ML022480415

Revised Emergency Plan Implementing Procedures

ML022480415
Person / Time
Site:	Duane Arnold
Issue date:	08/27/2002
From:	Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TAM-54
Download: ML022480415 (109)

Text

NMC DAEC EMERGENCY PLANNING DEPARTMENT PROCEDURE TRANSMITTAL ACKOWLEDGEMENT MEMO (TAM-54)

To: Hi~P.c-/ ý-N( IbOCAofALýA CO'J-rok 1b'k "5"o- ./

Re: ~pP Controlled Copy Distribution (Copy W)

PSM

Title:

n/a Distribution Date: 08/27/2002 Effective Date of Change: 09/02/2002 Return by: 09/16/2002 Please perform the following to you assign manual. If you have any questions regarding the TAM please contact Don A. Johnson at 319-815-7872.

REMOVE INSERT EPIP Table of Contents Revision Rev. 128 Rev. 129 EPIP 1.2 (PWR: 17656) Rev. 26 Rev. 27 Rev. 11 Rev. 12 EPIP 3.1 (PWR: 17658)

EPIP 3.2 (PWR: 17662) Rev. 12 Rev. 13 EPIP 3.3 (PWR: 17664) Rev. 17 Rev. 18 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 Personnelonly" Date TAM returned EPTools updated:

D-,rie 4 1.f -)

REMOVE INSERT EPIP EAL-01 (PWR: 17646) Rev. 1 Rev. 2 Update of necessary, may already be done.

EPIP EAL-02 (PWR: 17647) Rev. 1 Rev. 2 Update of necessary, may already be done.

EPIP EAL-03 (PWR: 17649) Rev. 1 Rev. 2 Update of necessary, may already be done.

Rev. 1 Rev. 2 EPIP EAL-04 (PWR: 17651)

Update of necessary, may already be done.

Rev. 2 Rev. 3 EPIP EOF-05 (PWR: 17910)

Rev. 5 Rev. 6 EPIP EOF-08 (PWR: 18270)

Rev. 1 Rev. 2 EPIP EOF-11 (PWR: 17909) n/a Rev. 0 EPIP EOF-38 (PWR: 18059) n/a Rev. 0 EPIP EOF-39 (PWR: 18060)

Rev. 2 Rev. 3 EPIP NOTE-01 (PWR: 17645) n/a Rev. 0 EPIP NOTE-07 (PWR: 17657) n/a Rev. 0 EPIP PAR-01 (PWR: 17665) n/a Rev. 0 EPIP PAR-02 (PWR: 17669) n/a Rev. 0 EPIP TSC-41 (PWR: 17660) n/a Rev. 0 EPIP TSC-42 (PWR: 17663)

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EMERGENCY PLAN -IMPLEMENTING PROCEDURES- Rev. 129 SINDEX PAGE 1 of 7 Procedure Title Revision Date Number 1.1 Determination of Emergency Action 19 09/12101 Levels 1.2 Notification 27 - 9/2/02 1.3 Plant Assembly and Site Evacuation 9 69/12/01 1.4 Release of Emergency-Related 3 09/12/01 Information _ _,,

1.5 Activation and Operation of the EOF 3 -- 10116/00 2.1- Activation and Operation of the OSC 13 - 09/12/01 2.2 Activation' and Operation of the TSC -22 02/22/02 2.3 Operation of the FTS-2001 Phone 5 09/12/01 Network 2.4 Activation and Operation of the ORAA 8 09/12/01 2.5 Control Room Emergency Response 14- 1015/01 Operation ,--,,_,,

2.6 Activation and Operation of the ORAL - 10/15/01-2.7 Activation and Operation of the ODEF 6 10/15/01 2.8 Security Threat 1 11/16/01 3.1 In-Plant Radiological Monitoring -7. , 12 9/2/02 3.2 Field Radiological Monitoring 13 9/2/02 3.3 Dose Assessment and Protective 18 -9*2/02 Action .

4.2 First Aid, Decontamination and Medical 7 8/23/02C

_ Support 4.3 Rescue and Emergency Repair Work 11 8/23/02 4.5

• o Administration of Potassium Iodide (KI) .- 6 10/15/01 5.2 Recovery and Re-entry . 9 10/15/01

1- 1 1, P

SEMERGENCY PLAN ýIMPLEMENTIN

G. PROCEDURE

S&i 'Rev.' 129 INbEX PAGE 2 of 7 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. 2 EPIP 1.1 EAL-02 Fission Barrier Table Rev. 2 EPIP 1.1 EAL-03 Hazards & Other Conditions Affecting Plant Safety Rev. 2 EPIP 1.1 EAL-04 System Malfunction Table Rev. 2 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. I EPIP 1.5

' Activities.

EOF - 05 EOF - 06 EOF Information Services Representative Checklist DAEC Key Parameter Log Rev. 3 EPIP 1.5 I

Rev. 0 EPIP 1.5 EOF - 07 Emergency Response and Recovery Director Rev. 3 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 - 11 Support Services Coordinator Checklist Rev. 2 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 Ij

I EMERGENCY PLAN. MPLEMENTING PROCEDURES- ,R'v",129.%- :,,.

GE3 of 7 K>

EOF - 14 EOF MIDAS Operator Checklist Rev. 1 EPIP 1.5; 3.3, EOF - 15 Radiologi6al Data Plotter Checklist . .. Rev. 0 - EPIP_ 1.5,3.3 EOF - 16 Radiological Assessment Co6odinatof-Checklist - Rev. I - EPIP 1.5, 3.3, EOF- 17 EOF Security Access Clerk Checklisf> .Rev, 1.... .. EPIPI1.5 EOF 18 EOF Staffing Accountability Roster - . .. Re. 2. EPIP'1.5 EOF 19

-- Drill Announcement Message .Rev'O. 0PIP 1.4, 1.5 EOF -20 Emergency Announcement Message, Rv.PIP 1.4,15 EOF -21 Personnel Access Log ,Rev. 1 -. EPIPI.41.5 EOF-22 Registration Form .. Rev. 0, ... EPIP 14,1.5 EOF - 23 Security Post Log R ev.1 - "EPIP 1.4, 1.5 EOF- 24 First Floor Security Post Description , Re v. EPIP 1.4,1.5 EOF-25 Fourteenih Floor Security Post Description ,. Rev. -100 " EPIP 1.5 EOF - 27 Status Update Message - EOF communicator - Rev. -. EPIP 1.5 EOF - 28 Verbal Closeout Summary Rev, 0 EPIP 1.5 EOP - 29 Written Closeout Summary', ' .,- , *' ' Rev: 0 EPIP L.5 EOF-30 Status.Board' , "-:y Rev.X0i) >, . EPIP 1.5 EOF-31 Access Badge Examnple it ,'. .,".Rey,'," " EPIP 1.5 EOF- 32 EOF Staff Response -. - Rev-2---- -' ,-EPIP .15 I_

EOF- 33 Recovery Issues- -- .. --.. - - - Rev 0..-... X'-.EtPIP 5.2 EOF- 34 EOF Activities - - --Rev. 0 ... IP 5.2 EOF- 35 Recovery Phase Plhn Outline Guidance: '- "-..'";"Re-..: . EPIP .52 EOF- 36 RE-Entry Briefing Guide " -, Rev.J 0 _.?.. EPIP 5.2 EOF- 37 RE-Entry Debriefing Guide --- -. - - -- Rev. 0 - . , EPIP 5.20 EOF -38 EOF Messenger Checklist . Rev.""' - EPIP ...

EOF- 39 Plant Status Recorder Checklist - Rev. 0 1 EPIP1.5 JPIC- 01 JPIC Manager Checklist 'Rev. 4 - ':EPIP 1.4 JPIC - 03 Alliant Spokesperson Checklist .. .. Rev. 3 EPIP 14

. -1 EMERGENCY-PLAN, IMPLEMENTING.P.ROCEDURESF- Rev.,129 INDEX PAGE 4 of 7 JPIC - 04 Technical Liaison Checklist Rev. 4 EPIP 1.4 JPIC - 05 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 - II Rumor Control Coordinator I Checklist, Rev. 3 EPIP 1.4 JPIC - 12 Rumor Control Event Summary Log Rev. 1 EPIP 1.4 JPIC - 13 Rumor Control Coordinator II 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 EPIP 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-01 ERO Notification - Off-hours Phone System Rev. 3 EPIP 1.2 Callout NOTE-02 ERO Notification - Alphanumeric Paging System Rev. 3 EPIP 1.2 Callout NOTE-03 Event Notification Worksheet Rev. 1 EPIP 1.2 NOTE-04 Plant Assembly Notification Rev. 2 EPIP 1.2 NOTE-05 Emergency Action Level Notification Rev. 4 EPIP 1.2 NOTE-06 Plant Page for Emergency Classification Changes Rev. 1 EPIP 1.2 NOTE-07 Basic Notification Flowpath Rev. 0 EPIP 1.2 ODEF-01 ODEF Decontamination Waiting Area Rev. 0 EPIP 2.7 ODEF-02 Floor Plan for ORAL/ODEF Rev. 0 EPIP 2.7 ODEF-03 Travel Route to ORAL/ODEF Rev. 0 EPIP 2.7 ODEF-04 12t Avenue Entrance to ORAL/ODEF Rev. 0 EPIP 2.7 I

I I I_. -1 , -- - 2ý - ý1ý EMERGENCY PLAN IMPLEMENTING PROCEDURES_ Rev;.129.

S INDEX NDEX ""PAGE 5 of 7 ORAA-01 Offsite Relocation and Assembly Area Supervisors Rev. I - EPIP 2.4 Checklist ORAA-02 Health Physics Support for the ,Offsite Relocation Rev. O' . EPIP 2.4 and Assembly Area'- -

ORAA-03 Security Spliport fori the'Offsite Relocation and - . Rev. 0 EPIP 2.4 Assembly Area,:ý-).. ' "

ORAA-04 Offsite Relocation and Assembly Area Rev: 0 EPIP 2.4 ORAA-05 Offsite Relocation and Assembly Area Parking ý.d' Rev. 0'_`_ 'EPIP'2.4 Vehicle Monitoring' .,, , .

OSC-01 OSC Layout 2,Rev..O EPIP 2.1 OSC-02 OSC Organization Chart .. Rev. 0. EPIP 2.1 OSC-03 Minlrfium Staffing Level Rev,, EPIP 2.1 OSC-04 Reconi-mended Log Entry Topics ,. -. Rev. 0. , EPIP 2.1 OSC-05, Emergency Event Log Sheet , Rev. 0 "EPIP 2.1 OSC-06.. Personal Statement Concerning Incident . - .Rev. , EPIP 2.1 OSC-07 Emergenf -Exposure Tracking Log  ; 'Rev. 0 -; EPIP 2.1 OSC-08 OSC Supervisor Checklist -. Rev. 0 - EPIP 2.1 OSC-09 Health Physics Supervisor Checklist Rev. 0 ,EPIP 2.1 OSC-1O Electrical, Mechanical, I&C Mairltenanbe; '. EPIP 2.1 Supervisor Checklist

• L I( j . -- *

( I -

• 1

EMERGENCY PLANIMPLEMENTING PRCCEDURESa-- Rev. 129 INDEX PAGE 6 of 7 OSC-1 1 Emergency Assignment 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 Selection of Volunteers 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 PASE-02 Onsite Assembly Locations Rev. 2 EPIP 1.3 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 I

TSC-02 TSC Supervisor Checklist Rev. 2 EPIP 2.2 TSC-03 Site Radiation Protection Coordinator Checklist Rev. I EPIP 2.2 TSC-04 Technical & Engineering Supervisor Checklist Rev. 2 EPIP 2.2 TSC-05 Quality Assurance Checklist Rev. 1 EPIP 2.2 TSC-06 Security & Support Supervisor Checklist' Rev. I EPIP 2.2 TSC-07 Administrative Supervisor Checklist Rev. 1 EPIP 2.2 TSC-08 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-1 1 TSC-EOF-JPIC Communicator Checklist Rev. 1 EPIP 2.2 TSC-12 ENS Communicator Checklist Rev. 2 EPIP 2.2 TSC-13 HPN Communicator Checklist Rev. I EPIP 2.2 TSC-14 TSC/OSC Operations Liaison Checklist Rev. 2 EPIP 2.2 TSC-15 Radiological Support Staff Checklist Rev. I EPIP 2.2 I TSC-16 Radio Operator- Offsite Checklist Rev. 0 EPIP 2.2

..IPAGE 7 of 7 K> INDEX ., E. of 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 Etlectrical 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 .... I Re.-.1 EPIP 2.2 I

TSC-26 Information Services Representative Checklist - .Rev. 2 EPIP 2.2 TSC-27 Fire Marshall Checklist - . -Rev. 1. EPIP 2.2 TSC-28 NRC Roles During A Nuclear Power Plant " RevO( 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 ,"1,L, . ,Rev..0-.,, , EPIP 2.2 TSC-32 Status Board Recorder ,.,*,*[ely., EPIP-2.2 TSC-33 Typical Organization of the NRCG Site Team ,;, - -Rev.A,:, EPIP 2.2 TSC-34 TSC Organization Chart .' '&, . -Re,,2.-: EPIP 2.2 TSC-35 Assignment Form ' ."& .', -, ,--,- .Rev.':0t --- EPIP 5.2 TSC-36 Deactivation'Report  :-,'., , " Rev. 0- EPIP 5.2 TSC-37 Plant Operations Status 'EPIP 5.2 TSC-38 TSC/Control Roorn/OSC Activities .Rev.'0.. EPIP 5.2 TSC-39 TSC Clerical Checklist ,Rev. 0 - EPIP 2.2 TSC-40 ARM Locations Rev; 0 -EPIP 3.1/4.3 TSC-41 PASS Capabilities' , Rev. 0 EPIP 3A1, I TSC-42 On-Site Map . Rev. 0 EPIP 3.2

EPIP 1.2 Rev. 27 NOTIFICATIONS Page 1 of 12 Noi_ 2 Effective Date:

PROCEDURE APPROVAL I am responsible for the technical content of this procedure.

Approved by: __ __ .Date: __-____ *b-/A Manager, Emergency Planning

I EMERGENCYA - IM LMEaN ~ PR ~GDRE,C D pI 1.2 Rev. 27 NOTIFICATIONS Page 2 of 12 Table of Contents Paqge 1.0 PU R PO SE .............................................................................................. 3 2.0 DEFINITIO NS ......... :................................................................................ 3 3.0 INSTRUCTIO NS ..................................................................................... 3 3.1 OVERVIEW .................................................................................. 3 3.2 INITIALLY NOTIFYING THE ERO, BENTON/LINN/STATE EOC'S, AND NRC ......................................................................... 4 3.3 NOTIFYING BENTON AND LINN COUNTIES AND THE IOWA EMERGENCY MANAGEMENT DIVISION OF EMERGENCY CLASSIFICATIO NS ............................................................................... 6 3.4 NOTIFYING THE NRC OF EMERGENCY CLASSIFICATIONS .......... 7 3.5 FOLLOW UP NOTIFICATION FROM THE TSC ............................ 7 3.6 FOLLOW UP NOTIFICATION FROM THE EOF ............................. 9 4.0 REC O RDS .............................................................................................. 11

5.0 REFERENCES

........................................................................................ 11 6.0 ATTACHM ENTS ...................................................................................... 11 ATTACHMENT 1: NOTIFICATION FORMS .................................. 12

-, A 1.0 PURPOSE (1) This procedure provides instruictions for initial and follow-up notifications of the Emergency Response Organization (ERO), Benton and Linn Counties, the Iowa Emergency Management Division, and the NRC in response to an emergency classification declared at the DAEC.

2.0 DEFINITIONS (1) Emergency Classification (a) Four classes of Emergency Action Levels designed to-provide early and prompt notification of events which could lead to more serious consequences given operator error or equipment failure or which nmight be indicative-of more serious conditions which are not yet fully realized.

(b) The four classes are;

, I Notification n'r -=ofUnusual

L_ý_G~e~ .env, '..Event,,*Alert,.

T . .. Site ' Area Emergency and Genera? Emergency.

, *. .. .zv .. ,.* * *,

3.0 INSTRUCTIONS

.. ).. ., 4.

3.1 OVERVIEW (1) The Operations Shift Manager/Operations Shift Supervisor (OSM/OSS),

.Emergency Coordinator (EC),-and Emergency Response &' Re~ove ry Director (ER&RD) shall ensure that initial and follow-up notifications are made to the ERO, counties, State, and NRC in accordance with this procedure.

(2) The Emergency Telephone Book (ETB) contains telephone numbers to support required notifications.

I I ,,

(3) Benton and Linn Counties, and the Iowa Emergency Management Division, shall be notified within 15 minutes after the declaration of an emergency classification, as required by 10CFR50 Appendix E (Reference 1).

(4) The NRC Emergency Operations Center (EOC) shall be notified as soon as possible after notifying Benton and Linn Counties and the Iowa Emergency Management Division, and not later than one hour after the declaration of an emergency classification as required by 10CFR50.72 (Reference 2).

(5) Continuous communications with the NRC shall be established for all events classified as an ALERT or greater when requested by the NRC. This will be supported by the TSC ENS Communicator.

(6) Completion of all notifications will be documented on the notification forms.

Completed forms will be forwarded to the OSM/EC/ER&RD as appropriate for review. The Manager, Emergency Planning, shall receive a copy of the notification form. {IC001}

3.2 INITIALLY NOTIFYING THE ERO, BENTONILINNISTATE EOC'S, AND NRC NOTE ,

Reference EPIP Form NOTE-07 for notification flowpath. ,

(1) STA (a) Upon declaration of the event, complete Form NOTE-05, 'EMERGENCY ACTION LEVEL NOTIFICATION FORM', and submit this form to the OSMiOSS for review and approval.

(2) OSMIOSS (a) Direct the Security Lt., (the STA performs this function during a security related emergency or if the Security Lt. is unable to get to the Control Room in time for this notification to be made within 15 minutes of the declaration), to make initial and follow-up notifications to Benton County, Linn County, and the Iowa Emergency Management Division per section 3.3.

EPIP 1.2 Rev. 27 Page 5 of 12 (3) ST) 1* 4- - -,4 (a) Complete the following forms and -submit them to the OSM/OSS for review and approval:

1. Form NOTE-02, 'ERO NOTIFICATION -,ALPHANUMERIC PAGING SYSTEM 0ALLOUT'.,, ".

2. Form NOTE-03, 'EVENT NOTIFICATION WORKSHEET.'

3. Form NOTE-04, '.PLANT ASSEMBLY NOTIFICATION FORM.'

4. Ifoff hours, compete'Frm NOTE-'0', ' NOTIFICATION

,, ,. , OFF-HOURS, PIONE SYSTEM CALLOUT'., as well.

(4) OSIMIOSS " '" ' --'-"4- "" 4- 4-(a) Direct a member of the Control Room crew to peifbrm'-the'plant page announcement per Form NOTE-04, 'PLANT ASSEMBLY;,NOTIFICATION FORM'. Ensure to lurn on thedultside speakers.

(b)' Direct the SAS Operator, (the STA performs this function during a security related emergency);.to conduct pager notifications per Form NOTE-02, 'ERO NOTIFICATION- ALPHANUMERIC, PAGING SYSTEM CALLOUT', and as necessdarForm NOTE-01 'ERO'NOTIFICATION OFF-HOURS PHONE SYSTEM CALLOUT.' Return the form(s) to the OSM/OSS when completed. , -. , .'

(c) As soon as possible, but within {1,hour after the declaration,,direct the

- TSC ENS Communicator, (the backups for this function are the STA and Security Lt.), to make the initial and follow-up notifications to'the NRC Emergency Operations Center per section 3.4.

(5) ER&RD . , , ,-,.,--, ,;4 (a) Inform Corporate Management ofthe suat . ,

'4- 4- 4-4-4 4-4

- '4-4--..),.

'.4-

I RGAKE I 4 EMENTING PROCEDUIES EPIP 1.2 Rev. 27 NOTI FICATIONS Page 6 of 12 (b) If activation of the EOF is desired or required, initiate notification of the EOF staff and direct the JPIC Manager to initiate notification of the JPIC staff.

(6) Support Services Coordinator (a) For an ALERT or greater, contact the Corporate Security Manager and instruct him/her to direct the Tower 1st Floor Security guard to make the appropriate (drill or emergency) announcement on the building page system.

(7) ERO Members (a) When notified of an ALERT or greater, report to assigned facility, as directed, and complete any assigned notifications in accordance with the ETB as applicable.

3.3 NOTIFYING BENTON AND LINN COUNTIES AND THE IOWA EMERGENCY MANAGEMENT DIVISION OF EMERGENCY CLASSIFICATIONS (1) Using the dedicated microwave line, select line 2 and dial "9999" (All-Call) to contact Benton and Linn Counties, and the Iowa Emergency Management Division. Upon verification that all three parties are on the line, dial "####"to cease further ringing on the line. Provide the information as read from Form NOTE-05, 'EMERGENCY ACTION LEVEL NOTIFICATION FORM'.

