Text

Emergency Plan Implementing Procedures
	ML031130570
Person / Time
Site:	Monticello
Issue date:	04/14/2003
From:	Denise Wilson; Nuclear Management Co
To:	; Document Control Desk, Office of Nuclear Security and Incident Response
References
	L-MT-03-026
	Download: ML031130570 (67)
	v • d • e

Monticello Nuclear Generating Plant Committed to Nuclear Excellence Operated by Nuclear Management Company, LLC L-MT-03-026 April 14, 2003 10 CFR 50, Appendix E Section V U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT DOCKET 50-263 LICENSE No. DPR-22 EMERGENCY PLAN IMPLEMENTING PROCEDURES Furnished with this letter is a revision to the Monticello Nuclear Generating Plant Emergency Plan Implementing Procedures. The following procedures are revised:

Procedure Procedure Title Revision A.2-204 Off-Site Protective Action Recommendations 16 A.2-302 Activation of the Assembly Points 11 A 2-807 Off-Site Dose Assessment and Protective Action Recommendations 9 Please post changes in your copy of the Monticello Nuclear Generating Plant Emergency Plan Implementing Procedures. Superseded procedures should be destroyed.

These revisions do not reduce the effectiveness of the Monticello Nuclear Generating Plant Emergency Plan.

Please contact John Fields at 763-295-1663 if you require further information.

David L. Wilson Site Vice President Monticello Nuclear Generating Plant CC Regional Administrator, USNRC, Region IlIl (with two copies of enclosure)

Project Manager, USNRC, NRR (w/o enclosure)

NRC Resident Inspector (w/o enclosure, EPIP dist. by Monticello Document Control)

Minnesota Dept. of Commerce (w/o enclosure)

Enclosure 2807 West County Road 75

Monticello, Minnesota 55362-9637 Telephone: 763-295-5151

Fax. 763-295-1454

MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SITE PROTECTIVE ACTION Revision 16 RECOMMENDATIONS Page 1 of 22 EMERGENCY PLAN IMPLEMENTING PROCEDURE - TABLE OF CONTENTS SECTION PiAGE 1.0 PURPOSE ........................................................ 2 2.0 -APPLICABILITY ................................................... 2 3.0 ORGANIZATION AND RESPONSIBILITIES ........................... 2 4.0 DISCUSSION. ..................................................... 2 5.0 PRECAUTIONS. ................................................... 2 6.0 INSTRUCTIONS ................................................... 4 6.1 Initial PARs for General Emergency Classification ................ 4 6.2 PARS for Sherco Plant ........................................ 5 6.3 Off -site PARs Based on Projected Doses ........................ 6 6.4 Protective Action Recommendation for Liquid Releases ........... 8 7.0 FIGURES ......................................................... 9 7.1 Definitions Related to Protective Actions Recommendations. 9 7.2 Discussion of Protective Action Recommendation ................ 12 7.3 Protective Action Guidelines (PAGs) ............................ 16 7.4 Emergency Worker Exposure Limits ............................ 18 7.5 Transport Time and Monthly Average Flowrates .................. 19 7.6 Liquid Release Protective Action Criteria ........................ 21 7.7 Forms Utilized in Procedure ................................... 22 Prepared B 1:( O l Reviewed By: )j j 5 C OC Review Req'd: YES meeting Number: -z 67 Date: 3 /.

Approved By: / Date:

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This revision incorporates Volume F Memos- K L 3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated: C3-RespSupv. EP lAssocRef. A2 (I'}: N IFreq 11rv/

ARMS A2-204 Doc Type 1060 lAdmin Initials: Date:;2,,L I/plr

MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SITE PROTECTIVE ACTION Revision 16 RECOMMENDATIONS Page 2 of 22 1.0 PURPOSE The purpose of this procedure is to provide instructions and guidelines to the Emergency Director (ED) and Radiological Emergency Coordinator (REC) for the formulation of off-site protective action recommendations for the general public during the early phase of an emergency.

2.0 APPLICABILITY 2.1 An emergency condition corresponding to an Unusual Event classification or higher has been declared at the MNGP, and 2.2 A release of radioactive material has occurred, is occurring, or is likely to occur.

3.0 ORGANIZATION AND RESPONSIBILITIES 3.1 The Emergency Director (Duty Shift Manager or designated Emergency Director) is responsible for:

3.1.1 Implementation of this procedure if the REC position is not staffed.

3.1.2 Directing off-site communications with State and Local authorities and Federal agencies (before turnover to the EOF).

3.1.3 Approving off-site Protective Action Recommendations (PARs) to State and/or County authorities (prior to turnover of this responsibility to the Emergency Manager).

3.2 The Radiological Emergency Coordinator is responsible for:

3.2.1 Implementation of this procedure.

3.2.2 Making off-site Protective Action Recommendations (PARs) to State and/or County authorities (prior to turnover of this responsibility to the Radiation Protection Support Supervisor).

4.0 DISCUSSION 4.1 For definitions related to PARs, see Figure 7.1 4.2 For general discussion of PAR, see Figure 7.2 5.0 PRECAUTIONS 5.1 Declaration of a General Emergency requires immediate Protective Action Recommendations (PARs) to off-site agencies. Under these circumstances, NO dose projections are required for formulating the initial offsite protective action recommendation.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SITE PROTECTIVE ACTION - Revision 16 RECOMMENDATIONS Page 3 of 22 5.2 Implementation of protective actions for off-site areas is the responsibility of the State of Minnesota. If it is determined by the Emergency Director that immediate protective actions are required, and the State EOC is not activated, the recommendation should be made directly to the local authorities (i.e.,

Wright and Sherburne Counties). Upon activation of the State EOC all off-site protective action recommendations should be made to the State.

5.3 The protective actions outlined in this procedure are limited to actions for minimizing the exposure of the public to external and internal radiation exposure from plume passage, inhalation of the radioactive plume and from internal exposure from drinking water during the early phase of an emergency.

Other protective actions for minimizing public exposure via the ingestion pathway will be determined and implemented by the State.

5.4 The transmission of Off-site Protective action Recommendations to the State EOC (State Duty Officer and Counties if the State EOC is not activated)

SHALL be completed within 15 minutes of the PAR authorization.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SITE PROTECTIVE ACTION Ievision 16 RECOMMENDATIONS Page 4 of 22 6.0 INSTRUCTIONS

.e....... ..

No dose projections are required when making initial PAR during GENERAL EMERGENCY CONDITIONS.

6.1 Initial PARs for General Emergency Classification 6.1.1 Initiate Form 5790-102-02 (MONTICELLO EMERGENCY NOTIFICATION REPORT FORM).

A. Complete Section 1.4 recommending an evacuation of a 2 mile radius and 5 miles downwind and advise the remainder of the plume EPZ to go indoors to monitor EAS broadcasts.

B. Determine which geopolitical subareas are affected by referring to the Sector-Subarea Conversion Table on Form 5790-102-02.

C. Ensure completion of Parts 1.0 and 2.0 of Form 5790-102-02 and submit the completed form to the ED for approval.

6.1.2 Ensure transmission of the recommendations, via telephone and telecopy, to the State EOC (State Duty Officer, Wright and Sherburne Counties if the State EOC is not activated) in accordance with EPIP A.2-501 (COMMUNICATIONS DURING AN EMERGENCY).

6.1.3 Approximately 30 minutes after making the recommendation, contact the State Planning Chief or State Duty Officer if State EOC is not activated to determine what protective actions are actually being implemented. Continue to track the status of the protective action until completely implemented and indicate the completion status on the Radiation Protection Status Board.

6.1.4 Update the Emergency Director and TSC personnel (if activated and staffed) on the status of off-site Protective Action implementation.

6.1.5 After making initial Protective Action Recommendations (at the General Emergency Class) continually assess plant conditions and off-site dose projection results. Make subsequent off-site protective action recommendations based on projected off-site doses using the Protective Action Guidelines (PAGs) listed in FIGURE 7.3.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SITE PROTECTIVE ACTION _ evision 16 RECOMMENDATIONS Page 5 of 22 6.2 PARS for Sherco Plant NOTE: To safely shutdown the Sherco Plant requires 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the unit(s) are tripped.

6.2.1 Throughout the event the REC (or Assistant REC) should review off-site projected doses and affected Sectors (Subareas) to determine if the Sherco Plant is or will be in the affected area.

NOTE: The Sherco Plant is located in the 5N subarea.

6.2.2 Formulate protective action recommendations for the Sherco Plant as follows:

A. Recommendations based on Projected Dose (whole body):

1. > 500 mrem (TEDE) - recommend evacuation of non-essential personnel from the Sherco site and shelter essential plant personnel during plant operation.

2. > 1 Rem (TEDE) - recommend shutdown of the Sherco Plant(s). Immediate evacuation of non-essential personnel and sheltering of essential personnel during normal plant shutdown.

