ML14198A398

Revised Emergency Plan and Emergency Plan Implementing Procedures (Epips)

ML14198A398
Person / Time
Site:	Monticello
Issue date:	07/17/2014
From:	Fili K Northern States Power Co, Xcel Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
FOIA/PA-2015-0025
Download: ML14198A398 (165)

Text

Xcel Energy@

July 17, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 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-14-059 10 CFR 50 Appendix E.V 10 CFR 50.54(q)(5) 10 CFR 72.44(f)

Revised Emergency Plan and Emergency Plan Implementing Procedures (EPIPs)

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 revisions to the Monticello Nuclear Generating Plant Emergency Plan and EPIPs as Enclosure 1. The revisions are provided as Enclosure 2. The Emergency Plan and EPIP revisions have been reviewed and do not result in a reduction in the effectiveness of the Emergency Plan.

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

o-r&r*

Kare D. Fili Site Vice President Monticello Nuclear Generating Plant Northern States Power Company-Minnesota Enclosures (2) cc:

Emergency Response Coordinator, Region Ill, USNRC MNGP Resident Inspector (w/o Enclosures)

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

Operations Branch Chief, Operator Licensing and Emergency Preparedness, Region Ill, USNRC Director, Division of Spent Fuel Storage and Transportation, Office of Nuclear Material Safety and Safeguards

ENCLOSURE 1 Summary of Changes - 10 CFR 50.54(q)(5) 4 pages follow

Page 1 of 4

50.54(q) #: MT-2014-168 Description (EXECUTIVE

SUMMARY

):

Conforming change providing information regarding offsite resources provided per letters of agreement. This is evaluated as Change 1 under Program Requirements.

• Section 5.6 is added to show offsite resources that are available to assist under Letters of Agreement with the Monticello Nuclear Generating Plant (MNGP).

Chemistry Technician Training Requirement. This is evaluated as Change 2 under Program Requirements.

• Remove the requirement for Chemistry Technicians to be trained as a Shift Emergency Communicator in Section 5.1.2.4 and Section 5.3.1.3.

Change to Periodic Testing references for the Public Alert Notification System (PANS).

This is evaluated as Change 3 under Program Requirements.

• Remove the reference to Surveillance 1409 in Section 8.1.2.6.4.

Change the range of the Feedwater Temperature indication from 0 to 400 degrees Fahrenheit to 32 to 430 degrees Fahrenheit. This is evaluated as Change 4 under Program Requirements.

• Change the range of the Feedwater Temperature Indicator to reflect conditions after the Extended Power Uprate.

Change (#) Change 1

==

Description:==

Conforming change providing information regarding offsite resources provided per letters of agreement Section 5.6 is added to show offsite resources that are available to assist under Letters of Agreement with the MNGP.

Doc ID or (Procedure Number)/ Revision Number: Emergency Plan/43 Document

Title:

MNGP Emergency Plan PCR Number: 01433207 Editorial Basis (applies to Emergency Plan changes only)

Licensing/Basis Affected This is an addition to the Emergency Plan (E-Plan) and provides a description of non-government, non-local offsite agencies that will provide assistance to the MNGP in the event of a declared emergency as described in Interim Staff Guidance (NSIR/DPR-ISG-01) and EP Frequently Asked Questions (FAQ) 2013-003 that is based on changes to Emergency Planning (EP) regulations in 10 CFR 50.47 and Appendix E that were published in the Federal Register on November 23, 2011.

Evaluation Determination:

Regulatory Compliance Basis The addition of resources within the plan is a conforming change as described in Interim Staff Guidance (NSIR/DPR-ISG-01) and EP FAQ 2013-003 that is based on changes to EP regulations in 10 CFR 50.47 and Appendix E that were published in the Federal Register on November 23, 2011.

Page 2 of 4

Emergency Plan Effectiveness Basis Information was added to provide guidance regarding resources provided by Offsite Response Organizations. These are considered conforming changes. The requirements of the E-Plan continue to be met. The addition of this information is not considered a reduction in effectiveness of the E-Plan.

Change (#) Change 2

==

Description:==

Chemistry Technician Training Requirement Remove the requirement for Chemistry Technicians to be trained as a Shift Emergency Communicator in Section 5.1.2.4 and Section 5.3.1.3.

Doc ID or (Procedure Number)/ Revision Number: E-Plan/43 Document

Title:

MNGP Emergency Plan PCR Number: 01433207 Editorial Basis (applies to E-Plan changes only)

Licensing/Basis Affected This change continues to comply with the minimum staffing requirements of the MNGP E-Plan and A.2-002, Monticello On-Shift Staffing Analysis. The Technical Specifications and Updated Safety Analysis Report (USAR) were unaffected.

Evaluation Determination:

Regulatory Compliance Basis This change continues to comply with the minimum staffing requirements of the MNGP E-Plan and A.2-002, Monticello On-Shift Staffing Analysis. From the Interim Staff Guidance, NSIR/DPR-ISG-01,Section IV.C:

"NEI developed the document NEI 10-05, "Assessment of On-Shift Emergency Response Organization Staffing and Capabilities," Revision 0, dated June 2011 (ADAMS Accession No. ML111751698), to establish a standard methodology for a licensee to perform the required staffing analysis. The NRC has reviewed NEI 10-05 and found it to be an acceptable methodology for this purpose."

"Any reduction in effectiveness can only be associated with a change to the emergency plan that modifies current on-shift staffing levels or task assignments. The licensee would need to consider this licensing basis, per the guidance in Regulatory Guide (RG) 1.219, in performing a change evaluation if modifying current staffing levels or task assignments based upon the results of the staffing analysis."

From RG 1.219, Section C1.1.b "...changes that reduce the number of personnel available to perform emergency response tasks or that lengthen the time it takes to staff and activate Emergency Response Facilities (ERFs) could impact the NRC's reasonable assurance determination and would require prior NRC staff approval."

This change continues to comply with the minimum staffing requirements of the MNGP E-Plan and A.2-002 Monticello On-Shift Staffing Analysis. The change does not modify the required on-shift staffing levels, task assignments or reduce the required number of personnel available to perform the communicator function.

The Technical Specifications and USAR were unaffected.

Page 3 of 4

Emergency Plan Effectiveness Basis The Shift Emergency Communications (SEC) training requirements are removed from the Chemistry Technician and are retained by Security and the Radiation Protection Technician.

Without the Chemistry Technician there are currently 49 individuals qualified as the SEC and only two are required on each shift. A typical shift complement has three to six individuals qualified as SEC. The shift staffing processes support assignment of the SEC position for all shifts as a non-collateral duty. The requirements of the E-Plan are maintained and there is no reduction in effectiveness.

Change (#) Change 3

==

Description:==

Change to Periodic Testing references for the Public Alert Notification System (PANS).

Remove the reference to Surveillance Test Procedure 1409 in Section 8.1.2.6.4.

Doc ID or (Procedure Number)/ Revision Number: E-Plan/43 Document

Title:

MNGP Emergency Plan PCR Number: 01433207 Editorial Basis (applies to E-Plan changes only)

Licensing/Basis Affected By combining Surveillance Test Procedure (STP) 1359 and STP 1409 the PANS testing requirements contained in the MNGP E-Plan are unaffected and do not change. Testing requirements found in the MNGP Alert and Notification System (ANS) Design Report are based on requirements of Standard Guide for the Evaluation of Alert and Notification Systems for Nuclear Plants, Federal Emergency Management Agency (FEMA) REP-10 and have not changed. No PANS equipment or processes were modified by combining the two procedures.

No modifications, removals or additions occurred by combining the procedures. No testing periods were affected. The Technical Specifications and USAR were unaffected.

Evaluation Determination:

Regulatory Compliance Basis The incorporation of STP 1409 into STP 1359 and the subsequent removal of the reference to STP 1409 from the E-Plan continues to comply with the requirements of 10 CFR 50.47(b)(8) and 10CFR50 Appendix E.IV.G. No PANS equipment or processes were modified by combining the two procedures. No modifications, removals or additions occurred by combining the procedures.

No testing periods were affected. Compliance with the requirements found in Final Design Report for the ANS for the MNGP is maintained.

Emergency Plan Effectiveness Basis The effectiveness of the MNGP E-Plan is maintained by incorporating all of the requirements from STP 1409 and placing them into STP 1359.

Change (#) Change 4

==

Description:==

Change the range of the Feedwater Temperature indication from 0 to 400 degrees Fahrenheit to 32 to 430 degrees Fahrenheit.

Change the range of the Feedwater Temperature Indicator to reflect conditions after the Extended Power Uprate.

Page 4 of 4

Doc ID or (Procedure Number)/ Revision Number: E-Plan/43 Document

Title:

MNGP Emergency Plan PCR Number: 01433207 Editorial Basis (applies to E-Plan changes only)

Licensing/Basis Affected The MNGP E-Plan is the licensing basis. The requirements in the E-Plan are based on information from NUREG-0654/FEMA-REP-1 Rev. 1, Section H.5.c.

Evaluation Determination:

Regulatory Compliance Basis This change reflects a change in Feedwater System operating parameters due to the Extended Power Uprate (EPU). All of the requirements of the E-Plan are maintained.

Emergency Plan Effectiveness Basis The requirements of the E-Plan are maintained and there is no reduction in effectiveness.

ENCLOSURE 2 Revised Emergency Plan and Emergency Plan Implementing Procedures E-Plan, Revision 43 (119 Pages)

A.2-410 - Out-Of-Plant Surveys, Revision 24 (32 Pages)

A.2-601 - Re-Entry, Revision 5 (7 Pages) 158 pages follow

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 1 of 119 M/eak Approval:

INFORMATION USE x Procedure should be available, but NOT necessarily at the work location.

x Procedure may be performed from memory.

x User remains responsible for procedure adherence.

