ML031880064

Transmittal of Emergency Plan Implementing Procedure

ML031880064
Person / Time
Site:	Duane Arnold
Issue date:	06/25/2003
From:	Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML031880064 (40)

Text

NIMC Committed to Nuclear ExceIlence DAEC EMERGENCY PLANNING DEPARTMENT PROCEDURE TRANSMITTAL ACKNOWLEDGEMENT MEMO (TAM41)

To: NRC-NRR Document Control Desk US NRC Washington DC 20555 Re: Entire EPIP Document (Copy 28)

PSM

Title:

nla Distribution Date: 06/25 /2003 Effective Date of Change: 06 /25 /2003 Return by: 07/16/2003 Please perform the following to your assigned manual. If you have any questions regarding this TAM please contact Don A. Johnson at 319-851-7872.

REMOVE INSERT EPIP Table of Contents Revision Rev. 136 Rev. 137 EPIP 3.3 (PWR: 21769) Rev. 18 Rev. 19 EPIP ERO-01 (PWR: 21830) Rev. 0 Rev. 0 Add new form.

PERFORMED BY:

Print Name Sign Name Date Please return to: K. Dunlap PSC/Emergency Planning 3313 DAEC Rd.

Palo, IA 52324 To be completed by DAEC EP personnel only:

Date TAM returned:

EPTools updated:

4v34S

[l EMERGENCY PLAN I- LE .T. G PCDUS Rev. 137 INDEX 1PAGE I of 7 Procedure Title Revision Date Number 1.1 Determination of Emergency Action Levels 19 09112/01 1.2 Notificabon 28 4/4/03 1.3 Plant Assembly and Site Evacuation 9 09/12/01 1.4 Release of Emergency-Related Information 4 09104102 1.5 Activation and Operation of the EOF 4 6/11/03 2.1 Activation and Operation of the OSC 13 09/12/01 2.2 Activation and Operation of the TSC 23 10/23/02 2.3 Operabon of the FTS-2001 Phone Network 6 09/04/02 2.4 Activabon and Operation of the ORAA 8 09/12/01 2.5 Control Room Emergency Response Operation 14 10/15/01 2.6 Activation and Operation of the ORAL 9 12/30/02 2.7 Activation and Operation of the ODEF 6 10/15/01 2.8 Security Threat 1 11/16/01 3.1 In-Plant Radiological Monitoring 12 9/2/02 3.2 Field Radiological Monitoring 13 9/2/02 3.3 Dose Assessment and Protective Action 19 6/25/03 I 4.2 First Aid, Decontamination and Medical Support 7 8123/02 4.3 Rescue and Emergency Repair Work 11 8/23/02 4.5 Administration of Potassium Iodide (KI) 7 2/10/03 5.2 Recovery and Re-entry 9 10/15/01

Form Title Revision Referencing Number Number Procedure CR-01 OSM/OSS Checklist Rev. 2 EPIP 2.5 CR-02 Back Panel Communicator Checklist Rev. 1 EPIP 2.5 CR-03 Dose Projection & ARM Data Sheet Rev. 0 EPIP 2.5 CR-04 Control Room to TSC Command and Control Rev. 1 EPIP 2.5 Transfer Checklist EAL-01 Abnormal Rad Levels/Radioactive Effluent Table Rev, 3 EPIP 1.1 EAL-02 Fission Barrier Table Rev. 3 EPIP 1.1 EAL-03 Hazards & Other Conditions Affecting Plant Safety Rev. 2 EPIP 1.1 EAL-04 System Malfunction Table Rev. 3 EPIP 1.1 EOF - 02 NRC - HPN Communicator Checklist Rev. 3 EPIP 1.5 EOF - 03 Technical Recorder Checklist Rev. 2 EPIP 1.5 EOF - 04 Summary of Computer Data Backup Collection Rev. 1 EPIP 1.5 Activities EOF - 05 EOF Information Services Representative Checklist Rev. 3 EPIP 1.5 EOF - 06 DAEC Key Parameter Log Rev. 0 EPIP 1.5 EOF - 07 Emergency Response and Recovery Director Rev. 4 EPIP 1.5 Checklist EOF - 08 Rad & EOF Manager Checklist Rev. 6 EPIP 1.5, 3.3 EOF - 09 EOF STA/OPS Liaison Checklist Rev. 0 EPIP 1.5 EOF -10 EOF-TSC Communicator Checklist Rev. 3 EPIP 1.5 EOF -1 i Support Services Coordinator Checklist Rev. 3 EPIP 1.5 -

EOF - 12 Field Team Director Checklist Rev. 0 EPIP 1.5, 3.3 EOF -13 Radiological Data Communicator Checklist Rev. 0 EPIP 1.5, 3.3

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INDEX ~~~~PAGE 3 of 7 EOF - 14 EOF MIDAS Operator Checklist Rev. 1 EPIP 1.5, 3.3 EOF - 15 Radiological Data Plotter Checklist Rev. 0 EPIP 1.5, 3.3 EOF - 16 Radiological Assessment Coordinator Checklist Rev. 1 EPIP 1.5, 3.3 EOF -17 EOF Security Access Clerk Checklist Rev. 2 EPIP 1.5 EOF- 18 EOF Staffing Accountability Roster Rev. 3 EPIP 1.5 EOF -19 Drill Announcement Message Rev. 0 EPIP 1.4, 1.5 EOF -20 Emergency Announcement Message Rev. 1 EPIP 1A 1.5 EOF - 21 Personnel Access Log Rev. 1 EPIP 1.4, 1.5 EOF -22 Registration Form Rev. 0 EPIP 14, 1.5 EOF - 23 Security Post Log Rev. 2 EPIP 1.4, 1.5 EOF -24 First Floor Security Post Description Rev. 2 EPIP 1.4, 1.5 EOF -25 Fourteenth Floor Security Post Description Rev. 11 EPIP 1.5 EOF -27 Status Update Message - EOF Communicator Rev. 0 EPIP 1.5 EOF -28 Verbal Closeout Summary Rev. 0 EPIP 1.5 EOP - 29 Written Closeout Summary Rev. 0 EPIP 1.5 EOF - 30 Status Board Rev. 0 EPIP 1.5 EOF -31 Access B adge Example Rev. 0 EPIP 1.5 EOF - 32 EOF Staff Response Rev. 3 EPIP.15 EOF -33 Recovery Issues Rev. 0 EPIP 5.2 EOF - 34 EOF Activities Rev. 0 EPIP 5.2 EOF - 35 Recovery Phase Plan Outline Guidance Rev. 0 EPIP .52 OF -. 36 RE-Entry Briefing Guide Rev. 0 EPIP 5.2 EOF - 37 RE-Entry Debriefing Guide Rev. 0 EPIP 5.2 EOF - 38 EOF Messenger Checklist Rev. 1 EPIP 1.5 ERO - 01 ERO Position Equivalency Table Rev. 0 EPIP 1.5 I

JPIC -01 JPIC Manager Checklist Rev. 4 EPIP 1.4 JPIC - 03 Alliant Spokesperson Checklist Rev. 3 EPIP 1.4