NOTE If the microwave* line is unable to contact either Benton County, Linn County, or State EMD then use the-commercial telephone to contact them. A list of the, numbers is available in the ETB and a copy is near the phone. The 15-minute requirement begins when the event is declared and ends when the FIRST EOC Representative answers the phone.

Priority shall be: (1) notify all respondents via microwave line; (2) place a commercial telephone call to those respondents who, because of equipment/line difficulties, cannot answer the microwave line; (3) fax page 1 of NOTE-05 to ensure notifications are properly completed and understood.

_EEGýNý,, 01jMPL*~Nf 1PROGEDU RES 4,ý-EPIP 1-.2 '

Rev. 27 NOTIFICATIONS Page 7 of 12 (2) Fax page 1 of 2 of the'completed Form NOTE-05, 'EMERGENCY.ACTION LEVEL NOTIFICATION 'FORM', to'Bentdn County, Linn County,'a'nd the Iowa Emergency Management Division to confirm the notification. Push button "01" for working hour distribution and button "02" for 6ff hour-and weekend distribution.

(a) If the f6x is'not operable, confitfiation will-be made via microwave, comm-rcial phone; &opoint-to-point rad.i.o..' . "

(b) Initiate any follow-up notifications to the counties and State for changes to PARs and EALs.

3.4 NOTIFYING THE NRC OF EMERGENCY CLASSIFICATIONS (1) Notify the NRC Emergency Operations Center on the F7TS.2001 Network ENS line using Form NOTE-03, 'Event Notification Worksheet'. The NRC EOC should be notified as soon as possible but no later than onehour after event classification. -,

4. 4, 3.5 FOLLOW UP NOTIFICATION'FROM THETSC-(1) EC (a) Upon activating the TSC, as~um'responsibility-fromrHe"OSM/OSS for directing follow up notifications for changes to PARs and EALs to the ERO,'Benton'and Linn County5 Emrge"cy Management, the Iowa Emergency Management Division and the NRC until the ER&RD assumes thiis rbsiinsilDitynhe nEOF. - - ,. .

(2) Periodic status updates shall be prove toth'eSateanhd counis by, the TSC-EOF-OFFSITE'Cofmmunicatorrurti thW EOF'has`assuieai follow-up' notifications: *- " ' -,

(3) TSC Operations Liaison r,...

(a) For changes-tb the declared emergency classification, PARs, and/or cancellation of the emergency, complete Form NOTE-05, 'EMERGENCY

I----------J_

EMERGENGY PLAN IMPCFMEi4fT ~-POCEL)tt"S ~EPIP 1.2 Rev. 27 NOTIFICATIONS Page 8 of 12 ACTION LEVEL NOTIFICATION FORM', and. submit it to the EC for approval.

1. Ensure to obtain SRPC concurrence on PARs.

(4) EC (a) Review and approve Form NOTE-05, 'EMERGENCY ACTION LEVEL NOTIFICATION FORM'.

(b) Direct the TSC-EOF-OFFSITE Communicator to notify Benton County, Linn County, and the Iowa Emergency Management Division per section 3.3 step (1).

(c) Direct the Admin Supervisor to send the backup fax to Benton County, Linn County, and the Iowa Emergency Management Division per section 3.3 step (2).

I (5) TSC Operations Liaison (a) Complete the following forms and submit them to the EC for review and approval:

1. Form NOTE-02, 'ERO NOTIFICATION -ALPHANUMERIC SPAGING SYSTEM CALLOUT:1'

2. Form NOTE-03, 'EVENT NOTIFICATION WORKSHEET.'

3. Form NOTE-06, 'PLANT PAGE FOR EMERGENCY CLASSIFICATION CHANGES'.

(6) EC (a) Direct the Security and Support Supervisor to conduct pager notifications per Form NOTE-02, 'ERO NOTIFICATION - ALPHANUMERIC PAGING SYSTEM CALLOUT'.

I

i=61P "1.2 ' '

Rev. 27 NOTIFICATIONS 'e..27 Page 9 of 12 (b) Direct the TSC Opebrations Liais6n toIperforrm the'plant page announcement per Form NOTE-06, 'PLANT PAGE FOR EMERGENCY CLASSIFICATION CHANGES'.

(c) As soon as possible, but within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after the 'change, direct the TSC

'ENS Communicator to notify the NRC Emergency Operations Center per section 3.4 .

3.6 FOLLOW UP NOTIFICATION FROM THE EOF ' -' ' '

(1) ER&RD *

(a) Upon activating the EOF, assume responsibility, from the EC for directing

, follow up notifications for changes to PARs and EALs to the ERO,

.counties, State, and the NRC until no longer necessary....

(2) Rad & EOF Manaqer

, 1'..

(a) For changes to the declared emergency classification PARs and/or

.cancellation of the emergency, complete the Form NOTE-05,

'EMERGENCY ACTION LEVEL NOTIFICATION FORM',.and submit it to the ER&RD for review and approval.

• (.* -* - , * .1 (b) Periodic updates shall bL- provldedlo-the State and.tounties by the Rad

& EOF Manager.

(3) EOF to TSC Communicator (a) Complete Form NOTE-02, 'ERO NOTIFICATION -ALPHANUMERIC PAGING SYSTEM CALLOUT', and submit it to the ER&RD for approval.

(4) Rad & EOF Manager (a) Using the Admin Hotlineto contactBenton and Linn Counties, and the Iowa Emergency Management Division, provide the information as read from Form NOTE-05, 'EMERGENCY ACTION LEVEL NOTIFICATION FORM'

E 'R ESi~' EPIP 1.2 Rev. 27 NOTIFICATIONS Page 10 of 12 (5) EOF Messenger (a) Conduct the pager notifications per the completed Form NOTE-02, 'ERO NOTIFICATION -ALPHANUMERIC PAGING SYSTEM CALLOUT' and fax page 1 of the completed Form NOTE-05, 'EMERGENCY ACTION LEVEL NOTIFICATION FORM', to Benton and Linn Counties and the Iowa Emergency Management Division to confirm the notification.

1. If the fax is not operable, confirmation will be made via microwave, commercial phone, or point-to-point radio.

(6) EOF HPN Communicator (a) Using Form NOTE-03, 'EVENT NOTIFICATION WORKSHEET', notify the NRC Operations Center on the FTS-2001 Network ENS and HPN line in the EOF. The TSC-ENS Communicator will maintain continuous communication on the ENS line with the NRC providing the needed plant technical information as requested by the NRC Emergency Operations Center.

I

I LEM IEEPIP'1.2 Rev. 27 NOTIFICATIONS Page 11 of 12

.4.0' RECORDS' (1) All logs, forms,'and records generated must be maintained in accordance with EPDM 1007. -,

5.0 REFERENCES

(1) 10CFR50Appendix E IV. D (2) 10CFR50.72, "Immediate Notification Requiremnenfs"  ?' - -.

(3) {IC001};Inspection Report 88-04' .'

'(4) DAEC Emergency Plan *

,(5) Emergency Telephone Book (ETB)*. .- - --f-(6) EPDM 1007 .

6.0 ATTACHMENTS (1) Attachment 1, Notification Forms I

SEMERGENCYPLA**MIMLEMENTING ROCEDURIES?-$ EPIP 1.2 Rev. 27 NOTIFICATIONS Page 12 of 12 ATTACHMENT I NOTIFICATION FORMS ERO Notification - Off-hours Phone System Callout NOTE-01 ERO Notification - Alphanumeric Paging System Callout NOTE-02 Event Notification Worksheet NOTE-03 Plant Assembly Notification NOTE-04 Emergency Action Level Notification NOTE-05 Plant Page for Emergency Classification Changes NOTE-06 Basic Notification Flowpath NOTE-07

EPIP 3.1 i Rev. 12 IN-PLaNT RADIOLOGICAL MONITORING' Page 1 of 14 I Effective'Date": 0o*

Dat- ' 1 Independent Reviewer PROCEDURE APPROVAL I am responsible for the technical content of this procedure.

Approved by: _ ._.____ ___Date:-

Manager, Emergency Planning

• M RG'-,-JX*J'..... --.. ... 4L( . EPIP 3.1 Rev. 12 IN-PLANT RADIOLOGICAL MONITORING Page 2 of 14 Table of Contents Page 1.0 PU RPO SE ............................................................................................... 3 2.0 DEFINITIO NS ............................................ ............................................ 3 3.0 INSTRUCTIO NS ...................................................................................... 3 3.1 RESPO NSIBLITIES ..................................................................... 3 3.2 DETERMINATION OF ASSEMBLY AREA HABITABILITY ........... 5 3.3 IN-PLANT RADIOLOGICAL MONITORING .................................. 10 3.4 POST-ACCIDENT SAMPLING .................................................... 11 4.0 R EC O R DS ............................................................................................... 14

5.0 REFERENCES

........................................................................................ 14 I

EPIP 31 I- . i - Rev. 12 IN-PLANT RADIOLOGICAL MONITORING .

Page 3 of 14 1.0 PURPOSE (1) This procedure provides instructions for performing radiological monitoring activities during an emergency including determination of habitable areas, In-Plant radiological monitoring, and post-accident sampling (PASS). This procedure supports the implementation of requirements in 10CFR50, Appendix A, NUREG 0654 and the DAEC Plan.

(2) This procedure is applicable to the Site Radiation ProtectionCoordinator, Chemistry Technicians, the OSC Health Physics ,Supervisor", He;alth Physics Technicians and other In-Plant Monitoring.Team personnel involved in In-Plant radiological monitoring activities. Ta psn in (3) This procedure should be implemented for events c"asIsified as an ALERT or

,greater, and may be implemented upon activation of the Operational Support Center (OSC) for an event classified as a NOTIFICATION OF UNUSUAL EVENT if necessary.

2.0 "DEFINITIONs (1) None 3.0 'INSTRUCTIONS 3.1 RESPONSIBILITIES 3.1.1 SITE'RADIATION PROTECTION COORDINATOR (1) Ensure that DAEC personnel are dispatched to monitor the environs in and around the plant for radiological consequences associated with the event.

"EMERGENCY**iPL. NIM LEMENTING..PROGEQDURE EPIP 3.1 IN-PLANT RADIOLOGICAL MONITORING Rev. 12 Page 4 of 14 (2) Conduct an initial evaluation and assessment of the results of radiological monitoring activities. Upon activation of the Emergency Operations Facility (EOF), this function will be assumed by the Radiological Assessment Coordinator for all Off-Site monitoring activities.

(3) Assess the On-Site radiological consequences and directing protective measures, including evacuation of the plant.

(4) During the initial stages of the event, apprise local and State authorities, through the Emergency Coordinator, of the results of radiological monitoring activities and providing protective action recommendations based upon the projected radiological consequences to the population-at-risk. Upon activation of the EOF, this function will be assumed by the Radiological Assessment Coordinator.

3.1.2 0SC HEALTH PHYSICS SUPERVISOR (1) Ensure that personnel dispatched from the OSC are properly outfitted with protective clothing and equipment, are briefed regarding ALARA and are apprised of existing and potential radiological hazards.

(2) Coordinate with the Site Radiation Protection Coordinator to obtain information regarding plant status, problems, response options, significant radiological releases in progress, offsite dose rates, plume location and meteorological conditions as necessary.

(3) Ensure the determninati6n of habitability of assembly areas and ERO facilities.

(4) Coordinate the dispatch of monitoring teams, PASS team and Offsite Relocation Assembly Area (ORAAJ) and Offsite Radiological Analysis Laboratory/Offsite Decontamination Facility (ORAL/ODEF) personnel. Ensure the continued briefing of the ORAA in terms of plant and radiological conditions.

(5) Supervise efforts to prepare injured/contaminated personnel for transport to offsite medical facilities.

(6) Brief rescue and emergency repair team personnel regarding radiological hazards which exist, or which potentially may be encountered, and provide I

N-yPLANT MEICAI U* .Og"D: .

IN-PLANT RADIOLOGICAL MONITORING Rev. 12'.

.°°.Page 5 of 14 guidance regarding pr6ca'utihs to be taken and limits that shall not be "exceeded.,: ....

3.2 - DETERMINATION OF ASSEMBLY AREA HABITABILITY (1) The assembly areas of concern at the DAEC include the following:

(a) Control Room , .+..

(b) TSC (c) OSC, which inclt~des the OSC Bfeak Room, SecuritW Building, the Health Physics Acc6ss Control Area 'ana inteirconnectiing passageways.

(d) Hot Lab *.,

(e) Warehouse (f) Badging Center ... ... . 4 (g) Training Center (h) Plant Support Center (PAC),*,., * 'T .

(2) The OSC HP Supervisor should determine the habitab-ilty-*fqthe.PSC, Badging Center and Training Center through the use of an On-Site Radiological monitoring team or, if unrayailablej usejadditional H.P.Ppersort~eJ tp.perform this function.

(3) Initial determinationsQf habitability for t heContro.,Roorn,*TGQ and Hot Lab should be, accomplished by ensuri~ng thatthe radiationjlivels$bKinqg detected by the permanently installed radiation monitoring .(Area LRadiation Mo_-.iitoring) system are normal.

(a) As discussed in EPIP, 2.5, Y'Contrpl Room Emergency Resppnse, ,

Operation", the Back Panel Communicator shall recorqthe indicated radiation levels monitored, by the Area Radiation Monitoring (ARM)

System which includes detectors located in .the Control Room and Hot Lab, and forward this information to the Site Radiation 'Protection

'EMERGENCY PLANi4ij-LIEMvENTING PROC IEOL1I3E ~1EPIP 3.1 IN-PLANT RADIOLOGICAL MONITORING Rev 12 1 Page 6 of 14 Coordinator. (When the Plant Process Computer is operational, this data is available to the TSC and EOF. The CR-TSC Communciator need only to forward the Main Steamline Rad Monitor data to the Site Radiation Protection Coordinator as these do not have computer points associated with them.)

NOTE EPIP Form TSC-40, "ARM Locations",

provides a listing of the installed Area Radiation Monitors throughout the plant, including their locations and ranges.

(b) As specified in EPIP 2.2, "Activation and Operation of the TSC", the three TSC radiation monitors (two monitoring the ventilation intake duct work and one in the TSC general area) shall be monitored upon initially I activating the TSC, by the Radiation Support Staff. This information should be forwarded to the Site Radiation Protection Coordinator.

(4) If radiation levels being monitored in the above areas are greater than normal, the Site Radiation Protection Coordinator should be advised and protective measures instituted.

NOTE If the monitors are alarming, the Site Radiation Protection Coordinator may recommend evacuation of such areas to the Emergency Coordinator.

If radiation levels are- higher than normal, priority should be given to radiation survey and sampling activities in those areas to determine their acceptability for continued access.

I

EMERGENCYPM1*NIM EPIP 11'.

Rev. 12, IN-PLANT RADIOLOGICAL'MONITORING

"____,_______ A Page7of14 (5)" -The OSC HP Superviso" shall bb responsible tb, initiate radiation survey and

-airborne sampling of the OSC,,TSC, PSC, WarehoUse, Badging Center, Training Center, Control Roomr, 'or other areas',;based upon the'priority "assignedby the Site Radiation Protection Coordinator. The following activities

,will be conducted by Health Physics Technician's assigned by the Emergency Assignment Tag Board. .

(a) Area radiation surveys shall be conducted and documented as prescribed in HP Procedures. ,

(b) 'Airborne radioactivity surveys shall be conducted and documented as prescribed in HP Procedures.- .. , .- ,,

(6) The results of such survey and sampling activities shall be reviewed by the OSC HP Supervisor, andtheirdegreeof conformance to normal DAEC Administrative Guidelines determined. The OSC Supervisor and Site Radiation Protection Coordinator (SRPC) shall be informed of any abnormal conditions.- .. . .

NOTE Normal personnel ,pexternal 'and, ,internal ' <:-

exposure limits in effect are prescribed in ACP ,':

1411.18 "Personnel Dosimetry".

Standard area contamination" limits" to' 'be ol6servedq are,,, prescribed ,,jin ,ACPj-,1411.'22 "Personne1,ec~cess A reas".. * ,

and

-, _;- *..':.i,, :, .:; ,:, 1; Egress. j. ,in,Radiological v.*

(7) Survey and sampling activities pirescribed above should~be conlucted in the

- Control Room, TSC,and Hot Lab if increasing trends are detected by the installed radiation monitors or~as directed by the Site Radiation Protection Coordinator. - .

EMERGENP!MTN IFGIPROCEDURE EPIP 3.1 Rev. 12 IN-PLANT RADIOLOGICAL MONITORING Page 8 of 14 (8) If an assembly area is determined to be uninhabitable or not suitable for long term habitability, the following should occur:

(a) The Site Radiation Protection Coordinator shall recommend evacuation of selected assembly areas or of the site, and, as appropriate, relocation of essential personnel to alternate assembly areas on site. Evacuation of non-essential personnel is required for a SITE or GENERAL EMERGENCY.

(b) Non-essential personnel should be evacuated to the ORAA, as prescribed in EPIP 2.4, "Activation and Operation of the ORAA".

(c) Essential personnel shall be relocated to another assembly area determined to be safe, or occupancy times established for the affected areas and relief shift assignments made so that essential functions can be conducted on a continuing basis.

(9) If evacuation of one or more assembly areas is required, essential personnel should be relocated to an alternate area, as follows:

I

EPIP 3.1

-: * * ,Rev. 12, IN-PLANT RADIOLOGICAL MONITORING 1.

Page 9 of 14

"- ' NOTE When' selecting'- "essential" personnel, consideration' should ibe"'giVen tbothe minimum shift staffing requirements defined in the DAEC Plain, Table 'a-1. The Emergency Telephone Book may be 'used as ai-reference for obtairjing shift staffing designations.

Guidance regarding TSCp*ersbnnel consideied to be essential 'is contained in EPIP 1.3, "Plant and Site Evacuation"., -,

(10) The OSO HP Supervisor shall assurethat follow-up monitoring of Assembly Areas is conducted, and shall obtain/seek the concurrence of the OSC Supervisor. . ,,, *

(a) Survey and sampling activities to be conducted and their frequency

-should be bas6d upon the.7poteitial fadioloj-cbl hazafds as well as the results of p~rior monitoring activiiies and the capability of installed instrumentation to detect changes in radiological conditions.-,

(b) In defining the type,' frequencyand location of monitoring activities to be conducted, consideration should be given to-increas,. in radiation levels

-.throughout the plant.

(11) 'The results of suclh*-inonitoring activitidgs shall be reveweieby the OSC HP Supervisor. The OSC.-Supervisor and Site Radiation Pr'otection Coordinator shall be advised of anyproblems or adverse trend's detected. ,

(a)' 'The Site Radiation Pr6tection C6ordinator h6ould provide guidance to the OSC Supervisor regarding further monitoring a'ctivities to be-conducted and protective measures to be instituted for personnel in those areas; for example, use of protective clothing and respirators, implementation (or modification) of occupancy times, administration of KI, etc.

AEMER GENC PN I*M EEDURE, EPIP 3.1 Rev. 12 IN-PLANT RADIOLOGICAL MONITORING Page 10 of 14 NOTE Use of accepted Health Physics practices ( i.e.,

clothing and limiting the stay time) should only be considered for Control Room and TSC personnel.

3.3 IN-PLANT RADIOLOGICAL MONITORING (1) Radiological monitoring activities inside the plant shall be conducted to support required response actions.

(2) A Health Physics Technician should accompany each rescue, repair and reentry team upon initial entry into an area where an actual or potential radiological hazard exists.

(a) As discussed in EPIP 4.3, "Rescue and Emergency Repair Work", repair activities may be conducted during the course of several staged entries; therefore, entries subsequent to the initial entry may be conducted without the presence of a Health Physics Technician, providing the hazards' are well known and the pos~ibility of a transient occurring is non existent.

(b) The determination as to whether or not a Health Physics Technician shall accompany a repair team or an operator into the plant and remain in their presence shall be made by the Site Radiation Protection Coordinator or OSC HP Supervisor.

(3) The OSC HP Supervisor shall provide guidance to the Health Physics Technician on the radiological conditions to expect and monitoring activities to be conducted prior to dispatch of personnel into an actual or potential radiological hazard area.

(a) The OSC HP Supervisor shall ensure that required protective clothing is donned properly.

I

EPIP 3:1 IN-PLANT RADIOLOGICAL MONITORING . , Rev 12 "Page 11 of 14 (b) Respiratory protection equipme6t,- if required, will be checked and "

determined to be'operable, and the user aware of equipment operating limitations. ' ....

(c) Dosimetry of sufficient range will be worn to adequately monitor whole body and extremity doses, where applicable. - , .

(d) Equipment and supplies anticipated to be required for the assignment are available and checked to en~ure operability,,,,,'

(e) Briefings will be conducted, to the extent required, to ensure that personnel are aware of the 'jobs to be performed..

(4) Upon being dispatched, the Health Physics Technician should, in addition to monitoring dose rates and total exposures: "

(a) Provide guidance to team members regarding precautions to be taken to minimize their total exposure.

