ML20063N470

Public Version of Revised Emergency Response Plan Implementing Procedures,Including Procedures A.2-001 Re Emergency organization,A.2-302 Re Assembly Point Activation & A.2-303 Re Search & Rescue

ML20063N470
Person / Time
Site:	Monticello
Issue date:	08/05/1982
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20063N471	List: ML20063N470
References
PROC-820805-01, NUDOCS 8209210559
Download: ML20063N470 (91)

Text

08/05/82 A.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES LIST OF CURRENT PAGES PROCEDURE PROCEDURE TITLE REVISION NUMBER O

L' 000 Series Organization l A.2-001 Emergency Organization 3 1 100 Series Activation A.2-101 Classification of Emergencies 3 A.2-102 Notification of an Unusual Event 3 A.2-103 Alert 4 A.2-104 Site Area Emergency 3 A.2-105 General Emergency 3 A.2-106 Activation of Technical Support Center 3 A.2-107 Activation of Operations Support Center 3 200 Series ' Assessment A.2-201 On-Site Monitoring and Protective Action Criteria 2 A.2-202 Off-Site Monitoring Durng an Emergency 1 A.2-203 Deleted 3-1-82 A.2-204 Off-Site Protective Action Recommendations 1 A.2-205 Personnel Accountability-Control Room /TSC 1 A.2-206 Deleted 3-1-82 A.2-207 Sampling Priorities During an Emergency 0 A.2-208 Core Damage Assessment 0 300 Series Protective Actions A.2-301 Emergency Evacuation 1 A.2-302 As,embly Point Activation 2 l'd A.2-303 Search and Rescue 2 A.2-304 Thyroid Prophylaxis 2 400 Series Radiological Surveillance and Control A.2-401 Emergency Exposure Control 1 A.2-402 Contamination Control 0 A.2-403 Emergency Surveys 2 A.2-404 Emergency Sampling and Analysis 2 A.2-405 Release Rate Determination 2 A.2-406 Off-Site Dose Projection 5 A.2-407 Personnel and Vehicle Monitoring 2 A.2-408 Sample Coordination During an Emergency 1 A.2-409 Self-Contained Breathing Apparatus (SCBA) Use During An Emergency 0 A.2-410 Out-of-Plant Surveys 1 A.2-411 Establishment of Secondary Access Control 0 A.2-412 Mobile Lab Counting Procedure 0 500 Series Communications and Documentation A.2-501 Communication During an Emergency 1 l A.2-502 Recordkeeping During an Emergency 0 A.2-503 Emergency Reports and Documentation 0 1

-i-AAA056 8209210559 820826 PDR ADOCK 05000263 p PDR

. - . . - . . . - - - - - . .~ . . - . .. . - . - - . .

08/05/82 A.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES -

LIST OF CURRENT PAGES P_ROCEDURE PROCEDURE TITLE REVISION NUMBER O 600 Series A.2-601 Re-Entry and Recovery Re-Entry 0 l

I A.2-602 Deleted 11-19-81  !

A.2-603 Repair and Corrective Action 1 700 Series i A.2-702 Response to an Emergency at Prairie Island 2 A.2-703 Response to Off-Site Situation Involving l

• Radioactive Materials 0 i

t O i e

AAA056 .

Procatdura A.2-001 Ravision 3 Page 1 of 28 Op. Com. Rev. Req'd. Yes X No Q. A. Review Req'd. Yes No X O ALARA Review Req'd. Yes No X V

EMERGENCY ORGANIZATION A.2-001 REVIEW AND APPROVAL i Prepared by: [pN//[d . w ALARA Review: G. D. Mathiasen Date 11/17/81 Reviewed by: Ikhh Q.A. Review: R. L. Scheinost Date 11/17/81 Operations Commi,tt E,ina R view: M eting Number /0 B /o Date 27/B2 Approved'by: d k 1l vs I\J h ]1 Date @ 6[//C/91

,, ,j Op. Com. Results Review: _,n1of t-e 9 u.: ced Mtg. IO8(o Date 6/27/B'4 D

PURPOSE The purpose of this procedure is to describe the on-site Emergency Response Organization (ERO) and to provide an orderly method of staffing the positions of which the ERO is comprised.

PRECAUTIONS No Monticello Nuclear Generating Plant personnel shall make any information releases to members of the news media or the general public during an O

v emergency unless cleared through the Emergency Manager, if established, or Emergency Director. Direct all inquiries to the Communications Department at NSP Headquarters or at the EOF.

DISCUSSION A. Although it is not practical to develop detailed procedures encompassing every conceivable emergency situation, advance planning should create a i

i high order of preparedness and ensure an orderly and timely decision-making body. Advance planning of the Emergency Organization ensures that during an emergency the duties of the plant staff members, who are required to direct the emergency ef fort, are defined. (See Figure 1)

B. The Emergency Organization is herein described. The duties and responsi-bilities of the indivioua' Emergency Organization members are defined.

C. The Tag Boards are used to make speedy personnel duty assignments during the initial stage of an emergency, to insure that qualified personnel fill the l

positions in the ERO, and insure that the more important positions in the ERO are filled first.

The Tag Board consists of a board with a layout of the Emergency Response

+

Organization. Under each position on the board is a list of the individuals who are qualified to fill that position, and a tag with the necessary instruction j for filling that position. There is also a sign-in sheet that serves to indicate who has taken a specific tag from the Tag Board.

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Procedure A.2-001 l Revision 3 Page 2 of 28 l The Tag Boards are located in the TSC outside the Supt. of Operations office and in the OSC at access control. All personnel who are members of the ERO have the responsibility of checking the Tag Boards when it is announced that ERO personnel are to report to their duty stations.

The Tag Board system is designed to work as follows:

When an announcement is made to activate the ERO duty assignments, ERO personnel should pa s by the appropriate Tag Boards. (See below lists) If an individual's name is on one of the lists for a position in the ERO, and the tag for that position has not been removed, he should remove that tag, read the instructions t on the tag, and sign the sign-in sheet indicating the position in the ERO that is being filled. If an individuals name appears on more than one list the individual must determine which of the positions should be filled first and remove the appropriate tag. (If you have a question as to the priority of filling positions contact the Emergency Plan Coordinator.)

If an individual arrives at the Tag Board and finds the tag is removed for a position they are qualified to fill, the person should check the sign-in sheet and determine if they are higher on the order of succession than the person performing that job. If so they should relieve that individual.

TSC Tag Board OSC Tag Board Emergency Director Maintenance Personnel Radiological Emergency Coord. I&CS Personnel Group Leaders RPS Personnel STA's Of f-Shif t Operators SEC's D. It is the Emergency Director's responsibility to ensure 24-hour coverage of key positions in the emergency organization. He must consider that the emergency may continue for some time and "nacf the utilization of personnel resources (e.g. , ensure rotation of personnel to allow time for eating and sleeping).

E. While the qualification criteria listed in this procedure will be used to determine who may be qualified to fill a given emergency organization position, it is not intended that a person who is not qualified may not be assigned to that position. The goal should be to have several people qualified to fill each position, but it there'is no one available from the qualified list, the most qualified per-son available should be selected.

Requalification, when applicable, will be required on an annual (? 3 months) basis. This procedure vill be reviewed quarterly, and revised if necessary.

F. In the periods between revisions of this procedure, personnel who become qualified may be used to st aff -these positions.

9 WP/dw

Procedure A.2-001

. Revision 3 Page 3 of 28 QUALIFICATION, ORDER OF SUCCESSION AND DUTIES I. Coordination and Direction Group A. Emergency Director

1. Qualifications

a. Five years experience at Monticello Nuclear Generating Plant NOTE: This requirement does not apply during initial phase of emergency when the Duty Shift Supervisor is Emer-gency Director.

b. Experience as Plant Manager Designee NOTE: This requirement does not apply during initial phase of emergency when the Duty Shift Supervisor is Emer-gency Director.

c. Knowledgeable or qualified in following areas:

- Corporate Emergency Plan

- Monticello Emergency Plan

- Emergency Implementing Procedures:

[~'\ A.2 - 001 A.2 - 101 A.2 - 303 A.2 - 102 A.2 - 304 A.2 - 103 A.2 - 401 A.2 - 104 A.2 - 501 A.2 - 105 A.2 - 502 A.2 - 204 A.2 - 503 A.2 - 205 A.2 - 601 A.2 - 301 A.2 - 603

- Safeguards Contingency Plan Implementing Procedures SCPIP - 1 SCPIP - 8 SCPIP - 2 SCPIP - 12 SCPIP - 4

2. Qualified Personnel in Order of Succession b.

c.

d.

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e. Duty Shift Supervisor WP/dw

ProcIdura A.2-001 R;visica 3 Peg 4 cf 28

3. Duties

a. Coordinates the response of the plant emergency organization;

b. Evaluates plant and radiological conditions;

c. Ensures assessment of offsite radioactivity releases;

d. Recommends offsite protective actions;

e. Determines emergency classification;

f. Calls in additional plant personnel;

g. Assumes control of Technical Support Center personnel and activities;

h. Makes decisions regarding habitability of emergency response centers and location of assembly areas;

i. Approves radiation exposures in excess of normal limits;

j. Ensures all injured personnel receive medical assistance; and

'.. Ensures 24-hour coverage for key positions of plant emer-gency organization.

B. Shift Technical Advisor

1. Qualifications Qualified per 4 AWI-4.7.1

2. Qual?fied Personnel 1

0 l

l

3. Responsibility Provide technical operational advice to the Shift Supervisor.

l C. Shift Emergency Communicator

1. Qualifications

a. Six months experience at Monticello WP/dw l

l

Procedure A.2-001 Ravisica 3 Page 5 of 28

b. Ability to communicate verbally in clear, concise manner

c. Knowledgeable or qualified in following areas:

- Emergency Implementing Procedures:

A.2 - 101 A.2 - 105 A.2 - 102 A.2 - 106 A.2 - 103 A.2 - 501 A.2 - 104 A.2 - 502

- Emergency Plan (Knowledgeable to degree necessary to be able to direct others in use of procedures)

d. Other administrative qualifications as determined by Planc Management.

2. Qualified Personnel W 69 QwG O

3. Duties

a. Assists Emergency Director in emergency classification;

b. Conducts initial and followup notification in accordance l with procedures;

c. Coordinates all incoming and outgoing communications;

d. Ensures proper logging and recording of communications.

e. Assist Emergency Organization in use of procedures.

II. Operations Group A. Operations Group Leader

1. Qualifications

) ,

a. Current SRO License for Monticello b'P/dw t

. , =._ . _ - . __ , . . - . _,. .- , _

Prcccdura A.2-001 R:visicn 3 Peg 2 6 of 28 bg Demonstrated ability in supervisory skills,

c. Knowledgeable or qualified in following areas:

- Monticello Emergency Plan

- Emergency Implementing Procedures:

A. 2 - 101 A.2 - 205 A.2 - 102 A.2 - 301 A.2 - 103 A.2 - 502 A.2 - 104 A.2 - 105 A.2 - 107

2. Qualified Personnel in Order of Succession

a. OELETED

b. Senior Site Superintendent present, not on duty shift

c. Senior Shif t Supervisor present, not on duty shift

d. Duty Site Superintendent

e. Duty Shift Supervisor

3. Duties

a. Coordinates response of Operations Group;

b. Evaluates plant and radiological conditions;

c. Ensures Emergency Director is informed of plant status;

d. Directs operation of the plant in compliance with all normal plant procedures, directives, technical specifi-cations and emergency procedures;

e. Monitors plant parameters and conditions.

B. Fire Brigade

1. Qualifications

a. Currently qualified in accordance with 4 AWI-3.13.2, including SCBA training and qualification.

b. Currently qualified in accordance with Appendix R, 10CFR50:

1.) The Team Leader and #2 & #3 Team Members shall have sufficient training in or knowledge of plant safety-related systems to understand the effects of fire and fire suppressants on safe shutdown capability.

2.) The Team Leader shall be competent to assess the poten-O WP/dw

Procedure A.2-001

• Revision 3 Page 7 of 28 tial safety consequences of a fire and advise control O- room personnel. This shall be evidenced by current SRO or RO or current enrollment in license i.a.I..ing program,

c. Qualified physically in accordance with Tab 7 of the NSP Medical Policy and Procedure Manual (annual requirement).

2. Qualified Personnel

a. Team Leader

-T D EW'6Q If a designated Team Leader is not on duty, an alternate Team Leader will be designated by the Shift Supervisor.

b. Team Memba.rs #2 & #3 ,

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c. Team Members #4 & #5 i

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Precedura A.2-001

. Revisicn 3 Pcg2 8 of 28 III. Maintenance Group The Maintenance Group consists of the Plant Superintendent, Operations O

and Maintenance; the Superintendent, Maintenance; the Maintenance Super-visors; all maintenance crew people; the plant electricians; plant helpers and the Instrument & Control Group including supervisors and coordinators.

A. Maintenance Group Leader

1. Qualifications

a. Five years experience at Monticello Nuclear Generating Plant

b. Demonstrated ability in supervisory skills

c. Knowledgeable or qualified in following areas:

- Emergency Plan

- Emergency Implementing Procedures:

A.2 - 001 A.2 - 106 A.2 - 107 A.2 - 603

2. Order of Succession

a. .

b.

c. 7g,Q I p@ l f.

B. Group Responsibilities The group shall have the primary responsibility for emergency repairs and corrective actions.

IV. Engir.eering Group The Engineering Group consists of the Superintendent, Technical Engineering and the Technical Engineering Group, plus the Superintendent, Operations Engineering and the Operations Engineering Group. ,

A. Engineering Group Leader

1. Qualifications

a. Five years experience at Monticello Nuclear Generating Plant

b. Demonstrated ability in supervisory skills O

WP/dw

Procedure A.2-001 Revision 3 Page 9 of 28

c. Knowledgeable or qualified in following areas:

- Emergency Plan

, - Emergency Implementing Procedures:

A.2 - 106 A.2 - 502

2. Order of Succession a.

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B. Group Responsibilities The group shall have the responsibilities for providing technical support for emergency repairs and corrective actions.

V. Health Physics Group The Health Physics Group consists of the Supt., Radiation Protection and all Members of the Radiation Protection Group.

The group is divided into two sections: The Offsite Dose Assessment and Chemistry Section and the Monitoring Section. The group leader is the Radiological Emergency Coordinator (See Figure 2).

A. Radiological Emergency Coordinator

1. Qualifications

a. Five years experience at Monticello Nuclear Plant;

b. Demonstrated ability in supervisory skills;

c. Knowledgeable or qualified in following areas:

- Health Physics

- Emergency Plan

- Emergency Plen Implementing Procedures:

A.2 - 101 A.2 - 301 A.2 - 405 A.2 - 106 A.2 - 302 A.2 - 406 A.2 - 107 A.2 - 303 A.2 - 407 A.2 - 201 A.2 - 304 A.2 - 409 A.2 - 202 A.2 - 401 A.2 - 410 A.2 - 204 A.2 - 403 A.2 - 502 A.2 - 205 A.2 - 404 A.2 - 702

(__s A.2 - 207 U

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Procedura A.2-001 R; vision 3 Page 10 of 28

2. Order of Succession

o<#sp e.