3. > 5 Rem (TEDE) - recommend immediate evacuation of non-essential personnel and sheltering of essential personnel during emergency plant shutdown. Evacuate all personnel immediately after plant shutdown.

B. Recommendations based on General Emergency:

1. If evacuation is implemented (in 5N) recommend evacuation of all non-essential personnel and sheltering of essential Sherco personnel. Recommend immediate initiation of plant shutdown.

6.2.3 If protective actions are required for the Sherco Plant, discuss the recommendations with the Emergency Director.

6.2.4 Monitor the progress of protective action implementation (at Sherco) to determine when they are completed.

6.2.5 Indicate any PARs recommended (and implemented) for the Sherco Plant on the RP Status Board in the TSC.

6.2.6 Advise the Emergency Director if conditions change (e.g., significant increase in release rate) which could change the protective action recommendations for the Sherco Plant.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SITE PROTECTIVE ACTION 3evision 16 RECOMMENDATIONS Page 6 of 22 6.3 Off-site PARs Based on Projected Doses

.UCAUTIN.~.:

Do not delay recommending off-site protective actions while waiting for off-site monitoring results to verify the accuracy of the dose projection model.

Do not delay recommending off-site protective actions while trying to resolve questionable data (MIDAS Data or Field Team Data).

6.3.1 Continuously review dose projection data (4 day integrated maximum TEDE and Thyroid CDE) on Form 5790-102-03 (EMERGENCY NOTIFICATION FOLLOW-UP MESSAGE) and compare with the Protective Action Guidelines in Figure 7.3. If an updated PAR, based on dose projections is required, proceed to Step 6.3.2. Continuously review meteorological data (wind direction and wind speed) on Form 5790-102-03 and determine the affected sectors. If an updated PAR, based on meteorological data is required, proceed to Step 6.3.2.

6.3.2 Initiate Form 5790-204-01 (MONTICELLO OFF-SITE PROTECTIVE ACTION RECOMMENDATION CHECKLIST) and complete the airborne release section.

6.3.3 Using current meteorological data (i.e., wind direction and wind speed), determine the affected Sectors, Geopolitical Subareas (using v-page 2 of Form 5790-204-01), population centers within the affected area and estimated plume arrival time in those areas.

6.3.4 Based on plant conditions, estimate the duration of the existing release or potential release.

6.3.5 Using available weather forecast data, evaluate the potential for wind direction and wind speed changes during the estimated duration of the release (and after). Determine what effect potential wind direction and wind speed changes would have on the affected areas identified in 6.3.3.

NOTE: Weather forecast information may be obtained from the National Weather Service. Refer to the Monticello and Prairie Island Emergency Preparedness Telephone Directory for telephone numbers.

NOTE: If data used in the determination of the PAR is/was questionable, attempt to verify the data. DO NOT delay the issuance of the PAR. If after verification of questionable data a PAR revision is necessary, complete section 6.3 of this procedure.

6.3.6 If based on dose projections or field team data a PAR beyond the 10 mile EPZ is necessary, immediately contact the State Planning Chief to inform them of this condition. Document the PAR recommendation in the comments section of Form 5790-204-01 and attach a copy of the supporting Follow-up Message.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SITE PROTECTIVE ACTION Revision 16 RECOMMENDATIONS Page 7 of 22 6.3.7 Indicate the recommendations on page 3 of Form 5790-204-01.

Indicate the recommendation in terms of Sectors and Subareas by completing and circling the applicable information as follows:

A. Identify the affected keyhole by selecting a 3600 out to 2 or 5 miles. Determine the affected Sectors by including both Sectors on either side of the downwind Sector (two Sectors on either side should be included if the downwind direction is on a Sector line).

Record the 3 (or 4) affected Sectors on page 3 of the Monticello PAR Checklist.

B. Identify the affected geopolitical subareas using the Sector-Subarea Conversion Chart (page 2 of Form 5790-204-01) and circle the affected subareas on the PAR Checklist.

6.3.8 Submit the completed page 3 of Form 5790-204-01 to the Emergency Director for approval. Review and discuss the recommendations with the Emergency Director as necessary.

NOTE: Prior to activation of the State EOC, protective action recommendations should be made directly to the State Duty Officer and Wright and Sherburne Counties (EOCs if activated). The State Duty Officer will coordinate the EAS message and PANs activation with counties. Once the State EOC is activated, all protective action recommendations SHALL be made directly to the State authorities.

6.3.9 The Emergency Director (or REC) should direct an Emergency Communicator to transmit the approved Monticello Off-Site Protective Action Recommendation Checklist, to the State EOC (Wright and Sherburne County EOCs only if the State EOC is not yet activated) in accordance with EPIP A.2-501.

6.3.10 When notified by the Emergency Communicator that the transmittal of the protective action recommendation has been made to the State Planning Chief (if State EOC is activated) or the State Duty Officer, Wright County and Sherburne County (if State EOC is not activated),

contact either the State Planning Chief or the State Duty Officer, Wright County and Sherburne County. Discuss the recommendations and explain the basis of the recommendations.

6.3.11 Approximately 30 minutes after making the recommendation, contact the State Planning Chief or State Duty Officer prior to State EOC activation, to determine what protective actions are actually being implemented. Continue to track the status of the protective action until completely implemented and indicate the completion status on the Radiation Protection Status Board.

6.3.12 If, as a result of continuing assessment, dose projection results or meteorological conditions change significantly, re-evaluate the previously implemented protective actions and, if necessary, update the protective actions by issuing another recommendation.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SITE PROTECTIVE ACTION Revision 16 RECOMMENDATIONS Page 8 of 22 6.4 Protective Action Recommendation for Liquid Releases 6.4.1 Initiate Form 5790-204-01 and complete the Liquid Release Section.

6.4.2 Obtain the isotopic analyses of liquid samples taken at the Discharge Canal or release point.

NOTE: During a liquid release, samples may be taken at the discharge structure, mid-canal sample station, canal out-fall to the river, or as near the source of the release as possible. To ensure samples are representative of the material being released to the river, the Canal Sample Station is the preferred sampling location.

6.4.3 Determine the present Discharge Canal flow rate and river flow rate at the plant (refer to the applicable plant computer point for flow rates).

6.4.4 Determine the river flow rate at either the Coon Rapids Dam or the Minneapolis-St. Paul water intakes by contacting the Minneapolis Water Department (refer to the Monticello and Prairie Island Nuclear Emergency Telephone Directory for telephone numbers).

6.4.5 Using the curve RIVER FLOW vs TIME curve (FIGURE 7.5) estimate the time of release arrival at the Minneapolis-St. Paul water intakes based on current, actual river flow (if actual river flow is not available, use the monthly average river flow in FIGURE 7.5).

6.4.6 Using the MIDAS User Manual Procedures access the MIDAS liquid release model. Enter the isotopic and other applicable release data.

6.4.7 Using the MIDAS Liquid Release Dose Assessment printout, formulate off-site protective action recommendations in accordance with the guidelines in FIGURE 7.6.

6.4.8 Indicate the recommendations on page 3 of Form 5790-204-01 and submit the completed form for Emergency Director approval.

6.4.9 Transmit the recommendations to the State Planning Chief (State EOC if activated) in accordance with EPIP A.2-501.

6.4.10 Contact the State Planning Chief (in the State EOC if activated) to explain the basis for the recommendations.

6.4.11 Approximately 30 minutes after making the recommendation, contact the State Planning Chief to determine what protective actions are actually being implemented. Continue to track the status of the protective action until completely implemented.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SITE PROTECTIVE ACTION Revision 16 RECOMMENDATIONS Page 9 of 22 7.0 FIGURES FIGURE 7.1 Definitions Related to Protective Actions Recommendations

1. Affected Area is any area where radiation emanating from a plume, or from material deposited from the plume, can be detected using field instruments (also known as the footprint).

2. Cloudshine is radiation from radioactive materials in an airborne plume.

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

4. 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.

5. Dose equivalent means the product of the absorbed dose in tissue, quality factors, and all other necessary modifying factors at the location of interest.

6. 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.

NOTE: Deep Dose Equivalent (DDE) is considered equivalent to EDE if the exposure is uniform.

7. Emergencv Planninq Zone (EPZ) is a defined area which facilitates emergency planning by State and local authorities to ensure that prompt and effective actions are taken to protect the public in the event of a radioactive release from the plant. The EPZ is defined for two areas:

A. Plume Exposure Pathway (10 Mile EPZ) is the 10 mile, 3600 radius around the plant in which the primary concern is short-term exposure from the plume. The principal sources of exposure in this area are 1) whole body external exposure to gamma radiation from the plume and deposited material from the plume, and 2) internal exposure from inhaled material from the plume.

B. Inqestion Exposure Pathway (50 Mile EPZ) is a 50 mile, 360° radius around the plant in which the principal exposure would be from ingestion of contaminated water or foodstuffs (such as milk or fresh vegetables).

8. Evacuation is the removal of people from an area to avoid or reduce high-level, short term exposure, from a plume or from deposited activity.