PCR 01433207

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 2 of 119 M/eak 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............................................................ 57 8.0 MAINTAINING EMERGENCY PREPAREDNESS........................................................ 86 9.0 RECOVERY.................................................................................................................. 90 10.0 APPENDIX A................................................................................................................ 92 11.0 APPENDIX B................................................................................................................ 96 12.0 ANNEX A.................................................................................................................... 104 13.0 FIGURES.................................................................................................................... 109 Figure 13.1 MONTICELLO PLANT EMERGENCY ORGANIZATION............................. 109 Figure 13.2 INTERFACE BETWEEN FUNCTIONAL AREAS OF EMERGENCY ACTIVITY..................................................................................................... 110 Figure 13.3 INTERFACE BETWEEN FUNCTIONAL AREAS OF EMERGENCY ACTIVITY DURING HOSTILE ACTION BASED EVENTS........................... 111 Figure 13.4 HEALTH PHYSICS GROUP ORGANIZATION............................................ 112 Figure 13.5 PLAN VIEW OF TECHNICAL SUPPORT CENTER, BACK-UP OPERATIONAL SUPPORT CENTER.......................................................... 113 Figure 13.6 PLAN VIEW OF THE EMERGENCY OPERATIONS FACILITY................... 114 Figure 13.7 DIRECT DEDICATED TELEPHONES (HOT LINES)................................... 115 Figure 13.8 PLAN VIEW OF OPERATIONAL SUPPORT CENTER................................ 117 Figure 13.9

SUMMARY

OF SIGNIFICANT CHANGES................................................... 119

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 3 of 119 M/eak 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:

x 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).

x 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 43 Page 4 of 119 M/eak 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 43 Page 5 of 119 M/eak 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 43 Page 6 of 119 M/eak 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 43 Page 7 of 119 M/eak 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.

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

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 8 of 119 M/eak 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 43 Page 9 of 119 M/eak 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:

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

i Performance Assessment i Business Support (including Document Control, Administrative Support, Emergency Preparedness, Accounting/Finance) i Training i Nuclear Security i Nuclear Oversight i Information Technology i Supply Chain i Regulatory Affairs/Licensing i Engineering (including Plant and Systems, Design, and Programs) i Human Resources i 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 43 Page 10 of 119 M/eak 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. One Radiation Protection Technician is also trained for Shift Emergency Communication responsibilities.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 11 of 119 M/eak 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 from other departments 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 43 Page 12 of 119 M/eak 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 43 Page 13 of 119 M/eak The Emergency Director is responsible for overall emergency direction and control until relieved of that responsibility by the Emergency Manager at the EOF. Initially, the Shift Manager assumes the role of Emergency Director until relieved by a designated Emergency Director. The Emergency Director has the authority and responsibility to unilaterally initiate emergency response actions including making off-site protective action recommendations to authorities responsible for implementing off-site emergency measures.

Functional responsibilities of the Emergency Director include:

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

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

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

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

Approval of emergency radiation exposures in excess of normal limits.

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

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

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EMERGENCY PLAN Revision 43 Page 14 of 119 M/eak 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 staff.

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.

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EMERGENCY PLAN Revision 43 Page 15 of 119 M/eak 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).

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EMERGENCY PLAN Revision 43 Page 16 of 119 M/eak 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.

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EMERGENCY PLAN Revision 43 Page 17 of 119 M/eak 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.

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EMERGENCY PLAN Revision 43 Page 18 of 119 M/eak 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.

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EMERGENCY PLAN Revision 43 Page 19 of 119 M/eak 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

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EMERGENCY PLAN Revision 43 Page 20 of 119 M/eak 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.

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EMERGENCY PLAN Revision 43 Page 21 of 119 M/eak 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 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. Included in this augmentation is the addition of one Operator, qualified in radioactive waste system operations, within approximately 60 minutes.

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 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 direct control room response as specified in the SAMGs. The Assistant Operations Group Leader is a member of the Accident Management Team (AMT).

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EMERGENCY PLAN Revision 43 Page 22 of 119 M/eak 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 Shift Radiation Protection Technician or other SEC qualified personnel from other departments may also be assigned the responsibility of initial notifications. 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 four 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

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EMERGENCY PLAN Revision 43 Page 23 of 119 M/eak personnel include in-plant surveys, access control, and off-site radiological monitoring.

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

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EMERGENCY PLAN Revision 43 Page 24 of 119 M/eak from these groups report to the OSC where they are assigned corrective action tasks by the OSC Coordinator.

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.

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EMERGENCY PLAN Revision 43 Page 25 of 119 M/eak 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:

i Emergency Directors i TSC Group Leaders i TSC Engineering Staff i Emergency Communicators i Radiation Protection/Chemistry personnel i Operations Shift Managers i Maintenance Supervision and Engineers i Support Group personnel i Emergency Managers i EOF Technical Engineering personnel i 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

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EMERGENCY PLAN Revision 43 Page 26 of 119 M/eak 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.

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EMERGENCY PLAN Revision 43 Page 27 of 119 M/eak 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 Railway 5.4.2.3 The Burlington-Northern Railroad 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.

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EMERGENCY PLAN Revision 43 Page 28 of 119 M/eak 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.

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EMERGENCY PLAN Revision 43 Page 29 of 119 M/eak 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.

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.

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.

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EMERGENCY PLAN Revision 43 Page 30 of 119 M/eak Monticello Civil Defense 5.5.4 The Monticello Civil Defense 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.

Area Civil Defense Groups 5.5.8 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. The Civil Defense consists of a permanent staff plus a pool of reserve personnel, vehicles and radiological monitoring equipment, located throughout the State Emergency Services Mobile Support Area VI, in which Monticello is located.

Minnesota Department of Transportation 5.5.9 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 5.5.10 The Water Department can shut off water intakes, if necessary.

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EMERGENCY PLAN Revision 43 Page 31 of 119 M/eak City of St. Paul Water Department 5.5.11 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.

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EMERGENCY PLAN Revision 43 Page 32 of 119 M/eak 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 1

1 Chemistry/Radio-Chemistry Chemistry 1

1

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 33 of 119 M/eak 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 Radwaste Oper 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

13

• May be provided by shift personnel assigned other functions.

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EMERGENCY PLAN Revision 43 Page 34 of 119 M/eak Table 2 MONTICELLO PLANT ERO RESPONSIBILITY MATRIX

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EMERGENCY PLAN Revision 43 Page 35 of 119 M/eak 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.

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EMERGENCY PLAN Revision 43 Page 36 of 119 M/eak 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

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EMERGENCY PLAN Revision 43 Page 37 of 119 M/eak 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.

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EMERGENCY PLAN Revision 43 Page 38 of 119 M/eak 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.

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;

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EMERGENCY PLAN Revision 43 Page 39 of 119 M/eak 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.

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.

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EMERGENCY PLAN Revision 43 Page 40 of 119 M/eak Notification of the general public is accomplished through Local Authorities use of the Public Alert and Notification System (PANS), 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.

0-5 Mile PANS Coverage 6.2.1.4.1 Notification capabilities within the 0-5 mile EPZ include 37 sirens with a designed output of 127 dBC. This represents essentially 100%

coverage of the population within the 0-5 mile portion of the EPZ.

5-10 Mile PANS Coverage 6.2.1.4.2 Notification capabilities within the 5-10 mile EPZ include 69 sirens with a designed output of 127 dBC. This represents essentially 100%

coverage of the population within the 5-10 mile portion of the EPZ.

Supplemental Notification Capabilities 6.2.1.4.3 To further ensure prompt notification of the public, auto dialing telephone systems are used to alert select facilities, within 10 mile EPZ, which could contain large groups of people during all or part of the day. The number and location of facilities contacted is determined by the local County Emergency Management Directors. These include commercial, institutional and educational facilities which may also be covered by State and County emergency warning plans. Provisions for transient population notification are also included in State and County plans.

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.

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EMERGENCY PLAN Revision 43 Page 41 of 119 M/eak 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 method used for authentication are developed and mutually agreed to by the utility and off-site authorities.

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).

RASCAL is a dose projection software program that uses manual data input for calculation of off-site dose rates under routine or accident conditions.

The program is designed to produce real time estimates of plume locations and dose intensity. This information establishes the basis for protective action recommendations which are communicated to off-site authorities.

Meteorological and effluent data from process monitors and meteorological instruments located at the plant site is manually entered into RASCAL. This data is typically obtained from ERIS (Emergency Response Information System) which compiles the data at one central location to be used by the Dose Projection Specialist to enter into RASCAL. As the data is collected, quality control checks are made to flag bad data and identify potential problems. RASCAL is software developed and used by the U.S. Nuclear Regulatory Commission (NRC) Emergency Operations Center to estimate projected doses from radiological emergencies.

RASCAL consists of two main tools: the Source Term to Dose model and the Field Measurement to Dose model.

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EMERGENCY PLAN Revision 43 Page 42 of 119 M/eak Source Term to Dose The Source Term to Dose model is used when you want to enter information about plant conditions or accident conditions in order to estimate projected radiation doses from a plume to people downwind. This model will first generate a time-dependant source term. This is the release rate for each radionuclide from the facility as a function of time.

This time-dependent release rate (the source term) then provides the input to an atmospheric dispersion and transportation model. The atmospheric dispersion and transport model estimates radionuclide concentrations downwind, both in the air and on the ground due to deposition. The calculated concentrations are then used to estimate projected doses. The dose pathways are: cloud shine from the plume, inhalation from the plume, and groundshine from deposited radionuclides.

Field Measurement to Dose The Field Measurement to Dose model is used when the plume-phase of the accident is over and you are in the intermediate-phase. The Field Measurement to Dose model estimates doses based on measurements of the radionuclide activity in the environment. The model will use the ground concentration of radionuclides to calculate intermediate-phase doses.

RASCAL calculates exposure rates for closed window gamma meter readings taken at 1 m above ground level. Projected integrated doses are calculated by taking into account the projected duration of release. The projected doses are compared to EALs for emergency classification purposes. The projected integrated doses are compared to EPA PAGs for purposes of protective action recommendations.

The RASCAL 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.

Dose calculations based on potential releases or theoretical conditions are accommodated using a manual input mode. Calculations can also be generated based on input of containment monitor readings or percentage of fuel damage.