3. Duties

a. Coordinate assessment of radiological aspects of accident, including offsite surveys prior to EOF activation.

b. Formulate protective action recommendations

c. Ensure radiological surveillance and control measures are implemented.

d. Advise Emergency Director on health physics matters B. Offsite Dose Assessment and Chemistry Section Leaders

1. Qualifications

a. One year experience at Monticello Nuclear Generating Plant

b. Knowledgeable or qualified in following areas:

- Chemistry and radiochemistry, including Monticello Chemistry Manual

- Emergency Plan Implementing Proedures:

A.2 - 207 A.2 - 208 A.2 - 404 A.2 - 405 A.2 - 406 A.2 - 408 A.2 - 412 A.2 - 502

2. Order of Succersion

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1. sp e.

3. Duties

a. Offsite dose projection WP/dw

Procedura A.2-001

. R;visica 3 Pege 11 of 28 p._ b. tease rate determination

(\-) c. Sampling and analysis of reactor coolant, containment atmos-phere and plant effluents

d. Sample coordination and recording C. Monitoring Section Leader *

1. Qualifications

a. One year experience at Monticello Nuclear Generating Plant

b. Knowledgeable or qualified in following areas:

- Monticello Radiation Safety Procedures (E.1)

- Emergency Plan Implementing Procedures:

A.2 - 107 A.2 - 403 A.2 - 201 A.2 - 404 A.2 - 202 A.2 - 407 A.2 - 301 A.2 - 409 A.2 - 302 A.2 - 410 A.2 - 303 A.2 - 411 bs A.2 - 304 A.2 - 501 I)

' A.2 A.2 401 402 A.2 - 502 A.2 - 601

2. Order of Succession b.

- 5) e; \ fe

d. $)

e.

3. Duties

a. Emergency exposure control

b. Contamination Control Emergency surveys c.

d. Personnel and vehicle monitoring

e. Personnel and equipment decontamination VI. Support Group The Support Group consists of all plant office personnel and all plant QA W

• personnel.

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Procedura A.2-001

. Revisien 3 Ptg2 12 of 28 A. Support Group Leader

1. Qualifications

a. One year experience at Monticello Nuclear Generating Plant;

b. Demonstrated ability in supervisory skills;

c. Knowledgeable or qualified in following areas:

A.2 - 501 A.2 - 503 A.2 - 502 A.2 - 106

2. Order of Succession a.

b.

c.

d.

e.

gk(,iq[)

3. Duties

a. Assign group personnel to provide administrative support, document control and document retrieval;

b. Assure that TSC is staffed adequately.

c. Coordinate and provide personnel for logistics functions

d. Act as TSC Coordinator and be responsible for conduct of Procedure A.2-106, Activation of the Technical Support Center.

B. Emergency Document Control Coordinator

1. Qualifications

a. Thorough understanding of Monticello document and record control system;

b. Knowledge of physical storage locations of plant documents and records;

c. Knowledgeable or qualified in following areas:

A.2 - 502 A.2 - 503

2. Order of Succession O

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Procedura A.2-001 R2vicion 3 Prge 13 of 28

, a. q

('- ) b. D (4,7 4

e.

3. Duties

a. Provide document retrieval support for TSC;

b. Assist Support Group Leader with records control in TSC area VII. Security Group The Security Group consists of all plant Security and Services personnel and the contract security force.

A. Security Group Leader

1. Qualifications

a. Two years experience at Monticello Nuclear Generating Plant

b. Knowledgeable or qualified in following areas:

- Monticello Security Plan

[

(,) - Safeguards Contingency Plan & Implementing Procedures

- Emergency Plan Implementing Procedures:

A.2 - 206 A.2 - 301 A.2 - 302

2. Order of Succession kg.,

2 'Do

3. Duties

a. Carry out plant security and accese control functions

b. Maintain strict personnel accountability onsite.

VIII. Emergency Team Personnel If required by procedure or for other purposes, an Emergency Team will be selected from the list of available candidates. (In special cases, however, exceptions to this procedure may be authorized by the Emergency Director.)

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Procedura A.2-001 Revisica 3 Pcgn 14 of 28 A. Qualifications

1. Current Red Cross Multi-Media First Aid training (i.e. within 9

last three years).

2. Currently qualified under respiratory protection program, including training for use of SCBA equipment.

3. One year experience in current <,eneral work classification.

B. Qualified Personnel Personnel who are qualified for emergency team are identified with an asterisk on form 5790-102-5, 'Monticello Emergency Augmentation List' (see attachment 1).

IX. Miscellaneous Positions A. Emergency Planning Coordinator

1. Qualifications

a. Health physics background or health physics expertise on staff.

b. Five years experience at nuclear power plant.

c. Two years experience at Monticello.

2. Designated Emergency Planning Coordinator Mathiasen, G.

B. Emergency Preparedness Instructors

1. Qualifications

a. Knowledgeable in Plant and Corporate Plans and Implementing Procedures.

b. Demonstrated ability in instructing methods.

c. Thoroughly familiar with subject matter of instruction.

2. Qualified Personnel Personnel approved by Monticello Training Superintendent C. Assembly Point Coordinator

1. Qualifications ,

See Qualifications for Shift Emergency Communicator WP/dw

Procedure A.2-001 Revisicn 3 Page 15 of 28

2. Qualified Personnel See Qualified Personnel for Shif t Emergency Communicator

3. Duties

a. Assume control of operational Assembly Point

b. Ensure proper radiological surveys are conducted

c. Conduct accountability procedure as required

d. Maintain communications between Assembly Point and TSC D. TSC Coordinator (See Support Group Leader)

E. OSC Coordinator

1. Qualifications - Experience as Radiation Protection Coordinator

2. Qualified Personnel C. N

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s 3. Duties

a. Be responsible for conduct of procedure A.2 - 107, Activation

, of the Operational Support Center.

b. Supervise OSC personnel assigned to star.dby duty.

F. Technical Communicator

1. Qualifications

a. Experience at Monticello

b. Systems expertise

2. Qualified Personnel This position will be filled by designating the most qualified ,

person from among available candidates. The Emergency Director

' will be responsible for assuring that this position is adequately staffed.

3. Duties

a. Continuously maintains an open telephone communicatians link

/-, between the Control Room, TSC, and EOF.

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Proczdura A.2-001

. R:vizien 3 Pega 16 cf 28

b. Communicate technical information between response centers.

c. If located in TSC, post information on Status be:rd.

X. Response Center Staf fing A. TSC Staffing

1. Emergency Director - In charge

2. Group Leaders

a. Radiological Emergency Coordinator

b. Engineering Group Leader

c. Operations Group Leader *

d. Maintenance Group Leader

e. Support Group Leader (TSC Coordinator)

f. Security Group Leader

• If primary designate is not available, this individual may be required to stay in Control Room.

3. Communicators

a. Lead TSC Communicator

b. Assistant TSC Communicator (offsite notification)

c. Technical Communicator (3-way to EOF and CR)

d. Assistant REC Communicators (2)

e. Assistant TSC Communicator

4. Auxiliary Staff

a. Monitoring Section Ieader

b. Offsite Dose Assessment and Chemistry Section Leader

c. Engineering Assistant

d. Security Assistant

e. Emergency Document Control Coordinator

f. Recorder B. OSC Staffing

1. OSC Coordinator - In Charge

2. Standby Personnel

a. All unassigned RPS

b. Extra Operators (i.e., not assigned to Control Room)

c. I&CS Supervisor, Coordinator and Specialists

d. Maintenance Supervisors, Chief Electrician, Station Electricians, Machinists, Welders, Repairmen, and Riggers.

WP/dw

Procedure A.2-001 Revision 3 Page 17 of 28

3. Communicator (To be designated by OSC Coordinator if needed)

J C. Control Room Staffing

1. Site Superintendent - In Charge

2. Assistance

a. Shift Supervisor

b. Shif t Operators

c. Additional operators assigned to Control Room 4 d. STA

3. Technical Communicator (CR to TSC)

4. Technical Support Center personnel as directed by Emergency Director REFERENCES

1. tionticello Nuclear Generating Palnt Emergency Plan

2.  ?!onticello Nuclear Generating Plant Operations ?!anuals

3. NUREG-0654/FEt!A-REP-1, " Criteria for Preparation and Evaluation of Radio-logical Emergency Response Plan and Preparedness in Support of Nuclear Power Plants".

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Emergency Director Shift Emergency Communicator r

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Enginee r i ng' '

Support Radiological Security y Group Group hergency Group M Leader Leader Coordinator Leader I 1 l l g 11calth E Engineering Support Security Q h l'hy sics Group Group Gr UP n ~

Group h

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Operations Grcup Maintenance y Group Leader Leader Shift l Technical l l Advisor C

Electrical & 7yy Mechanical "<

Section Operations Group Section kk co o e

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Procedure A.2-001 FIGURE 2 Revision 3 Page 19 of 28 HEALTH PHYSICS CROUP (SHIFT) ORGANIZATION b'~T Emergency Emergency

• Manager Director

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Rad. Prot. Radiological Support _ ,, ,, _, ,, ,,

Emergency .

Supervisor Coordinator 1f f-Site Dose Assessment Monitoring

() & Criemistry Section Section 1 Supervisor 1 Supervisor 2 Technicians 5 Technicians Off-Site Monitoring Team

• 1 Supervisor 4 Technicians i

• Staffed during initial hours of emergency.

After EOF activation, Off-Site Monitoring Team dissolves into Monitoring Section.

a -

A'ITAOMENT 1 Proceduro A.2-001 Form 5790-102-5 e sion 3

. Examplo of Paga 20 of 28 R; vision 5, 06/25/82 Page 1 of 9 MONTICELLO EMERGENCY AUGMENTATION LIST COORDINATION AND DIRECTION GROUP Pager Home h

• (

• (

)

• .09 W

17 Plant Manager Plt. Supt., Engr. & Rad. Prot.

D'llGcED

• ( , Supt., Security & Services

• ( ) Supt., Quality Engineering SECURITY GROUP Supt., Security & Services

• ( ) ~g

( ) , gfY Supervisor, Security & Services C#

l ( ) N Plant Scheduling Administrator

( ) Scheduling Coordinator

( ) Uuty Security Shift Supervisor (For Additional Guards)

(  : Security Shift Supervisor

( ) Security Shift Supervisor

( ) Secur ity Shif t Supervisor

( ) Security Shift Supervisor

( ) Security Shift Supervisor

( ) Security Shift Supervisor g SHIFT TECHNICAL ADVISOR

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• ' Emergency Team Candidates AAA149 l

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Procedure A.2-001 ,

Form 5790-102-5 s n ATTAONENT_1 (Cont'd.) o 28 Revision 5, 06/25/82 Page 2 of 9 Example of MONTICELLO EMERGENCY AUGMENTATION LIST MAINTENANCE GROUP Pager Home

• ( )~ Plt. Supt., Oper. & Maint.

• ( ) Superintendent, Maintenance

• ( ) g g\,, Maintenance Supervisor

• ( )- Maintenance Supervisor

• ( ) Lead Machinist gp

( ) Machinist QL

• ( ) Machinist j *( ) Appr. Machinist

• ( ) Appr. Machinist

• ( ) Appr. Machinist

*( ) Appr. Machinist

! *( ) Steam Fitter Welder

• ( ) Steam Fitter Welder

• ( ) _. _ Steam Fitter Welder

• ( ) Appr. Steam Fitter Welder 13 V ( ) Lead Rigger

• ( ) -

Rigger

( ) . Appr. Rigger

• ( ) Appr. Rigger

. *( ) Appr. Repairman

( ) - -

Appr. Repairman

• ( ) Chief Electrician

• ( ) Appr. Electrician l ( ) Appr. Electrician

• ( ) Sta. Electrician

• ( ) Sta. Electrician

• ( ) Nuclear Plant Helper Emergency Team Candidates

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Procedura A.2-@01 Itvisiin 3 Form 5790-102-5 ATTAOBENT 1 (Cont'd.) Pag) 22 cf 28 R: vision 5, 06/25/82 Page 3 of 9 Example of MONTICELLO EMERGENCY AUGMENTATION LIST MAINTENANCE GROUP (Cont'd.) h Pager Home

• ( )' Nuclear Plant Helper (Lead)

^( ) gf.IU d Nuclear Plant Helper ,gTTIU

( ) Nuclear Plant Helper -

• ( ) Nuclear Plant Helper

• ( ) Nuclear Plant Helper

( ) Nuclear Plant Helper

( ) Nuclear Plant Helper

( ) Nuclear Plant Helper

( ) Nuclear Plant Helper

( ) Nuclear Plant Helper

( ) Lead, Instruments & Controls Engineer

• ( ) I&C Coordinator

( ) I&C Specialist

• ( ) I&C Specialist

( ) I&C Specialist

() I&C Specialist h

• ( ) I&C Specialist

( ) I&C Specialist

( ) I&C Specialist Emergency Team Candidates h AAA149

Proceduro A.2-001 R: vision 3 Form 5790-102-5 4TTAONENT 1 (Cont'd.) page 23 of 28 Revision 5, 06/25/82

.. Page 4 of 9 Example of MONTICELLO EMERGENCY AUGMENTATION LIST OPERATIONS GROUP Pager Home

• ( ) Superintendent, Operations

• ( ) Relief Shift Supervisor g 4Q

( ) g g,,b h . () Shift Supervisor (J N

• ( ) Shift Supervisor

( ) Shift Supervisor

( ) Shift Supervisor

• ( ) Shift Supervisor

• ( ) Shift Supervisor

• ( ) Site Superintendent

• ( ) Site Superintendent ._

( .' Site Superintendent

• ( ) Site Superintendent

• ( ) Site Superintendent

( ) Site Supitrintendent g ( ) Lead Plt. Equip. & Reac. Oper.

• ( ) Lead Plt. Equip. & Reac. Oper.

• ( ) Lead Plt. Equip. & Reac. Oper.

• ( ) Lead Plt. Equip. & Reac. Oper.

• ( ) Plt. Equip. & Reac. Operator

• ( ) Plt. Equip. & Reac. Operator

• ( ) Plt. Equip. & Reac. Operator

• ( ) Plt. Equip. & Reac. Operator

• ( ) Plt. Equip. & Reac. Operator

• ( ) Pit. Equip. & Reac. Operator Asst. Plt. Equip. Operator

• ( )

• ( ) . . . . . Asst. Pit. Equip. Operator

• ( ) Asst. Plt. Equip. Operator .