9. Geopolitical Subareas are subarea within the 10 Mile EPZ that are defined by predetermined geographic and/or political boundaries.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SITE PROTECTIVE ACTION revision 16 RECOMMENDATIONS Page 10 of 22

10. Groundshine is radiation exposure caused by radioactive materials deposited on the ground.

11. Ingestion Pathway Projected Dose is the projected CEDE (ICRP-30) from consuming contaminated foodstuffs.

12. Keyhole Area an area within the 10 Mile EPZ defined by a 3600 radius out to a specified distance of 2 or 5 miles and continuing in the downwind direction in 3 or 4 Sectors.

13. Plume Projected Dose refers to future calculated doses from plume submersion, plume shine, plume inhalation and 4 days of ground deposition exposure.

14. Protective Action is an action taken to avoid or reduce a projected dose.

15. Protective Action Guide (PAG) refers to a dose (or commensurate dose rate) which warrants protective actions.

16. Public Alert and Notification System (PANS) is the system used to alert the public within the 10 Mile EPZ of an emergency condition at the plant. Once alerted, the public would turn to local commercial media broadcast messages for specific protective action instructions. The PANS consists of the following systems:

A. Fixed sirens for 100% coverage throughout the 5 mile EPZ and in population centers between 5 and 10 miles.

B. Local law enforcement emergency vehicles with sirens and public address capability driving route alerting in the 5 to 10 mile areas not covered by fixed sirens.

C. National Oceanic and Atmospheric Administration (NOAA) alert radios in institutional, educational, and commercial facilities.

D. The Emergency Alert System (EAS) which accesses local television and radio stations.

17. Recovery is the process of reducing radiation exposure rates and concentration of radioactive material in the environment to levels acceptable for unconditional occupancy.

18. Release is the release of radioactive material to the environment attributable to the event.

19. Relocation Proiected Dose is the projected effective committed dose from 1 year of exposure to radioactive material deposited as fallout from a plume, including whole body exposure to gamma radiation (groundshine), and internal dose from inhalation of resuspended material, but excluding internal dose from consuming contaminated foodstuffs.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SITE PROTECTIVE ACTION, 3evision 16 RECOMMENDATIONS Page 11 of 22

20. Return refers to people permanently reoccupying their normal residence within an area that was evacuated during the emergency condition.

21. Re-entry refers to temporary entry into a restricted (evacuated) area under controlled conditions.

22. Secondary Evacuation refers to relocating people from areas to avoid or reduce relocation projected dose.

23. Sector is one of 16, 22.50 sectors around the plant which compose the 10 Mile EPZ.

24. Sheltering provides radiation protection from an airborne plume and/or deposited radioactive materials. Sheltering also ensures effective public notification, via media, should the need for evacuation occur.

25. Total Effective Dose Equivalent (TEDE) is the sum of external EDE and CEDE.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SITE PROTECTIVE ACTION Ievision 16 RECOMMENDATIONS Page 12 of 22 FIGURE 7.2 Discussion of Protective Action Recommendation The following is a discussion of the various Protective Action Recommendations (PARs) that could be made to off-site authorities. The Protective Action Guidelines (PAGs) listed are derived from EPA guidelines (EPA 400).

A. NO PROTECTIVE ACTIONS The recommendation for no protective actions is self-explanatory and is appropriate when projected plume doses do not exceed 1000 mrem (TEDE) or 5000 mrem (CDE) thyroid dose. For liquid releases, no protective actions are warranted if the concentration in raw river water at outflow of discharge canal is less than the concentration listed in 10CFR20.1001-20.2402, Appendix B, Table 2, Column 2 (ODCM-04.01 (LIQUID EFFLUENT CALCULATIONS), Table 1).

B. EVACUATION Evacuation is the movement of a population out of an area in order to reduce or eliminate direct or indirect radiation exposure. Timely evacuation of the population is the most effective protective action.

Initial PARs for a General Emergency involving loss of physical control or core damage are based on NRC Response Technical Manual RTM-93, Vol 1, Rev. 3,Section I.

Immediate evacuation of the general public is justified without dose projection.

EPA 400 indicates that evacuation of the general public will usually be justified when the projected dose to an individual is greater or equal to 1000 mrem TEDE (or 5000 Thyroid CDE). At these dose levels, the risk avoided due to the radiation exposure is usually much greater than the risk from evacuation itself.

Using the projected dose criteria stated above, Monticello Nuclear Generating Plant (MNGP) should recommend evacuation to the State. In turn, they will independently assess and implement protective actions based on our recommendation, their independent assessment, and current off-site evacuation constraints.

C. CLOSURE OF WATER INTAKES Water Intakes PAG: Concentration in raw river water exceeds the value listed in 10CFR20.1001-20.2402, Appendix B, Table 2, Column 2 (ODCM-04.01, Table 1).

Closure of the water intakes is an appropriate recommendation in the case of a liquid release to the river which is expected to result in river water concentrations exceeding the MPC limits for unrestricted areas.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SITE PROTECTIVE ACTION IRevision 16 RECOMMENDATIONS Page 13 of 22 FIGURE 7.2 Discussion of Protective Action Recommendation (Cont'd)

D. SECONDARY EVACUATION Relocation PAG (in mrem): 2000 (TEDE)

To avoid social and family disruption and the complexity of implementing separate PAGs for individual members of the population, the relocation PAG may be applied for all members of the population. While the relocation PAG is based on projected doses to adults, infant relocation projected doses are not more than two times higher than the adult projected dose.

Based on EPA 400 PAGs, MNGP should recommend relocation of the general public from affected areas not previously evacuated when the projected dose is greater or equal to 2000 mrem CEDE from exposure or intake during the first year. This projected dose includes doses from external radiation, and inhalation of resuspended materials.

E. RETURN Return is allowed at levels below the secondary evaluation PAG (2000 mrem TEDE).

The decision to return segments of the public from previously evacuated areas will be determined by appropriate off-site agencies. Various cautions and dose reduction techniques will be assessed and, if necessary, communicated to the people upon their return.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SITE PROTECTIVE ACTION Ievision 16 RECOMMENDATIONS Page 14 of 22 FIGURE 7.2 Discussion of Protective Action Recommendations (Cont'd)

F. DESIGNATION OF THE AFFECTED PROTECTIVE ACTION AREA The designation of the affected protective action area depends on the nature and extent of the incident and existing meteorological conditions. The area will be described by designating an affected keyhole shaped area and the affected geopolitical subareas within the EPZ.

a Affected Keyhole Area The affected keyhole area should resemble a keyhole consisting of a 3600 area surrounding the plant out to a distance of 2 or 5 miles and continuing in the downwind direction out to a distance determined by the PAGs. The affected downwind portion of the keyhole should include 1 sector on either side of the affected sector (i.e., total of 3 sectors). If the downwind direction is on a sector line then 2 sectors on each side of the affected sector should be included (i.e.,

total of 4 sectors).

b Affected Geopolitical Subareas Geopolitical subareas are subareas of the 10 mile EPZ defined by predetermined geographic and/or political boundaries. The affected geopolitical subareas are defined by any and all subareas that intersect the affected keyhole area.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SIT PROTECTIVEACTION Revision 16l RECOMMENDATIONS Page 15 of 22 FIGURE 7.2 Discussion of Protective Action Recommendations (Cont'd)

G. (EXPOSURE PATHWAYS, Incident Phases, and Protective Actions POTENTIAL EXPOSURE PATHWAYS PROTECTIVE ACTIONS AND INCIDENT PHASES

1. External radiation from facility Sheltering Evacuation Control of access

2. External radiation from plume Sheltering Evacuation EA LY Control of access

3. Inhalation of activity in plume Sdelteringi f bl iodi Evacuation Control of access

4. Contamination of skin and Sheltering clothes INTE MEDIATE Evacuation Decontamination of persons

5. External radiation from ground Evacuation deposition of activity Relocation L;TE Decontamination of land TEand property

6. Ingestion of contaminated food Food and water controls and water

7. Inhalation of resuspended Relocation activity Decontamination of land and property NOTE 3: Based on EPA 400-R-92-001, May 1992 NOTE 4: The use of stored animal feed and uncontaminated water to limit the uptake of radionuclides by domestic animals in food chain can be applicable to any of the phases.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SITE PROTECTIVE ACTION Revision 16 RECOMMENDATIONS Page 16 of 22 FIGURE 7.3 Protective Action Guidelines (PAGs)

PAG VALUES' RECOMMENDED COMMENTS PROTECTIVE ACTIONS Less than None required The State may choose

<1 REM (TEDE) to implement sheltering at their discretion. No recommendations are required from MNGP.

Greater than Recommend The State may chose WHOLE BODY 2 >1 REM (TEDE) evacuation of the to implement sheltering PROJECTED general public. of the general public ROJ ED up to 5 REM (TEDE) or special population groups up to 10 REM (TEDE) if immediate evacuation is not practicable due to off-site constraints.

No sheltering recommendations are required from MNGP.