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.

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EMERGENCY PLAN Revision 43 Page 43 of 119 M/eak 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 containers. This equipment has the capability to detect and measure radioiodine concentrations in the air as low as 1x10-7 Ci/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.

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EMERGENCY PLAN Revision 43 Page 44 of 119 M/eak 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 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.

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EMERGENCY PLAN Revision 43 Page 45 of 119 M/eak 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.

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.

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EMERGENCY PLAN Revision 43 Page 46 of 119 M/eak 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.

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

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EMERGENCY PLAN Revision 43 Page 47 of 119 M/eak 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.

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.

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EMERGENCY PLAN Revision 43 Page 48 of 119 M/eak 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).

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

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EMERGENCY PLAN Revision 43 Page 49 of 119 M/eak Building, Security Access Facility or the EOF. In any case, strict exposure control of all individuals passing through the access point would be maintained on a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> basis.

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

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

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.

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

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EMERGENCY PLAN Revision 43 Page 50 of 119 M/eak 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.

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

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EMERGENCY PLAN Revision 43 Page 51 of 119 M/eak 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.

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.

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EMERGENCY PLAN Revision 43 Page 52 of 119 M/eak 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.

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EMERGENCY PLAN Revision 43 Page 53 of 119 M/eak 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)

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EMERGENCY PLAN Revision 43 Page 54 of 119 M/eak 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.

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EMERGENCY PLAN Revision 43 Page 55 of 119 M/eak 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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

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EMERGENCY PLAN Revision 43 Page 56 of 119 M/eak 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.

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EMERGENCY PLAN Revision 43 Page 57 of 119 M/eak 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.

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EMERGENCY PLAN Revision 43 Page 58 of 119 M/eak 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.

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:

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

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EMERGENCY PLAN Revision 43 Page 59 of 119 M/eak 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.

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.

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EMERGENCY PLAN Revision 43 Page 60 of 119 M/eak 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.

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,

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EMERGENCY PLAN Revision 43 Page 61 of 119 M/eak 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.

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.

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EMERGENCY PLAN Revision 43 Page 62 of 119 M/eak 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.

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.

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EMERGENCY PLAN Revision 43 Page 63 of 119 M/eak 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.

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.

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EMERGENCY PLAN Revision 43 Page 64 of 119 M/eak

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

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

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EMERGENCY PLAN Revision 43 Page 65 of 119 M/eak TSC and is used for plant parameter analysis and trending under the direction of the Engineering Group Leader.

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

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EMERGENCY PLAN Revision 43 Page 66 of 119 M/eak acceleration >.03 g. The second alarm is the 6-C-18 (DESIGN BASIS EARTHQUAKE (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 east of the Reactor Building. It consists of a 100 meter guyed steel tower with a climate controlled instrument shelter at its base. The tower has a motor driven elevator which raises and lowers the three separate instrument platforms mounted on the tower.

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EMERGENCY PLAN Revision 43 Page 67 of 119 M/eak The instrument platforms are located at 10, 43 and 100 meters. Each platform has two independent sets (trains) of instrumentation (A and B channels). Each instrument set includes one combination wind speed and direction sensor and one RTD temperature probe. Wind speed and direction transmitters are provided with heater elements to reduce the potential of becoming inoperable during low temperature conditions. The temperature sensors are housed in forced air, shielded aspirators which include air flow sensors. Insufficient air flow and motor inoperability indicator lights are provided in the instrument shelter. Signal transmission lines from the sensors to the instrument shelter junction box are provided with power surge protection and the tower is equipped with lightning rods and is grounded.

Both sets (trains) of sensors and related instrumentation normally receive power from one of two AC power sources. Transfer of power sources may be accomplished manually in the event of a loss of the normal AC power supply. In addition, a UPS is provided in the event manual transfer of the AC power supplies does not occur.

Signals from the 100 meter tower instrumentation are fed to the instrument processor rack located in the instrument shelter and provide the primary and secondary source of meteorological data.

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.

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EMERGENCY PLAN Revision 43 Page 68 of 119 M/eak 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.

Meteorological data from one train of sensors on the 100 meter tower 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.

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EMERGENCY PLAN Revision 43 Page 69 of 119 M/eak 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.

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.

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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.

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.

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EMERGENCY PLAN Revision 43 Page 71 of 119 M/eak 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.

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.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 72 of 119 M/eak 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.

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.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 73 of 119 M/eak 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.

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).

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 74 of 119 M/eak 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.

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.

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EMERGENCY PLAN Revision 43 Page 75 of 119 M/eak 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.

Public Alert and Notification System (PANS) 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 Monticello Nuclear Generating Plant has developed a 106 unit fixed siren system design for essentially 100% coverage of the population within 10 miles of the Site.

Sirens installed by MNGP have been sited according to a 70dB criteria to ensure the required coverage. Provisions for transient population notification are also included in State and County plans.

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.

In the event of an emergency condition, alert and notification information will be relayed through established communication links described in the Minnesota Emergency Response Plan. Upon receiving notification of the emergency, state and local governments will, if necessary, activate public warning and information procedures which include the State Emergency Alert System (EAS). With this system, essentially 100% of the population in the 0-10 mile zone will be alerted within 15 minutes.

In the event a county primary siren activation system fails to operate, each county has a backup siren activation process on a separate activation system utilizing a different tower and controls for activation of the sirens.

In the event a siren or sirens fail to receive the activation signal or function properly, each county has maps, directions and instructions for notifying the public in the areas where the sirens did not function.

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

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EMERGENCY PLAN Revision 43 Page 76 of 119 M/eak 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 X

X X

X X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

X X

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 77 of 119 M/eak 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 43 Page 78 of 119 M/eak 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 43 Page 79 of 119 M/eak 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 Ci/Sec Reactor Building Vent WRGM 2

Panel C-257 Panel C-258 100 - 1012 Ci/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 10 104 mrem/hr Continuous Air Monitors

1. Primary OSC

2. TSC

3. SJAE Room (Condensate Pump Area)

4. 951 Turbine Floor East

5. 1027 Reactor Building

6. Recombiner Building (TB RR Access)

7. Off-gas Storage Building

8. 962 Reactor Building (CUPR Vent)

9. 962 RX Building East (Samples Stm Chase)

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EMERGENCY PLAN Revision 43 Page 80 of 119 M/eak 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 43 Page 81 of 119 M/eak 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

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EMERGENCY PLAN Revision 43 Page 82 of 119 M/eak 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

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EMERGENCY PLAN Revision 43 Page 83 of 119 M/eak 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 43 Page 84 of 119 M/eak 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 43 Page 85 of 119 M/eak 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 43 Page 86 of 119 M/eak 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. At least once every six years, an exercise should demonstrate a response to a terroristic (hostile action based) event.

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.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 87 of 119 M/eak 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.

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.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 88 of 119 M/eak The Public Alert Notification System (PANS) is 8.1.2.6.4 tested weekly in accordance with plant Surveillance Test 1359.

The Annual Performance Review for the PANS 8.1.2.6.5 is 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.

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

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 89 of 119 M/eak Changes in State or Federal regulations.

8.2.2.6 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.

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 43 Page 90 of 119 M/eak 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:

x There must be assurance that the problem encountered is solved and that the same incident cannot immediately recur; x

The normally occupied areas must be free of significant contamination; x

Radiation areas and High Radiation areas must be properly defined; x

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:

x Investigation of the course of the incident.

x Investigation of plant conditions following an accident.

x Repair and restoration of facilities.

x 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 43 Page 91 of 119 M/eak Criteria for Resumption of Operation 9.4 If the plant is shutdown as the result of an emergency, it will be restarted only when:

x The conditions which caused the emergency are corrected.

x The cause of the emergency is understood.

x Restoration, repair and testing is completed as required.

x No unreviewed safety questions exist.

x 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 43 Page 92 of 119 M/eak 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 43 Page 93 of 119 M/eak 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 43 Page 94 of 119 M/eak 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 43 Page 95 of 119 M/eak 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 43 Page 96 of 119 M/eak 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 & Off-site Plan

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 97 of 119 M/eak 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.

6.1.3.11

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 98 of 119 M/eak 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

6.5.1.2, 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 43 Page 99 of 119 M/eak 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 43 Page 100 of 119 M/eak 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 43 Page 101 of 119 M/eak 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 43 Page 102 of 119 M/eak 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 43 Page 103 of 119 M/eak 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 43 Page 104 of 119 M/eak 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 43 Page 105 of 119 M/eak 12.0 FIGURE Annex A-1 Monticello Nuclear Generating Plant Emergency Action Level Matrix Left half of Page 1 of Form 5790-101-02

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 106 of 119 M/eak 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

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 107 of 119 M/eak 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

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 108 of 119 M/eak 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

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 109 of 119 M/eak 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 43 Page 110 of 119 M/eak 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)

(TSC)

OSC NRC EMERGENCY MANAGER (EOF)

NSPM EXECUTIVE MANAGEMENT (JIC)

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 111 of 119 M/eak 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)

State Agencies Utility Liaison Minnesota State EOC 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 43 Page 112 of 119 M/eak 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 EOF CR C

C F/T COMM OFF-SITE MONITORING TEAMS RP GROUP CHEM GROUP F/T COMM MONITORING SECTION LEADER OFF-SITE MONITORING F/T COMM 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 43 Page 113 of 119 M/eak Figure 13.5 PLAN VIEW OF TECHNICAL SUPPORT CENTER, BACK-UP OPERATIONAL SUPPORT CENTER

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 114 of 119 M/eak Figure 13.6 PLAN VIEW OF THE EMERGENCY OPERATIONS FACILITY

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 115 of 119 M/eak 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.

EP-7-3 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 43 Page 116 of 119 M/eak 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day with no limit to its use.