EM PL IEMEINP N PROCEDURES Rev. 137 INDEX INDEX ~~~~PAGE 4 of 7 J JPIC - 04 Technical Liaison Checklist Rev. 4 EPIP 1.4 JPIC-705 Sequence of Events Rev. 0 EPIP 1.4 JPIC - 06 Public Information Officer Support Checklist Rev. 5 EPIP 1.4 JPIC-07 Logistics Coordinator Checklist Rev. 4 EPIP 1.4 JPIC -08 Logistics Support Checklist Rev. 4 EPIP 1.4 JPIC - 09, Audiovisual Support Checklist . Rev. 4 EPIP 1.4 JPIC -11 Rumor Control Coordinator I Checklist Rev. 3 EPIP 1.4 JPIC- 12 Rumor Coitrol Event Summary Log Rev. 1 EPIP 1.4 JPIC -13 Rumor Control Coordinator H Checklist Rev. 2 EPIP 1.4 JPIC- 14 Public Rumor Control Checklist Rev. 2 EPIP 1.4 JPIC -15 News Media Rumor Control Checklist Rev. 4 EP1P 1.4 JPIC;- 16 Assistant JPIC Manager Checklist Rev. 3 EPIP 1.4 JPIC - 17 JPIC Security Access Control Checklist Rev. 3 EPIP 1.4 JPIC-18 Sixth Floor Security Post Description Rev. 2 EPIP 1.4 JPIC -19 JPIC Distribution List Rev. 2 EPIP 1.4 NOTE- I ERO Notification -Phone System Callo&t Rev. 4 EPIP 1.2.

NOTE-02 ERO Notification - Alpbanumeric Paging System Rev. 3 EPIP 1.2 Callout NOTE-03 Event Notification Worksheet Rev. 1 EPIP 1.2 NOTE-04 Plant Assembly Notification kRev. 2 EPIP 1.2 NOTE-O$ Emergency Action Level Noification Rev. 6 EPIP 1.2 NOTE-06 Plant Page for Emergency Classification Changes Rev. 1 EPIP 1.2 NOTE-07 Basic Notification Flowpath Rev. 1 EPIP 1.2 ODEF-01 ODEF Decontamination Waiting Area Rev. 0 EPIP 2.7 ODEF-02 Floor Plan for ORAIJODEF Rev. 0 EPIP 2.7 ODEF-03 Travel Route to ORAIJODEF Rev. 0 EPIP 2.7 ODEF-04 12& Avenue Entrance to ORALJODEF Rev. 0 EPIP 2.7 ORAA-01 Offsite Relocation and Assembly Area Supervisor's Rev. 1 EPIP 2.4

f. -- EMERuNMPL I M NC R Rev. 137 PAGE 5 of 7 INDEX Checklist ORAA-02 Health Physics Support for the Offsite Relocation Rev. 0 EPIP 2.4 and Assembly Area ORAA-03 Security Support for the Offsite Relocation and Rev. 0 EPIP 2.4

, Assembly-Area ORAA-04 Offsite Relocation and Assembly Area - Rev. 0 EPIP'2.4:

ORAA-05 Offsite Relocation and Assembly Area Parking and Rev. 0 EPIP 2.4i

.___ Vehicle Monitoring ', -.. , . -,

OSCO- - OSC Layout Rev. 0 EPIP 2.1 OSC-02 OSC Organization Chart Rev. 0 EPIP 2.1 OSC-03 Minimum Staffing Level Rev.1 EPIP 2.1 OSC-04 Recommended Log Entry Topics Rev. 0 EPIP 2.1 OSC-05 Emergency Event Log Sheet Rev.O0 EPIP 2.1 OSC-06 Personal Statement Concerning Incident' Rev. 0 EPIP 2.1 OSC-07 Emergency Exposure Tracking Log Rev. 0 EPIP 2.1 OSC-08 OSC Supervisor Checklist Rev. 0 EPIP 2.1 OSC-09 Health Physics Survisor Checklist , Rev. 0 -EP1P 2.1 -

OSC-10 Electrical, Mechanical, I&C Maintance Rev. 0 EPIP 2.1 Supervisor Checklist '_-__

OSC-11 EmergencyAssignment Staffing Board Duties Rev. 0 EPIP. 2.1 OSC-12; External Exposure Limits Rev. 0 EPIP 4.3 OSC-13 Guidance on Dose Limits for Workers Performing Rev. 0 EPIP 4.3 Emergency Services OSC-14 Guidelines Regarding SelectionofVolunteers Rev. 0 EPIP 4.3 OSC-15 OSC Repair Team Work Order - Rev. 0 EPIP 4.3 OSC-16 Repair Team Datasheet Flowpath Rev. 0 EPIP 4.3 PAR-01 PAR Decision Making - Recommendations Rev. 0 EPIP 3.3 PAR -02 PAR Decision Making - Flowchart Rev. 0 EPIP 3.3 PA...S&02 Onsite Assembly Locations Rev. 2 EPIP 1.3

EMERGENCPLA MPMENG PROCEDS Rev. 137 PAGE 6 of 7 INDEX PASE-05 Site Evacuation Routes Rev. 1 EPIP 1.3 SAM-01 EOP-SAG Transition Checklist Rev. 0 EPIP 2.2 TSC-01 Emergency Coordinator Checklist Rev. 3 EPIP 2.2 TSC-02 TSC Supervisor Checklist Rev. 2 EPIP 2.2 TSC-03 Site Radiation Protection Coordinator Checklist Rev. 1 EPIP 2.2 TSC-04 Technical & Engineering Supervisor Checklist - Rev. 3 EPIP 2.2 TSC-05 Quality Assurance Checklist Rev. 1 EPIP 2.2 TSC-06 Security & Support Supervisor Checklist Rev. 1 EPIP 2.2 TSC-07 Administrative Supervisor Checklist Rev. I EPIP 2.2 TSCm08 Material Management Supervisor Checklist Rev. 1 EPIP 2.2 TSC-09 TSC-CR-OSC Communicator Checklist Rev. 2 EPIP 2.2 TSC-10 CR-TSC-OSC Communicator Checklist Rev.-2 EPIP 2.2 TSC-I 1 TSC-EOF-JPIC Communicator Checklist Rev. 1 EPIP 2.2 TSC-12 ENS Communicator Checklist Rev. 2 EPIP 2.2 TSC-13 EPN Communicator Checklist Rev. 1 EPIP 2.2 TSC-14 TSC/OSC Operations Liaison Checklist Rev. EPIP 2.2 TSC-15 Radiological Support Staff Checklist Rev. 1 EPIP 2.2 TSC-16 Radio Operator - Offite Checklist Rev. 0 -EPIP 2.2 TSC-17, Radio Operator - Onsite Checklist Rev. 0 EPIP 2.2 TSC-18 TSC MIDAS Operator Checklist Rev. 0 EPIP 2.2 TSC-19 Technical & Analysis Engineer Checklist Rev. 1 EPIP 2.2 TSC-20 TSC Operations Supervisor Rev. 2 EPIP 2.2 TSC-21 Electrical Engineer Checklist Rev. 0 EPIP 2.2 TSC-22 I & C Engineer Checklist Rev. 0 EPIP 2.2 TSC-23 Mechanical Engineer Checklist Rev. 0 EPIP 2.2 TSC-24 Reactor Engineer Checklist Rev. 2 EPIP 2.2 TSC-25 SPDS Operator Checklist Rev. 1 EPIP 2.2

EEN.WN.IMRE Nq w Rev. 137 INDEX PAGE 7 of 7 TSC-26 Information Services Representative Checklist Rev. 2 EPIP 2.2-TSC-27 Fire Marshall Checklist Rev. 1 EPIP 2.