(b) Advise the OSO HP Superyisorof unexpected-radiological conditions encountered. -, , - -,,. .

(5) The OSC HP Supervisor-or designee.should,.as time peipmitswonitor the activities of in-plant personnel utilizing the network of cameras available on site.

(6) Upon egress from the plant, the Health P hysics Technician should provide guidance, -as requirec*, :in ,discardingprotective clothingand jr, the performance of personnel monitoring and decontaminalion, if required, prior to passing through the Health Physics Access Control Area.

3.4 POST-ACCIDENT SAMPLING,,- * - - "

(1) The OSC Supervisor and OSC HP Supervisor shall beadvised by the Site Radiation Protection Coordinator of post-accident sampling and analysis activities to be'conducted. ""

(2) If a particulate filter and charcoal cartridge sample from the KAMAN Effluent Monitoring System is to be obtained for analyses,

ýEMERdE:y*E.

MPLEME*NT1** *,

• R..CED * ,b.- EPIP 3.1 IN-PLANT RADIOLOGICAL MONITORING Rev. 12

-Page 12 of 14 (a) The Site Radiation Protection Coordinator should determine which cartridge(s) are to be obtained and the radiation level of the cartridge, as monitored by the KAMAN System.

(b) The OSC HP Supervisor should be advised of the projected radiation levels and review with the Site Radiation Protection Coordinator appropriate radiological protective measures to be taken.

NOTE Calculations have been completed which verify that the samples listed in EPIP Form TSC-41 I can be retrieved without exceeding exposure levels of 5 rem Deep Dose Equivalent to the whole body. Proper protective measures for personnel involved in sampling activities should be taken.

(3) Based upon the expected dose rates, an estimate should be made of the total exposure io be received while obtaining and analyzing a sample and exposure limit increaseas aothorized, if required, as specified in EPIP 4.3, "Rescue and Emergency Repair Work".

I

(4) The OSC HP Supervisor shall designate the' Chemistry Technician(s) accompanied by a Health Physics Technician to obtain the samples. The OSC HP Supervisor will conduct a briefing consisting of, at a minimum, the expected radiological conditions and associated precautions, increased exposure limits, stay times, access routes and that adequate protective clothing, dosimetry and respiratory protection equipment is donned before each entry.

ý-iNOTE ,~

Prior to dispatching the PASS Sampling Team personnel into the Power Block Structure, the OSM/OSS should-be advised and-Emergency Coordinator authorization received.

(a) Sample retrieval from the Off-Gas Stack should be'accomplished in accordance with PASAP'sZ .

(b) Sample retrieval from the Rea`ctr Building Stacks b&niiTurbine Building Vent should be accomplislhed i"acordance with PASAP s."

(c) Grab samples from the R~eactorBuilding should be obtained as, prescribed in PASAP's.

(5) Post-accident samplingconducted at the Post-AccidentSample System station should be conducted tby:Chiemistry.Tech nicians, irnafccdtdanrewith, PASAP's.

(6) Personnel dispatched to remote locations to obtain samples should maintain communications with the OSC, advising the OSC HP Supervisor of any unusual phenomena observed.

(7) Analyses of samples and documentation of results should be conducted using the PASAP's.

.I

-- I I EMERGENCY PNLA MPLEM ENTINGPROCEDURE EPIP 3.1 IN-PLANT RADIOLOGICAL MONITORING Rev. 12 1 Page 14 of 14 4.0 RECORDS (1) All records generated as a result of this procedure shall be forwarded to the Site Radiation Protection Coordinator for retention and is considered a QA Record (exception is for records generated during drills/exercises) in accordance with EPDM 1007.

5.0 REFERENCES

(1) DAEC Emergency Plan (2) NUREG 0654, Rev. 1, Planning Standard H, I, J, K (3) EPIP 1.3, "Plant and Site Evacuation" (4) EPIP 2.5, "Control Room Emergency Response Organization" (5) EPIP 2.2, "Activation and Operation of the TSC" (6) HP Procedures (7) ACP 1411.22 "Personnel Access and Egress in Radiological Areas" (8) ACP 1411.18 "Personnel Dosimetry" (9) EPIP 4.3, "Rescue and Emergency Repair Work" (10) EPIP 2.4, "Activation and Operation of the ORAA" (11) ENVIRONMENTAL SAMPLING PROCEDURES (12) PASAP's (13) OFFSITE DOSE ASSESSMENT MANUAL (ODAM)

Effective Date: 9 [.z, 107 PROCDURAPPROVAL I am responsible for the technical content of this procedure.

Approved by: "' . , Date "Manager,Emergency Planning

- **1

• 1* II *i 'I - I I I 1*, .

1 I , f':.l I'

SEMEiGElv .1!ý;Y Vi PRO D. R EPIP 3.2 Rev. 13 FIELD RADIOLOGICAL MONITORING Page 2 of 31 Table of Contents Page 1.0 PU R PO SE .............................................................................................. 4 2.0 D EFIN ITIO NS .......................................................................................... 4 3.0 INSTRUCTIO NS ...................................................................................... 5 3.1 RESPO NSIBILITES ..................................................................... 5 3.2 TEAM PREPARATION AND DISPATCH ...................................... 6 3.3 PLUME DETECTION AND MONITORING PRECAUTIONS ...... 9 3.4 RADIOLOGICAL MONITORING ACTIVITIES .............................. 11 3.5 AIR SAMPLING (LOW VOLUME SAMPLES) ............................... 14 3.6 RADIOLOGICAL SAMPLING ........................................................ 15 3.7 TRANSPORTATION OF SAMPLES TO THE ORAL ..................... 15 3.8 ON-SITE FIELD RADIOLOGICAL MONITORING ........................ 17 3.9 AIR SAMPLING (LOW VOLUME SAMPLES) ................................ 19 3.10 DOCUMENTATION AND ROUTING OF ON-SITE MONITORING A CTIV IT IES .................................................................................. 21 3.11 DOCUMENTATION OF RADIOLOGICAL MONITORING DATA ...... 21 3.12 DETERMINING SAMPLE POINT AND PLUME LOCATIONS ..... 22 4.0 R EC O R D S ............................................................................................... 24

5.0 REFERENCES

........................................................................................ 24

EMERGEC-Y,.PAN,-'MrL,'E ENTIj PR 'i DEPIP.a.2: - & '1

_ __ _ _ _IRev. 13 FIELD RADIOLOGICAL MONITORING  :  : " .

Page 3 of 31 Page 6.0 ATTACHMENTS ...................................................................................... 24 , '"Typical Radiological Monitoring Team Briefing Topics".-.* ....... . 26 , "Emergency Monitoring Log". ................................... 27 , -"Air Sample Identification".............................. 28 , "Conversion of Air Sample Results into Radioiodine.,

Concentrations" ............ ................................................ ............... 29 , "Emergency Environm6ntal Sample Cbllection Record, typical"........ 30 , "Emergency Environmental Sample Log/,typical"..: ........... .31

,4 1

EMERGEN*YPLANIMPLEMENTINGROCEDURE, EPIP 3.2 Rev. 13 FIELD RADIOLOGICAL MONITORING Page 4 of 31 1.0 PURPOSE (1) This procedure provides guidance associated with the performance of both onsite and offsite field radiological monitoring activities during an emergency.

(2) This procedure is applicable to the Site Radiation Protection Coordinator (SRPC), the Operational Support Center (OSC) Supervisor, OSc Health Physics (HP) Supervisor and Field Radiological Monitoring Teams personnel.

(3) Guidance associated with direction and control of the Field Radiological Monitoring Teams, and coordination of local, State and Federal agencies is contained in Emergency Plan Implementing Procedure (EPIP) 3.3, "Dose Assessment and Protective Action."

(4) This procedure is intended to be used in conjunction with the Offsite Dose Assessment Manual (ODAM), and the DAEC Environmental Sampling Procedures (ESP's).

NOTE It, is expected that the majority of the offsite radiological monitoring activities described in this procedure will be conducted under the direction of the Radiological Assessment Coordinator (RAC) in the Emergency Operations Facility (EOF). -

2.0 DEFINITIONS (1) None I

,rI EPlP3:2:

Rev. 13 K.JF FIELD RADIOLOGICAL MONITOIRING" -'

Page 5 of 31 3.0 INSTRUCTIONS 3.1 RESPONSIBILITIES

• a* * -

(1) Site Radiation Protection Coordinator (SRPC)

(a) Ensuring that DAEC pers6nnelare dispatched to monitor-the environs in and 'around the plant for radloi0gical consecjuence's associated with the event. .' , . . ', , ,- ,

(b) Conducting an initial evaluati6n and ass6ssmerint.ofthe results of.

radiological monitoring activities. Upon actiiation of the EOF, this

. function will be assumed by the Radiological Assessmeni Coordinator (RAC) for all offsite monitoring, activties. , .. ... .

(c) Assessing the onsite radilogiccal conse~quences, and cting protectve measures, including evacuation of the plant in paýrt ori id whlle.

(d) During the initial stages of the event, apprising local and State authorities, through the Emergency Coordinator; of the results of radiological monitoring activities and providing protective Iaction recommendations based upon the projected -radiological consequences to the population-at-nsk.*, Uon activation fthe ,oF,.this function will be assumed byte l -$C. ... . -, , - ,-

(2) OSC Health Physicýd(HP) Supervisor' " "

(a) Ensuring that personnel dispatched fr6omthe OSC arep'roperly outfitted with protective clothing and equipment, are briefed regarding ALARA (As Low As Reasonably Achievable).and are apprised of existing and potential radiological hiaziards.

(b) Coordinating with the SRPC in the TSC to obtain information regarding plant status, problems, response options, significant radiological releases in progress, offsite dose rates, plume location and meteorological conditions as necessary.

(c) Ensure the determination of habitability of assembly areas and ERO facilities.

M GIY'L8IIM EIROCEDURE EPIP 3.2 Rev. 13 FIELD RADIOLOGICAL MONITORING Page 6 of 31 (d) Coordinate the dispatch of Field Radiological Monitoring teams.

3.2 TEAM PREPARATION AND DISPATCH (1) Personnel are assigned to the Field Radiological Monitoring Teams by the Emergency Assignment Tag Board, as specified in EPIP 2.1, "Activation and Operation of the Operational Support Center."

(a) The OSC HP Supervisor may elect to reassign personnel initially assigned to the Teams to take maximum advantage of the capabilities and experience of assigned personnel.

(b) Activities to be completed by the Field Radiological Monitoring Teams prior to being dispatched are identified on the referenced checklists.

(2) Once an ALERT has been declared, and until there is a radiological release in progress, the OSC HP Supervisor will assemble, brief and dispatch the Field Monitoring Teams to assemble gear and establish radio contact with the SRPC. The OSC HP Supervisor will inform the Emergency Coofdinator via the SRPC of all teams dispatched.

NOTE Once set-up activities are complete, with concurrence from the Emergency Coordinator, peisonnel may be reallocated as necessary.

I I

(3) In preparation for conducting m6nitorinnctivities: . .

- (a) The SRPC shall evaluate the lociatiori and 'agnitude of thpe lume if a release is in progress, as specified in EPIP 3.3, "Dose Assessment and Protective Action" and providedireqtion to the field monitoring teams.

Both the computerized and manual methods of dose projection are covered in this procedure. -, .... - , - -

)NOTE Field radiological monitoring is required,,for events classified as a SITE or GENERAL EMERGENCY and should be considered as a precautionary measure-during -an ALERT. '-W" (b) Additionally, the-SRPC, shall pass on this informiati6n'tbithbOSC HP Supervisor and shall review the briefing information identified in Attachment 1, 'Typical Radi6logical Monitorin6 Tamni'BriefingTopics",

with the OSC HP Supervisor:  :' "

(c) The OSC HP Supervisor shall ensure that the Team members are Sappropriately dressed, have their required dosimetry and have checked out the operation of theirequipment. -: -- -. .),,r ,

NOTE ,

I i Each Team shall ensure that instrumentation is within calibration - and- has - been source checked.

(d) The OSC HP Supervsior should conduct the Team briefing, reviewing, at a minimum, items noted in Attachment 1, anJ dis'p~tch'the Teams to their vehicles. I I

EMERGENCY, MPEMENTING PROCED1UREI EPIP 3.2 Rev. 13 FIELD RADIOLOGICAL MONITORING Page 8 of 31 (e) Upon completing their vehicle checkout, including fueling, if required, and loading their equipment in the vehicle, the Team should contact the OSC HP Supervisor and advise him of their readiness to be dispatched offsite.

NOTE If an adequate number of functioning vehicles cannot be obtained, the OSC Supervisor should be advised, who in turn should advise the Security and Support Supervisor.

The Emergency Coordinator may authorize the use of personal vehicles, or if time permits, may elect to have the Security and Support Supervisor coordinate with the Emergency Support Manager to secure additional vehicles.

(4) The SRPC shall be advised by the OSC HP Supervisor of the readiness of the Teams to be dispatched, and responsibility for further Team communications should be transferred to the Radio Operator in the TSC.

(5) Upon receiving authorization from the Emergency Coordinator to dispatch the Teams, the SRPC should:

(a) Advise the Security and Support Supervisor that the Field Radiological Monitoring Teams are to be dispatched.

(b) Instruct the Radio Operator to advise the teams that they are under the control of the TSC and that all further communications are to be conducted with the TSC.

(c) Instruct the Radio Operator to dispatch the Teams to specific locations, to await further instructions.

(d) The SRPC will advise the Field Radiological Monitoring Teams of any releases in progress and the magnitude of the release.

I

NIP*EMENTINPROCEDU EPIP 3.2! " i i

': ' Rev. 13 FIELD RADIOLOGICAL MONItOrING Rev. 13 Page 9 of 31

"~I'

"* NOTE ' "

The SecuiriW and Support" Supervisor' should coordinate egress of morlitoring teams from DAEC with DAEC Se'ddritý' personnel "and members of Local Law-Enforcement Agencies, as appropriate... . . ..

3.3 PLUME DETECTION AND MONITORINGPRECAUTNS (1) The presence of a radioactive plume,should'be detectedbythe Field Radiological Monitoring ;Team by observing increasing count rates or dose rates on survey instrumentation ,used with the window-of the vehicle rolled down and the instrument heldoutside the vehicle.

(a) Upon observing an increase in count rate' or dose- rates,'the Team should inform the TSC of levels encountered and their location. The data

- should be documented in acc6rdance with instructions..". ,

, , I* , !.*. , * . r"* *" "

(2) To determine if the plume is on'the ground, open and closoea S6hield surveys should be made with the probe iield'6utside the vehicle."

NOTE ,

For the E-140. (or eguivalent),,place'hanod ,over .. :.

,the window for clQsedwi1dow surviyser.:,,L . 1' (a) Ifthe open shieldsand closed shieldreadings'are app~oximately the same, the team IS NOT in the plume. . ,,. ,

(b) An open shield reading that significantly exceeds.a cldsed shield reading (i.e., two to three times higher indicates that the ,teamlIS'in the plume.

(3) If abnormally high dose rates persist even after'itis expected that the plume has been exited, perform a radiation -srveyof the vehicle. (Inside and outside

- including personnel) ... .......

{EMERGENCY PLANIMPLEf-ENTING,,PROCEDURE 2 EPIP 3.2 I.

Rev. 13 FIELD RADIOLOGICAL MON=TORING Page 10 of 31 L

NOTE Caution should be observed near the air cleaner and radiator since the area is likely a source of the high radiation levels.

(a) Dose rates within the vehicle may be high enough to preclude use of the vehicle for further monitoring activities.

(b) If such is the case, the TSC (EOF) should be contacted regarding actions to be taken.

(c) If continued use of the vehicle is desired for some period of time, it may be necessary to leave the vehicle to obtain accurate survey data.

(4) Upon encountering radiation levels of 500 mRem/hr or greater, Teams should:

(a) Proceed to an area of lower dose rate (preferably background).

(b) Document the location of the high dose rate on Attachment 2, "Emergency Monitoring Log" (c) Inform the TSC (EOF) of the dose rate encountered and the location.

(d) Review instructions with the TSC (EOF) before resuming monitoring activities.

(e) Check team members personal dosimeters and record on Attachment 2, "Emergency Monitoring Log".

NOTE Entries into radiation levels of 500 mRem/Hr or greater may be allowed with authorization from the SRPC (TSC) or RAC (EOF).

(5) Communications with the Teams will normally be transmitted via radio.

I

lbiEPIP-3:2....-.

Rev. 13 FIELD RADIOLOGICAL MONITObIN, K., Page 11 of 31 (a) Ifthe radio is inoperative, the Team should proceed to a telephone and contact the SRPC to-obtain a spare radio. Caution should be used in not passing 'through the last knowih plume location.

(b) The SRPC should take actionas required to obtain'a radio and provide it to the Team.-,. .', ',

(c) The SRPC should advise the Radiological Assesgnent Coordinator, if activated, of problems and response actions being taken, as soon as possible. .,,. . ,, . , .,r,* -.

NOTE Intermittent radio communications may be due to the terrain. When this occurs, the Teams should, proceed toa higher location and try to' establish contact with the'TSC(EOF): ":

f1l"r, I - , "' -

3.4 RADIOLOGICAL MONITORINGA'AC'TIVITIES (1) The Field Radiological Monitoring Teams shall proceed to locations, as, directed. *t ,-.' .`. ..

(a) The maps of the Emergency Planning Zone, posted in the facility and the maps in the Teams' kits,"fiýy'be usedtoplan routes "

(b) 'Survey instrumentati6n 6hiould'be operating, obtheBW6flwange available to enable initial detection of elevated levels of radioacftý,.'Y' (2) Upon reaching the aisigriied' Idcatiotiho;thb Teams'shiail rei6t to tie TSC(EOF) and advise that they are standing by and rehdý' t6obtair dat&as requested.

(a) Initial offsite radiological monitoring will usually be accomplished under the direction of the SRPC.

(b) Upon activation of the EOF this, responsibility will be asýUmed by the RAC. '

EMERGENCY PLANIMPLEMENTING PIROCEDOR'E EPIP 3.2 Rev. 13 FIELD RADIOLOGICAL MONITORING Page 12 of 31 NOTE Instructions regarding coordination of this turnover are contained in EPIP 3.3, "Dose Assessment and Protective Action."

(3) Upon receiving direction to traverse the plume, the Teams should proceed as follows:

(a) Obtain survey information as necessary to identify plume edges and areas of highest dose rate (centerline), or as directed.

(b) Take air samples as requested at the centerline of the plume (or as directed).

(c) After each traverse of the plume, report survey information to the EOF, if activated; otherwise, report to TSC.

(d) Monitor each team member's dosimeter reading periodically.

(e) Periodically monitor the team vehicle for contamination after exiting the plume. Monitor the team vehicle after completion of plume tracking.

(4) Document all radiological data in accordance with instructions.

(5) The Field Teams may be directed to change out the particulate filters and charcoal ,cartridges at the environmental monitoring stations located offsite in the downwind direction prior to, following and/or during the time when a release is in progress.

(a) The location of each of the air samplers is provided in the ODAM.

NOTE Sample stations located on-site are identified in EPIP 3.1, "Inplant Monitoring."

Instructions for obtaining air samples are provided in this procedure. I

WEMERGENCYG -1 00P~.2 >

FIELD RADIOLOGICAL MONITORING- Re".13

. " ,Page 13 of31 (6) Team members should be alert to local conditions or'situations which may not be reflected on maps or which could not be anticipated by personnel involved in directing Team activities.- .

(a) Examples. include locations of members of the public who appear to be remaining in evacuated areas; accidents and whetherfuhther radiological surveys should be obtained, etc.,,- - -.

(b) Additionally, information of this nature should be recorded by the Team.

C- r NOTE Recording -of information of this nature as -well as recording, of !;,,!as'-.,much. -,radiological information -as is possible by the Field Radiological., Monitoring ,-Teams will Weigh

• I heavily during post-accident evaluation of total man-rem exposure to the public.

Consequently, "^bffsite -mhonitoring activities' should be documented ' as well- ndIF*i extensively as possible. . .

-j.

(7) Team members snould periodicay cneck iheir pocket dosimeters and record the readings' and time on Attachiment2, Emergency Monitoring Log," and report these readings to the TSC/EOF,. * , rcm,, :lL- "

(8) Authorization for tean)_ qembers to~exceed theDAEC9 adgist ative exposure limits orjthe adminstralynof potassium iodide (KI) pust be'r.ecommended by the SRPCand apprqved by.the Eer"em c¥ Coo'rdinator, oriace-by-case (9) While conducting surveys, the Field Teams shouldminirpize the contamination I of survey equipment. - - -

I I

-- 1-ý EMERGE-NOY'PLANIHMPIIMENT44 PRCDR EPIR 3.2 Rev. 13 FIELD RADIOLOGICAL MONITORING Page 14 of 31 3.5 AIR SAMPLING (LOW VOLUME SAMPLES)

(1) Load the air sampler with appropriate filters (Particulate and Iodine).

NOTE During drills, charcoal cartridges should be used in lieu of silver zeolite cartridges.