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 117 of 119 M/eak Figure 13.8 PLAN VIEW OF OPERATIONAL SUPPORT CENTER PAB 1st Floor OSC Assembly Areas

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 118 of 119 M/eak Figure 13.8 PLAN VIEW OF OPERATIONAL SUPPORT CENTER (CONTD)

PAB 2nd Floor OSC Command Center

MONTICELLO NUCLEAR GENERATING PLANT E-PLAN TITLE:

EMERGENCY PLAN Revision 43 Page 119 of 119 M/eak Figure 13.9

SUMMARY

OF SIGNIFICANT CHANGES Section Change and Reason for Change 5.1.2.4 Removed Shift Emergency Communicator responsibilities from the duties of the Chemistry Technician.

5.3.1.3 Removed the Shift Chemistry Technician from the list of positions that may be assigned the responsibility of initial notifications.

5.6 Added a new section identifying support to be provided by off-site non-government agencies in accordance with existing letters of agreement.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 1 of 32 M/arb Approval:

INFORMATION USE x Procedure should be available, but NOT necessarily at the work location.

x Procedure may be performed from memory.

x User remains responsible for procedure adherence.

PCR 01407081

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 2 of 32 M/arb EMERGENCY PLAN IMPLEMENTING PROCEDURE - TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE........................................................................................................... 3 2.0 APPLICABILITY.................................................................................................. 3 3.0 ORGANIZATION AND RESPONSIBILITIES....................................................... 3 4.0 DISCUSSION...................................................................................................... 4 5.0 PRECAUTIONS................................................................................................... 4 6.0 INSTRUCTIONS.................................................................................................. 8 6.1 Field Team Activation............................................................................... 8 6.2 Plume Search Procedure........................................................................ 10 6.3 Particulate and Iodine Air Sampling........................................................ 11 6.4 Gaseous Air Sampling............................................................................ 13 6.5 Stationary Dose Rate Survey.................................................................. 14 6.6 Liquid Sampling...................................................................................... 15 6.7 Discharge Canal Sampling (Monticello Only).......................................... 16 6.8 Ground Deposition - Direct Frisk Survey................................................. 17 6.9 Ground Deposition - Smear Samples..................................................... 17 6.10 Ground Deposition - Gamma Dose Rate Survey.................................... 18 6.11 Ground Deposition Samples - Snow/Dirt Survey.................................... 18 6.12 Ground Deposition - Vegetation/Food Sampling..................................... 19 6.13 Off-Site Sample Courier Instructions...................................................... 21 6.14 Prairie Island Off-Site Field Team Driver Instructions............................. 23 7.0 FIGURES.......................................................................................................... 24 7.1 Gross Iodine Activity Table..................................................................... 24 7.2 Gas Chamber Table................................................................................ 25 7.3 Gross Liquid Activity Table..................................................................... 26 7.4 Gross Particulate Activity Table.............................................................. 27 7.5 On-Site Liquid Sample Locations............................................................ 28 7.6 Air Sample Filter Assembly..................................................................... 29 7.7 Instructions for the GPS Unit.................................................................. 30 7.8 Forms Utilized in this Procedure............................................................. 31 7.9 Summary of Significant Changes............................................................ 32 NOTE: The following Instruction sections begin with a new page for ease of use in the field: 6.2, 6.3, 6.4, 6.5, 6.6, 6.7, 6.8, 6.13 & 6.14.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 3 of 32 M/arb 1.0 PURPOSE This procedure provides instructions for the activation of Off-site Radiological Monitoring Teams (Field Teams) and the various methods of radiological and environmental monitoring during a declared Emergency at either the Monticello or Prairie Island plants.

2.0 APPLICABILITY 2.1 Abnormal conditions exist which involve an airborne or liquid radiological release to the Monticello plant environs and out-of-plant surveys have been requested.

2.2 An emergency (Alert or higher classification) has been declared at the Prairie Island Nuclear Generating Plant and Monticellos assistance has been requested.

3.0 ORGANIZATION AND RESPONSIBILITIES 3.1 The Radiological Emergency Coordinator (REC) is responsible for:

3.1.1 Overall direction and control of the Field Teams until these responsibilities are assumed by the Emergency Operations Facility (EOF).

3.2 The Radiation Protection Support Supervisor (RPSS) is responsible for:

3.2.1 Overall direction and control of the Field Teams after these responsibilities are transferred from the Technical Support Center (TSC).

3.3 The Field Team Communicator(s) are responsible for:

3.3.1 Coordination of the Field Teams via radio communication from the TSC or EOF.

3.4 The Field Teams are responsible for:

3.4.1 Implementation of this procedure.

3.4.2 Maintaining a constant communication link with the Field Team Communicator in the TSC or EOF.

3.4.3 Performing surveys in accordance with applicable instructions contained in this procedure and as directed by the Field Team Communicator.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 4 of 32 M/arb 3.5 The Sample Courier(s) are responsible for:

3.5.1 Transportation of samples (taken by the Field Teams) to the EOF.

4.0 DISCUSSION Off-site surveys during an emergency are normally performed by sister plant Radiation Protection personnel when the EOF is fully activated. Prior to this, off-site surveys must be performed by the affected plants personnel. Surveys of on-site, out-of-plant areas are always assigned to the affected plants personnel.

During the initial stage of an emergency, the number of personnel available to perform surveys may be limited. The REC will make decisions on deployment of personnel resources. When the RPSS position is staffed and the EOF is fully operational, control of the Field Teams will be transferred to the RPSS.

There are normally two vehicles designated for off-site monitoring purposes. The Radiation Protection Coordinator maintains control of the keys (24 or 25) for these vehicles.

The EOF Count Room is the primary off-site facility for the receipt and analysis of radioactive samples. The EOF Count Room is staffed by Chemistry personnel from the affected plant who are familiar with its equipment and operation. Unless circumstances dictate otherwise, the EOF Count Room will be used for most samples taken pursuant to this procedure.

The ability to sample and analyze for I-131 meets NRC Commitment 03002A.

GPS units are available in the EVES building to assist field team members in identifying precise sample locations with GPS coordinates when samples are taken at locations other than the pre-determined survey points. Also, the pre-determined survey point coordinates are programmed into the GPS units so the GPS units can assist in directing the teams to and finding these points.

Portable electronic data devices can be used as a tool for the field teams to access the Emergency Electronic Information System (EEIS).

5.0 PRECAUTIONS 5.1 Monitoring and sampling instruments SHALL be operated in accordance with standard procedures for each instrument type.

5.2 During off-hours activations, Field Team personnel should verify their fitness-for-duty (FFD) with appropriate supervisory personnel (F/T communicator) prior to engaging in activities which directly affect the Health and Safety of the public (e.g. off-site surveys to validate off-site dose projections). This confirmation may be conducted via radio (or telephone) and need not occur in person.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 5 of 32 M/arb 5.3 Minnesota has severe weather conditions which can seriously affect instrument operation. The following guidelines have been established to eliminate or minimize cold weather instrument problems:

5.3.1 Allow approximately 5 minutes for the instrument to warm up completely.

5.3.2 If the outside temperature is greater than 32°F(0°C), instrument use is not restricted by temperature.

5.3.3 If the outside temperature is between 32°F (0°C) and 0°F (-18°C), use the instrument outside no more than 5 (five) minutes.

5.3.4 If the outside temperature is between 0°F (-18°C) and -20°F (-28°C),

use the instrument outside no more than 2 (two) minutes.

5.3.5 If the outside temperature is below -20°F (-28°C), the instrument should not be used outside unless special batteries (alkaline or Ni-Cd) are installed in the instrument. These batteries increase the minimum temperature range to -40°F (-40°C) but allows less than 30 seconds of use in this type of environment.

5.4 If an instrument malfunctions or pegs out during survey operations, immediately exit the area by the same route used to enter, and obtain a new instrument if necessary.

5.5 During radio and cellular phone communications, observe the following precautions:

5.5.1 Since radio and cellular phone communications can be intercepted by commercially available scanners, all communications must be brief, factual and free of all exclamatory or alarming expressions.

5.5.2 Carefully word data transmission to minimize confusion, in particular, avoid abbreviations such as mrem which could be misinterpreted as rem.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 6 of 32 M/arb 5.5.3 Use the phonetic alphabet when communicating sample points location, etc., as follows:

A ALPHA J

JULIET S

SIERRA B

BRAVO K

KILO T

TANGO C

CHARLIE L

LIMA U

UNIFORM D

DELTA M

MIKE V

VICTOR E

ECHO N

NOVEMBER W WHISKEY F

FOXTROT O

OSCAR X

X-RAY G

GOLF P

PAPA Y

YANKEE H

HOTEL Q

QUEBEC Z

ZULU I

INDIA R

ROMEO 5.5.4 Preface each communication with the title or name of the receiving party and your title and name. For example: Monticello TSC; Monticello Field Team 1...

After the communication is completed, request the receiving party to repeat the message, if numerical data was relayed.

End message transmission with an appropriate termination phrase.

For example: Monticello Field Team 1, out. During drills always include the words, THIS IS A DRILL, with each transmission.

5.6 Observe respiratory protection and exposure precautions at all times while performing off-site monitoring. If substantial airborne activity or contamination is suspected, don appropriate protective clothing as directed by the REC (or RPSS) IAW the following guidelines:

5.6.1 Field Team members should don respirators with GMR canisters if the following conditions occur:

A.

A General Emergency is declared and the affected sectors have been evacuated; and B.

Measured dose rates are more than 100 mrem/hr true Beta.

5.6.2 Respiratory equipment may be removed if the following is indicated:

A.

Field measurements of gross iodine activity indicates less than 1E-7 Ci/cc; or B.

The REC/RPSS indicates that no significant iodine is or has been released from the plant; and C.

Measured dose rates are less than 100 mrem/hr true Beta.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 7 of 32 M/arb 5.7 Exposures of survey team personnel SHALL be IAW administrative control levels. All Field Team members and Sample Couriers SHALL have proper dosimetry, which is frequently checked. They SHALL remain alert to their own exposure and request relief if cumulative exposure approaches administrative control levels. The Emergency Director may authorize exposure limit extensions if necessary (refer to A.2-401). All exposures SHALL be maintained AS LOW AS REASONABLY ACHIEVABLE aided by the following guidelines:

5.7.1 Field Teams should not linger in areas greater than 100 mr/hr.

5.7.2 Field Teams should not proceed to areas projected to be greater than 1000 mrem/hr unless directed by the REC or RPSS.