TSC-28 NRC Roles During A Nuclear Power Plant Rev. 0 EPIP 2.2 Emergency Checklist TSC-29 TSC Minimum Staffing Level Rev. 2 EPIP 2.2 TSC-30 Emergency Action Request Log Rev. 0 EPIP 2.2 TSC-31 Radio Operator Log Rev. 0 EPIP 2.2j, TSC-32 Status Board Recorder Rev. 1 EPP 2.2 TSC-33 Typical Organization of the NRC Site Team Rev. 0 EPIP-2.2 TSC-34 TSC Organization Chart - Rev. 3 EPIP 2.2 TSC-35 Assignment Form Rev. 0 EPIP 5.2 TSC-36 Deactivation Report Rev. 0 EPIP 5.2 TSC-37 Plant Operations Status Rev. 0 EPIP 5.2 TSC-38 TSC/Control RoomlOSC Activities Rev. 0 EPIP 5.2 TSC-39 TSC Clerical Checklist Rev. 0 EPIP 2.2 TSC-40 ARM Locations Rev. 0 EPIP 3.1i4.3 TSC41 PASS Capabilities Rev. 0 EPIP 3.1 TSC-42 On-Site Map Rev. 0 EPIP 3.2 TSC-43 ESB Logon Instructions (TSC/CR/EOF) Rev. 0 EPIP 2.2

EPIP 3.3 Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 1 of 25

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'ROC f Ea t ~ APPRi A I am responsible for the technical content of this procedure.

Approved by. Man r g cla Date: C/;L Manager, Emergency Planning

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sLA- **ffi.PLM~ StO~ew, anEPIP 3.3 Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 2 of 25 I

Table of Contents Page 1.0 PURPOSE ............ 3 2.0 DEFINITIONS ........... 3 3.0 INSTRUCTIONS .......... 3 3.1 PAR DECISION MAKING .3 ........................... 3 3.2 INITIAL AND PERIODIC BRIEFINGS ............................ 6 3.3 OFFSITE RADIOLOGICAL MONITORING TEAMS .........................8 3.4 DOSE PROJECTION ACTIVITIES ............................................... 10 3.5 COORDINATION OF DOSE ASSESSMENT WITH THE STATE OF IOWA ............................................... 11 3.6 DATA RECORDING AND TREND ANALYSIS FROM THE TSC ..... 12 3.7 DATA RECORDING AND TREND ANALYSIS FROM THE EOF..... 13 3.8 RE-ENTRY AND FOLLOW-UP ACTIVITIES .................................... 14 4.0 RECORDS ........................................ 14

5.0 REFERENCES

........................................ 14 6.0 ATTACHMENTS ........................................ 15 ATTACHMENT 1, EVACUATION TIME ESTIM:ATES _ . . 16 ATTACHMENT 2, WIND DIRECTION AND AFFECTED SUBAREAS POPULATIONS FOR DAEC EPZ .24 ATTACHMENT 3, WIND DIRECTION AND AFFECTED SUBAREAS . 25

EPIP 3.3 Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 3 of 25 1.0 PURPOSE (1) This procedure provides instructions for directing offsite radiological monitoring activities performed by Duane Arnold Energy Center (DAEC), coordinating such activities with those accomplished by the State of Iowa, assessing the offsite radiological impacts of an event at the DAEC, and formulating Protective Action Recommendations.

2.0 DEFINITIONS

. .(

(1 ) .MIDAS Meteorological

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Information I. ..-

and Dose Assessment System.

(2) PAR (Protective Action Recommendation) - Made to the State with regards to evacuation or sheltering of subareas within the Emergency Planning Zone (EPZ).

(3) PAG (Protective Action Guides) --Established by the Environmental Protection Agency (EPA) Reference 2.

3.0 INSTRUCTIONS 3.1 PROTECTIVE ACTION RECOMMENDATION DECISION MAKING (1) At the Initial Emergenqy Classificatlcih declaration, the on-shift chemist reports to the TSC MIDAS Computer to initiate MIDAS dose projection runs. Projected off-site doses shall be communicated.to the Control Room, until the TSC is activated.

(2) Plant conditions and/or dose projections (as available) shall be reviewed to determine:

(a) Ifthe Emergency Action Level (EAL) has changed, reclassification of the event is necessary and/or protective actions are warranted.