Less than None required The State may choose

<5 REM (CDE) to implement sheltering at their discretion. No recommendations are THYROID3 required from MNGP.

(CDE) Greater than Recommend The State may choose PROJECTED >5 REM (CDE) evacuation of the to implement sheltering DOSE general public. of the general public if immediate evacuation is not practicable due to off-site constraints.

No sheltering recommendations are required from MNGP.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SITE PROTECTIVE ACTION fevision 16 RECOMMENDATIONS Page 17 of 22 FIGURE 7.3 Protective Action Guidelines (PAGs) (Cont'd)

PAG VALUES1 RECOMMENDED COMMENTS PROTECTIVE ACTIONS SKIN 4 Less than None required The State may choose (CDE) <50 REM (CDE) to implement simple PROJECTED personal protective DOSE actions (washing). No recommendations are required from MNGP.

Greater than Recommend The State may choose

>50 REM (CDE) evacuation of the to implement sheltering general public of the general public or simple personal protective actions if immediate evacuation is not practicable.

NOTE 1: Protective Action Guides are based on EPA 400-R-92-001, May 1992.

NOTE 2: TEDE = Total Effective Dose Equivalent; is the sum of the effective dose equivalent from exposure to external source and the Committed Effective Dose Equivalent incurred from all significant inhalation pathways during the Early Phase.

NOTE 3: CDE = Committed Dose Equivalent to the Thyroid from radioiodine.

NOTE 4: Committed Dose Equivalent to the skin from exposure to beta radiation from radioiodines and particulates.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SITE PROTECTIVE ACTION Ievision 16 RECOMMENDATIONS Page 18 of 22 FIGURE 7.4 Emergency Worker Exposure Limits EXPOSURE LIMIT1 EMERGENCY ACTIVITY' COMMENTS 5 REM (TEDE)( 2 )(3 ) All emergency activities This dose limit applies when a lower dose is not practicable through application of ALARA practices.

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

2

> 25 REM (TEDE)( )( ) 3 Life saving or protection of Doses in excess of 25 REM large populations 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 400-92-001, 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/or extremities should be limited to 10 times the value listed.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SITE PROTECTIVE ACTION Revision 16 RECOMMENDATIONS Page 19 of 22 FIGURE 7.5 Transport Time and Monthly Average Flowrates 80000 = I 70000- -I I-60000 -

50000 -

40000 30000'--

U-C-, 20000 - -1 I 0

-J IL w 10000I Sr 8000 w 7000 - -

60000-500 I 4000 - - -

30000-----

2000 --- -

100 0--I 60 50 40 30 20 10 TIME (HRS) TO MINNEAPOLIS INTAKE (MULTIPLY BY .9 FOR ST PAUL INTAKE)

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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SITE PROTECTIVE ACTION Revision 16 RECOMMENDATIONS Page 20 of 22 FIGURE 7.5 Transport Time and Monthly Average Flowrates (Cont'd)

MONTH AVG RIVER FLOWRATE (CFS)

JANUARY 4663 FEBRUARY 4579 MARCH 6336 APRIL 10890 MAY 10157 JUNE 7369 JULY 5352 AUGUST 3506 SEPTEMBER 3334 OCTOBER 5690 NOVEMBER 5438 DECEMBER 4555 I/pir

MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SITE PROTECTIVE ACTION Revision 16 RECOMMENDATIONS Page 21 of 22 FIGURE 7.6 Liquid Release Protective Action Criteria A. PROTECTIVE ACTION BASED ON PROJECTED INTERNAL DOSE A. Concentration in Raw River: < Value listed in 10CFR20, Appendix B. - No protective action required.

B. Concentration in Raw River: > Value listed in 10CFR20, Appendix B. - Recommend closure of water intakes.

C. Projected Internal (Drinking) Dose:

5 250 mrem - No protective action required.

> 250 mrem - Preventive protective actions are necessary.

> 1000 mrem - Emergency protective actions are necessary.

B. PROTECTIVE ACTION BASED ON PROJECTED EXTERNAL DOSE A. Projected Total External Doses

250 mrem - No protective action required.

>250 mrem - Preventive protective actions are necessary.

> 1000 mrem - Emergency protective actions are necessary.

NOTE: Obtain total external projected dose by calculating the swimming, boating and standing projected doses using the following time assumptions for shoreline activities.

Swimming - 3 hrs/day Boating - 1 hrs/day Standing - 6 hrs/day RECOMMENDED PREVENTIVE PROTECTIVE ACTIONS A. Close Raw Water Intakes B. Restrict Intake of Drinking Water, and Foodstuffs obtained from River.

C. Restrict swimming and boating on River.

D. Restrict access to River.

E. Restrict use of River for irrigation and industry.

RECOMMENDED EMERGENCY PROTECTIVE ACTIONS A. Close Raw Water Intakes B. Condemn drinking water obtained from river.

C. Condemn affected foodstuffs (milk or meat from animals consuming contaminated water or foodstuffs).

D. Prevent access to river.

E. Condemn use of river for irrigation and industry.

F. Substitute uncontaminated water and foodstuffs for contaminated water and foodstuffs.

G. Condemn water usage from river.

Reference:

Minnesota Department of Health, Dose Assessment Manual: Part 2, Liquid Releases.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE: OFF-SITE PROTECTIVE ACTION Revision 16 RECOMMENDATIONS Page 22 of 22 FIGURE 7.7 Forms Utilized in Procedure NUMBER TITLE

1. 5790-1 02-02 MONTICELLO EMERGENCY NOTIFICATION REPORT FORM

2. 5790-204-01 MONTICELLO OFF-SITE PROTECTIVE ACTION RECOMMENDATION CHECKLIST I/pIr

MONTICELLO NUCLEAR GENERATING PLANT A.2-302 TITLE: ACTIVATION OF THE ASSEMBLY POINTS Revision 11 Page 1 of 11 EMERGENCY PLAN IMPLEMENTING PROCEDURE - TABLE OF CONTENTS SECTION Pi AGE 1.0 PURPOSE ........................................................ 2 I2.0 APPLICABILITY ................................................... 2 3.0 ORGANIZATION AND RESPONSIBILITIES ........................... 2 4.0 DISCUSSION. ..................................................... 3 5.0 PRECAUTIONS. ................................................... 4 6.0 INSTRUCTIONS ................................................... 4 6.1 Immediate Action of Assembly Point Coordinator ................. 4 6.2 Site Administration Building (SAB) Assembly Point Activation and Operation ............................................... 4 6.3 Transfer to Off-Site Assembly Points ............................ 5 6.4 Monticello Service Center Assembly Point Activation and Operation 5 6.5 Sherco Assembly Point Activation and Operation ................. 5 6.6 Evacuation to a State Relocation Center ........................ 5 7.0 FIGURES ......................................................... 6 7.1 Site Administration Building Assembly Point ..................... 6 7.2 Monticello Service Center Off-Site Assembly Point Location ....... 7 7.3 SherCo Off-Site Assembly Point Location ....................... 8 7.4 SherCo Assembly Point Diagram ............................... 9 7.5 Osseo Relocation Center Location ............................. 10 7.6 Osseo Relocation Center Diagram ............................. 11 Prepared By: Reviewed By:

OC Review Req'd. YES ing Number: c93sf7k Date:,z/, 3 Approved By: Date:.y/0,3 Th.s revisioN CN HD ADMIENIST RATIVEUSEONLYt -

Tireiinincorporates Volume F Memos:________________________________

3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) Incorporated 03 ' of 117 Resp Supv: EP lAssoc Ref. A 2 r1§DR N Freq, 1 vr ARMS: A 2-302 Doc Type: 1060 lAdmin Initials Date:AL)Y/@

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MONTICELLO NUCLEAR GENERATING PLANT A.2-302 TITLE: ACTIVATION OF THE ASSEMBLY POINTS Revision 11 PageI2f 11 1.0 PURPOSE The purpose of this procedure is to provide information and instructions for the activation and operation of the on-site and off-site Assembly Points in support of the MNGP Emergency Plan.

2.0 APPLICABILITY 2.1 An emergency condition has been declared which may require a plant or site evacuation at the Monticello Nuclear Generating Plant.

2.2 A Plant or Site evacuation may be ordered or is being conducted which requires the use of an on-Site and/or off-Site Assembly Point for the purpose of personnel accountability, monitoring and decontamination.

3.0 ORGANIZATION AND RESPONSIBILITIES 3.1 Emergency Director (ED) is responsible for:

3.1.1 Decision to remove personnel to an Assembly Point.

3.2 Assembly Point Coordinator is responsible for:

3.2.1 Overall coordination of activation and operation of the designated Assembly Point(s).

3.2.2 Coordinating the transfer of evacuees from an on-site to an off-site Assembly Point as directed.

3.2.3 Implementation of this procedure.

3.3 Radiation Emergency Coordinator (REC) is responsible for:

3.3.1 Selection of an off-site Assembly Point based on meteorological conditions and assembly point habitability.

3.3.2 Providing radiation protection support for operation of the On-Site and off-site Assembly Points including personnel monitoring and decontamination.