Emergency Team Candidates AAA149

Procedura A.2-001 Revision 3 form 5790-102-5 AiTAONENT 1 (Cont'd.) Paga 24 of 28 Revision 5, 06/25/82 Page 5 of 9 Example of MONTICELLO EMERGENCY AUGMENTATION LIST OPERATIONS GROUP (Cont'd.) h Pager Home

• ( ) Asst. Plt. Equip. Operator .g,4()

• ( ) ggiE.TCO g Asst. Plt. Equip. Operator Ot'

• ( ) Asst. Plt. Equip. Operator

• ( ) Asst. Plt. Equip. Operator

• ( ) Asst. Plt. Equip. Operator

• ( ) Asst. Plt. Equip. Operator

• ( ) Asst. Plt. Equip. Operator

• ( ) Plant Attendant

• ( ) Plant Attendant

( ) Plant Attendant

• ( ) Plant Attendant

• ( ) Plant Attendant

• ( ) Plant Attendant

• ( ) Plant Attendant

• ( ) Plant Attendant

• ( ) Appr. Plant Attendant h

• ( ) Appr. Plant Attendant

• ( ) Appr. Plant Attendant

• ( ) Appr. Plant Attendant

• ( ) Appr. Plant Attendant Emergency Team Candidates O

AAA149

Form 5790-102-5 ATTAO NENT 1 (Cont'd.) 5o 28 R2 vision 5, 06/25/82 i Page 6 of 9 Exampic of MONTICELLO EMERGENCY AUGMENTATION LIST HEALTH PHYSICS GROUPS  !

Pager Home

( ) g.p .gp Supt., Radiation Protection QELETED

• ( ) Health Physicist

( ) Senior Chemist

• ( ) Chemist

• ( ) Supervisor, Radiological Services

• ( ) Radiation Protection Coordinator

• ( ) Radiation Protection Specialist

• ( ) Radiation Protection Specialist

• ( ) Radiation Protection Specialist

• ( ) Radiation Protection Specialist

• ( ) Radiation Protection Specialist

• ( ) Radiation Protection Specialist

( ) Radiation Protection Specialist

• ( ) Radiation Protection Specialist ,

• ( ) Chemistry Coordinator

• ( ) Radiation Protection Specialist

• ( ) Radiation Protection Specialist

( ) Radiation Protection Specialist --

( ) Radiation Protection Specialist

( ) Radiation Protection Specialist

( ) Radiation Protection Specialist

( ) Contract RPS

(

Emergency Team Candidate lb .

AAA149 -

- Proceduro A.2-001 ATTAONENT 1 (Cont'd.)_ Revision 3 Form 5790-102-5 Revision 5, 06/25/82 Example of Page 7 of 9 MONTICELLO EMERGENCY AUGMENTATION LIST ENGINEERING GROUP Pager Home

( ) Dh- , m Supt., Technical Engineering

• ( ) Supt., Operations Engineering <

• ( ) Lead Chemical Engineer OQ7g

• ( ) Asst. Chemical Engineer

• ( ) Engineer

( ) Lead Production Engineer

( ) Production Engineer

• ( ) Engineer

• ( ) Engineer Lead Production Engineer

( )

( ) Asst. Production Engineer

( )i Engineer

( )* Engineer Associate

( ) Engineer Associate

( ) Engineer Associate

• (

( )

)

Associate Production Engineer (Lead)

Asst. Production Engineer h

• ( ) Asst. Production Engineer

( ) Engineer --

• ( ) Nuclear Engineer

( ) Lead Nuclear Engineer

• ( ) Lead Computer Engineer

• ( ) Computer Engineer l

( ) Assoc. Engineer Instr.

l ( ) Asst. Instr. Engineer

( ) Asst. Instr. Engineer

( ) Engineer

( ) Engineer j ( ) Engineer l () Engineer

, ( ) Engineer l

l Emergency Team Caadidates AAA149 l

A (Cont M.) Ri o 3 Form 5790-102-5 Revisien 5, 06/25/82 Example of E#

Page 8 of 9 MONTICELLO EMERGENCY AUGMENTATION LIST SUPPORT GROUP Pager Home

• ( ) Supt., Quality Engineering

( )

DELETED Plant Office Manager DELETED

( ) Quality Engineer (Lead)

• ( ) Quality Specialist

• ( ) Quality Specialist

• (  ; Quality Specialist

( ) Quality Specialist

( ) Document Control Supervisor

( ) Plant Administrative Specialist

( ) Administrative Aid .

( ) Plant Administrative Specialist

( ) Administrative Aid

( ) Administrative Aid

( ) Purchasing / Inventory Control Supv.

e ( ) Plant Administrative Specialist

() Plant Administrative Specialist

( ) Administrative Services Supervisor --

( ) . Plant Administrative Specialist

( ) Administrative Aid

( ) Administrative Aid

( ) Plant Aaministrative Specialist

( ) Quality Engineer l () Administrative Aid 1 ( ) Administrative Aid

( ) Plant Administrative Specialist .

( ) Administrative Aid i

( ) Assoc. QC Engineer

( ) Quality Specialist

( ) Quality Engineer Emergency Team Candidates D

AAA149 i

ATTACINE5.T 1 (Contod.) &TocWtire7RFW9h Examplo or P.evision 3, Page 28 of 28 Form 5790-102-5 MONTICC'_LO EMERGENCY AUGMENTATION LIST Revision 5, 06/25/82 Page 9 of 9 Pager Home

( )

SHIFT EMERGENCY COMMUNICATOR DELEIEC h DELETED

( )

()

( )

( )

( )

( )

( )

( )

( )

( )

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( )

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Procedure A.2-302 i Revision 2 Page 1 of 8 Op. Com. Rev. Req'd. Yes X No Q.A. Review Req'd. Yes No X O ALARA Review Req'd. Yes No X ACTIVATION OF THE ASSEMBLY POINT Procedure A.2-302 Prepared by: n + N e b f ALARA Review: Revision 0 Date 3/27/81 Reviewed by:

[A/2/ahiu - Q.A. Review: Revision 0 Date 3/28/81 Operations Committee Final Review: Meeting Number //07_ Date 6/s/Bz Approved by: N kh Date F-Io-fi Op. Com. Results Review: Not Required Mtg. # 948 Date 3/25/81 PURPOSE ,

This procedure provides information and instruction for the organization, activation and operation of the on-site Assembly Points in support of the Monticello Nuclear Generating Plant and NSP Emergency Plan.

CONDITIONS AND PREREQUISITES A. An emergency condition requiring plant or site evacuation has been declared at the Monticello Nuclear Generating Plant.

B. Procedure A.2-301 (Emergency Evacuation) has been initiated.

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

ORGANIZATION AND RESPONSIBILITIES A. Emergency Director - Overall In-Charge Responsible for decision to evacuate and designation of Assembly Point Coordinator.

B. Assembly Point Coordinator - In charge of Assembly Point reports to Emergency Director. Responsible for implementation of this procedure.

C. Radiation Protectio 9 Specialist - Assists Assembly Point Coordinator.

Responsible for ensuring radiation protection procedures are followed.

(

WP/kk .

s Proceduro A.2-302

-2 Revision 2 Fage 2 of 8 DISCUSSION A. Assembly Point Operation The function of the Assembly Point is to provide a center for personnel accountability and radiological contamination screening along with any other immediately necessary actions in the event of a Plant Evacuation.

The steps ,in this procedure assume an crderly evacuation in which some time ,

is available for staging. In the event that there is no time for prepara-tion, some of the steps in this procedure may have to occur out of sequence a or simultaneously. The persons who are candidates for Assembly Point Coordinator should be familiar with the intended function of the Assembly Point so that this procedure can be adjusted to fit the circumstances.

~

B. Location The primary on-site Assembly Point is located east of the reactor building, in the south end of Warehouse #1. -The assembly coincides with the cold machine shop. An alternate on-site Assembly Point is located approximately 1000 feet south of the reactor building =across from the substation.

The off-site Assembly Points are located at ths Monticello Service Center and at the SherCo Plant.

C. Data and Information Rescurces,'-

Each On-Site Assembly Point coltains tho following:

1. Site and Area Maps.

2. Appropriate Emergency Plan'Ieplementing Procedures

3. Employeo Home Telephone Listings / Phone Book

! 4. Telephone Numbers 01 AsseneSly Areas (Attachment 3) 1 r

D. Communications

1. On-Site Assembly Points have plant telephone extensions and the Assembly Point Coordinator will be issued a portable radio for communications with all emergency. response centers.

O WP/kk

Precedure A.2-302

. Rsvision 2 Page 3 of 8 l

E. Equipment and Facilities Each On-Site Assembly Point contains the following:

1. 10 (0-200 mR) pocket dosimeters and charger

2. 10 badges

3. 1 dose rate meter

4. 1 GM survey meter

5. 1 air sampler with supply of particulate filters, charcoal and Silver Zeolite cartridges

6. 1 decontamination kit l

7. 10 sets of protective clothing

8. Radiation barrier tape / rope and radiation signs

9. 10 sets of building diagrams

10. First aid kit

11. Stationary supplies

12. Portable generator NOTE: No equipment is stored at the off-site Assembly Points.

PROCEDURE PART I - ACTIVATION STEP 1: Proceed to the TSC. Ask the Emergency Director which Assembly Point will be activated. Contact the Security Group Leader and arrange for g security force member to assist at Assembly Point. Collect the following items before proceeding to the designated assembly point:

a. Keys to assembly point (from Security Group Leader or Shift Supervisor)

b. Baseball cap with Assembly Point Coordinator designation Initiate ASSEMBLY POINT ACTIVATION CHECKLIST, Form 5790-302-1 (example:

Attachment 4).

STEP 2: At the assembly point, unlock applicable doors and position radiation barrier rope for contamination control and radiological screening.

String rope from point A to B (and from C to D at the warehouse location) as depicted in Attachments 1 and 2, ON-SITE ASSEMBLY POINT DIAGRAMS.

STEP 3: Contact the CAS Operator ( ) and verify that the security computer is set up for accountability.

STEP 4: Direct Radiation Protection personnel to set up step-off pad (s) and frisker(s) at point F (as designated in Attachment 1) and to conduct a radiological survey of the area.

STEP 5: Contact the TSC and notify the Security Group Leader that the Assembly Point is prepared for a plant evacuation.

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Pr:c; dura A.2-302

. Rivisicn 2 Page 4 of 8 PART II - OPERATION STEP 1: If the warehouse location is being used, channel all evacuees from the Cold Shop area, through the classroom and into the radiological holding area. Ensure that each person properly inserts his (her) security badge into one of the card readers at point G (see Attachment 1) and that the red light is received after each card.

NOTE: Time is important. Use both readers and do what is necessary to keep the process moving until all evacuees, including the Radiation Protection personnel and yourself, have been processed through the card readers.

STEP 2: If the warehouse l'ocation is being used, contact the TSC and notify the Security Group Leader as soon as the last of the evacuees has been processed.

NOTE: Once the Security Group Leader has been contacted, it is very important to start a sign-in sheet for all persons arriving subsequently at the Assembly Point. Maintain the sign-in process (use Form #5790-107-1) until notified that the accountability procedure is completed.

STEP 3: Direct personnel in the radiological holding area to pass through the control point, using the frisker to detect contamination as they do so.

A Radiation Protection Specialist should be available at the control point to oversee this process. Contact the TSC and notify the REC of any contamination and when the radiological screening is complete'.

STEP 4: Keep all personnel at the Assembly Point unless and until directed otherwise.

STEP 5: If available, direct Radiation Protection personnel to survey, and clear if possible, the radiological holding areas (and also the classroom and south end of the Cold Shop if applicable).

STEP 6: Maintain communications with the TSC. Keep appropriate TSC personnel apprised of status.

STEP 7: Release personnel when so ordered by the Emergency Director and complete the checklist.

REFERENCES

1. Monticello Nuclear Generating Plant Emergency Plan

2. Monticello Nuclear Generating Plant Operations Manual

3. NUREG-0654/ FEMA-REP-1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" ATTACHMENTS

1. On-Site Assembly Point Diagrams g

2. On-Site Assembly Point Diagrams W

3. Te.ephone Listing For Assembly Areas

4. Example of Assembly Point Activation Checklist WP/kk

Procedure A.2-302 Revision 2 Page 5 of 8 ATTACHMENT 1 ab

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WAREHOUSE ASSEMBLY POINT O

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Procedure A.2-302 Revision 2 Page 6 of 8 ATTACHMENT 2 le I

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I DfERGENCY EQUIT'!ENT LOCKER SOI lh I

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Procedura A.2-302

. Rrvision 2

- Page 7 of 8 (G

%Js

)

ATTACHMENT 3 Page 1 of 1 TELEPHONE LISTINGS Primary Assembly Area -------------------------------------

1 i Alternate Assembly Area ----------------------------------- i f

~

Control Room ---------------------------------------------- g:; jib Guard's Station ------------------------------------------- 9 l Technical Support Center Emergency Director -----------------------------------

) l Security Group Leader --------------------------------

g,gjk ,

REC --------------------------------------------------  !

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Operations Support Center O S C C o o rd i n a to r - ------- ----------------------- ------- [3 EEL.iE'fE5[) f Emergency Operations Facility Emergency Manager Of fice & Conference Table ----------

Dose Assessment Area ---------------------------------

l O

RPSS -------------------------------------------------

t i

Technical Support Station ---------------------------- -E4e?""(G

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Count Room -------------------------------------------

Te l e c o py S ta t i o n -- -- - ----- - - --- - -- - -- ---- ---- - -- -- - --

l k+ma WP/kk k

Proc dura A.2-302

. R:visicn 2 Page 8 of 8 ATTACHMENT 4 Form 5790-302-1 Revision 2, 2/02/82 Page 1 of 1 Example of ASSEMBLY POINT ACTIVATION CHECKLIST (For Use With Procedure A.2-302)

1. Assumed the responsibilities of Assembly Point Coordinator.

APC Initials Time Date

2. Security computer ready" for account-ability.

APC Initials Time Date

3. Survey of Assembly Point Area initiated and radiological control point established.

APC Initials Time Date

4. Emergency Director notified that Assembly Point is prepared for -

evacuation.

APC Initials (l k" Time Date

5. If warehouse location is activated, notified Security Group Leader when all evacuees were processed.

APC Initials Time Date

6. Completed radiological screening and so notified REC.

APC Initials Time Date

7. Released Assembly Point personnel on order from Emergency Director.

APC Initials Time Date ,

NOTE: After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for the Emergency Records.

O WP/kk

Proccdure A.2-303

. Revision 2

. Page 1 of 3 Op. Com. Rev. Req'd. Yes X No Q.A. Review Reg'd. Yes No X ALARA Review Reg'd. Yes X No SEARCH AND RESCUE A.2-303 Prepared by: _ o.f ALARA Review: NOld!Ou~ Date 7[z 7k 2_

Reviewed by: (N)///ul[Ju- Q.A. Review: Revision 0 Date 3/26/81 Operations Committee Final Review: Meeting Number //62 Date B/5/62.