I - - - ~~~~~~

LI U EXAM 3.3

~~~~~~~~~~~~EPIP Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 4 of 25 (b) If the EPA Protective Action Guides (&AGs) are being exceeded and if protective actions are warranted or need to be revised.

(3) There are two tables intended to assist in the recommendation of appropriate protective actions to the State of Iowa, PAR-01 and PAR-02. The Protective Action Recommendations for emergency classification levels and radiological releases impacting the areas outside of the site boundary, are in PAR-01. The Protective Action Recommendations for Severe Core Damage or loss of control of plant functions are contained in PAR-02. All protective actions listed are appropriate for the conditions indicated but do not restrict the decision-maker(s) should it be desirable to recommend other protective actions based on the situation at the -time of the emergency.

(4) When an emergency class has been declared, or dose projections are available for radiological releases, go to PAR-01. PAR-01 allows for the

..- assessment of appropriate: protective actions based on downwind dose projections resulting from airborne radiological releases.

(a) Protective Action Recommendations shall be recorded in your log, the Status Board and NOTE-O5.

(b) To determine the subareas affected and the maximum evacuation time (if needed), refer to Attachment 1, "Evacuation Time Estimates " .

(c) Continue to work through the table as new -classifications are determined or dose projection information becomes available.

(5) If the incident is classified as a General Emergency, with core damage as specified in PAR-02, recommend the minimum protective action as given in PAR-02. PAR-02 allows for the assessment of a core melt sequence and provides appropriate protective actions based on the conditions adopted from Section G of the RTM-96.

(a) Enter the table at the top decision block which asks, 'Actual or projected severe damage or loss of control of facility".

(b) To determine the sectors affected and the maximum evacuation time (if needed), refer to Attachment 1, "Evacuation Time Estimates."

(6) Continue to work through the table as new information becomes available.

EPIP 3.3 Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 5 of 25 (7) Protective Action Rebomrfiendations should be determined (forecast weather information should be considered during all Protective Action Decision Making) by:

(a). The Operations Shift Manager/Supervisor If neither the TSC nor the EOF Is activated. This person is responsible for ensuring that Protective Action Recommendations are provided to offsite authorities.

(b) The Site Radiation Protection Coordinator once the TSC Is activated.

This person shall develop these recommendations for approval by the Emergency Coordinator. -The Emergency Coordinator shall ensure that this Information is provided to offsite authorities.

(c) -The Radiological and EOF Manager, assisted by the Radiological Assessment Coordinator, upon activation of the EOF. These persons shall assume responsibility for development and recommendation of the Protective Actions and, upon approval by the Emergency Response and Recovery Director, provide formal communication of these recommendations to offsite agencies. . -

(8) Recommend the Protective Actions as specified In PAR-01 for all declared events.

(a) If the situation is degrading such that a potential exists for declaration of a General Emergency; evarluate trends and prognosis for change to determine the need-for precautionary protective measures for the general public.

(b) Pay special attention to wind direction and speed as this may lead to a Protective Action Recommendation for other affected subareas, reference Attachment 2, 'Wind Direction and Affected Subareas'.

(9) Field readings should be used to evaluate Protective Action Recommendations. If a significant number of actual dose rates, measured in the field, are greater than those projected to be occurring at the time, consideration should be given to upgrading or expanding the current protective actions, as appropriate.

(10) Formulated Protective Action Recommendations shall be recorded on NOTE-05, 'Emergency Action Level Notification Form'.

I 11

¢  ;; ok} EPIP 3.3 Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 6 of 25 (a) The Emergency Cocrdinator/Emergency Response and Recovery Director shall approve the Protective Action Recommendations by signing NOTE-05, 'Emergency Action Level Notification Form'.

(11 ) The SRPC/Radiological and EOF Manager should release Protective Action Recommendations in the following manner:

(a) Short pre-briefing of impending recommendations and related plant conditions should be given to State EOC Dose Assessment personnel via the microwave phone.

(b) When the EOF is activated this briefing shall be followed by official recommendations being delivered via the "Administrative Hotline" within 15 minutes of recognizing the criteria.

(c) State, County, and Federal notifications shall be made in accordance with EPIP 1.2, 'Notification'.

(12) Information regarding emergency classification, plant status, offsite radiological data, Protective Action Recommendations, and response actions underway shall be provided when significant changes occur and on a periodic basis to the ERO, Linn and Benton County EOCs, the State EOC, and the NRC in accordance with EPIP 1.2, 'Notification'.

(13) If protective actions actually implemented by local and State officials differ from those recommended by DAEC, the Emergency Coordinator/Emergency Response & Recovery Director should be informed.

(14) The Protective Action Recommendations will be continuously assessed and changed, as appropriate, depending upon the changing conditions.

3.2 INITIAL AND PERIODIC BRIEFINGS (1) Prior to assuming responsibility for offsite radiological monitoring and dose assessment activities, the Site Radiation Protection Coordinator/Radiological Assessment Coordinator should obtain the following information:

(a) Effluent release information, if a release is in progress, including the release point and release concentration from the KAMAN Effluent Monitoring System.

(b) Weather forecast information. This infonnation can be obtained from the National Weather Service (phone number listed in the ETB).

~', '1'_-1~Z`;___2:... EPIP 3.3 Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 7 of 25 (c) Meteorological infornaftion, including stability class (or AT), wind speed and wind direction from the Safety Parameter Display System (SPDS). If meteorological information cannot be obtained from SPDS via the Met Tower, then call the National Weather Service phone number and request an update of the current Met conditions.