3.4 Radiation Protection Technician (RPT) are responsible for:

3.4.1 Assisting individuals with contamination control.

3.4.2 Monitoring and decontamination of vehicles.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-302 TITLE: ACTIVATION OF THE ASSEMBLY POINTS Revision 11 Page 3 of 11 3.5 Security Officers are responsible for:

3.5.1 Crowd control at the On-Site Assembly Point.

3.5.2 On-Site traffic control during evacuations.

3.5.3 Assisting with personnel accountability in the On-Site Assembly Point.

4.0 DISCUSSION 4.1 Assembly Point Operation The function of the Assembly Point is to provide a center for personnel accountability and radiological contamination monitoring along with any other actions immediately necessary in the event of a plant evacuation.

The steps in this procedure assume an orderly evacuation in which time is available for staging. In the event that there is no time for preparation, some of the steps in this procedure may have to occur out of sequence or simultaneously. Assembly Point Coordinators should be familiar with the intended function of the Assembly Point so that this procedure can be adjusted to fit the circumstances.

4.2 Location The On-Site Assembly Point is located approximately 1000 ft south of the reactor building in the Site Administration Building (SAB) see FIGURE 7.1.

There are two off-site Assembly Points, one is located in the Monticello Service Center, see FIGURE 7.2, and the other is located at the Sherco Generating Plant, see FIGURES 7.3 and 7.4.

4.3 Data and Information Resources 4.3.1 The On-Site Assembly Point contains the following information sources.

A. Monticello Emergency Plan Drawings B. Monticello Emergency Plan Implementing Procedures l

4.4 Communications 4.4.1 The On-Site Assembly Point has plant extensions with "outside line" capability.

4.4.2 The Assembly Point Coordinator is equipped with a portable radio for communication with the MSL.

4.4.3 The Assembly Point Security Officer is equipped with a portable radio for communication with the Security Group Leader.

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4.5 Equipment and Facilities 4.5.1 The On-Site Assembly Point contains the following:

A. Dose Rate and Survey Instruments B. Air Sampling Equipment C. Decontamination Supplies D. First Aid Supplies 4.5.2 The off-site Assembly Points A. Obtain the Vehicle and Personnel Decontamination Kit locker contents, portable survey instrumentation, and Radiation Protection frequency radio from the Emergency Vehicle and Equipment Storage (EVES) Building before proceeding to the off-site Assembly Point.

5.0 PRECAUTIONS In the event of a radiological release at MNGP, the Assembly Point may become uninhabitable. If such a situation occurs, the Emergency Director must be immediately contacted and informed of conditions.

6.0 INSTRUCTIONS 6.1 Immediate Action of Assembly Point Coordinator 6.1.1 Report to the ERO Tagboard by the TSC and flip-over the duty tag for the Assembly Point Coordinator after reading the instruction.

6.1.2 Contact the Rad Emerg Coord or the Security Group Leader to ascertain if/when the Assembly Point will be activated.

6.1.3 Contact the Security Group Leader and arrange for a security officer to assist in the Assembly Point.

6.2 Site Administration Building (SAB) Assembly Point Activation and Operation 6.2.1 Initiate the Form 5790-302-01 (ON-SITE ASSEMBLY POINT ACTIVATION CHECKLIST) and proceed to the on-site Assembly Point (2nd floor of the SAB, conference room 5).

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MONTICELLO NUCLEAR GENERATING PLANT A.2-302 TITLE: ACTIVATION OF THE ASSEMBLY POINTS Revision 11 Page 5 of 11 6.3 Transfer to Off-Site Assembly Points 6.3.1 Contact the Security Group Leader or the Radiological Emergency Coordinator to determine which off-site Assembly will be used.

6.3.2 Initiate Form 5790-302-02 (OFF-SITE ASSEMBLY POINT ACTIVATION CHECKLIST).

6.4 Monticello Service Center Assembly Point Activation and Operation 6.4.1 Complete the appropriate instructions provided in 5790-302-02.

6.5 Sherco Assembly Point Activation and Operation 6.5.1 Complete the appropriate instructions provided in 5790-302-02.

6.6 Evacuation to a State Relocation Center 6.6.1 If the 5 mile EPZ is evacuated contact the DEM to determine location of relocation center for the Monticello Personnel. (For maps to the Osseo relocation center refer to Figure 7.5 and 7.6).

6.6.2 Proceed to the relocation center as directed by the state DEM.

6.6.3 Upon arrival at the Relocation Center contact the Facility Coordinator and follow the directions of the Facility Coordinator for monitoring.

6.6.4 NOTE: In order for personnel to return into the evacuated area, a company ID will be required.

Direct site personnel whose services may be required at the site to notify the Site at 763-295-3739 of their location if other than permanent residence.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-302 TITLE: ACTIVATION OF THE ASSEMBLY POINTS Revision 11 Page 6 of 11 7.0 FIGURES FIGURE 7.1 Site Administration Building Assembly Point 1st. FLOOR ENTRANCE I 1 PERSONNEL-ENTER HERE AND GO UP THE STAIRWAY TO THE HALLWAY TO S A.B 5 EAST SITE ADMINISTRATION BUILDING ASSEMBLY POINT SECOND FLOOR MONTICAD SABASBS2-302-1 SABASBLE I/mab

MONTICELLO NUCLEAR GENERATING PLANT A.2-302 TITLE: ACTIVATION OF THE ASSEMBLY POINTS Revision 11 1 Page 7 of 11 FIGURE 7.2 Monticello Service Center Off-Site Assembly Point Location DUNDAS ROAD I/mab

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MONTICELLO NUCLEAR GENERATING PLANT A 2-807 TITLE: OFF-SITE DOSE ASSESSMENT AND Revision 9 PROTECTIVE ACTION RECOMMENDATIONS Page 1 of 33 EMERGENCY PLAN IMPLEMENTING PROCEDURE - TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE .................................. 2 2.0 APPLICABILITY ............................... 2 3.0 ORGANIZATION AND RESPONSIBILITIES ........................... 2 4.0 DISCUSSION.. 3 5.0 PRECAUTIONS.. 4 6.0 INSTRUCTIONS.. 5 6.1 Initial PARs for General Emergency Classification. 5 6.2 PARS for Sherco Plant. 6 6.3 Off-site PARs Based on Projected Doses. 7 6.4 Protective Action Recommendation for Liquid Releases. 9 6.5 Ground Deposition Assessment ...... ........................... 10 6.6 Return Dose Assessment ....... .............................. 11 6.7 General Instructions for Field Team Deployment .... ............. 11 6.8 Field Team Deployment During Airborne Releases .... ........... 12 6.9 Field Team Deployment for Ground Deposition Assessment ....... 14 6.10 Dose Assessment and Field Team Deployment for Ingestion Pathway 15 7.0 FIGURES . .................................................. 16 7.1 Definitions Related to Protective Actions Recommendations ....... 16 7.2 Discussion of Protective Action Recommendations .... ........... 19 7.3 Protective Action Guidelines (PAGs) ...... ...................... 22 7.4 Emergency Worker Exposure Limits ...... ...................... 24 7.5 Transport Time and Monthly Average Flowrates .... .............. 25 7.6 Liquid Release Protective Action Criteria ..... ................... 27 7.7 Ground Deposition Modeling ........ ........................... 28 7.8 Secondary Evacuation Dose Projection ..... .................... 30 7.9 Relocation Protective Action Guidelines ..... .................... 32 7.10 Forms Utilized in Procedure ........ ........................... 33 I/pIr

MONTICELLO NUCLEAR GENERATING PLANT A 2-807 TITLE: OFF-SITE DOSE ASSESSMENT AND Revision 9 PROTECTIVE ACTION RECOMMENDATIONS Page 2 of 33 1.0 PURPOSE This procedure provides instructions and guidance for the conduct of off-site dose assessment and formulation of off-site Protective Action Recommendations at the Monticello EOF.

Steps in this procedure satisfy commitment M90125A.

2.0 APPLICABILITY 2.1 An Alert has been declared at the Monticello plant and, 2.2 The EOF has been activated, staffed and has assumed the responsibility for off-site communication, dose assessment and Field Team coordination.

3.0 ORGANIZATION AND RESPONSIBILITIES 3.1 The Emergency Manager (EM) is responsible for:

3.1.1 The approval of off-site Protection Action Recommendations prior to their transmittal to the State (or local) authorities.

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

3.2.1 Implementation of this procedure.

3.2.2 Overall direction and coordination of EOF Rad Prot Support group activities including off-site dose projections, dose assessment, and the formulation of off-site protective action recommendations.

$ 3.2.3 Making recommendations regarding off-site Protective Actions to the Emergency Director (ED) and discussing the basis for off-site Protective Action Recommendations with the State Planning Chief and NRC.