Approved by: $ Date 2-10-P2, Op. Com. Results Review: Not Required Mtg. # 949 Date 3/26/81 PURPOSE This procedure provides instructions pertaining to in plant search and rescue operations if required to locate and/or rescue personnel who are unaccounted for during or following an emergency.

CONDITIONS AND PREREQUISITES A. One or more individuals are missing following an evacuation of an affected area, or B. A report has been reraived of personnel trapped and/or disabled within the plant.

O V PRECAUTIONS Permissible exposures incurred during search and rescue operations are governed by A.2-401, " Emergency Exposure Control".

PERSONNEL REQUIREMENTS Emergency Team Leader Emergency Teams ORGANIZATION A. Overall Responsibility - Emergency Director B. In Charge - Emergency Team Leader C. Assistance

1. Emergency Team Members

2. Radiation Protection Group O

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Procedure A.2-303 Revision 2

- Page 2 of 3 RESPONSIBILITIES A. Emergency Director

1. Implement appropriate Emergency Plan Implementing Procedures.

2. Appoint Emergency Team teader.

B. Emergency Team Leader

1. Select Emergency Team Members.

2. Instruct Team Members on probable locations of missing personnel and expected dose rates.

3. Ensure that proper equipment and first aid supplies are obtained to perform necessary action.

C. Emergency Team Members Perform search and rescue.

D. Radiation Protection Group Provide radiological information and emergency exposure control.

DISCUSSION A. If an individual is trapped or disabled it, a high radiation area, the rescue must be performed as expeditiously as possible to minimize the dose to the victim and the doses to the rescue personnel, and to ensure t"at first aid can be provided as soon as possible.

B. In an emergency situation, an exposure of 75 rer.1 to rescue and first aid personnel is appropriate if necessary to save a life. Refer to A.2-401 (Emergency Exposure Control).

C. Rescue of a victim shall take precedence over fire-fighting or damage control ef forts, unless such actions are necessary to ef fect rescue, or to relieve an immediate threat to the lives of other personnel.

D. Rescue of a victim shall take precedence over isolation of steam, hot water under pressure, hydraulic fluids, etc. , unless such isolation is necessary to effect rescue; or if failure to isolate will seriously affect reactor safety or will place the lives of other personnel in immediate danger.

E. Emergency Team Members should be selected from volunteers, as these opera-tions could involve high exposure and risk.

PROCEDURE STEP 1: Upon notification of missing / trapped / disabled individuals, select Team Members and direct Emergency Team in search and rescue operation.

Form 5790-102-5 contains a listing of Plant Personnel with candidates for Emergency Team duty identified.

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Proccdure A.2-303

, Ravision 2

, Page 3 of 3 O STEP 2: Obtain necessary equipment and dosimetry. Don protective clothing V and any respiratory equipment required by the Health Physics Group (RWP). If exposure limit extensions are necessary, refer to Procedure A.2-401, Emergency Exposure Control.

STEP 3: Proceed to the designated search area as directed by the Emergency Director or his designee, while maintaining radio contact.

STEP 4: Provide the following information, as known:

a. Location of victim

b. Extent of injuries

c. Additional assistance required, if necesary

d. Complications affecting rescue STEP 5: Perform search and/or rescue operation as expeditiously as possible.

a. If the indiviaual(s) cannot be moved immediately, first aid should be applied as necessary.

b. If appropriate, move the individual to the closest safe area and apply first aid as necessary.

c. Evaluate the condition of the individual:

(1) If the individual is injured and requires off-site medical treatment, refer to MNGP Operations Manual, Procedure A.5-100. l (2) If the individual has or may have received a biologically significant overexposure, report to Radiological Emergency Coordinator.

STEP 6: Comolete all necessary forms and submit to appropriate group for recording and filing.

REFERENCES

1. Monticello Nuclear Generating Plant Emergency Plan

2. Monticello Nuclear Generating Plant Operations Manual

3. NUREG-0654/ FEMA-REP-1, " Criteria for Preparation and Evaluation of Radio-logical Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" ATTACHMENTS None l

l O

U WP/kk i

l 1

Procedura A.2-405

. Rnvis on 2 i

Page 1 of 6 Op. Com. Rev. Reg'd. Yes X No Q. A. Review Reg'd. Yes No X O

b ALARA Review Req'd. Yes X No RELEASE RATE DETERMINATIONS A.2-405 Prepared by: M/w # ALARA Review: OdOl4 <

• Date / M 2--

Reviewed by: Od/dedd Q.A. Review: Revision 0 Date 3/29/81 Operations Committee Final Review: Meeting Number //o2 Date O/5/Ba Approved by: M_M Date  % -le-R a Op. Com. Results Review: Not Required Mtg. # Y49 Date 3/26/81 PURPOSE This procedure gives guidance and criteria for making release rate determinations for accidental releases from the Monticello Nuclear Generating Plant.

CONDITIONS AND PREREQUISITES An event at the facility has resulted in an unplanned release of radioactivity in excess of normal levels.

DISCUSSION O

() This procedure is for making release rate determinations based on readings from rr.onitors at the point of release. Verification of these detecminations or deter-mination of release rate from an enmonitc.ed source (e.g., turbine building) should be made.

PERSONNEL REQUIREMENTS Radiation Protection Specialist PROCEDURE NOTE: This procedure is divided into four parts based on the point of release:

Reactor Building Vents, Stack, Discharge Canal (Liquid Release), and l Primary Containment.

Determination of Reactor Building Vents Release Rate NOTE: The method used to determine release rate from the Reactor Building -

Vents depends upon the reading of the Reactor Building Vents effluent Monitor. This leads to two cases:

O WP/kk

Procedura A.2-405

. Revision 2

- Page 2 of 6 STEP 1: Case 1 Reactor Building Vent Effluent Monitor Operable

a. Ensure flow and EFF lights are lit on the RBV Monitor and note effluent release rate in pCi/sec (Panel C257 & C258).

STEP 2: Case 2 Reactor Building Vent Effluent Monitor Not Operable CAUTION: Monitor dose rate as you approach plenum (see Attachment 3).

a. Take a direct contact radiation reading on the north side of plenum vent ducts on plenum building roof.

AA

b. Determine the flow from the vents (cfm)

NOTE: Use 120,000 cfm unless flow indicators on 1027' R>. Building are accessible, in which case use a flow rate based on actual readings.

c. Calculate the release rate according to the following formula:

C' Release Rate (pCi/sec) = R/hr x (conversion factor ) x cfm x 472 -

f t -sec A

See RBV Exhaust Conversion Factor Table - Attachment 1.

Determination of Stack Release Rate NOTE: The method used to determine release rate from the Stack depends upon the reading of the Stack Effluent Monitor. This leads to two cases:

STEP 1: Case 1 Stack Effluent Monitor Operable

a. Ensure flow and EFF lights are lit on the Stack Ef fluent Monitors and note effluent release rate in pCi/sec (Panel C257 & C258).

STEP 2: Case 2 Stack Effluent Monitor not operating CAUTION: Stack could be a high radiation area (see Attachment 3).

a. Take a direct contact radiation reading on the stack pipe at a point downstream of the dilution air inlet (reading can be taken with a teletector at a point near the isokinetic sample probe or with any dose rate instrument on the next level up).

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Procedure A.2-405 Ravision 2 Page 3 of 6 O b. Determine flow rate from stack (cfm).

O NOTE: Use 4300 1 100 cfm unless flow indicator in stack sample room is accessible, in which case the actual flow rate should be used.

c. Calculate the release rate according to the following formula:

Release Rate (pCi/sec) = R/hr x (factor ) x cfm x 472 cc-min f t 3-sec

. See Attachment 2 Discharge Canal Release Rate (Liquid Release)

STEP 1: Read both channels of the Discharge Canal Monitors (Control Room panel CO2), and use the highest value for calculation.

STEP 2: Multiply conversion factor of 1.58 x 10 -7 Ci/cc/ cps by cps reading on monitor to arrive at pCi/cc. l STEP 3: Obtain river flow rate in CFS (computer point D504) and multiply by 60 to obtain cfm. l 3

STEP 4: Take pCi/cc value and multiply by 28,320 cc/ft to obtain pCi/ft3 cod i

multiply by the river flow rate in cfm to obtain pCi/ min release

] rate.

Primary Containment Release Rate Determination STEP 1: Go to Apple computer in TSC.

STEP 2: Follow computer instructions posted locally on computer.

REFERENCES

1. Monticello Nuclear Generating Plant Emergency Plan

2. Monticello Nuclear Generating Plant Operations Manual

3. NUREG 0654/ FEMA-REP-1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support -

of Nuclear Power Plants" ATTACHMENTS

1. R8V Exhaust Conversion Factor Table

2. Stack Exhaust Conversion Factor Table

3. Emergency Sample and Measurement Considerations WP/kk

Procedure A.2-405 Revition 2 Page 4 of 6 ATTACHMENT 1 RBV EXHAUST CONVERSION FACTOR TABLE AA Time pCi/cc per R/hr

.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 6.7 (-2)

.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1.2 (-1) i 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1.4 (-1) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 1.8 (-1) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 2.3 (-1) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 3.3 (-1) 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> 5.2 (-1) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 7.0 (-1) 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 8.8 (-1) 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> 1.1 (+0) 7d 1.1 (+0) 14 d 3.0 (+0) 30 d 8.0 (-1) 60 d 2.5 (+0) 120 d 3.C (+1) 180 d 3.9 (+1) 1 yr 3.9 (+1)

AA Time after accident O

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. . _ _ . ~ . - - _ _ _ . . ._ . _.. . . _ _ _ . . . - _ . _ .. - . .... _ _.-.- . ..

5 -Procedure A.2-405 i . Revision 2

. Page 5 of 6 i

l ATTACHMENT 2 A

STACK EXHAUST CONVERSION FACTOR TABLE 1

Time pCi/cc per R/hr i

^ ,

i .1 hr 1.6 '

a

.5 hr 3.2 I hr 4.0 l l

2 hr 5.4

't 4 hr 7.7 8 hr 1.3 (+1)- ,

! 16 hr 2.6 (+1) 24 hr 3.9 (+1) 48 hr 6.5 (+1) i 1

96 hr 7.9 (+1)

! 7d 8.0 (+1)

\

14 d 8.2 (+1)  !

i j 30 d 1.0 (+2)  !

60 d 6.5 (+2) 120 d 1.1 (+3) 180 d 1.1 (+3) 1 yr 1.1 (+3) 4

! Time after accident  ;

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Procedura A.2-405

. R: vision 2

. Page 6 of 6 ATTACHMENT 3 EMERGENCY SAMPLE AND MEASUREMENT CONSIDERATIONS INTRODUCTION In the event of certain postulated accidents, it is possible that effluent release rates would exceed the upper limits of installed monitors and that access to normal sample points for ef fluents, coolant and containment atmosphere may be encumbered by extremely high radiation fields. The purpose of this guidance is to preclude any unnecessary exposure resulting from the execution of such emergency sampling and measurement activities.

ESTIMATING RBV RELEASE RATE THROUGH DIRECT RADIATION READING ON PLENUM DUCT The procedure for quantifying the plenum release rate depends on taking a contact dose rate on the plenum duct which is located on the roof of the plenum room.

To get into a position to take this reading, one must climb first to the admini-stration building roof and then up the side of the reactor building to the area of the air intake structure. From the time one reaches the administration building roof, that person should be aware of possible high radiation fields.

The main source is expected to be the plenum duct work and stack. The method that seems to be most economical in terms of exposure involves moving quickly to the reactor building ladder, climbing to the next level and then transferring to the turbine building roof. Once on the turbine building roof, one can make a wide arc, keeping maximum distance from the plenum stac.k and then make a direct approach to the designated point.

One should also consider tt.e instrument to be used. One opticn is an irestrument with a telescoping probe such as a teletector. If such an instrument is unavail-able, and more readings are anticipated, an instrument that has the capability of remote readout, such as the radgun can be used. The detet. tor position could be positioned initially and subsequent readings could be made from 25' feet away. Lastly, a simple hand-held instrument such as a radector could be positioned by remote means and subsequent readings could be made with binoculars (and flashlight if necessary).

ESTIMATING STACK RELEASE RATE THROUGH DIRECT RADIATION READING ON STACK PIPE The procedure for quantifying the stack release rate depends on taking a contact dose rate on the stack pipe at a point downstream of the dilution air inlet.

The stack area could be a high radiation area, especially in areas where there is no shielding for the stack pipe. The preferred method would seem to be one using a teletector which could be inserted through the penetration for the iso '

kinetic sample probe. From this location, one could obtain the required read-ings while utilizing the installed shielding. The other option is to climb up the outside of the stack to the first landing. At this level, the stack pipe is not shielded and caution must be exercised.

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Procedura A.2-406

, Ravision 5

. Page 1 of 17 Op. Com. Rev. Reg'd. Yes X No Q.A. Review Req'd. Yes No X ALARA Review Req'd. Yes No X OFF-SITE DOSE PROJECTION A.2-406 REVIEWANDAPPROVAL7 Prepared by: /M ALARA Review: Revision 0- Date 3/29/81 Reviewed by: [ [ 3 j % Q,A. Review:

Revision 0 Date 3/29/81 OperationsCommitte[FidlReview: Meeting Number //o it Date ir/4/22.

Approved by: dN Date @-l o -h Op. Com. Results Review: Not Required Mtg.# 949 Date 3/26/81 PURPOSE The purpose of this procedure is to provide' guidance and instructions for estimat-ing of f-site doses resulting from an unplanned and/or abnormal airborne release of radioactive material. The main body of this procedure identifies criteria and guidelines for dose projection, such as how often it should be performed, and which dose projection method to use. The attachments to this procedure provide instructions for performing dose projection using the various methods. Alternate methods are provided to cover possible contingencies such as offscale monitors, e inoperative instrumentation, etc.

l CONDITIONS AND PREREQUISITES A. An emergency condition has been declared at Monticello Nuclear Generating Plant as provided in the. Emergency Plan.

8. An airborne release of radioactive materials in excess of environmental technical specifications has occurred, !s suspected to have occurred, or is imminent.

PRECAUTIONS

! Precautions are verified in the text of the applicable attacnment(s)

ORGANIZATION Responsible- Radiological Emergency Coordinator In-Charge - Of f-Site Dose Assessment and Chemistry Section Leader Assistance - Radiation Protection Specialist DISCUSSION A. General Applicability The region surrounding the plant site is divided into sixteen 22 1/2 degree sectors. The regions of interest extend from the effluent release points out to fifty miles in each sector. Contained within the regions of interest are special locations of interest. The special locations are the site WP/kk

Procedure A.2-406

. Rsvision 5 Page 2 of 17 boundary and the nearest receptor. The site boundary and the nearest recept -

locations differ for each sector.

B. Dose Projection Methods This procedure provides 2 different methods for performing dose projections.

The method (s) used will depend on the availability of release and meteoro-logy information and the operability of computers. They appear as attach-ments to this procedure with Attachment I being the most preferred method and Attachment 2 being the least preferred.