(2) If the vehicle battery is used, raise the hood on the vehicle and leave the vehicle running.

(3) Connect the air sampler to the battery, ensuring the red lead goes to the positive (+) terminal.

(4) Turn the air sampler "ON".

(a) Take precautions to prevent contamination of the sampler.

(b) The sampler should be positioned approximately waist high.

(c) Obtain a 1, 5 or 10 cubic foot air sample, as instructed.

NOTE Normally, a 10 cubic foot air sample will be obtained in those areas where dose rates are low, ie; <5 mr/hr. A 1 cubic foot sample will be taken if dose rates are high, ie; > 200 mr/hr.

(5) Periodically perform a radiation survey on the radiator of the vehicle.

(6) Record information regarding the sample on Attachment 3, "Air Sample Identification." Include the count rate and airborne activity based on field assessment, as appropriate.

NOTE The filter paper and silver zeolite cartridge should be stored separately.

I

-EPIP32-FIELD RADIOLOGICAL MONITORI!NG 16,Rv1 Page 15 of 31 (7) Remove the sample from the'sampler, takl~ing" precaution's to prevent sample contamination.

(a) Place the samrple-in a plastic bag, attach the Air Sample Identification label and seal the bag.

(b) Position' the sample in the vehicle to minimize exposure to the occupants of the vehicle.

(8) Monitor the filter cartridge.with a survey instrument, determine the airborne activity concentration, record the results, and report same to the TSC (or EOF) as follows: ' " - '

(a) Record the count rate or dose rate, as appropriate, -using either an E-140 (or equivalent) or an operi'windo'w RO-2 (or equivalent).*

(b) Using Attachment 4, "Conversion of Air Sample Results into Radioiodine Concentrations," convert the survey instrument reading to airborne

,activity concentration based ,upon the sample volume drawn.

(9) Deliver samples as described in this procedure. .

3.6 RADIOLOGICAL SAMPLING  :

"(1) As directed by either the SRPC or RAC'-team members shoulA initiate selected environmental sampling'activities in accordance with 'DAEC ESP's.

, >.-, , , , ~..."

., " -","', * 'i:*.o 4 3.7 TRANSPORTATION.OF SAMPLES, TO. THE OFF,,SITE RADIQIOGICAL AND ANALYTICAL LABORATORY ,. ' 6 ' C "

(1) As directed by the'SRPC'( _RAC), off"ife" irfnt"a"l'Q media should be transported to the Offsite.Radiological anc !AnalyticalLab'ot'tory (ORAL) by one of the following means: ,

(a) Samples may be taken-lirectly t6 the ORAL bý'the U*dit6rrg Teams, if they are close to that facility (refer to EPIP APPENDIX 1 form ODEF-3, "Travel Routes to the.ORAL/ODEF").-_ -- .

(2) If samples are to be delivered to the offsite laboratory, the RAC should contact the ORAA Supervisor (if activated) .or the SRPC and request that he dispatch a "Sample Runner.' * - ..

(a) Prior to dispatching the Sample Runner, the ORAA Supervisor or the SRPC should ensure that the Sample Runner has been properly briefed regarding:

i) Sample pickup point.

NOTE The sample pickup point designated for environmental sample media transfer should be selected such that it will minimize the amount of time the Monitoring Team(s) will have to suspend plume monitoring activities.

ii) Route(s) recommended for travel to the sample pickup point to avoid the plume.

iii) Travel route to the ORAL. (See EPIP APPENDIX 1 form ODEF-3, "Travel Routes to the ORALIODEF").

iv) The Sample Runner should have appropriate dosimetry and a TLD.

v) The RAC, or SRPC, should advise the Security and Support Supervisor in the TSC of the planned transport of samples to the ORAL.

vi) Once the Sample Runner and Monitoring Team(s) have reached the sample pickup point, samples should be transferred to the Sample Runner's vehicle by the Monitoring Team Leader. Samples should be located in the vehicle such that the exposure to the Sample Runner will be minimized. The outside of the bags should be wiped down to minimize spread of contamination.

NOTE The Sample Runner should at all times avoid handling samples. Samples are to be handled by qualified personnel only. I I

EMFPL PL IFGrtEPIR-3.2 "Rev.13 FIELD RADIOLOGICAL MONITORING- , ,

-. "Page 17 of 31 vii) The Sample Runnersshould proceed to'the ORAL to deliver Ssamples. - '

3.8 ON-SITE FIELD RADIOLOGICAL MONITORING (1) Personnel shall be assigned to the On-Site Field Monitoring Team by the appropriately-numbered tags on the Emergency Assignment Tag Board, as specified in EPIP 2.1, "Activation and Operation of the6OSC".

(a) The OSC HP Supervisor may elect to reassign personnel initially" assigned to the'Teams to takl maximum'advantage of the capabilities and experience of pers6nnel available to perform'radiqological monitoring functions. ... .

(b) Activities to be completed by personnel assigned to theOn-Site Team prior to being dispatched dre identified"on the chlicklists.

NOTE EPIPMForm TSC42"Oiisiie Map";should be' used when reporting location of survey data to the TSC/OSC.

(2) In making preparations for conductingmonitoring activities:

(a) The SRPC shall evaluate location and mr-gnitud6 of the projected on-site dose rates, asspecified,in EPIP 3.3,ý 'Dose Assessmenet and Protective Action";, relafyhis inora*fvion to the OSCoHl Supervisor and identify the

.sequence of moriitbýnc ,acttiviT§tq le conducted.

(b) The OSC HP,Supervisor shaill brief the Team with this information, as well as the precautions to be tarken, and ensure that the team members are appropriately d6sse, havetle required dosimetry, and have checked out thl6 operation of their"equipment..

(3)' The Onsite Team may be directed toc'hange out the particulate filters and charcoal cartridges at the environmental monitoring stations located onsite prior to, following and/or during the tinie when a release isin progress..

S(a) The'particulate filters and charcoal cartridges located at both -stations on site should be changed.

SEMERGENCY )AN lMPLEIENTiN POREDOCEDURE EPIP 3.2 Rev. 13 FIELD RADIOLOGICAL MONITORING Page 18 of 31 NOTE When changing out charcoal cartridges, they should be replaced with Silver Zeolite cartridges.

(b) Directions to each air sampler are provided in the ODAM.

(4) The Onsite team may be directed to perform habitability checks of the Badging Center, PSC, and Training Center prior to evacuating these areas as necessary.

(5) The OSC HP Supervisor shall advise the OSC Supervisor and SRPC when the Onsite Team is ready to be dispatched.

(6) The SRPC shall assume control of the Onsite Team, and dispatch them after ensuring that the Security Shift Supervisor has been advised.

(7) The following surveys will normally be conducted and documented in accordance with the accompanying procedure:

(a) Radiation survey in accordance with HP Procedures.

(b) Radiation contamination surveys in accordance with HP Procedures.

(c) Airborne radioactivity surveys in accordance with HP Procedures.

NOTE Instructions for obtaining a low volume air sample and estimating the activity concentration using a portable survey instrument are provided in this procedure.

(8) Onsite Monitoring personnel should maintain communications with the TSC via radio.

(9) Upon completion of the survey and as directed Team members shall return to the OSC, observing all control point requirements, and report to the OSC HP Supervisor for further instructions and debriefing.

EMERGEN~CY PLANlMPL~E' NPP-3.2REDNRE "Rev.13 FIELD RADIOLOGICAL MONITORINGA k ~ ,Page 19 of 31 3.9 AIR SAMPLING (LOWVOLUME'SAMPLES)

(1) Load the air sdmpler with appropriate filters.

NOTE.

Use -of Silver -'Zeolite cartridges- is re66mmended wvh6n 6t'baining I6w volume -air samples to detect radioiodines.

(2) Perform a radiation survey on the radiator of the vehicle.

(3) Raise the hood on the vehicle and leave the vehicle running.

(4) Connect the' air sampler to the batter'y,'ensurinIg the iedilead goes to the positive terminal.

(5) Turn the air sampler "ON":_

I .9-'

(a) Take precautions to prevent contamination of the sampler.

(b) The sampler should be held'ap'proximately Waist high.,'"

(6) Obtain a 1, 5 or 10-cubic foot *ir'sanmple, as inistructed."

,, ",-,, "'2 ; ,E"' ','* , .. , "O7~ , (*.i;:'9 "NOTE:' '* ~.....

i" Normally, a 10,cubic f6'& air sample' will be obtained in those areas where dose rates are low, i.e., :irikr/'A I cbbi.foGt sample will',be -'I taken if dose rates are higg, jie., >200 mrr/hr."

" II I (7) Record information regarding the sample on Attachment 3, "Air Sample Identification". Include the count rate and airborne activity based on field I

assessment, as appropriate. - " '

(8) Remove the sample from the sampler, taking precautions to prevent sample cross-contamination.

(a) Place the sample in a plastic b'aj, attach the Air Sample Identification label and seal the bag.

PROCEDUE IEPIP 3.2 Rev. 13 FIELD RADIOLOGICAL MONITORING Page 20 of 31 (b) Position the sample in the vehicle to minimize exposure to monitoring team members.

NOTE The filter paper and Silver Zeolite cartridge should be stored separately.

(9) Evaluate the filter cartridge (Silver Zeolite) with a portable survey instrument, determine the airborne activity concentration, record the results, and report same to the TSC (or EOF), as follows:

NOTE Sample evaluation must be conducted in a low background area; therefore, the Team may be required to travel to another location in order to evaluate the sample.

(a) Record the count rate or dose rate, as appropriate, using either an E-140 (or equivalent) or an open window RO-2 (or equivalent).

(b) Using Attachment 4, "Conversion of Air Sample Results into Radiological Concentrations", convert the survey instrument reading to airborne activity concentration based upon the sample volume drawn.

(c) Report results as iodine concentration in qCiicc.

I

Rev. 13 FIELD RADIOLOGICAL .MONITRICK Fey. 13 Page 21 of 31 3.10 DOCUMENTATION AND ROUTING OFONSiTE MONITORING ACTIVITIES (1) Documentation of radiological monitoring activities results should be provided to the Admin Supervisor in the TSC where three copies of each document shall I be made. ,

NOTE -

As conditions warrant, the SRPCand the OSC HP Supervisor may need this documentation.

immediately; therefore, they s~hould be allowed to review the documentation ' before' it is forwarded to the Records Clerk. -

(2) The original should be retained by the Admin. Supervisor in the TSC.

(3) The SRPC and the OSC HP Supdrvisor should be jbrovided'porie copy each of I

all documentation. ...... . e (4) The other copy should be distributed, as follows: .

(a) Habitability surveys - He'lii PhysicsAccess Cohlidl'Poirht" (b) " In-Plant surveys - HealthlP'hybibs Access ControloPbit .

(c) On-Site'monitoring.activities -,,HealthPh'si cg.Access Gontfol Point 3.11 DOCUMENTATION OF RADIOLOGICA L MONITORING DATA", .

(1) Radiological monitoring data gathered at the offsite areas shall be recorded on Attachment 2, "Emergency Monitoring Log" (or equtivalent).

(2) Entries shall include the following information, as applicable.

(a), Date * ..

(b)' Page number (c) Team Leader and Tearm Member names (d) Exposure limit

-'EMER GENCY, PLAN IMPLEMENT! P*!MCMD*RE EPIP 3.2 Rev. 13 FIELD RADIOLOGICAL MONITORING Page 22 of 31 (e) Wind conditions (f) Personal dosimetry readings (g) Survey instrument information (h) Air sample data

a. Time

b. Location

c. Volume (ft 3)

d. Activity (LCi/cc) (Refer to Attachment 4, "Conversion of Air Sample Results into Radioiodine Concentrations").

(i) Location of survey (See Step 3.12, "Determining Sample Point and Plume Locations")

(j) Date and time of survey (k) Radiation levels in mR/hr or R/hr (open and closed window readings)

(I) Pertinent observations by Monitoring Team members, including physical hazards (m) Initials of the individual rewording the data.

(3) The Emergency Monitoring Logs and any other pertinent notes should be provided to the OSC HP Supervisor upon returning to the plant and subsequently provided to the Admin Supervisor in the TSC.

3.12 DETERMINING SAMPLE POINT AND PLUME LOCATIONS (1) By use of available maps:

(a) Use the maps provided to determine your location as close as possible.

Be sure to capture and document information such as landmarks and demarcations in order to be able to return to the same location if necessary. This is the 'normal' method of determining sample point and plume location.

(2) By use of the Garmin 45XL GPS Unit:

LM[EM ENT INGP P GED URE AEPIP I EP1P3.3."2_____ -__"__,_"

Rev. 13 FIELD RADIOLOGICAL MONITORING' ," .. ,

Page 23 of 31 Note The Garmin 45XL GPS Unit is needed when providing exact location information for use when performing back-calculations for -Dose Projections (MIDAS). The location information A-needed for MIDAS is distance from the Offgas Stack and the direction from YOUR location TO the Offgas Stack.

The Garmin 45XL GPS Unit is also needed when providing information in coordination with government agencies in support of an emergency-at DAEC" Tie common sta'ndard is to document -,location Jifformati6n' using latitude and longitude.

(a) To determine where you are in relation to the Offgas Stack:

1. Turn on and initialize GP,S unit (reference instructions provided with unit).

-P  !.I "2.Press 'GOTO' arn'ds'ýl6ct 'Stack'

3. Press 'PAGE,'until you get to the screen t1a, has Bearing

- (BRG) and'gistanrce"(DST);on it. -'lnformtheiS"e 'SýCEOF) of the SBearipgand Distance fromyour position to theOffas Stack.

(b) To determine whertLo airearn,Latitude'andLo'ngitude:-,

1. Turn.on and initialize GPS unit.(reference instructions provided

'with uniit): " ' "' ' " ' ' ' *"'

2. Press 'PAGE' until you get to the-screen that has 'TRACK' and

'SPEED' on it. The coordinates under 'POSITION' are latitude and longitude (in that order). Inform theTSC(EOF)'of your latitude arid longitud e.

e ' ,

i

PRCENJ;rc1 EPI 31.2 Rev. 13 FIELD RADIOLOGICAL MONITORING Page 24 of 31 4.0 RECORDS (1) All records generated by this procedure shall be retained in accordance with EPDM 1007 and QA Record Retention Requirements.

5.0 REFERENCES

(1) DAEC Emergency Plan (2) NUREG 0654 FEMA-REP-1 Rev. 1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," November 1980 (3) NUREG-CR-5212, "Emergency Environmental Sampling and Analysis for Radioactive Material Facilities" (4) EPIP 3.3, "Dose Assessment and Protective Action" (5) EPIP 2.1, "Activation and Operation of the Operational Support Center" (6) EPIP 3.1, "Inplant Monitoring" (7) Offsite Dose Assessment Manual for Gaseous and Liquid Effluents (ODAM)

(8) HP Procedures (9) DAEC Environmental Sampling Procedures (ESP's) 6.0 ATTACHMENTS , 'Typical Radiological Monitoring Team Briefing Topics" , "Emergency Monitoring Log" , "Air Sample Identification"

, MER*E M L 6`;`32"" E 'EEPIITGR i "-'-'Rev. 13, FIELD RADIOLOGICAL MONI"ORING ": Re.,1 Page 25 of 31 , "Conversion of Air Sample Results into Radioiodine Concentrations"' ;"Emergency Environmental Sample Collection-Record, typical" , "Emergency Environmental Sample Log, typical".. -...

t2 )

" {j o-V ' I-', ,.'; t f F . ,

F

~iEMERGENCY~PLAN IMPtEMEh FiNG PROCEOURFE$. EPIP 3.2 Rev. 13 FIELD RADIOLOGICAL MONITORING Page 26 of 31 ATTACHMENT I TYPICAL RADIOLOGICAL MONITORING TEAM BRIEFING TOPICS (1) Meteorological Information, including:

(a) Wind Speed (b) Wind Direction (2) Radiological Information - if a release is in progress:

(a) Release Point (b) Release rate (c) Maximum projected dose rate and location (d) Plume boundaries (e) Affected sectors/area (3) Location to which Teams will initially be dispatched, routes to be used to avoid radiological hazard areas if such exists, and tasks to be accomplished.

(4) To the extent capable of being projected, the duration of time until either a release begins or is stopped.

(5) Documentation requirements (maintenance of logs and charts)

(6) Protective measures to be employed.

(a) Consider the need for dose extensions.

(b) Authorize use of KI.

(c) Protective clothing/respiratory protection equipment usage.

(7) Reporting requirements, including, for examFle:

(a) Radiation survey readings (b) Airborne sample estimates (c) Unusual or unexpected problems or situations which may impact the ability to perform monitoring functions (d) Observations of actions taken by local, State or Federal assistance groups or the public (8) Precautions to be observed upon entering the plume and as appropriate, in high radiation fields.

,EPIP 3.2' t

'- MONITGRI.G.

• Rev. 13 FIELD RADIOLOGICAL MONITRING, K> Page 27 of 31 "9  ;

ATTACHMENT 2 "

EMERGENCY MONITORINGILOG)

C.

I Date TEAM - ,Page__ of_

TEAM LEADER CI) PERSONAL DOSIMETRY READINGS SURVEY INSTR. INFORMATION TEAM MEMBER TIME T L T M TIME T L 'M TYPE , °SERIAL CAL DUE (IM) NO.

EXPOS. LIMITS

-4 EXTENDED TO WIND SPEED / TIME DIRECTIONfTIME

. c iAIR SAMPLE DATA '., , C ',,

4 .- I I INST. USED SAMPLE LOCATION START TIME STOP TIME tdw (CFM) VOL' 'NI'CPM (IODINE) IOD&IE 131 (pCVcc) 4 F 4 4 4 F 4 RADIOLOICAL DATA - '

LOCATION TIME OPEN/CLOSED REMARKS LOCATION TIME " 'bP1 N/CL(SED REMARKS

___,_______-__,___. ,,____.____....__-___"_-___ a."*,"

,-ei, v pr',./

I . ,, , , , ,

• r  ! "lr' 4 If~;

I -/

/ ~ /

/ /

I I I I

/ I PERFORMED BY: DATE.

I

EMERGENCY PLAN ELMEITING PROCEUR EPIF) 3.2 Rev. 13 FIELD RADIOLOGICAL MONITORING Page 28 of 31 ATTACHMENT 3 AIR SAMPLE IDENTIFICATION AIR SAMPLE SAMPLE LOCATION DATEITIME ON DATErrIME OFF SAMPLE FLOW RATE CFM SAMPLE COLLECTED BY I

'EME,,P NýF M ýTN 'PG E U E EPIP 13.2, Rev. 13 FIELD RADIOLOGICAL MONITORING Page 29 of 31 ATTACHMENT4 NOTE: This chart is only applicable for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the Reactor scram.

