Text

Changes to the Monticello Nuclear Generating Plant (MNGP) Emergency Plan
	ML17108A825
Person / Time
Site:	Monticello
Issue date:	04/18/2017
From:	Gardner P; Northern States Power Company, Minnesota, Xcel Energy
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-MT-17-029
	Download: ML17108A825 (125)
	v • d • e

Xcel Energy@

April 18, 2017 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 Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 L-MT-17-029 10 CFR 50.54(q)(5) 10 CFR 72.44(f)

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.

~~

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 Nucl~ar Material Safety and Safeguards (with Enclosure 1)

ENCLOSURE1 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:

"Hardened Containment Venting System NRC Order EA-13-1 09 Phase 1 ", replaces the hard pipe vent radiation monitor, RM-4544. This radiation monitor provides input to computer point ARM135 (ARM Hard Pipe Vent Rad Analog). The existing radiation monitor has a range from 0.1 mrem/hr to 10 rem/hr whereas the new radiation monitor replacing it has a range of 10 mrem/hr to 10,000 rem/hr. The new monitor range does not encompass the lower range of the existing monitor from 0.1 mrem/hr to 10 mrem/hr and the current off-normal alarm setpoint of 5 mrem/hr. The new monitor's range was established to meet the requirements of NEI 13-02 Revision 1 Section 4.2.4.1.2 which states that the range of the instrument should be consistent with the dose rates anticipated during a severe accident venting.

This change does not result in a reduction of effectiveness of the Emergency Plan.

Change (1)

==

Description:==

To comply with NRC Order EA-13-1 09 "Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation under Severe Accident Conditions" and align with NEI 13-02 Revision 1 "Industry Guidance for Compliance with Order EA-13-109", installation of a new Hard Pipe Vent monitor is planned. The existing radiation monitor has a range of 0.1 mrem/hr to 10 rem/hr while the new radiation monitor has a range from 10 mrem/hr to 10,000 rem/hr. This expanded range was selected to meet the requirements of NEI 13-02 Revision 1 Section 4.2.4.1.2 which states that the range of the instrument should be consistent with the dose rates anticipated during a severe accident venting which conforms with the NRC Order EA-13-109.

Doc ID or (Procedure Number) I Revision Number: E-Pian I 48 Document

Title:

Emergency Plan Licensing/Basis Affected:

NRC Commitment M90085A required installation of a hardened wet well vent to reduce the risk of a TW Sequence. This was in response to Generic Letter 89-16, "Installation of a Hardened Wetwell Vent". In MNGP Commitment M90085A, MNGP committed to the NRC to: "Install a hardened wetwell vent of plant specific design based upon the generic criteria of IPE consisting of a dedicated vent." To meet the commitment, the existing monitor was installed per the guidance of Generic Letter 89-16. The radiation monitoring capabilities of GL 89-16 identified the following instrument requirements to which the current monitor RM-4544 was installed per modification 920295:

"Radiation monitoring shall be provided to alert control room operators of radioactive releases during venting."

Page 1 of 3

In response to NRC Order EA-13-1 09, MNGP is modifying the hard pipe vent radiation monitor using the guidance of NEI 13-02, Industry Guidance for Compliance with Order EA-13-1 09, Revision 1, April 2015. The information contained in this guidance will be used by NRC licensees to implement the requirements of Phase 2 of NRC Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions, June 6, 2013.

NEI 13-02 Revision 1 Section 4.2.4.1.2 identifies the new/revised radiation monitor instrument capabilities for the hardened containment venting system (HCVS) as follows which also is/becomes the new licensing basis for the hard pipe vent monitor measurement range: 4.2.4.1.2 HCVS vent pipe radiation levels. The range of the instrument should be consistent with the dose rates anticipated during severe accident venting. The use of a multi-range instrument that will span the expected dose rates is acceptable. 4.2.4.1.2.1 The effluent discharge radiation monitor is required to provide additional knowledge of HCVS operation not as a required change for Emergency Preparedness off-site dose functions.

NOTE: TW Sequence is defined as: The TW Sequence is the loss of long term decay heat removal capabilities. This is a complete failure of the RHR Service Water System and/or the RHR System with the Primary Containment isolated, which results in the incapability of removing decay heat from the suppression chamber, the primary containment atmosphere, or the reactor pressure vessel.

Evaluation Determination Regulatory Compliance Basis:

Appendix E- "Interface with Generic Letter 89-16, Installation of a Hardened Wetwell Vent" of NEI 13-02, Revision 1 identifies the following: A review of the requirements of EA-13-1 09 Phase 1 and Phase 2 concludes the requirements of this order bounds the previous requirements of GL 89-16. As such, licensees have a basis for changing commitments to GL 89-16 in accordance with NEI 99-04, Guidelines for Managing NRC Commitment Changes.

Summary:

The existing hard pipe vent radiation monitor design basis does not include any specification or requirement that it include measuring capabilities in the range of 0.1 mrem/hr to 10 mrem/hr. It was designed to meet the generic design requirements of GL 89-16 and installed to provide a signal to a local recorder and local alarm to alert operators of releases during venting. The new radiation detector being installed will continue to provide an off-normal alarm of a release during venting to the operators. In addition, the expanded range of the instrument will be consistent with the dose rates anticipated during severe accident venting meeting the Phase 2 requirement for this of NRC Order EA-13-1 09. The new parameters will be provided for revision to the computer point summary document and update to the computer point as part of the engineering change package.

Receipt of actual elevated dose rates on the Hard Pipe Vent Radiation Monitor requires both inboard and outboard primary containmElnt isolation valves to be opened by intentional operator actions. In this case, the off-normal condition would be known/expected by the Operators and Emergency Response Organization (ERO) based on the planned Operator actions to open the vent.

If an expected instrument response (alarm and/or recorder) is not received providing indication of the vent being open, use of the instructions contained in A.2-405 provides an alternate means for the ERO to confirm that the vent is open and obtain release rate data.

Page 2 of 3

The Emergency Plan revision for this change to the radiation detector is limited to updating the new/replacement monitor's measuring range. The range of the new/replacement radiation monitor meets and fulfills the requirements and guidance in NEI 13-02, Revision 1 with respect to monitoring of the HCVS vent pipe radiation levels and provides the basis for the new detector's capabilities and the types of accident scenarios to which its use applies.

An Engineering Evaluation verified the new monitor will continue to provide radiological release data within the range required for conducting accident assessments, classifying events, and performing dose projections for the release rates expected and for the types of accident scenarios credited to using the hard pipe vent as a viable release pathway (beyond design basis accident scenarios). In the event that use of the hard pipe vent release pathway is used during other accident scenarios for which it is not credited and that have a lower release rate than can be measured by the new monitor (range of 0.1 mrem/hr to 10 mrem/hr), A.2-405 includes provisions for use of hand held dose rate instrument to obtain the hard pipe vent dose rate for use in determining release rates, completion of dose projections, and conducting accident assessment activities.

It is therefore concluded that the new radiation monitor continues to meet the requirements in 10 CFR 50.47 (b) standards 8 and 9 and 10 CFR 50, Appendix E, Section IV.B.1. and Section IV.E.2 and the change in the instruments measuring range does not result a reduction of effectiveness of the site Emergency Plan.

Page 3 of 3

ENCLOSURE 2 Monticello Nuclear Generating Plant Emergency Plan, Revision 48 120 pages follow

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 1 of 120 Approval:

PCR 01527699 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 48 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 48 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 48 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 48 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 48 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 48 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 48 Page 8 of 120 Following is a brief description of each emergency classification and its associated response level.

Notification of Unusual Event 4.1 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.

Alert 4.2 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.

Site Area Emergency 4.3 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 48 Page 9 of 120 General Emergency 4.4 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 Normal Site Organization 5.1 Site Management Organization 5.1.1 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 48 Page 10 of 120 Shift Organization 5.1.2 Operations 5.1.2.1 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.

Fire Brigade 5.1.2.2 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).

Radiation Protection 5.1.2.3 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 48 Page 11 of 120 Chemistry 5.1.2.4 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.

Security (Shift Emergency Communicator) 5.1.2.5 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.

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

Onshift Staffing Analysis 5.1.4 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 48 Page 12 of 120 Emergency Organization and Responsibilities 5.2 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).

Technical Support Center Emergency Organization 5.2.1 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.

Direction and Control 5.2.1.1 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 48 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 48 Page 14 of 120 Radiation Protection and Chemistry Groups 5.2.1.2 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 48 Page 15 of 120 Support Group 5.2.1.3 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.

Operations Group 5.2.1.4 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 48 Page 16 of 120 Engineering Group 5.2.1.5 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.

Maintenance Group 5.2.1.6 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.

Security Group 5.2.1.7 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 48 Page 17 of 120 Emergency Communications Group 5.2.1.8 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.

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

Coordination and Direction 5.2.2.1 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.

Mechanical Maintenance 5.2.2.2 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.

Electrical Maintenance 5.2.2.3 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 48 Page 18 of 120 Instrument & Control 5.2.2.4 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.

Radiation Protection 5.2.2.5 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).

Operations 5.2.2.6 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).

EOF Emergency Organization 5.2.3 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.

Direction and Control 5.2.3.1 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 48 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.

Technical Support Group 5.2.3.2 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.

Radiation Protection Support Group 5.2.3.3 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 48 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.

EOF General Staff, Logistics, and Support Group 5.2.3.4 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 48 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).

Emergency Response Organization Augmentation 5.3 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.

ERO Augmentation Description and Goals 5.3.1 Plant Operations and Operational Assessment 5.3.1.1 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 48 Page 22 of 120 Emergency Direction and Control 5.3.1.2 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.

Notification and Communications 5.3.1.3 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.

Radiological Assessment and Protective Actions 5.3.1.4 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 48 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.

Engineering and Technical Support 5.3.1.5 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.

Repair and Corrective Actions 5.3.1.6 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 48 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.

Firefighting 5.3.1.7 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.

Rescue Operations and First Aid 5.3.1.8 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.

Site Access Control, Accountability and Security 5.3.1.9 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.

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

Environmental Monitoring Support 5.3.1.11 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 48 Page 25 of 120 Augmentation Methods 5.3.2 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 48 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.

Augmentation of On-Site Emergency Organization 5.4 Licensee Headquarters Support 5.4.1 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.

Local Support Services 5.4.2 Monticello Fire Department 5.4.2.1 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 48 Page 27 of 120 CentraCare Health Monticello 5.4.2.2 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.

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

Ambulance Service 5.4.2.4 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 48 Page 28 of 120 Local Law Enforcement 5.4.2.5 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 48 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.

Coordination with Participating Government Agencies 5.5 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.

Minnesota Department of Public Safety 5.5.1 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.

Minnesota Health Department 5.5.2 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 48 Page 30 of 120 Wright County Sheriff 5.5.3 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.

Monticello Radiological Emergency Preparedness 5.5.4 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.

U.S. Department of Energy 5.5.5 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.

Sherburne County Sheriff 5.5.6 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.

Minnesota State Patrol 5.5.7 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.

Minnesota Department of Transportation 5.5.8 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.

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

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 31 of 120 City of St. Paul Water Department 5.5.10 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.

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

Pooled Equipment Inventory Company (PEICo) 5.6.2 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 48 Page 32 of 120 Table 1 MINIMUM SHIFT STAFFING AND CAPABILITY FOR ADDITIONS FOR NUCLEAR POWER PLANT EMERGENCIES Capability for Additions Major Functional Area Major Tasks Position Title or Expertise On Shift 30 min 60 min Plant Operations and Assessment of Operational Aspects Shift Manager 1

Control Room Supv 1

SRO 1

Nuclear Lead PE&RO (RO) 1 Nuclear PE&RO 2

Nuclear Asst. PEO 3

Emergency Direction and Control Emergency Director (Shift Manager until relieved) 1*

Notification/

Communication Notify licensee, Local, State, and Federal personnel &

agencies Shift Emerg Communicator 1

Maintain Communications Emergency Communicators 1

2 Radiological Accident Assessment and Support of Operational Accident Assessment Emergency Operations Facility Emergency Manager 1

Coordinate EOF prior to arrival of Emergency Manager EOF Coord 1

Off-Site Dose Assessment Radiological Emergency Coord 1

Off-Site Surveys On-Site (out-of-plant)

In-Plant Surveys Radiation Protection 2

1 1

1 Chemistry/Radio-Chemistry Chemistry 1

1

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 33 of 120 Table 1 MINIMUM SHIFT STAFFING AND CAPABILITY FOR ADDITIONS FOR NUCLEAR POWER PLANT EMERGENCIES (CONTD)

Capability for Additions Major Functional Area Major Tasks Position Title or Expertise On Shift 30 min 60 min Plant System Engineering, Repair and Corrective actions Technical Support Technical Advisors 1*

Core/Thermal Hyd.

1 Electrical 1

Mechanical 1

Repair & Corrective Actions Mech Maint 1*

1 Elec Maint 1*

1 1

I&C 1

Protective Actions (In-Plant)

Radiation Protection Radiation Protection 2*

1 1

a.

Access Control

b.

HP Coverage for response actions

c.

Personnel monitoring

d.

Dosimetry Fire Fighting Fire Brigade per 4 AWI-08.01.01 Local Support Rescue Operations and First Aid 2*

Local Support Site Access Control and Personnel Accountability

Security, Communications, Personnel Accountability Security Force All per Security Plan 13 9

12

May be provided by shift personnel assigned other functions.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 34 of 120 Table 2 MONTICELLO PLANT ERO RESPONSIBILITY MATRIX I

P - PRIMARY RESPONSIBILITY S - SECONDARY RESPONSIBILITY COMMAND/

CONTROL NOTIFICATION/

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

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

FIRST AID ACCESS CONTROL RECOVERY OPERATIONS CHEMISTRY/

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

s s

p s s p s

s s

s p

I p

s s

s p

p p

p s

s p

p p

p s

p s p

s p p p p s s p

s s p

p p

p s

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 35 of 120 6.0 EMERGENCY MEASURES Summary of Responses 6.1 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.