1. Dose Projection By Computer (MODCOM)

The Monticello Off-Site Dose Computation System (MODCOM) is a computerized atmospheric dispersion and radiolcgical dose assessment software system.

The system is specific for the Molticello Nuclear Generating Plant and is structured in the form of an executive nain program (MODCOM) and several subprograms. The software system is coded in a high level interpretive language called C.L.A.S.S.. The software runs on Digital Equipment Corporation computer systems which are located at the plant site.

Data required for input to the software system are: (1) meteorlogical infor-mation acquired from the meteorological tower (MET Tower) S.E.D.A.R. computer system, and, (2) plant stack and R.B. ventilation radioactive airborne effluents release rate information acquired from effluents monitors or dose rate readings converted to release rates. Wind direction data is used to determine tha correct sector. Wind speed dat1 is used to determine the plume dispersion parameters and maximum plume distance. Temperature difference values are used to determine the plume dispersion parameters.

The plume is assumed to completely fill the sector in which it is located.

Release rate data is combined with dispersion data to yield dose rate data. The release rate data is input in the form of pCi/sec for noble gases, iodines, and particulates for the plant stack and Reactor Building ventilation release points. Whole body and thyroid dose factors as well as default nuclide concentration ratios are contained in system mass storage files for use in calculating dose rates. Data is accumulated into the program at 15, 30, or 60 minute intervals. The program computes dose rates at the site boundary, the nearest receptor, and out to the maximum plume distance which may be anywhere from one mile to 10 miles in one mile increments.

The dose rate values are reported in mrem / hour. The dose rate values are cnnverted to an accumulated dose for that period. The dose values are then stored according to sector for the whole body and thyreid. During the course of an accident, dose values are accumulated in several sectors, as the stack plume and R.8. vents plume are sometimes not in the same sector, and wind direction shifts will cause the accumulated doses to be O

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Procedure A.2-406 Rnvision 5 Page 3 of 17 placed into several different sectors over a period of time. Accumulated

,9 dose information may be extracted from storage and read out according to V sector, or a specific distance from the plant for all sectors. Accumulated dose information is reported in " mrem".

NOTE: Thyroid doses are calculated for the child thyroid.

2. Dose Projection By Hand Calculation l This method calculates the whole body and thyroid doses in the event that the computer systems are not available.

PROCEDURE STEP 1: When directed by the Radiological Emergency Coordinator or the Emergency Director, perform off-site dose projections in accordance with Attachments 1, 2 or 3. Attachment 1 is the most preferred method and Attachment 2 l

[ is the least preferred method, l

STEP 2: Continue doing dose projections until otherwise directed by the Radiological Emergency Coordinator or Emergency Director.

PEFERENCES

1. Monticello Nuclear Generating Plant Emergency Plan

2. NUP.EG-0654/ FEMA-RFP-1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans for Preparedness in Support of Nuclear Power Plants" ATTACHMENTS

1. Ocse Projection by Computse (MODC0iG

2. Dose Projection by Hand Calculation

3. Example of Off-Site Dose Projection Worksheet

4. Obtaining Meteorological Data From General Office Eclipse Computer System

5. Obtaining Meteorological Data From Weather Information Service

6. Program Example WP/kk

Procedure A.2-406

. R: vision 5

. Page 4 of 17 ATTACHMENT 1 DOSE PROJECTION BY COMPUTER (MODCOM)

PREREQUISITES

1. Proceed to the Body Count Room and place the computer system in the l timesharing mode (TYPE " Control-C", then RUN TSG0).

2. Proceed to the TSC and turn on the MET Tower Data Terminal and the Plant l Computer CRTs, if this has not already been done. Release and meteorological data must be available for this method.

PROCEDURE STEP 1: Turn on the dose projection printer and depress the "300 BAUD" button.

Ensure that the terminal is on line. Depress the return key and the terminal will print:

TSX Version CIO7E (Date-Time)

STEP 2: Type in "RUN CLASS" and press carriage return. The terminal will respond with:

CLASS V04.24-RT (DATE)

NOTE: Systen operation may be verified by running program and usirig information from Attachment 6.

STEP 3: Type in "RUN M90COM" and press carriage return. The terminal will respond with:

INITIAL EVALUATION ? :

STEP 4: Respond as follows:

a. If this is the initial evaluation, type in "Y" and press carriage return. The terminal will respond with a list of the available options in the MODCOM program ending with:

PLEASE ENTER THE OPTION YOU DESIRE:

CAUTION: Do not respond with "Y" unless this is the first post-release execution of this procedure, as all stored data will be lost.

b. If this is a subsequent evaluation, type in "N" and press carriage return. The terminal will respond with:

PLEASE ENTER THE OPTION YOU DESIRE:

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Procedure A.2-406 Ravision 5 Page 5 of 17 ATTACHMENT 1 (Cont'd.)

s/ Page 2 of 4 STEP 5: Select one of the following options:

OPTION DESCRIPTION 1 PERFORM TYPICAL DOSE RATE CALCULATION 2 LIST ACCUMULATED DOSES FOR ANY SECTOR (A-R) 3 SEARCH ALL SECTORS FOR HIGHEST DOSE AND REPORT DOSE DATA 4 PRINT ALL SECTOR DOSES (A-R) AT A SPECIFIED DISTANCE 5 UPDATE THE NUCLIDE DATA FILE 6 PERFORM DOSE PROJECTION (NO DATA STORAGE) 7 LIST ACCUMULATED POPULATION DOSES FOR ANY SECTOR (A-R) 8 LIST ACCUMULATED GROUND CONTAMINATION FOR ANY SECTOR (A-R) 9 STOP PROGRAM EXECUTION and proceed to the appropriate portion of this procedure.

NOTE: Option 1 should be used unless specific information available through one of the other options is sought.

STEP 6: PERFORM TYPICAL DOSE RATE CALCULATION:

a. Type in "1" and press carriage return. The terminal will respond by requesting that you enter current date information. Type in this information as it is requested. The terminal will then respond with:

PLEASE ENTER THE FOLLOWING METEOROLOGICAL DATA FROM THE SEDAR COMPUTER PRINT 0UT:

NOTE: If the meteorological tower met data printer is unavail-able, refer to Attachment 4 and enter starting and ending i day and time data such that 15 minute summary data is printed.

If the meteorological tower met system data is unavail-able, refer to Attachment 5 and use the St. Cloud 1 reporting station data for stability class, windspeed and wind direction data. Enter a Zero for the requested day and time information.

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Proc: dure A.2-406 R: vision 5 Page 6 of 17 ATTACHMENT 1 (Cont'd.)

PLEASE ENTER THE FOLLOWING EFFLUENTS RELEASE RATE DATA:

The terminal will request specific numerical information. Obtain j this information from the Plant Computer CRTs and type it in as requested. If release rate data is not available, refer to Procedure A.2-405.

NOTE: During the early stages of an accident when Iodine release rates are not available, enter Iodine release rate values corresponding to about 2% of that release points noble gas release rate. This should be done until grab samples have been taken and analyzed. Grab samples should be taken and anlayzed as soon as possible.

b. The terminal will respond with a printout of off-site dose projections for the affected sector (s) from the Site Boundary to a distance of 10 miles. Communicate this information to the Radiological Emergency Coordinator.

c. The terminal will then print:

PLEASE ENTER THE OPTION (0U DESIRE:

d. Type in the option number per STEP 5 or STEP 9.

NOTE: MET data is updated every 15 minutes and that should be the frequency with which Option 1 is run during an emergency condition with an airborne release. You should continue to update dose rate data every 15 minutes until the Radiological Emergency Coordinator directs other-wise.

STEP 7

LIST ACCUMULATED DOSES FOR ANY SECTOR

a. Type in "2" and press carriage return. The terminal will respond

! with:

ENTER THE SECTOR (A-R) FOR WHICH YOU WANT THE ACCUMULATED DOSES REPORTED.

SECTOR:

i 1

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1 Procedure A.2-406  !

, Ravision 5 I

. Page 7 of 17 ATTACHMENT 1 (Cont'd.) 1 Page 4 of 4

b. Type in the sector letter (A-R). The terminal-will ask you if you wish to perform dose projection calculations. Answer Y or N, then the terminal will respond with a printout of the accumulated doses for the affected sector from the Site Boundary to a distance of 10 miles. Communicate this information to the Radiological j Emergency Coordinator. '

c. The terminal will then print:

PLEASE ENTER THE OPTION YOU DESIRE:

d. Type in the option number per STEP 5 or STEP 9.

STEP 8: SEARCH ALL SECTORS FOR HIGHEST DOSE AND REPORT DOSE DATA

a. Type in "3" and press carriage return. The terminal will respond with a printout of the accumulated dose values to the highest sector (s) as well as a list of the sectors where accumulated whole body or thyroid doses exceeded pre programmed limits.

Communicate this information to the Radiological Emergency Coordinator.

b. The ter:ninal will then print:

O b PLEASE ENTER THE OPTION YOU DESIRE:

c. Type in the option numbers per STEP 5 or STEP 9.

STEP 9: Should it be desirable to cease dose projection activities for extended periods of time (with the concurrence of the Radiological Emergency Coordinator), when the terminal prints:

PLEASE ENTER THE OPTION YOU DESIRE:

Type in "9" and press carriage return. You may subsequently re-enter the program by typing in "RUN MODCOM".

STEP 10 Upon receiving instructions from the Radiological Emergency Coordinator to secure from dose projection activities, turn off all equipment and ensure that all data is appropriately filed.

e)

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Procedura A.2-406 R; vision 5 Pege 8 of 17 ATTACHf1ENT 2 '

Page 1 of 4 DOSE PROJECTION BY HAND CALCULATION EQUIPMENT REQUIRED

1. Calculator (with scientific notation capability)

2. Supply of 0FF-SITE DOSE RATE PROJECTION WORKSHEET Forms (TSC),

Form 5790-406-4 (Attachment 4)

PROCEDURE STEP 1: In the INPUT DATA section of the worksheet, enter the date and time for which this projection will be made.

STEP 2: Enter the TIME AFTER REACTOR TRIP value. This is the elapsed time from the reactor trip to the time recorded in STEP 1. If there has not been a reactor trip, enter ZERO.

STEP 3: Determine the necessary meteorological parameters and record as indicated on the worksheet. This data should be taken from the meteorological tower printer. If the printer is unavailable, refer to Attachment 4.

NOTE: If eneteorological tower met data printer is unavailable, refer to Attachment 4 and enter starting and ending day and tima data such that 15 minute summary data is printed.

If the meteorological tower met system data is unavailable, refer to Attachment 5 and use the St. Cloud reporting station data for stability class, windspeed and wind direction data.

Enter a Zero for the requested day and time information and enter requested data.

a. R8 Vent Stability Class - Divide the value for Dfl by 100, paying attention to whether the value is positive or negative. Use the result to enter Table I. Record the class designation.

b. Stack Stability Class - Divide the value for DT2 by 100, paying attention to whether the value is positive or negative. Use the result to enter Table I. Record the class designation.

c. RB Vent Windspeed - Record the windspeed at the 33 feet level (use 1 mph when indication is zero).

d. Stack Windspeed - Record the windspeed at the 330 feet level (use 1 mph when indication is zero).

e. Stack Wind Direction - Record the wind direction at the 330 feet level. (If value is greater than 360, subtract 360 before recording.)

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Procedura A.2-406

, Revision 5

. Page 9 of 17 ATTACHMENT 2 (Cont'd.)

Page 2 of 4

. Stability Class RB Vent (DT1/100) Stack (DT2/100)

A Less than -0.62 Less than -1.71 B -0.62 to -0.56 -1.71 to -1.53 C -0.55 to -0.49 -1.52 to -1.35 0 -0.48 to -0.16 -1.34 to -0.45 E -0.15 to +0.49 -0.44 to +1.35 F +0.50 to +1.31 +1.36 to +3.60 i G** Greater than +1.31 Greater than +3.60

• • Stability Class G is not to be used. (Ref: Letter of 3/9/81 from certified consulting meteorologist to Bert Clark.) Use Class F when G is indicated.

STEP 4: Determine and record the SECTOR designation (A-R). Use the 330 feet wind direction and Table II to find the letter designation for the area directly downwind from the plant.

NOTE: If the wind speed indicates zero, use Sector designation "L" (most critical sector based on nearest receptor).

TABLE II Wind Direction Sector 168.75 to 191.25 A 191.25 to 213.75 B 213.75 to 236.25 C 236.25 to 258.75 0 258.75 to 281.25 E 281.25 to 303.75 F 303.75 to 326.25 G 325.25 to 348.75 H 348.75 to 11.25 J 11.25 to 33.75 K 33.75 to 56.25 L 56.25 to 78.75 M 78.75 to 101.25 N 101.25 to 123.75 P 123.75 to 146.25 Q f

146.25 to 168.75 R STEP 5: From Table III select and record the XU/Q values as required.

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Proceduro A.2-406

- R: vision 5 Page 10 of 17 I

ATTACHMENT 2 (Cont'd.)

Page 3 of 4

, TABLE III R.B. VENTS XU/Q Stab. Class A-B-C D E F-G Distance SB 6.4E-5 9.4E-5 1.2E-4 2.1E-4 NR 6.4E-5 9.4E-5 1.2E-4 2.1E-4 1 1.9E-5 4.3E-5 5.8E-5 1.9E-4 2 5.7E-6 1.7E-5 2.6E-5 1.0E-4 3 2.9E-6 1.0E-5 1.8E-5 7.4E-5 4 1.9E-6 7.2E-6 1.3E-5 5.9E-5 5 1.3E-6 5.1E-6 9.9E-6 4.8E-5 10 4.6E-7 2.1E-6 4.6E-6 2.6E-5 STACK XU/Q Stab. Class A-B-C D E F-G Distance SB 2.74-4 4.03E-7 6.]7E-10 2.54E-18 NR 2.74-4 4.03E-7 6.17E-10 2.5E-18 1 1.2E-5 6.4E-6 1.6E-6 1.1E-9 2 5.0E-6 9.0E-6 7.6E-6 4.4E-7 3 2.7E-6 6.7E-6 6.4E 6 1.1E-6 4 1.8E-6 5.4E-6 6.2E-6 1.7E-6 5 1.3E-6 4.2E-6 5.4E-5 2.1E-6 10 4.5E-7 2.0E-6 3.6E-6 3.2E-6 STEP 6: From Table IV, determine and record the Non!e Gases Factor and the Iodines Factor as appropriate for the elapsed time value previously recorded.