(d) The results of dose projection calculations.

(e) -Containment High Range Radiation Monitor levels.

(f) Protective Action Recommendations which have been made.

(g) On-site radiological information, post-accident sampling activities, and effluent release isotopic mixes, if available.

(h) Status of off-site monitoring activities conducted, if any, and locations of the DAEC Off-site Radiological Monitoring Teams.

(i) Plant status information and prognosis for deteriorating conditions.

Uj) The status of activation of the Off-site Radiological and Analytical Laboratory (ORAL).

(k) The status of activation of the Off-site Radiological and Assembly Area (ORM)., , ., ,-,

(2) The Site Radiation Protection Coordinator should summanze this information, advise the Emergency Coordinator of pertinent points discussed, and brief the Radiological Assessment Group.;

OR The Radiological Assessment Coordinator should summarize this information, advise the Radiological and EOF Manager of pertinent points discussed, and brief the Radiological Assessmernt Group.>

(a) The Radio Operator/Field Team Director should ensure that the Offsite Radiological Monitoring Teams are apprised of pertinent information regarding plant potential radiological problems expected.

(b) Caution should be exercised In relaying Information to teams over the radio, since the radio transmission becomes public information. Only transmit information that Is necessary for the field teams to perform their duties safely and information that is made public through news releases.

I ik 41WI '",EPIP 3.3 Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 8 of 25 (3)-. -The Radio Operator should ensure that the meteorological and field team information on the DAEC EPZ maps/status boards are updated and maintained. Items such as the following should be considered for display.

OR The Field Team Director should ensure that the Radiological Data Plotters display the following information on the DAEC EPZ maps/status boards.

(a) Wind direction (b) Wind speed (c) Stability class (d) Weather forecast information (e) Plume width and centerline (f) Team locations (g) Survey results at selected locations and an outline of the subarea Protective Action Recommendations as necessary.

(h) Projected TEDE doses or dose rates in the plume path (i) Projected thyroid doses or dose rates in the plume path (4) Additionally, the Radiological Data Plotter in the EOF should display selected radiological information obtained by the State monitoring teams, as reported by the State Field Team Captain in the EOF.

3.3 OFFSITE RADIOLOGICAL MONITORING TEAMS (1) Offsite Radiological Monitoring Teamsshould be Initially briefed and dispatched in accordance with EPIP 3.2, "Field Radiological Monitoring."

(2) In preparation for directing the Offsite Radiological Monitoring Teams, the Radio Operator should:

(a) Conduct a radio check with the Teams and verify their locations.

(b) Advise the Teams of the latest radiological and plant status information, as necessary to perform their duties safely.

(c) Inform the Site Radiation Protection Coordinator of readiness to assume control of the Offsite Radiological Monitoring Teams.

(3) Direction and control of the Offsite Radiological Monitoring Teams should be done in accordance with the directions given in EPIP 3.2.

(4) In preparation for assuming control of the Offsite Radiological Monitoring Teams, the Field Team Director should:-

(a) Contact the TSC Radio Operator and inform them of the intent to establish contact with Teams.

(b) Conduct radio check with the Teams and verify their locations.

(c) Advise the Teams of the latest radiological and plant status information, as necessary to perform their duties safely.

(d) Inform the Radiological Assessment Coordinator of readiness to assume control of the Field Radiological Monitoring Teams.

(5) When the EOF has been activated, the Radiological Assessment Coordinator should contact the Site Radiation Protection Coordinator and advise that the EOF is ready to assume control of the Offsite Radiological Monitoring Teams.

(a) The Site Radiation Protection Coordinator should Inform the Emergency Coordinator that control of the field radiological monitoring teams and dose assessmenit has been'transferred to the EOF.

(b) The Radiological Assessment Coordinator should then advise the

-Radiological aind EOF Mah'a'ger that the' Radiological Assessment Group Is ready to assume responsibility for offslte monitoring and dose assessment activities. .

(c) The Field Team Director (in the EOF) should follow up with each Team and the TSC Radio Operator and advise them that all further communications should be conducted with the EOF.

(d) Transfer of responsibility should be recorded In both the TSC and EOF Logs.

I II.

ups- ;gg ~~~~~~~~~~~EPIP 3.3 Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 10 of 25 3.4 DOSE PROJECTION ACTIVITIES (1) Until the TSC is activated, the Operations Shift Manager/Supervisor, as the Emergency Coordinator, is responsible for assuring dose projections by the on-duty shift chemist are performed.

(a) The results of these projections will normally be summarized for the Site Radiation Protection Coordinator as part of the initial briefing.

(2) Until the EOF is activated, the Site Radiation Protection Coordinator and/or the Operatiors Shift Manager/Supervisor are responsible for performing dose projections.

(a) The results of these projections will normally be summarized for the Radiological Assessment Coordinator as part of the initial briefing.

(3) Dose projection calculations will be performed by the MIDAS Operator using one of the following methodologies:

(a) MIDAS computer, MIDAS Instruction Manual User's Guide.

(b) MIDAS Backup on the Personal Computer.

(c) MIDAS Laptop Personal Computer, (4) Dose projections will normally be performed in accordance with the MIDAS instructions in the MIDAS -Usercs guides- If MIDAS;is unavailable, the options below will be reviewed: by theSite Redi ation Protection Coordinator/Radiological Assessment Coordinator to determine the appropriate back-up methodology.

(a) If real-time data collection in MIDAS; is not functional, the TSC MIDAS Operator should coordinate directly with the Back Panel Communicator to

- determine updated radiological and meteorological parameters applicable to actual or potential release rates.

(b) If there is a loss of MIDAS in the TSC consider using the following:

(i) MIDAS Backup on the Personal Computer (ii) Use of MIDAS Laptop Computer