Conversion of Air Sample Results Into Radiolodine Concentrations E-140 or RO-2 COUNT COUNT COUNT RATE RATE RATE (cpm) ift 3 5ft3 lOft 3 (cpm) ift 3 '"5ft3' , lOft3 (cpm) 5 lft3 50 lo0 100 3 18E- 6.36KE-9 3 19-o9 5700 1.81E-6 3 63E-7 1 8E-7 23K 7-32-6 1.48E-6 7.3--7 200 wo 6 36F-8 127E-S 6 36K-9 1.823-6 3 69E-7 1 85E-7 24K 7.54E-6 153 764E-7 T

2O0 9 54E-8 191E-8 9 54E-9 5900 1.88K-6 3.75E-7 1 88E-7 25K 7 95E-6 159E-6 7 95E-7 400 127E-7 2.$4E-8 1.2rE-8 6=00 1.91K-6 3 82E-7 1 91E-7 26K 827E-S6 I K -6 27E-7 Soo 1.59E-7 3 18E-$ 1 59E-8 6100 1-94E-6 3.88K-7 1 94E-7 27K 8 596-6 1.72E- B 59E-7 600 I 90E-7 3 S2-8 I 9OE-f 6200 1.97K-6 3 94E-7 1 97E-7 28K 8 9IE-S 1.78E-6 8 91E-7 700 2-2E-7 4 45E-8 223E-8 6300 2OOE-6 4 00K-7 Z00?-7 29K -923E-6 9 1 8,E-6 9 23E-7 800 2 54E-7 5 09E-8 2 .5E-8 6400 2.04E-6 4 07E-7 2.04E-7 30K 9 54E-6 1 91E-6 9 54E-7 S00 2 86E-7 5 72E-8 2 865-4 6500 2 07E-6 4 14E-7 2 07E-7 31K 9 86E-6 1.97-6 9 868E-7 1000 3 18E-7 6 36EK8 3 18KE-f 6600 2.10E-6 420E-7 2 10E-7 32K 1.01=-5 2 04E-6 1 02K-6 1100 3 49E-7 6 99K-3 3 50E-8 6700 2.13E.6 42KE-? 2.13E-7 33K 1.05E-5 2.10E-S - I 05E-6 1200 3 81E-7 7 64E-8 3 82E-8 6800 2.16E-6 433E-7 2.16E-7 34K I 09-5 2.16E-6 10KE-6 1300 4 13E-7 8 27E-8 4 14E-8 6900 2-0KE-6 4 39E-7 2.20E-7 35K 1 11E-5 2.23E-6 111E 1400 4 45E-7 a 91E-K 4 45E-8 7000 223E-6 4 45E-7 2.23E-7 36K 1.12E-5 2.29K-6 1.15E-S 1500 4 T7E-7 9 54E-8 4 77E-8 7100 22SE-6 4 52E-7 3.26E-7 37K I 18KE-S 32. -6 11 8E-6 1600 5 09E-7 1 02K-7 5 09E-f 7200 - 229K-6 4 58E-? 2.29E-7 38K 121E-S 241E-6 1.21E-6 1700 5 40E-7 1 08E-7 5 41E-S 7300 2.32E-S 4 64E-7 22.3-7 39K 1-24E-5 2 4SE-6 1.24E-S 5 73E-7 1 5E-7 5 73E-fl 7400 2.35K-S - 471E-7 232E-7 40K 127E-5 2.54E-4 - 1.27K 19oo 6 04E-7 121E-7 6 04E-8 7500 2.39E-S 4 77E-7 239E-7 41K 1.3KE-5 2A6IE-6 I 30E-6 200O 6 36E-7 1.27E-7 6 368-8 7600 2.41E-6 4.94E-7 2-42E-7 42K 1.34E-S 2.62E-6 1.34E-6 2100 6 68E-7 I 34E-7 6 68KE 7700 2.4SK-S 4 90E-7 2 45E-7 43K 1.39K-S 2.74E-6 17E-6 2200 8 99E-7 1 39E-7 6 99E-8 7800 2-48E-6 4 96E-7 3.4KE-7 "44K 1A4E-5 23.8E-6 I 40E-6 2300 731E-7 1 46K-7 7222E-8 7900 2.1KE-S 5.03E-7 .51E-7 45K 1.43E-S 2 86E-6 I 43E-6 2400 7 63E-7 1 52K-7 7 64E-8 8000 2.53E-, 5 09E-7 3.55E-7 46K 1 46E-5 2-93E-6 I 46E-6 2500 7 95E-7 1 59E-7 7 95E-5 8100 2.58E-6 5.1M3-7 2.8E-7 47K 1.50K-5 2.99E-6 - 1 50E-6 2600 8 27E-7 1 65E-7 8.27E-8 8200 261SE-6 5.22E-7 261IE-7 45K 1.53-S 3 05E-6 I 53E-6 2700 8 58E-7 1 72E-7 - 859E8 8300 2.84E-S 52SE-7 864E-7 49K - 1.6K-S - 3 12-6 1 5KE-6 2800 8 90E-7 1 7KE-7 8 91E-8 8400 2 67K-6 5.34E-7 2.87E-7 50K I 59E-5 3 18E-6 1 59-6

.. 2900 9 22E-7 1.85E-7 9.23E-8 2 70E-6 5 40E-7 2-70E-7 S51K 1 62E-5 325E-6 1 62E-S 3000 9 54E-7 I 91E-7 9 54E-8 8600 2.74E-S 5 47E-7 2.74E-7 52K 1 62E-5 3 31E-6 1 65E-6 3100 9 86E-7 1 97E-7 9 9E-8 SSW B700 2 77E-S 5.54E-7 2.77E-7 53K 1 69E-5 3 37KE-6 1.69E-6 3200 1 01E-6 2 04E-7 1 02E-7 6900 2.80K-S 5.60E-7 2.80E-7 54K 1 72E-5 3 43E-6 I 72E-S 3300 I 04E-S 2.10E-7 I 05E-7 8690 2 3E-S 5.66E-7 2.83E-7 55K 1 72E-5 3 49E-6 1 75E-6 3400 I 98E-6 3.16E-7 I 08E-7 6500 2 86E-4 S 73E-7 2.-6E-7 56K 1 78E-5 3 56E-6 I 78E-6 7000 350o 1 11E-6 223K-7? 188E-7 8100 2.89E-6 5 79E-7 2.90E-7 57K I 81E-S 3 63K-S I.E-S 3600 1.14E-S 2.29E-7 -1.15E-7 9200 2 92M-6 5 8E-7 3Z93E-7 58K 1 85E-S 3869E-5 1.823-6 3700 1.17E-6 2.35E-7 1.18E-7 6300 2 96E-6 5 92E-7 2.96E-7 59K 188E-S 3 75E-6 I 88E-6 382O -120E-6 2.24E-7 121E-7 94500 2 99E-S 5 8E-7 - 2.99E-7 60K -191E-S 3 82E-6 11KE-6 3950 124E-6 2.48E-7 124E-7 9500 3 28-S 6 045-7 3 023-7 61K I 94E-5 3 88E-S 1 4E-S 4000 1275E-6 Z54E-7 127E-7 8600 3 058E-. - 11E-7 3 05E-7 62K 187KE-5 3 84E-6 187-4100 1.30K-6 2.61E-7 120E-7 9700 388KE-6 6 17E-7 3 09E-7 63K 2.-0E-5 4 01E-6 2 90K-S 4200 1-33E-6 2.57E-7 1.34E-7 98W0 3 12E-S 6 24E-7 3 12E-7 64K - 204E- - 4 07E-6 2 04E-6 43W0 1 36E-6 Z74E-7 1 37E-7 9M0 3 15E-S 6 30E-7 3 15E-? 65K 207E-5 4 14E8- 2 07E-6 4400 1 40K-6 2.79E-7 1 40E-7 21K 3.1E-6 6.36E-7 3 18E-7 56K 3.10K-S 4-20K-S 2.1K-S "4500 I 43E-6 2.86E-7 1 43F-7 I2K 3 50-6 6899E-7 3 50E-? 67K 3.123-S 426K-S 3.13-S 4600 1 46E-6 2 93-7 1 46E-? 12K 3.82E-6 7 64E-7 3 82-7 68K 3.19K-S 4-23K-S 31E6K

-4700 1.50E-6 2 99E-7 -1 49E-7 13K " 4 14E-6 8.2"E-7 4 14E-7 69K 20K-5 4-39E-6 2.20KE 4500 I 52E-6 3 02E-7 I 53E-7 14K A 4E-6 8391E-7 4 45E-7 70K 223K-S 44SK-6 223E-6 4900 I 56E-6 3 12E-7 1 56E-7 4 T7E-S 954E-7 4 77E-7 8lmRfl" 2 55E-5 5 10E-6 2.55E-6 8000 "1.59E-6 3 18E-? 1.9KE-7 16K 5 09E-S 1.02.-6 5 09E-7 125R~r 3 18E-5 6 36E-6 3 18K-6 5100 .62K-S 3.25E-7 I 82E-7 17K 541E-6 108E-6 5 41E-7 3 82K-5 7 64E-6 3 82-6 8200 I 65E-6 3 31E-7 1 62E-7 13K 5 73E-6 115E-6 5.73E-7 4 77E-5 6 54E-6 4 7TE-,6 5300 I 69E-S 3.37E-7 1.69E-7 18K 6 04E-6 121E-6 6 04E-7 10,PJhr 6 36E-5 I 27E-5 6 36E-6 5400 25nRt 7 95E-6 1.72E-S 3 44E-7 I 72E-7 20K 6 36E-6 1.27E-6 6 36E-7 7 95E-5 I 59E-5 5500 I 75-6 3 50E-7 1 7.E-7 21K 5 68E-S 1234E-6 6 6W5-7 9 54E-5 1 91E-5 9 54E-6 5SSW I 7KE-6 3 56E-7 1 7BE-7 22K 6 99-6 1 40E-6 6 99E-7 ,50ffRRw 1 59E-4 3 18E-5 1.59E-5

I_-

'*EMERGEN PLAN IMPLEM ENTING I PROGEDURE EPIP 3.2 Rev. 13 FIELD RADIOLOGICAL MONITORING Page 30 of 31 ATTACIHMENT 5 I

Emergency Environmental Sample Collection Record typical Sample #

Date/Time Location Sample Type Contact Dose Rate Sample Collector Personnel Chain of Custody Record Relinquished by Recieved by Picture ID Date Tiem Reason for change (sampler) of custody White copy stays with sample.

I

7 1 MEENTIN.E GRROCED&* ,* EPIP 3.2"

-.Rev. 13 FIELD RADIOLOGICAL MONITORING Page 31 of 31 ATIACHMENT 6 Emergency Environmental Sa mipleLog typk i,,I Team: Team Leader: ...

Sample # Sample Sample type Dose rate Date/Time Supplemental Sample by Location (be sample specific) information I i

- .. . .. . . .. . ..- ... .... . .. . i . .

EPIP 3.3 K-) DOSE ASSESSMENT AND PROTECTIVE ACTION Rev. 18 Page 1 of 26 I

I ,

Effective Date: , (1, 1 ,, II.

11

- ~PROCEDURE, APPROVAL r I am responsible for the technical ýontent of this procedure.'

Approved by: (iQ . C Date:

Manager,, Emergency Planning

E ME R.... N. P I.P L,,*F,-,Fz N..*IN PROE* URES EPIP 3.3 Rev. 18 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 2 of 26 Table of Contents Pa1e 1.0 PURPOSE......................................................................... 3 2.0 DEFINITIO NS .......................................................................................... 3 3.0 INSTRUCTIO NS ...................................................................................... 3 3.1 PAR DECISION MAKING ............................................................ 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 R EC O R D S ................................................................................................. 15

5.0 REFERENCES

........................................................................................ 15 6.0 ATTACHM ENTS ...................................................................................... 15 ATTACHMENT 1, EVACUATION TIME ESTIMATES ............................. 16 ATTACHMENT 2, WIND DIRECTION AND AFFECTED SUBAREAS ........ 26 I

NtMERGEN

ýPSL 4 M & OE ~P33i S;*',*

DOSE ASSESSMENT AND PROTECTIVEACTION ,

,iRev.

Re.

18 18 i

Ku Page 3 of 26 1.0 PURPOSE (1) This proceduire 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 "

4.3.: 3 J. 3 ,' ,f (1) MIDAS Meteorological Information and Dose Assessment System.

(2) PAR (Protective Action Recommendation) - Made to the State with regards to evacuation or sheltering of subaireas within the Emergency Planning Zone S~(EPZ (3) PAG (Protective Action Guides),- Established by, the Environmental Protection Agency (EPA) Reference 2.

3.0 INSTRUCTIONS 3.1 PROTECTIVE ACTION'k RECOMMENDATION DECISION MAKING (1) At the initial Emergency Classification declaration, the on-shift chemist reports to the TSC MIDAS Compute&to initiade MIDAS " i"r"rn" '

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.

S~ EMERGENCYGY* N IMM ING EROCE EPIP 3.3 Rev. 18 ACTION DOSE ASSESSMENT AND PROTECTIVE Page 4 of 26 (b) If the EPA Protective Action Guides (PAGs) 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-05.

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

(c) Continu'e 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 appopriate 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.

-V

. * " .Rev. 18 DOSE ASSESSMENT AND PFWRTEC'V*EAACT'IOiN,' "';

,) Page 5 of 26 (7) Protective Action Recommendatidris-sfhduld 1be deterfiined '(forkcast weather information should be considered duirnall Protective Acotion'D1ision Making) by: -* . :'

(a) The Operations Shift ManagerfSfpervisor-if neither the TSC'hdr the EOF is activated. This persgbh isi'ýe*spbnsible for ehsuring that Protective Action Recommendations &re prbvided'tb offsite authiorities:

(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*Coordinatbr-shall ensure that this information is provided to offsite authorities.

(c) The Radiological and EOF Manager, assisted by the°Radiological Assessment Coordinator,"upon activatiori of the:EOF.--These persons

-,shall assume responsibility for development and recomnmendation of the Protective Actions and, upon approval by the Emergency Response and Recovery Director, provide formal communication of these recommendations t6 offsite a'gencies. '_

> (8) Recommend the Protective Actions as specified in PAR-01 for all declared events. .. s r a.¶:., ' . , .3 a, f4 r .4'; '-.*.*"

(a) If the situation is degrading such that a potential exists for declaration of

'a General Emergency, eValuaitetrehdsland pgr6ghosiý .ff*fthange to determine the need foirprecautionar' pi-otective° mkdresfor'the general public. -

(b) 'Pay special attention tovwind direction-and - pIed'asý-tl'i ay'lead to a

Protective'Action:Recommenda*ion- fgr.other affected b-9Kreas;*f "referenceAttachlient 2;"W-ind 'Di ection and Affecte*d,8[lbreas'."

(9) Field readings should be used to evaluate Protective Action Recommendations..lf'asignificant nuniber of~actual dose rat4t,'Tiheasured in the field, are greater than' those projetted to'be occurring,atithe 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 Notificatioh Form'. .' '

I V-EEPLCAN IM[MEN. jFROCEDURF., EPIP 3.3 Rev. 18 ACTION DOSE ASSESSMENT AND PROTECTIVE Page 6 of 26 (a) The Emergency Coordinator/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 EOC's, 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 shouid 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.

I

-EPIP:3.3V

• Rev 18 DOSE ASSESSMENT AND PROTECTfVE, ACTION, K.-"Page7 of26 (b) Weather forecast information., This infoýmation can be'obtained from the National Weather Service (phone -number listed iA* the ETB).

(c) Meteorological information, including stability class (or AT), wind speed and wind direction from the Salfety Parameter Disjolay System (SPDS). If meteorological information cantfbt be obtained'fr6rnmSPDS via the Met Tower, then call the National Weather Service phone number and request an update of the curren't Wdt conditiohs.

(d) The results of dose projection calculations. .

(e) Containment High Range Radiation'Monitor'leve  :

(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 RadiologicalMonitoring Teams,-, . 2' (i), .Plant status information and prqgnosis for deteriorating conditions.

(j) The status of activation of the (ff-site Radiological and Analytical Laboratory (ORAL). ,- ." . - -S, 1.) EA'.

, V, ;-, r , - .- . . ii(j', .

(k) The status of activatin ofthe Off-ite Radioogical and, A ssembly.Area Area (ORAA).

(2) ade thbe Emeargenc!rokeConrdoordiertiieh s ummarze thisinformation, advise the Emergency Coordator of pertinent points discussed, and brief the Radiological Asse'ssment Group.' _* .: ,.. +. ,

T

~ h e~ ~ ,O R - '* '.

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

(a) The Radio Operator/Field Team Director should ensureithat the Offsite Radiological MonitoringTeams are'apprised of pertinentinformation regarding plant potential radiological problems expected.

EMERGE NCY PLAN IMPLMENTIG IROCEDUR ES' EPIP 3.3 Rev. 18 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 8 of 26 (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.

(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 Teams should be initially briefed and dispatched in accordance with EPIP 3.2, "Field Radiological Monitoring."

NiN 3EQ1VE. 4 .3!

I-EMERG-EPP3 .... .P..

- *',:, , '*/- Rev..18 DOSE ASSESSMENT AND PROTECTIVE A,*CT6ION *v .18 Page 9 of 26 (2) Inrpreparationfor directing the Offsite Radiol6gical Mohiitorinb 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 Moinitoring Teams, the Field Team Director should:

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

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

(c) Advise the Teams of the latest radiological and plarif't"atu's information, as necessary to perform their duties safely. ,

(d) Inform the Radiological Assessment Coordinator of readiness to assume control of the Field Radi6tooig Monitoring Teams. ,

(5) When the EOF has been activated, the Radiological Assessment Coordinator should contact the Site' Radiaton Protecbtion Coodiratbo andýidVise that the EOF is ready to assume control of the Offsite Radiologial ,Moitoring Teams.

(a) The Site Radiation ProtectionrCpor~dinator should inform the Emergency Coordinator that cohtr'ol of thbfield rf6ldi8logcal hionit.ring-4 teams and doseassessment has beeIntransferred to thn uEOF. , .,

(b) The Radiological Assessment Coordinator should then R A .-advise"' the Radiological and EOF Manager th~t the Radiological Assessment Group is ready to assume responsibility for offsite monitoring and dose assessment activities. - 4 . . -

(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.

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 Operations 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 User's Guide. If MIDAS is unavailable, the options below will be reviewed by the Site Radiation 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.

EMERG.EN N6NPROEURSI.iM&EPP1 GYP... . 0G* , Rev. 18 SASSESSENT AND PROTECTIVE ACTION Page .1.f.

, Page 11 of 26 S,. ,

(b) If there is a loss of MIDAS in the TSC consider using the f6llowing:

(i) MIDAS Backup on the Personal Computer, (ii) Use of MIDAS Laptop Cotnputer (c) If real-time data collection in MIDAS is not functional, the EOF MIDAS Operator should coordinate directlywith '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'ti6, EOF consider the'folowing:,,,

(i) Transfer of dose assessment back to the TSC..

"(ii) Use'the MIDAS Backdp ori the'Pers6nal Computer:

(iii) Use of MIDAS Lapt6p'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 fadiological monitoring activities.

OR Following review of the latest dose projection, the .Radiol6gidalPAssessment Coordinator should brief the Field Team Director on the magnitude of the projected doses and the need to'6adjtt-field radfologi*c&l oit"Thdring-activities.

(6) if Field Team readings are signifi-,I tly hijher tllaib pocte by MIDAS, consider the possibility of an unmonitored release.;,

3.5 COORDINATION OF DOSE ASSESSMENT WITH THE STATE OF IOWA (1), 'Upon activation of the EOF; the Radiological Data Communicatorshall'verify ,

that the "Rad Data Line"js established and operable or contact the State EOC and request that it be established. ' .. ,.

(2) Once established, the Radiological Data'Comrmiunicator sh allmaintain communications with the State EOC 'andthe Benton anid Linn County EOC's.

(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.

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 of 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 PASAP's.

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

(4) The Site Radiaticrn 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 radiological status, significant trends, and potential implications (prior to operation of the EOF).

I

EE6EINJPLCMElNG'ROGEDUR SEPIP 3.3" '

Rev. 18 DOSE ASSESSMENT AND PROTECTIVE, ACTION',,

> 'Page 13 of 26 3.7 DATA RECORDING AND TREND ANALYSIS-FROM THE EOF (1) The Radiological Assessment Coordihator'or'his designee should trend the following inforftiation:

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

(i) Site Boundary (ii):Two Miles.

(iii) Five Miles * - *.- !I V.,

.(iv)Ten Miles:'

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

(b) Containment High Range Radiati6n Monitors levels fOr' both'the Drywell and Torus (2) An estimate of fuel failure can be determined by using the PASAP's.

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

(4) The RadiologicalarddEOF Managerand the-Radiological'A*sessmnent Group should be periodikally advised oflhe-'current radiological status,' significant trends, and potential implications.

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

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

SRev. 18 ACTION R DOSE ASSESSMENT AND PROTECTIVE Page 14 of 26 (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.

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.

I

EPIPý.'3, I

Rev. 18, K-) DOSE ASSESSMENT AND PROTECTIVE"ACTION Page 15 of 26 V

4.0. - -RECORDS (1) All logs forms and other pertinent information shall be maintained in, accordance with EPDM 1007,'(excepti6n js for.material generated duning drills and exercises.)

5.0 REFERENCES

-__ "r (1) DAEC Emergency Plan ' - ,

(2) Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA-400-R-92-001) - .

(3) DAEC Radiological Engineering Calculation 93-022-H; dated December 17, 1993 (4) EPIP 3.2 "Field RadiologicalMonitoring" , ,c.-

(5) EPIP 1.2 "Notification" . a a (6) Response Technical Manual (RTM) 1996 Section G.

6.0 ATTACHMENTS (1) Attachment 1 -Evacuation Time Estimates (2) Attachment 2 -Wind Direction and Affected Subareas I.

- I ý DOSE ASSESSMENT AND PROTECTIVE ACTION IR Rev. 18 Page 16 of 26 ATTACHMENT I EV'ACUATION 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 defined as Labor Day to Memorial Day.

I

-EPIP.3.3:. '- *'V

.' Rev. 18 DOSE ASSESSMENT ANDPROTECTIVEACTION "Page17 of 26 ATrACHWMNT I (Cont),

EVACUATION TIME ESTIMATES FOR SUMMER WEEKEND MIDDAY AND SUMMR MIDWEEK EVENING SCENARIOS WIND DIRECTION AFFECTED GENERALPOPULATION,- SPECIAL POPULATION IN DEGREES FROM SUBAREAS 1ORMA' 1. RAIN-' . NORMAL RAIN

...... , , -,,".',WITHIN 2 M-. . ..

Any Direction I , - , 03.35 " ,,',03:35

,--.. ', "- 03:35 03:35

-WITHI 5 MILES 348.76 - 11.25 ( -. 1,4,5,6 ,- . - .- . 03:40 %03.40

. 03:40 03:40 11.26 - 33.75N (N*E) 1,5,6,7 j) 03:40 "' .03:40 "- 03:40 03:40 33.76 56.25 (NE) 1,5,6,7' 03A0 03:40 03:40 03.40 56.26 7875 (ENE) 1,5,6,7  : .

