 3 I 4 5 I OEF I A VALID ala rm or readtllJ on al?( of the followtrg radiat1011 VALl) indlcahonoi i.JI'ICOI'tJ'olled water levellowen llJ In the Monitor reactor rel~ ingcavrty, spent fuel pool, or fuel transl eJ canal Alternate Sht.tdown Panel t;,vsurvey

"""'"~ with a~ irraGated fuel as.5ef'l"bb.es rematf'lirO covered by water Montor Alam'V'Tnp as ndlcated b( any of the followt!"(l Cable SpreadllJ Room Turbine Building (excluding t;,vsurvey b>,'survey

~; ~~~~~=~~ Unexpected Spert Fuel F:w k:Jw water level alarm Vttual ob6ervat101"1 of an uncontrolled water I~ drop A-3 1027 RB WStatrway below a fuel pool sklrtmef st.Xge tarf< Inlet T url:ttne operatii"IQ dec!<) B-2 TG FRONT STANDARD (951') RM*17-452A Reactor Butldlf"9 VenblatiOil ct:teervatJOil of water leakage tnto the Qoywel or the reactor ExhaUSI Pleoom Mootor Ch A B-3COOOENSATE OEM IN OPERATING bulding from piping penetrattonS surrOI.XIdng the drywel RM-17-4528 Reactor Bulldtrg Venblat1011 26mRIIY B-491 1 TURB ELDG MVP ROOM ExhaU'SI Plerun Monrtor Ch B AND RM-17-453AFue! Fool RadlationMonll.orCh A 50 mR/tY Any UNPlANNED VAllO Area Radl3bon Monttor reaclllJ nse B-5FEEOVVATER PlJMP AAEA(911') RM-17*4538 Fuel Pool Radl.!ltton Monitor Ch B 50 mRihr as Indicated I;Jj any of the followtng General Reactor Butldi"tg A-1 1027 RX BLDG LON RANGE A*1 1027 RB NE Low Areas (exdudi~ normally A*2 1027 RB N HrJh A-31027 RXBLOOWSTAIRWAY Hxl<ed hi!tt radar"') A-3 1027 R8WS1atrway A*5 1001 RX BLDG Fl.EL PCX:X.. ROOM RM-17-453A orBfiJe!Pool MonconngSystem A-7985 RX BL.OGCHEM SAMPLE AREA A-8 962 RX EI...OG tofiN OUTSIDE RVvCtJ ROOM o Ru2.2 l 1 I 2 I 3 I 4 I 5 l oe=l Any UNPlANNED VAllO Area Radiation Montbr readirg nses A-9 962 RX EI...OO EAST t'Ja factorof1{l)()overnormal"levels A*10 EAST CR0 MODULE AREA ' Normal leYef5 a m be con$1defed a5 the htghest reading in !he pnt

~four houfsexclvdinglhecurrentpeakvalue A-11 \o\oEST CRD MCX>ULE AREA A-1 2935 RX BlOGNE TIP DRIVE AREA A-14 HPCI TURBINE AREA A-15 896 RX BlDG DRAIN TANK ROOM A*16 RCIC EQUIPMENT AREA A-17 EAST COOE SPRAY & RHR AREA A-18 Vv'EST CORE SPRAY & RHR AREA HU t N~lur~ ..0 0.5lruo;tl.,. PtleflomeN Aff..:t ~ 11M 1'1-PitO TI!CTI:O ..ItEA 0 HA1 .1 I 1 I 2 I 3 I 4 I 6 I DEF I 0 HU1.1 I 1 I 2 I 3 I 4 I 5 I DEF I Se1&mic event GREATER THAN c:,erattng Basi& Earthqua~e Earthqua ~e felt In p!ar( as tneicated by (OBE) as indicated by' Amunctalor OPERATIONAl BASIS Consensus of Cortrol Room operator.;. on d~

EARTHQUAKE (6-C-13) receM!d AND 0 HA1 .2 I 1 I 2 I 3 I 4 I 5 I DEF I 0 Anr'J..trootor EAA1HOJAKE !6-C-08) rect'!Ved HU1.2 I 1 I 2 I 3 I 4 I 5 I OEF I Tornado or hi\1lwinds GREATER "THAN 100 rTV~witt"ln plant PROTECTED AREA boundary and r~ng tn VISIBlE Report b( ~ant persornel d tom.!IO;) or hrJh Winds GREATER DAMAGE to a"i ~nt structt.Xes.l equtpmenl (Table H-1) or THAN 100 mph within piarc PROTECTED AREA boi.X1dary Control Room irtdic::at1011 of degltded petformance d tho6e D HU1.3 I 1 I 2 I 3 I 4 I 5 I OEF I systems. VehiCle Ct"c.t$h 111to piar<< &tn.ICCI..Ke&. or &y$tem& Wllhtn ptar<<

0 HA1 .3 I 1 I 2 I 3 I 4 I 5 I DEF I PROTECTED AREA bOI.Xldary VehiCle crash wrthin p!a r<< PROTECTED AREA t:x>trdary end 0 HU1.4 I 1 I 2 I 3 I 4 I 5 I DEF I resUbng 111 VISIBlE DAM AGE to afli plant s1Juctures01 Report b( ptarc persomel dan ln211"111Ctpated EXPLOSION ecp..lipnert therein (Ta ble H-1) or Control Room lfldic:atJon eX wtti'W'I plant PROTECTED AREA DOI..tldary restJttng In degraded pertormanoe of ti"'I&e systerrtS VISIELE DAMAGE to permanert structt.Xe or equpment None None 0 HA1 .4 I 1 I 2 I 3 I 4 I 5 I DEF I u HU1.6 I 1 I 2 I 3 I 4 I 6 I OEF I Turb ne fa i~Xe-geoerated mts&lles resJI 111 any VISIBLE Report d turbine f&~t.Xe re&ulttng in castng penetratiOn or DAMAGE to or penetration ola"f plant areas (Table H--1) damage to t t.rlline Of generator sea fs 0 HA1 .5 I 1 I 2 I 3 I 4 I 5 I DEF I 0 HU1.5 I 1 I 2 I 3 I 4 I 5 I OEF I Lhcontrolled flooding tn areas (Table H-1) of the plant that Uncontrolled ftoodin;;tln areas (Table H*1) dlhe plant that has re&I.Ats In degraded s.afety system performance as tndicated tn the potential to affect safety related equtpmenl needed for the the conlrol room or that creates trd.Jstrial safety haza rds. (e g , CU'rert oper8lt!ll mooe.

e1ectoc Shock) tNt prech.ldes aocess neoessary to operate or I'T'()flll()r aafety equtpment o Huu l 1 I 2 I 3 I ,. Is j oe=!

~of the following htgl liver le~~el or low river level o HA1 .e I 1 I 2 I 3 I 4 I 5 I DEF I occurrences a!Tecttng the p!art PROTECTED AREA Either d the lolowtng OOCU"en::es Wlthlrt plant PROTECTED River level GREAT ER THAN 918 n~

AREA bOI..f'IOary and re&l#:tng 1n VISI BlE DAMAGE to ~11 Rtver level L ESS THAN 902 4 ei n sti'UC(IJres contatll!"(l eq\llprner1 ~ssa.'Y lor safe Shutdown.

or has caused damage as evte~erad 1:J! Control Room trtdicallOn d deg~ petformance d those S'(Sieml Rrver ~el GREATER THAN 919 It el OR Rtver level LESS ll-IAN 900 5 n el H..U fll'tl! or EXPLOSION .. ffecting the ()pe< ~blllly of 1'1- S.Nty HU1 fllti!'Mihin Pl'tOTECTI!D A !'tEA llound.ory Not Eo:bngul...,_d OMII'IIn SYtttons l'tfQI.Ii"d 10 hldsh or thlnt.,_ S life Shutdown 1SMonul:esoi0.1Ktion 0 HA2.1 I 1 I 2 I 3 I 4 I 5 I DEF I 0 HU2.1 I 1 I 2 I 3 I 4 I 5 I OEJ" I FIRE or EXPL.OSIOI\Itn any ollt'te followtng areas (Table H-1) FtRE tn bU11dti"'Q'S or areas OOf'IIIQI..IOO&IO any Table H-1 area None None not exongu!Shedwrthin 15 rnntJ:e$ cl control room nobficetlon AND or venficallon d a control room alarm Affected system parameter tndlcatJons show degraded performance or plan! pefSO~ report VISIB..E DAMAGE to permanent structt.Xes or equpment w tthin the speeif1ed area HU ll'te tuw C.I To~Ot ...Sf)l'ly.:l.lol'lll, ot Fl.iOTIITIIIbt* GUH o..rn..:l Detriment*ltoNonn~Op..-illl onoltr**l'l-0 HA3.1 I 1 I 2 I 3 I