5.7.3 Field Teams SHALL NOT proceed to areas projected to exceed 10,000 mrem/hr.

5.8 During off-site monitoring operations, vehicles and/or survey instruments could become highly contaminated and plume, ground contamination or background radiation conditions may be encountered which could interfere with sample analysis or survey results. Remain alert to these conditions and take appropriate precautions to ensure accurate sample/survey results (i.e., move away from vehicle to analyze samples, prevent instrument contamination by bagging instrument, prevent sample from cross-contamination, etc.).

5.9 GPS units are provided in the EVES building and can be used as a supplemental tool to improve the Field teams capability for finding Survey Points and identifying sample locations not taken at pre-determined Survey points. Use of the GPS units is not required and should not delay initial deployment to the field or to perform directed surveys.

5.10 Portable electronic data devices may be provided to access the EEIS for data entry and event status information. When applicable, the use of EEIS is preferred with the use of hard copies as a backup. Use of the electronic data devices and EEIS should not delay initial deployment to the field or to perform directed surveys.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 8 of 32 M/arb 6.0 INSTRUCTIONS NOTE 1:

Sections of this procedure can be performed concurrently. It is acceptable to collect all directed samples and then proceed to a low background area to count the samples.

NOTE 2:

Survey data may be entered into the EEIS, hard copy forms should be used if EEIS data entry is not available.

6.1 Field Team Activation 6.1.1 If responding to a MNGP event, refer to the OSC tagboard to determine Field Team assignment.

6.1.2 Obtain Emergency vehicle keys. (From the Radiation Protection Controlled Key Cabinet.) If necessary obtain a dose rate meter for use enroute to the EVES Building.

6.1.3 Obtain respirator corrective lenses, as applicable.

6.1.4 Log in on the declared emergency work order. If responding to an event at MNGP, then retain your personal dosimetry (TLD, and electronic dosimeter) from the plant when exiting. If responding to an event at Prairie Island or circumstances prevent use of normal plant dosimetry, then obtain dosimetry from the Emergency Kits in the EVES building.

6.1.5 At the EVES Building initiate Form 5790-410-02 (OUT-OF-PLANT SURVEY CHECKLIST).

NOTE: Emergency Instrument and Equipment Kits may be stored in the vehicles.

6.1.6 Obtain one (1) Instrument Case (aluminum) and two (2) Equipment Cases A black case and B grey case from the storage area in the EVES Building, if not in vehicle.

6.1.7 Ensure that each member of the monitoring team has dosimetry, one TLD and an electronic dosimeter.

6.1.8 Record the applicable dosimetry information for each member of the team on Form 5790-410-02.

NOTE: A check source is provided in the EVES Building for this purpose.

6.1.9 Obtain a count rate meter with 2 pancake probe and dose rate meter from the cabinet and perform the applicable operability and source checks. Leave the instruments on.

6.1.10 Obtain one (1) cellular phone and one (1) cellular phone adapter unit from the EVES Building and install in vehicle.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 9 of 32 M/arb NOTE: Instructions for using the cellular phones are located in each vehicle.

6.1.11 Perform an operability check of the mobile radios by establishing contact with the TSC or EOF (when staffed). Obtain a phone number in the area (TSC or EOF) to call. Perform an operability check of the cellular phone by calling the number obtained.

6.1.12 For emergency events at the Monticello plant, contact the Field Team Communicator (TSC/EOF). When ready to depart, obtain updated information pertaining to the event and wait for further instructions.

NOTE: Use of the GPS units is not required and should not delay initial deployment to the field or performing directed surveys.

6.1.13 IF a Global Positioning System (GPS) unit is to be used, THEN obtain a GPS unit from the EVES building and prepare the unit for use. Refer to basic instructions for the operation of the units located in Figure 7.7.

IF GPS units are used for identifying locations of samples or survey points taken, THEN the coordinates should be recorded on the data sheets.

6.1.14 If responding to a PI event, refer to Section 6.3 of EPIP A.2-702 (RESPONSE TO AN EMERGENCY AT PRAIRIE ISLAND) for travel routes and instructions for response to the Prairie Island EOF.

6.1.15 When departing the plant site area (or entering PI 10 mile EPZ), initiate a plume search (if applicable) IAW Section 6.2 of this procedure.

6.1.16 Document all survey/sample data on Form 5790-410-01 (EMERGENCY SAMPLE RESULTS LOG) or Form 5790-410-03 (GROUND DEPOSITION SAMPLE RESULTS LOG) as applicable.

6.1.17 Report all survey/sample results to the Field Team Communicator.

6.1.18 Forward samples which require further analysis (as directed by the Field Team Communicator) to the EOF Count Room via sample courier or retain the samples for future analysis and/or disposal as directed.

6.1.19 When directed, return to the EOF for debriefing and reassignment.

Complete and submit all sample result logs and Form 5790-410-02 to the RPSS for review.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 10 of 32 M/arb 6.2 Plume Search Procedure 6.2.1 With the count rate meter on the lowest scale (on which meter deflection can be observed) place the probe on the dashboard facing the windshield and observe the instrument for meter deflection while in transit.

NOTE: A BETA reading indicates that the plume has been encountered. A GAMMA reading with zero BETA indicates the plume is elevated or displaced.

6.2.2 If a meter deflection is observed, stop the vehicle and perform a dose rate survey in accordance with Section 6.5.

NOTE: If the survey location is NOT at a predesignated survey point, identify the location using known landmarks or road intersections, etc.

6.2.3 Report the survey results to the Field Team Communicator as recorded on Form 5790-410-01.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 11 of 32 M/arb 6.3 Particulate and Iodine Air Sampling 6.3.1 Install a particulate filter and a Silver Zeolite cartridge into the air sampler cartridge/filter holder. (See FIGURE 7.6 for Assembly Diagram.)

NOTE 3:

Engine should be running to maintain a steady battery voltage.

NOTE 4:

If precipitation is occurring, the sample should be drawn from a covered area. The umbrella included in the Emergency Kit may be used for this purpose.

6.3.2 Connect the air sampler to the vehicle power supply and start the air sampler.

6.3.3 Record the sample START TIME, SURVEY POINT (sample location),

sample FLOW RATE and SURVEY TYPE on Form 5790-410-01.

NOTE: Whenever possible air samples should be a standard 25 cu. ft. sample (i.e. 7.07 E+5 CCs or approximately 10 minute sample run time).

6.3.4 When the desired sample time has lapsed, stop the air sampler and record the sample STOP TIME.

6.3.5 Calculate and record the sample volume in cubic centimeters (cc) using the following formula:

Sample Volume in ccs = (Flow Rate in cfm) x (Sample Time in Minutes) x (2.83 E+4 cc/ft3).

6.3.6 Remove the particulate filter and the Silver Zeolite cartridge from the filter cartridge holder, place them in SEPARATE plastic sample bags and seal the bags.

6.3.7 Complete a pre-printed sample label including the sample time and date, sample location, sample volume and the contact dose rate and attach a label to each sample bag.

6.3.8 In a low background area (i.e. < 1000 cpm) determine the gross activity of each sample by using the following methods:

A.

Particulate Activity

1.

Count the particulate filter using a count rate meter with a 2 pancake probe. Subtract the background to determine the Net cpm of the sample.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 12 of 32 M/arb NOTE 1:

Probe Efficiency = 0.1 (10%) for Count Rate Meter with a 2 pancake probe.

NOTE 2:

Correction Factor (CF) = 0.3 for 4 filter paper counted with a 2 pancake probe or 1.0 for 2 filter paper counted with a 2 pancake probe.

2.

Calculate the gross particulate activity of the sample using the Gross Particulate Activity Table (FIGURE 7.4) or the following formula:

ACTIVITY (Ci/cc) = (NET cpm) x (4.5 E-7 Ci/dpm)

(PROBE EFFICIENCY) x (SX VOLUME in ccs) x (CF)

B.

Iodine Activity

1.

Count the Silver Zeolite cartridge using a count rate meter with a 2 pancake probe. Subtract the background to determine the Net cpm of the sample.

2.

Calculate the sample activity using the Gross Iodine Activity Table (FIGURE 7.1) or the following formula:

IODINE ACTIVITY (Ci/CC) = (Ci(s) on cartridge determined by Table)

(SX volume in ccs) 6.3.9 Record the results on Form 5790-410-01.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 13 of 32 M/arb 6.4 Gaseous Air Sampling CAUTION If hands are contaminated, handle chamber with clean surgeon gloves.

6.4.1 Obtain the gas sampling chamber, suction bulb and filter assembly from the Emergency Kit. (See FIGURE 7.2 for assembly diagram.)

6.4.2 Install a new filter in the filter holder assembly.

6.4.3 Connect the suction bulb, sample chamber and filter assembly such that air passes through the filter assembly into the sample chamber then to the suction bulb.

6.4.4 Open the stop cocks on the gas sample chamber, squeeze the suction bulb ten (10) times to obtain a representative sample, then shut the stop cocks on the gas sampling chamber.

6.4.5 Record the SAMPLE TIME, SURVEY POINT, (sample location) and SAMPLE TYPE on Form 5790-410-01.

6.4.6 In a low background area (i.e., <1000 cpm) determine the activity of the gas sample (Ci/cc of Xe 133 equivalent) using a count rate meter with a 2 pancake probe and the following method. Record the results of each step on Form 5790-410-01.

A.

Count the gas sample by placing the probe directly against the flat side of the container. Record the results as Gross cpm.

B.

Determine the background count rate by placing the probe directly against the flat side of an empty gas sample container.

Record the results as Bkgrd cpm.

C.

Calculate and record the Net cpm (Gross minus Bkgrd).

D.

Determine the gas sample activity using the Net cpm and Figure 7.2 (Gas Chamber Table). Record the result as uCi/cc.