• 03140  :

.03:40 " 03:40 03.40 78.76 = 101.25 (E) 1,7,8 :03':45

-' '. , 03:45 . 03:45 03:45 10126 - 123.75 (ESE) 1,7,8 03:45 O3:45 6 - 03:45 03:45 123.76 - 146.25 (SE) 1,7,8 .,, 03:45 03-45 " 03:45 03.45 146.26 - 168.75 (SSE) 1,2,8 03.45 03:45 03:45 03.45 168.76 - 191.25 (S) 1,2,3,8 03:45 03:45 03:45 '03.45 191.26 - 213.75 (SSW) 1,2,3 ., 03:35 03:35 , 03:35 03:35 213.76 - 23625 (SW) 1,2,3 03:35 03"35 03:35 03:35 236.26 - 258.75 ,2,3,4.,r-........

,,'*' . '.,"  :'o 5 -,.. . .. 0335

': F

• 03:35 03:35 258.76 - 281.25 (W) . 1,3,4 , ,0335 , , - _ 03:35 03:35 281.26 - 303.75 (WNW) 1,3,4,5 03:40 03:40 -- 03:40 '03:40 303.76 - 326.25 (NMW) 1,3,,5 . ... c-k

' 03 :4 6 ,.¶"t . , 03:40 03:40 326.26 - 348.75 (NNW) - 1,4,5,6 03:40 A ,O ,, ,03:40. ,. 03:40 03:40 Any Direction 18.. 03:45 03:45'1

- 03:45 03:45

'-4--

MP L EMEPENTI-NG, PP*OCEDURES', EPIP 3.3 Rev. 18 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 18 of 26 ATTIACHMENT 1 (Cont.)

EVACUATION TIME ESTIMATES FOR SUMMER WEEKEND MIDDAY AND SUNUV4ER MIDWEEK EVENING SCENARIOS WIND DIRECTION AFFECTED GENERAL POPULATION SPECIAL POPULATION IN DEGREES FROM SUBAREAS NORMAL RAIN NORMAL RAIN WITHIN 10 MILES 348.76 - 11.25 (N) 1,4,5,6,15-18 0540 07:35 12:00 15.05 11.26 - 33.75 (NNE) 1,5,6,7,16-19 05:35 06:35 12:00 15.05 33.76 - 56.25 (NE) 1,5,6,7,17-20 03:35 06:25 03:35 06"25 56.26 - 78.75 (ENE) 1,5,6,7,18-21 03:45 04 00 03:45 0400 78.76 - 101.25 (E) 1,7,8,18-21 03:45 04:00 03:45 0400 101.26 - 123.75 (ESE) 1,7,8,19-22 03:45 04 00 03:45 04.00 123.76 - 146.25 (SE) 1,7,8,9,20-22 03:45 04 00 03:45 04.00 146.26 - 168.75 (SSE) 1,2,8,9,10,21,22 03:45 04:00 03:45 04:00 168 76 - 191 25 (S) 1,2,3,8-12,21,22 03.45 04:00 03:45 04:00 191.26 - 21375 (SSW) 1,2,3,9-13,22 03.45 04:00 03:45 0400 213.76 - 236.25 (SW) 1,2,3,10 -13 03:40 03:40 03:40 03:40 236.26 - 258.75 (WSW) 1,2,3,4,10-14 05:35 06:45 12.00 15.05 258.76 - 281.25 (W) 1,3,4,12-15 05:40 07:35 1200 1505 281.26 - 303.75 (WNW) 1,3,4,5,12-16 05:40 07:35 1200 15 05 303.76 - 326.25 (NW) 1,3,4,5,13-17 05:40 07:35 12 00 15 05 326.26 - 348.75 (NNW) 1,4,5,6,14-18 05:40 07:35 12.00 15.05 Any Direction 1-22 05:40 07:35 12.00 15.05 TO EPZ BOUNDARY 348.76 - 11.25 (N 1,4-6,15-18,23,24 09:10 11.25 12.00 15.05 11.26 - 33.75 (QINE) 1,5-7,16-19,24 05:30 06:15 12:00 1505 258.76 - 281 25 (W) 1,3,4,12-15,23 08:40 10:40 12.00 15 05 281.26 - 303 75 (WNW) 1,3-5,12-16,23,24 09.05 11:35 12.00 1505 303.76 - 32625 (NW) 1,3-5,13-17,23,24 09.05 11:35 12.00 15.05 326.26 - 348.75 (NNW) 1,4-6,14-18,23,24 09:10 11:35 12.00 15.05 Any Direction 1-24 09:10 11:35 12.00 15.05 I

116ID * *' .. :+",:

L..F II ,J..J I.

+*

Rev. 18 DOSE ASSESSMENT AND PROTECcivE'AO A ' o

- Page 19 of 26 ATfACHMENrT1 (Coh't.)'

EVACUATION TIME ESTIMATES FOR SUMMER MIDWEEK MIDDAY SCENARI'oU'S" WIND DIRECTION .. AFFECTED . .GENERAL POPULATION --- - SPECIAL POPULATION IN DEGREES FROM - , SUBAREAS NORMAL) RAIN . NORMAL j RAIN

, -WITHiIN2MILES ..

Any Direction ".1' ". 03:05 03:05 - 03:05 1 03:05

-~ - -TIM5N5MLES -'

348.76 - -. 11.25 (N) 1,4,5,6 - 03:10 ', 03:10 ' 03:10 -- 03:10 11.26 - 33.75 (NNE) 1,5,6,7 - 03:1.0 .03:10 °, 03:10 " 03:10 33.76 56.25 (NE)" 1,5,6,7 " 03:10 0310 03:10 03:10 56.26 - 78.75 (E.NE) 1,5,6,7 03:10 03:10 -03:10 - 03:10 78.76 101.25 (E 03:15 - 030 03:15- - ,03:30 101.26 - 123.75 (ESE) 1,7,8 ,03:15 . "03:30 03:15 _63:30 123.76 - 146.25 (SE) -1,7,8 . . 03:15 - --- - 03:30, -03:15 03:30 146.26 - -168.75 (SSE) -1,2,8 03:15 ... 03:30 03:15 -- 03:30 191.26 168.76 - -+2-16.'75 -. (S- E ,

(S) +12, 1,2,8 " ." 71

-"0 03:15 +-':

-- - + 0 03:30:31- -' " 0 :5 03:15 . .. 03:30 33

-- + 19-

"16876 191.25 9125 (S) 1,2,3,8 03:15", 0:0. -. 31 33 1-3.75

.26 (SSW) 1,2,3  : 03:05 03:05 ;03:05 03:05 213.76- 236.25 (SW) 1,2,3 -" - 03:05 03 :05 . - 03:05. '03:05 236.26. - . 258.75 (WSW) - 1,2,3,4 -' -"- .... 03:05' -:. 03.0b5- 03:05 03.05 25876 - 281.25 (W), 1,3,4 -- 03:05

'..--  :-0:5O .... 03:05 03.05 281.26- - 303.75 -(WNW) 1,3,4,5 F . D-'

03:] - . -- 0 0. 203:10 .... _03:10 303.76 _- 326.25 . (NW) 13, .. ' 03:10 " . 03:10 0__:-03:10 03:10 326.26 348.75- (NNW) 1,4,5,6 ,.

' 037,10 .? . 03:10,1:, ...... '03:10 03:10 Any Direction ' 1-8 . .. - 03.15* *,'  !- 03:30;,-  :' 03:15 03:30

- '- - - I- -C' I -

I_-

ATTACHMENT I (Cont)

EVACUATION TIME ESTIMATES FOR SUMMER MIDWEEK MIDDAY SCENARIOUS WIND DIRECTION AFFECTED GENERAL POPULATION SPECIAL POPULATION IN DEGREES FROM SUBAREAS NORMAL RAIN NORMAL RAIN WITHIN 10 MILES 348 76 - 11.25 (N) 1,4,5,6,15-18 06:05 07.40 12:00 15:05 11.26 - 33.75 (NNE) 1,5,6,7,16-19 05:45 06.50 12:00 15.05 33.76 - 56.25 (NE) 1,5,6,7,17-20 05:45 06:40 05:45 06:40 56.26 - 78.75 (ENE) 1,5,6,7,18-21 03:15 03:30 03:15 03:30 78.76 - 101.25 (E) 1,7,8,18-21 03-15 03:30 03:15 03:30 101.26 - 123.75 (ESE) 1,7,8,19-22 03.15 03:30 03:15 03:30 123.76 - 146.25 (SE) 1,7,8,9,20-22 03.15 03:30 03.15 03:30 14626 - 16875 (SSE) 1,2,8,9,10,21,22 03.15 03:30 03"15 03:30 168.76 - 191.25 (S) 1,2,3,8-12,21,22 03:15 03"30 03:15 03-30 19126 - 213.75 (SSW) 1,2,3,9-13,22 03:15 03:30 03:15 03:30 213.76 - 236.25 (SW) 1,2,3,10-13 03:10 03:10 03.15 03:30 23626 - 258.75 (WSW) 1,2,3,4,10-14 05:50 07.05 03:10 03:10 258.76 - 281.25 (W) 1,3,4,12-15 0605 07:40 1200 15:05 281.26 - 303.75 (WNW) 1,3,4,5,12-16 0605 07:40 12.00 15:05 303 76 - 32625 (NW) 1,3,4,5,13-17 0605 07:40 12.00 15:05 32626 - 348.75 (NNW) 1,4,5,6,14-18 06.05 07.40 12.00 15.05 Any Direction 1-22 06 05 07:40 12:00 15 05 TO EPZ BOUNDARY 348.76 - 11.25 (N) 1,4-6,15-18,23,24 09:40 12-05 12.00 15.05 11.26 - 33.75 (NNE) 1,5-7,16-19,24 05:40 06-40 12.00 15.05 258.76 - 281.25 (W) 1,3,4,12-15,23 09.05 11:05 12.00 15.05 281.26 - 303.75 (WNW) 1,3-5,12-16,23,24 09"40 12:05 1200 15.05 303.76 - 326.25 (NW) 1,3-5,13-17,23,24 09:40 12:05 12 00 15 05 32626 - 348.75 (NNW) 1,4-6,14-18,23,24 09.40 12-05 12.00 15.05 Any Direction 1-24 09.45 12:05 12:00 15:05 I

'7' 77MO 3-Y,--§4C'PIP PLME 1 7 1$,? "'EP.P 3"3"°'* ".3.

Rev. 18 DOSE ASSESSMENT AND PROTECTIVE'ACTION Page 21 of 26 ATTACHMENT 1 (Cont.) .

EVACUATION TIME ESTIMATES FOR WINTER MIDWEEK, MIDDAY SCENARIOS WIND DIRECTION AFFECTED GENERAL POPULATION SPECIAL POPULATION IN DEGREES FROM SUBAREAS NORMAL RAIN SNOW NORMAL RAIN I SNOW

- - WITHIN 2 MILES Any Direction 1 03:0 000 0 - 03:00, 05:05

- ITHIN5MILES 348.76 - 11.25 (N), 1,4,5,6 03:10 --- 03:10 05:10 03:40 -03:40 06:05 11.26 - 33.75 (NNE) 1,5,6,7 , 03:10 -- ' 03:10 05:10 03:40 03:40 06:05 33.76 - 56.25 (NE) 1,5,6,7 03:10 '03:10 -05:10 i 03:40 " 03:40 , 06:05 5626 - 78.75 (ENE), 1,5,6,7 " 03:10 - 03:10 "05:10 03:40 03:40 06:05 78.76 - 1 1.25 (E)_ 1,7,8 03:15 . '03:30 05:30 -o02:20 02:20 03:10 101.26 - 123.75 (ESE). 1,7,8 . 03:15 0330 05:30 '0220 02-10 03:10 123.76 - 14625 (SE) 1,7,8 - 03:15 b03:30 - 05: 02:20 02:20 03:10 146.26 - _ 168.75 (SSE) 1,2,8 - 03:15 . 03:30 -- 05:3 .03:40 03:40 05:05 168.76-- - - 191.25 (S) 1,2,3,8 -- -- 03:15 03:0 '05.30 -03:50 03:50 05:15 191 26 - -, 213.75 (SSW) - 1,2,3 03:05 03:05 - 05,10 .03:50 03.50 05:15 213.76 - - 236.25 (SW) 1,2,3

" - 03:05 .. 03.05 "05.J0 03:50 - 03:50 05:15 23626 "--.25-8.75 (,WSW)'- 1,2,3,4 . 03:05 .- 03:05 D,.5:10 "-03:50 - 03:50 05:15 258.76 - 28125 (W)' 1,3,4 - 03:05 03.05 05:10 03:50 03:50 05:15 281.26 - 303.75 (WNW) 1,3,4,5" *i. 03:10 03:10 05:10 03:50 03:50 05:15 303.76 - 326.25 (NW) ."- 1,3,4,5 93.!0 ," 010 0

• 05ýl0 c,'03:50 03:50 05:15 326.26 - 348.75 _(NNW) i,4,5,6 03:10 6 . "' .03:10 _..51ib 03:40 03:40 05:00 Any Direction '.1-8  : _. 03:15 03:30 " .- 5:30J.F0350 03:50 05:15

diý' rEMERGENGYPLNlM C E0 . ., EPiP 3.3 Rev. 18 I ACTION Pev 2 o DOSE ASSESSMENT AND PROTECTIVE Page 22 of 26 ATTACHMENT 1 (Cont.)

EVACUATION TIME ESTIMATES FOR WINTER MIDWEEK, MIDDAY SCENARIOS WIND DIRECTION AFFECTED GENERAL POPULATION SPECIAL POPULATION IN DEGREES FROM SUBAREAS NORMAL AIN SNOW INORMAL WITIIN 10 MILES 348.76 - 11.25 (N) 1,4,5,6,15-18 06:05 07:35 08:10 12.00 15:05 15:05 11.26 - 33.75 (NNE) 1,5,6,7,16-19 05:45 06"45 07:15 12.00 15.05 15:05 33.76 - 5625 (NE) 1,5,6,7,17-20 05:45 06.45 07:15 03 40 06.05 06:05 56.26 - 78.75 (ENE) 1,5,6,7,18-21 03:15 03:30 05:30 03 40 06:05 06:05 78.76 - 101.25 (E) 1,7,8,18-21 03:15 03:30 05:30 02.20 03:10 03:10 101 26 - 123.75 (ESE) 1,7,8,19-22 03:15 03:30 05:30 02:20 03:10 03 10 12376 - 14625 (SE) 1,7,8,9,20-22 03:15 03"30 05:30 02:20 03:10 03 10 14626 - 168.75 (SSE) 1,2,8,9,10,21,22 03:15 03.30 0530 03:40 05:05 0505 168.76 - 191 25 (S) 1,2,3,8-12,21,22 03:15 03:30 05.30 03:40 (15.05 05 05 191.26 - 213.75 (SSW) 1,2,3,9-13,22 03:15 03:30 05:30 03:40 05:05 05 0' 213.76 - 236.25 (SW) 1,2,3,10-13 03-10 03:15 05.10 03:40 05:05 05 b0 236.26 - 258.75 (WSW) 1,2,3,4,10-14 0540 06:50 07:20 12:00 1505 1505 258.76 - 281.25 (W) 1,3,4,12-15 06:05 07:35 08.10 12.00 15.05 15.05 281.26 - 303.75 (WNW) 1,3,4,5,12-16 06:05 07:35 08:10 12.00 15.05 15.05 303.76 - 326.25- (NW) 1,3,4,5,13-17 0605 07:35 08:10 12.00 15.05 15"05 326.26 - 348.75 (NNW) 1,4,5,6,14-18 06.05 07:35 08:10 1200 1505 15:05 Any Direction 1-22 06.05 07:35 08:10 1200 15.05 15.05 TO EPZ BOUNDARY 348.76 - 11.25 (N) 1,4-6,15-18,23,24 0905 12:05 12:10 12.00 1505 1505 11.26 - 33.75 (NNE) 1,5-7,16-19,24 05:40 06:30 07-10 12.00 15.05 15 05 258.76 - 281.25 (W) 1,3,4,12-15,23 0900 11.00 11[35 12:00 15.05 1505 281.26 - 303.75 (WNW) 1,3-5,12-16,23,24 09"10 11:40 12"35 12.00 15:05 1505 303.76 - 326.25 (NW) 1,3-5,13-17,23,24 09:10 11-40 12-35 12:00 15:05 1505 326.26 - 348.75 (NNW) 1,4-6,14-18,23,24 09 10 12.05 12 10 12:00 15.05 1505 Any Direction 1-24 09:10 1205 12"35 1200 15:05 1 1505 I

.', -i EPIP'3.3":,,:

KJK S+

DOSE ASSESSMENT AND PROTECTIVE ACTION .

Rev. 18 Page 23 of 26 ATTACHMENT 1 (Cont.)'7 +

EVACUATION TIME ESTIMATES FOR WINTER, WEEKEN D, MIDDAY AND WINTER, MIDWEEK, EVENING SCENARIOS WIND DIRECTION ' AFFECTED. - GENERAL POPULATION -SPECIAL POPULATION IN DEGREES FROM SUBAREAS NORMAL - RAIN ..- SNOW- NORMAL j RAIN SNOW

. - - . -..WITHIN2 MILES ...... . .

Any Direction '1 - 03:35 03:35 05:00 03.35 03:35 60:00

.- - + WrHN 5MILES- . "

,348.76 - 11.25 (N). 1,4,5,6 -03:40 03:40'-' 05:10 03-:4.0- 03:40 05:10 11.26 - 33.75 (NNE) 1,5,6,7 ' . - 03:40 03:40 05:10 ,03:40 03:40 05:10 33.76 - 56.25 (NE) ,J,5,6,7 03:40 03:40, 05:10 03.40 03:40 05:10 56.26 - 78.75 (ENE) 1,5,6,7 03:40 - 03:40 05:10 - '03:40 03:40 05:10 78.76 '- 101.25 (E) 1,7,8 03:40 03:55 05:10 03:40 03:55 05:10 101.26 - -' 123.75 '(ESE) 1,7,8 '-- - 03:40 03:55 . 05:10 - 03:40 - 03:55 05:10 "123.76 - 146.25. (SE) 1,7,8 03:40 - - 03:55 05:10 03:40 - 03:55 . 05:10 146.26 .,168.75 1 "(SSE) 1,2,8 ' 03:40 "..03:55 ."05.:10 -.03.:40- 03:55 -05:10 168.76 .191.25' (S) 1,2,3,8 .. 03:40 ,--:03:55 05:10 . ,03:40 -. 03:55 05:10 191.26 213.' (SSW) 1,2,3 03:35 ' 03:35 - 05:05 03:35 03:35 605:05 213.76 -- ' 236.25 ' (§W) 1,2,3 -" - 03:35 - 03:35 -- 05:05 --03:35 03.35 05:05 236.26-. - 258.75 (WSW) _1,2,3,4 -03:35-" 03:35 - 05.05--- -. 03:35 03".35 05:05 258.76 281.25 (W) --1,3,4 ... . . 03:35 -- 03:35 . 05"05 __03:35 03:35 -- '05.05 281.26 - - 303.75"-- (*,NW) 1,3,4,5 - - -03:40QT- _'-03:40'1-* -05::05 .03A0_ 03:40 05:05

.303.76 326.25- (---03-:4.0- 03:40* 0505 03:40 03:40 05:05 326.26 - 348.75' " (NNW) J1,4,5,6 03:40 - 03:40, 05:05 03:40 03:40 " 05:05 Any Direction A1-8' T 03:40 03:55' 05:i0 ' -.03:40 03:55 05:10 r

- , - I

EMERGENCYPLA*IMPLMENTING PROCEDURES EPIP 3.3 Rev. 18 DOSE ASSESSMENT AND PROTECTIVE ACTION Page 24 of 26 ATTACHMENT 1 (Cont)