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

Inform the NRC of the Unusual Event.

6.1.1.2 Augment on-shift resources as necessary.

6.1.1.3 Assess and respond to the off-normal condition.

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

OR Escalate to a more severe emergency class.

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

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

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

Assess and respond to the emergency condition.

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

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

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

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 36 of 120 Terminate the Alert with notification to the State and Local 6.1.2.9 off-site authorities and the NRC.

OR Escalate to a more severe emergency class.

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

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

Notify the NRC of the Site Area Emergency.

6.1.3.3 Establish the ERDS communication link with the NRC.

6.1.3.4 Assess and respond to the emergency condition.

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

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

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

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

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

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

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

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

OR Escalate to a General Emergency.

6.1.3.14

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 37 of 120 General Emergency 6.1.4 Promptly inform the State and Local off-site authorities of the 6.1.4.1 General Emergency and the nature of the emergency condition.

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

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

Notify the NRC of the General Emergency.

6.1.4.4 Establish the ERDS communication link with the NRC.

6.1.4.5 Assess and respond to the emergency condition.

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

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

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

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

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

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

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

Emergency Response Activation 6.2 Notification Scheme 6.2.1 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 48 Page 38 of 120 Activation of the On-Site ERO 6.2.1.1 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.

State and Local Authorities and NRC 6.2.1.2 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 48 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):

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

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

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 40 of 120 Off-site Emergency Response Organization 6.2.1.3 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).

General Public 6.2.1.4 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.

Emergency Action Levels (EALs) 6.2.2 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.

Authentication 6.2.3 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 48 Page 41 of 120 Assessment Actions 6.3 Determining Magnitude of Release 6.3.1 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.

Off-Site Dose Projection 6.3.2 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.

Rapid Assessment 6.3.2.1 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 48 Page 42 of 120 Detailed Assessment 6.3.2.2 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.

Sum Assessment 6.3.2.3 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.

Field Radiation Surveys 6.3.3 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 48 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.

Corrective Actions 6.4 Fire Control 6.4.1 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.

Repair and Damage Control 6.4.2 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.

Protective Actions 6.5 Protective Cover, Evacuation, Personnel Accountability 6.5.1 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.

Plant Site 6.5.1.1 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 48 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:

All plant employees not having emergency 6.5.1.1.1 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; All working and non-working visitors and 6.5.1.1.2 contractor and construction personnel, having been cleared of radioactive contamination, will be directed to leave the site, unless requested otherwise by the Emergency Director; Persons who may be within the restricted area 6.5.1.1.3 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.

Persons who are not cleared of radioactive 6.5.1.1.4 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 48 Page 45 of 120 Onsite Protective Actions for Hostile Action Events 6.5.1.2 Onsite Protective Actions designed for 6.5.1.2.1 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.

Off-Site Public 6.5.1.3 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 48 Page 46 of 120 Routes for Site Evacuation 6.5.2 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.

Monticello Service Center Assembly Area -

6.5.2.1 118 Dundas Road, Monticello, Minnesota Xcel Energy Sherburne County Generating Plant (Sherco) -

6.5.2.2 13999 Industrial Blvd, Becker, Minnesota Evacuation Time Estimates (ETE) - Plume Exposure EPZ 6.5.3 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.

Use of On-Site Protective Equipment and Supplies 6.5.4 Respiratory Protection and Protective Clothing 6.5.4.1 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 48 Page 47 of 120 Thyroid Prophylaxis 6.5.4.2 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.

Emergency Exposure Control 6.5.5 Exposure Limits 6.5.5.1 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:

In order to avoid restricting actions that may be 6.5.5.1.1 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).

In situations where protecting valuable property 6.5.5.1.2 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 48 Page 48 of 120 Exposure Control 6.5.5.2 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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.

Contamination Control Measures 6.5.6 Plant Site 6.5.6.1 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 48 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:

A.Use of a counting system that meets a 6.5.6.1.1 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.

B.Using a frisker type instrument to conduct a 6.5.6.1.2 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.

Off-Site Areas 6.5.6.2 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 48 Page 50 of 120 Aid to Affected Personnel 6.6 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 Decontamination and First Aid 6.6.1 Decontamination 6.6.1.1 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 48 Page 51 of 120 The waste generated in decontamination operations will be retained for proper disposal.

First Aid 6.6.1.2 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.

Medical Transportation 6.6.2 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.

Medical Treatment 6.6.3 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 48 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.

Monitor environmental radiation levels.

Thyroid <5 (CDE)

Skin <50 (CDE)

Whole Body >1 (TEDE)

Evacuate unless constraints make it impractical. Monitor environmental radiation levels. Control access.

Shelter if evacuation were not immediately possible.

Thyroid >5 (CDE)

Skin >50 (CDE)

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 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 6800 450 C3 + C6 < 1 180,000 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 48 Page 54 of 120 Table 5 RECOMMENDED PROTECTIVE ACTIONS Accident Phase Exposure Pathway Example of Actions to be Recommended EARLY (EMERGENCY)

PHASE (NOTE 1)

(0 to 4 days)*

Inhalation of gases, radioiodine or particulate Evacuation, shelter, Access Control, respiratory protection, prophylaxis (thyroid protection)

Direct whole body exposure Evacuation, shelter, Access Control INTERMEDIATE PHASE (NOTE 2)

Ingestion of Milk Take cows off pasture, prevent cows from drinking surface water, discard contaminated milk, or divert to stored products such as cheese Ingestion of fruits and vegetables Wash all produce, or impound produce, 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to 30 days)*

Whole body exposure an inhalation Relocation, decontamination, Access Control LATE PHASE (NOTE 3)

Ingestion of food and water contaminated from the soil either by resuspension or uptake through roots Decontamination, condemnation, or destruction of food, deep plowing, condemnation or alternate use of land (over 30 days)

Whole body exposure from deposition material or inhalation of resuspended material Relocation, Access Control, decontamination, fixing of contamination, deep plowing 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 48 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.

10 REM (TEDE)(2)(3)

Protection of valuable property This dose limit applies when a lower dose is not practicable through application of ALARA practices.

25 REM (TEDE)(2)(3)

Life saving or protection of large populations This dose limit applies when a lower dose is not practicable through application of ALARA practices.

> 25 REM (TEDE)(2)(3)

Life saving or protection of large populations Doses in excess of 25 REM should be 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 48 Page 56 of 120 7.0 EMERGENCY FACILITIES AND EQUIPMENT Emergency Response Centers 7.1 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.

Technical Support Center 7.1.1 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.

Operations Support Center 7.1.2 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 48 Page 57 of 120 Emergency Operations Facility 7.1.3 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 48 Page 58 of 120 Alternative Facilities 7.1.4 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.

Back-up EOF 7.1.5 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 48 Page 59 of 120 Assembly Points 7.1.6 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.

Access Control 7.1.7 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.

Sign-in Boards for ERO Assignments 7.1.8 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 48 Page 60 of 120 Communications Systems 7.2 Normal On-Site Communications 7.2.1 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.

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

46 two way ISDN trunks (TDS Telecom) 7.2.2.1 46 two way ISDN trunks to Minneapolis (Dial 8 access) 7.2.2.2 23 ISDN trunks to the Monticello Training Center 7.2.2.3 Alternate Off-Site Communications 7.2.3 Radio Receiver/Transmitter 7.2.3.1 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 48 Page 61 of 120 Emergency Response Organization Pager Network 7.2.3.2 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).

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

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

Site FTS System - this dedicated telephone 7.2.3.3.2 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.

EOF FTS System - this dedicated telephone 7.2.3.3.3 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.

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

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

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

Four dedicated Federal Telephone System 7.2.3.3.7 (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 48 Page 62 of 120 Two dedicated cellular phones providing back-7.2.3.3.8 up communications for Field Teams.

Radio Links 7.2.3.4 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.

Emergency Response Data System 7.2.3.5 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.

Emergency Communications Matrix 7.2.4 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.

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

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

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

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 63 of 120 Assessment Facilities 7.3 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.

On-Site Systems and Equipment 7.3.1 Safety Parameter Display System (SPDS) 7.3.1.1 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 48 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:

Top Level SPDS Displays 7.3.1.1.1

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 48 Page 65 of 120 Lower-Level SPDS Displays 7.3.1.1.2

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 48 Page 66 of 120 Geophysical Phenomena Monitors 7.3.1.2 Seismic Monitoring System 7.3.1.2.1 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 48 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.

Meteorological Monitoring System 7.3.1.2.2 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 48 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 0.00278 hours 1.653439e-5 weeks 3.805e-6 months .

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 48 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.

Radiological Monitors 7.3.1.3 Process Radiation Monitoring System 7.3.1.3.1 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 48 Page 70 of 120 Area Radiation Monitoring System 7.3.1.3.2 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 48 Page 71 of 120 Process Monitors 7.3.1.4 There are many instruments in the plant which 7.3.1.4.1 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.

Reactor Protection System 7.3.1.4.2 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.

Primary Containment Isolation System 7.3.1.4.3 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 48 Page 72 of 120 Containment Radiation Monitor 7.3.1.5 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.

Fire Detection Devices 7.3.1.6 Early Warning Fire Detectors 7.3.1.6.1 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.

HAD (Heat Activated Device) 7.3.1.6.2 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.

LHD (Linear Heat Detection) 7.3.1.6.3 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 48 Page 73 of 120 Post-Accident Sample System 7.3.1.7 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:

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

Gas samples from drywell and torus.

7.3.1.7.2 Facilities and Equipment for Off-Site Monitoring 7.3.2 Geophysical Phenomena Monitors 7.3.2.1 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:

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

National Earthquake Information Service 7.3.2.1.2 (Golden, Colorado)

Radiological Monitors 7.3.2.2 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.

Laboratory Facilities 7.3.2.3 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 48 Page 74 of 120 Protective Facilities and Equipment 7.4 Assembly Points 7.4.1 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.

Emergency Operations Facility (EOF) 7.4.2 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.

Back-up EOF 7.4.3 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 48 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.

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

First Aid and Medical Supplies 7.5 First Aid Center 7.5.1 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.

First Aid Kits 7.5.2 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.

Damage Control Equipment and Supplies 7.6 Firefighting Equipment 7.6.1 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.

Spill and Leak Control Equipment 7.6.2 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 48 Page 76 of 120 Public Alert and Notification System (ANS) 7.7 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.

Emergency Alert System Auto Dialing Telephone Systems 7.8 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.

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

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 77 of 120 Table 7 MONTICELLO NUCLEAR GENERATING PLANT COMMUNICATIONS MATRIX STATE PATROL MNGP-PINGP MONITORING TEAMS PLANNING & ASSESSMENT Xcel ENERGY SYSTEM DISP MNGP Security Incident Command Post X

X X

X X X

X X

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 78 of 120 Table 8 COMMUNICATIONS CONTACTS LOCATION CONTACT PRIMARY ALTERNATE Control Room Shift Manager Control Room Supervisor EOF and Back-up EOF Emergency Manager EOF Coordinator Minnesota Division of Emergency Management Duty Officer Duty Officer Minnesota Planning and Assessment Center Planning Chief State Duty Officer 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 Earthquake OBE Alarm Module

.03 g 6-C-18 Design Basis Earthquake DBE Alarm Module

.06 g

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 79 of 120 Table 10 ON-SITE METEOROLOGICAL MONITORING INSTRUMENTATION SYSTEM PARAMETER SENSOR LOCATION (METERS)

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

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

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

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

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

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

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

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 80 of 120 Table 11 PROCESS RADIATION MONITORS MONITOR NUMBER OF DETECTORS INDICATOR 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 Panel C-258 100 - 1012 µCi/Sec Reactor Building Vent WRGM 2

Panel C-257 Panel C-258 100 - 1012 µCi/Sec Fuel Pool Monitor 2

Panel C-10 0.1 - 1000 mrem/hr Reactor Building Exhause Plenum Monitor 2

Panel C-02, C-10

.01 - 100 mrem/hr 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 Sump Radiation Monitor 2

Panel C-02, C-10 10 - 106 CPM Drywell CAM Monitor 1

Panel C-02 10 - 106 CPM Control Room Radiation 2

Panel C-257 Panel C-258 10 104 mrem/hr Sewer Lift Station 1

Panel C-249 10 - 107 CPM Hard Pipe Vent 1

Panel C-289B 10 - 107 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 48 Page 81 of 120 Table 12 AREA RADIATION MONITORS STA.

PANEL C-11 SENSOR LOCATION BUILDING AREA SENSOR RANGE (MR/HR)

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 Area 0.1 - 1000 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 Room 13.8kV Switchgear Room 0.1 - 1000

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 82 of 120 Table 12 AREA RADIATION MONITORS (CONTD)

STA.

PANEL C-252 &

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

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 STA.

PANEL C-257 &

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

Reactor Containment 100 - 108 R/HR

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 83 of 120 Table 13 INSTRUMENTS AVAILABLE FOR MONITORING MAJOR SYSTEMS Measured Parameter Type of Readout Range Indicator Location

1.

Source Range

a.

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

b.

Reactor Period Linear Scale Indicator, Annunciator

-100 to 10 Sec System Cabinets Main Control Panels

2.

Intermediate Range

a.

Neutron Level Digital Bargraph Display, Recorder, Annunciator 0 to 125 (units)

System Cabinets Main Control Panels

3.

Power Range

a.

Neutron Level Linear Scale Indicator, Recorder, Annunciator 0 to 125%

System Cabinets Main Control Panels

4.

Reactor Coolant Range

a.

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

b.

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

c.

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

d.

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

e.

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

5.

Main Steam

a.

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

b.

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

c.

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

Main Control Panels

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 84 of 120 Table 13 INSTRUMENTS AVAILABLE FOR MONITORING MAJOR SYSTEMS (CONTD)

Measured Parameter Type of Readout Range Indicator Location

6.

Containment

a.

Pressure Linear Scale Recorder, Computer Printout, Annunciator

-2 to +3 psig recorder 0-80 psig recorder 0 to +250 psig recorder Main Control Panels

b.

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

c.