TABLE IV Elapsed Time (Hours) Noble Gases Iodines From To Factor Factor 0.00 0.49 6.49E-01 254 0.50 0.99 5.48E-01 282 1.00 1.99 4.06E-01 329 2.00 3.99 3.43E-01 398 4.00 7.99 2.93E-01 485 8.00 15.99 1.65E-01 607 16.00 23.99 8.70E-02 705 24.00 47.99 6.10E-02 923 48.00 95.99 3.90E-02 1117 96.00 167.99 3.30E-02 1270 168.00 335.99 3.30E-02 1280 336.00 719.99 3.20E-02 1280 720.00 1439.99 2.60E-02 1280 1440.00 Beyond 3.60E-03 1280 WP/kk

Procedure A.2-406 Revision 5 Page 11 of 17 ATTACHMENT 2 (Cont'd.) l i

STEP 7: Record the release rates (pCi/sec) for t5e gas and iodine portions of the stack and vent effluents. The gas portion release rates may be obtained directly from' effluent monitor readings. If direct monitor readings are unavailable, obtain release rates from procedure A.2-405 (Release Rate Determination). The iodine portions will be determined by Radiation Protection Group personnel through actual samples. If sample analysis data is not available, use a value of 2% of the noble gas release rate values.

STEP 8: Using the values recorded in the INPUT DATA section, complete calcula-tions for the location of interest as required.

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-- -- ,- , - - - .-,,n-- , , , , , ,.,,. , ,. -

l Procedure A.2-406 Revision 5 Page 12 of 17 ATTACHMENT 3 ,

Revision 1, 05/10/82 Page 1 of 1 Example of 0FF-SITE DOSE RATE PROJECTION WORKSHEET (For use with Procedure A.2-406, Attachment 3)

INPUT DATA Time Date Time After Rear: tor Trip hours Stability Class: RB Vent Stack Windspeed: RB Vent mph (c) Stack mph (c)

Wind Direction: Sector Location (S.B., N.R., or distance):

XU/Q Value for Location:

Noble Gas Release Rate pCi/sec: (a)

Noble Gas Fac'or: _ (b)

Iodines Release Rate pCi/sec: (d)

Iodines Factor: (e)

WHOLE BODY DOSE RATE Multiply (a) x (b) x XU/Q x (C) x .447: mrem /hr THYROID DOSE RATE Multiply (d) x (e) x XU/Q x (C) x .447: committed mrem / hour of exposure.

REVIEW AND APPROVAL Completed by: / Date Reviewed by: Date Radiological Emergency Coordinator NOTE: After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for Emergency Records.

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Procsdure A.2-406

, Rsvision 5 '

~ Page 13 of 17

- ATTACHMENT 4 ,

{ ,. ,

S* ,

(V'. . ,

-Ohtaining .41eteorological Date- From Gen tral Office Eclipse Computer System iJ f e; (READ ALL INSTRUCTIONS CA'IEFULLY BEFORE STARTING)

,N STEP 1 Turn terminal on (back right of terminal).

• Set terminal to MED Speed. '

Set terminal to full duplex, modem set to full duplex.

Set all caps key to ON.

~

y[

Depress on-line butt,on. ,

STEP 2 Dial , (if no answer use ') .

When tone is heard,, place phone in termiral coupler wit.h the cord to the-rear. Green. light.cn coupler in 5-15 seconds.

STEP 3 You will see the following: .

i

• • • • NORTHERN STATES POWER / TYPE NEV-LINE TO BEGIN LOGGING ON **** *

~-

.

9 ,

STEP 4 Type: RETURN - ,

STEP S You will then see the follo'w'ing: ,,

) ', ~

USERNAME: '

STEP 6 Type: MONTI.SEDAR

• STEP 7 See---PASSWORD:

STEP 8 Type: MONTI.SEDAR '

(note password will not print)

STEP 9 System will display the current time in'JULIAN form.

STEP 10 System will ask for beginning and ending time in JULIAN form, enter data with NO SPACES.

NOTE: Report is formatted by your entiy.

(8200DHEMM) ------- will give 15 minute sampler '

(82DDDHH) ------- will give hourly summaries (8200D) ------- will give daily summaries (Data is only available,for the current day starting at 0200.~)

STEP 11 The report will take several minutes to print out', there will be several bits of meaningless information printed after which the report will be printed.

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Proc:durs A.2-406

. R: vision 5

. Page 14 of 17 ATTACHMENT 5 PROCEDURE FOR USE OF THE WEATHER INFORMATION SERVICE O

EQUIPMENT: Western Union Terminal, Telephone and Accoustic Coupler

1. Turn terminal on (back right of terminal).

Set terminal to MED Speed.

Set terminal to full duplex, modem set to full duplex.

Set all caps key to ON.

Depress on-line button.

2. Dial When tone is heard, place phone in terminal coupler with the cord to the rear. Green light on coupler in 5-15 seconds.

NOTE: If no green light, hang-up and re-do STEP 2.

OPERATOR ACTION PRINTER OUTPUT

3. Press return twice. TELENET TERMINAL =

4. Type "01" Press return @

5. Type "C 617133" Press return. 617 1338 CONNECTED

6. Press return. PLEASE LOG IN

7. Type "LOGIN NSM".

Press return. PASSWORD

8. Type " POWER".

Press return. LOGGED INTO WEATHER SERVICES -------

+

+ Indicates computer awaiting instructions.

9. Type"MONT".

Press return.

10. When printout is completed type " LOG 0UT".

Press return.

When computer prints out that it is disconnected immediately hang-up phone.

NOTE: Use this service only as needed.

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Procedure A.2-406

. Ravision 5

. Page 15 of 17 ATTACHMENT 6-

/ \

CLASS V04.24.24-RT U 16-NOV-77 SYSTEM VERIFICATION EXAMPLE

• RUN MODCOM INITIAL EVALUATION ? " YES ARE YOU SURE ? (IF SO ANSWER YES)  : YES FREQUENCY AT WHICH YOU WISH TO PERFORM COMPUTATIONS (15,30,0R 60 MINUTES) : 15 THE AVAILABLE OPTIONS ARE AS FOLLOWS:

OPTION DESCRIPTION 1 PERFORM TYPICAL DOSE RATE CALCULATION 2 LIST ACCUMULATED DOSES FOR ANY SECTOR (A-R) 3 SEARCH ALL SECTORS FOR HIGHEST DOSE AND REPORT DOSE DATA 4 PRINT ALL SECTOR DOSES (A-R) AT A SPECIFIED DISTANCE 5 UPDATE THE NUCLIDE DATA FILE 6 PERFORM DOSE PROJECTION (N0 DATA STORAGE) 7 LIST ACCUMULATED POPULATION DOSES FOR ANY SECTOR (A-R) 8 LIST ACCUMULATED GROUND CONTAMINATION FOR ANY SECTOR (A-FJs 9 STOP PROGRAM EXECUTION PLEASE ENTER THE OPTION YOU DESIRE: _6 THIS IS EVALUATION # 1 PLEASE ENTER THE FOLLOWING :

CURRENT YEAR 1982 CURRENT MONTH OF YEAR (1-12) : 07 CURRENT DAY OF MONTH (1-31) : y PLEASE ENTER THE FOLLOWING METEOROLOGICAL DATA FROM SEDAR COMPUTER PRINTOUT :

DAY AND TIME ( 7 DIGIT NUMBER )  : 2090830 33' WINDSPEED  : 8 330' WINDSPEED  : 5 33' WIND DIRECTION  : 337 330' WIND DIRECTION  : 6 DT1 (VALUE MAY BE NEGATIVE)  : 743 DT2 (VALUE MAY BE NEGATIVE)  : -76 PLEASE ENTER THE FOLLOWING tFFLUENTS RELEASE RATE DATA :

STACK GAS pCI/SEC.  : 1.0E7 STACK 10 DINES pCI/SEC.  : 2.0E5 STACK PARTICULATES pCI/SEC.  : 1.0E4 (S R.B.V. GAS pCI/SEC.  : 1.0E7

() R.B.V. 10 DINES pCI/SEC.  : 2.0E5 R.B.V. PARTICULATES pCi/SEC.  : 1.0E4 WP/kk

Procedurs A.2-406 R: vision 5 Page 16 of 17 ATTACHMENT 6 (Cont'd.)

MONTICELLO NUCLEAR GENERATING PLANT OFFSITE DOSE RATE COMPUTATIONS 7-28-82 0830 STACK SECTOR = J S. VENTS SECTOR = H SSE STACK WINDSPEED = 5 MPH, VENTS WINDSPEED = 8 MPH MAX PLUME DISTANCE = 2 MILES.

STACK STABILITY CLASS = 0. VENTS STABILITY CLASS = D N0 STACK FUMIGATION THE CALCULATED WHOLE BODY DOSE RATE VALUES ARE IN MREM / HOUR.

THE CALCULATED THYROID DOSE RATE VALUES ARE COMMITTED MREM PER HOUR OF EXPOSURE.

STACK STACK STACK EST'D VENTS VENTS W. 800. W.80D. THYROID PLUME W.B00. THYROID MREM /HR MREM /HR MREM /HR ARRIV MREM /HR MREM /HR FINITE SEMINF S. B. 9.7 5.33E-04 4.92E-03 8:32 4.51E+02 3.64E+03 N. R. 7.3 0.2 2.4 8:36 96. 1.05E+03 1 MI 5.0 9.1 1.46E+02 8:37 56. 7.52E+02 2 MI 2.8 8.5 1.78E+02 8:45 16. 2.66E+02 3 MI 1.9 5.9 1.54E+02 8:52 7. 5 1.45E+02 4 MI 1. 2 3.7 1.18E+02 9: 0 4.2 95.

5 MI 0. 7 2.3 90. 9: 7 2. 7 68.

6 MI 0.5 1.4 72. 9:15 1. 8 52.

7 MI 0.3 0.9 60. 9:22 1. 2 42. l I 8 MI 0.2 0.5 50. 9:30 0.8 34.

9 MI 0.1 0.3 43. 9:37 0.6 29.

10MI 9.90E-02 0.2 37. 9:45 0.4 25.

STACK STACK VENTS VENTS PLUME X/Q PLUME X/Q WIDTH SEC/M3 WIDTH SEC/M3 METERS METERS S.B 1.72E+02 1.10E-10 1.87E+02 8.11E-05 N.R. 2.51E+02 5.33E-08 4.05E+02 2.34E-05 1 MI 4.95E+02 3.25E-06 4.95E+02 1.68E-05 2 MI 9.26E+02 3.96E-06 9.26E+02 5.92E-06 3 MI 1.34E+03 3.43E-06 1.34E+03 3.24E-06 4 MI 1.73E+03 2.64E-06 1.73E+03 2.12E-06 5 MI 2.12E+03 2.01E-06 2.12E+03 1.52E-06 6 MI 2.50E+03 1.60E-06 2.50E+03 1.17E-06 7 MI 2.87E-03 1.33E-06 2.87E+03 9.30E-07 8 MI 3.24E+03 1.11E-06 3.24E+03 7.65E-07 9 MI 3.60E+03 9.48E-07 3.60E+03 6.45E-07 10MI 3.96E+03 8.21E-07 3.96E+03 5.53E-07  ;

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4 Proceduro A.2-406 R vision 5

. Page 17 of 17 ATTACHMENT 6 (Cont'd.)

ammannan=5z************************a******************************************

NOTE TO SHIFT SUPERVISOR OR R.E.C.

WHOLE BODY PROTECTIVE ACTION GUIDELINE = 1000 MREM.

THYROID PROTECTION ACTION GUIDELINE = 5000 MREM.

SECTION J S SECTOR H SSE DISTANCE HOURS EST'O HOURS TO PLUME TO REACH ARRIVAL REACH A PAG TIME A PAG 5.B. 1.03E+02 8:32 1.4 N. R. 1.37E+02 8:36 4.8 j 1 MI 34. 8:37 6.7 .

! 2 MI 28. 8:45 19.  !

3 MI 33 8:52 34.

4 MI 42. 9: 0 53.

5 MI 55. 9: 7 73.

6 MI 70. 9:15 96.

f-~g 7 MI 84. 9:22 1.20E+02

- 8 MI 1.00E+02 9:30 1.46E+02 9 MIN 1.18E+02 9:37 1.73E+02 10 MIN 1.36E+02 9:45 2.02E+02 INITIATE EMERGENCY PROCEDURE A.2-105, ATTACHMENT 2.

RECOMMEND PROTECTIVE ACTION FOR SECTOR H SSE ,

PLEASE ENTER THE OPTION YOU DESIRE : 9 i

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Procedure-A.2-407 1 . Revision 2 Page 1 of 11 Op. Com. Rev. Req'd. Yes X No 4

Q.A. Review Reg'd. Yes No X h ALARA Review Req'd. Yes X No

, PERSONNEL AND VEllICLE MONITORING AND DECONTAMINATION t I A.2-407 Prepared by: / w b ALARA Review: hNk ' o.u . Date 0 /.2-Reviewed by: [hd/44h[deas, Q.A. Review: R. L. Scheinost Date 3/29/81 Operations Committee Final Review: Meeting Number / t?"4 "4 Date c,-/O.?0?

, Approved by: kNU(LAA Da te 9 81, s-

.- as ,

! Op. Com. Results Review: Not Required Mtg. # 949 Date 3/26/81 i

PURPOSE The purpose of this procedure is to specify requirements, methods, action levels and documentation for survey of personnel and vehicles during an evacuation. This is a total rewrite.

CONDITIONS AND PREREQUISITES 1 A. An evacuation is underway as per A.2-301, " Emergency Evacuation" or i

B. The Radiological Emergency Coordinator or other senior radiation protection individual has directed that appropriate sections of this procedure be implemented,.and C. The reasons for evacuation are radiological in nature, e.g., there is cause to suspect contamination of personnel / vehicles.

1 PRECAUTIONS A. The safety of personnel shall take precedence over the monitoring of personnel and vehicles for radiation / contamination control purposes.

i Monitoring of personnel and/or vehicles shall be terminated (or not  ;

implemented in the first place) if such monitoring is known or suspected to be increasing the hazard to personnel during evacuation.

B. If any personnel are injured, or are suspected to have received a biologically

significant dose (greater than 25 rem whole body) report to Radiological Emergency Coordinator.

j C. Monitoring stations should be selected and monitoring operations should be conducted in such a manner as to maintain personnel exposures as low as is i

reasonably achievable.

D. Personnel monitoring beyond normal frisking should be performed by qualified radiation protection personnel.

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a Procedure A.2-407

. Revision 2

. Page 2 of 11 PERSONNEL REQUIREMENTS Emergency Director - overall responsibility Radiological Emergency Coordinator - in charge Radiation Protection Specialist procedure implementation DISCUSSION Evacuation may be grouped into three general types of procedures: Local, Plant and Site Evacuations, as per A.2-301, " Emergency Evacuation". For dite Evacuations personnel and vehicle monitoring and decontamination will be

, performed, if the EOF is activated, by EOF personnel per EPIP 1.1.16.

PROCEDURE A. Local Evacuation NOTE: Evacuated personnel should be directed to the monitoring and decontamination facilities at Access Control, located in the basement of the Administration Building. If these facilities are not accessible, an alternate location will be specified by the Emergency Director / REC.