EVACUATION TIME ESTIMATES FOR WINTER, WEEKEND, MIDDAY AND WINTER, MIDWEEKL EVENING SCENARIOS WIND DIRECTION AFFECTED 'GENERAL POPULATION SPECIAL POPULATION IN DEGREES FROM SUBAREAS NORMAL RAIN SNOW NORMAL RA SNOW WITHIN 10 MILES 348.76 - 11.25 (N) 1,4,5,6,15-18 05:40 0720 08:10 1200 1505 15.05 11.26 - 33.75 (NNE) 1,5,6,7,16-19 05:10 05:55 07.00 05.10 05.55 07.00 33.76 - 56.25 (NE) 1,5,6,7,17-20 05:30 06-25 07.00 05-30 0625 07 00 56.26 - 78.75 (ENE) 1,5,6,7,18-21 0400 04:05 05:10 0400 04 05 05:10 78.76 - 101.25 (E) 1,7,8,18-21 04-00 04.05 05:10 04 00 04.05 05:10 101.26 - 123.75 (ESE) 1,7,8,19-22 04.00 04:05 05:10 0400 04.05 05:10 123.76 - 146.25 (SE) 1,7,8,9,20-22 04 00 04:05 05:10 04 00 04.05 05:10 146.26 - 168.75 (SSE) 1,2,8,9,10,21,22 04 00 04.05 05:10 04 00 04:05 05:10 168.76 - 191.25 (S) 1,2,3,8-12,21,22 04:00 04:05 05:10 04.00 04:05 05:10 191.26 - 213.75 (SSW) 1,2,3,9-13,22 03:40 03:40 05:10 03.40 03:40 05:10 213.76 - 236.25 (SW) 1,2,3,10-13 03:40 03:40 05:10 03:40 03:40 05:10 23626 - 258.75 (WSW) 1,2,3,4,10-14 05:20 06:35 06:55 12.00 15:05 15:05 258.76 - 281.25 (W) 1,3,4,12-15 05:40 07:20 08.15 12.00 15.05 15:05 281.26 - 303.75 (WNW) 1,3,4,5,12-16 05:40 07:20 08:15 12-00 15:05 15 05 303.76 - 32625 (NW) 1,3,4,5,13-17 05:40 07:20 08:15 12.00 15.05 15:05 326.26 - 348.75 (NNW) 1,4,5,6,14-18 05:40 07:20 08.15 12:00 15.05 15:05 Any Direction 1-22 05:40 07:20 08:15 12:00 15.05 [15.05 TO EPZ BOUNDARY 348.76 - 11.25 (N) 1,4-6,15- 08:30 10:45 11:10 12:00 1505 15:05 18,23,24 11.26 - 33.75 (NNE) 1,5-7,16-19,24 05:30 06:25 06:55 12.00 1505 15.05 258.76 - 281.25 (W) 1,3,4,12-15,23 08:35 10:35 11:05 12.00 15405 15:05 281.26 - 303.75 (WNW) 1,3-5,12- 08:35 10.45 11:10 12.00 15:05 15.05 16,23,24 303.76 - 32625 (NW) 1,3-5,13- 08:35 1045 11:10 12.00 15:05 1505 17,23,24 32626 - 348.75 (NNW) 1,4-6,14- 08.35 10:45 11:10 12:00 15.05 15.05 18,23,24 Any Direction 1-24 08.45 10:50 11 25 12.00 1505 15.05

EPIP 3.3 Rev. 18 DOSE ASSESSMENT AND PR TEC -T"IVAEA(C TiION K-) Page 25 of 26 ATTACHMENT I '(Cont)

"EVACUATION TIME ESTIMATES

.-The evacuation time estimates for the All-Iowa-'Fair and the Cedar Rapids Freedom Festival consider an evacuation of the general population within the entire DAEC Emergency Planning Zone (Subareas 1-24) while each of these events is in progress., ..... "

All-Iowa Fair: 9:10 Cedar Rapids Freedom Festival: 10:15 4.-;

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Rev. 18 DOSE ASSESSMENT AND PROTECTIVE ACTION I Page 26 of 26 ATTACHMENT 2 WIND DIRECTION and AFFECTED SUBAREAS

<<<<<<<<<<<<<<<<<< MILES OUT >>>>>>>>>>>>>>>>>>>

Wind Direction 0-2 2-5 5-10 10 - EPZ N (348.75 - 11.25) 1 4,5,6 15,16,17,18 23,24 NNE (11.25-33.75) 1 5,6,7 16, 17,18,19 24 NE (33.75 - 56.25) 1 5,6,7 17, 18, 19, 20 ENE (56.25 - 78.75) 1 5,6,7 18,19,20,21 E (78.75 - 101.25) 1 7, 8 18, 19, 20, 21 ESE (101.25 - 123.75) 1 7, 8 19, 20, 21, 22 SE (123.75- 146.25) 1 7, 8 9,20,21,22 SSE (146.25 - 168.75) 1 2, 8 9, 10, 21, 22 S (168.75 - 191.25) 1 2,3,-8 9,10,11, 12, 21, 22 SSW (191.25- 213.75) 1 2,3 9,10,11, 12,13, 22 SW (213.75- 236.25) 1 2,3 -10, 11, 12,13 WSW (236.25 - 258.75) 1 2,3,4 10,11, 12,13,14 W (258.75 - 281.25) 1 3,4 12,13,14,15 23 WNW (281.25- 1 3,4,5 12,13,14,15,16 23,24 303.75)___ ___

NW (303.75 - 236.25) 1 3, 4, 5 13, 14, 15, 16, 17 - 23, 24 NNW (326.25-348.75) 1 4, 5, 6 14, 15, 16, 17, 18 23, 24 I

EAT BLE ABNORMAL RAD LEVEL. DIQACTIVE EFFLUENT K> K)j EVENT UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY TYPE AU1 AA1 AS1 AG1 Any Unplanned Release of Gaseous or Any Unplanned Release of Gaseous or Site Boundary Dose Resulting from an Site Boundary Dose Resulting from an Liquid Radioactivity to the Environment Liquid Radioactivity to the Environment Actual or Imminent Release of Gaseous ,Actual or Imminent Release of Gaseous That Exceeds Two Times the Offslte that Exceeds 200X the Offsite Dose Radioactivity Exceeds 100 mrem TEDE , Radioactivity Exceeds 1000 mrem TEDE Assessment Manual (ODAM) Limit and or 500 mrem CDE Thyroid for the Actual or" 5000 mrem CDE Thyroid for the Dose Assessment Manual (ODAM) Limit and Is Expected to Continue For 60 is Expected to Continue for 15 Minutes or Projected Duration of the Release Actual or Projected Duration of the Minutes or Longer or Longer Release

. . Valid Reactor Building or Turbine Building Valid Reactor Building or Turbine Building, Valid Reactor Building or Turbine Building Valid'Reactor Building or Turbine Building ventilation (Kaman) rad monitor reading ventilation (Kaman) rad monitor reading ventilation (Kaman) rad monitor'reading above 6 E-2 piCl/cc for more than 15 above 6 E-1 pCi/cc for more than 15 ,

ventilation (Kaman) rad monitor reading ,

above I E-3 pCVcc for more than 60 above 3 E-2 p.CI/cc for more than 15 minutes. (Dose assessment not available) minutes. (Dose assessment not available)

OR

• OR minutes.~

"m"ieminutes.

OOR Valid Offgas Stack (Kaman) red monltof Valid Offgas Stack (Kaman) rad monitor .

Valid Offgas Stack (Kaman) radmonitor- Valid Offgas Stack (Kaman) tad monitor reading above 4 E+1 pCI/cc for more than reading above 4 E+2 ipCI/cc for more than reading above I E-1 .CI/cc for more thao-; reading above 6 E+O pCI/cc for more than 15 minutes. (Dose assessment not 15 minutes. (Dose assessment not 60 minutes. I1 - 15 minutes. available) available)

"".OR ,. OR Valid LLRPSF (Kaman) rad monitor, Valid LLRPSF (Kaman) rad monitor reading above 5 E-4 pCi/cc for nm6re than reacfing above 1 E-1 pCi/cc for more than 60 minutes. " "-.; 15 mrlnutes.

OFFSITE RAD OR OR CONDITIONS Valid GSW rad monitor reading above 3E+3 Valid GSW rad monitor reading above 3E+5 CPS for more than 60 minutes. CPS for more than 15 minutes.

OR -, e':'." s "-. ,, OR,i . ,, %..,,

Valid RHRSW &ESW rad monitor reading Valid RHRSW & ESW rad monitor reading above 8E+2 CPS for more than 60 minutes. above 8E+4 CPS for more than 15 minutes.

OR ... .-. . OR, Valid RHRSW & ESW Discharge Canal rad Valid RHRSW & ESW Discharge Canal rad monitor reading above 1IE+3 CPS for more monitor reading above 1E+5 CPS for more than 60 minutes. than ,15 minutes.

OR I*. OR Confirmed sample analyses for gaseous or Confirmed sample 6nalyses for gaseous or liquid releases indicates concentrations or liquid releases Indicates concentrations or release rates In excess of 2 times ODAM release rates with a release duration limits for greater than 60 minutes, expected to last forI15 minutes or longer In OR excess of 200 times ODAM limit OR OR Valid perimeter adiation monitor reading of. Valid field survey reading outside the site Valid field survey reading outside the site greater than 0.10 mRehr above normald' OR boundary >100 mR/hr or >500 mRPhr CDE boundary >1,000 mR/hr or >5,OOOmR/hr background for 60 minutes. Valid site'boundary radiation reading of Thyroid. CDE Thyroid.

greater than 10 mR/hr above normal background and expected to last for 15 OR OR OR Valid dose assessment Indicating dose minutes or longer. Dose assessment determines integrated Dose assessment determines Integrated rates beyond the site boundary above 0.1 accident dose projection outside the site accident dose projection outside the site mR/hr TEDE for a period greater than 60 OR boundary above 100 mrem TEDE or above boundary above 1,000 mrem TEDE or "minutes. Valid Indication on MIDAS of a release 500 mrem CDE Thyroid. above 5,000 mrem CDE Thyroid.

greater than 200 times ODAM limit and expected to last for 15 minutes or longer.

Op. Modes: ALL Op. Modes: ALL Op. Modes: ALL Op. Modes: ALL AU2 AA2 Unexpected Increase In Plant Radiation Major Damage to Irradiated Fuel or Loss of Water Level that Has or Will Result In the Uncovering of Irradiated Fuel Outside the Reactor Vessel

- Uncontrolled loss of reactor cavity or fuel - Report of ANY of the following: - - - ... ..

pool water level with all spent fuel 0 Valid ARM HI RAD alarm for the assemblies remaining water covered as Refueling Floor North End, Refueling Indicated by ANY of the following: -Floor South End, New Fuel Storage

• Report to control room .Area, or Spent Fuel Storage Area 0 Valid fuel pool level Indication (LI-. Valid Refueling Floor North End, ONSITE 3413) below 36 feet and lowering Refueling Floor South End, or New RAD 0 Valid WR GEMAC Floodup Indication Fuel Storage Area ARM Reading CONDITIONS (LI-4541) coming on scale. above 10 mR/hr

• Valid Spent Fuel Storage Area ARM OR Reading above 100 mR/hr Unexpected ARM reading offscale high or OR above 1000 times normal reading. Report of visual observation of Irradiated Fuel uncovered Op. Modes: ALL OR Water level reading below 450" as Indicated on L14541 (floodup) for the Reactor Refueling Cavity that will result In Irradiated Fueluncovedng, 0 Vald ue Pol OR

,Valid Fuel Pool water level indication (LI-3413) below 16 feet.

.. .Moe:ALL AA3 Release of Radioactive Material or

,Increases in Radiation Levels Within the Facility That Impedes Operation of Systems Required to Maintain Safe Operations or to Establish or to Maintain

-- Cold Shutdown Valid area radiation Monitor (RE9162)

S"----- -- --- reading greater than 15 mR/hr in the Control= --- * ------ '- ----- - I2' Room., I I ,

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, Valid area radiation.monitor (RE9168)

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Remote Shutdown Panel, 1C388. C SOp.Modes: ALL '-.

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EAL TABLE ii FISSION 13ARRIER ONE BARRIER AFFECTED FUEL CLAD BARRIER RCS BARRIER PRIMARY CONTAINMENT BARRIER INDICATORS Loss Loss Loss- None "L'Fueldamage assessment (PASAP 7.2) determines at Valid drywell rad monitor reading above 5 R/hr after least 5% fuel dad damage OR reactor shutdownPoenil os Nn IEI Valid drywell rad monitor Potential OR Loss reading above 3E+3 R/hr PotentialLoss - None Fuel damage is indicated by any of the following:

Valid drywell rad monitor reading above 7E+2 R/hr Valid torus rad monitororeading above 1E+2 Rihr RADIATION RADATIN I [RjOR Core damage assessment determines at least 20%

OR r aabove 3E+1 E Rfhr fuel dad damage CORE DAMAGE Valid tows rd monitor reading OR

- Coolant activity above 300pCi/gm DOSE EQUIVALENT 1-131 PotentialLoss - None Loss - None TWO BARRIERS AFFECTED Loss Loss

'RPV Level below -25Inches E lRPV Level below 15 inches eel P]V- inches Potential Loss - No ne RPV LEVEL Po tential Lo ss RPV Level below -39 inches RE RPV Level below 15 inches Loss- None Loss

'R Failure of both isolation valves and a downstream Potential Loss pathway to the environment exists RCS Leakage is above 50GPM OR OR [- Unisolable primary system leakage outside the drywell as indicated by area temps or ARMs exceeding the LEAKAGE None ' Unisolable primary system leakage outside the drywell Max Safe Limits per EOP 3, Table 6. after as Indicated by area temps or ARMs exceeding the Containment Isolation.

Max Normal Limits per EOP 3. Table 6. OR

[L- Primary containment venting performed per EOPs Potential Loss - None rI Loss Loss L- Drywell pressure above 2 psig and not caused by a El Rapid unexplained decrease following initial increase in pressure loss of DW Cooling Potential Loss - None []Drywell pressure response not consistent with LOCA PRIMAR T CONTAINMENT None conditions ATMOSPHERE Potential Loss

[-ITorus pressure reachesO53 psig OR

[lJDrywell or torus 1-12CANNOT be determined to be below 6% AND Drywell or torus 02 CANNOT be determined to be below 5%

Any condition which in the EC/OSM's judgment indicates Any condition which in the EC/OSM's judgment indicates Any condition which in the EC/OSM's judgment indicates ECIOSM loss or potential loss of the fuel clad barrier due to loss or potential loss of the RCS barrier due to Imminent barrier degradation OR Degraded fission barrier monitoring loss or potential loss of the primary containment barrier due to Imminent barrier degradation OR Degraded fission F Op. Modes: Run, Startup, Hot S/D JUDGMENT Imminent barrier degradation Degraded fission barrier capab~iity, barrier monitoring capabfilty.

monitoring capability,

[] Loss OR r* Potential Loss E] Loss OR - Potential Loss [] Loss OR E] Potential Loss IMMINENT - No turnaround in safety system performance Is expected and escalation to General Emergency conditions is expected within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

stop 2, transcribe all L's and "P's marked on Barrier Table to the Logic Diagram (at right). 'L's and "P's should be marked for each affected barrier(working NOTE: Step 1; for all indicators, move from left to fight across table, marking all applicable "L's"and P's for each barier,based on plant indications. Then, then the EAL can be declared.

top to bottom) on the flowchart.Step 3, an U.or P" marked for each associated barrierwill constitute a Logic I input. When coincidence is met, performing its safety function.

Loss (of a fission product barrier) - A severe challenge to a fission product barrier exists such that the barrieris considered incapable of R =PotentialLoss (of a fission product barrier) -A challenge to a fission product barrier exists such that the barrier is considered degraded in its ability to perform its safety function.

EAL-02 Rev 2

K)j EAL TABLE HAZARDS and OTHER CONDITIONS AFFECTING PLANT SAFETY EVENT UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY TYPE 1 HUI HA1I Natural and Destructive Phenomena Natural and Destructive Phenomena Affecting the Protected Area Affecting the Plant Vital Area Earthquake detected per AOP 901, Earthquake peak horizontal acceleration above +/- 0.06 Gravity.

Earthquake.

OR 'OR Safe Shutdown Areas Report of tornado touching down within plant Report of tornado striking plant vital area, protected area or within switchyard. Category Area OR OR Electrical Power Switchyard, 1_G31 DG and Day Tank Rooms, I1G21G Assessment by the control room that an event Report to control room of damage affecting and Day Tank Rooms, has occurred. safe shutdown areas. OR Battery Spreading RoomEssential Switchgear Rooms, Rooms, Cable OR Heat Sink! Torus Room, Intake Structure, Pumphouse Vehicle crash Into plant structures or systems Vehicle crash affecting plant vital areas. Ceat S upIcy within protected area boundary. Coolant Supply OR OR NATURAL Report of an unanticipated explosion within Sustained wind speed above 95 MPH. Containment Drywell Torus DISASTERS the protected area boundary resulting In Emergency NE, NW, SE Corner Rooms, HPCI Room, RCIC Room, visible damage to structures or equipment. Systems RHR Valve Room, North CRD Area, South CRD Area OR OR Other Control Building, Remote Shutdown Panel 1C388 Area, Turbine failure resulting In casing penetration Missiles affecting safe shutdown areas. Panel 1C56 Area, SBGT Room or damage to turbine or generator seals.

OR OR River level above 757 feet. River level above 767 feet. Water Level Operating Limits OR OR Max Normal Max Safe Any area water level above Max Normal Water level above Max Safe Operating Limit Room Area Indicator Operating Operating Operating Limit In2 or more areas AND Reactor shutdown is Limit (inches) Limit (inches)

Room Area LI 3768 2 6 ORrequired.RHPCI RCIC Room Area LI 3769 3 6 River level below 725 feet 6 inches. River level below 724 feet 6 Inches, 2 10 A RHR Comer Room SE Area L13770 Op. Modes: ALL B RHR Comer Room NW Area L13771 2 10 Op. Modes: ALL Torus Area LI 3772 2 12 HU2 HA2 Fire Within PROTECTED AREA Not Fire Affecting the Operability of Plant Extinguished Within 15 Minutes of Safety Systems Required to Establish or Detection Maintain Safe Shutdown Systems & Equipment of Concern Fire Inbuildings or areas contiguous to any of Fire or explosion In any of the following areas:

• Reactivity Control the following areas not extinguished within 15 v Reactor, Turbine, Control. AdminlSecurlty , Containment (Drywell/Torus) minutes of control room notification or 9 Intake structure 0 RHRICore Spray/SRV's FIRE verification of a control room alarm: a Pump house 0 HPCI/RCIC

• Reactor, Turbine, Control, Admin/Security AND 0 RHRSW/RIver Water/ESW

- Intake structure Affected system parameter Indications show

• Onsite AC Power/EDG's a Pump house degraded performance or plant personnel 0 Offsite AC Power report visible damage to permanent structures 0 Instrument AC or equipment within the specified area. 0 DC Power Op. Modes: ALL

• Remote Shutdown Capability Op. Modes: ALL HU3 HA3 Release of Toxic or Flammable Gases Release of Toxic or Flammable Gases Deemed Detrimental to Safe Operation of Within a Facility Structure Which the Plant Jeopardizes Operation of Systems7 Required to Maintain Safe Operations or to Establish or Maintain Cold Shutdown OTHER Toxic or flammable gas release affecting Toxic or flammable gas making safe HAZARDS normal operation, shutdown areas uninhabitable or Inaccessible.

AND OR FAILURES Report by local, county or State official for potential evacuation of site personnel based on offslte event.

Op. Modes: ALL Op. Modes: ALL HU4 HA4 HSI HGI Confirmed Security Event Which Indicates Security Event in a Plant Protected Area Security Event In a Plant Vital Area Security Event Resulting in Loss of a Potential Degradation inthe Level of Ability to Reach and Maintain Cold Safety of the Plant Shutdown Suspected sabotage device discovered within Intrusion Into plant protected area by a hostile Intrusion Into plant vital area by a hostile Loss of physical control of the Control SECURITY plant protected area and outside plant vital force. force, Room.

area. OR OR OR OR Suspected sabotage device discovered In Sabotage device discovered In the plant Sabotage device discovered In the plant vital Loss of physical control of remote plant switchyard. protected area. area. shutdown capability.

OR OR "LO" Credible Security Threat "HI" Credible Security Threat Op. Modes: ALL Op. Modes: ALL Op. Modes: ALL Op. Modes: ALL HA5 HS2 Control Room Evacuation Has Been Control Room Evacuation Has Been None Initiated Plant Control Cannot Be Initiated and Established None CONTROL CONTROL ROOM Control room evacuation Initiated per Control room has been evacuated AND EVACUATION -AOP 915.Shutdown Outside-ControFR67or-- -control of plant-frbm-Re-m--toShutdown Panel 1C388 NOT established within 20 minutes.

Op. Modes: ALL Op. Modes: ALL HU5 HA6 HS3 HG2 Other Conditions Existing Which In the Other Conditions Existing Which In the Other Conditions Existing Which In the Other Conditions Existing Which In the Judgment of the EC/OSM Warrant Judgment of the ECIOSM Warrant Judgment of the EC/OSM Warrant Judgment of the EC/OSM Warrant Declaration of an Unusual Event Declaration of an Alert Declaration of a Site Area Emergency Declaration of a General Emergency Other conditions exist which Inthe judgment Other conditions exist which in the judgment Other conditions exist which inthe judgment Other conditions exist which In the of the EC/OSM Indicate potential degradation of the EC/OSM Indicate that plant systems of the EC/OSM indicate actual or likely major judgment of the EC/OSM Indicate EITHER:

ECIOSM of the level of safety of the plant. may be degraded and that Increased failures of plant functions needed for 0 Actual or Imminent substantial core JUDGMEmonitoring of plant functions Iswarranted. protection of the public, degradation with potential for loss of containment.

JUDGMENT

• Potential for uncontrolled radionuclide releases which can reasonably be expected to exceed EPA PAG plume exposure levels outside the site boundary.