Torus Level Linear Scale Indicator

-15 to 15

-8 to 14 recorder (in Linear Feet)

Main Control Panels

d.

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

e.

N2 Makeup Flow Linear Scale Recorder, Annunciator 0 - 2 SCFM Main Control 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 Fans Indicator Lights Stby/Off/On System Cabinet Control Panels

7.

Station Electric

a.

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

b.

Breaker Positions Indicator Lights Open/Closed Main Control Panels

c.

Amperage Linear Scale Indicators Various Main Control Panels

d.

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

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 85 of 120 Table 13 INSTRUMENTS AVAILABLE FOR MONITORING MAJOR SYSTEMS (CONTD)

Measured Parameter Type of Readout Range Indicator Location

8.

Feedwater Condensate

a.

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

b.

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

c.

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

d.

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

e.

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

9.

Condenser Systems

a.

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

b.

Hotwell Level Linear Scale Recorder, Annunciator

-15 to +15 Main Control Panels

c.

CST Level Linear Scale Indicator 5 to 30 Main Control Panels

10. ECCS Systems

a.

LPCI, Core Spray Pump Status Indicator Light

b.

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

c.

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

d.

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

e.

ADS Valve Positions Indicator Lights Annunciator Main Control Panels

f.

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

Controller 0 to 500 GPM Main Control Panel

b.

LPCI Mode of RHR (see above)

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 86 of 120 Table 14 EMERGENCY KITS LOCATION GENERAL CONTENTS Site Administration Building Assembly Point Protective Clothing & Equipment 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 &

Equipment Storage Facility Vehicles for Emergency Use (2)

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

Protective Clothing & Equipment Dosimetry CentraCare Health Monticello

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

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 87 of 120 8.0 MAINTAINING EMERGENCY PREPAREDNESS Organizational Preparedness 8.1 Emergency Response Organization Training 8.1.1 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.

Drills, Exercises and Tests 8.1.2 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:

An exercise which tests the integrated capability and basic 8.1.2.1 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.

In order to ensure that adequate emergency response 8.1.2.2 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.

A medical emergency drill, involving response to and transport 8.1.2.3 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 48 Page 88 of 120 Health Physics Drills which involve response to and analysis of 8.1.2.4 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.

The analysis of in-plant liquid samples (with 8.1.2.4.1 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.

Radiological monitoring drills which include the 8.1.2.4.2 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.

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

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

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

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

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

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

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 89 of 120 The Annual Performance Review for the ANS is 8.1.2.6.5 conducted in accordance with plant Surveillance 1408.

The Emergency Alert System Auto Dialing 8.1.2.6.6 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.

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

Planning 8.2 Responsibility 8.2.1 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.

Review and Updating of the Emergency Plan 8.2.2 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:

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

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

Modifications to plant systems, components or instrumentation.

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

Lessons learned from real emergency plan activations.

8.2.2.5 Changes in State or Federal regulations.

8.2.2.6

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 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.

Maintenance and Inventory of Emergency Equipment and Supplies 8.3 Equipment and Supplies Inventory 8.3.1 Emergency Equipment and supplies SHALL be inventoried at least quarterly in accordance with plant Surveillance Procedure 1102-01 and 1102-02.

Instrument and Facilities Functional Check 8.3.2 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 48 Page 91 of 120 9.0 RECOVERY General Approach 9.1 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.

Investigation of Incidents 9.2 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.

Recovery Procedures 9.3 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 48 Page 92 of 120 Criteria for Resumption of Operation 9.4 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.

Long Term Recovery 9.5 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 48 Page 93 of 120 10.0 APPENDIX A Procedure No.

Procedure Title Plan Section 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 Event 7.1.4 200 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 48 Page 94 of 120 10.0 APPENDIX A (CONTD)

Procedure No.

Procedure Title Plan Section 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 Decontamination 6.5.1 A.2-408 Sample Coordination During Emergencies 6.3 A.2-409 Self-Contained Breathing Apparatus (SCBA) Use During an Emergency 6.5.4.1 A.2-410 Out-of-Plant Surveys 6.3.3 A.2-411 Establishment of a Secondary Access Control Point 7.1.6 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 48 Page 95 of 120 10.0 APPENDIX A (CONTD)

Procedure No.

Procedure Title Plan Section 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 48 Page 96 of 120 10.0 APPENDIX A (CONTD)

Procedure No.

Procedure Title Plan Section 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 48 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 48 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 48 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 48 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 48 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 48 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 48 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 48 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 48 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.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 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 I

I

~ilililililililil~il~ilil~~ilil GENERAL EMERGENCY I SITE AREA EMERGENCY I ALERT I

UNUSUAL EVENT I

~.~.~~.*~*:.J Abnormal othl14111t..,

Conc*l-Nauui S OHI:rudl~

~-

Control RQ1 Ottti *Oon 111*-tr.g rom >r1 AdtMI or lmmln<<lt llltllns. or a.-au~ Radloac!Mry bc-..11: 1000 mlt.m TEOE 0< ~ mit.,..

Thyrc*:ICOI!foflhtActtai<< Prof<<ted~IMHiof theRekfte USirlg ACIWIIIIIM-alogy NQte-ltOowa~meflt re$1.1\\'s areavllil<'lble.tthetimeof Oeclaraborl. tOe clnSiflc:atlon sl'tovld be based on RG 1 2 ~r~S!Nd d RG11 'MWeMCeSNiy<leciarallons5ttouldnotbedelayedawalb,g

'""'ltt.ttledowlls~~ldbeiniti<ttedl~itlor<lef to Oetetmifle If the c:IH~ic<JllOn ~1o11d be.ub5equer(ly n<:lWatii!O 0

RG1.1 I 1 I 2 I 3 I 4 I 5 I DEF I VAUO reiKitrg on any Of 1t1e foil~

radiaton monrt01$1hal bCeeds Of IS expected to exceed the read1ng st!CM'n !Of 15 rn r.Aesor~<:~nger Moot or GE

~~uer.I Mol'ltoc 21E9,..Ctlsec (Ch A orB)

RB Vert Emuerl: MonrtOf 1_ 5E8 ~o~Ctlsec (ChAorB) l.W!S!

ServiCe 'Water NIA Discharge Carel Mon1tor NIA T13NWS NIA 0

RG1 2 I 1 I 2 I 3 I 4 I 5 I DEF I Dose as.ses.smert USif'9 aci.Ui'll meteoroio9J' ll"ldicates doses GREATER THAN 1COO ~emTEOEor 5000 mRem thyrOid COE at or beyond the site tx:u'ldary 0

RG1.3 I 1 I 2 I 3 I 4 I 5 I DEF I Field,.urvey result,. indicate dosed window a>se rate,.

exceedng 1000 mRenvhr expected to contll"'..e lor melle lhilln one hour, at or beyond the site boi.Xldary OR Anatym Of field SJ.XVeY safl'llles w.oieate tt?(roicl COE of 5000 m=<:em for one hou-of tnhalatJon, at or beyond the sue bounda~

ltS1 Oftsll:t DoH R1MIIlng IYom M Actual or llnmilwolll ill:... _

ol

~*lbdlo.KIIW! y bic:-* 100 mb m TI!OEor ~

mit...,

lhyrold CDefor tM At~ or Pro~

Clu'illion oflhe llt.tnw tcxe* llao.ea~

ret~.~tts are""ajat>Je atlhet>mecrl dedarabon. the claftlfialtorl s~'lo~Md be b.,ed on RS1 :2 JM!ead ot RS1 1 'M'Ide necessary dedaratlons should not be delayed av.eltlt'lg rnu~. '- lk>M nw~ thovl(lbeinWted/~inor'ISef lodeteffrinelthe cl~oonahouldbe$1.1~1y~ated a

Rsu I 1 I 2 I 3 I 4 I s I oeF I VAUD readi!"Q on any Of the IOIIONtng ractatJOn monrtors that exceeds or 1sexpected to exceed the readirg s.hoWn IOf 15 rr.n\\Aet Of IOI'gef Mon1tor SAE

~ ~ueniMorilof 21E8~o~C!Jsec (ChA or B)

R8 Vert Effluent Morrtor 1.5E7 "Q/sec (0\\A or B)

Ll!llll!

SeNICt'Wster NIA Discharge Canal Mol"lltor NIA TSNWS NIA 0

RS12i 1 I 2 I 3 I 4 I 6

!DEF !

Dose assessment USirg actual meteorology 1ndlc.atesdoses GREATER THAN 100 mRem TEOE or 500 mRem tt'¥roid CO:

atort::Jeyondthe&itetx::M.x"'dary 0

RS1.3 I 1 I 2 I 3 I 4 I 5 I DEF I Fteld suvey resUts inchcate closed Wlndow dose rate$

exoeed~r~g 100 rtRernl'hr expected to continue for l'rOff! than one l'lou", at or beyond the s1te boundary OR Analy~1t of field s..r.-ey samples Indicate thyrotd COE Of 500 rrRem for one hots of IMalation, at or beyond the srte Tabte R*1 Areas Rtqulriftv lnfTetqu.nt Accus Alternate ShU:down Panel Cable Spreadir-g Room Turbine Building (excluding Turl:tlne opetat1ng dec!<)

General Reactor Building Areas (excfudtng oormaJiy iod<ed h~

rad area&)

None None None Monitor bysuNey by survey b>,'survey B-2 TG FRONT STANDARD (951 ')

8--3 CCfo.IOEN SA TE OEM IN OPERATING B-4 911 11JR8 El.OG MVP ROOM B-5FEED-NATER PUMP AREA (911'}

A-1 1027 RXBlDGLOORANGE A--3 1027 RxBlDGWSTAIRwAY A-5 1001 RX. BlDG Fl.EL F'<X>L ROOM A*7 985 RX aoo CHEM SAMPLE AREA A-8 962 RX B.OG t-MI OUTSIDE R'Y\\CtJ ROOM A-9 962 RX El..DG EAST A-10 EAST CRO MODULE AREA A-11 \\'\\<EST CRO MCX>ULE AREA A-12935 RX BI..DGNE TJP DRIVE AREA A-14 HPCI T URBINE AREA A--15 896 RX BLDG ORAJN TANK ROOM A*16 RCIC EQUIPMENT AREA A*11 EAST CORE SPRAY & RHR AREA A-18 VvEST CORE SPRAY & RHR AREA None None None K01 ttOsnL£ ACn ON ilteWIIIIlQin Lon Of Pnysk;JI Control oiiM l'..:llty

[J HGU I 1 I 2 I 3 I 4 I 5 I DEF I A HOSTILE ACTKlN has occurred such that plart personnel are unable to operate equ~rt requ*red to mairta1n t;afety lurd:Ons 0

H01.2 I 1 I 2 I 3 I 4 I 5 I DEF I A HOSTILE.ACTtoN has caleed la ~I.Ke a Spert Fuel Coohng Sys!emsard IMMINEr.rffuel damage is hl<ely fora lrestiy off.

loaded reactor core 1n pool None HOl Oth<< CondltiOM EICIUIIlg Which In the Judg!Mnll ol the fm<<QMCJ OlrKtor Watl-o.d*OIIio<l ol Ge<w.t !IMfgMl{:J 0

HG2.1 I 1 I 2 I 3 I 4 I 5 I DEF I ether cordlttons exist whdl m the judgment of the Emergency Dr ector indicate that events are 1n p-ocess or have ooet.rred wt1ich tnvolve actual or 1rnm1nert sub6tam!!l <XXe de!'J"IIIWIIOO or meltng with poteol181 for k:lss d ooroJrwnent tntegity Releases can be reasonably expected to exceed EPA ProtectiVe Act10n Gude~ne exposure levefs otfSlte for more than the immediate &rte area None Q

HS4.1 I 1 I 2 I 3 I 4 I 6 I DEF I A HOSTILE ACTION i8 oocurnng or has occooed within the Ptart PROTECTED AREA as reponed by the Se<:unty Shltt Supe<VIOO<

1'1$? COI'III<oiiiiOGm I!YiV;U.tiOI'I tt~~ a..nlnllllUd WI<! !'llolC Cont<OI Cilll\\nOI Be E.. IIIb"$1\\IMI u HS2.1 I 1 I 2 I 3 I 4 I 5 I DEF I Control room evacuaton has been tn~llatecl AND Control of the plant cannot be establi~hed per C.4-C, ShtJ.down Oui:Side the Cof1r()j Room, wt hln 10 rnnul:es ttS30th<<CondldonsEldstlng'MtkhlnrheJud!ilfTlllllof!M Em<<9911CY OlrtoetorW...-r..t;O.d..-OitionofSil* "'"" &r!Mg..,.;y 0

HS3.1 I, I 2 I 3 I 4 I 5 I DEF I Othef COI'l(ltiofl!l. ex$1: wncn tn the judgmet't r:l the Errergency Director indicate that events are n process or have occurred wtld"l 1nvolve actual Of l1kefy mlliJOf fa1kxes of plant flJ'"ICOOns needed for protection ot lhe pubic Any re ~a$1!$ are not expected to resUt in exposure levels which exceed EPA Protective Acbon GUideline exposu-e levels beyond the site

"'"""~

None lltA1 Arr1 UfiiP't.AfilfiiEOIItto!Nse ol O.~llfllqul<llltM!Ioae!NitytottM Ell>Aro....- I~Ex CM<IIlOOTim.. ~t..Off*Do... C*ul.tion ManuMllmillor1SMinutnllf l~

0 RA1.1 I 1 I 2 I

3 I 4 I 5 I OEF I V AUO reading on any effluent monitor that t:>Xoe4!'0$ 200 llrl'le'S lhe alarm setpojr.l establiShed by a current radoact.Mty ctscharge peorrM for 15 llllfl~es or longer 0

AA1.2 I 1 I 2 I

3 I 4 I

6 I DEF I VALID read1119 on any d the lollowlrg radiatiOn morutors that exceeds the fe&Ong Shown !Of 15 mrutes Of lorQef Mcnror Alert

~luentMonitor (ChAorB) 1 46E7,_.Q~sec*

RB Vert Effluert Monitor 2.16E6,_.Qisec (ChAorB) l.loll<l Servtee Water 31,400 cps Discharge Canal Mon1tor 93,000 cps TEWWS 900.000 com-0 AA1 3 I 1 I 2 I 3 I 4 I 5 I DEF I Conflfmed sample anaiy$1$ for Q3SeOL$ or ~q.ld release nd!cates conoeruab0n6 or release rates, W1th a rele~

cUat1011 of 15 flllf"lJ1es or e -ver. tn exceu of 200 times OOCM

<10 times OOCM calculated !mil 48tlf'l'le&COCMcalcUated *rnt lltA10wlwge NI IIIM..