"IIn, iEPIP 3.3 Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 11 of 25 (c) If real-time data collection in MIDAS Is not functional, the EOF MIDAS Operator should coordinate directly with the Site Radiation Protection Coordinator to determine updated radiological and meteorological parameters applicable to actual or potential release rates.

(d) 'If there is a loss of MIDAS in the EOF consider the following:'

(i) Transfer of dose assessment baci'o the TSC (ii) Use the MIDAS Backup on theXPersonal Computer (iii) Use of MIDAS Laptop Computer (5) Following review'of the latest dose projection,-the Site Radiation Protection Coordinator should brief the Radio Operator on the magnitude of the projected doses and the need to adjust offsite radiological monitoring activities.

OR Following review of the latest dose projection, the Radiological Assessment Coordinator should brief the Field Team Director on the magnitude of the projected doses and the need to adjust field radiological monitoring activities.

(6) If Field Team readings are significantly higher than those projected by MIDAS, consider the possibility of an unmronitored release.

3.5 COORDINATION OF DOSE ASSESSMENT WITH THE STATE OF IOWA (1) Upon activation of-the EOF, the Radiological Data Communicator shall verify that the uRad Data Line 3 is established and operable or contact the State EOC and request that,it be established. . i.:--

(2) Once established, the Radiological Data Communicator shall maintain communications with.the State EOC and the Benton and Linn County EOCs.

-(3) Radiological release, dose projections, and meteorological data from the electronic MIDAS print out shall be provided to the State in order for the State to conduct dose assessment and projection activities.

(4) The Radiological Data Communicator shall request the State's dose projection results as they become available, and provide this information to the Radiological Assessment Coordinator.

I i.

. . it'd ;9;~~~~It iA d

-40 EPIP 3.3 Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 12 of 25 3.6 DATA RECORDING AND TREND ANALYSIS FROM THE TSC (1) The Site Radiation Protection Coordinator should initiate and ensure conduct of trend analysis.

(a) Parameters of interest include KAMAN System Effluent Monitor readouts, analyses conducted ot effluent stream particulate filters and iodine cartridges, meteorological data, ARM levels and Containment High Range Radiation Monitor levels.

(b) ARM and Containment High Range Radiation Monitor levels are of dual importance due to their direct impact on response activities within the plant and their significance with respect to determining the quantity of radioactive material potentially available for release offsite.

(2) An estimate of fuel failure can be determined by direction found in the PASAPs.

(3) An estimate of the potential release rate can be determined by using the PASAPs.

(4) The Site Radiation Protection Coordinator should evaluate the trending plot periodically to determine if any significant trends are apparent.

(5) The Emergency Coordinator and the Radiological Assessment Team should be periodically advised of the current radiological status, significant trends, and potential implications.

(a) The SRPC should ensure to periodically inform representatives of the, State and Federal Government of the current rpdiological status, significant trends, and potential implications (prior to operation of the EOF).

EPIP 3.3 Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 13 of 25 3.7 DATA RECORDING AND TREND ANALYSIS FROM THE EOF (1) The Radiological Assessment Coordinator or his designee should trend the following information:

(a) Projected TEDE and Thyroid dose rates at the following locations:

yr.

(I) Site Boundary (ii) Two Miles

-(iii) Five Miles " '  ;

(iv)Ten Miles

.(v) Greater than ten miles (vi) Location(s) of peak Whole Body and Thyroid dose rates if other than-at one of the above locations.

(b) Containment High Range Radiation Monitors levels for both the Drywell and Torus (2) An estimate of fuel failure can be determined by using the PASAPs.

(3) An estimate of the potential release rate can- be determined using the PASAPs.

(4) The Radiological and EOF Ma'nage and'the 'Radiological Assessment Group should be periodically advised of the cufretht radiologicalfstatus, significant trends, and potential implications.;

(a) The Radiological and EOF Manager should periodically inform the EOF staff and representatives of local, State and Federal governments of the current radiological status, significant trends, and potential implications.

(b) The Field Team Director should ensure that the Offsite Radiological Monitoring Teams are provided updated information periodically.

(5) The trending of offsite doses can be utilized as an estimation of integrated dose(s) to the general public throughout the course of the event.

III WINi MEPIP 3.3 Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 14 of 25 3.8 RE-ENTRY AND FOLLOW-UP ACTIVITIES (1) Once releases have been terminated, the Radiological and EOF Manager, Radiological Assessment Coordinator and Site Radiation Protection Coordinator should coordinate with local, State and Federal officials to identify the activities required prior to re-entry of the general public into areas that have been evacuated.

(2) As directed by the Emergency Response and Recovery Director, the Radiological and EOF Manager should establish an environmental monitoring program as part of the Recovery Plan to more adequately quantify the impact of this release on the environment.

(a) As a minimum, this program should include sampling and analysis of milk, surface water, vegetation, and soil in the affected area surrounding DAEC.

(b) This program should be structured such that it complements the routine DAEC environmental sampling program.

(c) This program should be coordinated with the State's environmental program.

4.0 RECORDS (1) All logs forms and other pertinent information shall be maintained in accordance with EPDM 1007, (exception is for material generated during drills and exercises.)

5.0 REFERENCES

(1) DAEC Emergency Plan (2) Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA-400-R-92-001) i

___1/

IEPIP 3.3 Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 15 of 25 (3) DAEC Radiological Engineeridg Calculation 93-022-H; dated December 17, 1993 (4) EPIP 3.2 "Field Radiological Monitoring' (5) EPIP 1.2 "Notification" (6) Response Technical Manual (RTM) 1996 Section G.

6.0 A1 TACHMENTS.

(1) Attachment i -Evacuation Time Estimates

• I (2) Attachment 2 -Wind Direction and Affected Subareas.

IM$- -RO -k, .EPIP 3.3 Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 16 of 25 ATTACHMENT I EVACUATION TIME ESTIMATES (1) Select the appropriate table for the event scenario (Summer or Winter, Midweek or Weekend, Midday or Evening)