Op. Modes: ALL Op. Modes: ALL Op. Modes: ALL Op. Modes: ALL EAL-03 Rev. 2

EAL . ,LE SYSTEM MALFUNCTION UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY EVENTTYPE SUl SAl SS1 SGI Loss of All OffsIte Power and Loss of All Loss of All OffsIts Power and Loss of All Prolonged Loss of All Offslts Power and Prolonged Loss of All OffsIte Power to Essential Loss of All Onslte AC Power Busses for Greater Than 15 Minutes Onslte AC Power to Essential Busses Onslte AC Power to Essential Busses During Cold Conditions vhan 15 minutes Loss of Voltage on Buses 1A3 and 1A4 lasting Loss of Voltage on Buses 1A3 and 1A4 and ANY of the Loss of Offsite Power Lasting More Than 15 following Minutes more than 15 minutes 0 Restoration of power to either Bus 1A3 or 1A4 is Op. Modes: Cold S/D, Refuel, Defueled NOT likely within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> o..Modes: ALL 0 .. Modes: Run.Statup, Hot SID e RPV level indeterminate LOSS OF POWER SU7 SA5 SS3 Loss of All Vital DC Power RPV Level below +15 Inches Unplanned Loss of Required DC Power AC Power Capability to Essential Busses During Cold Shutdown or Refuel Mode Reduced to a Single Power Source for For Greater Than 15 Minutes Greater Than 15 Minutes Such That Any Additional Single Failure Would Result In Station Blackout Unplanned Loss of Div 1 and Div 2 Only one AC power source remains available Unplanned Loss of Div 1 and Div 2 125 VDC busses based on bus voltage less to supply Bus 1A3 or Bus 1A4 AND Ifit Is 125 VDC busses Lasting More Than 15 than 105 VDC Indicated, lost, a Station Blackout will occur. Minutes AND Failure to restore power to at least one required 125 VDC bus within 15 minutes from time of loss Op. Modes: Run, Startup, Hot S/D Op. Modes: Run, Startup, Hot S/D Op. Modes: Run, Startup, Hot S/D Op. Modes: Cold SID, Refuel SA2 SS2 SG2 Failure of Reactor Protection System Failure of Reactor Protection System Failure of the Reactor Protection System to Instrumentation to Complete or Initiate an Instrumentation to Complete or Initiate on Complete an Automatic Scram and Manual Scram Automatic Reactor Scram Once a Reactor Automatic Reactor Scram Once a Reactor was NOT successful and There Is Indication of an Protection System Setpolnt Has Been Protection System Setpolnt Has Been Extreme Challenge to the Ability to Cool the Core Exceeded and Manual Scram Was Exceeded and Manual Scram Was NOT Successful Successful RPS FAILURE Entry Into ATWS EOP- RPV Control is required Auto Scram Failure In ATWS EOP AND AND AND Operator actions to reduce power are Reactor power above the APRM Downscale RPV level cannot be maintained above -25 Inches None SUCCESSFUL as Indicated by either Alarm on ANY valid APRM Instrument, OR OR HCL Curve (EOP Graph 4) exceeded.

ALL Rods Full-In, Boron Injection Initiation Temperature (BIIT)

OR Curve (EOP Graph 6) exceeded Reactor Shutdown Under All Conditions Without Boron, OR Reactor power below the APRM Downscale Alarm on ALL valid APRM Instruments Op. Modes: Run, Startup Op. Modes: Run, Startup Op. Modes: Run, Startup SU2 SA3 SS4 Inability to Reach Required Shutdown Inability to Maintain Plant In Cold Complete Loss of Function Needed to Within Technical Specification Limits Shutdown Achieve or Maintain Hot Shutdown Plant NOT brought to required mode wIthn 1. Loss of decay heat removal systems EOP Graph 4 Heat Capacity Limit Is exceeded applicable LCO Action Statement Time Limits required to maintain cold shutdown. OR AND Reactor CANNOT be brought subcdtical See Fission Barner Table CLOSURE nst 2 With CONTAINMENT established, temperature conditions exist Op. Modes: Run, Startup, Hot SID

--- INABILITY TO - that either" ------

MAINTAIN3SS5 MAUTDOWN (a) Cause reactor coolant temperature Loss of Water Level In the Reactor Vessel SHUTDOWN to exceed the Technical That Has or Will Uncover Fuel In the CONDITIONS Specification limit of 212,F. Reactor Vessel OR (b) Result In uncontrolled temperature NO cooling method lined up or available AND rise approaching 212,F. RPV Level below 15 Inches.

Op. Modes: Run, Startup, Hot S/D Op. Modes: Cold SID, Refuel Op. Modes: Cold SID, Refuel SU3 SA4 SS6 Unplanned Loss of All Safety System Unplanned Loss of Most or All Safety Inability to Monitor a Significant Transient Annunlcatlon or Indication In the Control System Annunlcatlon or Indication In In Progress Room for Greater Than 15 Minutes Control Room With Either (1) a Significant Transient In Progress, or (2)

Compensatory Non-AlarmIng Indicators are Unavailable See Fission Bamer Table Unplanned loss of most annunciators on Unplanned loss of most annunciators on Significant transient In progress and BOTH of panels 1C03, 1C04 and IC05 lasting more panels 1C03, 1C04 and 1C05 lasting more the following' than 15 minutes AND compensatory non- than 15 minutes and EITHER alarming indications are available 0 Loss of annunciators on panels 1C03, a Significant transient in progress. 1C04 and 1C05 AND INSTRUMENTATION I Op. Modes: Run, Startup, Hot S/D 0 Loss of compensatory non-alarming Loss of compensatory non-alarming COMMUNICATION ISU6Indications Indications.

Unplanned Loss of All Onslte or Offslte Communications Capabilities Loss of ALL onsIte telephone and radio communication methods (PABX, direct-ring, UHF, and radiological survey radio systems)

OR Loss of ALL electronic communication methods with government agencies (PABX, direct-dring, ENS, microwave and police adio) Op. Modes: Run, Startup, Hot S/D Op. Modes: ALL Op. Modes: Run, Startup, Hot S/D SU4 Fuel Clad Degradation Valid Pretreat RM-4104 red monitor reading SeFsinBre al above 4E+3 mR/hr OR See Fission Barrier Table See Fission Bamer Table COOLANT ACTIVITY Coolant activity above 1.2 pCVml DOSE EQUIVALENT 1-131 Op._Modes:_Run,_Startup, Hot S/D SU5 RCS Leakage Unidentified or pressure boundary leakage COOLANT LEAKAGE greater than 10 GPM, See Fission Barrier Table See Fission Barrier Table OR See Fission Bamer Table Identified leakage greater than 25 GPM OR Main steam line break as determined from annunciators or plant personnel report.

IOp. Modes: Run, Startup, Hot SID _I EAL-04 Rev. 2

EOF INFORMATION SERVICES REPRESENTATIVE CHECKLIST The following checklist shall be used by the EOF Information Services Representative as a guide to ensure that necessary actions are completed. The blanks at the left can be used to put either a check when the action is completed or any notes which may assist the user.

Upon arrival at the EOF, the Information Services Representative will:

_ 1. Place/sign in name tag on the sign in board under your position and establish a log.

2. Assist the EOF Ops Liaison and/or the Rad and EOF Manager with the start up of the IDT emulation.

3. Verify the two SPDS broadcasting monitors are turned on and functioning to display the proper SPDS information.

4. Verify the computer system used to display ERDS data being sent to the NRC is turned on and projecting to the proper large screen display.

5. Verify the ERDS data being sent to the NRC is accurate and ensure the NRC Communicators in the EOF have notified the NRC of any change in the accuracy of the data. (you may have to consult with your counterpart in the TSC)

6. Verify time displayed on EOF clocks is synchronized with SPDS displayed time.

Adjust the EOF clocks as necessary. (Control box is located near the Information Services EOF position.)

7. Establish phone contact with Information Service Representatives in the TSC and inform them of the operational status of the EOF Computer Equipment.

8. Upon determination that computer data is good/bad turn on/off displayed data as necessary and make the announcement of such to the EOF Responders.

9. Assist the TSC-EOF Communicator with the startup of the Electronic Status Board (ESB); ensure the PC clock is synchronized with the EOF/JPIC clock.

10. Assist the MIDAS Operator to verify operability of all MIDAS system required parameter inputs.

EOF-05 K> Rev3

RAD AND EOF MANAGER CHECKLIST Page 1 of 2

1. Establish a Rad &'EOF Manager log. _

2. Brief the RAC on plant conditions, actual or potential releases, met conditions and field monitoring team status.

3. Log-on to ERDS and SPDS. _

4. Verify MIDAS is operational in the EOF. "'

5. Ensure communication channels are established RAC with SRPC ___

FTD with RMTs -___

EOF Communicator with TSC Communicator NRC-HPN Communicator- _

6. Establish communication with the State and County EOC's _

using the Admin Hotline (786-8172) or call the State.

(Put Iowa EMD phone iddrawer to keep'line open.)

7. Denote the time MIDAS is being broadcasted to the TSC. _

8. Denote time the FTD has assumed'control of field monitoring teams.

9. Notify county and state agencies that the _

EOF is operational and that the Rad & EOF Manager has assumed responsibilities for follow-up notifications. Report general status. Use admin hotline (786-8172).

Also do one-on-one briefing with the State via the phone marked "red phone" by dialing (6666), line 2.

• • Notify INPO via the INPO duty office that EOF is operational.

(Press automatic dial button.) -

10. Verify the Technical Liaisons have arrived at the State and County EOC's by checking with the Technical Recorder.,

MAKE PROTECTIVE ACTION RECOMMENDATIONS/NOTIFICATIONS

1. Monitor the development of EALs and review does projections ;

for required EAL changes.

K>2. Review dose projections to determine PARs per EPIP 3.3 _

EOF-08 Rev 6

RAD AND EOF MANAGER CHECKLIST Page 2 of 2

3. Record PAR on NOTE-05 "Emergency Action Level _____

Notification" form.

4. Discuss potential recommendations with State.

Use the red phone, line 2, 6666, per EPIP 3.3.

5. Get Approval/Authorization to transmit from ER&RD per EPIP 1.2.

6. Notify State and local agencies .'ithin 15 minutes of EAL declaration per EPIP 1.2. Use Admin Hotline 786-8172.

7. Verify that the TSC Communicator directed the messenger to conduct the group page.

8. Have the messenger FAX recommendations to counties _

and State per EPIP 1.2, and return original EAL Notification Form.

9. Ensure the NRC is notified within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> via the NRC-HPN Communicator over the HPN and ENS line.

10. Notify INPO via the INPO duty office. (Press automatic dial button.)

11. If Subarea 23 is evacuated, notify JPIC to move to Alternate JPIC.

12. Ensure the rad status and PAR's to'be implemented are displayed in the EOF, log any differences between utility's PAR and states PA. _

13. Update the State and Counties on the status of the emergency event at'least every 30 minutes usinig the admin Hotlime.

14. Use PA system to brief EOF of changes to PARs.

RECOVERY AND RE-ENTRY

1. Coordinate with the Site Radiation Protection Coordinator and local, State and Federal agency representatives in the development and implementation of a long-term environmental monitoring program as an element of recovery. Send forms EOF-23 and 29 to the State and Counties.,J_

EOF-08 Rev.6 I

SUPPORT SERVICES COORDINATOR CHECKLIST The following checklist is available for use by the Support Services Coordinator as a guide to put eitherthat ensuring emergency response actions are completed. The column to the right can be used to a check when an item has been completed orany notation which will be of assistance to the user.

1. Place name/sign in on the position board and establish a log

2. Receive a briefing from the Assistant ER&RD or the ER&RD.

3. Verify with Tower Security that the building-wide announcement was mande

4. Notify the Corporate Security Manager to lbr6*vide security for the 6th and 14th floors. _ _

"NOTE " "

If necessary, additional security guards may be obtained by contacting the Corporate Security Manager.

5. Coordinate with Corporate Security to ensure security posts and access control points are established (personnel and equipment). Refer to EPIP 1.5.

6. Verify with Security that signs are posted in elevator lobbies.

7. Inform the Assistant ER&RD and the JPIC Manager that security posts are established. '_."____

8. Notify Support Services and place on standby. -. ,,

9. Assist the Assistant ER&RD/ER&RD as needed.

'i~i7 _"',

10. When directed initiate EnergencyM ting ystem message as asthetack-up to Linn or Benton County

11. Establish a 24-hour staff rotation (consult with the'ER&RD)"_"

'/*

EOF-11I REV2

EOF Messenger Checklist Place nametag I sign-in on staffing board & post the "This is a drill" signs

___ Post Emergency Action Level signs and inform Security Access Clerk of changes Ensure adequate supplies are available (paper)

Provide the JPIC the EPZ transparency obtained from the Rad Data Plotter ERO Notification Form - from ER&RD Send alpha-mate message Sign and date form after page has been sent Return original to TSC Communicator EAL Notification Form - from RAD & EOF Manager (distribute as follows)

ER&RD Assistant ER&RD STNOps Liaison NRC HPN Communicator Iowa EMD and State Dose Assessment (when present)

Technical Recorder JPIC Original to the Rad & EOF Manager TSC Communicator RAD Data Plotter RAC Fax to: State, Counties, TSC, and Control room/Simulator

[When the EOF is operational]

_,___ Plant Status Report - from printer distribute as follows Assistant ER&RD JPIC Plant Status Recorder Midas Dose Projections - from printer, goes to RAC for signature before distributon Assistant ER&RD Rad & EOF Manager State Dose Assessment (when present)

Rad Data Communicator Midas Operator JPIC Original to the RAC EAS Messages - from JPIC distribute as follows ER&RD Assistant ER&RD NRC HPN Communicator Iowa EMD (when present)

Technical Recorder EOF Manager EOF-38 Rev. 0

Electronic Status Board - from fax or printer distribute as follows (original to TSC Comm.)

ER&RD Assistant ER&RD NRC HPN Communicator Iowa EMD (when present),

Technical Recorder, JPIC.

EOF-38 Rev. 0

, - ý , I . I : , , tC - -!

Plant Status Recorder Checklist'.

1. Place nametag/sign in on the position board.

2. Obtain Plant Status Recorder book and follow instructions

3. Logon to EDS and display EDS in the EOF

4. Plot trends of plant status on the boards every 15-30 minutes

5. If the PPC is down obtain plant status information from the TSC Communicator.

EOF-39 Rev. 0

ERO NOTIFICATION - OFF-HOURS PHONE SYSTEM CALLOUT NOTE I In the event the AVS100 callout system is inoperable, the manual method of calling the ERO shall be implemented per SD-22 using the Emergency telephone book.

(1) This form shall be used when an Alert or greater classification is declared during non-normal working hours at the DAEC.

(2) The OSM/OSS shall direct the Security Officer/STA to initiate the Off-Hours Notification.

(3) For drills or exercises, a member of the Emergency Planning Department staff shall initiate the Off-Hours Notification.

(4) Completed form will be taken to the SAS operator or the STA if this is a Security event. To initiate the callout, follow the instructions for the Off-Hours Notification System.

REQUESTED BY: DATE/TIME:

OSM/OSS INITIATED BY: DATE/TIME:

Security Officer/STA (5) The SAS Operator will receive a call from the Off-Hours Notification System as confirmation of the callout system initiation. The Off-Hours Notification System call to the CAS signifies the callout system has attempted every telephone number on the list once.

CALL RECEIVED BY: DATE/TIME:

Security Officer/STA NOTE-01 Rev. 3

---.RG:E E CY.**LAN iMP.LEM ENTI NGi EN M EDU *ESý, -NOTE-07 Rev. 0

_._ BASIC NOTIFICATION FLOWPATH Page 1 of 1 Initial State and County Notifications from the Control Room NOTE-07

PROTECTIVE ACTION DECISION MAKING RECOMMENDATIONS El [A] [B] [C]

None None Activate the Prompt Alert and Notification System AND Place dairy animals within the entire EPZ on stored feed and covered water.

Gener'a Imerq6 eC- 7 Default Recommendations for Default Recommendations for Default Recommendations for GENERAL GENERAL EMERGENCY, core GENERAL EMERGENCY with dose EMERGENCY with dose projections Ž>1 damage or dose projections Ž1 REM projections Ž1 REM TEDEor25 REM TEDE or Ž5 REM CDE @ 5-10 miles TEDE or Ž5 REM CDE @ 0-2 miles REM CDE @ 2-5 miles from site from site boundary.

from site boundary. boundary. I

[] [D] EI[q [] [F]

Activate the Prompt Alert and Activate the Prompt Alert and Activate the Prompt Alert and Notification Notification System, Place dairy animals Notification System, Place dairy System, Place dairy animals in the entire EPZ within the entire EPZ on stored feed animals within the entire EPZ on on stored feed and covered water.

and covered water. stored feed and covered water.

AND AND AND Evacuate within a 2 mile radius and to Evacuate within a 2 mile radius Evacuate within a 2 mile radius, evacuate 5 miles in the downwind subareas. and to 5 miles in the downwind from 2 miles to EPZ edge in downwind subareas, and shelter downwind subareas, and shelter as appropriate beyond subareas from 5 miles to EPZ EPZ edge.

1_edge. _

PAR-01 Rev. 0

PROTECTIVE ACTION DECISION MAKING FLOWCHART Protective actions in the event of severe core damage or loss of control of facility.

NOTES 8

severe core damage is indicated by:

(1) Fuel damage assessment (PASAP 7.2) determines at least 5% fuel clad damage (2) Valid drywell rad monitor reading above 7E + Activate the Prompt Alert and AtvtthPrmtAetadNotification System 2R~hr (3) Valid torus rad monitor reading above 3E + place lactating dairy animals within the entire EPZ

()Rhr ton stored feed and protected water I4) C t aAND (4) Coolant activity above 300IjCi/gm DOSE Evacuate a 2 mile radius and 5 miles downwind EQUIVALENT 1-131 unless conditions make evacuation dangerous and (5) RPV Level remains below -25 inches advise remainder of plume EPZ to go indoors to b Distances are approximate - actual distances monitores bracast.

(See notes b, c, d, e, t) will be determined by the size of the preplanned sub-areas, which are based on geopolitical boundaries.

c If there are very dangerous travel conditions.

initially shelter rather than evacuate the Continue assessment population until conditions improve. based on all avaiable d Transit-dependent persons should be advised plant and field to remain indoors until transportation resources monitonng information arrive, if possible.

• Shelter may be the appropriate action for controlled releases of radioactive material from the containment if there is assurance that the Modify protective release is short term (puff release) and the area actions as necessary near the plant cannot be evacuated before the Locate and evacuate plume arrives, hrl potects. Do not I Consider EPA PAGs (Table G-1) in modifying relax protectsue actions initial protective actions. untl the source of the (Located on page 2 ofI 2) threat is cleary under control.

Source: U.S N.R.C. RTM-96/NUREG/BR-0150 Table G-1. Early phase Protective Action Guides (PAGs)

Protective action (projected PAG dose) Comments 0

1-5 rem b Evacuation (or for some situations, sheltering) should I Evacuation (or sheltering) normally be initiated at 1 rem.

Administration of stable iodine 25 rem thyroid Requires approval of State medical officials.

0 Sheltering may be the preferred protective action when it will provide protection equal to or greater than evacuation, based on consideration of factors such as source term characteristics, and temporal or other site-specific conditions.

For further guidance, see EPA 400-92-001, Sect. 2.3.1.

b The sum of the effective dose equivalent (EDE) resulting from exposure to external sources and the committed effective dose equivalent (CEDE) incurred from all significant inhalation pathways during the early phase. Committed dose equivalents to the thyroid and to the skin may be 5 and 50 times larger, respectively.

'Committed dose equivalent (CDE) to the thyroid from radioiodine.

Source:Adaptedfrom EPA 400-R-92-001, p. 2-6 PAR-02

EMERGENCY PLAN 1IMPLEMENTING PROCEDURE TSC-41 POST-ACCIDENT SAMPLING CAPABILITIES Rev. 0 1 Page 1 of I (1) High Range Effluent Monitoring (KAMAN) System particulate and iodine filter cartridges can be drawn from:

(a) Off-Gas Stack (b) Reactor Building Stack(s)

(c) Turbine Building Vent System (2) Post Accident Sampling System samples can be drawn from:

(a) A pressurized Reactor Coolant System sample from the Jet Pump flow sensing instrument lines (b) A depressurized Reactor Coolant System sample from the RHR Heat Exchanger discharge line when RHR is in the Shutdown Cooling mode of operation (c) A Torus sample from the RHR Heat Exchanger discharge line when RHR is in the LPCI, Torus Cooling, or Test mode of operation (d) A Drywell atmospheric sample from the Containment Atmosphere Monitoring System analyzer sample lines (e) A Torus atmospheric sample from the Containment Atmosphere Monitoring System analyzer sample lines (3) Reactor Building grab samples can be taken from the backup sampler located on the Turbine Building roof.

TSC-41

ON-SITE MAP A

B C

D E

F G -

H i.o L

M N

0 P

Q 1 "2 -314 166 G 7 18 19 TSC-42 Rev. 0