6.4.7 Complete a pre-preprinted label with all applicable sample data. Place the sample in a plastic sample bag, seal the bag, and attach the label to the bag.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 14 of 32 M/arb 6.5 Stationary Dose Rate Survey 6.5.1 IF the Dose Rate Meter is de-energized THEN energize the Meter and allow the instrument to stabilize (approximately 30 seconds) then re-zero the meter.

6.5.2 Perform a BETA/GAMMA survey of the area as follows:

A.

With the window open, hold the instrument approximately one (1) meter from ground level and survey the area for the maximum meter deflection; B.

Record the WINDOW OPEN (BETA/GAMMA) reading.

C.

Close the instrument window and obtain the GAMMA reading; D.

Record the WINDOW CLOSED (GAMMA) reading.

NOTE: Assume a BETA CORRECTION FACTOR of 5.0 if the BETA CORRECTION FACTOR for the instrument is unknown.

E.

Calculate the TRUE BETA reading as follows:

TRUE BETA = (WINDOW OPEN - WINDOW CLOSED) x (BETA CORRECTION FACTOR)

NOTE: If the survey location is NOT a predesignated survey point, identify the location using known landmarks or road intersections, etc.

F.

Record the TRUE BETA results on Form 5790-410-01.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 15 of 32 M/arb 6.6 Liquid Sampling NOTE: An additional supply of sample bottles are available at the EOF.

6.6.1 Obtain a 1 liter sample bottle and install the bottle in the holder.

CAUTION Use the appropriate radiological precautions when handling potentially radioactive samples.

6.6.2 Cast or lower the bottle into the water to be sampled, allow the bottle to fill completely then withdraw and cap the bottle.

6.6.3 Bag the sample bottle, complete a pre-printed label. Attach the label to the sample bottle, label and seal the plastic bag.

6.6.4 Record the sample TIME, SURVEY POINT (sample location) and SURVEY TYPE on Form 5790-410-01.

6.6.5 In a low background area (i.e., <1000 cpm) determine the gross activity of the sample using the following method:

A.

Count the sample using a count rate meter with a 2 pancake probe by placing the probe on the sample as indicated on the Gross Liquid Activity Table (FIGURE 7.3). Subtract the background to determine the Net cpm of the sample.

B.

Record the background, and Net cpm on Form 5790-410-01 (EMERGENCY SAMPLE RESULTS LOG);

C.

Determine the activity of the sample using the Gross Liquid Activity Table (FIGURE 7.3) and the Net cpm of the sample.

6.6.6 Record the sample results on Form 5790-410-01.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 16 of 32 M/arb 6.7 Discharge Canal Sampling (Monticello Only) 6.7.1 Obtain 1 liter sample bottles from an Emergency Kit or from the Chemistry lab.

6.7.2 Obtain the keys for one of the Plant vehicles (if needed) and a hand held radio. (Radios are available in the TSC and OSC.)

6.7.3 Proceed to the Discharge Canal Sample Station (DCSS) located on the south bank of the discharge canal approximately 550 downstream of the discharge structure. (FIGURE 7.5) Sample point (3) of on-site liquid sample locations map.

6.7.4 In the DCSS Building locate pumps P-112A and P-112B. Verify the sample flow into the drain trough down stream of CW-27 is at least 7 gpm as indicated by reading flow indicator FIS-1905 centered above pumps P-112A and P-112B.

6.7.5 Using a 1 liter bottle, take the desired sample(s) from the 1.5 inch line dumping water into the trough.

6.7.6 Bag the sample bottle, complete a pre-printed sample label, attach the label to the sample bottle, label and seal the plastic bag.

6.7.7 Record the sample TIME, SAMPLE POINT (sample location) and SURVEY TYPE on Form 5790-410-01.

6.7.8 Determine the gross activity of the sample using the following method:

A.

Count the sample using a count rate meter with a 2 pancake probe by placing the probe on the sample as indicated in Gross Liquid Activity Table (FIGURE 7.3). Subtract the background to determine the Net cpm of the sample.

B.

Record the background and Net cpm on Form 5790-410-01; C.

Determine the activity of the sample using the Gross Liquid Activity Table (FIGURE 7.3) and the Net cpm of the sample.

6.7.9 Record sample results on the Form 5790-410-01.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 17 of 32 M/arb 6.8 Ground Deposition - Direct Frisk Survey 6.8.1 Obtain a count rate meter with a 2 pancake probe or equivalent.

6.8.2 Determine a background cpm in a unaffected area or estimate background cpm (typically 30-40 cpm) record on Form 5790-410-03.

6.8.3 Proceed to the designated survey point and carefully scan flat surfaces in the area (e.g., roads, lawns, mailboxes, vehicles, fields, etc.).

6.8.4 Record the sample TIME and SURVEY POINT (sample location) on Form 5790-410-03.

6.8.5 Calculate the ground deposition activity as follows:

Ci/m2 = Net cpm 400 6.8.6 Record sample results on Form 5790-410-03.

6.9 Ground Deposition - Smear Samples 6.9.1 Obtain the appropriate number of cloth smears from the Emergency Kit and number the smears (if necessary).

NOTE: Each smear area should be clearly identified on a map of the area or in a written description of the area.

6.9.2 Proceed to area to be surveyed and smear approximately 100cm2 of selected smooth surfaces (e.g., cars, mail boxes, machinery, rain gutters etc.).

6.9.3 Place the smear(s) in plastic sample bag(s) and seal and label the bag(s).

6.9.4 Record the sample TIME AND SURVEY POINT (sample location)

SURVEY TYPE on Form 5790-410-03.

6.9.5 In a low background area (i.e., <1000 cpm), calculate the smearable activity of each smear sample using the following method:

A.

Establish an area suitable for counting potentially contaminated smears; B.

Determine the background cpm;

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 18 of 32 M/arb C.

Remove the smear(s) from the bag(s) and count using count rate meter with a 2 pancake probe.

D.

Calculate the ground deposition activity as follows:

Ci/m2 = Net cpm 200 6.9.6 Rebag the smear sample(s). Contact the Field Team Communicator and arrange to have the sample(s) transported to the EOF Count Room for analysis or retain the sample(s) for future analysis and proper disposal.

6.9.7 Record smear sample results on Form 5790-410-03.

6.10 Ground Deposition - Gamma Dose Rate Survey 6.10.1 Obtain a dose rate meter. Energize the dose rate meter and allow the instrument to stabilize (approximately 30 seconds) then re-zero the meter.

6.10.2 Proceed to the designated survey area and perform a closed window dose rate survey of the area at 1 meter above the ground.

6.10.3 Record the sample TIME, SURVEY POINT (sample location) and mrem/hr readings under Gamma Survey on Form 5790-410-03.

6.10.4 Calculate ground deposition as follows:

Ci/m2 = 100 x (CLOSED WINDOW mr/hr READING) 6.10.5 Record sample results on Form 5790-410-03 and report the results to the Field Team Communicator.

6.11 Ground Deposition Samples - Snow/Dirt Survey NOTE: The selection should be based on an evaluation of current weather and ground cover conditions (high winds, rain, snow, etc.) such that the sampled area is representative of the ground cover surface. Sample the area where the deposition of contamination is most likely to occur.

6.11.1 Proceed to the designated survey area and select an area where the sample will be taken.

6.11.2 Obtain the aluminum scoop and a large plastic sample bag from the Emergency Kit.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 19 of 32 M/arb NOTE: The area of the scoop is approximately 1,000cm2. When removing surface snow to a depth of 1 centimeter the volume of the melted snow is approximately 100 cc of liquid. This assumes a 10:1 snow to water ratio.

6.11.3 Using the scoop, remove snow/dirt from a surface area of about 1000 cm2 to a depth of about 1 centimeter (0.4 inches).

6.11.4 Place the sample material in a large zip-lock bag, seal and label.

6.11.5 Record the sample TIME, SURVEY POINT (sample location), and the SAMPLE TYPE on Form 5790-410-03.

NOTE: Field count rate for snow/dirt sample not required, analysis is performed by count room.

6.12 Ground Deposition - Vegetation/Food Sampling 6.12.1 Proceed to the designated survey area and select the area where the sample will be taken.

NOTE: The selection should be based on locating herbage eaten by grazing animals, since the herbage provides a key pathway to human exposure. Also, depending on season of year, plant fruit (strawberries, sweet corn, beans, wheat, oats, etc.) may be selected for sampling.

6.12.2 Obtain scissors or trimming device and large zip-lock bag from the Emergency Kit.

NOTE: If the vegetation is grass an area of at least 1 m2 of ground should be sampled.

The vegetation should be cut at approximately.5 to 1 inch from the ground and should not be contaminated in the process by soil.

6.12.3 Obtain enough vegetation/food to fill the zip-lock bag. This is about a 1/3 of a kilogram.

6.12.4 Compress the air from the bag, seal and label bag.

6.12.5 Record the sample TIME, SURVEY POINT (sample location) and SURVEY TYPE on Form 5790-410-03.

NOTE: This calculation is based on I-131 and CS-137.

6.12.6 Calculate the activity of the sample using the following method:

A.

Flatten the bag and lay probe of a count rate meter with 2 pancake probe on the center of the bag.

B.

Wrap bag around probe and note reading.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 20 of 32 M/arb C.

Calculate the activity using the following formula:

Ci/kg = Net cpm 1.32 6.12.7 Record the sample results on Form 5790-410-03 and report the results to the Field Team Communicator.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 21 of 32 M/arb 6.13 Off-Site Sample Courier Instructions 6.13.1 When dispatched by the OSC Coordinator, obtain an electronic dosimeter (either from the OSC or Access Control), respirator corrective lenses, as applicable, and log onto the declared emergency work order. Retain your TLD and dosimeter when departing the plant.

6.13.2 Obtain the keys for a plant vehicle and the keys to EVES building.

Keys may be obtained from the Security Access Facility or Nuclear Plant Helper Supervisor key cabinet.