3.3 The Assistant RPSS is responsible for:

3.3.1 Assisting the RPSS with the coordination of EOF Radiation Protection Support Group activities including dose projections, assessment and Field Team direction.

3.4 The MIDAS Operator is responsible for:

3.4.1 The conduct of off-site dose projections using the MIDAS (or backup) methods including the generation of periodic Emergency Notification Follow-up Messages for transmittal to the State.

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MONTICELLO NUCLEAR GENERATING PLANT A -

TITLE: OFF-SITE DOSE ASSESSMENT AND Revision 9 PROTECTIVE ACTION RECOMMENDATIONS Page 3 of 33 3.5 The Field Team Coordinator is responsible for:

3.5.1 Direction and coordination of Monticello and Prairie Island Field Teams under the supervision of the RPSS (or Assistant RPSS).

3.6 The Field Team Communicator is responsible for:

3.6.1 The coordination of Monticello and Prairie Island Field Teams via radio under the direction of the Field Team Coordinator.

4.0 DISCUSSION 4.1 Summary Dose assessment refers to the integrated process of dose projection, collection of field measurements and meteorological data, comparison of projected data to field data, and consideration of plant status to develop a working knowledge of the current and near-term radiological environment resulting from a radioactive release.

The radiological forecast developed in the dose assessment process provides the input for making appropriate recommendations to protect the health and safety of the public.

The responsibility for dose assessment is initially assigned to the TSC. The Radiological Emergency Coordinator (REC) formulates protective action recommendations which are forwarded to State or County officials through the ED. After the EOF is activated, the EM is responsible for dose assessment. At the decision of the EM, the dose assessment function transfers from the TSC to the EOF.

The decision to transfer dose assessment responsibilities from the TSC to the EOF will be based on the emergency situation, the EOF equipment status and staffing of the Radiation Protection Support Group. The transfer is implemented by informing the TSC, directing the RPSS to assume the responsibility and closely coordinating the transfer with the REC.

4.2 For definitions related to PARs, see FIGURE 7.1 4.3 For general discussion of PARs, see FIGURE 7.2 I/plr

MONTICELLO NUCLEAR GENERATING PLANT A 2-807 TITLE: OFF-SITE DOSE ASSESSMENT AND Revision 9 PROTECTIVE ACTION RECOMMENDATIONS Page 4 of 33 5.0 PRECAUTIONS 5.1 Declaration of a General Emergency requires immediate initial protective action recommendations (PARs) to off-site agencies. Under these circumstances, NO dose projections are required for formulating the initial off-site protection action recommendation.

5.2 Implementation of protective actions for off-site areas is the responsibility of the State of Minnesota. If it is determined by the EM that immediate protective actions are required, and the State EOC is not activated, the recommendation SHALL be made directly to the local authorities (i.e., Wright and Sherburne Counties). Upon activation of the State EOC all off-site protective action recommendations SHALL be made to the State.

5.3 The protective actions outlined in this procedure are limited to actions for minimizing the exposure of the public to external and internal radiation exposure from plume passage, inhalation of the radioactive plume and from internal exposure from drinking water during the early phase of an emergency.

Other protective actions for minimizing public exposure via the ingestion pathway will be determined and implemented by the State.

5.4 Exposures of Field Team personnel should be in accordance with administrative control levels. They should have proper dosimetry, which is frequently checked, remain alert to their own exposure and request relief if cumulative exposure approaches administrative control levels. The ED may authorize exposure limit extensions if necessary (refer to EPIP A.2-401 (EMERGENCY EXPOSURE CONTROL)). All exposures should be maintained ALARA.

5.5 Monticello Field Teams should not be recalled from field monitoring until Prairie Island teams have relieved them in the field.

5.6 The transmission of Off-site Protective Action Recommendations to the State EOC (State Duty Officer and Counties if the State EOC is not activated)

SHALL be completed within 15 minutes of the PAR authorization.

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MONTICELLO NUCLEAR GENERATING PLANT A .2-807 TITLE:

OFF-SITE DOSE ASSESSMENT AND Revision 9 PROTECTIVE ACTION RECOMMENDATIONS Page 5 of 33 6.0 INSTRUCTIONS CAUTION' No dose projections are required when making initial PAR during GENERAL EMERGENCY CONDITIONS.

6.1 Initial PARs for General Emergency Classification 6.1.1 Initiate Form 5790-102-02 (MONTICELLO EMERGENCY NOTIFICATION REPORT FORM).

A. Complete Section 1.4 recommending an evacuation of a 2 mile radius and 5 miles downwind and advise the remainder of the plume EPZ to go indoors to monitor EAS broadcasts.

B. Determine which geopolitical subareas are affected by referring to the Sector-Subarea Conversion Table on Form 5790-102-02.

C. Ensure completion of Parts 1.0 and 2.0 of Form 5790-102-02 and submit the completed form to the EM for approval.

6.1.2 Ensure transmission of the recommendations, via telephone and telecopy, to the State EOC (State Duty Officer, Wright and Sherburne Counties if the State EOC is not activated) in accordance with EPIP A.2-803 (EMERGENCY COMMUNICATIONS AT THE EOF).

6.1.3 Approximately 30 minutes after making the recommendation, contact the State Planning Chief or State Duty Officer if State EOC is not activated to determine what protective actions are actually being implemented. Continue to track the status of the protective action until completely implemented and indicate the completion status on the Radiation Protection Status Board.

6.1.4 Update the EM and EOF personnel (if activated and staffed) on the status of off-site Protective Action implementation.

6.1.5 After making initial Protective Action Recommendations (at the General Emergency Class) continually assess plant conditions and off-site dose projection results. Make subsequent off-site protective action recommendations based on projected off-site doses using the Protective Action Guidelines (PAGs) listed in FIGURE 7.3.

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MONTICELLO NUCLEAR GENERATING PLANT A2-807 TITLE: OFF-SITE DOSE ASSESSMENT AND Revision 9 PROTECTIVE ACTION RECOMMENDATIONS Page 6 of 33 6.2 PARS for Sherco Plant NOTE: To safely shutdown the Sherco Plant requires eight (8) hours after the unit(s) are tripped.

6.2.1 Throughout the event the RPSS (or Assistant RPSS) should review off-site projected doses and affected Sectors (Subareas) to determine if the Sherco Plant is or will be in the affected area.

NOTE: The Sherco Plant is located in the 5N subarea.

6.2.2 Formulate protective action recommendations for the Sherco Plant as follows:

A. Recommendations based on Projected Dose (whole body):

1. > 500 mrem (TEDE) - recommend evacuation of non-essential personnel from the Sherco site and shelter essential plant personnel during plant operation.

2. > 1 Rem (TEDE) - recommend shutdown of the Sherco Plant(s). Immediate evacuation of non-essential personnel and sheltering of essential personnel during normal plant shutdown.

3. > 5 Rem (TEDE) - recommend immediate evacuation of non-essential personnel and sheltering of essential personnel during emergency plant shutdown. Evacuate all personnel immediately after plant shutdown.

B. Recommendations based on General Emergency:

1. If evacuation is implemented (in 5N) recommend evacuation of all non-essential personnel and sheltering of essential Sherco personnel. Recommend immediate initiation of plant shutdown.

6.2.3 If protective actions are required for the Sherco Plant, discuss the recommendations with the EM.

NOTE: Generation management will implement the required protective actions for Sherco personnel through established management channels.

6.2.4 Monitor the progress of protective action implementation (at Sherco) to determine when they are completed.

6.2.5 Indicate any PARs recommended (and implemented) for the Sherco Plant on the RP Status Board in the TSC.

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MONTICELLO NUCLEAR GENERATING PLANT A-2-807 TITLE: OFF-SITE DOSE ASSESSMENT AND Revision 9 PROTECTIVE ACTION RECOMMENDATIONS Page 7 of 33 6.2.6 Advise the EM if conditions change (e.g., significant increase in release rate) which could change the protective action recommendations for the Sherco Plant.

6.3 Off-site PARs Based on Projected Doses CA UTION Do not delay recommending off-site protective actions while waiting for off-site monitoring results to verify the accuracy of the dose projection model. Do not delay recommending off-site protective actions while trying to resolve questionable data (MIDAS Data or Field Team Data).

6.3.1 Continuously review dose projection data (four (4) day integrated maximum TEDE and Thyroid CDE) on Form 5790-102-03 (EMERGENCY NOTIFICATION FOLLOW-UP MESSAGE) and compare with the Protective Action Guidelines in FIGURE 7.3. If an updated PAR, based on dose projections is required, proceed to Step 6.3.2. Continuously review meteorological data (wind direction and wind speed) on Form 5790-102-03 and determine the affected sectors.

If an updated PAR, based on meteorological data is required, proceed to Step 6.3.2.

6.3.2 Initiate Form 5790-204-01 (MONTICELLO OFF-SITE PROTECTIVE ACTION RECOMMENDATION CHECKLIST) and complete the airborne release section.