I.cl ~.-. er LOSIOIWllfil.*.... lhal HM Of W11

~==I In,,_ ~-Ill'S oflrf.... lled f\\MI OUisl(l.e thJ II;Nidor Q

RA2.1 I 1 I 2 I 3 I 4 I 5 I DEF I A VALlO alarm Of re21ding on any dthe follow~ngradla!IOI'l

""""'~

MOI'lltor A-; ~~~~~=~~~

A-31027 RB WStalfWay RM*11-~2A Reactor BUilding Ventilation Exhaust PtetJJm Montor Ch A RM-17-<1528 Reactor Bu11d1ng Ventilation Exhaust Plerun Montor Ch 8 AlarrrvTnp

~ ~m:'~r 100mRihr 26mR!tr 26mR!tr RM-17-4531\\ F~ Fool RadiatiOn Morutor Ch A 50 mRihr RM-17-<1538 F~ Pool Radra!iof'l Monitor Ch 8 50 mRhlr 0

HA1.1 I 1 I 2 I 3 I 4 I 6 I OEF I Se1smc event GREAT ER THAN Operatmg Basis Ealthquake (OBE) as 1ndtcaled by Am!X1C1a:or OPERATIONAL BASIS EARTHQUAKE (6-C 1 3) receM!d 0

HA1.2 I 1 I 2 I 3 I 4 I 5 I OEF I Tornado or higt wind!i GREATER 1HAN 100 fl'l*1 witt'in plant PROTECTED AREA bouncl.ary and r~ng "' VISIEl.E DAMAGE to any plant structures I equipment (Table H* 1) or Control Room irdcabon of degitded petformance cl tl'l068

~terns.

0 HA1.3 I 1 I 2 I 3 I 4 I 5 I DEF I Vehicle crash Within plart PROTECTED A_REA bolnjary and resulting m VISIBlE DAMAGE to any plart structures or ecp.lipmeri lhere;n (Ta ble H-1) or Control Room irdicDtiOn of tJegra<led perlormance of thO&e systems 0

HA1.4 I 1 I 2 I 3 I 4 I 5 I DEFj Turbine f11i u-e-generated missiles res\\.Ji n any VISIBLE DAMAGE to or penetration ofaf"'/ plart areas (Table H-1) 0 HA1.5 I 1 I 2 I 3 I 4 I 5 I OEF I l)ncQntrolled flooding ltl areas (Table H-1) of the plart that reslAts tn degraded safety system performarce as lrdicaled In the caA:rol room or that creates tndustrial safety hazards (e g,

electl'lC $hOCk) that precJIJ(les aocess neoe-ssary 10 operate or mon~tor safety eq.tip-nent o HA1.e I 1 I 2 I 3 I " I 5 I DEF I Either d the following CIOCUen:es Wlthtn plant PROTECTED AREA b01-f"16ary and rHl.<<1ng In VJSIEl.E DAMAGE to f::Cant structvres contallllrg equipment l"'leOO&SaiY lor safe &hUI:do'M"l, or has cau&ed damage as EMC!enced I:P,' Control Room trdicatiOfl ot degrltded pelformanoe ot those systems RNer ~I GREATER THAN 919 ft e(

OR River level l.ESS ll-IAN 900 5 net H-'1,I'll! or VlPi.OSION Atfe~llng thl ()pM01bUIIy of PI- ~leCy Srsl"""to<l".-;llo ht.tl-llshO<M.lllnii...,S,.-eSI"IUido....,

0 HA2.1 I 1 I 2 I 3 I 4 I 5 I DEF I FIRE or EXPLOS!()t\\1 11"1 any of the foiiOWiflg area& (Table H-1 )

AND Affected system parameter II"ICicalions show ClegJI!ded perl0fl"l1ance or plant pefSO~