6.13.3 Obtain one Sample Courier Kit (aluminum case), one portable mobile radio kit from the EVES Bldg.

6.13.4 Place the Sample Courier Kit in the vehicle and install the mobile radio and antenna.

6.13.5 Perform an operability check of the installed radio unit, prior to departing the EVES Building, by contacting the TSC (or EOF).

6.13.6 Proceed to the EOF Command Center, using the back (Receiving Area) personnel entrance, and contact the Radiation Protection Support Supervisor (RPSS) immediately upon arrival.

6.13.7 Standby in the EOF for assignments as directed by the RPSS.

6.13.8 When dispatched from the EOF to pick up samples:

A.

Logout of the EOF (if necessary) with EOF Security (ensure you keep your dosimetry when departing the EOF).

B.

Establish and maintain constant radio communication with the Field Team Communicator and follow the communicators instructions regarding travel routes, etc.

C.

Rendezvous with Field Teams at designated locations for sample pickup.

D.

Frequently check your dosimeter and notify the Field Team Communicator when exposure approaches administrative limits.

6.13.9 When picking up samples from the Field Team(s):

A.

Obtain any special instructions for handling the sample(s) from the RPSS (e.g. ALARA precautions, etc.).

B.

Ensure the sample(s) are properly packaged (bagged) and labeled.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 22 of 32 M/arb NOTE: Protective clothing is provided in the Sample Courier Kit.

C.

Confirm radiological conditions along your travel route(s) with the RPSS and follow the instructions regarding the use of protective clothing (e.g. respiratory protection) that may be warranted.

6.13.10 Transport the sample(s) promptly to the EOF Count Room for analysis.

While enroute (to the EOF) contact the EOF Count Room (by radio) and inform the Count Room Tech you will be delivering samples.

6.13.11 Upon arrival at the EOF use the back (Receiving area) personnel entrance into the EOF Controlled Area (the posted Contaminated area in the EOF loading dock) and:

A.

Notify the Count Room Tech samples have arrived.

B.

Ensure the samples are properly re-bagged, re-labeled and surveyed (with a frisker or dose rate meter) prior to transfer out of the posted Contaminated Area into the EOF Count Room.

6.13.12 While at the EOF:

A.

Check and report dosimeter readings to the RPSS.

B.

Perform a whole body frisk (check) prior to proceeding back into the field (if immediately dispatched).

C.

If remaining at the EOF, doff protective clothing (if applicable) and perform a whole body frisk when exiting the posted Contaminated Area (at the Step-Off-Pad).

D.

Perform personnel decontamination (as necessary) under the direction of the Count Room Tech.

6.13.13 Upon completion of sample delivery notify the Field Team Communicator you are ready to be dispatched again.

6.13.14 If dispatched into the field again, obtain additional sampling supplies (e.g. sample bottles, filters, etc.) from the storage cabinet in the Receiving Area and deliver the supplies to the Field Teams (as requested).

6.13.15 When sample courier(s) are no longer required (or when relieved by the next shift) report to the RPSS for debriefing and next shift assignments.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 23 of 32 M/arb 6.14 Prairie Island Off-Site Field Team Driver Instructions 6.14.1 When dispatched by the OSC Coordinator, obtain an electronic dosimeter (either from the OSC or Access Control), respirator corrective lenses, as applicable, and log onto the declared emergency work order. Retain your TLD and electronic dosimeter when departing the plant.

6.14.2 Report to the EOF and check in with the Radiation Protection Support Supervisor (RPSS).

6.14.3 Serve as a driver for the Prairie Island Off-Site Survey Team. The EOF Field Team Communicator will provide instruction on desired sample points.

6.14.4 Request advice from the RPSS regarding procedures or special precautions which should be considered when approaching or searching for the plume.

6.14.5 Provide assistance to the Field Team as requested.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 24 of 32 M/arb 7.0 FIGURES FIGURE 7.1 Gross Iodine Activity Table Using Count Rate Meter with 2 inch Pancake Probe and Silver Zeolite Absorber CFM Flow Min.

Volume 2.5 10.0

=

707500 cc Probe eff. 0.10 3.0 8.3

=

707500 cc Flow CF 1.0 3.5 7.1

=

707500 cc 4.0 6.2

=

707500 cc NOTE: The Ci/cc activity assumes the above conditions.

NCPM Ci Iodine Ci/cc NCPM Ci Iodine Ci/cc NCPM Ci Iodine Ci/cc 100 4.3E-02 6.E-08 800 4.0E-01 6.E-07 6000 3.2E-00 5.E-06 120 5.3E-02 7.E-08 900 4.6E-01 7.E-07 7000 3.8E-00 5.E-06 140 6.0E-02 8.E-08 1000 5.0E-01 7.E-07 8000 4.5E-00 6.E-06 160 7.0E-02 1.E-07 1200 6.0E-01 8.E-07 9000 5.0E-00 7.E-06 180 9.0E-02 1.E-07 1400 7.0E-01 1.E-06 10000 5.6E-00 8.E-06 200 1.0E-01 1.E-07 1600 8.0E-01 1.E-06 12000 6.0E-00 8.E-06 220 1.2E-01 2.E-07 1800 9.0E-01 1.E-06 14000 7.5E-00 1.E-05 240 1.4E-01 2.E-07 2000 1.0E-00 1.E-06 16000 1.0E+01 1.E-05 260 1.5E-01 2.E-07 2200 1.1E-00 2.E-06 18000 1.3E+01 2.E-05 280 1.6E-01 2.E-07 2400 1.2E-00 2.E-06 20000 1.5E+01 2.E-05 300 1.7E-01 2.E-07 2600 1.4E-00 2.E-06 25000 2.5E+01 4.E-05 350 1.8E-01 3.E-07 2800 1.5E-00 2.E-06 30000 3.3E+01 5.E-05 400 2.0E-01 3.E-07 3000 1.6E-00 2.E-06 35000 5.0E+01 7.E-05 450 2.3E-01 3.E-07 3500 1.8E-00 3.E-06 40000 6.0E+01 8.E-05 500 2.6E-01 4.E-07 4000 2.1E-00 3.E-06 45000 1.0E+02 1.E-04 600 3.0E-01 4.E-07 4500 2.5E-00 4.E-06 700 3.6E-01 5.E-07 5000 2.8E-00 4.E-06

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 25 of 32 M/arb FIGURE 7.2 Gas Chamber Table Using Count Rate Meter with 2 inch Pancake Probe and 100cc Poly Gas Chamber NCPM Ci/cc (Xe-133 Equivalent)

NCPM Ci/cc (Xe-133 Equivalent)

NCPM Ci/cc (Xe-133 Equivalent) 50 2.9E-04 100 5.8E-04 1000 5.8E-03 10000 5.8E-02 150 8.6E-04 1500 8.6E-03 15000 8.6E-02 200 1.2E-03 2000 1.2E-02 20000 1.2E-01 250 1.4E-03 2500 1.4E-02 25000 1.4E-01 300 1.7E-03 3000 1.7E-02 30000 1.7E-01 350 2.0E-03 3500 2.0E-02 35000 2.0E-01 400 2.3E-03 4000 2.3E-02 40000 2.3E-01 450 2.6E-03 4500 2.6E-02 45000 2.6E-01 500 2.9E-03 5000 2.9E-02 50000 2.9E-01 Stop Cocks Filter Air Flow Suction Bulb Marinelli

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 26 of 32 M/arb FIGURE 7.3 Gross Liquid Activity Table using Count Rate Meter with 2 inch Pancake Probe and 1000 ML Poly Bottle NCPM Ci/ML 100 1.5E-04 200 2.5E-04 300 3.5E-04 400 4.5E-04 500 5.5E-04 600 6.5E-04 700 7.5E-04 800 8.5E-04 900 9.5E-04 1000 1.0E-03 2000 1.8E-03 3000 2.6E-03 4000 3.4E-03 5000 4.1E-03 6000 4.8E-03 7000 5.5E-03 8000 6.2E-03 9000 6.9E-03 10000 7.6E-03 Detector Position

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 27 of 32 M/arb FIGURE 7.4 Gross Particulate Activity Table using Count Rate Meter with 2 inch Pancake Probe CFM Flow Min.

Volume 2.5 10.0

=

707500 cc Probe eff. 0.10 3.0 8.3

=

707500 cc Flow CF 1.0 3.5 7.1

=

707500 cc 4 filter CF 0.3 4.0 6.2

=

707500 cc Conversion 4.51E-07 Ci/dpm NOTE: The Ci/cc activity assumes the above conditions.

NCPM Ci/cc NCPM Ci/cc NCPM Ci/cc 100 2.E-09 900 2.E-08 6000 1.E-07 120 3.E-09 1000 2.E-08 7000 1.E-07 140 3.E-09 1200 3.E-08 8000 2.E-07 160 3.E-09 1400 3.E-08 9000 2.E-07 180 4.E-09 1600 3.E-08 10000 2.E-07 200 4.E-09 1800 4.E-08 12000 3.E-07 220 5.E-09 2000 4.E-08 14000 3.E-07 240 5.E-09 2200 5.E-08 16000 3.E-07 260 6.E-09 2400 5.E-08 18000 4.E-07 280 6.E-09 2600 6.E-08 20000 4.E-07 300 6.E-09 2800 6.E-08 25000 5.E-07 350 7.E-09 3000 6.E-08 30000 6.E-07 400 8.E-09 3500 7.E-08 35000 7.E-07 500 1.E-08 4000 8.E-08 40000 8.E-07 600 1.E-08 4500 1.E-07 45000 1.E-06 700 1.E-08 5000 1.E-07 800 2.E-08 5500 1.E-07

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 28 of 32 M/arb FIGURE 7.5 On-Site Liquid Sample Locations

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 29 of 32 M/arb FIGURE 7.6 Air Sample Filter Assembly

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 30 of 32 M/arb FIGURE 7.7 Instructions for the GPS Unit Prepare the GPS for use. (Obtaining initial position information)

1.

Turn the GPS on by pressing and holding the POWER (right side top) button for 2-3 seconds.

2.

Press ENTER ( ) button.

3.