6.3.3 Using current meteorological data (i.e., wind direction and wind speed), determine the affected Sectors, Geopolitical Subareas (using page 2 of Form 5790-204-01), population centers with in the affected area and estimated plume arrival time in those areas.

6.3.4 Based on plant conditions, estimate the duration of the existing release or potential release.

6.3.5 Using available weather forecast data, evaluate the potential for wind direction and wind speed changes during the estimated duration of the release (and after). Determine what effect potential wind direction and wind speed changes would have on the affected areas identified in 6.3.3.

NOTE: Weather forecast information may be obtained from the National Weather Service. Refer to the Monticello and Prairie Island Nuclear Emergency Preparedness Telephone Directory for telephone numbers.

NOTE: If data used in the determination of the PAR is/or was questionable, attempt to verify the data. DO NOT delay the issuance of the PAR. If after verification of questionable data a PAR revision is necessary, complete Section 6.3 of this procedure.

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MONTICELLO NUCLEAR GENERATING PLANT A 2-807 TITLE: OFF-SITE DOSE ASSESSMENT AND Revision 9 PROTECTIVE ACTION RECOMMENDATIONS Page 8 of 33 6.3.6 If based on dose projections or field team data a PAR beyond the 10 mile EPZ is necessary, immediately contact the State Planning Chief to inform them of this condition and document in comments section of Form 5790-204-01. Attach a copy of the supporting Follow-up Message to Form 5790-204-01.

6.3.7 Indicate the recommendations on page 3 of Form 5790-204-01.

Indicate the recommendation in terms of Sectors and Subareas by completing and circling the applicable information as follows:

A. Identify the affected keyhole by selecting a 3600 out to 2 or 5 miles. Determine the affected Sectors by including both Sectors on either side of the downwind Sector (two Sectors on either side should be included if the downwind direction is on a Sector line).

Record the 3 (or 4) affected Sectors on page 3 of the Monticello PAR Checklist.

B. Identify the affected geopolitical subareas using the Sector-Subarea Conversion Chart (page 2 of Form 5790-204-01) and circle the affected subareas on the PAR Checklist.

6.3.8 Submit the completed page 3 of Form 5790-204-01 to the EM for approval. Review and discuss the recommendations with the ED as necessary.

NOTE: Prior to activation of the State EOC, protective action recommendations should be made directly to the State Duty Officer and Wright and Sherburne Counties (EOCs if activated). The State Duty Officer will coordinate the EAS message and PANs activation with counties. Once the State EOC is activated, all protective action recommendations SHALL be made directly to the State authorities.

6.3.9 The ED (or RPSS) should direct an Emergency Communicator to transmit the approved Off-Site Protective Action Recommendation Checklist, to the State EOC (Wright and Sherburne County EOCs only if the State EOC is not yet activated) in accordance with EPIP A.2-803 (EMERGENCY COMMUNICATIONS AT THE EOF).

6.3.10 When notified by the Emergency Communicator that the transmittal of the protective action recommendation has been made to the State Planning Chief (if State EOC is activated) or the State Duty Officer, Wright County and Sherburne County (if State EOC is not activated) contact either the State Planning Chief or the State Duty Officer, Wright County and Sherburne County. Discuss the recommendations and explain the basis of the recommendations.

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MONTICELLO NUCLEAR GENERATING PLANT A 2-807 TITLE: OFF-SITEDOSE ASSESSMENT AND Revision 9 PROTECTIVE ACTION RECOMMENDATIONS Page 9 of 33 6.3.11 Approximately 30 minutes after making the recommendation, contact the State Planning Chief or State Duty Officer prior to State EOC activation, to determine what protective actions are actually being implemented. Continue to track the status of the protective action until completely implemented and indicate the completion status on the Radiation Protection Status Board.

6.3.12 If, as a result of continuing assessment, dose projection results or meteorological conditions change significantly, re-evaluate the previously implemented protective actions and, if necessary, update the protective actions by issuing another recommendation.

6.4 Protective Action Recommendation for Liquid Releases 6.4.1 Initiate Form 5790-204-01 and complete the Liquid Release Section.

6.4.2 Obtain the isotopic analyses of liquid samples taken at the Discharge Canal or release point.

NOTE: During a liquid release, samples may be taken at the discharge structure, mid-canal sample station, canal out-fall to the river, or as near the source of the release as possible. To ensure samples are representative of the material being released to the river, the Canal Sample Station is the preferred sampling location.

6.4.3 Determine the present Discharge Canal flow rate and river flow rate at the plant (refer to the applicable plant computer point for flow rates).

6.4.4 Determine the river flow rate at either the Coon Rapids Dam or the Minneapolis-St. Paul water intakes by contacting the Minneapolis Water Department (refer to the Monticello and Prairie Island Nuclear Emergency Preparedness Telephone Directory for telephone numbers).

6.4.5 Using the curve RIVER FLOW vs TIME curve (FIGURE 7.5) estimate the time of release arrival at the Minneapolis-St. Paul water intakes based on current, actual river flow (if actual river flow is not available, use the monthly average river flow in FIGURE 7.5).

6.4.6 Using the MIDAS User Manual Procedures access the MIDAS liquid release model. Enter the isotopic and other applicable release data.

6.4.7 Using the MIDAS Liquid Release Dose Assessment printout, formulate off-site protective action recommendations in accordance with the guidelines in FIGURE 7.6.

6.4.8 Indicate the recommendations on page 3 of Form 5790-204-01 and submit the completed form for ED approval.

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MONTICELLO NUCLEAR GENERATING PLANT A-2-807 TITLE: OFF-SITE DOSE ASSESSMENT AND Revision 9 PROTECTIVE ACTION RECOMMENDATIONS Page 10 of 33 6.4.9 Transmit the recommendations to the State Planning Chief (State EOC if activated) in accordance with EPIP A.2-803.

6.4.10 Contact the State Planning Chief (in the State EOC if activated) to explain the basis for the recommendations.

6.4.11 Approximately 30 minutes after making the recommendation, contact the State Planning Chief to determine what protective actions are actually being implemented. Continue to track the status of the protective action until completely implemented.

6.5 Ground Deposition Assessment 6.5.1 Perform ground deposition projections as follows:

NOTE: The purpose of this step is to obtain a rough estimate of ground deposition. If estimates of curies released are not available, proceed with Field Team deployment.

A. Determine the number of microcuries of iodine and particulate material (i.e., not noble gases) that were released.

B. Refer to FIGURE 7.7 to calculate the projected ground deposition. Using the guidance in FIGURE 7.7 develop a footprint, or map of the area, that could have ground contamination levels above 1 uCi/m2.

C. Record Field Team ground deposition survey results on Form 5790-410-03 (GROUND DEPOSITION SAMPLE RESULTS LOG).

6.5.2 As exposure rate data is obtained, calculate relocation projected doses using the conversion factor of 5000 mrem per mR/hr (i.e., 5000 mrem relocation projected dose per 1 mR/hr initial gamma exposure rate 1 meter above the ground).

NOTE: This conversion factor may be conservative. The factor depends on the isotopic distribution and decay time of the ground deposition. With actual isotopic data, a better conversion factor can be calculated using the data in FIGURE 7.8.

6.5.3 As smear samples are analyzed and isotopic data is obtained use FIGURE 7.8 to refine the relocation projected doses.

6.5.4 Plot the relocation projected doses on a map. (Consider using a dedicated map to avoid confusion).

6.5.5 Determine the appropriate protective action recommendations in accordance with FIGURE 7.9.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE: OFF-SITE DOSE ASSESSMENT AND Revision 9 PROTECTIVE ACTION RECOMMENDATIONS Page 11 of 33 6.6 Return Dose Assessment 6.6.1 As soon as resources allow, obtain dose rate surveys and smear samples per EPIP A.2-410 (OUT-OF-PLANT SURVEYS) in evacuated areas that are believed to be outside the footprint.

6.6.2 As the priority for return to evacuated areas within the known footprint increases (per the States recommendation), obtain dose rate surveys and smear samples within the affected (evacuated) areas in accordance with A.2-41 0.

6.6.3 Use FIGURE 7.8 and calculate relocation projected doses based on known (measured) ground deposition.

6.6.4 Plot the relocation projected doses on a map.

6.6.5 Refer to FIGURE 7.9 and develop Protective Action Recommendations regarding return to evacuated areas as appropriate.

6.6.6 Indicate the recommendation on Form 5790-204-01.

A. Submit the completed form to the Emergency/Recovery Manager for approval and processing.

6.7 General Instructions for Field Team Deployment 6.7.1 Identify the team(s) as Monticello Field Team 1 and 2 and direct the team(s) to establish and maintain radio communication with the Field Team Communicator in the EOF.

6.7.2 When the Prairie Island Field Teams arrive identify the PI teams as Field Team 3 and 4.

6.7.3 Determine the starting point of the survey based on the release point, source term, magnitude of the release, wind direction, and dose projection data (if available).