(2) Select the section of the table corresponding to the extent of the evacuation recommendation (Within 2, 5, or 10 miles, or to the EPZ boundary).

(3) Select the wind range for the expected wind direction, and read across for the evacuation time estimate under the expected weather condition for both the general population and special population (special population consists of those at hospitals, nursing homes, and other residential care facilities).

(4) Following the tables are evacuation time estimates for two recreational events occurring annually within the DAEC EPZ: the All-Iowa Fair and the Cedar Rapids Freedom Festival.

(5) Times in the tables are given in hours and minutes (i.e., 03:35 = 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, 35 minutes).

NOTES-For Summer or Winter Weekend Evening times, use the Summer or Winter Midweek Evening times, respectively.

Summer defined as, Memorial Day through Labor Day. Winter Idefined as Labor Day to Memorial Day.

( ( (

Tabb 5.5 Evacuation Times Esimates for Scena s 1-8 0

Region Iu.-

1 2 3 4 -6 .8 7 8 sumer SaM; smer Suumer Su Summer smer Sner I

Summer

. ai Wrld -eedWled Wheke V" YVbel Wbekdy Weekdy MNday Wdday Eveft t-e9 Mda Mki Etng eoeg

_ _ _ _ _ _ sF*r Poo - Fsr Poor Fair Poor hlr Poow 3

1 - . 1 245 2-45 2.45 3:00 245 3:15 245 3:15 2 1-8 5:30 5:45 5:15 5:45 5:45 .0.0 5:15 5:30 I

3 1-24 10:45 11:45 11:15 11:45 10.30 11:15 - 1015 1100 4 1,2,8 300 3:45 3:15 4:15 3:30 3:45 3:15 3.30 4:15 3:30 3.45 3:15 330 In 5 1.2,3 3:00 ' 3.45-: 3:15 6 123,8 3D00' 345 3:15 4:15 3:30- 3.45 3:15 ' :3:30 7 1Z3,4 3:00 3:45 3:15 415 3:30 3:45 3:15 330 8 1,3,4 t:00 3:45' 3D00 4:15 3:30 3:45 3:15 3:30 p Ig 9 1,3,4.5 3:15 400 -3:15 4-00 3:30: 345 3:15 3:30 10 1,4,5.6 t15" '400 3:15 4:00 3:30 -3:45' 315 33 11 1j5,6,7. 3:15 4:00 3:15 4:00 3:30 3A45' .315 3:30 12 1,7.8 3:00" '4:00 300 4.00 3:45 4:00 3'30 3:45 .1 13 1,5,8,7,17.20 4:15 5:15 4:15 4:30 4:30, 4:45. 4:00 4:15 9 14 1,56,7,1821 ':15 .5:15 4'15 4:30 4:30 4:45 '4.00 *4:15 r",

15 1,7,851.1 4:00 -5:15 4:00 4:15. 4:30. 45-- 5 4.D0 : 4:15 la 1,7,8,1.2 4.D0 515 400 4:15 4:30 4:45 4:00 4:5 -

17 . 1,7,8,9,-22 ' 4.0 ' 5:45. 4.00 4:15 4:30 4A5 4:00 4:15 18 1.2,8,9,10,21,22 40 5:45 4:00 4:15 4:30 4A4 ' 40 4:16 19 1,2,3,8-12,21 40 . 545 4:00 4:15 4:30 4:45 '4-00  : 4:16 20 1.2,3,-13,22 4D00 5:45 400 4:15 4:30 4:45 4:00 4:15 21 1*3,10-13 345 A 5:45 3.45 4:00 4:30 4:45 4:00 4:15 22 123410-14 . 4:30 .:45 4:30 5:00 4:45 .5:' 4:30 5.-C0 23 1,45,6,15-182324 9.45 10:15 9:45 10:00 7:45 8D0 7:30 7:45

• 24 1,5,6,7,1819,24 :00 10:00 90 900 7:30 800 7:30 7:45 25 1,3,4,12-1523 M00 10:00 00 30 7:45 8:00' 7:30 7:45 28 1,3,4,5,12-6234 10:30 11:45 11:30 11:45 '10.5 11:00 10:0 10.45 27 1,3,4,5,13-1723,24 10:45 11:45 11:15 11:45 10:45 11:00 10:30 10.45-28 1,4,56,14-18232 103 11-45 11:15 11:45 10.45 11:0 1030 10:45

EPIP 3.3 Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 18 of 25 ATIACHMENT 1 (Cont.)

EVACUATION TIME ESTIMATES FOR WINTER WEEKEND MIDDAY. WINTER WEEKEND EVENING.

WINTER WEEKDAY MIDDAY. WINTER WEEKDAY EVENING SCENARIOS I1 I!

I 11

l Gus j}L3 EPIP 3.3 Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 19 of 25 ATTACHMENT I (Cont.)

EVACUATION TRME ESTIMATES FOR SUMMER WEEKEND EVENING SCENARIOUS K

I v OMM"12151811 co ,W W VV-V-lw-lc

1. ,* I- q- I- v-W.

W-. q Vo I.

V1 vullWVPt.

Ii II

'F-

.. .. ...

• n

• t ,  :

. . - - . W. . E .

• R - - *: - .

. . .. , . , . j .. . .. .. . ..

\-~~~~~~4 EPI P3.3 Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 20 of 25 ATTACH1I1ENT 1 (Cont.)

EVACUATION TIME ESTIMATES FOR SCHOOLS IN WITR FAIR WEATHER SCENARSOUS 8 Q o a 8-iI. * . q v.-

SDi C) o T: "-

0 R-ed 0 I- V. q fSD SD! SD q 8 !49 ID D 1 0 *~ p 4 In 0

8 I! I* a5.

d a O a ,9 0;

. .8 a6

.412 4646

.- 5 a boa-51R is 6 6 I  ! n .1 .5 ~

00~ o) is  ; 006a

'9 A- 0 . 6.9 0 . 6 0 09 I- a a 40 codei 46 o6 I

a;

.!9 . . 46 46 46 I 3? SO SD is

',-" *  ; V.Q- 46 0 aD

.46 oId ! * .

aI to to I

I W.

0-v-bbv

.6 0 0 0

(9

• Cl S vt I. I-I I .

8's .

'5-

-V:.

v

.Bj . 8 8 8! . 8' 5 I

i'i" -.

i- Viii Viii %r ii

( ( (:

Table5.11. EvCUSoftmesematesforschools in terpoorwetr(based on scenatlo*14).

1st Trl 2nd Tfip DTueI ... Tmvem EPZ lTRCto I. eel .-

MobWIfftn to LofEtng to EPZEdgeto Unfa EPZ EPZEdge Long toEPZ Subaea time (httmQ.)mhools tin" edge TRM Ia Edge to Scho tim edge ETE I

2.

3..

4 100 0:20 015 2:00 0.30 0:30 0.30 0:30 0:15 1:30 720 5 1:00 0:20' O.1-S -230 0.45 0:30 0:30 015 215 9.05 6'

7. 100 020- 015 2.00 0.35 0:30 0.35 0.30 0:15 1:30, 7:30 8

9 1 00 020 0:15 1:15 0 35':* 0.30 0:35 0 30 0.15 0:45 5:45 II ii; 10 II 12 1t00 0:20 015 1:15 O:30 0:30 0:30 0:30 0:15 0:45 5:50 13 14 ' too: 0:20t 0:15 2:00 0:35' 0:30 0 35 0:30

. 0:15 1:45 7:45 1s 1:00 0:20 0:15 +/-30 0.40 0:30 O40 0.30 015 - 2:00 8:40 16 100 0:20- 015 215 0:40 0:30' 0:40 0:30 0:15 1:45 8:10 17

18. 1:00 020 0:15 1:15 0.40 0:30 0:40 0:30 0:15 0.45 B:10 19 20 _ . . .

21

. 22' -100 0:20 0:15 1:15 0:25 0:30 0:25 0:30 ' 015 0-45 5:40 I 23 1 00, 020 0:15 1:45 0:35 0:30 0:35 030 ' 0:15' 1:30 7:15 24 1 00 0:20 0:15 215 0:35 0:30 0:35 0:30 0:15 1:45 aoo

K ~~~~~~~~~~~~EPIP3.

Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 22 of 25 I

ATTACHMENT 1 (Cont.)

EVACUATION TIME ESTMATES FOR HEALTH-RELATED SPECIAL FACILITIES UNDER FAIR WEATHER SCENARIOS I. AI

~4?4N 6I I-I-l W a 9 515ti ad id i-i i i-i SN* .( .9 N In to W3 0 to w q- vq- I- sI 0 2 21 rV-- rv-r r- rv-

• 1 I.'

R as a a0 4a vc d 4 oe a

Ii :1' is 4-'T-C',id e; s I-'v-i~I 26R

~c ORall a

vI I§i II 1~

ad i $ . I a. a II po to 4- a 4 a t is-Ul) 4 c) to .S 4l X s I.-

_ _ _ _ _ _ _ _ _HEPIP

_ _ _ _ _ _ _ _ _ _ _ _ 3.3 Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 23 of 25 ATTACHMENT I (Cont.)

EVACUATION TIME ESTIMATES The evacuation time estimates for the Cedar Rapids Freedom Festival consider an I evacuation of the general population within the entire DAEC Emergency Planning Zone (Subareas 1-24) this event Is in progress. I Cedar Rapids Freedom Festival: 11:15 I rI I .

i.;

itI z.;.

EPIP 3.3 Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 24 of 25 I

ATTACHMENT 2 l WIND DIRECTION and AFFECTED SUBAREAS Wind direction and affected subarea populations for the DAEC EPZ (based on Table 5.2 from the Evacuation Time Estimate Study report).

Subareas (Population)

Wind (degrees) 0-2 2-5 5-10 10-EPZ Total Direction Miles Miles Miles edge Population N (348.76-11.25) I 4,5,6 15,16,17,18 23,24 (124,968)

(1,134) (1,781) (64,839) (57,214)

NNE (11.26-33.75) 1 5,6,7 16,17,18,19 24 (64,002)

(1,134) (5,491) (35,237) (22,140)

NE (33.76-56.25) 1 5,6,7 17,18,19,20 (10,690)