Obtain a clear view of the sky and observe the Satellite Status screen as the GPS unit acquires positioning information from the satellites.

NOTE 1:

The process for computing your position the first time may take up to 2 minutes. If the GPS unit is experiencing a problem doing this, you will be prompted with a series of questions to aid your GPS unit in computing its initial position.

NOTE 2:

Pressing the Nav button will allow you to select the navigation screen (Map, Position or Compass) that best suits your needs.

Select a Destination

1.

Press the GOTO button

2.

Select a Point of Interest (POI) Note: The Pre-Determined Offsite Survey points have been created as POIs and programmed into the GPS. Use the arrow joystick to highlight the desired Survey point and press ENTER. The information at the bottom of the screen is the bearing and distance to the POI from your present location.

Go to your Destination As you travel you will notice that the GPS unit will continue to update your position as well as providing you the necessary details to arrive at your destination.

Navigational Screens - Press the Nav button allows you to cycle through the navigation screens.

The MAP screen displays your present position using a map of the area as the background. You can zoom in or out using the zoom in/out buttons to show just the portion of the map you need. The Map screen also displays an indication of where you have been as a dashed line as well as a visual indicator of a route you may be navigating on.

The POSITION screen displays your present position (using the coordinate system),

your elevation, accuracy, date, time, trip odometer and battery life. The trip odometer can be reset by 1) pressing the Menu button. 2) Highlight the Reset Trip. 3) Press the Enter button.

The COMPASS screen uses a graphical compass to provide you with directional information. An icon outside the compass ring indicates your destination and the compass points in the direction are heading.

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 31 of 32 M/arb FIGURE 7.8 Forms Utilized in this Procedure

1. 5790-410-02 OUT-OF-PLANT SURVEY CHECKLIST

2. 5790-410-01 EMERGENCY SAMPLE RESULTS LOG

3. 5790-410-03 GROUND DEPOSITION SAMPLE RESULTS LOG

MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE:

OUT-OF-PLANT SURVEYS Revision 24 Page 32 of 32 M/arb FIGURE 7.9 Summary of Significant Changes Section Change and Reason for Change 4.0 Added a paragraph describing the use of portable electronic data devices and the use of the Emergency Electronic Information System (EEIS).

5.10 Added information on the use of EEIS by the field teams.

6.0 Added a NOTE for survey data entry into EEIS.

RE-ENTRY Revision 5 A.2-601 MONTICELLO NUCLEAR GENERATING PLANT TITLE:

Page 1 of 7 I/arb Approval:

INFORMATION USE S Procedure should be available, but NOT necessarily at the work location.

S Procedure may be performed from memory.

S User remains responsible for procedure adherence.

PCR 01271897

RE-ENTRY Revision 5 A.2-601 MONTICELLO NUCLEAR GENERATING PLANT TITLE:

Page 2 of 7 I/arb EMERGENCY PLAN IMPLEMENTING PROCEDURE - TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE 3

2.0 APPLICABILITY 3

3.0 ORGANIZATION AND RESPONSIBILITIES 3

4.0 DISCUSSION 4

5.0 PRECAUTIONS 4

6.0 INSTRUCTIONS 5

6.1 Re-entry Team Activation 5

6.2 Re-Entry Activities 5

6.3 Re-entry Team Debriefing 6

7.0 FIGURES 7

7.1 Summary of Significant Changes 7

RE-ENTRY Revision 5 A.2-601 MONTICELLO NUCLEAR GENERATING PLANT TITLE:

Page 3 of 7 I/arb 1.0 PURPOSE This procedure provides instructions and guidelines for re-entry into areas of the plant or plant site, following an emergency condition, when radiological and/or environmental conditions are unknown.

2.0 APPLICABILITY 2.1 An emergency condition at Monticello Nuclear Generating Plant has resulted in the evacuation of the plant site or affected areas of the plant.

AND 2.2 The magnitude and/or nature of the radiological conditions in the affected areas is unknown.

3.0 ORGANIZATION AND RESPONSIBILITIES 3.1 The Emergency Director is responsible for:

3.1.1 Initiating re-entry activities.

3.2 Radiation Emergency Coordinator is responsible for:

3.2.1 The organization, Size, and composition of the Re-entry Team.

3.2.2 Radiological aspects for support of Re-entry Teams.

3.3 The OSC Coordinator and Radiation Protection Coordinator are responsible for:

3.3.1 Implementation of this procedure including briefing re-entry teams dispatched from the OSC. Briefing should include discussion of known hazards (i.e., radiological, environmental, etc.) and possible risk.

3.3.2 Coordination of re-entry activities as directed by the TSC.

3.4 Re-entry Team Members are responsible for:

3.4.1 Performing re-entry activities under the direction of the OSC.

3.5 The Radiation Protection Group is responsible for:

3.5.1 Providing radiological surveys, emergency exposure control and personnel to support re-entry efforts.

RE-ENTRY Revision 5 A.2-601 MONTICELLO NUCLEAR GENERATING PLANT TITLE:

Page 4 of 7 I/arb 4.0 DISCUSSION When re-entry operations are to be conducted in hazardous radiation areas, emergency exposure criteria will be in accordance with the guidelines established in EPIP A.2-401 (EMERGENCY EXPOSURE CONTROL). Only the Emergency Director or the Radiation Emergency Coordinator are authorized to permit emergency exposures.

The Radiation Protection Coordinator will direct the activities of the team via radio after the team has been dispatched from the Control Point IAW. Part 6.2 of this procedure.

5.0 PRECAUTIONS 5.1 Re-entry teams SHALL consist of a minimum of two individuals, at least one of which is qualified in radiation protection. The team members should remain in visual/voice contact at all times when in the affected area.

5.2 If there is reason to believe that the atmosphere within the affected area is toxic or an oxygen deficiency exists, Self-Contained Breathing Apparatus (SCBA) respiratory protection SHALL be used. In this case, one or more individuals should be assigned to remain outside the affected area, standing by in the appropriate protective clothing, to effect search and rescue if it becomes necessary.

5.3 Appropriate protective clothing should be specified, for re-entry team members, on the basis of suspected conditions. If a reasonable estimation of radiological conditions in the affected areas cannot be made, protective clothing with the highest protection factor should be specified.

5.4 If at any time during re-entry observed dose rates exceed a predetermined level, if the exposure of re-entry team members approaches a predetermined amount or if radiation monitoring instruments appear to be malfunctioning the re-entry team should be directed to retreat to a safe area.

5.5 Mechanical or Robotic Equipment should be used whenever possible for entry into unknown environs.

5.6 Lifelines should be used in areas containing heavy smoke or in areas where visual contact between team members is impossible or hampered.

5.7 Re-entry team members should be selected from volunteers, as these operations could involve high exposure and risk.

RE-ENTRY Revision 5 A.2-601 MONTICELLO NUCLEAR GENERATING PLANT TITLE:

Page 5 of 7 I/arb 6.0 INSTRUCTIONS 6.1 Re-entry Team Activation 6.1.1 Initiate Form 5790-601-1 (RE-ENTRY CHECKLIST).

6.1.2 Utilize all pertinent data available including area and process radiation monitors, survey data, visual observations, observations made by previous Re-entry Teams and any other source of information applicable to determine:

A.

Which plant areas are affected.

B.

Conditions in affected areas (hazards, radiological, temperature, etc.).

C.

Actions which should be taken to reduce the potential hazards to the Re-entry Team prior to or during the re-entry.

6.1.3 Utilize any mechanical or robotic equipment available to assist the re-entry team in performing their task.

6.1.4 Assemble the appropriate Re-entry Teams.

6.1.5 Ensure that preparation for the Re-entry Teams are complete, i.e.,

personnel are properly clothed, badged, respiratory protection is issued per Form 5790-601-1, and exposure is controlled in accordance with A.2-401.

6.1.6 Use portable communication gear allowing continuous contact with the OSC Coord/RPC.

6.2 Re-Entry Activities CAUTION Complete an RWP Checklist prior to dispatching the team. Prescribe the appropriate radiological precautions and ensure search and rescue begins immediately.

NOTE: Two survey meters should be used if radiation levels are expected to exceed 10R/hr.

6.2.1 Re-entry Team should continuously observe the portable radiation instrument while approaching the affected area.

6.2.2 A continuous dialogue should be maintained between the Re-entry Team and the OSC concerning dose rates and conditions observed.

RE-ENTRY Revision 5 A.2-601 MONTICELLO NUCLEAR GENERATING PLANT TITLE:

Page 6 of 7 I/arb 6.2.3 Periodically, or when requested, the Re-entry Team SHALL read and report dosimeter readings.

6.2.4 If at anytime during the re-entry, observed dose rates exceed a predetermined level or if the exposure of team members approaches a predetermined amount, the Re-entry Team SHALL return to a safe area.

6.2.5 If exposure or dose rates are acceptable, direct the Re-entry Team to complete the functions assigned to it (e.g. surveys, inspections, repairs, valve operations, etc.).

6.2.6 Upon completion of work, the Re-entry Team SHALL return to a safe area (control point).

6.3 Re-entry Team Debriefing 6.3.1 Direct Radiation Protection Group to assist the team members at the control points assuring an accurate dose assessment and proper removal of protective clothing and respiratory protection equipment.

6.3.2 Direct the Radiation Protection Group to complete the dose assessment for team members in accordance with A.2-401.

6.3.3 Debrief the team and ensure that all follow-up actions are completed.

6.3.4 Inform the Emergency Director/Emergency Manager of the re-entry teams findings and survey results. Determine appropriate access control measures for entry into the affected area and make recommendations for restoring access to the affected area.

RE-ENTRY Revision 5 A.2-601 MONTICELLO NUCLEAR GENERATING PLANT TITLE:

Page 7 of 7 I/arb 7.0 FIGURES FIGURE 7.1 Summary of Significant Changes Section Change and Reason for the Change 3.3.1 Added Re-entry team briefing items.

6.2.4 and 6.2.6 Removed Team Leader and replaced with Re-entry Team.

Figure 7.1 Added Summary of Significant Changes.