rep;~rt VISIEl.E DAMAGE to permanent st ructlKe~ or eq~.~:pmeot Wltt"Wl the specified area

~~~~i~~JJ~~S1~~,~~:~

Q HA3.1 I 1 I 2 I 3 I 4 I 5 I DEF I Report or detectiOn ot toloc or a~x1ant gases wl(hin or ooriiQUOUS to a VITAL AREA (Tat:te H*1) in C0f1Ce1"1ttat!OOS that may result 1n an at~e 1M MEDIATELY DANGEROUS TO UFE ANO HEALTH (IOI...H) 0 HA3.2I 1 I 2 I 3 I " I 5 I DEF I R!!portor det:ecnon of gases tn concentrabon GREATER THAN the LOVY'ER FLAMMABl.ITY UMIT withtn or contJguous to a VITAL AREA (Table H-1) 0 HA4.1 I 1 I 2 I 3 I 4 I 5 I DEF I A HOSTILE />CTION 1t OCCUTif'lQ or has oocurrOO wrthn the CMtJER CONTRQLEO AREA as reported 17,' the Sea.-iy StvftSupeorvisor

[J HA4.2 I 1 I 2 I 3 I 4 I 5 I OEF I A validated notJfiCalion from NRC d an a1rhner aUad< tiYeat within 30 mn~e:s of the Site 0

HA5.1 I 1 I 2 I 3 I 4 I 5 I DEF I

&try into C 4-C, srutdown OUside the Cortrol Room, lor ooncrOiroomevacuat.oo HMOth<<ConditloM fltlstlng 'MllchtntheJud-IJmenll of the fm<<QtOCY OirKtor w.t"a-1111 0..:1...-.tion ol '"""'-rt 0

HA$.1 I 1 I 2 I 3 I

I 5 I DEF I Other rordrtiOI"IS exiSt wt1id't 1n the )lidgmem or the Ef'l'lefgency Oired.or 1rdcate ltlat ev1mts are in process Of have oco..ned whiCh iwolve actual or ~kely potertlal substantial degradation d the level of safety d the plant An( releases are expeocted ID be ~!Tilted to small fr&<<~oos of the EPA ProtectiVe Action Guldel ne expowe level$

None lltU1 "'FVJ UNPl."'fiiNI!:O lit...,.. o l 0-ous Of Liquid lltidiC>>CtMiyto thl Envlrorw--.1 ttullll ExcHik TWD Tl-thl Ofh.lt* Dose C*:.utlon M~Umillol'501111nu1Horl~r 0

RU1.1 I 1 I

2 I

3 I 4 I 5 I OEF I VAl() readng on ¥?f effluer<< monrtor th<lt eJo:ceed$ !'NO IIIT'le&-

the atarm setpoWn estabhshed by a cu-rert radloact.Mty discharge perm!: !Of 60 rnrutes or longer 0

RU1.2 I 1 I 2 I 3 I 4 I 5 I DEl' I VALID re~ng on ant of the foliowtng radiation montors that exceed$ the rea<lfll Shown fOf 60 m f'li.Aes or lOnger Monrtoc

~uertMOI'lltor (ChAorB)

UE 7.3E5jJCIIsec RB Vert Effluert Morvtor 216E<t,..Cilse<:

(ChAOfB)

LI!W Service Wster 31<1 cps Discharge Carel MorMtor 9 30 cps lEJIM'S 37752com o RU13 I 1 I 2 I 3 I 4 I 5 l oEF!

Conrlf'med saiTC)Ie analysts for gaseous Of llql.ld release N""tdlcates CCIOCf:ntfatiOI'ls or release rates, with a release duratiOn 0( 60 ll'W'lUtesor longer, in exceu d two lime!. OOCM hmil 0

RU2.1 I 1 I 2 I 3 I 4 5 I OEF I VAllO indlcabonof uncontrolled water levellower1rg nthe reactor refueling cavJty, sper.l fuel pool, or fuel lram.fer canal with a~ irra<iated fuel a.s.sembllel rema1ning covered I:P,' water as llf"dcated b'f any of the foltowuv UnexpectedSpert Fuel F\\xlllowwa:er level alarm Visual ob6eNatiOfl of a n Uf"WXIf'ttrolle<J water le'Vel drop belOw a fuel pool skirrmer surge tank tnlet

();)servahon of water leakage lfto the aywel or the reactor tulding from pping penetrnlions surrO!Xldng the drywel AND Any UNPlANNED VALID Area Rad131j00 MOrMtor readirg nse as Indicated Dt af1'J of the followtr-g A*1 1027 RB NE Low A*2 1027 R8 N HIGJh A-3 1027 RB W StatiWay RM-1 7-453A or 8 fuet flooj Monconng Sy$tem o Ru2.2 l 1 I 2 I 3 I 4 I

5 J oe=!

Any UNPLANNED VALCl Area Radiation MOrMtor readirg r1ses l>j a factor of 11XXlover rJ()(maJ" Ievels

'Notmel levelscan ~ !XIIl~edMthe hlghest~inginthepur

~-four hours exc:Wngthe curreM~kvaJue WJI filiollnl iN\\d OnHuctlve """"om-Afl"toetWlg 11M Plilnt PlltOTECTEO AlltlA 0

HU1.1 I 1 I 2 I 3 I 4 I 5 I OEf I Earthqual<e felt 1n plart as lfdlcated by Consensus of Cor1rol Room operators on cMy AND

~~or EARTHOJAKE !6-C-08! recetved

[J HU1.2 I 1 I 2 I 3 I 4 I 5 I OEf I Report tv pi lift pe~nnel Of tornado or hgh Winds GREATER THAN 100m~ withlfl plar<< PROTECTED AREA bot.rdary D HU1.3 I 1 I 2 I 3 I 4 I

5 I DEF I Vehicle crash 11"110 plall: structi.Kes. or &y$1.ems Wlth.n pfall:

PROTECTED AREA boi.JI"ldary IJ HU1.4 I 1 I 2 I 3 I 4 I

5 I DEl' I Report by ~arc peorsonnel dan t.nantb pared EXPLOSION within plart PROTECTED AREA bOoo:::lary restAting 11"1 VISIE!lE DAMAGE to permaneri structtxe or eqUipment

[J HU1.6 I 1 I 2 I 3 I 4 I 5 I DEF I Report d turbine fadlse resutl!ng In cas1ng penetrat!Ofl o r damage to tlrlline or generator seals o Huu I 1 I 2 I 3 I 4 I 5 l oEF!

Unoortro Ued flood1rg tn areas (Table H*1) ct the plant that has the potenbal to arfect sa~ety related eq.JipfTll!fll needed for the curet1: operi!lllr-Q mooe 0

HU1.7 I 1 I 2 I 3 I 4 I 5 I DEF I Any of the following higl river level or low rt..'ef level occurrences all"ect1ng the plart PROTEC TED AREA River leve!GREATERTHAN918 ft~

River level LESS THAN 902 4 ft el HU2flllt!'Mthln PIItOTI!CTI!DAIIti!A8oun:l.oryH01E:*lk*go.ll_,*dWitl"in t )Mir>vtHoro.tKtion 0

HU2.1 I 1 I 2 I 3 I 4 I 5 I DEF I FIRE tn bU41dn""IQ"& or areas OOI"'I.lgtJ(:I(.$ to any Table H-1 area not exilngul$hed Wlthm 15 rn m.in d control room nobficabon or venficatiOilofacontrolroomaBrrn HUlllt... ~H Ol TOltlC:, "'~l"lfd-, 0t f iMtlrtUbll GiSH DHmiMI o.tl"lmlnllallofilormOifOp..-..tlonol tM I'Iant 0

HU3.1 I 1 I 2 I 3 I 4 I 5 I OEF I Report 011 deted.IOI'l ot tox.c, asptr(Xiant or flammable gases that hs~or could enter the Site lll"ea l::toun:i1ry tn arrourts that can affect IIK)RMA.l PlANT OPERATIONS a HU3.2 I 1 I 2 I 3 I 4 I

5 l oEF!

Report br' t.ocal, Courty or State on'IOiaJS!or evacwuon or sheltemJg of srte r::e!'SOmel ba.sed on an otfs~ event HI.N Conlltmto<l S£CUIIt4TY CONOITlON or TrnM WNCn lndt iiiH a Pot-;11 [Mgr-onlntM L* vetor S~lllyOI tM l'l01nl 0

HU4.1 I 1 I 2 I 3 I 4 I 5 I DEF I A SECURITY CONDITIO'! that does NOT ~

a HOSTILE ACTION M reported by the Secu-lly Shift S~r o HU4.2 !

1 I 2 I 3 I 4 I 5 l oEF!

A credible MNGP sect.rrty threat no!llica-non o HU4.3 I 1 I 2 I 3 I 4 I 5 !oEF!

A validate<:! notllicatiOI"t from NRC prCNKing 1riorrna110n rJ an a1rcraftthreat None 0

HU5.1 I 1 I 2 I 3 I 4 I 5 I OEF I Other cond!:tons exis.t wtld"l in tt-e Judgneri ot the Emet"gency Director Indicate thltt everts are in process or have occurred whiCh irdiCate a potenl!ltl de!Jadallon of the ~eve! of safety ot the plant No releases of radioactr.te matenal requrmg olf$tte response or mor'II!Or*ng ace expected I.X'IIess ruther degaldat1on of sa-fe!y sy,.tOOI$ OOCUI'$.

I!U1 o-.g.tolltoHM~c.-eotmM~:MINT.ooNOAIItY.

J ~t!;,~~ ~~Ja :nJ~

3 a ICW J~ &mL~~~I!NT BOUNDARY TonladoSb-11\\e

.J EU1.2 I 1 I 2 I 3 I 4 I s I DEF I Accdenlc:ondltlona..n.ct1ng aloaOedc:ask CO~I~I.EN T~Y AccidentaiTransiMCaak~

0 ~:~lti(tn in Jhi!plllL $tf! b!J-! a 1

,:Ltlft~!~kes 1os.s o1 loaded fuel sUage cask CONRNEMENT BOUNOARY

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 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 I

I

!l!l~!l~!l;l!l§!l!l~!l§;l!l!~ GENERAL EMERGENCY I SITE AREA EMERGENCY I ALERT I

UNUSUAL EVENT I

t!~~::a:::::~:~~

c.-

1MI./

c-

'""OM -

At Lo.tiJIIAIOfhltt'""-.w:I LOMofAIIOntlc. AC~IO l!sSMWUI..

IAS ACilo_C...,.IO ttMntt:ll~triK\\CtodiO*U1tiM~

soun:e bGitL\\TDITMANISmlnuiH -'IIhlllnY..._...

......,..... _................ tta.:koul

.U1lott of.. ~'-" 10 1E...._.III.._..IotOitlAftR~Mt5 0

SG11 I 1 I 2 I 3 I I

loss of offSite power to Essential busses 15 and 16 AND Failu'e ol 11 Emef'Qency [)esel Generator and 12 Eme.veocr~l Generator to supply power to Es~tial busses15 and 16 AND E1ther of the lollow1ng (a or b) a Restoratoo of at least one Essennat bus within 4 hotXs ISwl ~kety.

DR a

ss1.1 1 1 I 2 I 3 I Lossofotrsitepowe.-to Essential busses t5<Wid 16.

AND Failure of 11 Emef90rlCY OteseiGenerator ;~nd 12 Emeorgenty I:M$!!1 GeneratOf IOsupp/y power10 EMentialtKmes 15 and 16.

AND Fall~Se to restore power to at least one Essert1al bus, 1 !5 or 16, w1th n 15 ITW'li.Aes from the ~me d 1068 ol bothoffsrte a nd onsrte AC power

b. Cont1rung degradatiOn of core cooling based on

I::gS::iJ:S~~=J FI$SIOI'I PrOOJct Barner morutorng as Indicated by RPV o SS3.t. I 1 I 2 I 3

~~LESS THAN.t26 in (TAF)

Lossot al VItal OC power based on LESS THAN 106VOC oothe 125 VOC main distnWion busses for GREATER THAN 15rnrues M2P...... ~tPie"-~1

........ ~.., A....,.-o

=~:..-=::~:-..:~':-:-;!.!"-..

c SG2.1 I 1 I

2 I

I a An al..lomatiC scram (trip) failed to srutdoWn the reactor AND b Indication(&) exist that all marual scram actions were not successfU 1n redo::tng power to LESS THAN 4%

AND c Either of the folow1n9 ex1st or have occured due to continued po.ver gel'lefahon

RPV level canrot be restored and maintatned GREATER THAN OR EQUAl TO -149 1n

lndication(s) ex1st that heat removal !S extr~ty dlallerged as indicated "f Torus terfl)erati.Xe and RPV P"esSISe cannot be mairtalned LESS THAN Heat CaP<'¢1ty L11T11 (C !>-1200 fig M, SPOS 78) 112 '*""~"---....._.t,.....,l"*_...._* c-.-.or"""'*

... ~,.__.... o.........,......,...........

........._.................,w.NOTs.-.t.ot o 5s21 I 1 I 2 I I

lndication(s) exist that automatiC and marual scram were NOT StX.CeSSfd tn reGu:;ing power to LESS THAN 4%

0 SA5.1 I 1 I 2 I 3 I AC power capability to Essert~l bllsses 15 and 16 reduced to oft/ one of the folloWing SOISces lor GREATER THAN 15 mini.Aes

1R transformer

- 2R transformer

1AR transformer

- 11 EOG

12EOG AND An{ additooal single failure wdl reSUt in statJOO blaclo:::lt.t tA2P...... ~"-*'"'...... ~ Ioo~- ~Ofl--

.......... "-.... 0...*,.._.~.,..........

~..... ~

0 5A2.1 I 1 I 2 I I

lndication(s) eXIst that a Reac10r Pr()(ectlon System setpoirt.

was exceeoeo AND RPS aotomaticsaam didwtrecfuoe power k)LESS THAN 4%

AND Art( of the toiiOWlng operator actoos m successfi.A 1n reduCing

!XJWer to LESS THAN 4%

manual 9Cfam pushbtJ:tons

mode swrtch to stu.down

- AJ!ernate Rod InsertiOn (ARI) 0 SU11 I 1 I 2 I 3 I I

Lossofotfs'rte JXlWef to Essert1al busse-s 15and 16for GREATER THAN 15 min~J:es AND Essential bu$&e$ 15 and 16 are JXl'Wefed t:¥ thelf respectiVe Emergen:y Diesel Generators None

... COft'CM4* Lou of HNIIIIIIIIO'f<ll C.IMily SU21~ylolludlllequlrtld~'IW:'*'T.ctn~ llpKIIc....,

-*~

None None None None None 8

F0 1.1 O SS41I112 I 3I I

Heat C8pec11y l.JITIIt Curve (C.5*1200 fig M and SPOS 78) exc~ded o 5ss.t I 1 I 2 I 3 I I

Loss of mos1 or a ll annunctatofs associated wrth safely systems on control room panels C03, CC4, COS, C06C, COB C20, C24 and C259 AND SIGNIFK::ANT TRANSIENT in progress AND CompensatO!)' non-alatrring ll'ldications 21re Ul"'aVailat:H!.

AND lndlcatiOflS neE!(Ied to montor the ability to shl.t down the reactOf, ma1nta1n the core cooled, mainta1n the reactor COolant system 1rtact, and mainta1n conta.nmert irtact are 1.6\\available None None None None UA U.. II'UINNI!O Loss of.OSI or M.....,..,._ olnnuncl.rlon or lnciCMtonln CortiOI IIOCII'II WMh DhW 111* IKIMnCAifT

.':"!'."*etnlnPN!gr*s, or(l)Campenl;llllooy~

!fDCliiiCII'S W*Uftw.....

a SA4.1 1 1 I 2 I 3 I Uf'..PLANNED loss ot most or all annunaators or n::hcalors asSOCiated w11h safety systems !Of GREATER THAN 15 ITIIru:es on cortrol room panels C03, C04, COS, C06C, COO, C20, C24 and C259.

AND Erther Ol the followlng (a or b) a A SIGNIFK::ANT TRANSIENT 1$ 1'1 progress OR

b. Cornpemat<xynon-a!aiTT'Iing:indic.atiMsareunavai&able.

None None None 0

SU2.1 I 1 I 2 I 3 I Plant JS no1: brougtt to reqt.u ed operatlnQ mode within TeeiVIical Spe¢1fiC8110nS LCO ActiOn Stateme-rt TimE'

&UlUiff'I.AHUILouof._orAII....., I¥-~I.etonor lnlkilforolnlMCOI'IIollloomforGr.-nun1,...,...

0 SU3.1 I 1 I 2 I 3 I

UNPI..Af>t'oJED loss rj moSl or a ll.ann..nc~ators or 1ndicat0ft>

assooatedwllh satetysystemslOfGREATER 11-lAN 15 mintAes on control room panels COO, C04, COS, C06C, COS, C20 C24 AND C259 I UIUIIIP'LAIHIIIDLoss oiAIIOMihoiX OftiiM ~illlont 0

SU6.1 I 1 I 2 I 3 I

Loss of all Table C-1 OOSite COI'lVT'IU'liCations capabll1ty affecting the ablhty to perform rOIAine operations

[J SU6.2 I 112 I 3I I

I Loss of all Table C-2 otfsite comrnt.rliCatiOns capabdity 0

SU4.1 I 1 I 2 I 3 I

Offgas Ptetreatmert RadiatiOn Monitor (RM*17*150A and B) hi!T' radiation alarm (4-A-12) reoerved indicaung fuel clad degradation O

SU4.2 I 112 I 3I Coolant sa~TlJfe actl',..lty GREATER THAN 0 2 J.ICI}gm dose eqUvatentl-131

&IHftC& L.....

0 SU51 I 1 I 2 I 3 I

Unidentified or pressure boundary leakage GREATER THAN 10gJ:m 0

SU5.2 I 1 I 2 I 3 I

Identified leakage GREATER THAN 25 gpm 0

SU81 I I 3 I

AA UNPLANNED extended posllive penod observed Ofl nuclear instn.merltallon 0

FA1.1 0

FU1.1 Loss of ANY Two Barriers AND Loss or Potential loss of Thrrd Barner(TableF-1)

~entJ~I Loss~ ANY 3

Two Bamers(TableF-1)

ANY Loss Of ANY Potertial Loss of EITHER Fuel Clad OR RCS ANY Loss or ANY Potential Loss ofContairrnent (Table F-1)

(TableF-1)

Table F-1 FISSION PRODUCT BARRIER MATRIX NOTES 1

The logic used for these n lttahng condrt1001:1 reflects the folloWing oons1defahons The Fuel Clad Barrier and the RCS Barrier are ~ted more heav~y than the Contallmert Barrier. UE ICs associated with RCS and Fuel Clad Barriers are adctessed under System Malfooctioo ICs At the S1te Area Emergency level, there llllJSI be some-ability 10 dynamcally assess how far pr~t condrbOns are from the threshold fOf a General Emergency For exarrpe, 1f Fuel Clad and RCS Barrier"Loss* EALs eXISted, that, 1n addition to olfs1te OOse assessmerts, W<<Jid reqwe cortlrJJal assessments of radl08ctJve ifT.Iert.Of)' and conta1rvnent irteglty. Alternatively, 11 both Fuel Oad and RCS Barrier "Potert1alloss" EAls emted, 1t1e Emergency ()rector would haVe more assurance that there was ro immed'ate need to escalate to a General Emergency.

The ability to escalate 10 higher emergency classes as an evert deteriorates must be maintained. FOf example, RCS leakage steadily increasing woi.Ad represert. an IncreaSing nsk to pubic healltl and safety 2

Fiswn Prod.Jct Sarrier ICs must be capable of addressmg event dyna!TIIcs Thus, the EAL Referer.::e T!!ible F*1 states that irrmnert (i e., w1thm 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) Loss or Poten:~a t Loss shoUd result in a clasSification as if the affected threshold(s) are already exceeded, partictJa~ for the higher emergency classes Fuel Cladding Barrier Reactor Coolant System Barrier Primary Containment Barrier 0

Loss 0

1 Pn!TWY 9'l!'ll&rrt MIN!ht I eye!

Coolant: ActNrty GREATER THAN 300 f!Q/gm 1-131 dose eq..~ivalert 0

2. Reactor \\{esse! Water l eye!

LEN"el l ESS THAN *149 In (MSCR\\NL.)

0 Potential Loss 0

1 Primarv Cootaru ActM'Y 1 ryt>J NotAWticable Q

Loss 0 1~

!Jfywell Pressure GREATER THAN 1 84 ps~g NOT caUBed by a loss of ON Cooling Q

Potential Loss 0 1~

NotAppl~:a~

0 Loss

" '~

Rapid unexplained decrease n drywell presSU"e followlfll lr¥1131 OR D'ywell preSSl.l'e response not COOS!Stert. wrth LOCA. ()()()Qtlons ll"ldicat1ng conta1rrnent t:teach 0

Potential Loss 0

1 ~

Orywell Pressure 56 PSIG and 1ncreaslflg OR GREATER THAN OR EQUAL TO 6% hydrogen and GREATER THAN OR EQUAL TO 5"4 oxygen in OryNeK or Torus 0 2. Renctor Ylsw! Water l tm:!

0

2. Reactor yesse! 'fllater Level jcoi22JR~e~

act~~~~~~e~m;;wiM!;ir;;;er:L;t evl;;e;!t --t<OU2C". R~*~*~~or~y

~e~sse!~W.iitio;er~L:<i~<>i*--1 0 2 Reactor Yesser W3ter Level Leve1LESSTHAN*126in (TAF)

LevetLESS THAN-126n(TAF)

Not Applicable NO( AppliCable PnmarycontafYnentllooding requred 0 $~

a 3 CNMT IS91j)1'9n f >ll!Lre or 9.tPSIM 0

3 CNMT t@t100 failure or Btoan FaillXe of both valves In any one l1ne Not Applicable-0 3 ~

U!'I&Oiab!e Main Steamlir~e Bleak as indiCated by the f21Hure of both MSIVs In any one ltne to close AND EITHER RCS leakage GREATER THAN 50

!P'n inside aywen DR to close AND downstream palhway f-----------11 to the efh'rormert extsts a 3. QotWf>ll RaOOo MoMQ!jOO Corta*rrneri High Range Rad mof'llor reading GREATER THAN 15E3Rihr a

6 Emeromu OirectJ:tf Judgrnen!

Any oondibOfl '"the optnion of the Emergeooy Director thal trdcates Loss Of Potentlad Loss of the Fuel C~Barner Table H-1 EAL Classification AfeM Reactor 8!dg HPCI Bidg Ttxl:lineBidg Control & AdminiStratoo Bldg Diesel Generator Bldg Diesel Fuel Od Transfer House EFT Bldg lntaKeStru:ture Security Boilding 1

Secunty Diesel Generator Bulldmg 1

Nc:te1*Tl\\t5ebuildlf95¥Strlttonoode<edwhen dnsif'Jin9 per HU2.t. HA3.1.nd HA3 2 H1gh MSL flow Of h9'1 steam IIS!ne! temperati.Xe ann.Joc1ators OR Direct report olsteam release loCilJl~llrywt!:§'~tR~adilJ~

t~oo>DJ.!M.tlio!'l!ii!tormrow-J o

4 Drywett Rsswoo Mgn~tnqm I'"

Not Aj;plicable Conta1rrnent: Hi!;,tl Range Rad monitor reading GREATER THAN 65 RIIY a