• I 5 I DEF I 0 HU3.1 I 1 I 2 I 3 I

• I 5 I DEF I Report or detedton of toxiC or a~iar<< gases within or Report or detediOil of IDxc, asptr(Xiant or namrnable gases oortJguous to a VITAL AREA (Table H*1) n concentrattons that that has or could enter the stle area bour'Kiary lf1 amounts that may result 111 an auro~phefe IM MEDIATELY DANGEROUS can affect NORMAl PlANT OPERATIO'\IS None None TO UFE ANO HEALTH (IDI...H) a HU3.2 I 1 I 2 I 3 I 4 I 5 l oe=l 0 HA3.2 I 1 I 2 I 3 I 4 I 5 I DEF I Report t7r' L..ocal, Courty or State Offictal!llor evacuaHon or Report or detectiOn Ofga&e$ 111 concentration GREATER aheltering of srte persomel based on an offsite eveot THAN the Lov.'ER FLA MMABl.ITY U M IT W11h111 or conllgu:JUS to a VITAL AREA (Table H*1)

~11t0STI L I! ACTION l'tiSUIIIng lll LOUOII'ny slut ConlrOI Ollhe HU.f Cootlrm e<l SI!CUI'tiTY CON CliTION Of Tnreal: W!1ICfl tnattiJIK ll

,~.., Pot-iiiOeg<~lnth* L*.,.Ioi S~etyotth* I'IM~t a HG1. 1 I 1 I 2 I 3 I 4 I s I oeF I 0 H$4.1 I 1 I 2 I 3 I 4 I 6 I OEF I 0 HA4.1 I 1 I 2 I 3 I 4 I 5 I DEF I D HU4.1 I 1 I 2 I 3 I 4 I 5 I OEF I A HOSTILE ACTION has occurred such that plant per-some! A HOSTIL E ACTION is OOCU"nrg or has OCCI.Xfed within the A HOSTILE ACTION IS OOCUTI!"(l or ~S oocurred wtthtnlhe A SECURITY CONOIT IQ'\1 thai 00es NOT trrVOIVt! II HOSTILE are u~bioe 10 operate equipment requtred to ma1r1a1n safety Plart PROTECTED AREA as reponed 17,' the Sect.Xtty Shft OMoJER CONTRQLED AREA a s reported 17,' the Secu"fy ACTION as reported bj the SecU1ty SMt S~r IL1rct10ns Supervtsor Stilt Supervisor o HU4.2 I 1 I 2 I 3 I 4 I 5 l oe=l 0 HG1.2 I 1 I 2 I 3 I 4 I 5 I DEF I 0 HA4.2 I 1 I 2 I 3 I 4 I 5 I DEF I A a edible MNGP wciXlty threal notlficatOO A HOSTILE ACTION has caused laitt.Xe of Spert Fuel CoollflQ A validated nottl.cation from NRC cA an awkner allad< th'eat Systems a I'd IMMINEF'ff fuel damage IS likely fora lrestfy off. within 30 m tnlies cA the stte loaded reactor OOI'e tn pool o HU4.3 I 1 I 2 I 3 I 4 I 5 l oe=l A validated notification from NRC prcNidtng trtormatton dan atrcraft threat C*nnot 8e EJiabli$hed a HS2.1 I 1 I 2 I 3 I 4 I 5 I DEF I 0 HA5.1 I 1 I 2 I 3 I 4 I 5 I DEF I None Control room evacuatiOn has been ll"lll.tated None Entry ir1o C 4-C, Sh.Jtdo.vn OJ:stde ltle Cortrot Room, for AND oortrOiroomevacuatJon Control of the plant cannot be establi~hed per C .4..C, StllAdown Qui:Si()e the ContrOl Room, wth1n 10 mint.Aes t-;02 Othef Condltlons EldMtng Which Nllhe Judgment of !he Emlfgency HUOtherCondltlortsE..stlngwtlkhln lhe Judgmentof lhe Em..-genc:y OH-.,;tor w~"""' DKI*OIII<m of U.n..- ill l!m..-tlfi!Cy DH-Mior W*n - 0.<.1....-~ol Slt* Arn Emt<g*n<Y 0 HG2.1 I 1 I 2 I 3 I 4 I 5 I OEF I 0 HS3.1 I 1 I 2 I 3 I 4 I 5 I OEF I 0 HAS.1 I 1 I 2 I 3 I

• I 5 I DEF I 0 HU5.1 I 1 I 2 I 3 I

• I 5 I OEF I Oher cordtt1011s e xist whiCh Wtlhe judgment of the Emergency Other cordllona ex.tSI wt-.ch tn the judgmert eX the Emergency other coOOrhons exiSt which tn the _iudgment of the Efl"lefgenc:y Other conditiOns exist whch in the Judgnert of the Emergency Director indicate that events are tn prooess or have oocured Dtrector todicate that evenls are n p-oc:ess or have occurred Director tndicate ltlat events are In p-ooess or haVe OCCI..fl'ed Dtrector tndicate that evern are in p-ooess or have occurred Vlttich 1rrvoNe actual or trrmtnent ~ubE.t artaal core degadaltOn wtld'l trwotve actual Of kkely map flltkxes of plant fi..OCtlons whiCh 111Yolve actual or ~kely potential substantial degradat1011 whch indicate a potenbal del7lldallon of the le'llel of safety of or melting with potertiat for loss of COrfaJrment lflte!Jily needed for protedkm d the pubic. Any re~ases ere not d the level of safety d the plant An( releases are ele"pected ID the plant No releases of rad'oactive matenal requnng ormte Releases can be renonaljy e

• pected to e xceed EPA expected to res.Ut N1 exp>>Ure levels whiCh exceeo EPA be ~mtled to small fracttoos ol the EPA Protecbve Acbon response or ITIOI'IItori~ are expec:ted I.Xlless fu'ther Protective Action Gudeline e:w;po~ure levefs offsite lor more Protective Acbon Gl.ldeltne exposu-e levels beyond the ~ite GutdeNne expotl,J'e levelt; de!Jadatton d satfe!y &ystetrl$ OO:::UI$

than lhe tmmedate $1!e area

"""""~

0 ~~~ ~~J~s ;nJ~ ~klJJ;&}(£~!~&T 3 BOUNOARY

~l'lhquake None None None To.-radoStrtke Q E U1 .2 I 1 I 2 I 3 I .. I 5 I DEF I Aoctdenlcondittonsaflecttng aloadedcasio; C0 ~'£1.ENT~Y AocidentaiTr*nsfefCas-lr.Orop

~;!mllion in !te !JOO!d! b~n! Olr~Ji.~&Jtes 0

1oM ot lo;tded fuel&b'age QJ$11. CONANEMENT BOUNOARY

I I MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 107 of 120 12.0 FIGURE Annex A-1 Monticello Nuclear Generating Plant Emergency Action Level Matrix (Contd)

Right half of Page 1 of Form 5790-101-02

~ii~iiiiii:iiiiiiiii~ii:i:ii~i! GENERAL EMERGENCY I SITE AREA EMERGENCY I ALERT I UNUSUAL EVENT I M*!<<t:t!+!*!*!o!-,!<<t!t!*!o~

N1 LC4t ofAIOfhlltl"o-tndloH ofNMOniiM AC~to JA$AC l'o_C..,...,. IOttMOlllalllu$MtrM~CHtott.lnglot ..-r .U1lott of. . Ollllllt '"-"to t:....-allunM lorOitlATIII TKAN U l!llswtlll . ._ sourctfafOitL\TI!II TMAJI15ftllldM IUdllhll~ny.a.IOIUI Unglebll.... -*tr-*ln.aallonba.r:~

0 SG11 I 1 I 2 I 3 I I 0 SS1.1 I 1 I 2 I 3 I 0 SAS1 I 1 I 2 I 3 I I 0 SU11 I 1 I 2 I 3 I I Loss of offSite power to Essenllal busses 15 and 16 Loss of otrsite power to Easenbal bus.ses 15 <rod 16. AC power capability to Essert~l busses 15 and 16 reduced to LossofolfSJte power to Essert*al t:xAses 15 and 16for AND AND or1)' one or the follow!OQ SOI.M'ces IOf GREATER THAN 15 GREAT ER THAN 15 mm!J:es Faiure af 11 EmerverJCY Diesel Generator <rod 12 Emeorgency OK!sel rrirUes Fabe of 11 Emergency Diesel Generator and 12 Em~ C)eseJ AND Generator IOsuppfypoweriO Essenlialbus;!es 15 and 16. - 1R transformer, Genemtor to supply IXJWef to Essential busses 15 Wid 16 Essential buS&eS 15 and 16 are powered by thew respectNe AND - 2R transformer AND F1n1u-e to restore I)Oo'ler to at least one Esser1.al bus, 1!5 or 16,

• 1AR transformer Emergen:y Diesel Generators E 1ther of the following (a or b) wrthn 15 mnUes from the !Jrre of loss of both offsrte and - 11 EOG

a. Restorat100 of at least one Essential bus wlhin 4 hou"s onsrte AC power

• 12EDG is.DQlli kely AND OR Ar.f additiOnal s ingle fa ilure Will reSlit in station txackol.t.

b Cont*rung degradatiOn of core cooling based on Fission Product Barner morut.Ofing as indicated by RPV o s53.1 I 1 I 2 I 3 lev~ILESS THAN-126 1n {TAF)

Loss o fal vital OC power based on LESS THAN 1 06 VDC on the 125 VOC ma in distnbt.C:ion busses for GREATER THAN 15ITllrU:es 0

MZP......cltt.e"-~l,.....,.c~.,A-*

SG2.1 1 2 I

.."""-*Cooi..