6.7.4 Dispatch the team(s) to the selected survey/sample points to conduct surveys/sampling in accordance with EPIP A.2-410.

6.7.5 Direct the team(s) to transmit survey/sample results (by radio) to the Field Team Communicator in the EOF.

6.7.6 Direct the Field Team Communicator to record survey results on Form 5790-202-01 (OFF-SITE SURVEY RESULTS DATA SHEET) or Form 5790-41 0-03.

6.7.7 Direct the Field Team Communicator to periodically update the team(s) on plant conditions, emergency classification changes, protective actions and meteorological information as it becomes available.

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MONTICELLO NUCLEAR GENERATING PLANT A 2-807 TITLE: OFF-SITE DOSE ASSESSMENT AND Revision 9 PROTECTIVE ACTION RECOMMENDATIONS Page 12 of 33 6.7.8 Direct the team to check personal dosimetry and request relief if their exposure approaches administrative limits.

6.7.9 Direct the team(s) in the use of protective measures (including Anti-C clothing, respiratory protection and exposure control) in accordance with the following guidelines:

A. Direct protective clothing and respirator (with GMR-1 canisters) use if:

1. Substantial airborne activity and ground contamination is suspected or observed and the affected sectors have been evacuated; or

2. A General Emergency has been declared and measured dose rates are more than 100 mrem/hr True Beta.

B. Direct the implementation of ALARA exposure control measures as follows:

1. Field Teams should not linger in areas greater than 100 mrem/hr;

2. Field Teams should not proceed into areas projected to be greater than 1000 mrem/hr unless directed by the REC;

3. Field Teams should not proceed into areas projected to be greater than 10,000 mrem/hr.

6.7.10 Based on initial survey results request backup surveys or confirmatory sampling as necessary.

6.7.11 Upon completion of Field Team survey operations, direct the team(s) to report to the Emergency Operations Facility for exposure processing, de-briefing and re-assignment.

6.8 Field Team Deployment During Airborne Releases NOTE: For events that do not involve a radioactive release off-site monitoring is required to confirm that a release (above normal limits) is not occurring.

6.8.1 Dispatch the Field Teams in the downwind direction to conduct a search for the plume in accordance with EPIP A.2-41 0.

CAUTION Do not allow the Field Team(s) to sit idle. Teams should traverse the projected path of the plume in downwind affected sectors rather than remain in one location awaiting plume arrival.

6.8.2 When the plume is located (positive meter deflection) instruct the team(s) to perform dose rate surveys in accordance with EPIP A.2-41 0.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE: OFF-SITE DOSE ASSESSMENT AND Revision 9 PROTECTIVE ACTION I RECOMMENDATIONS Page 13 of 33 6.8.3 Based on the results of the dose rate survey(s) determine if the team is in the plume (positive beta reading) or if the plume is elevated (gamma only).

6.8.4 When the plume is encountered (i.e., positive beta reading) direct the team(s) to obtain airborne particulate, gaseous and Iodine airborne, and ground deposition samples. Instruct the team to analyze the samples (in low background area) and transmit the field analysis results to the EOF.

6.8.5 Upon completion of the field analysis direct the team to retain the samples or deliver them to the EOF Count Room for further analysis.

NOTE: A sample courier may be used to transport samples from the team(s) to the applicable Count Room.

6.8.6 Direct the Field Team Communicator to record all survey results on Form 5790-202-01 or Form 5790-410-03.

6.8.7 Track and plot the movement of the plume on the Radiological Survey Point map as follows:

A. Using current meteorological conditions (wind speed, direction, etc.) project the path of the plume; B. Using available MIDAS data (GAMMA & THYROID PROJECTED DOSE REPORT and PROJECTED DOSE

SUMMARY

REPORT) project the location of the leading edge and trailing edge (if "puff" release) of the plume; C. Using the team(s), locate the leading edge of the plume; D. Using the field team(s), locate the lateral boundaries (sides) of the plume; E. Using the team(s), verify that upwind ("backdoor") areas near the site are not affected by the release; F. For "puff" releases, direct the team(s) to locate the trailing edge of the plume; 6.8.8 Compare off-site monitoring results for consistency with State survey results as applicable. Reconcile inconsistencies in data and/or re-survey areas of concern as necessary.

6.8.9 Determine the centerline dose rate by directing a team to traverse through the plume, while monitoring enroute.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE: OFF-SITE DOSE ASSESSMENT AND Revision 9 PROTECTIVE ACTION RECOMMENDATIONS Page 14 of 33 NOTE: This survey should be coordinated with the MIDAS dose projection run in an attempt to verify the projection by comparing survey results to the projection data.

6.8.10 Compare off-site survey results with dose projections for consistency.

Reconcile major inconsistencies in data and/or re-survey areas of concern as necessary.

NOTE: A factor of < 100 is appropriate to use as the reasonable deviation when comparing model vs. actual field data.

6.8.11 Direct the Field Team Communicator to periodically update the team(s) on plant conditions, emergency classification changes, protective actions and meteorological information as it becomes available.

6.9 Field Team Deployment for Ground Deposition Assessment 6.9.1 Deploy Field Teams to obtain ambient dose rates and collect samples (in accordance with A.2-410) in areas that are not evacuated, but within the footprint.

6.9.2 Concentrate first on areas suspected of having the highest deposition.

6.9.3 Priority should be given to initially performing dose rate surveys, with more detailed smear surveys to follow. Target areas with dose rates above 0.2 mrem/hr or direct frisker readings above 20,000 cpm for collection of smear samples.

6.9.4 Enough dose rate surveys/smear samples should be obtained to have confidence that "hot spots" have not been overlooked. Ten survey points per square mile is suggested as a minimum in areas where roads will allow this to be practical.

6.9.5 Ensure that areas not within the projected footprint are surveyed sufficiently to verify that the affected area has been identified completely.

6.9.6 Plot the Field Team results on a map. Compare them to the ground deposition projections, and direct follow-up surveys as appropriate to ensure the affected area is identified.

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MONTICELLO NUCLEAR GENERATING PLANT A 2-807 TITLE: OFF-SITE DOSE ASSESSMENT AND Revision 9 PROTECTIVE ACTION RECOMMENDATIONS Page 15 of 33 6.10 Dose Assessment and Field Team Deployment for Ingestion Pathway 6.10.1 Contact the EOC of each affected State and see if they have sample collection needs of particular priority that MNGP could satisfy.

NOTE: MNGP survey teams have the capability of performing dose rate, smear, liquid, soil/snow and air sampling and analysis. If there is a need for more sophisticated environmental samples, contact Teledyne and implement the letter of agreement. Once notified, Teledyne will dispatch a team to the affected site. They will also make their laboratories available for use should we need to send samples for analysis.

6.10.2 Direct the Field Teams to obtain samples according to the State(s) needs or to collect samples to confirm the results of the State(s) survey team.

6.10.3 Ingestion pathway dose projections should not be performed. Instead concentrate available resources on the collection, analysis, and transmittal of results to the States of smear, liquid, soil and/or snow samples.

6.10.4 Ingestion pathway protective actions will be determined by the State of Minnesota.

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MONTICELLO NUCLEAR GENERATING PLANT A 2807 TITLE: OFF-SITE DOSE ASSESSMENT AND Revision 9 PROTECTIVE ACTION RECOMMENDATIONS Page 16 of 33 7.0 FIGURES FIGURE 7.1 Definitions Related to Protective Actions Recommendations

1. Affected Area is any area where radiation emanating from a plume, or from material deposited from the plume, can be detected using field instruments (also known as the footprint).

2. Cloudshine is radiation from radioactive materials in an airborne plume.

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

4. 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.

5. Dose equivalent means the product of the absorbed dose in tissue, quality factors, and all other necessary modifying factors at the location of interest.

6. 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.

NOTE: Deep Dose Equivalent (DDE) is considered equivalent to EDE if the exposure is uniform.

7. Emergency Planninq Zone (EPZ) is a defined area which facilitates emergency planning by State and local authorities to ensure that prompt and effective actions are taken to protect the public in the event of a radioactive release from the plant. The EPZ is defined for two areas:

A. Plume Exposure Pathway (10 Mile EPZ) is the 10 mile, 360° radius around the plant in which the primary concern is short-term exposure from the plume. The principal sources of exposure in this area are 1) whole body external exposure to gamma radiation from the plume and deposited material from the plume, and 2) internal exposure from inhaled material from the plume.

B. Ingestion Exposure Pathway (50 Mile EPZ) is a 50 mile, 3600 radius around the plant in which the principal exposure would be from ingestion of contaminated water or foodstuffs (such as milk or fresh vegetables).

8. Evacuation is the removal of people from an area to avoid or reduce high-level, short term exposure, from a plume or from deposited activity.

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MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE: OFF-SITE DOSE ASSESSMENT AND Revision 9 PROTECTIVE ACTION RECOMMENDATIONS Page 17 of 33 FIGURE 7.1 Definitions Related to Protective Actions Recommendations (cont'd)