5. Erpergeroy Djrec!of k!drJment An( condioon 1n the Optnion of the Emergency Director that indicates Loss Of RJtential Loss of the Fuel C~Barner a 6_ frrerr,ux;y O.recror ttdgmer1 Any conditiOn in tile opuion of the Emergency Director that indicates Loss or Pol:ent.al Loss at 1:tte RCS Barr~r T-.e C-1 Ons.. Corrmun6elll:loM SysliMM Corrmerc1altelephones Aart telephOnes Portable radios Aart. page system Tallie C-2 Offstle Communtc.t:6ons Systems Corrmercial telephones FTS Phone System Radio Rece~veoTransmtte.

Un solable pnmaty system leakage outside drywell as lnckate<l!:.¥ Ally SecondaryConfajrYnenlarea temperature GREATER THAN max nonnat (C >tJOOT.a~

W)

DR Art( Secondary Contauvnent area radiatiOn GREATER THAN max normal (C 5*1300 Table X) 0

5. ~

Noi:Appi1C8ble a 6 Emergency Dlrectnr hrnrnern Afr.J conditiOn in the opifliOfl of the Emergency Director ltlat indiC3tes loss or Potert~al Loss of the RCS Barrier OR IntentiOnal Primary containment venllng lf'l progess per EOP$

OR Ul'liSOiat4e pnmary system le<~k<lge outside dryWell as ir.d1cated by A"'/ Secondary contatrrnent area temperatUfe GREATER THAN max sate (C 5-1300 Table W)

OR

~Secondary conta~rrnent area rad~tion GREATER THAN max safe (C.5-1300Table X)

Cl5~

Not A.pphcaNe 0

6 Emergency Quecw 11 rlmlent Aft.~ condihon in the: Optrioo of the Emergency Director that indiCates Loss or Potert1atloss of the Contalf'll"l'lenl Barrier

05. ~

NotAWJIC8ble 0

6 Ememency Qirector !t!l!J!Tlf'r!

Any coo0t10n in the optnion of the Emergency Director that indicates Loss or Potential Loss or the Cont:amment Barrier i

~ "

~

Modes 1, 2, 3 ~

MONTICELLO NUCLEAR GENERATING PLANT 5790-101-02 Revision 10 Modes:

IT]

Power Operation

[TI Startup

[TI Hot Shutdown IT]

Cold Shutdown

[!]

Refueling I DEF I Oefueted

~ EMERGENCY ACTION LEVEL MATRIX Page 1 of 2 Approval: ~

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 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 I

I

~j!~j!j~!j~:j!~j~~:~~j!j!l GENERAL EMERGENCY I SITE AREA EMERGENCY I ALERT I

UNUSUAL EVENT I

~

Abnormal Relei1$e...

Effluent Hau rds Ofklleft.ld c-...

Explos kln Toxrc and FiammHM lt:01 Ofhb Dost~ lt:nulllfllil from<<~ Actu.l << lmminenll lt_..He <<

~- Jt~o.clilllly [K.-h1000 mJII-TUM!<< SOOCI mlt.m 1trtl'oldCMforthtActv*Off'WI~ttd~llllor>oiiM~M UslngActuilllllttloOfcHogy

~ - tfdOM n~r~ *re fN,_.,._~

thellmec:A Oecl*~lon. ltleCIOIWhc*toon~ld be WI~ on RG12~ei><f ~

R01 1 'l".tlileneo::nNry~raOOrls~notbe~yed-.rong r-..lb., d'141~ *s~~dboln~totteodlc:orrplll!led*no:>r,_.

!Qd~mi~ft!'IO!ol~lfie,bona.houlr:lbew~~""'~

t RG1.1 I 1 I 2 I 3 I.. I 5 I DEF I VAUD reading on af'1./ of the following rad.ation roonitors that exceed&ori& expectedto e)(ce4!dthe reading shown fOf 15 rr.ra.rtes or torger Monitor GE Stack Effluent Montor 2.1E9~Cilsec (ChAorB)

RB Vert. Effluent Monitor 1 5E8 JJCV$ec (ChAorB)

LW!<I Service water N/A O.scterge canal Monrtor N/A TBNWS N/A

~ RG1.2 I 1 I 2 I 3 I.. I 5 I OEF I

~assessment USirg actual me~e<>ro~e>gy ~rocatet aoses GREATER THAN 1000 rrRem TEDE or 5000 rrRem thyroid CDE at or beyond the s~e l:lounOaly 0

RG1.3 I 1 I 2 I 3 I.. I 5 I DEF I Fteld SUfVey resUI:s ll'ldic:ate closed Window dose rates exceedng 1000 mRem'IY expected to <.::O!'ttnue fOf more tt'lan one hotx, at or beyond the ~e boundary OR AnalySIS of field SlJI"'Iey safll)le& ndlcate thyrOid CCE of 5000 rrRem for one hc:xx d tnhalation, Bl or beyond ltle Site

""'"Y None None None None HG1 HOSl\\LI! ACtiON ~tsuling lnlossoflfltlysluiConrrolofltM

,.t.. r,.

J HGu I 1 I 2 I 3 I

I 5 l oeFI A HOSTILE ACTION ha' OOO!.Kl'ed WCh N t plart pef'6()r't)el are U"'al*! to opetate eq.. 11pment requtred to rnatrtatn safety

~ HG1.2 I 1 I 2 I 3 I 4 I 5 I OEF I A HOSTILE ACTK)N hils c&t.JSed fatltxe of Sped Fuel Cool.og 9yo$tefn6 and IMMINENT luel damage tS ll~ly lor a fl'eshfy off-loadedreactorOOfelnpool None HG201h<<Condldons[JclsllnQWhktl lnlhiJudgmenlofllllt.m.'g.n<::y Olredor w.~

O.CI*rllllon ofGtnHillll!m*~rK J 0 HG2.1 I 1 I 2 I 3 I 4 I 5 I OEF I Other corUhons exiSt which 111 the jOOgnent of !he Emergercy Director llldicate that everts are m process or ha11e occurred which if1V<llve ~Jctual or irm"'lneft s\\.bstartlal core ctegad!ltton or melt*rYJ wrth p::~tentiallor loss of oontatnmert trtegrity Releases can be reasonabl'{ e-xpected to f'Xceed EPA Protective ActiOn Guidf'hoe expoSU"e levels offsite for roore than lhe lmneciate site area None ltSl Ofl'skt Dose lti'MA:InQ hm iln Actual or llnn*l<<"f ~81nse of GKI<loln ltlldiNCttvlty Exceteh 'OOmlt..., nDI!or ~mit""

Tl'lw'l'o4dCOI!fo<lht Ao;CualorPI'oild~O..*io<lofthtltlitfiSI NQ~e* lfo:kJM~-mef'llr"uben~..-,4,ble

thetimeQf deel:ilr~. the d~~tiOn Vlo.lld be bo>sed onRS12 i~Qf R$11 Wltle necef.SII'Y Oecl.-auom tllould nol be ~ye<I-~JOg rft ~!b, th01~ "~

~ld be ll'lllli>ted leomp&n!d in or~

todet~llll'oec~ifie~Qonthoull;l be~~~rtlyMC.tl;oted Q

RS1.1 I 1 I 2 I 3 I 4 I 5 I DEF I VALIO readtng onany dthe followng radiMJOO mol'lllors lhal exceeds or IS expected to exoeed the reading shown lor 15 mii'IUesOI'IOngef Monttor SAE St3ck Etnuert Mortlor 2.1E8JJCt/sec let'~ A orB)

RB Vert Effluent Monrtor 15E7,..clls.ec (ChAorB) lJsWi<j SeNiceW3ter N!A Olsctsrge Canal MOOitor NIA TBNWS N!A 0

RS12I 1 I 2 I 3 I 4 I 5 loeF I Dose asses.smei'C USifll actual meteorotog,- W'IQCates c::I06e5 GREATER THAN 100 mRem TEOE or 500mRemthyrOKICOE at or beyond the &lie bOI..ndary 0

RSUI 1 I 2 I 3 I 4 I 6 IDEF I Fteld SlAVe'( results indicate cbsed window OOse rates e.xoeeding 100 mRerWtv expected to OOf'lhoue for more than one hour, at or beyond the stle boundary OR Ana¥M of field SlX\\I'eY sa~

ll"'ddcate tl'ftrold COE of 500 mRem for ooe l'1otX of *nha'atJon at Of beyond the sne

-~

None None None None a HS4.1 I 1 I 2 I 3 I 4 I s I oeF I A t--K>STllE ACTION i6 OCCU"nng or r.n occurred wtthln the Plane PROTECTED AREA as reported brr' the Security Shift S~isor HS2ContrOIItoom EVKWIIIIO<'I HH81tonlnlllatiGan.:II'Uon1ConlrOI Clnnol8tEitabkhiG 0 HS2..1 I 1 I 2 I 3 I 4 I 5 I DEF I Cof'crol room evacuabon has been Initiated A ND Cortrol of the part carYlOt be establi~hed per C.4-C, Srkltdown Wside the Cortrol Room, wtthrn 10 mlnt.Aes HS3o.to*Condtlom.Eid~WNch~llll ~looflhlfmtrgM~Cy llio-*~lor W;wranl DKI*;olion of Slle Afn bow _.c.~

0 H$3.1 I 1 I 2 I 3 I 4 I 5 I DEF I Other condtllons e)( 1St......r.ch in the Judgrneot of the Emergency Director indiCate that ~ts are m process or have OCCtxred which 1rr.toNe actual or ~kely rna,or fl!uUes or part lurotom neede-d for prorecuon of the pWIIC Any release5 are rot expected to resut in exposure ~els whiCh exceed EPA Pro!ectlYe Action G..-dellne expo&U"e le11els beyond the Site

-~

None

~Al Any UMI'U.MHI!O ~*n* ofGneous Of Liquid ltidiCNCtlvWy 10 tt.

6'!10\\-ormenlltwf b ee.,. lOO TlmH lt. Ofhllt OoM Clk!lltion llll.....,liiLJmliiiOI'ISIIIIiMII:nw~

a RA1.1 I 1 I 2 I 3 I 4 I 5 I DEF I VAUD reading on 8fltl effluent: morttor that exceeds 200 time-s the aiarm setpoint eslabll$hed tov a currert radiOI!ICII'IItly cbcharge ~rmit for 1~ mirutes or longer 0

RA1.2 I 1 I 2 I 3 I

I 5 I DEF I VALID reading on anry ~the fOIOWIIlg radiatiOn morrtors that exoe-eds tne re~tng Shown for 15 mrues ()( tooger Montor

~uen!Monitor (ChAO( B)

Alert 146E7.. Cilsee' RB Ved Emuerl. Mo.-.tor 2.16E6 j.iCiJse.c (ChAorB)

~ce\\N'atet" 31.400cps Discharge canal Monrtor 93CXJOcps TBNINS 900 000 cpm

0 RA1.3 I 1 I 2 I 3 I 4 I 5 I DEF I Confirmed sample anal'{sts for gaseou& or liqUid release tndica1es ooocertraliOns or release rates With 11 retease ckxaooncl15rnm.resorlooger, in excess ~200umesODCM

40 limes OCICM calculated lirrll

- 48 tfnes OCCM calcWted Umt.

ltA2~1ohld*tod l'tMif>l'lau afW**Lt,...ltwi:HftoorW.

~:::In lht UncO\\'Wing ofi!Tadl"~ ~uti Oulsldt m. ~uctor 0

RA2.1 I 1 I 2 I 3 I

I 5 I DEF I A VALIOt~~larmor re*clng on ;~nycA me follOWing rad.anon rronitors Mon1tor A:~ ~ ~;~~=~~~

A*3 1027 RB W statrway RM-H-452A Reactor Buldlrg Vertllabon Exhaust Plerun MoMor 0'1 A RM-17-4528 Reactor Buildtr-g Vertllallon Exhaust Plet"'11 Monttor a. 8 AlarmtTnp 100.-RhY 26mRih<

26mRAY RM-17-453A Fuel Pool Radiation MOI'Itof Ch A 50 mRihr RM-17-4538Fue1PooiR~tallOnMontorCh8 50mRJhr a HA1.1 I 1 I 2 I 3 I 4 I 5 I oeF I Setsrnc evei'C GREATER THAN Operattrg BaSIS Earthquake (OBE) as indiCIIIed t,r Anru'lCialor OPERATIONAL BASIS EARTHOJAKE (6.C.13) reoe.ved a HA1.2 I 1 I 2 I 3 I 4 I 5 I DEF I Tornado Of t41 wiOct&GREATER THAN 100 mphwrthn plant PROTECTED AREA bOundary and r~t.Jttrg tn VISIBlE DAMAGE to any plam &ol ructure&lequtpment (Table H-1)or Cont101 Room lfldicat:JOO of degraded performance ot lh0$e systems 0

HA1.3 I 1 I 2 I 3 I 4 I 5 I DEF I Vehicle crast\\wtthtn plart PROTECTED AREA boundi!ry and reslJI:Ing 11 VISIBLE DAMAGE to ll"f planl strudtxesor eq~

mer~n (T&Oie H-1) or Control Room indication of degrndf'd performance of tllo&e syst('(T'$.

0 HA1.4 I 1 I 2 I 3 I 4 I 6 I DEF I TtXblne fatlure-generaled msSlles resU!tn any VIS IBLE DAMAGE to or ~netrat10n r:/a"f j:UI'C areas (Table H*l ).

a HA1.5 I 1 I 2 I 3 I 4 I 5 I DEF I Urloortrol edflOodlng in areas (Table H-1) of the ~nlthat results tn degaded safety system performaooe as inc:lcated 111 thecortrol room or that creates tnd.Jstrtal safety hazards (e g.

~c shock) tl'ltlt precludes IICOef.S I'JeCe5Sary to operate or mol"'lttr satett equtpment.

a HAu I 1 I 2 I 3 I 4 I 5 I DEF I Bitler of the foDowtng OCCU"eeCeS within plart PROTECTED AREA bour'ldary and resull:lf"Q In VISIB..E DAMAGE to piart

&otru::t...-ea oortamlflg ec,.Mpmert necessary for safe shtJ:down, or has cat.Md OO~Nge as ~need by Cortrol Room 11'ldlcat!on Of degraded performance cl those systems Rwer leve-IGREATERTHAN919fl el OR River ~LESS THAN 900 5 fl el HAl ~lfll f: or E.I:PLOSION A111c:!lng tlll 0p*.OM1ty of Plant Safety

~$1.n'o*"I<!Ui' IGIOE$1 ar.ti$1106 M:llni:W"$a'-stl!l d-0 HA2.1 I 1 I 2 I 3 I

I 6 I DEF I FIRE or EXPlOSION in any of lhefolowrng areas (Table H-1)

AND Affected system para meter todicallons show degraded performer.::e or pia Ill per&OI"'ne! report VISIBLE DAMAGE to permanent structures or equtpmei'C wtttun the speafied area ti!§:41~1r~~~i~-s~E\\r:.~*:

D HA3.1 I 1 I 2 I 3 I

I 5 I DEF I Report()( oetectiOO or tOKIC or &~1ate gases within or contiguous to a VITAL AREA (Table K-1) 111 concentratiOOS that rrey resi.Jt inanatm:lspt>ere IMMEDIATELY DANGEROUS TO LIFE AND HEALTH (IDLH) 0 HA3.2 I 1 I 2 I 3 I 4 I 5 I DEF I Report Of detection of~

in coocertrahon GREATER THAN the LONER FLAMMABILITY L1MIT Within Of oont~uous to a VITAL AREA (Table l-f.1)

HMiiOSTILI! AC110H ~~ liM C!Wt!f:.lt COHTitOLLI!OAfiiEA or AlftromeAna.ek lht***

t:J HA4.1 I 1 I 2 I 3 I

I 5 I DEF I A HOSTILE ACTON Is occurring or has occured within the CM'NER CONTRCX..LED AREA as reported 1:¥ the Security Shil't Supef\\11801 0

HA4.21 1 I 2 I 3 I. I 6 I DEFI A validated nottflcaton from NRC d an a.rltoer attack threat Wlthn 30 mf'KAes o1 the site 0

HA5.1 I 1 I 2 I 3 I 4 I 5 I DEF I Entry 1nto C 4-C, Shl.IOJwn WSide the Cortrol Room, lor controlroomevaouatl()t"t HASOiilii'Coodillon51!1dsrlngwtlkh lnllliJudliJIMfll of lilt fm*!if'lrK'I' Oi!-.cl or W*riii'IIOKIM;ollonoi..,A'-1 0 HA$.1 I 1 I 2 I 3 I 4 I 5 I DEf I Other COO()!On; exist whiCh in the jodgrnent cl the Emergef'ICY Director Indicate that everts &rem s::rooess or hilve occurred whch tnvolve actual or ltkely potenbal sl.tlstarii81 degractltion a the leve4 of safety or the plam My releases are expected to be ~mited to sma~ fractiOnS of the EPA Protecflve Action GI.IPde~ne expo-st.Xe ~Is None

~u' :n"!.~':!:X~:::,:~o.;,=~:.'o':':.~~!'J:;:e IIIII__, Umlt ~of to lillllnulft or LQf>Oef

J RU1.1 I 1 I 2 I 3 I 4 I 5 I DEF I VALID reading on a"' effluent monitor that exceeds two limes.

the alarm setpo!rt ~tabl1shed tJ( a CU'rent radtoactlYity discharge permit for 60 rrvni.Aes Of lorger 0

RU1.2 I t I 2 I 3 I

I 5 I DEF I VALID reading on af" of the followtng rad'ation monl:ors that e)(~ trle readng Shown rot 60 n-.l"'lJJes or lOnger Monitor

~uentMonitor (ChAorB)

UE 7 3E~j.iCilsec RB Vert emuent Monrt:or 2.16E4 ~ewec (ChAorB) l&l.l<l S~Water 314cps Olscharge canal MOI'lll.or 930 cps T8'M5 37 752 cpm 0

RU1.3 I 1 I 2 I 3 I 4 I 5 I OEF I Corlirmed sal1l)e analysis ror gaseous or tlqud release indl¢ates ooooenlra!Jons or tl!!lease ra:es with a release c)Jration of 60 mirutes or Ionge!', in excess~ two limes ax;M

"~

J RU21 I 1 I 2 I 3 I 4 I 5 I DEF I VAUDif'dca tionofoocorfr~ed w~e r tevel lowenngnthe reactor refue~ng caYrty ~nt l uel pool, or fuel transfer canal wtth a11 ~m~Ooated luelassembll86 remall'ing OO'It'ered by watl!f asiOdicatedf:>taNydtl'le fOIIowtng Unexpected Spenl Fuel Poollo.<< water level a~llTI Vi'sual observatKlfl of an uncontrolled water level drop below a luel pool sklrrmer Stxge tank.nlel Observation of water IPakage 111:0 the ciywell or the reactor building rrom ppwg penetrations su-roundii'IQ the clyweU AND A"'! UNPLANNED VALID Area Radlalloo Monrtor ~t!iclt"'Q rise astndicatedt::y anry~the followlng A-1 10'27 RBNE lo.<<

A*21C!27RBN Htgh A-3 1027 RBWStairway RM-17-453A orB fue4 Pool Monitoring System

':J RU2.2 I 1

[

2 I 3 I 4 I 5 loeFI A"/ UNPLANNED VALID Area Radtatton Mon101' reatdlrg rtses ty afaaor ot 1000r;,~er rori'Mt* ~ets.

"Normal ~15 e 11n be oon5'dered n m. htghnt ll!'~ inn. past twenty.four tlo.ort "~eb:ll"'iJflteunerd pec;okvllfU<<!

HU1 N;J!ul"*.-rn:r Dtl.lruolllvt PNnom.,..1 A**lino lht Pl..t I'~OTECTEOAitEA

.J HU1.1 I 1 I 2 I 3 I 4 I 5 I DEF I Earthquake lel\\ 111 plillnt as 1ndcated [¥ Coosei15U5 of CorWrol Room operators oo duly AND Anll.JOC1a'tor EARTHQUAKE {6-C.oBI received

J HU1.2 I 1

[

2 I 3 I 4 I 5 I OEF I Report by p.;tnl persomel of tornado Of hig\\ WI~ GREA T£R THAN 100 mph wtthtn p art PROTECTED AREA boundary

.J HU1.3 I 1 I 2 I 3 I 4 I 5 I OEF I Vehde crash IIlio pant stru::!Ul'es or systems wlthn plant PROTECTED AREA bourdary 0

HU1.4 I 1 I 2 I 3 I 4 I 5 I OEF I Report by ~rt pers.omel of t~n una r11Ctpated EXPLOSION wtthm plant PROTECTED AREA boundary resultnJ 1n VISIBlE DAMAGE topermanentstru::tt.Xe or equt~

0 HU1.5 I 1 I 2 I 3 I 4 I 5 I DEF I Report or tllblne Ia fllxe restAI:Irg 1n castng pe~tratiOf'l or darMge to h.I'Oine Of generator seals a HU1.6 I 1 I 2 I 3 I 4 I 5 I oEF I Unoottro~ fl()()(jtflj in areas (Table H-~) of the p!<lm th<ll has the potertlat to affect safety related eq~.~pmert needed for the Ct.. nert o~rn tJOQ mode

J HU1.7 I 1 I 2 I 3 I 4 I 5 I OEF I A"'f Of ltle folk:Jwlng high rillet leve4 or 101¥' rwer level OOOJn"erw::e' 11lfecc1ng the plli'C PROTECTED AREA Rwer level GREATER THAN 918 fl et RM!f level LESS THAN 902.4 fl el HUl Filtf 'Mihln l'ftOTECT'EO A~ [A Bowldacy Moe f:xtmgo.HIMd Wlmln 1S M....-uot 0.1*ctlon 0

HU2.1 I 1 I 2 I 3 I 4 I 5 I OEF I F"IRE in buildirysor areas conti!J,IOus to II"/ Table H-1 area rot exl!f19ut!ohed wlltln 15 mtnutes of cor&rol room nottficatOO or vertficat1on of e control room alarm HUllt.tust of TO>elc, A$phy* l..... (K fl.>mm.... O..MS Otemld Dmm...tillto l'lormiiiiOp"adonofltltPI-a HU3.1 I t I 2 I 3 I 4 I s I DEF I Report or oete(6on of lo}IIC, a~taN: or flammable gases that has or coulderter the Site area boundary m amourts thllt can affect ~MAL PLANT Cf>ERATIONS.

a HU3.2 I 1 I 2 I 3 I 4 I 5 loeFI Report by locll~ County or Stale Offaals for evacuaton or shetlering r:l srte persol'Ylel b8&e<l on an otrSlte evert Ht.W C~nMd SfCUitiTY CONOI '!IOH or Th'nl Whim lndcMK ~

f>Me<'IIIM Dl(lra.:IMIOI'I 11'1 lnl UVII ot $al~y OIIM PUnl.

!J HU4.1 I 1 ! 2 I 3 I 4 I 5 I OEF I A SE~ITY CONOfTIONthatd:>esNOT Jwo._.e a HOSTILE ACfiON as reported by the SectSity Shift Supervisor o HU4.2 I 1 I 2 I 3 I 4 I 5 loeFI A cre<lble MNGP sectxlty ltlreat notdlcahon 0 HU4.3 I 1 I 2 I 3 I 4 I 5 I DEFI A validated not"Mion from NRC pr<Mdlng informaoon of an aJrCfal'tthreat None HUS om. Coocttlons l!ld<<~g IMllchln lilt Judgmlnt ol ltM f:merg.n<::y Dlrtclor W-illf'll()t<;f;or.,ionohUI!

0 HU5.1 I 1 I 2 I 3 I 4 I 5 I OEF I Other ooncMons e): 1St wtlch 111thejUdgmert of the Emergency Director ti'Kicatethal events are rn process or 1'\\!rve oocu-re<l which indicate a potenllal degadaloo of the level of safety c1 the plar1 No releases a raao.cttve material req~.~nng otfSite response or moNtonrQ are exJ:eded IX'lless fl.rther degrad8t!On of &afety systems occlX6

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 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 I

I

~llllili~~~lll~~j~~ll~ GENERAL EMERGENCY I SITE AREA EMERGENCY I ALERT I

UNUSUAL EVENT I

Cold SOl

..... ~ -

None None CQ1 Loe;* of rtl"tt l.,...,.ory *~"'-'0........,....