I<<MitMAI MMu.! k-~1 -NOT...._II'III MIIIft..ll tM--..IIf .. b-~*

I I C..

o N2 , ......." - - ' ............ * ,....., ......_....._ .c-....... t. . . .

s52.1

-~,_._

.._.._~_...._.

I 1 I 2

.... o.... ......... ...-.. .... ......

I

......,W.MOT'-sflll I c IAl:P-...of"'-'kw ......... a,_~----..-c-...

SA2.1

• ~ ...........

.... ._~

I 1 I 2 I

a._ _ ._....

I

.. t--

O.,.e""-',....._.,.........,.._

a An a l..lomattc scram (trip) failed to sN.JtdoWn the reac1or lndlcation(s) exist that automatiC and manual scram were NOT lndicalton(s) eXIst that a Reactor PJO(ectlon System setpoirt AND SI..(:;C;eSS!"U in tedlX:ing p:JWer to LESS THAf'.l 4% was exceeded b lndcation(s) exist that all marual scram actions were not AND successfU in redtclng power to LESS THAN 4% RPS automatic scram didDQlreduce power to lESS THAN 4%

AND A ND c Either of the folow.ng ex1st 01 have ow.xred due to Art{ of the follOWing opera tOI" act100s m soocessfi.A in reducing None continued po.ver generation !XJWer to LESS THAN 4%

• RPV level canrot be restored and maintan--.ed GREATER

• manual scram pusht:Utons THAN OR EQUAl T0*1491n

• mode swrtch to sht.tdown

• l ndication(s) ex1st that heat removal is extremely

• M:ernale Rod lllRrtiOn (ARI) challerJJE!d as indcated "f Torus terf1)eratL.-e and RP-1 pressu-e cannot be mairtained LESS THAN Heat C<IP<~C*tv L1mt (C !>-1200 fig M, SPOS 78)

SUZI~Io~hhqulred~Wit'*'Tectnc.. llpKI!Ic.ellon ln..... IO None o ss.t.1 I 1 I 2 I 3 I Heal capecity LirTIII CI..M! (C.5*1200 fig M and SPOS 78)