(1,134) (5,491) (4,065)

ENE (56.26-78.75) 1 5,6,7] 18,19,20,21 (9,439)

(1,134) (5,491) (2,814)

E (78.76-101.25) 1 7,8 18,19,20,21 (5,659)

(1,134) (1,711) (2,814)

ESE (101.26-123.75) 1 7,8 19,20,21,22 (5,524)

(1,134) (1,711) (2,679)

SE (123.76-146.25) 1 7,8 9,20,21,22 (7,566)

(1,134) (1,711) (4,721)

SSE (146.26-168.75) 1 2,8 9,10,21,22 (6,451)

(1,134) (559) (4,758)

S (168.76-191.25) 1 2,3,8 9,10,11,12,21,22 (8,140)

(1,134) (1,262) (5,744)

SSW (191.26-213.75) 1 2,3 9,10,11,12,13,22 (7,863)

(1,134) (1,019) (5,710)

SW (213.76-236.25) I 2,3 10,11,12,13 (4,250)

(1,134) (1,109) (2,097)

WSW (236.26-258.75) I 2,3,4 10,11,12,13,14 (41,714)

(1,134) (3,523) (37,057)

W (258.76-281.25) I 3,4 12,13,14,15 23 (105,755)

(1,134) (3,207) (66,340) (35,074)

WNW (281.26-303.75) I 3,4,5 12,13,14,15,16 23,24 (163,388)

(1,134) (7,160) (97,880) (57,214)

NW (303.76-326.25) I 3,4,5 13,14,15,16,17 23,24 (164,525)

(1,134) (7,160) (99,017) (57,214)

NNW (326.26-348.75) I 4,5,6 14,15,16,17,18 23,24 (164,674)

(1,134) (7,160) (99,790) (57,214)

EPIP 3.3 Rev. 19 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 25 of 25 ATTACHMENT 3 i WIND DIRECTION AND AFFECTED SUBAREAS . . - .7 .

_<<<<<<<<<<<<<<<<< MILES OUT >>>>>>>>i>>>>>>>>>>>

Wind Direction 0-2 2-5 5-10 10 - EPZ N'(348.76- 11.25) 1 4,5,6 15,16,-17,-18 23, 24 NNE (11.26 - 33.75) 1 5,6,7 16,17,18,19 24 NE (33.76 - 56.25) 1 5,6,7 .17,18,19,20 ENE (56.26 - 78.75) 1 5,6,7 '18,19,20,21 E (78.76 - 101.25) 1 7,8 18,19,20,21 ESE (101.26 - 123.75) 1 7 8 19,20,21,22 S\_.>23.76 - 146.25) 1 7,8 9,20,21,22 SSE (146.26- 168.75) 1 2,8 9,10,21,22 S (168.76 - 191.25) 1 2,3,8 9 10,11,12,21,22 SSW (191.26 - 213.75) 1 2,3 9,10,11, 12,13,22 SW(213.76 - 236.25) 1 2,3 10,11,12,13 WSW (236.26 - 1 2,3,4 10,11 *,;12,13,14 2 58 .75)_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

W (258.76 - 281.25) 1 3,4 .12,13,14,15 23 WNW (281.26 - 1 3,4,5 12,13,14,15,16 23,24 303.75) _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

NW (303.76 - 326.25) 1 3,4,5 13, 14,15,16,17 23,24 I NNW (326.26-34B.75) 1 4,5,6 14,15,16,17,18 23,24 I

r Ire.~~~~~~~~~~~~~~~~~~~~EO0 ERO POSITION EQUIVALENCY TABLE Paev 0f ERO POSITION EQUIVALENCY TABLE (1) ERO Position Equivalency Table: A table used to provide guidance for determining which ERO positions can be called upon to support other ERO positions where skil sets and training are similar.

(a) Inthe event that timely augmentation with qualified ERO responders becomes suspect, the ER&RD and EC have the authority to appoint plant personnel to staff these positions until a qualified responder can respond (reference E-Plan 'B3 & EPIP 1.5, 2.2)

(b) This ERO Equivalency Table provides a subset of positions with similar skill sets to allow the ER&RD or EC to determine who should staff what.

NOTE Staffing via the Equivalency Table shall only be until a qualified responder is available.

Positions staffed by the Equivalency Table shall receive increased direction & oversight, and shall be appropriately documented.

(2) When staffing ERO positions with additional staff, use this table as follows:

(a) Determine the ERO position you wish to staff (b) Determine if additional ERO personnel equivalent to the open position are available (i) If an afternate is not available for the open position, staffing the open position with anyone else is satisfactory.

However, as much as possible, adherence to this equivalency table should be maintained.

(c) Staff the open ERO position with the additional ERO staff member (d) Provide additonal direction and oversight to this staff member (e) Continue to locate qualified ERO staff members for the given position.

(3) This staffing decision shall be documented in the logs of the ERO Staff member making the decision.

• - REFER TO ETB FOR QUALIFIED STAFF ERO-01

ADMIN SUPV TSC CLERICAL / SECURITY SUPV ASST JPIC MANAGER WEBMASTER AV SPECIALIST LOGISTICS SUPPORT / LOGISTIC COORDINATOR BACKPANEL COMM EDS / POOL FROM TSC BENTON-COUNTY LiAISON ANY STATE / COUNTY LIAISON CHEM TECHS CHEM STAFF CR-TSC COMM TSC-CR COMM DAEC SPOKESPERSON JPIC MANAGER EMERGENCY COORDINATOR TECH & ENG SUPV / TSC OPS SUPV ELECTRICAL ENGINEER ANY ERO ENG ELECTRICAL SUPV OSC / IC MM

/ SUPV

• - REFER TO ETB FOR QUALIFIED STAFF ERO-01

ELECTRICIANS . EM ENGJ EM SUPV EOF HPN COMM TSC HPN l TSC ENS COMM EOF MIDAS OPERATOR RAD PRO STAFF EOF OPS LIAISON TSC OPS SUPV / TSC OPS LIAISON / OSM-CRS-STA ER&RD -NONE

.~

FIELD TEAM DIR RAD SUPPORT STAFF I RAC FIELD TEAM DRIVER

• ANYONE WITHA DRIfVERS LICENSE FIELD TEAM MONITOR

• RAD PRO STAFF HP SUPV SRPC HP TECHS

• HP STAFF I&C ENGINEER ANY ERO ENG I&C SUPV OSC /IC /EM SUPV I - . , 7 -- -. , .i--. : . -%.", I

• - REFER TO ETi FOR QUALIFIED STAFF : : I ERO-01

- ..... T,'.7f,-T - -~~~~~~~~~~W

<.-~~~~~~~ *~~~~~L ~~~~~~ ERO-01 ERO-Ol~~~~~~~Ni Rev. 0 ERO POSITION EQUIVALENCY TABLE Page 0of I&C TECHS IC ENG /IC SUPV INFO SERVICES REP EDS FROM TSC OR EOF JPIC MGR ASST JPIC MGR / TECH LIAISON JPIC SECURITY ACCESS CLERK LOGISTICS SUPPORT / P1O SUPPORT LINN COUNTY LIAISON ANY STATE I COUNTY LIAISON LOGISTICS COORD JPIC MGR I ASSISTANT JPIC MGR LOGISTICS SUPPORT SPECIALIST PlO SUPPORT MECHANICAL ENGINEER . ANY ERO ENG MECHANICAL SUPV OSC IC / EM SUPV MECHANICS MM ENG / MM SUPV MESSENGERS POOL EOF NEWS MEDIA RUMOR CONTROL ASST JPIC MGR

• - REFER TO ETB FOR QUALIFIED STAFF ERO-01 QZ-

FT ~~ERO PI T POSITION EQUIVALENCY TABLE Rev. 0 I ORAA SUPV . ANY RAD PRO STAFF ORAIJODEF SUPV -ANY RAD PRO STAFF OSC STAFF (RADWASTE) . .. .POOL TSC OSC SUPV ....... .IC /MM I EM /HP SUPV.-

PIO SUPPORT LOGISTICS SUPPORT I LOGISTISC COORDINATOR RAC RAD & EOF MGR _. - I RAD & EOF MGR .SRPC--.

RAD DATA PLOTTER . .  : . INFO SERVICES -

RAD STATUS COMM POOL EOF RAD SUPPORT STAFF SRPC / TSC OR EOF HPN COMM RADIO OPERATOR FIELD TEAM DIR / RAD SUPPORT I SRPC I HPN RUMOR CONTROL COORD ALLIANT-CUSTOMER SERVICE SUPV

. ,s,

. I I .

• - REFER TO ETB FOR QUALIFIED STAFF p I .. .1 ..

• I- rERO-01

RX ENGINEER STA SECURITY & SUPPORT SUPV SECURITY LT.

SECURITY ACCESS CLERK POOL EOF SPDS OPERATOR ANY ERO ENG SRPC HP SUPV STATE LIAISON ANY COUNTY LIAISON SUPPORT SERVICES COORD POOL FROM EOF TECH & ANALYSIS ENG ANY PRA QUALIFIED ENG OR STA TECH & ENG SUPV ANY ERO ENG TECHNICAL LIAISON ASST JPIC MGR I ANY ENG OR OPS LIAISON / SPOKESPERSON TECHNICAL RECORDER TSC DED COMMUNICATOR / ANY STATE & COUNTY LIAISON TSC CLERICAL PLANT POOL

• - REFER TO ETB FOR QUALIFIED STAFF ERO-01

TSC DEDICATED COMM TSC-CR / CR-TSC, COMM TSC-CR COMM. CR-TSC COMM TSC-EOF COMM SECURITY LT / POOL TSC-OPS LIAISON . EOF OPS LIAISON / TSC OPS SUPV/ OSM-CRS-STA WAREHOUSE SUPV . . ANY ERO ENG.-

..-IC,:

j o wlI: ....

I -

- REFER TO ETB FOR'QUALIFIED STAFF . i . 1, ERO-01 E'O