STEP 1 Monitor personnel as per Attachment 1.

NOTE: If practicable, evacuated personnel should be passed through a portal monitor prior to frisking.

STEP 2 If conditions permit, an immediate attempt will be made to redace to below limits any contamination detected on the person of an individual as per Attachment 3. If contamination is coin-cident with injury, procedure A.5-100 will t'e followed.

B. Plant Evacuation NOTE: Evacuated personnel should be directed to monitoring and decon-l tamination facilities at one of the assembly points. Personnel

! will be directed to the appropriate assembly point by the Emergency Director.

STEP 1 Monitor personnel as per Attachment 1.

NOTE: If practicable, evacuated personnel should be passed through a portal monitor prior to frisking.

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Procedure A.2-407 Revision 2

Page 3 of 11

') S{KP 2 If conditions permit, an immediate attempt will be made to reduce to below limits any contamination detected on the person of an individual as per Attachment 3. If contamination is coincident

with injury procedure A.5-100 will be followed.

STEP 3 If a radioactive release has taken place or is-taking place which could result in the contamination of vehicles, personnel should be directed to take their vehicles to a monitoring and decontamination facility.

Vehicles should be monitored per Attachment 2.

, STEP 4 If conditions permit decontamination of vehicles, decontamination l should be performed per Attachment 4.

C. Site Evacuation NOTE: Personnel evacuated from the site under these conditions may not have adequate time for contamination surveys onsite. It is likely that all non-essential, contractor and visiting personnel will have already been evacuated. The personnel involved should be plant staff. They may have passed through a frisking station or a portal monitor prior to entering their vehicle. However, the potential for recontamination enroute to their vehicles exists.

The vehicles should be routed to the Main Access Road or the West access Road, depending on the direction of the plume. Personnel will be directed to a monitoring and decontamination facility offsite. The EOF would normally be activated by the time a site i evacuation would be declared and EOF personnel would perform personnel and vehicle monitoring and decontamination per EPIP 1.1.16. However the possibility does exist that the EOF may not yet be manned in which case Plant Staff HP's will be required to perform monitoring and decontamination of personnel and vehicles.

i STEP 1 Monitor personnel as per Attachment 1.

STEP 2 Attempt personnel decontamination if necessary per Attachment 3.

If contamination is coincident with injury procedure A.5-100 will be followed.

STEP 3 Monitor vehicles per Attachment 2.

l STEP 4 Attempt vehicle decontamination if necessary per Attachment 4.

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Procedure A.2-407 Revision 2 Page 4 of 11 ATTACHMENT 1 PERSONNEL MONITORING NOTE- Personnel monitoring takes precedence over all other monitoring require-ments. Guidelines expressed below should be followed for personnel monitoring.

Monitoring teams should dress in appropriate protective clothing.

3 STEP 1 Using a RM-14 with a 2" GM pancake probe (or equivalent instrumentation) quickly scan evacuees for contamination.

STEP 2 Segregate those personnel identified in Step 2 into three groups; highly contaminated () 5000 cpm), contaminated (> 100 cpm) and non-contaminaced (( 100 cpm). Non-contaminated personnel may be released immediately and should be directed to proceed to their homes and take a shower.

STEP 3 For highly contaminated personnel proceed as follows:

a. Initiate Whole Body Survey Form (Figure 1) for each contaminated person scanned.

b. Carefully scan personnel. If contamination appears to be confined to clothing, have the personnel carefully strip contaminated clothing and rescan. Pay particular attention to nose, mouth and eyes. Segregate contaminated clothing. Record results of initial scan on Figure 1.

NOTE: Contamination levels of 10,000 dpm/ scan (1,000 cpm) of nose or mouth shall require further bioassay information. Direct affected personnel to blow nose and scan for loose contam-ination in mucus. Rescan nose. If results of either scan or nasal blow are greater than 1000 dpm/ scan (100 cpm), record name and social security number for future Body Burden Analysis. Record results on Figure 1.

c. Personnel with body contamination levels greater than 1000 dpm/ scan (100 cpm) should be segregated until they can be decontaminated in accordance with Attachment 3.

STEP 4 When monitoring of highly contaminated personnel is complete, begin monitoring the second group of contaminated personnel as specified in Step 3.a - c above.

STEP 5 When monitoring of personnel is complete, isolate all contaminated items and return them to plant for disposal.

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Procedure A.2-407 Revision 2

- Page 5 of 11 ATTACHMENT _2_

J VEHICLE MONITORING NOTE: If time and personnel permit, vehicle monitoring should be done concurrently with personnel monitoring, however, personnel monitoring will take precedence.

STEP 1 Dress monitoring teams in appropriate protective clothiag.

STEP 2 Establish a " clean" area (non-contaminated) for vehicle staging, and monitoring.

STEP 3 Using a RM-14 with a 2" GM pancake probe (or equivalent instrumentation) scan interior and exterior of vehicles for surface contamination.

STEP 4 Initiate a Vehicle Survey Form (Figure 2) for each contaminated vehicle.

~

NOTE: To avoid decontamination of entire vehicles and the resultant generation of large volumes of dry waste, indicate small areas of contamination using a grease pencil to outline the area.

STEP 5 If area indicates greater than 1000 dpm/ scan (100 cpm), smear the area with a paper disc smear and count.

(M STEP 6

( j Record results of monitoring effort on a Vehicle Survey Form, Figure 2.

STEP 7 If vehicle is not contaminated, i.e. less than 1000 dpm/100 cm smea rable (100 cpm), it may be released to a clean area.

STEP 8 Contaminated vehicles, i.e. greater than 1000 dpm/100 cm2 smearable (100 cpm), shall have a Vehicle Survey Form taped to the front windshield and shall be isolated. They will be decontaminated on a time-allowed basis.

STEP 9 Decontamination of vehicles shall be performed in accordance with Attachment 4.

STEP 10 When monitoring of vehicles is complete, isolate all contaminated materials and return them to the plant.

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Procedure A.2-407 0 Revision 2

, Page 6 of 11 l

ATTACHMENT 3 PERSONNEL DECONTAMINATION NOTE: Personnel shall not be released if skin contamination levels exceed 1000 dpm/ scan (100 cpm). Personnel who indicate nasal, ear canal, mouth or eye contamination shall be decontaminated under medical surpervision only. Personnel who indicate nasal or mouth contamination shall have further Body Burden Analysis performed as soon as practicable.

Decontamination of personnel shall begin with the most highly contaminated personnel receiving priority.

Personnel shall be decontaminated as follows:

STEP 1 Decontamination team personnel should be equipped with the following:

a. Lab coat

b. Rubber gloves

c. Shee covers STEP 2 Establish a decontamination area.

STEP 3 Using Whole Body Survey Form, decontaminate individual using the following guidance:

NOTE: These steps are provided as guidleines. It is not mandatory that each step be followed in sequence. The individual technician's judgement may be used to determine the complete decontamination method.)

a. Using soap and water, wash the affected area and survey.

b. If results indicate less than 1000 dpm/ scan (100 cpm), record results on Figure 3 and release individual from control group.

c. If results are still greater than 1000 dpm/ scan (100 cpm), repeat Step 3a as necessary.

d. If results continue to indicate greater than 1000 dpm/ scan (100 cpm), proceed to Step 4.

STEP 4 NOTE: Do not use Tide paste near eyes, nose or ear canal.

Make a paste using plain water and Tide detergent. Using a soft cloth, apply paste liberally to contaminated area. Wait two minutes.

Rinse area with copious amounts of pl,ain water, catching the water in a poly bag. Wipe area one time and survey.

If results are less than 1000 dpm/ scan (100 cpm), record results and release individual from control group. Issue appropriate clothing as necessary.

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Procedure A.2-407 Revision 2 Page 7 of 11 ATTACIDIENT 3 (Cont'd.)

PERSONNEL DECONTAMINATION If results are-greater than 1000 dpm/ scan (100 cpm), repeat Step 4.

STEP 5 If results continue to indicate greater than 1000 dpm/ scan (100 cpm) af ter a 'second attempt to decon using Tide and water, record results and proceed to Step 6.

STEP 6 CAUTION: Do not use betadyne near eyes. The application of betadyne should be used one time only.

a. Using betadyne, water'and soft cloth, make_one application of betadyne, wipe one time with soft cloth. Fold cloth, rinse with copious amounts of water, wipe one final time with folded soft cloth and survey.

b. If results indicate less than 1000 dpm/ scan (100 cpm), record results and release individual from control group.

c. If results are still greater than 1000 dpm/ scan (100 cpm), notify the REC to receive medical guidance for more-stringent decontam-ination methods.

STEP 7 Segregate all wastes generated by this procedure and label these materials as contaminated waste.

NOTE: Label all bags containing liquid or absorbed liquid for special processing.

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Procedure A.2-407 Revision 2 Page 8 of 11 ATTAClIMENT 4 vel!ICLE DECONTAMINATION NOTE: Vehicles shall be decontaminated to less than 1000 dpm/100 cm (100 cpm) smearable or 0.1 mrem /hr fixed. If these limits cannot be reached by techniques expressed in this Attachment notify the REC.

STEP 1 Establish a decontamination area.

STEP 2 Decontamination personnel should be equipped with the fellowing

a. Lab coat

b. Rubber gloves

c. Shoe covers STEP 3 Using Vehicle Survey Form and indicated contamination areas as a guide, decontaminate vehicle as follows:

a. Using masslinn cloths or equivalent, wipe contaminated area.

b. Af ter each wipe-down, survey the area by smear and scan, and record results on Figure 3.

c. Vehicle may be releasgd when smearable contamination levels are below 1000 dpm/100 cm (100 cpm) or fixed activity is less than 0.1 MREM /hr. Note that air filters, radiators and similar equipment may contain concentrated levels of contamination and should be checked separately.

d. If af ter a reasonable number of attempts, levels are still greater than in Step 3 above, isolate vehicle in a holding area.

n

e. Isolate all radioactive contaminated material.

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Procedure A.2-407

. Revision 2

- Page 9 of 11 O Form 5790-407-1 Revision 2, 02/25/82 Page 1 of 1 FIGURE 1 -

Example of WHOLE BODY SURVEY FORM NAME TLD NUMBER _ _ _ _ _ _

BI0 ASSAY REQUIRED: INITIAL I

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NOTE: Indicate Contaminated Area on Drawing and Record Results in CPM.

Check if survey: Before Decon After Decon Limits 100 cpm above background with RM-14/HP-210.

NOTE: After this checklist is completed and is not required for immediate ON use, it shall be placed in the appropriate container provided for emergency records.

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Procedure A.2-407 Revision 2 Page 10 of 11 FIGURE 2 1

Form 5790-407-2 l Rev. 2, 02/25/82 1 Page 1 of 1 i Example of 1 vel [ICLE SURVEY FORf!

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Owners Social Security Number: -

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Front Back NOTE: Indicate Contaminated Areas on drawing and record results in cpm.

Check if survey: Before Decon or After Decon Limits 100 cpm above background with Rti-14/ IIP-210 NOTE: Af ter this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for emergency records.

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Procedure A.2-407 Revision 2 Page 11 of 11 FIGURE 3 Form 5790-407-3 Rev. 2, 02/25/82 Page 1 of 1 Example of PERSONNEL AND VEHICLE SURVEY RECORD Before Decon After Decon Name/ Smearable Fixed Smearable Fixed

License No. Date Time dpm cpm dpm cpm Initials D

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NOTE: After this checklist is completed and is not required for immediate i

use, it shall be placed in the appropriate container provided for emergency records.

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Procedure A.2-501

. Revision 1

. Page 1 of 12 Op. Com. Rev. Reg'd. Yes X No Q.A. Review Req'd. Yes No X O)

V ALARA Review Req'd. ies No X COMMUNICATIONS DURING AN EMERGENCY A.2-501 Prepared by: ( .L,.f d_ i ALARA Review: Revision 0 Date 3/28/81 Reviewed by: #CMllde- Q.A. Review: Revision 0 Date 3/29/81 Operations Committee Final Review: Meeting Number //62 Date 8/o-/GR, Approved by: MM_ g.

Date 2-/6-9 L Op. Com. Results Review: Not Required Mtg. # 949 Date 3/26/81 PURPOSE This procedure describes the actions to be taken by the Emergency Communicators in response to an emergency declaration.

This procedure also describes the communications systems that are available for use during an emergency, their location, and their funct. ion. General communica-tions instructions are also described, but specific equipment instructions are not included.

CONDITIONS AND PREREQUISITES A. An emergency condition has been declared.

B. The Emergency Communicator has been summoned by the Emergency Director.

ORGANIZATION AND RESPONSIBILITIES A. Emergency Director - overall in-charge B. Lead Emergency Communicator - responsible for implementation of this procedure and coordination of the communi-cations aspect of the response.

C. Emergency Communicators - responsible for assigned areas and parts of this procedure as delegated by the Lead.

DISCUSSION A. General This procedure is composed of two parts: FACILITIES ACTIVATION and OPERATION, The activation items are not required to be performed in the given order, but rather are presented as a checklist of items that should be completed in the course of an event. The actual order of completion will depend on personnel available and the sequence of events taking place at the time.

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Proc: dure A.2-501

, R: vision 1

. Page 2 of 12 The operations items are presented as a checklist which should be referred t throughout the event. Items in this part are to be repeatedly performed as required. In some cases guidance on how a particular case should be handled may be given.

A table of communications locations and appropriate primary and alternate contacts is located in Attachment 2, Attachment 4 contains a listing of available Auto Ringing Hotlines.

B. Onsite Communications

1. Normal onsite communications is provided by the plant telephone system of approximately 256 lines and 24 trunks. The system is powered by its own 48 volt DC battery and charger which are located in the Admini-stration Building. If the charger fails, the battery will supply the system for about 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. The battery charger is supplied by a 208 VAC auxiliary circuit with diesel generator backup.

2. The Plant PA System may also be used for in plant communications.

The PA System is powered by the uninterruptible power system, and also functions as a paging system.

3. The plant sound powered system is also available and particularly useful for communications between the control room and areas in the plant.

4. Intercom units are instr.11ed at selected plant locations primarily for specific task-related activities.

5. The Control Room two-way radio system (described later) may be used for onsite communications with radio equipped trucks and portable radio transceivers.

6. Pocket radio pagers (beepers) are available for use.

7. The plant Alarm System provides a means of rapidly informing personnel of an emergency condition and initiates predetermined immediate actions.

C. Normal Offsite Communications Normal offsite communications is provided by the following telephone circuits:

1. 9 - PABX circuits to the Bridgewater Telephone Company central exchange in the city of Monticello. l

2. 4 - Business telephone circuits to th.e Bridgewater Telephone l Company central exchange. These circuits are not part of the PABX system.

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Precedura A.2-501

, Revision 1

. Page 3 of 12 O 3. 1 - Leased circuit between the control room and the Control Center U in Minneapolis. This circuit is direct and involves no dialing or switchboard equipment.