~~~ Ch...,.....,...,.....,,.wtlne. *w

J CG1.1 I I

I I 4 I 5 I I

0 CS1 1 I I 4 I I

1 Loss of RPV I!'Nerii:OfY as 1ndtcated by uoe)(platne<:l nse lfl drywel floor or e~pner<< dra111 su~ teve!_

A ND 2 RPV level a LESSTHAN*1261n. (TAF)forGREATER THAN30 mnties_

OR

b. camot be morvtoredWII:h lndltatlOI'ldc:ore t.nCOVel)'for G REATER THANJO ITIIIlliesasevi~ncedby a r?{dthe 0 fOllOWing

Errabc SoU"ce Rarge Morllor *ndicalion Ref\\leling Roorradiabon le...etsGREATER THA.N3 R.tY A ND

3. lnd~ea tlOI'lciCONTAINMENT challenged aslndicateclby anv of the fOIIoYo-lrg G REATER THAN OR EOOAL TO 6% hydrc:gen and GREATER THAN OR EQUAL TO 5% oxygeo in prmary cortainmert Drywell p1essu-e above 56 p&ig Secondary oonta~nmert not establiShed V"..th Secondary Cortammerc n estaDirSheO a RN iwentory as lndicaed by RPV le~ LESS THAN -53 in O R

b. RPv level cannot be monnored fotGREATER THANJO mlnute$wltl1t10$SofR.PVlrroerttoryasrdC8\\ect~eiUler unex~a.ned level nse 1n dryWell nOOI' or eqUipment dtl!lr'ISUI'Tf'S Erra:~e Source Range Momor lndiclltK>n CS1.2 I I

I I 4 I I

I Witt\\ Seoondarycor(anmerc e~OI!She<l

a. RP>/I'IventoryasindiCiteel by RP\\flevej LESS THAN *126 in.

(TAF)

OR b

Rp.,!level ~n !'IOfbftmonilored forGREATERTHAN30 minutesw.ttla loss of RP\\Iinventofy asincicatedbojeilher

LJnexplalfled level nse JO drywell ftOOf or eQUipment dra11 &Ufll'$

EtraiiC Source Range Morwtor lndicatiOI'l CU Lon fti AJIV........,.~ C.. O.., ItNI--..~

lor..._..,_.,....,

Two or more Reactor a.. nlding areas exceed Max Safe Ra<iat1011Leve!s (C 5*1300 Table X).

o cs2.1 [I :::;::r;::::J:::::::.r::;~l ;sgi;::::J W th Secondary Cortaueeri ll2t establl$hed None None None None None Table H*1 EAL Classification A reM Reactor Bldg HPCI Bldg T""""Bldg Conltot & Adm~ntst rat.:>n Bldg Otese! Generator BI"J D.esel Fuel 011 Tranwer House EFTBklg Intake Strudure 5ecunty Bu~ding I

Security Diesel Generator Blllding1

~., n.~tw.~~~c~~~~r~ *'-on'f _,~"dwto..,

clas~ng per HU2 1, HA3 1 lol'ld HA3 2 a RPI/iwootory as indicated by RPV level LESS THAN -53 in.

O R b RPV level caMOI be monitored w+1h lrdcatoo of core

~as eY1~

by &Bf cJ the fOU(lWing

ErratiC Source Range Morlltorlndication

Re!u<elllgfiOorrtdia(lonlevets GREATERTHAN 3Rihr o cs2.2 !

I I

I Is !

I W th Secondary eoru~fll establ1sned a RPV l'lven!aty as indiCated by RPV he~ LESS THAN -125 in.

(TAF)

O R b RPv' ~I camo1 be rralltored w!th lrdcauon of core IX'rOOVef'y M evtoeooed by il"'t d the fOIIOWirQ

- ErratiC Soul'ce Range Monrtor.n<JK:atlon.