I None

~~~*~~~~~~~~~~----L*

0 SU2.1 ~-: 1 I 2 I 3 I Planl is no1 brougtt to req11red operat.ng mode within

"""'""' IAA UMII'LAMMI!OLoss ot*-orMklltr trst-Annundellonor Ted"w'lieal Speciflcat iOI'IS LCO ActiOn Staternert Time lnclc.M6onln C-101111- WMh Dlw 11) e IIOMI'ICAIIIT

.

.-.:~~=.:..or(l)eon.-.,...,~

o sse1 I 1 I 2 I 3 I I 0 SA4.1 I 1 I 2 I 3 I 0 SU3.1 I 1 I 2 I 3 I Loss of most or a ll annuncaators assoc~ated wrth safety Uf\PLANNED loss of most 01 all annullC'ators 01 IndiCators UNPlA~ED loss of most or all ani'U"IC.ators or indicators systems on control room panels COO, C04, C05, C06C, C08 asSOCiated w1th safety systems lor GREATER THAN 15 assooatedwrth safetysystemsfOIGREATER THAN 15 m:ru:es on COI"1r01 room panels C03, C04. COS, C06C, ros, C20, C24 and C259 rTVnl..le s on control room panels C03, a:J4, COS, CXJ6C, <XI6, lAM. I None AND C20, C24 and C259. C20 C24ANDC259 c-SIGNIFK::ANT TRANSIENT in progess AND .UI UIIII"LAIIIMIRI Loss of All OnsiM or OffiiM c-.Nc:Mionl AND E11t~ of the follOWing (a or b)

Compensatory fiOI'WIIIatmng Indications are U"laVai la~e a A SIGNIFICANT TRANSIENT 1$ rn progress 0 SU61 I 1 I 2 I 3 I I OR Loss of all Table C-1 OflSite corrrm..n cations capabll*ty AND affectirg the ability to perform rOOine operatklns b . Comi)Msat<<y non-alaiTT"Iing indications are unavailable.

lndlcaiK>m needed to montor the ability to s.hl.( down the react01, maJntaJnthe core cooled, maintain the react01 coolant 0 SU6.2 I 1 I 2 I 3 I I I system 1ntact, and ma*nta*n conta1nmen1 irtact a re unava ilable Loss of all Table C-2 offstte commt.ncat10ns capability 0 SU4.1 I 1 I 2 I 3 I Oflgas Pretreatrrer1 RadiatiOn Monrtor (RM-17-150A and B)

'""""" None None None hi!11 radia tion alarm (4*A*12) reoeived indicating fuel clad d egradatiOO O SU4.2 I 1 1 2 I 3 )

Coolant sample act*vrty GREATER THAN 0 2 11CiJgm dOSe eqUvalen1 1*131

• u~IIIC* L.-..

0 SU51 I 1 I 2 I 3 I Unident ified or pressure boundary leakage GREATER THAN None None None 10 gprn OSU5.2 I 1 1 2 I 31 Identified leakage GREA TER THAN 25 g:rn None None None 0 SU81 I I 3 I All UNF'l..ANNEO extended posrtive period observed on nuclear instnmematlon

~ FO t.t 0 FS1.1 0 FA1.1 0 F U1.1 Loss of ANY Two Bamers AND L oss 01 Potential Loss of Thnd Loss 01 A:)ter11al Loss of A NY Two Bamers (Table F*1) ANY Loss or ANY Poter1ial Loss of EITHER Fuel Clad OR RCS ANY loss or AN'( Potential Loss ofContaurnent {Table F*1)

Barrler(TableF*1) (TableF*1)

Table F-1 FISSION PRODUCT BARRIER MATRIX NOTES 1 The logiC used for these n ltJatmg condrt100s reflects the folloWing con&lderallons The Fuel Clad Barrier and the RCS Barrier ar e Wi!I!1Jted more heavfy than the Conta llmenl Barner. UE ICs associated wrth RCS and Fuel C lad Barriers are adctessed under System MalflllCtion ICs..

At the Srte Area E~gency level, there must be some ability to dynarrically assess how far present condibons are f rom the threshold for a Gene-ral Emergency For exa~Jl)ie, if Fuel Clad and RCS Barrier "loss' EALs exJsted, that, rn addition to o lfs1te OOse assessmer1s, W(I(Jid reql.ll"e oor11nual assessments of rad10aC!Jve II"M!ntOf)' a nd containment irtegrty. Alternatively, 11 both Fuel Oad and RCS Barrier "P\::Itert1al Loss' EAL.s existed, the Emergency Director wolid haVe more a ssurance that there was ro immedate need to escalate to a General E ~gency.

The ability to escalate to higher eiTIE!fgency classes as an event deteriorates must be maintained. F01 example, RCS leakage steadily ilcreastng woi.Jd represert an increastng fiSk to pubic healltl and safety.

2 F1SstOn Proruct Barner ICs must be capable of address.ng event dyna.ITllcs Thus, ltle EAL Reference Table F* l states that itm11nert (i e., with1n 2 hoi.Xs) Loss 01 PotentJa l Loss stoUid result in a clasSification as if the affected threshold(s) are a lready exceeded, partiCIJaft)' for the ~r emergency classes Fuel Cladding Barrier Reactor Coolant System Barrier Primary Containment Barrier 0 Loss 0 Potential Loss 0 Loss 0 Potential Loss 0 Loss 0 Potential Loss

1. f?t1!J\'W P>olg!QI Acc!IYrty I ftYf'l f?t!marv CooJaru ActiYY l cvet 0 1. ~ 0 1.~

" '~ 0 1~

0 0 1 Coolant Activity GREATE R THAN Not Awlicable Ofywell Pressure GRE ATER THAN Not Applicable Rapid uoexplained decre ase n Orywell Pressure 56 PSIG and 300 11Cilgm 1*131 dose equivalent 1 84 ps~g NOT caiJSed by a loss of ctrywell presSU"e fOllowing irwt.al IncreaSing ON Cooling OR OR GREATERTHANOREOUAL TO Orywen pressae response not 6% hydrogen and GREATER THAN consiStent Wllh LOCA. ooodl10ns OR EQUAL TO 5% oxygen in

• nQcat*ng conta1rmen1 breach Orywell Of TOfUS 0 2. Reactor \'esse! Water t eye! 0 2. Reactor Vessel Water eye! l 0 2. Reactor Vessel water Level jcoi22JR~e~act~n~ry~e~,..;;jiiM!~t;;;er:i;tfYf~l- -t<0,.-;2;:-.R~e~*~~Q[~V~e~....

~wo;>ti<i<<LLOieve!iOj~~ 0 2. RejtCt()[ V essel water Leyel Level L ESS THAN *149 in Level LESS THAN *126 in (TAF) Level LESS THAN

• 126 in. {TAF) Not AppliCable Not Applicable Pmnary contaiYnent flooding reqUred Fission Product (MSCR'M.)

0 3~ a 3. ~ o 3 (;NMT IM'MIOO Ea1'~ rt or e.tpass o 3 CNMT hiQill'loo f:@c or fttpasa Urnolable Main Steamline Break as RCS leakage GREATER THAN 50 FaillJ"eofbolhvatves in art(one l1ne Not Applicable M""ldrcated by the faiiLK~ of both !PTl inside aywe* to close ANO<bwnstream pathway f-- - - - - - - - -- -

MSIVs in a ny one hne to close ANO OR to the ertv'Jrormert extsts EITHER Un solable pnmary system leakage OR High MSL flow or h9"1 steam outside ctrywell as indicated "f lr1eo!lonal Primary containment tlJ1ne-l temperatlle ann.Jnciators Any Secondary Conlairrnent area venting r1 progess per EOPs OR lemperalllre GREATER THAN ma;.r OR Oned repor1 of steam release normal (C > 1300Tat>le W)

OR Unlsolable pomary system leakage ANI Secondary Cor1arrv nen1 outside ~I as ind1eated hV area radiation GREATER THAN A"'! Secondary oonta~rrnent a rea max normal (C5*1300 Table X) temperatlJ'e GREATER T HAN max safe (C.5-1300 Table W)

OR A"'! Secondary oonta~rment a rea radiationGREATERTHAN max safe (C.S..1300TableX) 0 3. prvwe!! Racyttoo Mgortgnoo }-;c<JJJ3!!lriwr!:§'~'R~od!a§'non>il!r!M.2ioo!iltorl!iirnw-J o 4 Dryyu:nRamaroo Mgmtorm Cont:a1rmer1 H1!1J Range Bad I'" NQc Applicable Conta1nmen1 High Range Rad morwtor reading GREATER T HAN monitor reading GREATER THAN 1.5E3Rihr 65R!IY 0 4. ~ 04~ 0 5.~ 0 5~

Not AppliCable No!Appl>oable Not .Appicable NotAJ.1)11Cabie 0 6 Emergency Director JtJdcrmeot a 5. Emergency Q!res;tor tuooment 0 6. frnergeooy P,recror **dQmert 0 6. Emergency Director hmment a 6 Emergency O.rea.x ' trirr'r!ftrf o 6 Ememeocy Djrect9f ll!l!Jmell Art( condibon 11'"1 the opfliOn of the An( condioon 1n the op~nion of the Ally condrt10n in the op1Aon of the Any conditiOn in ltle opnon of the A~ condition in the opinion of the An( conditKJn in t he opn100 of the Emergency Director that inQcates Emergency Director that indicates Emergency Director that 100cates Emergency Director that indiCates Emergency Director that indiCates Emergency OirectOf that indicat es l oss or Potential Loss of the Fuel l oss 01 Potential l oss of the Fuel Loss or Polent~al Loss of lhe RCS Loss or Potenlial Loss of t he RCS Loss or Poter1~1 Loss of the Loss o r Potenlial Loss of the C~Barner C lad Barrier Ba rr~r Barner COnta1nmeot Barrier Conlainment Barrier Tabl* H*1 EAL Class ification A r* as T.,._ C-1 Ons. . Corrmuntca~tloM Sysi!Mns Reactor Bldg Comnerc1allelephones HR:! Bldg Plari: telephOnes Tubne- Bidg Portable ra dios Conlrol & AdiTllniStratiOI'l Bldg Plart page system 0.~ Generator Bldg 0.~ Fuel 011 Transfer House EFT Bldg Tallie C-2 Ol'htte Conwnuntc.tloM Systems l ntake Stru:t.ure Corrrnercial telephones 1

Security Blilding FTS Phone System 1  !

Secunty D.esel Generator Buld1ng Radio Rece*vefiTransmtter

~

Nai*I: TMHbuildings . . cnlyODrnoderedwhen cllost/tftl9peo-MU2.t . HAl.tend~2 *~

Modes 1, 2, 3 ~

MONTICELLO NUCLEAR GENERATING PLANT 5790-101-02

~ EMERGENCY ACTION LEVEL MATRIX Revisio n 10 Modes: IT] [TI [TI L!J [!] I DEF I Page 1 of2 Power Operation Startup Hot ShutdOIMI Cold Shutdown R~fueling Defueled Approval: ~

I I MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 108 of 120 12.0 FIGURE Annex A-1 Monticello Nuclear Generating Plant Emergency Action Level Matrix (Contd)

Left half of Page 2 of Form 5790-101-02

~:~:~:~:~:~:~:~~:~~:~:~:~:!

~::::::::::::::::::::::::::::::::~

GENERAL EMERGENCY I SITE AREA EMERGENCY I ALERT I UNUSUAL EVENT I 11:0 1 Offsltt Don ltKUIIIng from.-. Ac!Ua!CM' lmminenll lt...iiW ot Oll'sltt Oose ~HUlling *om in ActUIII Of """**- ~ti tHe of

!.~.:~~~:=~~s:.=~==:~-:.~~~~r. ~U1 :n~~~':!:.~=~~=~:.=.~~!:~=!~:

~ 11 c;.,....,. lt..:lo.clhtly beNds 1000 mlllom TI!DI! or 54100 mltwn G KI'OUS lbdlo~lvlly EXCM<I'i 100 ml f - T1!.01: Of ~mit'"' AA1 lhyroldCDe:fort,.Actv*or Pro)M:tf<l Owllllon oi i:M ~MM Thrl"old Cot! lo< lh* Ac:tU'III Of Plojld..:l O..Mionoftht ~* - 1111.-.uiii LimllfO<Uflllinii"Of Long.r Ill__,. Umll for flO lllinuln Of Longer UsklgAciWIMIIIOfOio.gy fiQte* lf doMH~I~iillll! ~*~bjoe *tt~eiJmeof Note- lfOow*-rnenl tet<.~bilre*v*Q,~ at the timed a RA1.1 I 1 I 2 I 3 I 4 I 5 I DEF I a RU1 .1 I 1 I 2 I 3 I 4 I 5 I oeF I

<ieeli1r;Jlon,ltlecl*~*tlon~ld be bil~onRG12~~r;J Qecfilflllbon.ltle ci"Wbt1011 ~ld be bneQ onR$12 i~d VAUD reading on a"¥ etf!uert montor that exceeds 200 times VALID reading on artt effluent moN!or tturt e Kceeds two limes RG1 1 V'.tlilenecnNry dedarabonsshouldnotbe~yed.-rting RS1 1 'M'nle necftNJY Oeclwlltion$ thJukl no1 be Oel1ye<;l I"'Mtiting r~lta,thecknoeas~-.houldbe n rtL;oted/00<11lletedrn Qfclec raulta, the dOM n~ 5houkl be irutiil;ile<l/ eompleWd in ordef the alarm selpolnt establiShed by a currert radioact~i ty the alarm setpo1rt establ~ ~ a w rent radioactiVIty

!Qd~rni,.,.if tn*clns.ificll:.on~ldbew~~:,~..,~ W detemroe li the c~ifieaOon thoukl be ~uently~l*ted chcharge perrnit for 15 min.Jtesor loogef discharge permit f or 60 minl.tes or larger a Rau l 1 I 2 I 3 I .- Is ! oeF! Q RS1.1 I 1 I 2 I 3 I 4 I 5 I DEF I VALID reading on af'¥ cA tnelollo.vtng rad.aUon rmnitors that VALI Oreacllngon any olthe folk:PN.ng rad.abon morMtors lhat 0 RA1.2 I 1 I 2 I 3 I 4 I 5 I DEF I 0 RU1.2 I 1 I 2 I 3 I 4 I 5 I OEF I exceed&orisexpectedto eiCceedthe readirg shown for 15 exceeds o r IS expected to exoeed the reading shown for 15 VAUD readir-G on anv o1 the folowng rad1a11on montors that VALID reading on artt of the follow1rg radiaHon montors that mtru~es or torger mlluesork:w'1Qer excee<~s the re ad1ng Shown for 15mrues. Of lOnger e)(~ the reading Shown fOf 60 ITllf'llAes. or k>nger Monitor GE Mon1tor SAE M ontor Alert Monitor UE

~ ~

Stack Emuent Mor11tor 2 .1e9 ~cnec Stack Emuent Monrtor (ChAorB) (CtlAor8) 21E81-1Ctl!ec

~uentMoN!or 146E7 }ICilse<:' ~uent Monitor 7 3E5 J.1C ilsec RB Vert Eftluern Morvtor 1.5E8 ...Qisec RB VertEffiuent Monrtor 1.5E7 "Qisec (ChAOf"B) (ChAorB)

~llelt.-1 (ChAorB) (CtlAorS) RB Vel1 Etnuel1 MoMor 2 16E6 }ICilse<: RB Vert Emuent Monitor 2. 16E 4 "CWec c-~ l.JOi.jg (ChAOfB) (ChAorB)

LW<I Serv~ceWater NIA Service Water NIA I..I!Wl<l J.iOl.lg Oscharge cared Monrtor NIA Dtsctlarge Canal Monitor NIA ~ce~ec 31400cps. SeMce- Water 314 cps TBNWS NIA TBNWS NIA Discharge canal Mol"lltor 93 000 cps. O.Charge canal Monitor 930 CfJ5 T BM\'5 900 000 cpm TBN'M5 37 752 cpm a RG1 .2 I 1 I 2 I 3 I " I s I DEF I 0 RS12I 1 I 2 I 3 I 4 I 5 IDEF I

[)ose a ssessmen~ using actual meteorolOgy tndlcates doses Dose as.sessmert uSIIll actUSII meteorOlogy indicates do6es 0 RA1.3 I 1 I 2 I 3 I 4 I 5 I DEF I 0 RU1 3 I 1 I 2 I 3 I 4 I 5 I OEF I GREATER THAN 1000 rrRem TEDE or 50Xl rrfiem thyroid GREATER THAN 100 mRem T EOE or 500 rrRem thyi'Oid CCE Confirmed sample ana~Sis for gaseous o r liQuid release Corilrmed sall"f.'leanalysis ror gaseous or liquid release CDE at or beyond the s~e boundal)' at or beyond the s1te bolndary indicates coooertrallons Of release rates, With a release Kldicates ooooertratJont or re~se rates, with a release clrratklnof 60 mirJJtesor longer, in excess ol two limes a:x;M I I I I I I OEF I RSU I I I I I IDEF I W"at10nol15 rnm.i:E'$ or longef, lll e Kcess ol200hmes OOCM

J RG1 ,3 1 2 3 4 5 0 1 2 3 4 5 Field survey resUts indicate clo11ed W1ndow dose rat es e><oeedng 1000 rrRem'tw expected to oort1nue fOf more than Field Sl.f\leY results indicate dosed v.indow <Dose rates exceeding 100 rrRem'tw expected to oont1nue fOf 1'1"10fe than one hotx, at or beyond the site boundary one hour, at or beyond the s1te boundary * -40 bmes CXX:M calcuiated limt OR OR ** 48 tfnes OOCM calcUated ~ml AnalySis of field Sl.f\leY saf1l)le& indicate thyrOid ca::: oi501Xl Are~ o f neld 5\IVeY sarrl)les Indicate tt.,.rotd COE ot 500 mRem for one hou- ol inhalation, Bl o r beyond the srte mRem for one hou of 1nhala!J011 at Of beyond tre Site Abnormal Releilse

""""""' tx>undo'Y Effluen1 ltA2 o.n.g. toh..tllllltd~utlor Lon atW~* L.wollhliiiHii* Of Wll

~-=: In m.Uncovll1ng oflrndllllltoel ~ut>l Outsldt m. ~nctOf 0 RA2.1 I 1 I 2 I 3 I 4 I 5 I DEF I 0 RU21 I 1 I 2 I 3 I 4 I 5 I DEF I A VALID alarm Of reading on any d the foiiCPNJng rad~anon VALID ln<icationof l.riCOOi rolledwater level lowec*ng n the tTIOilltors reactor refue~r"G cavrty, spent fuel pool, o r fue! transfer canal With atllffill<iated fuel a ssemblies rema1nir"9 covered t1)' wateJ Morutor AlarnvTrip as *ndicate<li)jarrydthefOIIo<ooflnQ A:~ ~~;~=~~~ Unexpected Spert Fuel Pool ION water level alarm V~ OO&ervat10n of an unoontrofled water level drop A-3 1f127 RBW SI:a11Way 100"""" belOW a fuel pool s.ltinYner wge tank lf"llet RM-17-452A Reactor Buld*fll VertJ.Iabon 26m""'

• Observation of water leakage 11110 the liywell 01 the reactor Exhaust P leru-n Mor"litOf 0"1 A building from PIPII'Q penetrations surOUndlf'IQ the ciyweM R M-17 -4528 Reactor Build*ng Verttlabon Exhaust Pleru-n MonitOf 0"1 B AND RM-H -453A Fuel Pool RadiatiOn MontorCh A 50 mRihr Artt UNPLANNED VALID Area RadiatiOn Morrtor reading rise RM*17-4538Fuel Pool Rad1at10n Mon-torChB 50 mR.hv asindicated~ af¥ olthe f011owtng A- 1 1027 R8NELo.v A*21027 RBN HIQh None None

• A.J 1027 RBWStairway

• RM-17-453Aor BWPootMonrtoringSystem a RU2.2 ( 1 I 2 I 3 I 4 I 5 loeFI Artt UNPLANNED VALID Area RadiatiOn Morttof reading nses t:y a f.actor oi1000(J<Ier normal* le'llels

" lolormallevMe*nbeeon~e<lutt.l"llghnt rNdirlgintMp.5t twenly-lour hou~e-.;eb;:l*ngtheeunent pco*k v~

HU1 NOIIurol - O.~lru~tln Pllotnomtn~ AII"K bng 11"1* Plonl PlfOTECTEOA~EA.

a HA 1.1 I 1 I 2 I 3 I 4 I 5 I oeF I a HU1 .1 I 1 I 2 I 3 I 4 I 5 I oeF I SeiSmiC evert GREATER THAN Operat1ng BaSIS Earthquake Earthquake lett 11'1 ptant as indicated t:¥ (OBE) as indicated ~ ANUlCialor OPERAT IONAL BASIS Consensus of Control Room operators on duty EARTHOJAKE (6.C.13) rteeiYed AND a HA 1.2 I 1 I 2 I 3 I 4 I 5 I DEF I a HU1.2 AnrlJoclator EARTHQUAKE {6-C-081 receiVed I 1 I 2 I 3 I 4 I 5 I oeF I Tornado or t41 wnd& GREATER THA/11100 l"fl)h Wll.hn plant PROTECTED AREA boundary and resiA*fl!n VISIBlE Report t1)' ~rt persomel of tornado or hig'l Wlrdi. GREATER DAMAGE to any plant structaes leq.Jpmeflt (Table H-1)or THAN 100 mph Wlthlll plart PROTECTED AREA boun:tary Control Room *f'!Ckatoo of degraded perlormance ol th06e a Hut.3 I 1 I 2 I 3 I 4 I 5 I oeF I systems VetiiCie crash ll'llo pant stn.dtxes or system& within pl3nt 0 HA1.3 I 1 I 2 I 3 I 4 I 5 I DEF I PROTECTED AREA boundary Vehicle CBSh Wilhlfl plart PROTECTED AREA boundary and a HU1 .4 I 1 I 2 I 3 I

• I 5 I oeF I resulting 11 VISIBLE DAMAGE to Btl( part struciUres o r Re port b'f' part personnel Ofan um rt1C1paled EXA..OSIOI">>

eqi.JII)ffiel"'l ther~n (Table H*1) orCortrOI Room indication of Within plant PROTECTED AREA boundary rewltng 1n degraded pedorrna rce of those systems VISIBLE DAMAGE topermanentstn.dtXe Of eq.Jpnert None None 0 HA1.4 I 1 I 2 I 3 I 4 I 5 I DEF I 0 HU1 .5 I 1 ( 2 I 3 I 4 I 5 I OEF I Tu-tline failure-generated rnsSJies reS\Jllll any VIS IBLE Report oft..-blne fa ilure reSIAI:*r"G 1n C3Sing penelratoo or DAMAGE to or penetratiOn a al'fr' plart areas (Table H-1) da1T\21ge to tne or generator seals a HAu I 1 I 2 I 3 I 4 I 5 I DEF I a HU1 .s I 1 I 2 I 3 I 4 I 5 I oeF I Uooortroled IIOodrlQ in areas (Table H-1) or me p4art that l)ncor(rolle<l H()()(jirg in areas (Tabte H ~)of the p~Mtthat h&'S results n degaded safety system performance a s 1nckated 111 the potential to affect safety r~ated ecp.~pment needed lor 1t1e the oortrol room or that creates.ltiC1JstriaJ safety hazards (e g, ctXrert operatii"IQ fOOde elecbic 1-hock) lhat precludes access necessary to operate or tTIOnrtor safety eQUipment 0 HU1.7 I 1 I 2 I 3 I 4 I 5 I OEF I a HA1.s I 1 I 2 I 3 I 4 I 5 I DEFI A"'J of the fOIIOwlf"lQ high rive r level or bw nver level ooconerw:::es affecting the plait PROTECTED AREA Eithef Of the followlllQ OOCU"eoces w1thm pla rt PROTECTED Rwer level GREATER THAN 918ft el AREA boundary and resullfll in VISIB..E DAMAGE to part

• RJYer level LESS THAN 902.4 ft el strl.du"es oon1a m1ng ec,.Jipnerl necessary for safe sht.tOOwn, or has caused damage~ eVIdence<!~ Corcrol Room indicatJOil Ofdegaded performance ol those systems Rrver leveiGREATERTHAN919rtel OR Rrver ~ LESS THAN 900 5 tt el t1A2 ,I~[ Of U ,LOSIOH -'!Mcllng tllot 0p<<<<Millyol fl'lar<< hlery HU2 Fl~f Withln , ~OTtC TEOA~EA 8oundilf)' Hot h llngo.ts lltd Wllllln

~" 'M$1f*q..>~* ..t*o h* ~bll$111)0 *~"~' s...r, Shuldo- 1 ~MN.... uor O.I* ( IIOh 0 HA2.1 I 1 I 2 I 3 I 4 I 5 I DEF I a HU2.1 I 1 I 2 I 3 I 4 I 5 I oeF I

~"* Of FIRE or EXPlOSION in &f¥ ol the f olowlng areas (Table H -1) FIRE in buildings or areas cont9Jous to Btl( Table H-1 area Explosion None None not extirrgUished within 15 mnutes of cortrol room notifiCation AND or ver*fica t*on of 11 control room alarm.

Affected syst em pa ra meteJ 1ndicabons show degraded perf()fi"Tl;,noe or planl per$01lnel report VISIBLE DAMAGE to permanent sltuctures Of eqUipmert w.ttun the speafied area

os. n,rnm..,.

t~Ef~~i~~~~~i~~::'Fi~::~~:

HUl lt.... 01 ToKit . A~pi>Jr-.;lanl . or Ga w~ OM~~>~td Oeulmentolto HOfmol ~1atlon ofi:M 1'1-0 HA3.1 I 1 I 2 I 3 I 4 I 5 I DEF I 0 HU3.1 I 1 ( 2 I 3 I 4 I 5 I DEF I Report <X detectoo or tOl<IC Of &~1art gases within <X Report or detecoon Of tox.c, a~lart Of flammable gases contrguous to a V tTALAREA(Ta blf! H-1) 111 concentratiOOS tturt that has 01 could e rteJ the Site area boun:tary m amourts that may result in an atmosphere IMMEDIA TELY DANGEROUS can affect ~ M AL PI....ANT Cf>ERATION$

None None TO LIFE AND HEAL TH (IOI...H)

!J HU3.2 I 1 I 2 I 3 I 4 I 5 IDEFI 0 HA3.2 I 1 I 2 I 3 I 4 I 5 I DEF I Report b'f' Loca~ Courty or state OffiCials for evacuaton or Report or detectiCIII Of gases 1n ooooertrahon GREAT ER shenering cl site persomel b8sed on a n offSite evert THJV.J the LONER FLAMMABILITY LIMIT Wll.hn or oont9UOU6 to a VITAL AREA (Table H.1)

HG1 HO$llLE AC"nOH ~.suR~ kl Loss of ,..,vsk~ CorMrol oflht HM HOSTILE AC"nOH Wn.hkl tlw OWHE~ CONT~OL LEOA~EA or Hu.t Coniii!Md SECU~I TY COHOi llON or TIY*a~ Whkll lndlu t .s a

~a.::lllly. Alfi:>Ofl~ An~k ThtUI Pol.!llla!DI>grad.iltiOnlnm* UvMOI ~I..yorln* PIJMII:.

0 HG1 .1 I 1 I 2 I 3 I 4 I 5 I DEF I 0 HSC.1 I 1 I 2 I 3 I 4 I 5 I DEF I 0 HA4.1 I 1 I 2 I 3 I 4 I 5 I DEF I !J HU4.1 I 1 I 2 I 3 I 4 I 5 I OEF I A HOSTILE ACTION has occwed wch tMt ~rt pef6()f"t)tl A HOSTILE ACTION IS OCCU"nng Of hn OC(;Urred Within the A HOSTILE ACTION IS occurring or has OCCU"red Within the A SEClRITY CONDtTION that does NOT lnvot.le a HOSTl.E are ...nable to operate eq ..11pment reqUired to ma11"U1n safety Plant PROTECTED AREA as reported t1r' the Security Shin CNVNER CONTRO..LEO AREA as reported t1y' the Secu rity ACTIOO ~reported bV the SectXily Shift SUpervisor f\Jnctions S~ISOr Shift Supervisor a HU4.2 ( 1 I 2 I 3 I 4 I 5 loeFI

I HG1 .2 I 1 I 2 I 3 I 4 I 5 I DEF I 0 HA4.21 1 I 2 I 3 I 4 I 5 I DEFI A cre<lble MNGP sectxty threat notification A HOSTILE ACTION has caused fa1I1Xe of Spent Fuel Cooi!Og A validated not1flca tion from NRC Of an a r11ner attack threat

&{st em& and IMM INENT fuel damage IS blolely for a ffes.hly 01'1* Wltl'lln 30 m.ntAes o1 the srte loadedreactorcoreinpool 0 HU4.3 I 1 I 2 I 3 I 4 I 5 IDEFI A validated notJficat*on from NRC pr()llfl()rg informaoon Of an a*rcraftthreat I I I I I I DEF I

..... I I I I I DEF I 0 HS2.1 1 2 3 4 5 0 HA5.1 I 1 2 3 4 5 con1101 None Cortrol room evacuatiOn has been Initiated None Entry into C 4-C Stn.t<Xlwn Ot.cside the Cortrol Room, lor AND oonuOI room e¥acoatoo Cortrol of the plart cannot be establi!.hed per C .4-C Sh.Jtdown o.tside the Cort¥01 Room, w ~hn 10 ITllni.Aes HG201tt.Condltlons E~ lsllng Which l nlhl~ ofl llot Emergency H$3 Olher Condlllons Eldstlng wtokh 1r1 tllot Judgmenl of lh* Emtrgenc:y DI,.<.!Of W** - O.C I~*~tlon ofG-ral EmlfQIOn<v Dlr.,;tOf Warronl o.d*OIIkm or Sll* Afu £merg"""~

I HG2.1 I 1 I 2 I 3 I 4 I 5 I OEF I 0 HS3.1 I 1 I 2 I 3 I 4 I 5 I OEF I 0 HAe.1 I 1 I 2 I 3 I 4 I 5 I DEF I a HU5.1 I 1 I 2 I 3 I 4 I 5 I oeF I ether conditions exiSt which 111 the JI.Dgnent a the Emergency Other cond1I1011S exist ......nch in the judgment of the Emergency Olher coo01Jons exrst ¥otiich 1n the~ ol the Emergef"ICY Othel oondltons e:..ISt which 1n the~ o f the Emergency Diredof indicat e that events are in process or have occurred Director indicate that evt!nts are 1n process o r have occured Director 1ndicate that events are m p-ooess or have ooourred Director 1n<1cate that~ a re m p-ocess or have OOC!.fled which involve l!tCtual or irTmlnert s\bstartJal core degad211boo which 1nvotve actual or ~kefy m!IJOf fa1k.fes of pant !Uf""d:10ns which Involve actua l or likely potential SJ.bstartial degradation whiCh indicate a potential degadatiCIII of the level of safety c1 or melting Wllh pot ential for loss ot conta1nmert integrity needed for prorectJOil o f the pWIIC Any releases are oot ol the ~of safety of the plant My releases are expected to the pant No re ~ases ol radioactiVe matena1 recp.~rlllQ oti"Site Releases can be reasonably expected to exceed EPA expected to rest.it 111 exposure ~els whiCh exceed E PA be ~miled t o small fractiOnS of the E P A Protective .1\ction response or morltonrg are expected unless futher Pro tectr.te Ac1JOI1 Guideline exposu-e levels offsite f or more Protective Acllon Gudel1ne exposu-e levefs beyond the srte GJ!del*ne exposiSe ~Is degradatiOn o1 safety sys:cems. OCCIXS than the immediate ~te area tx>undo'Y None None None

I I MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 109 of 120 12.0 FIGURE Annex A-1 Monticello Nuclear Generating Plant Emergency Action Level Matrix (Contd)

Right half of Page 2 of Form 5790-101-02

!llllllllllllllllllllllllllllllll~ GENERAL EMERGENCY I SITE AREA EMERGENCY I ALERT I UNUSUAL EVENT I

!*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*!

~

0 CA 3.1 I I

_. I CA3 L-ti AI Otfsb~ lfiCILOMoi .U elftth AC~-~o I 4 I 5 I OEF I CUS L-a eu;.~*~..

of A.II Oiftll* ~ to ! ....,. . .... for OII!ATP: TMAll I

• I sI I -

Loss d oft'..s.te poNer 1o Essential busses 15 and 16 loss of oft-lite power to Essential bus.so&S 15and 16 for GREATER A ND ~ 15 mn.rtes Faii!Je d 11 Ernergeooy Diesel GeneraiOf and 12 Emergency AND Diesel Generator to supply poNer 1o EsSoefltlal busses 15 and Alleastooe Euential bua, 15or 16, ispa.yered t,.. its 16

....... emergency <le6t'l generator AND None None Faii!Je to restore power to at leas.! one Es.sertaal bus, 1501" 16, CU7 UJIIOI,.ANNI:D Lon of ~ DC'"-' for QIIIATI:II TMAN U wrthln 15 m.-.u:es from the time ollossof both offslte and onsite AC power 0 CU7.1 I I 4 I s I I UNPLANNED loU 01 '<rita! DC pcmtr to ~ured 125 VDC bu~S ba$ed on LESS THAN 111 VOC bus wltaQe ndicatx:m.

A ND Fatl<.re to restore powe r t o a t least one reqllred 125 VDC bus wlth1n 15 rnrutes from the tune of loss C01 LOf.* of ffi'Y I-ory A~PVII Ciid .......-v .....

C~Ctl. . . . . . . . . ln-.... MIIP\Itt ln . . II:N

[I

J CG1.1 ::;:c=:~=:ID*:::I I J*DI=:: J 0 CS11 I I 4 I 0 CA1 1 I 4 I I 1 Los:& of RPV II'!Vertory as indicated by une>epiane<:l rise lf'l W th Secondary Coruirmerc ll!:t establl$hed LOB& of RCS invertory as tndicated bof RPV level LESS THAN dryweg floor Of e~pnert d ran SUrfl> tevet a RPV i1Yellloty as indicated by RPV le~ LESS THAN -53 in -47 11'1 A ND OR

2. RPV Level b. RPv level carnot be monnored for GREATER THAN 30 0 CA 1.2 I I 4 I I a LESS TKAN-126 1!'1. (T~)forGREATERTHAN 30 mlnuteswlflamof RPV In~eniOI')' as Indica-ted b)' elttler LOS$ ol RCS invenlory as lf"l(lcated bof U""lt'XPained \eVeol rise in mnct~

• Unexpau"led level nse lf'l dryWell ftOOf or eqUipment drywelt noor or eq..11pmert draun sumps.

OR dransufll)& A ND

b. camot be montored with lnc:l lcation d core ...-.covery for Erraoc Source Range Montor lndlcatiOI'I.

RCS level cannot be monitored for GREATER THAN 15 GREATER THAN 30 rYln\Aes as evidenced by l!lf¥ of the 0 C S1 .2 I I I I 4 I I mrues.

fOllOw!~ W th Secondary cortanmert e&U~bli&hed

• Errabc Sou-oe Rarge Mon1or irdcatoon a RPV l"'vento.-y as indiCiteel by RPV le~ LESS THAN -126 10.

• Refueling:Roorradia\Jonle... GREATERTHAN3 R.tlr (TAF)

A ND OR 3 . lnd1C8t101'1 of CONTAINMENT challenged as inclcated by b RPol level (;tl n ~bemoniiOfl)dforGREATE RTHAN30 any of lhe follow\rg minutes'Mtl a los.sofRPVirrterttol)o asindicatedt)'Jeittler GREATER THAN OR EQUAL TO 6% hydrogen and - Urlexplamed level nse .n drywell nOOf or eQUipment GREATER THAN OR EQUAL TO 5% oxygen in pnmary d t8rl$Urfl)$

corta inmert Errabc Source Range MoMor lndicat10r1 Dtywe* pressu-e above 56 p&ig CSZLGM fll ffiiY~.......,.~C..O.., ItMI ...._..~ C Ul ~IO a...fti~ I......_, _,,,..,.... , ...... .IIPY Itt._..Fwl .. . . ffiiY Secondary oont~nment rot established T wo or more Rea ctor 8J1kling a reas exceed Max Safe Ra<iatJon Levels (C 5*1300, Table X) o cs2.t [I::;r;:=;:~:::::::.c:::~!;*gi;::::J W lh Secondary Cortairmert J!l1 establiShed 0 CA2.1 .~~:;:r:=;:~:::::r:::::::r1~sg1;:J Loss ot RPV ~ventory a s indicated by R PV level LESS a cu2.1 1c.:;:~;;:::I::I=II:::*o1:;~

UNPLANNED RCS level lOwering below the RPv Range ror a RPV i'IYOO!ory as indicated by RPV le~ LESS THAN -53 in. THAN -47 in GREATER THAN OR EOJAL TO 15 rlllnl.les OR b RPV level cai'I'IOI be morutOI'ed wJth lrdicatiOI'I of core 0 CA22 I I 5 I I 0 CU2.2 I[ =r==:~=I=II:::*0 1=]

~"~~b'larry-d thefOIIOWirg Loss Of RPV invertory as indicated t:lV unexp11!11ned level nse 11'1 Loss o f RPV Inventory as llldcated by u nexplauned level nse ll dryweu floor or eq.11pmen1 dra1n sumps. d rywell noor or equpment ch*n s.umps

• ErratiC Source Range Monitor IOdicahon.

• Rt!'uelng FIOorraa.atton levet3 GREATER THAN 3 Rlhr. A ND AND Cold SCI I I I l s i I RPV level camot be moritored fa GREATER THAN 15 o c s2.2 1 R PV level ca nnot te montored mn..tes W th Seoondary Coi'UII'IITiert e&IKI!Ist\ed

""'"""- a RPVnventoryasindicaled by RP\t' le~ LESS THAN -125 in.

(TAF)

OR b RPV level cai'I'IOI be morutore-d with lrdcat1011 of core

~ ItS t'VIdeoced b'/ 8rry' d the fOII()Mrg

- ErratiC Soul"ce Range MonilOI' .ndicatlon

• Reluei(Jg Fklorr&diation 11!1..-e!s GREATER THAN 3 RJtn .

.._.doNI 0

eM lnllbllly 10 * ..,.... ,.... In Cold CA...1 I I 4 I 5 wftl lrr . ..... , .... In I 0 Ctw '*"LANNeD Lon ofO.C., HMIIIII-CU4 1

'""I-"'h!lo""' I 4 I

¥1111Capibltly . .hlll. . .tod 5 I I W.th SecondaJY Conta irmen. and RCS 1rtegr1ty ~ An UNPLANNED evert reslAts 1n RCS temperature exceeding established an UNPLANNED evert results lf1 RCS temperatU"e 212degees F exceedii'IQ 212 degrees F 0 CU4 2 I I 4 I 5 I I

'Note. U on RCS ~'~.eat rfo!TI(W.ol *"Y5tem ** in operatiOtl...ch*n th;. time- Loss dan RCS temperatiSe and RPV level indlcat()n fOf frame ondRCS~ r.. ,.~ing rll'd~~tn.. EAL 11' not GREATER Tl-iAN 15 mn..tes appk:Clle No ne None O CA4.2 j j 4 l s j W.th Secondary Contair"meft estati1s hed fiLl! RCS ntegnty Qat esta til&hed Of RCS inverltory rec:I!Xled an UNPLANNED evert results in RCS teJ'I'l)eratiJe exoeed1~ 212 oegrees F lor GREATER TKAN 20 rT'InUte&'

a CA4 .3 [I::::~;:=:~=:IO*;:J:IJ*OI=]

An UNP...ANNED evern results 1n RCS temperature exceedi-v 212 degees F for GREATER TI--l AN 60 m1nutes' or results in an RCS Pl'es.SU"e Increase Of GREATER THAN 10 P6l(l CutUJIIOI.ANNIO ""-ofAI Onth or ow.!.. ~

0 CU61 I I 4 I 5 I Lossol all Table C-1 oos.te COilYfK..IniCatiOos capability No ne None None aflectng the abilrty 10 pertoon rou1ne operations

t

;::;:J.;;:Ig*;r:!~*gi::;;J.

o cue.2 ~ ~

Loss of all Table C-2 ctfsite COilYfK..IriCI!IOOOS capability

..""' None None None None C111~Sl.._.

0 CU 1.1 I 4 I None None None U f"lidenifled Of pressure 00\n:tary ~k3ge GREATER Tl-iAN 10gpn 0 CU 1.2 I I 4 I ldenbfied Jeakage GREATER THAN 25 gpm.

No ne None None 0 CU8 1 I I 4 I 5 I I An UNPLANNED extended positive peood obseNed on nuclear 1nstn..menlatl0f"l TlbM C.1 Onslt Conmunk-lltlons Sys...,.

Reactor Bldg Conrnerc1al lelepllones Monitor HPCIBidg Plart telephor-re$ Alternate Shutdown Panel By survey TiJblne Bldg Portable rados cable Spreading Room By survey ConlfOI & AdrnnstratiOI'I Bldg Plart pege system T!Jbne Buld1rg (exch.ldlrg By survey turbne operatng deck)

D.esel Generator 91dg B*2 TG FRONT STANOAAO (951')

D.esel Fuel 0.1 Transter House B-3CONOENSATE OEM IN OPERATif'o.G ERBidg T* IM C.2 Ofbttll ComnunigUons Systenw; B---4 91 1 TURB BL0G MVP ROOM Intake Structure Corrrnerc~a l telephones B-5 FEECY.'ATER PUMP AREA (911')

Secunty 9.J~dlng' FTS Ptlone System General ReactOI" Building A-1 1027 RX El..OG LON RANGE Areas(excluding m rmi!l lly Secunty Diesel Generator BulklitV' Radio ReceiVerlfransmtter A-31027 RX B....OG W STAIRWAY lOcked l"lq\ri!ld areas)

"k'* ' Th~tuldl*"* oNy c:onslde"dwlllol'l d8ssi1y111g per HU2 1. HA3 1lol'ld HA3 2 A-5 1001 RX BlDG FUEL PO:l.. ROOM A*7985 RX. 8l00 CHEM SAMPlE AREA A-.8 962 RX El..DG Nl/'l OUTS Ice RIM::U ROOM A-9 962 RX 8t.OG EAST A-10 EAST CRD MODULE AREA A-11 WEST CRDMOOUlE AREA A*12935RX B...OG NETIPORIVE AREA A*14 HPCI TURBINE AREA A-1 5896 RX BlOO DRAIN TANK ROOM A-16 RCIC EQUIPMENT AREA A* 17 EAST CORE SPRAY & RHR AREA A*18 WEST ~E SF'RAY & RHR AREA i

i Modes 4, 5, DEF ~

MONTICE LLO NUCLEAR GENERA TING PLAN T 5790-101.()2

~ EMERGENCY ACTION LEVEL MATRIX Revision 10 Modes: [I]

POMJ O !Mfat)on ITJ Startu p

[TI Hot ShutdO'Ml

[TI Cold ShutdO'M"I

[I]

Refu.tlng Page 2 of 2

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 110 of 120 13.0 FIGURES Figure 13.1 MONTICELLO PLANT EMERGENCY ORGANIZATION EMERGENCY DIRECTOR SHIFT EMERGENCY COMMUNICATOR ENGINEERING SUPPORT RADIOLOGICAL SECURITY GROUP GROUP EMERGENCY GROUP LEADER LEADER COORDINATOR LEADER SUPPORT HEALTH SECURITY ENGINEERING GROUP PHYSICS GROUP GROUP OPERATIONS MAINTENANCE GROUP GROUP LEADER LEADER TECHNICAL ADVISOR OSC COORDINATOR OPERATIONS GROUP I&C ELECTRICAL &

GROUP MECHANICAL GROUP

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 111 of 120 Figure 13.2 INTERFACE BETWEEN FUNCTIONAL AREAS OF EMERGENCY ACTIVITY NSPM EXECUTIVE MANAGEMENT (JIC)

EMERGENCY MANAGER (EOF)

NRC EMERGENCY DIRECTOR (TSC)

OSC LOCAL SUPPORT SERVICES Fire Department County Sheriffs Ambulance Service CentraCare Health STATE EOC Monticello WRIGHT SHERBURNE STATE COUNTY COUNTY FEDERAL AGENCIES EOC EOC AGENCIES LOCAL GOVERNMENT Initial lines Lines after EOF is staffed

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 112 of 120 Figure 13.3 INTERFACE BETWEEN FUNCTIONAL AREAS OF EMERGENCY ACTIVITY DURING HOSTILE ACTION BASED EVENTS Federal Agencies MN State Police County Sheriff Fire Ambulance Law NSPM Departments Services Enforcement Executive Management Incident Joint Commander Information (ICP) Center CentraCare Monticello Health Emergency ICP Monticello Manager Federal Liasons (EOF) Agencies Utility Minnesota State NRC Liaison State EOC Agencies Security Monticello Liaison Control Room Wright Sherburne County County EOC EOC Local Government Direct Interface

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 113 of 120 Figure 13.4 HEALTH PHYSICS GROUP ORGANIZATION EMERGENCY EMERGENCY DIRECTOR MANAGER RADIATION RADIOLOGICAL PROTECTION EMERGENCY SUPPORT COORDINATOR SUPERVISOR Dose Projection Dose Projection Specialist Specialist CHEMISTRY MONITORING SECTION F/T COMM EOF CR SECTION CHEM TECH LEADER LEADER CHEM RPC F/T COMM OFF-SITE COORD MONITORING TEAMS CHEM RP OFF-SITE GROUP GROUP MONITORING TEAMS Continuous interface between EOF & TSC Command chain for TSC and EOF

I I MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 114 of 120 Figure 13.5 PLAN VIEW OF TECHNICAL SUPPORT CENTER, BACK-UP OPERATIONAL SUPPORT CENTER

....... f.~-~.

*.~-~--;._,*:*.;*:.,;:_

lil...ENfAST

\ TRANC BACK UP ALTERNATE FIRE BRIGADE ROOM osc

~:

-~-

B NRC

[ij]

~-**

\:.:

E B ENGINEERING SUPPORT TSC HP ROOM B

COMP RM

~~~~{__~*

)~ ......,.*****~*****.*.

B ILJ STORAGE ;U

~~-

.. ADMIN ROOM I EN~~?~

L.J

I I MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 115 of 120 Figure 13.6 PLAN VIEW OF THE EMERGENCY OPERATIONS FACILITY TRAINING TRAINING ROOM 11 ROOM 12 RECEIVING TRAINING ROOM 10 COUNT ROOM EXAM ROOM COMMUNICATIONS ROOM OFFICE TRAINING EOF COMMAND ROOM 9 CENTER DOSE ASSESSMENT TRAINING ROOM 14

\

TRAINING FAX ROOM ROOM 8

\ I 7 OFFICE SIM SUPV

/'\

~ ~ II II Xll V1 VI v MENS RESTROOM MECH/ELEC ROOM STORAGE MOCK-UP ROOM J WOMENS RESTROOM N"

\ IL

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 116 of 120 Figure 13.7 DIRECT DEDICATED TELEPHONES (HOT LINES)

MONTICELLO TELEPHONE NETWORK (Primary Communications Link) 1 NRC CONTROL NRC OPERATION ROOM OPERATION CENTER 14 CENTER 1 7 1a 7a 2 5 3 BACK-UP TSC EOF EOF 9

8 6 4 12a 12 STATE 11 EOF 13a 11a 10a NRC NRC OPERATION OPERATION CENTER CENTER Number Name Stations 1 Emergency Notification System 5 station FTS line between the Control (ENS) Room, TSC, NRC Conference Room in TSC, NRC Office, and NRC Operations Center.

1a ENS (EOF) 3 station FTS line between the EOF, EOF NRC work area, and NRC Operations Center.

2 EOF - TSC 1 (EM-ED) 2 station line between the EOF (EM) and TSC (ED).

3 EOF TSC 2 (RPSS-REC) 2 station line between the EOF (RPSS) and TSC (REC).

4 EOF - MN. State EOC (1) 3 station auto ring hotline between the EOF and the Minnesota State EOC. Either station can activate the circuit.

5 EOF - Back-Up EOF 1 2 station line between the EOF and the Back-Up EOF.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 117 of 120 Figure 13.7 DIRECT DEDICATED TELEPHONES (HOT LINES) (CONTD) 6 EOF - Back-Up EOF 2 2 station line between technical support (Tech Support) groups at the EOF and the Back-Up EOF.

7 Health Physics Network (HPN) 4 station FTS line between the TSC, TSC Health Physics Room, NRC Conference Room in TSC, and NRC Operations Center.

7a HPN 3 station FTS line between the EOF, EOF NRC work area and NRC Operation Center.

8 TSC - MN State EOC (1) 2 station auto ring hotline between the TSC and the Minnesota State EOC. Either station can activate the circuit.

9 EOF - TSC 3 2 station line between the Technical Support (Tech Support) groups at the EOF and the TSC.

10a Management 2 Station FTS line between EOF and NRC Counterpart Link (DSO/STL) Operations Center 11 Protective Measures 2 station FTS line between NRC protective Counterpart measures personnel at the site and NRC Operations Center.

11a Protective Measures 2 station FTS line at the EOF between NRC Counterpart Link (PMCL) protective measures personnel at the EOF and NRC Operations Center.

12 Reactor Safety 2 station FTS line between NRC reactor Counterpart Link (RSCL) safety personnel at the site and NRC Operations Center.

12a Reactor Safety 2 station FTS line at the EOF between NRC Counterpart Link (RSCL) reactor safety personnel at the EOF and NRC Operations Center.

13a Local Area Network (LAN) 2 Station FTS line between EOF and NRC Operations Center 14 Emergency Response Data ERDS VPN channel link over which raw System (ERDS) reactor process data is transmitted from the site.

(1) Auto-Ring Hotlines (Dedicated Private Lines). The interconnection of two or more telephones, which automatically ring the circuit when the telephone is removed from its cradle. This service can be provided intra-facility, intra-city, or inter-city. This is a full-period circuit which is available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day with no limit to its use.

I I MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 118 of 120 Figure 13.8 PLAN VIEW OF OPERATIONAL SUPPORT CENTER PAB 1st Floor OSC Assembly Areas n

f-J I ~ ""'

w

,.\1 o 1-o UJ 2

g ~~

(.? -

z cr:: ow 0 I 2 I o._n_ z w

0 z

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f-- W

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_J Maintenance and V Operations craft assembly areas. 11 I

~ LL G 7

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MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 119 of 120 Figure 13.8 PLAN VIEW OF OPERATIONAL SUPPORT CENTER (CONTD)

PAB 2nd Floor OSC Command Center

[ L PAB-2 ~

0

~

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w c;

0 w

u 0

0::

()_

q]JJD /

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MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE: EMERGENCY PLAN Revision 47 Page 120 of 120 Figure 13.9

SUMMARY

OF SIGNIFICANT CHANGES Section Change and Reason for Change 5.5.1, Update to reflect the changes made in 1996 under state law 5.5.8 (deleted) when MN Statute-Chapter 12 was enacted. Responsibilities for the items listed in previous section 5.5.1 now fall under State and local agencies. State Emergency Services Mobile Support Area VI was abolished.

7.1.5 Update to include description of Back-up EOF capabilities.

Table 1 Removed asterisk next to Core/Thermal Hyd. 30 min responder Throughout Minor editorial and reference corrections