4. 2 - Interstate WATS lines. l S. 2 - Intrastate WATS lines.

6. 5 - Minneapolis Tie lines (microwave links) I NOTE: Three extensions on the line are located in the TSC for the purpose of facilitating message verifications. For this reason, it is advisable that offsite notifications be made from the TSC'as opposed to the Control Room. These extensions are set up to allow incoming and outgoing calls simultaneously.

D. Alternate Offsite Communications

1. Radio Receiver / Transmitter An alternate method for communications is provided by an AC powered radio transceiver with control consoles located in the TSC and Control Room.

From either console, communications may be established with the EOF, p Sherburne and Wright County Sherif fs, Plant Security, Operations hand-sets and Radiation Protection handsets. The NSP System Dispatcher, (w) St. Cloud System Dispatcher and radio-equipped service trucks may be contacted from the Control Room only.

2. One-Way Radio Alert System To facilitiate the initial notifications which are necessary in emergency situations, a one-way radio alert system is available.

Key. personnel in the plant emergency organization and local agencies are supplied with radio receivers which are tuned to a transmitter at the plant site. To make the notifications, a tape with a pre-recorded message is trarsmitted to each person equipped with a receiver.

3. Direct OcJicatea Telephone

a. Two automatic-ringing lines between the Technical Support Center (TSC) and the Emergency Operations Facility (EOF). ,

b. Emergency Notification System - this dedicated telephone network connects the plant site with NRC offices at Bethesda (NRC Head-quarters) and Glen Ellyn (Region III). Site extensions are located in the Control Room, TSC and E0F.

c. An automatic-ringing line exists between the Technical Support l Center and the State E0C.

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Pr:c"; dura A.2-501

. R:visi:n 1 Page 4 of 12

d. Health Physics Network - this dedicated telephone network connects the plant site wito NRC offices at Bethesda and Glen Ellyn. Site -

extensions are located in the office of the Supt., Radiation Protection, TSC, and the EOF.

e. Radio-telephone links exist for communica-tions between the State Division of Em'ergency Services and the Control Room /TSC.

E. Communications Matrix A matrix of locations versus communications capabilities ie. provided as Attachment 1. ,

F. Communications Techniques

1. Messages should be worded to avoid possible errors in transcription /

interpretation in accordance with the following guidelines as applicable:

a. To the extent possible, avoid the use of technical jargon, particularly in communications with offsite agencies.

b. Ensure that message is complete. Do not assume that the message recipient can supply the proper missing words, etc. ,

necessary to make the message complete.

c. Avoid the use of abbreviations. For example, millirem--not "m-rem o r "m-R" .

d. Read numbers individually (e.g., 135 should be stated "one-three-five", not "one hundred and thirty-five").

e. Do not use codes.

f. Preface each communication with the title or name of the receiving party and your title or name. For example:

"Monticello Technical Support Center, this is monitoring team number 1 ...".

g. After the communication is complete, request the receiving party read the message back, if appropriate (particularly if numerical data was relayed).

h. For radio communications, end message with an appropriate termination phrase. For example: " ... monitoring team number 1, out.".

2. All communications from news media or.from the public should be referred to the NSP Communications Department (telephone numbers).

3. When the Emergency Operations Facility (EOF) has been activated, authori;ed callersshouldbeencouragedtocontacttheNSPrepresentativeattheErg for information. This will minimize the number of communications and improve the accuracy of information dissemination.

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Procedura A.2-501 R:: vision 1 Page 5 of 12 O

V G. NSP Communications Department The NSP Communications Department is responsible to provide briefings and press releases to the news media. The Emergency Director will provide information on plant status as requested by Communications Department personnel. No information should be held back from the Communications Department by Monticello Nuclear Generating Plant personnel. The Emergency Director will ensure that the information provided the Communications Department is current and corisistent with information provided to offsite emergency organizctions.

PRECAUTIONS A. To the maximum extent possible, all communications regarding the extistence or severity of the event, or recommendation of protective actions, will be made on communications circuits which cannot be readily intercepted by persons outside of the emergency organizations. Telephone circuits shall be used as the primary means with radio used only as a backup. This proto-col will minimize the spread of rumors, minimize congestion of telephone circuits, and minimize undue public anxiety. In those cases where radio communications are necesscry, the use of such equipment and the wording of transmissions shall be in keeping with this protocol.

B. When sending taped messages via the tone-alert radios, be very careful to send the appropriate ressage. Cassettes are marked TEST or DRILL for q simulated emergencies. The cassettes intended for actual events are Q marked REAL.

C. When transmitting messages by telephone, radio, or public address during drills or test, begin and end the message with "THIS IS A DRILL" or "THIS IS A TEST".

PROCEDURE Part 1 - Facilities Activation STEP 1: Before making any offsite notifications, activate the 3739 lines in the TSJ by moving the toggle switch to the ON position. Notify the Control Room and SS Office that the TSC will answer calls on the 3739 line for the duration of the event.

STEP 2 When the two plant Tech. Communicator positions are staffed, establish a two-way telephone link between the TSC and Control Room STEP 3 When the E0F is activated, establish a three-way link by adding the l E0F Tech Support Communicator to the two-way at the plant.

l STEP 4 When the State E0C is activated, the Health Department (MHD) will

( initiate a call to the plant on the dedicated hotline. At this time, discontinue the information channel to the DES and provide the update information directly to the MHD at the State E0C via the dedicated

[] line.

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Procedure A.2-501 R: vision 1 Page 6 of 12 STEP 5 When the E0F is activated (the Emergency Director should announce this) discontinue answering the State EOC hotline. As long as the EOF is activated, they will respond to requests from the State (MHD).

Part 2 - Operation STEP 1 Continually monitor the communications equipment in your area.

STEP 2 Log all calls, both in-coming and out going. (This does not apply to internal plant calls.) Calls which are prescribed by procedure usually are logged on a checklist or form of some kind and are not required to be logged separately. All other calls, however, should be logged on Form 579G-501-1, Emergency Calls Log. The call log should also be used to indicate when blocks of calls (e.g., initial notifications or a followup notification) are completed.

STEP 3 When making public address announcements, the GAI-TRONICS units are preferrable to telephones. If a telephone must be used, speak loud and slowly to be heard and understood by plant personnel.

REFERENCES

1. Monticello Nuclear Generating Plant Emergency Plan

2. Monticello Nuclear Generating Plant Operations Manual

3. Title 10 Code of Federal Regulations Part 50, Appendix E

4. NUREG-0654/ FEMA-REP-1 " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" ATTACHMENTS

1. Monticello Nuclear Generating Plant Communications Matrix

2. Communications Contacts

3. Example of Emergency Call Log

4. Monticello Auto Ringing Hotline Network  !

5. Monticello Low-Band Radio Link

6. Monticello Radio Network O

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Procedure A.2-501

. R vision 1

. Page 8 of 12 ATTACHMENT 2 COMMUNICATIONS CONTACTS Contact Location Primary Alternate Control Room Shift Supervisor LPE&R0 EOF Emergency Manager Any member of the Advisory Support Group Minnesota Division of Emergency Services Duty Officer Duty Officer Minnesota Department State Emergency Alternate State of Health Plan Coordinator Emergency Plan Coordinator l Wright County Sherif f Sheriff Dispatcher Sherburne County Sheriff Sheriff Dispatcher Monticello Civil Monticello CD Sheriff Dispatcher Defense Director Minnesota Highway Captain Dispatcher Patrol (St. Cloud)

Monticello City Hall Mayor City Administrator Monticello F.D. Sheriff Dispatcher l

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Procedure A.2-501 Ravision 1 Page 9 of 12 ATTACHMENT 3 Form 5790-501-1  ;

Revision 1, 12/11/81 '

Page 1 of 1 Example of EMERGENCY CALL LOG 1

1 DATE:

CONTACTS TIME MNGP OTHER PARTY MESSAGE t

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4 NOTE: Af ter this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for Emergency Records.

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, Procedure A.2-501 R: vision 1 Page 10 of 12 ATTACHMENT 4 MONTICELLO AUTO RING HOTLINE NETWORK (Primary Communications Link)

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rgal 5. ate Plant Ellyn B3c , IDC F2 Cffice Number Name Stations

1. Emergency Notification System (ENS) (Multiple station line between the EOF, TSC, SS, Control Room and NRC Bethesda NRC. Each station can activate circuit.)

(EM) (ED)

2. E0F - TEC (2 station line between the EOF a TSC. Either station can activate the circuit.)

(RPSS) (REC)

3. E0F -

TSC (2 station line between the EOF, TSC. Each station can activate circuit.)

4. Control Room - System Dispatcher (2 station line between the C.R.

and System Dispatcher. Each station can activate circuit.)

5. State E0C - TSC (2 station line between the State E0C and TSC. Each station can activate the circuit.)

6. Health Physics Network (HPN) (Multiple station line between the E0F, TSC and Plant HP Office, NRC Bethesda, NRC Glen Ellyn, and other utilities. Each station can activate circuit.)

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Procedure A.2-501

( Revision 1  !

Page 11 of 12 I

' ATTACHMENT 5

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MONTICELLO LOW-BAND RADIO LINK (Radio-Telephone Hotline)

Control Room State Division NSP

!i of Emergency -------- /

TSC l, Rice Street Services (DES)

, EOF i

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Hardwire 1 To contact the DES:

Lift the handset, push the Push to Talk button and read j () predetermined message.

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Procedure A.2-501 Revision 1 Page 12 of 12 ATTACHMENT 6 MONTICELLO RADIO NETWORK SECURITY

@ORTABLES SECURITY d

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CONTROL i ROOM

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SECURITY SAS TSC RAD SURVEY MEF1 RS k PLANT PORTABLES 8 FUNCTION CONSOLES l I WRIGHT SHERBURNE SHERIFF / SHERIFF /

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Proceddfa A.2-702

. Revision 2 ,

. Page 1 of 5 Op. Com. Rev. Req'd. Yes X No __

Q.A. Review Reg'd. Yes No X O ALARA Review Req'd. Yes No X O

RESPONSE TO AN EMERGENCY AT PRAIRIE ISLAND ,

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A.2-702 Prepared by: Mw AL4RA Review: Revision 0 Date 03/29/81 Reviewed by: C [/L. M Q.A. Review: Revision 0 Date 03/29/81 Operations Committee Final Review: Meeting' Number //02. Date S/5/82 Approved by: __ k Date 2-/O-91 Op. Com. Results Review: Not Required Mtg.U'#' 950 Date 03/27/81 PURPOSE The purpose of this procedure is to provide instructions for the Monticello Nuclear Generating Plant Radiation Protection Group when called upon to . respond 'to. an emergency at Prairie Island. Also included is a-list of the equipment required and a " priority list" of qualified Radiation Protection Designees and their home telephone numbers.

CONDITIONS AND PREREQUISITES ,

A declared emergency exists at the Prairie Island site-and conditions have -

made necessary a request for health physics support.

v DISCUSSION In an emergency situation which includes a release of radioactive materials to the environs, the process of off site and environmental monitoring is limited by the personnel and equipment available for sampling, and to a lesser degree, by the facilities available for analysis. In an effort to enhance NNGP's capacity to handle this type of emergency, MNGP has made a reciprocal agreement with Prairie Island whereby each plant would, supply personnel, equipment and a'nalysis facilities to the other upon request.

PERSONNEL REQUIRED Supt. , Radiation Protection or designee (to assume duties of Radiation Protection Support Supervisor)

Three (3) persons qualified in radiation protection.

PROCEDURE NOTE: Upon notification that Prairie Island has requested assistance, the ,

Superintendent, Radiation Protection or designerwill organize a team

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of four people.

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Procedure A.2-702

, Revisicn 2

- Page 2 of 5 STEP 1: Refer to the " List of Qualified Radiation Protection Specialists /

Support Supervisors", Form 5790-702-1 (Attachment 1). Arrange for three Specialists and one Supervisor to travel to Prairie Island.

NOTE 1: The Radiation Protection Designee must remain available at Monticello (within 30 miles).

STEP 2: The response team members meet at the MNGP site to pick up vehicles and equipment per, " Prairie Island Emergency Support Equipment List" (Attach-ment 2).

NOTE 1: Other arrangement: may be made if necessary, as long as all equipment and personnel arrive at Prairie Island E.0.F. with a minimum of delay.

NOTE 2: Obtain Monticello E.0.F. keys from the Guard House and Emer-gency Survey Team Kits from the Monticello E.0.F.

l STEP 3: Proceed to Prairie Island E.0.F. (The E0F is on the plant site West of the exclusion fence.)

NOTE 1: Fo1 low Highway 194 to I694, I694 to I494, I494 to 61, 61 South to 316 (in Hastings), left on 316 to 61, left on 61 to 18 (NSP-P.I. sign at this intersection),

left on 18 to P.I.

NOTE 2: Detailed maps are included in each Emergency Team Kit.

STEP 4: Upon arrival determine if tne Emergency Operation Facility (E0F) has been activated. If so, report to the EOF to begin off-site monitoring.

STEP 5: If the EOF has not been activated or does not yet have the capability to direct the of f-site monitoring ef fort, notify the Prairie Island Radiological Emergency Coordinator for further instructions. (This may be accomplished by means of telephone or radio contact--it is not necessary to report in person.)

STEP 6: Obtain necessary Maps, Procedures, and Equipment from Emergency Kits.

NOTE 1: Extra supplies or equipment may be available at the Prairie Island E0F.

NOTE 2: The Radiation Protection Support Supervisor will direct the off-site monitoring effort.

STEP 7: If the analysis facilities at Prairie Island are not sufficient or become unavailable, the facilities at.Monticello will be available.

Transportation of samples will be arranged by EOF or Prairie Island personnel.

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I Procedure A.2-702 j Revision 2 Page 3 of 5 i

i REFERENCES

1. Prairie Island Nuclear Generating Plant-Emergency Plan and Implementing Procedures

[ ATTACHMENTS .

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1. Example of List of Qualified Radiation Protection Specialists / Support  ;

Supervisors l

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2. Prairie Island Emergency Support Equipment List

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Procedurs A.2-702 R: vision 2 Page 4 of 5 Form 5790-702-1 Revision 3, 07/21/82 Page 1 of 1 ATTACHMENT 1 Example of .

QUALIFIED RADIATION PROTECTION SPECIALISTS

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____________________________ DELETEG L_____________;_________________

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Procedure A.2-702 Revision 2 Page 5 of 5 ATTACHMENT 2 PRAIRIE ISLAND EMERGENCY SUPPORT EQUIPMENT LIST Personal TLD's; self-reading dosimeters (rezero)

Vehicles that may be used for off-site monitoring purposes NOTE: Obtain E0F Key from Security before proceeding to the EOF.

3 Emergency Survey Team Kits (from' EOF) -

4 Portable Radio Transceivers and Magnetic Antennas (from E0F)

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