- R~elflg FloorntdWI!:ion leY'EIIs GREATER THAN 3 Rlhr.

None None None None None TattM C.1 Ons.. CommunlelldoM SysltmS Corrmerc~al telepl"ones Area Plarc telephor're-6 Portablerados Plarc page system Tallie C.2 Offsitll Communic:IIUOM S ystenw; Corrrnerc*a l telephones FTS Phone Systen'l Radio Rece*ver/frammtler Alternate ShUtdown P~nel cable Spreading Room Tl.lbne BOid1ng (exell..ldli'Q turbine operatlllQ deck)

General Reactor Butarg Area& (excluding noiTlli!lly locked I"'V'Jrl!lld areas)

Modes: [I]

Powet Opefatlon

[I]

Startup

[I]

Hot Shutdo'Ml ITJ Cold Sh utdo'Ml CAlL-of All 0..... '"- rd LOM of U 0M61* AC ~- 10 0

CA3.1 I I.. I 5 I OEF I Loss ol ofl--s~te po.Ner 10 Essential bu&ses 15 and 16 A ND FU *.te d 11 EIT'!efgeocy Dleset Geoerator alld 12 Emetgeocy Diesel Generator to supply power 10 Essential tusses15 and 16 AN D Fa1hxe to restore power to at least one Essertaal buS, 15or 16, wrthm 15 mnu:e-s from the time of loss of txllh offslte and onsrte AC power 0

CA1 1 I 4 I I

LOB& of RCS ll'l'lleriory as Indicated 0( RPV level LESS THAN

-.Q711"1 Cl CA1.2 I I.. I I

LOIS ol RCS ir'N-eniOfY as IO(icated bj li"Mlltpl~ined leveol rise ~

drywetl floor or eq.. upmert draun sumps A ND RCS level camct be monitored for GREATER THAN 15 0

CA2.1

.~~ :;::r::::::J::::r:;:::rl ~sg1;:J Loss of RPV ~ventory as indicated by R PV le\\tellESS THAN -47/n 0

CA2 2 I I 5 I I

LOM Of RPv IIWertory as ndcated Dy unexpta1ned ~el nse in drywell floor or equ.pmen! d(a11"1&1.XnP6 AND RPV levelcamot be rrontored for GREATER TH AN 15 mn..tes CM iniMIIylo M......... In Coldlhl.l:*'-'watlln.. -..,.... _..

a CA4.1 I I

I 5 I Wlh Secondary Conta irmert and RCS 1rtegr11:v Jl5J!

eW!bk&hed an UNPLANNEDfNert r~s 1n RCS temperatU"e exceedll'lg 212 degrees F "Ncxe " " " RCS ~t r~.ill IJ~t.m *~ '" QPO!r.lbQn wCh*n lh~..,.,..

hme 111nd RCS~re l'lbe-W>g redvced then th*EAL.. not

<Jpf*Cde 0

CA4.2j j

.t j

s j

'Mih Secondary Conta irmert estat:f1shed II.IJd RCS ntegrty ogt est<Jbhshed or RCS 111Vefltoty redu::ed an UNPLANNED evert result& 1n RCS ttf'l'l)erat~..re e)foeecl*rQ 212 deg-ees F 101 GREATER THAN 20 l'l'mJie&'

0 CA4.3 [I :::::~;:::J=:IO*;:J:

I J*DI=]

An UNP..ANNEO event results 111 RCS temperature exceeding 212 clegees F for GREATER TI-l AN 60 m1rutes' or rnults in an RCS Ol'es.stte IOOI'ease of GREATER THAN 10 PS10 None None None None Monitor By survey By survey B*2 TG FRONT STANDARD (951')

B-3CONDENSATE OEM IN OPERATING 8-4911 iURBBL.OO MVPROOM B-5 FEECNVATER PUMP AREA ~11 ')

A*1 1027 RX El.._DG LON RANGE A-31027RX B...CGWSTAIRWAY A-5 1001 RX B..CG FUEL P<Xl... ROOM A*7985 RX B...OO CHEM SAMPLE AREA A.S962RX aDG tmOlJTSIC ROCU ROOM A*9 962 RX 8l..CG EAST A-10 EAST CRD MODULE AREA A-11 WESTCROMOOULE AREA A-12935RX. EU)G NETIPDRIVE AREA A*14 HPa TURBINE AREA A-1 5 896 RX El.OG ORA IN TANK ROOM A-16 RCIC ECIUIPMENT AREA A*11 EAST CORE SPRAY & RHR AREA A*18 'NEST ~E SPRAY & RHR AREA CU) L-of._,, OW.*...,_ IO r............. for Glti!ATUI TttAJI I SIIIrUet..

a cu31 I I 4 I 5 I I

lou of oft-lite poweriO Essenbal busses 15and 161orGREATER T~15 mnutes A ND At least one Enential bua, 15or 16, is powered b,< its emergency desel gtner~tor CU7 UMI"LAJiliii!O Lou M II~

0C,_.far OIII!Al!:II 'IMAJI U a c u1.1 1 1 4 1 s I I

UNPLANNED loU o1 vrt:el 0C perwtr to~

125 VDC tlu~S based on LESS THAN 111 VOC bus YOitaQ8 ~liOns.

A ND Fedtxe to restore power to at least one requred 125 VDC bus within 15 mirutes from the tlf'ne o( loss 0

CU2.1 C.l :;~::::J::I=I I J*DI:::;::~

UNPLANNEO RCS teveltowerlf"'Q below the RPV flange fOr GREATER Tl-IAN OR EQUAL TO 15 rni'I\\Aes Q

CU2.2 [I =r:::J=I=II J*DI=]

l oss of RPV Inventory as Jnchcaled by unexplained level nse 11 dry.¥ell noor or equpment ctam sumps AND RPVIevelca nnolte momored CtM ~dD LOM ofO.C.,-......_..... C......,'flllhln......:l

'""'""tbtllr"i 0

CU4.1 I I 4 I 5 I An UNPLANNED evert res!AS 1n RCS temperature exceed..-.g 212degees F a cu* 2 I I 4 I 5 I I

Loss a aN RCS temperat~Xe a no RPV levellndlcaoon for GREATER THAN 15 mrues cw=:.:o L-MNA Onsh or~~

Q CU81 I I

I 4 I 5 I Loss of all Table C 1 onste cotrm.J!11Catlons capability affectng the ablltty to pefform r0o..t1ne opefatloos a c ue.2 ~

~ :;t:;::;:J.;::Ig*;r:l ~*gi::::;J.

los$ of all Table C-2 otfsl!e corrtl"'UfCattons capability None CvtiiUL..._.

0 CU1.1 I 4

I U~ifled or pressure bo\\n:Salry k!-akage GREATER THAN 10gpn 0

CU1.2 I I 4 I Identified H!akage GREATER THAN 25 gpm cue..,..,_.ent~..,

0 CU8 1 I I 4 I 5 I I

An UNPlANNED extended positiVe peood obtiefved on nuclearimtn.xnertation i

6 I Modes 4, 5, DEF ~

MONTICELLO NUCLEAR GENERATING PLAN T 5790-101.()2

~ EMERGENCY ACTION LEVEL MATRIX Revision 10 Page 2ol2

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 110 of 120 FIGURES 13.0 Figure 13.1 MONTICELLO PLANT EMERGENCY ORGANIZATION OSC COORDINATOR ELECTRICAL &

MECHANICAL GROUP I & C GROUP OPERATIONS GROUP TECHNICAL ADVISOR MAINTENANCE GROUP LEADER OPERATIONS GROUP LEADER SECURITY GROUP HEALTH PHYSICS SUPPORT GROUP ENGINEERING GROUP SECURITY GROUP LEADER RADIOLOGICAL EMERGENCY COORDINATOR SUPPORT GROUP LEADER ENGINEERING GROUP LEADER SHIFT EMERGENCY COMMUNICATOR EMERGENCY DIRECTOR

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 111 of 120 Figure 13.2 INTERFACE BETWEEN FUNCTIONAL AREAS OF EMERGENCY ACTIVITY Lines after EOF is staffed Initial lines Fire Department County Sheriffs Ambulance Service CentraCare Health Monticello LOCAL GOVERNMENT FEDERAL AGENCIES STATE AGENCIES SHERBURNE COUNTY EOC WRIGHT COUNTY EOC STATE EOC LOCAL SUPPORT SERVICES EMERGENCY DIRECTOR (TSC)

OSC NRC EMERGENCY MANAGER (EOF)

NSPM EXECUTIVE MANAGEMENT (JIC)

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 112 of 120 Figure 13.3 INTERFACE BETWEEN FUNCTIONAL AREAS OF EMERGENCY ACTIVITY DURING HOSTILE ACTION BASED EVENTS Security Liaison Federal Agencies State Agencies Sherburne County EOC Utility Liaison Minnesota State EOC Incident Commander (ICP)

Emergency Manager (EOF)

NRC Federal Agencies Local Government MN State Police County Sheriff Fire Departments Ambulance Services Law Enforcement CentraCare Health Monticello Monticello ICP Liasons NSPM Executive Management Joint Information Center Wright County EOC Monticello Control Room Direct Interface

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 113 of 120 Figure 13.4 HEALTH PHYSICS GROUP ORGANIZATION Command chain for TSC and EOF Continuous interface between EOF & TSC EOF CR CHEM TECH OFF-SITE MONITORING TEAMS F/T COMM OFF-SITE MONITORING TEAMS RP GROUP CHEM GROUP F/T COMM MONITORING SECTION LEADER RPC CHEM COORD Dose Projection Specialist Dose Projection Specialist CHEMISTRY SECTION LEADER RADIATION PROTECTION SUPPORT SUPERVISOR RADIOLOGICAL EMERGENCY COORDINATOR EMERGENCY MANAGER EMERGENCY DIRECTOR

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 114 of 120 Figure 13.5 PLAN VIEW OF TECHNICAL SUPPORT CENTER, BACK-UP OPERATIONAL SUPPORT CENTER I

....... f.~-~.: *.~-~--;._,*:*.;*:.,;:_

~:

-~-

~-**

ALTERNATE FIRE BRIGADE ROOM NRC ENGINEERING SUPPORT HP ROOM COMP RM

[ij]

\\:.:

E

~~~~{__~*

)~

......,.*****~*****.*.

~~-.-

STORAGE

U BACK UP osc TSC ADMIN ROOM B

B B

B ILJ lil...ENfAST

\\

TRANC I

EN~~?~

L.J I

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 115 of 120 Figure 13.6 PLAN VIEW OF THE EMERGENCY OPERATIONS FACILITY I

TRAINING ROOM 10 EXAM ROOM TRAINING ROOM 9 TRAINING ROOM 8 MECH/ELEC ROOM

\\

~

Xll TRAINING ROOM 11 I

V1 EOF COMMAND CENTER TRAINING ROOM 12 7

COMMUNICATIONS ROOM DOSE ASSESSMENT FAX ROOM

\\

VI STORAGE MOCK-UP ROOM

\\

N" I

RECEIVING COUNT ROOM OFFICE TRAINING ROOM 14 OFFICE SIM SUPV

/'\\

~

II II v

MENS RESTROOM J WOMENS RESTROOM IL

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 116 of 120 Figure 13.7 DIRECT DEDICATED TELEPHONES (HOT LINES)

MONTICELLO TELEPHONE NETWORK (Primary Communications Link)

Number Name Stations 1

Emergency Notification System (ENS) 5 station FTS line between the Control 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.

CONTROL ROOM NRC OPERATION CENTER TSC EOF BACK-UP EOF NRC OPERATION CENTER STATE EOF NRC OPERATION CENTER 1

14 1

7 12 11 2

3 9

8 13a 4

12a 11a 10a 7a 1a NRC OPERATION CENTER 5

6

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 117 of 120 Figure 13.7 DIRECT DEDICATED TELEPHONES (HOT LINES) (CONTD) 6 EOF - Back-Up EOF 2 (Tech Support) 2 station line between technical 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 (Tech Support) 2 station line between the Technical Support groups at the EOF and the TSC.

10a Management Counterpart Link (DSO/STL) 2 Station FTS line between EOF and NRC Operations Center 11 Protective Measures Counterpart 2 station FTS line between NRC protective measures personnel at the site and NRC Operations Center.

11a Protective Measures Counterpart Link (PMCL) 2 station FTS line at the EOF between NRC protective measures personnel at the EOF and NRC Operations Center.

12 Reactor Safety Counterpart Link (RSCL) 2 station FTS line between NRC reactor safety personnel at the site and NRC Operations Center.

12a Reactor Safety Counterpart Link (RSCL) 2 station FTS line at the EOF between NRC 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 System (ERDS)

ERDS VPN channel link over which raw 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months a day with no limit to its use.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 118 of 120 Figure 13.8 PLAN VIEW OF OPERATIONAL SUPPORT CENTER PAB 1st Floor OSC Assembly Areas I

I n

f-J I

~

w

"~

o o UJ 2

8

~~

(')

z er:

0~

0 I

I L.

z

(]_{]_

~

we:;

w

_jo

~w

~.

v

_J Maintenance and V Operations craft assembly areas.

11 I

~

LL 7 G

0

~

r-2 0

D 0

cr:

I u

~

z w

J 0

_j J

~~

z 0 u

/

I n

~

ID l

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 119 of 120 Figure 13.8 PLAN VIEW OF OPERATIONAL SUPPORT CENTER (CONTD)

PAB 2nd Floor OSC Command Center

[

L q]JJD PAB-2

~

0

~ J

()_

I w c; 0 w u

0 0::

()_

/

G..:

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 48 Page 120 of 120 Figure 13.9

SUMMARY

OF SIGNIFICANT CHANGES Section Change and Reason for Change Table 11 Revise Process Radiation Monitor Indicator Range for Hard Pipe Vent from 10 104 to 10 - 107 mrem/hr for EC 26083.

L-MT-17-029, Changes to the Monticello Nuclear Generating Plant (MNGP) Emergency Plan

Contents

Text

Title:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu