ML20028D436

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures A.2-001 Re Emergency organization,A.2-107 Re Activation of Operational Support Ctr & A.2-402 Re Contamination Control

ML20028D436
Person / Time
Site:	Monticello
Issue date:	12/22/1982
From:	Marlone Davis NORTHERN STATES POWER CO.
To:
Shared Package
ML20028D429	List: ML20028D428 ML20028D431 ML20028D436
References
PROC-821222, NUDOCS 8301190118
Download: ML20028D436 (91)

Text

{{#Wiki_filter:, ! gi;"T 3' .nprna! Carrascenconc' care December 20, 1932 ( l M..\\. Davi s Locanon Monticello Frorn Lcnn Various 7 S; ecial i'istributica of Frergency Procedures subiect Perised Procedures for Ibergency Procedures Book Revisiens to the Ikergency Procedures were reviewed in a rccent Onerations Conaittee Meeting. Listed below are the procedures superseded and revised. Other pages not revised may have been reprinted with the revised pages to facilitate updating the Ecok. i Superseded Paces List of Current Procedures (Dated 8/5/82) Procedure A.2-001 (Pages 1 through 28), Revision 3 ,m ( ) Revised Paces List of Current Procedures (Dated 12/15/82) Procedure A.2-001, (Pages 1 through 28), Revision 4 l l Prepared by: C w / w 1l n \\1,- s Reviewed by: $ iNd _ / 2- [f !J 2_ l Op. Com. Final P view: Mcchin'I* I / / (. 3 _, Date Approved by: .aw( ( / ju,wh( Date / 7 [3 '} [d ~yu f n I o l l ,f <.J l 9301190118 930113 f PDR ADOCK 05000263 1 F PDR E'

-. - - _ _ _. - -.= . ~ -. Internal Correspondence D3t* December 20, 1982 from M. A. Davis Location Monticello Y"#I "3 7 Special Distribution of Fnergency Procedures l Subject Reyiged proCeditres for fDergenCy Procedures Book i Revisions to the F2nergency Procedures were reviewed in a recent Oncrations Corni.ttee Meeting. Listed below are the procedures superseded and revised. Other pages not revised may have been reprinted with the revised pages to facilitate updating the Book. li f Superseded Pages I ( List of Current Procedures (Dated 12/15/82) Procedure A.2-107, (Pages 1 through it ) Revision 3 l Procedure A.2-204, (Pages 1 through 11 ) Revision 1 1 Revised Pages List of Current Procedures (Dated 12/20/82) Procedure A.2-107, (Pages 1 through 12) Revision 4 Procedure A.2-204, (Pages 1 through 19) Revision 2 Prepared by. ('i ld h _ l. k-Reviewed by: % A.)\\ jJwO u.10 /.2.f/ / 1 Op. Com. Final Rev ew: Meeting # //06 Date Approved by. . b l\\ Date 19'2')Jt 6 9 2 2 s 3

I'f internal Correscenaence u oate December 20, l.,2 (

51. A. Davis Locanon Slonticello rrom NJ teawn V rious T

Special Distribution of Ibergency Procedures Subiect Revised Procedures fOr ihergency Procedures Book Revisions to the lhergency

cedures were reviewed in a recent Doerations Committee Sleeting.

Listed below are the procedures superseded and revised. Other pages not revised nay have been reprinted with the revised pages to facilitate updating the Ecok. Superseded Pages List of Current Procedures (Dated 8/5/82) Procedure A.2-401, (Pages 1 through 8), Revision 1 Procedure A.2-402, (Pages 1 through 10), Revision 0 (m) v Revised Paces List of Current Procedures (Dated 12/15/82) Procedure A.2-401, (Pages 1 through 8), Revision 2 Procedure A.2-402, (Pages 1 through 8), Revision 1 Prepared by: b /db <" Reviewed by: %d [dku'fLP l Op. Com. Final Reviewk >1etting # 1/6 ) Date IL !l ' -A deg_ i Date 1 "> 4 2 -E't Approved by: LJ ~ l 1 (

l 'I internal Corresconcence cate December 20, 1982 [^% rrom M. A. Davis Location MOnticello (v) V"#iU"3 SpcCial 1)istrii .on of Ibergency Procedures l { Subject geyjged proCedilres for fDergency Procedures POok Revisions to the fhergency Procedures were reviewed in a recent Oncrations Cornittee Meeting. Listed below are the procedures superseded and revised. Other pages not revised may have been reprinted with the revised pages to facilitate updating the Book. I Superseded Pates I List of Current Procedures (Dated 8/5/82) { l in) L.J Revised Pages List of Current Procedures (Dated 12/15/82) Procedure A.2-422 (Pages 1 through 5), Revision 0 Procedure A.2-423 (Pages 1 through 5), Revision 0 j i Prepared by: es - _,4-Periewed by: hhb f/00 Date 7 29 T2.. Meetin$g# d 424, Op. Com. Final Review: Date n - 2 2 -f 1. Approved by: ,m 1 m. m i

12/20/82 A.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES LIST OF CURRENT PAGES PROCEDURE PROCEDURE TITLE REVISION NUMBER 000 Series Organization A.2-001 Emergency Organization 4 l 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 4 200 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 2 l 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 Assembly Point Activation 2 O 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 2 A.2-402 Contamination Control 1 A.2-403 Emergency Surveys 2 A.2-404 Emergency Sampling and Analysis 2 A.2-405 Release Rate Determination 2 e 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 A.2-422 Stack Iodine / Particulate Sampling & Analysis 0 A.2-423 Reactor Building Vents Iodine / Particulate Sampling and Analysis 0 500 Series Communications and Documentation A.2-501 Communication During an Emergency 1 A.2-502 Recordkeeping During an Emergency 0 A.2-503 Emergency Reports and Documentation 0 0 _j-AAA056

A.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES LISI 0F CURRENT PAGES PROCEDURE PROCEDURE TITLE REVISION NUMBER 600 Series Re-Entry and Recovery A.2-601 Re-Entry 0 A.2-602 Deleted 11-19-81 A.2-603 Repair and Corrective Action 1 700 Series A.2-702 Response to an Emergency at Prairie Island 2 A.2-703 Response to Off-Site Situation Involving Radioactive Materials 0 l \\ l - ii - 1 AAA056 i I

m Procedure A.2-001 1 Revision 4 Page 1 of 28 Op. Com. Rev. Reg'd. Yes X No Q. A. Review Reg'd. Yes No X ALARA Review Req'd. Yes No X EMERGENCY ORGANIZATION A.2-001 REVIEW AND APPROVAL Prepared by: / /[ s 2, ALARA Review: G. D. Mathiasen Date 11/17/81 Reviewed by: MIM Q.A. Review: R. L. Scheinost Date 11/17/81 l Operations Comm Lt e Final iew:' M ting Number /l G 'S Date /1dha. Approved by: d f mw (1 ) Ms Date d/[9/R1 Op.Com.Resultslevied: Not Required Mtg. 1086 Date 5/27/82 i l 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. I PRECAUTIONS No Monticello Nuclear Generating Plant personnel shall make any information releases to members of the news media or the general public during an emergency O unless cleared through the Emergency Manager, if established, or Emergency Director. Direct all inquiries to the Communications Department at NSP Head-quarters or at the E0F. I i DISCUSSION i A. Although it is not practical to develop detailed procedures encompassing every conceivable emergency situation, advance planning should create a 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 effort, are defined. (See Figure 1) 8. The Emergency Organization is herein described. The duties and responsi-bilities of the individual 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 positions in the ERO, and insure that the more important positions in l the ERO are filled first. l l The Tag Board consists of a board with a layout of the Emergency Response l Organization. Under each position on the board is a list of the individua.ls who are qualified to fill that position, and a tag with the necessary instruc-tion 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. WP/kk

Procedure A.2-001 Revision 4 Page 2 of 28 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 pass 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 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 Emer-gency 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 Off-Shift 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 " pace" 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 if there is no one available from the qualified list, the most qualified person available should be selected. Requalification, when applicable, will be required on an annual ( 3 months) basis. This procedure will be reviewed quarterly, and revised if necessary. F. In the periods between revisions of this procedure, personnel who become qualified may be used to staff these positions. O WP/kk

Procedure A.2-001 Revision 4 Page 3 of 28 Q GUALIFICATION. ORDER OF SUCCESSION AND DUTIES l ~ ' ' i I. Coordination and Direction Group A. Emergency Director 1. Qualifications Five years experience at Monticello Nuclear Generating Plant a. 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 W 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 l SCPIP - 1 SCPIP - 8 SCPIP - 2 SCPIP - 12 SCPIP - 4 2. Qualified Personnel in Order of Succession a. c b.) DELETED c. d. DELETED e. l l l WP/kk

Procedure A.2-001 Revision 4 Page 4 of 28 4 3. Duti s 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 k. 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. Qualified Personnel DELETED . DELETED DELETED DELETED 3. Responsibility Provide technical operational advice to the Shift Supervisor. C. Shift Emergency Communicator 1. Qualifications a. Six months experience at Monticello WP/kk

Procedure A.2-001 Revision 4 Page 5 of 28 7] 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 Plant Management. 2. Qualified Personnel DELETED DELETER DELETER 3. Duties a. Assists Emergency Director in emergency classification; b. Conducts initial and followup notification in accordance with procedures; c. Coordinates all incoming and outgoing communications; d. Ensures proper logging and recording of communication;. e. Assist Emergency Organization in use of procedures. II. Operations Group A. Operations Group Leader 1. Qualifications a. Current SR0 License for Monticello WP/kk

Procedure A.2-001 Revision 4 Page 6 of 28 b. 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. Pearson, S. b. Senior Site Superintendent present, not on duty shift Senior Shift Supervisor present, not on duty shift c. d. Duty Site Superintendent e. Duty Shift Supervisor 3. Duties Coordinates response of Operations Group; a. b. Evaluates plant and radiological conditions; Ensures Emergency Director is informed of plant status; c. 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. 8. 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-WP/kk

Procedure A.2-001 Revision 4 Page 7 of 28 I l tial safety consequences of a fire and advise control 1 l room personnel. This shall be evidenced by current j SRO or RO or current enrollment in license training program. 1 c. Qualified physically in accordance with Tab 7 of the NSP i Medical Policy and Procedure Manual (annual requirement). 2. Qualified Personnel a. Team Leader I j OELETED DELETED } 8 l 1 If a designated Team Leader is not on duty, an alternate Team Leader will be designated by the Shift Supervisor. i b. Team Members #2 & #3 l (7 DELETED i 1 I l l i c. Team Members #4 & #5 L r ( DELETED G WP/kk

Procedurs A.2-001 Revision 4 Page 8 of 28 III. Maintenance Group The Maintenance Group consists of the Plant Superintendent, Operations and Maintenance; the Superintendent, flaintenance; 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 Five years experience at Monticello Nuclear Generating Plant a. b. Demonstrated ability in supervisory skills Knowledgeable or qualified in following areas: c. - Emergency Plan - Emergency Implementing Procedures: A.2 - 001 A.2 - 106 A.2 - 107 A.2 - 603 2. Order of Succession a. b. I DELETED e. f. B. Group Responsibilities The group shall have the primary responsibility for emergency repairs and corrective actions. IV. Engineering 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 Five years experience at Monticello Nuclear Generating Plant a. b. Demonstrated ability in supervisory skills WP/kk

Procedure A.2-001 Revision 4 Page 9 of 28 c. Knowledgeable or qualified in following areas: ), %.J - Emergency Plan - Emergency Implementing Procedures: A.2 - 106 A.2 - 502 2. Order of Succession a. b OEbEIEU c. d. e. 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. g) The group is divided into two sectiors: 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 Five years experience at Monticello Nuclear Plant; a. b. Demonstrated ability in supervisory skills; c. Knowledgeable or qualified in following areas: - Health Physics - Emergency Plan - Emergency Plan 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 - 41C A.2 - 204 A.2 - 403 A.2 - 502 A.2 - 205 A.2 - 404 A.2 - 702 ( ~y A.2 - 207 C/ WP/kk

Procedure A.2 '001 Revision 4 Page 10 of 23 2. Order of Succession g I. DELETED I c. d. e. l 3. Duties Coordinate assessment of radiological aspects of accident, a. 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 One year experience at Monticello Nuclear Generating Plant a. b. Knowledgeable or qualified in following areas: - Chemistry and radiochemistry, including Monticello Chemistry Manual - Emergency Plan Implementing Procdures: 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 Succession a. b.

c. DELETED d.

l e. 3. Duties a. Offsite dose projection WP/kk

Procedure A.2-001 Revision 4 Page 11 of 28 l b. Release rate determination c. Sampling and analysis of reactor coolant, containment atmos-phere and plant effluents 4 d. Sample coordination and recording C. lionitoring Section Leader 1. Qualifications One year experience at Monticello Nuclear Generating Plant a. i I b. Knowledgeable or qualified in following areas: - Mcnticello Radiation Safety Procedures (E.1) - Eniergency Plan Implementing Procedures: A.2 - 107 A.2 - 403 A.2 - 201 A.2 - 404 A.2 - 202 A.2 - 407 i A.2 - 301 A.2 - 409 A.2 - 302 A.2 - 410 A.2 - 303 A.2 - 411 i A.2 - 304 A.2 - 501 A.2 - 401 A.2 - 502 A.2 - 402 A.2 - 601 2. Order of Succession a.

b. DELETED c.

d. l e. 3. Duties a. Emergency exposure control b. Contamination Control c. Emergency surveys 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 personnel. t l l WP/kk

Procedure A.2'001 Revision 4 Page 12 of 28 A. Support Group Leader 1. Qualifications One year experience at Monticello Nuclear Generating Plant; a. b. Demonstrated ability in supervisory skills; Knowledgeable or qualified in following areas: c. A.2 - 501 A.2 - 503 A.2 - 502 A.2 - 106 2. Order of Succession a. y, oELETED d. e. 3. Duties Assign group personnel to provide administrative support, a. document control and document retrieval; b. Assure that TSC is staffed adequately. Coordinate and provide personnel for logistics functions c. 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; Knowledgeable or qualified in following areas: c. A.2 - 502 A.2 - 503 2. Order of Succession WP/kk

Procedure A.2-001 Revision 4 ] Page 13 of 28 1 x 3 I n$ % ergo I L 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. i A. Security Group Leader l 1. Qualifications Two years experience at Monticello Nuclear Generating Plant a. b. Knowledgeable or qualified in following areas: i - Monticello Security Plan - Safeguards Contingency Plan & Implementing Procedures - Emergency Plan Implementing Procedures: I i A.2 - 206 A.2 - 301 A.2 - 302 2. Order of Succession a. b: DELEreo

d. '

3. Duties a. Carry out plant security and access 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.) WP/kk

Procedure A.2-001 Revision 4 Page 14 of 28 A. Qualifications 1. Current Red Cross Multi-Media First Aid training (i.e. within last three years). 2. Currently qualified under respiratory protection program, including training for use of SCBA equipment. 3. One year experience in current general 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/kk

Procedure A.2-001 Revision 4 Page 15 of 28 ,- s 2. Qualified Personnel ( ) See Qualified Personnel for Shift Emergency Communicator 3. Duties Assume control of operational Assembly Point a. b. Ensure proper radiological surveys are conducted Conduct accountability procedure as required c. d. Maintain communications between Assembly Point and TSC D. TSC Conrdinator (See Support Group Leader) E. OSC Coordinator 1. Qualifications - Experience as Radiation Protection Coordinator 2. Qualified Personnel a. b. DQ34Ql c. d. l f e. (; 3. Duties a. Be responsible for conduct of procedure A.2 - 107, Activation of the Operational Support Center, b. Supervise OSC personnel assigned to standby 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 communications link between the Control Room, TSC, and E0F. WP/kk mr-

Procedure A.2'001 Revision 4 Page 16 of 28 b. Communicate technical information between response centers. c. If located in TSC, post information on Status board. X. Response Center Stm'+ing 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 Leader 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/kk

Procedure A.2-001 Revision 4 Page 17 of 28 3. Communicator (To be designated by OSC Coordinator if needed) C. Control Room Staffing 1. Site Superintendent - In Charge 2. Assistance a. Shift Supervisor b. Shift Operators c. Additional operators assigned to Control Room d. STA 3. Technical Communicator (CR to TSC) 4. Technical Support Center personnel as directed by Emergency Director REFERENCES 1. Monticello Nuclear Generating Palnt Emergency Plan 2. Monticello Nuclear Generating Plant Operations Manuals l 3. NUREG-0654/ FEMA-REP-1, " Criteria for Preparation and Evaluation of Radio-logical Emergency Response Plan and Preparedness in Support of Nuclear Power Plants". l l { O l WP/kk l

Emergency Director Shift Emergency 'onrnin i c a t or oz t us Engineerin}: Support Radiological Security y Group M Group Emergency Group 1.eader T.eader Coo rill na t or Leailer Q en l I l l 5 m o M o llealth Engineering Support Se urity Q Ej g Physics Group Group Group Group E: U> H Opcrations !!a int enance o Group I'" Group Leader Shift Technical l I Advisor Electrical 6 ??? I&C Flechanical y1 Operations Section Section E1 Group woc an 0 4 > to t,4 ' o O ~ O 9 9

Procedure A.2-001 FIrt'RE 2 Revision 4 Page 19 of 28 IIEALTil PIIYSICS GROL*P (SilIFT) ORGANIZATION s O' Emergency Emergency Manager Director A / Rad. Prot. Radiological Support Emergency Supervisor Coordinator lf f-Site Dose Assessment Monitorino () & Criemistry Section Section 1 Supervisor 1 Supervisor 2 Technicians 5 Technicians =--- Off-Site Monitoring ' ?l' ' '.". Team

• 1 Supervisor 4 Technicians
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After EOF activation, Off-Site Monitoring Team dissolves into Monitoring Section. s 4

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Procedure A.2-001 Revision 4 Page 20 of 28 For., 5790-102-5 ATTACHMENT 1 Revision 7, 11/19/82 Example of Page 1 of 9 MONTICELLO EMERGENCY AUGMENTATION LIST C00RDitlATION AND DIRECTION GROUP P ger Home

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Procedure A.2-001 Revision 4 Page 21 of 28 Forn 5790-102-5 ATTACHMErlT 1 (Cont'd.) mh Revision 7, 11/19/82 Page 2 of 9 Example of M0f1TICELLO EMERGEfiCY AUGMENTATION LIST MAINTErlANCE GROUP Pyer Home

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Procedure A.2-001 Revision 4 Page 24 of 28 Form 5790-102-5 ATTACHMENT 1 (Cont'd.) h Revision 7, 11/19/82 w Page 5 of 9 Example of MONTICELLO EMERGENCY AUGMENTATION LIST OPERATIONS GROUP (Cont'd.) t Pager Home

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Procedure A.2-001 Revision 4 Page 28 of 28 ATTACHMENT 1 (Cont'd.) Example of Form 5790-102-5 MONTICELLO EMERGENCY AUGMEllTATION LIST Revision 7, 11/19/82 Page 9 of 9 Pacer Home SHIFT EMERSENCY COMMUNICATOR ( ) ( ) ( ) ( ) ( ) ( ) ( ) ( ) DELETEp ( ) ( ) ( ) ( ) ( ) h ( ) ( ) ( ) ( ) ( ) ( ) ( ) DELETED ( ) ( ) ( ) ( ) ( ) ( ) ( ) ( ) ( ) )! M ( ( ) ( / WP/kk ~

Procedure A.2-107 Revision 4 Page 1 of 12 Op. Com. Rev. Reg'd. Yes X No Q. A. Review Reg'd. Yes No x ALARA Review Req'd. Yes No X ACTIVATION OF THE OPERATIONAL SUPPORT CENTER (OSC) A.2-107 REVIEW AND APPROVAL Prepared by: Cd///,.N,

• ALARA Review Revision 0 Date 3/28/81 Reviewed by:

%QdJi@$ Q. A. Review Revision 0 Date 3/28/81 OperationsCommNteeFinalReview: Meeting Numbe.r //le/r Date //- //, -J ' Approved by: N.$ M Date lQ ? 2 Op. Com. Results Review: Not Required Mtg.# "1056 Date 1/22/82 l PURPOSE AND REQUIREMENTS This procedure provides specific information and instructions for the organiza-tion, activation, operation and de-activation of the Operational Support Center (OSC) in support of the Monticello Nuclear Generating Plant and NSP Emergency Plan. CONDITIONS AND PREREQUISITES (D (j An emergency ccadition corresponding to an Alert or a higher emergency classi-fication has been declared at the Monticello Nuclear Generating Plant as provided in the MNGP Emergency Plan. PRECAUTIONS The OSC facilities may be used for normal daily operations as well as for training and emergency drills, provided that these activities do not interfere with the immediate activation of the OSC or the continuing OSC operations in the event of an accident. OSC facility use during normal operation shall be limited to l activities that will not degrade the level of OSC preparedness to react to accident situations and will not reduce OSC reliability. ORGANIZATION AND RESPONSIBILITIES A. Emergency Director - Overall In-Charge B. Radiological Emergency Coordinator - Assist Emergency Director by providing I supervision for OSC Coordinator. C. Operational Support Center Coordinator - Responsible for implementation of this procedure. t /h l l WP/kk l

Procedure A.2-107 Revision 4 Page 2 of 12 DISCUSS 10fl A. OSC Function The OSC will function as a staging area for personnel and equipment necessary to respond to an emergency. It will provide an access control function and will be the primary information source to the TSC on plant radiological conditions. B. Location The Primary OSC location will be at Access Control. The alternate location will be on the second floor of the Administation Building. (See Attachment 1 for OSC Floor Plan.) C. Data and Information Resources The OSC area contains the following: 1. A complete set of up-to-date radiological survey maps. 2. Plant Operating Procedures 3. Plant Emergency Procedures 4. Bechtel Accident Dose Rate Maps D. Communications 1. OSC to TSC Intercom 2. Rad Survey Portable Radios (4) 3. Plant Extensions (2) 4. Radio Console (capable of communicating with Rad Survey and Operations portable radios) E. Equipment and Facilities (Primary Location) 1. GDE Terminal for exposure control 2. BBA System 3. Count Room equipment a. Automatic Smear Counter b. GeLi Counting System 4. Status Board 5. Radiological Survey Maps 6. Procedure Forms 7. Portable CAM 8. Portal Monitor 9. First Aid Kits and Stretcher 10. Decon Facilities 11. Friskers 12. Respiratory Protection Equipment 13. Fire Fighting Equipment 14. Protective Clothing 15. Signs and chains for use in positively maintaining plant access control O WP/kk [

1 Procedure A.2-107 Revision 4 Page 3 of 12 4 ( PROCEDURE PART I - ACTIVATION STEP 1 Direct or perform radiological survey in the OSC and SAS. Forward result to REC. The REC will be responsible for ensuring routine surveys of the OSC and for evaluation j of the results. 4 STEP 2 Position portable CAM in area outside of BBA Room and place in i operation. STEP 3 Verify Automatic Smear Counter and GeLi Detector systems in operation. 4 STEP 4 Obtain 4 portable radios on the OPERATIONS net, plus a gang charger, for use at the OSC. Establish radio contact with the REC. STEP 5 Direct the removal of non essential personnel, interferring equipment, etc. from the OSC. STEP 6 Initiate the OSC log in accordance with A.2-502. i STEP 7 Obtain a copy of the most current exposure information for active personnel. If personnel are available, process any dosimeter cards and update the master exposure file. PART II OPERATION Note: The following is a list of procedural steps for which the OSC Coordinator is responsible. Each step which contains the word " continually" means that the steps should be repeated regularly as needed while the OSC is in operation. 1 l STEP 1 Continually update survey floor plans. This will require review of incoming survey results, and also review of ARM data (Form 7 No. 5790-107-3, Emergency ARM Log (Attachment 4) may be used to record ARM data.). STEP 2 Continually maintain OSC status board. STEP 3 Ensure that communications are continuously attended. Obtain the services of a Shift Emergency Communicator, if needed. NOTE: Use OPERATIONS radios for in plant communications. Use RAD SURVEY radios for out-of plant activities. I STEP 4 Keep the REC apprised of OSC events and activities. i STEP 5 Supervise personnel assigned to the OSC for standby status. All personnel should have dosimetry and current exposure information. WP/kk

Procedure A.2-107 Revision 4 Page 4 of 12 PROCEDURE (Cont'd. ) STEP 6 Determine the need for special supplies, equipment, etc. to support OSC operation. Any requests should be forwarded to Support Group Leader. STEP 7 Support emergency rescue, first aid, maintenance and survey teams by verifying their preparedness to initiate their activities and by coordinating their movements in and out of the controlled area with the Control Room and TSC. Prepare emergency RWP's i.a.w. Attachment 2, to ensure that adequate precautions have been taken. STEP 8 Maintain strict access control (signs should be used to aid in this process) and keep the TSC and Control Room advised of personnel entering and leaving controlled areas. Request Security Personnel assistance in maintaining access control if required. STEP 9 Coordinate the arrival and departure of offsite support services and coordinate their standby status while on site. STEP 10 Make necessary preparations to relocate access control (Procedure A.2-411) in the event that the primary access control point becomes uninhabitable. STEP 11 Continually maintain the OSC log. l STEP 12 Assume responsibilities of RP Coordinator and ensure that Radiation Protection Procedures are followed. STEP 13 If and when directed to do so, ensure that all personnel in the OSC (including the SAS) insert their security badges into the accountability reader located near the portal monitor. Caution I personnel to make sure they get a red light after inserting cards. As part of the accounting process, prepare a list of names, initials and TLD numbers of any personnel who are in the Controlled Area and not available to use card reader. Forward the list to the TSC. i l I PART III - DE-ACTIVATION Upon termination of Emergency condition or when deemed by Emergency Director that the OSC may be deactivated perform the following: STEP 1 Initiate Surveillance Test #1102. STEP 2 Return Operations Radios to their storage location. STEP 3 Return Radiation Protection Radios to their storage location. i O WP/kk

Procedure A.2-107 Revision 4 Page 5 of 12 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. Floor Plan of OSC 2. Guidelines for Use of Emergency RWP Checklist 3. Example of Emergency RWP Checklist 4. Example of Emergency ARM Log i i l 1 i O WP/kk

Procedure A.2-107 Revision 4 Page 6 of 12 O ATTACHMENT 1 g Fire Brigade l Ilot Lib Battery Storeroom Equipment Area Count - 9 Q Room 1:oom y ^ 2 Ql Battery Room Microfilm Area l l OSC Control l I f! CD1 3 0"IC' 4 Battery l Room 1 8 RPS and Operators Staging Area = s i.-- Decon 5 and gag .hid first Station p l l 7 BBA lloom and Exposure 6 Control J OSC Phone #'s 1 - 1212 Count Room 2 - 1138 110 t I.ab 3 - 1137 OSC Control Engineering Office l 4 - 1150 OSC Coordinator 9 Maintenance 10 i 5 - 1195 SAS and 6 - 1272 Exposure Control I&C's 7 - 1135 Standby RPS Staging Area 8 - 1268 Standbv Operators i 9 - 1327 Standby Maintenance 10 - 1323 Standby ICS f 1 1 I I \\ \\ l t

Procedure A.2-107 Revision 4 Page 7 of 12 O Page 1 of 2 ATTACHMENT 2 Guildelines for Use of Emergency RWP Checklist PURPOSE i The purpose of this attachment is to detail the process of how emergency RWP's will be used to govern emergency work. DEFINITIONS An emergency RWP is defined as the process which ensures certain radiological precautions for emergency work are considered, and appropriate actions are taken. The emergency RWP checklist (Form No. 5790-107-2, Attachment 3) is the instrument that documents which actions were taken. DISCUSSION In general, the entire process as outlined below should be completed each time an emergency RWP is needed. However, in urgent situations, completing the whole process may hamper the timely execution of certain corrective actions. On the other hand, hazardous radiological conditions that could be present during an accident may increase the importance of ensuring the necessary precautions are taken. Therefore, each circumstance will dictate the extent to which an ') emergency RWP will be completed, and this procedure is intended to outline the p philosophy which will be used to ensure the degree of control required by the Q emergency RWP is appropriate for the task at hand. EMERGENCY RWP ISSUANCE PROCESS To the extent that is practical, the entire emergency RWP process as outlined below should be completed. One should be able to readily determine from the urgency of the situation how much job preplanning should be done and to what extent the emergency RWP process should be completed. Fo. all emergency RWP's, an emergency RWP checklist shall be completed, post job completion, if necessary, for items a, b, c, e, g, h, & j. a. Determine the urgency and verify the validity of the proposed emergency work. Normally, this information'will be supplied through normal channels from the TSC (e.g. phone call from MSL or approved WRA). If it has not been supplied, contact the ED, REC, or MSL to obtain this information before allowing the work l to commence. The only exception to this may be if it is learned that immediate actions are necessary to save a life. If the work has been ordered to begin immediately, do not spend time completing the checklist if it will hold up the start of the job. Prescribe appropriate precautions, and ensure job begins ASAP. However, complete as much of checklist as possible while waiting for necessary precautionary steps to be taken (e.g. donning P.C.'s etc.). b. Assess the radiological conditions to Le encountered during the job. Determine if the precautions contained in the existing extended RWP's are adequate, and O if they are, use the extended RWP, while still completing sections c, e, and V j of the process. If the extended RWP's are not adequate, complete the rest of the process. WP/kk

Procedure A.2-107 Revision 4 Page 8 of 12 Page 2 of 2 ATTACHMEllT 2 c. For all jobs, an accurate and complete description of work, work site location and the protective equipment and dosimetry to be used shall be determined. If there is doubt as to the exact nature of the work to be performed, or the location of the work, the workers supervisor should be consulted. d. If at all possible, ensure an RPS is ja attendance for the jcb. Log personnel in and out by completing page 2 of the emergency RWP checklist. e. f. The Bechtel accident dose rate maps should be used to determine the best route to the work site in order to keep doses ALARA. g. Emergency workers should have completed form-4's and procedure A.2-401 shall be completed for exposures which are expected to result in the individuals quarterly accumulated dose to exceed plant administrative limits. h. For areas in which the dose rate is expected to be > 1R/hr, the expected time at the work site and the authorized individual doses for the job shall be determined (assume the current quarterly allowable, unless told otherwise). From this infor-mation, determine the highest working area dose rate which would result in the limiting individual authorized dose being received, while also taking into account any significant doses that may be received in route. Perform timekeeping during the job to ensure planned exposures are not exceeded. Continual radio contact should be available between emergency workers and the OSC to aid in such timekeeping. While the job is in progress, if it is determined that planned exposures will exceeded, contact the ED immediately for further instructions. In addition, a maximum travel route dose rate should be determined. This dose rate should be ~ 4 times higher than any expected to be encountered enroute to the work area, up to 1000 R/hr for the worst case. The purpose of this dose rate is to serve as a caution flag to the RPS that means " Beware conditions are signifi-cantly different than originally thought" Actions to be taken if this dose rate is reached or exceeded will be determined during the job briefing and will be dependent upon job.mportance, duration, and the exposure limits of the individuals doing the job. i. To increase personal safety, the buddy system should be employed in the following conditions: 1) If the equipment needed for the job is too much for one person, l slowing the job down and resulting in non ALARA exposures. 2) If radiological conditions could change abruptly and drastically during the job, and one person is not available to watch a dose rate meter continuously. 3) If radio contact cannot be maintained between the OSC and the emergency workers. j. Prior to dispatching personnel to perform emergency work, ensure adequate job planning has been performed and that emergency workers have been adequately briefed regarding the proper precautions which should be exercised to maintai worker risk to an acceptable level. Since the OSC may be a very busy place, extra effort will have to be exercised to esure this is effectively done. The higher the expected hazards, the more important this becomes. WP/kk

Procedure A.2-107 T<evision 4 Page 9 of 12 O Form 5790-107-2 d Revision 2, 12/02/82 Page 1 of 2 ATTACHMENT 3 Example of Emergency RWP Checklist Date WRA No. Time a. Job must begin immediately. Yes No b. Existing extended RWP used. Yes No. No c. Work location Work description Protective equipment and dosinetry used O Hood C Rubber gloves O TLD D Front & Back O Coveralls O Canvas gloves O 200 mR SRD C Waterproof [ Rubbers O 1 R SRD Outer Layer SCBA O 10 R SRD 0 Full Face O 200 R SRO Part Resp C Beta Protection for O Extremity TLD(s) v Eyes d. RPS in attendance Yes No e. Personnel logged in (Complete the backside of this form) Initial f. ALARA routes specified Yes No If yes, record route g. A.2-401 completed Yes No h. Expected time to be spent at work site Limiting Authorized individual dose for job Highest allowable working area dose rate Highest allowable travel route dose rate Timekeeping ready Yes No Radio contact available Yes No i. Buddy system employed Yes No j. Briefing conducted Yes No Completed by RPS (Q WP/kk

Procedure A.2-107 Revision 4 Page 10 of 12 Form 5790-107-2 Revision 2, 12/02/82 Page 2 of 2 ATTACHMENT 3 Example of Emergency RWP Checklist I Time i Dosimeters Authorized In Out j 0-200 i 1R 10R ! 200R i Name l Dose l In!0ut ! In l0ut i In!0ut Inj0ut l l l l l l l I i i i i I i l h l I l I i l l i IS I i i i I I I i l l l l i i I l I l l l l I I I i l I l I I l l I i NOTE: After this form is completed and is not required for immediate use, it shall be placed in the appropriate container provided for emergency records. WP/kk t

Pro e A.2-10h-Revision 1 Form #5790-107-3 ATTACHMENT 4 Revision 0, 2/25/82 Page 1 of 2 Example of EMERGENCY ARM LOG Date Normal Current Reading (record time in top box) ARM No. Area Description Reading A-1 Refuel Floor Low Range 2 A-2 Refuel Floor High Range 5 A-3 Refuel Floor Stairway 1 l i A-4 New Fuel Vault (1001 North) 7 l A-5 Fuel Pool Pump Room 9 A-6 Contaminated Storage Area (1001 South) 2 A-7 985 Sx Hood 5 A-8 962 N.W. 0.25 A-9 962 Tool Crib 0.65 A-10 East CRD Mod Area 7 A-11 West CRD Mod Area 5 A-12 TIP Drive Area 2 A-13 TIP Cubicle 30 i A-14 HPCI Turbine Area 0.25 A-15 896 Radwaste Drain Tk Room 6 A-16 RCIC Pump Area 1 A-17 A-RHR Room (East) 10 A-18 B-RHR Room (West) 10 A-19 Chemistry Hot Lab 0.26 l A-20 Control Room Low Range 0.02 A-21 Control Room High Range 3 WP/dw

Procedure A.2-107 Revision 1 Page 12 of 12 Form #5790-107-3 ATTACHMENT 4 Revision 0, 2/25/82 Page 2 of 2 Example of EMERGENCY ARM LOG Normal Current Reading (record time in top box) ARM No. Area Description Reading l l 1 I B-1 Operating Floor - 951 20 l l l B-2 T. G. Front Standard 10 l l l B-3 Cond Demin Operating Area 1 l l l B-4 MVP Room 9 l i B-5 FW Pump Area 1 l I I CI R.W. Control Area 0.2 _C-2 Sample Tank Area - 947 3 C-3 Conveyor Operating Aisle 0.2 0-1 Machine Shop (Hot) 0.2 F e e-

Procedure A.2-204 Revision 2 Page 1 of 19 Op. Com. Rev. Reg'd. Yes X No Q.A. Review Req'd. Yes No X ALARA Review Reg'd. Yes No X OFFSITE PROTECTIVE ACTION RECOMMENDATIONS A.2-204 Prepared by: dd /c,J ha-ALARA Review: Revision 0 Date 03/29/81 M t d kdO C Q.A. Review: Revision 0 Date 03/29/81 I Reviewed by: Operations ComnI[ttee Final Review: Meeting Number //6+ Date /2//v/f z_ Approved by: M MM Date J f-17.P 2. Op. Com. Results Review: Not Required Mtg. # 948 Date 03/25/81 PURPOSE This procedure provides the guidelines to be used in formulating off-site protective action recommendations. The purpose of this procedure is to provide recommendations for off-site protective actions to the Emergency Director. CONDITIONS AND PREREQUISITES A. An emergency condition has been declared. B. A release of radioactive material has occurred, is occurring or is likely. O D ORGANIZATION AND RESPONSIBILITIES A. Overall Responsibility - Emergency Director B. In Charge - Radiological Emergency Coordinator C. Assistance - Off-Site Dose Assessment Section - Monitoring Section PRECAUTIONS l A. Prior to E0F activation, the Emergency Director has the non-delegatable authority for the decision to make off-site protective action recommenda-tions. During this period, all recommendations for protective actions shall be made to the Emergency Director. 8. With the activation of the EOF, the Emergency Manager assumes the authority and responsibility for making off-site protective action recommendations. The Radiological Emergency Coordinator will continue to provide protective action recommendations until relieved by the Emergency Manager. Recommendations formulated during this time will be submitted to the Emergency Manager and should be channeled through the Emergency Director. O WP/kk

Procedure A.2-204 Revision 2 Page 2 of 19 OISCUSSION A. Protective Action Protective actions are measures taken to avoid or reduce the projected dose when the benefits derivej from such action are sufficient to offset any undesirable features of the protective actions. The protective actions in this procedure are limited to protective actions for minimizing the exposure of the public to external and internal radia-tion exposure from passage or inhalation of the radioactive plume and from internal exposure from drinking water. Other protective actions for minimizing public exposure via the ingestion pathway will be determined and implemented by the appropriate State authorities. B. Protective Action Options 1. No Recommendation No protective actions for members of the general public should be recommended for incidents involving radioactive releases which are projected to result in doses less than 250 mrem whole body and/or 1250 mrem thyroid (child). 2. Sheltering a. Sheltering is a protective action which involves members of the general public taking cover in a building that can be made relatively air tight. Although sheltering, particularly in masonry buildings, will also reduce the exposure of personnel to external radiation as the plume passes, this effect is less significant than the corresponding reduction in internal expo-sure. Generally, any building suitable for winter habitation, with windows and doors closed and ventilation turned off, would provide reasonably good protection for about two hours; but would be ineffective af ter that period due to natural ventila-tion of the structure. Sheltering is an appropriate protective action for: Severe incidents in which an evacuation cannot be imnle-mented because of inadequate lead time to the rapid passage of the rlume (" puff" release). When an evacuation is indicated, but local constraints, such as inclement weather, road conditions, etc., dictate that directing the public to seek shelter is a more feasible and effective protective measure than evacuation. As a precautionary measure, while a determination of the need to evacuate is made. b. Sheltering of the general public may be recommended at 250 mrem whole body or 1250 mrem thyroid (child). I WP/kk

Procedure A.2-204 Revision 2 Page 3 of 19 3. Evacuation a. Timely evacuation of members of the population is the most ef fective protective action. There are, however, disadvantages and constraints that may make evacuation inappropriate. Esti-mates of the time necessary to effect an evacuation are tabu-lated in Attachment 9. Evacuation is an appropriate protective action for: Situations where the lead time between declaration of the emergency and population relocation is compatible with plume movement. Situations which do not provide for advance warning, but for which substantial reductions in population dose can be made by avoiding exposure to residual radioactivity (plume fallout) in wake of sudden severe incidents. b. Evacuation of pregnant women and children may be recommended if the whole body dose is expected to exceed 500 mrem. c. Evacuation of the general public may be recommended if the whole body dose is expected to exceed '1000 mrem or thyroid dose is ex'ected to exceed 5000 mrem (child). s ) 4. Thyroid Prophylaxis The effect of thyroid blocking agents, normally potassium iodide (KI), is to saturate the thyroid with stable iodine and significantly reduce the probability of thyroid uptake of radiciodine. Since some individuals may have allergic reactions to KI, it is administered only under medical surveillance. For this reason, offsite thyroid prophylaxis will not be recommended by MNGP personnel. 5. Secure Water Treatment Intakes Recommendations shall be made to downstream watt:r treatment plants to secure taking water from the Mississippi River for liquid releases i when concentrations at the intake are projected to exceed 10CFR20, Appendix B limits for unrestricted areas. St. Paul is the first intake of concern. The assumed dilution factor from Monticello to the St. Paul intake is 7:1. l 6. Public Alert & Notification System (PANS) i The PANS is designed to alert the public within a 10 mile radius of the plant (EPZ). Activation of the PANS should be recommended in the following situations: l A General Emergency has been declared; a. 1 O i WP/kk .-__7 __m ..- ~. mm-.t

Procedure A.2-204'- Revision 2 Page 4 of 19 b. A protecti-action such as sheltering or evacuation has been recommendea for areas within the EPZ and the PANS has not yet been activated. c. A protective action such as sheltering or evacuation has been recommended for areas within the EPZ and the Emergency Director determines that the PANS should be activated, regardless of whether the system has previously been activated. C. Designation of Affected Areas 1. The designation of the area requiring protective actions will depend on several variables, each of which will have to be evaluated at the time of the incident. Major variables, include the nature and extent of the incident, local geography, and existing meteorological condi-tions. Generally, the affected area will resemble a keyhole consist-ing of a circle with a 90 (or larger) wedge shaped sector attached in the downwind direction. 2. Affected areas will be defined by MNGP personnel on the basis of circles of various diameters, and if wind patterns permit, particular sectors beyond the initial circle. County and State authorities have been provided with maps having sector designations identical to those on maps in use at the plarit. PROCEDURE FOR LIOUID RELEASE: STEP 1: If there has been a release to the Mississippi River, estimate the volume and amount of radioactivity released. Initiate Form 5790-204-1 0FF-SITE PROTECTIVE ACTION RECOMMENDATION CHECKLIST, Attachment 8. STEP 2: Determine the MPC Ratio for the release (refer to 10CFR20 Appendix B). STEP 3: Using Attachment 1 of this procedure, estimate the time at which the l release will arrive in the vicinity of the Minneapolis and St. Paul intake. STEP 4 Complete the checklist.. If the MPC ratio exceeds 5.0, advise Emer-gency Director to recommend closing the water intakes. FOR GASEOUS AIRBORNE RELEASE: NOTE: Do not delay recommending protective actions while waiting for off-site monitoring team results, or completion of checklist. STEP 1: Obtain projected dose data generated by Procedure A.2-406 (Off-Site Dose Projection). Initiate Form 5790-204-1, OFF-SITE PROTECTIVE ACTION RECOMMENDATION CHECKLIST, Attachment 8. WP/kk

Procedure A.2-204 Revision 2 Page 5 of 19 NOTE: If actual field data on radiciodine concentrations is v available, attachments 10 and 11 may be used to estimate thyroid inhalation doses and exposure times which would result in a 5 Rem child thyroid dose. STEP 2: Using meteoralogical data, determine the plume direction and wind speed. Evaluate the potential for wind direction shifting as part of the determination. (Either call National Weather Service @ 725-3401 (725-3400 if no answer) or refer to weather information service reports.) STEP 3: Determine how long the release is likely to continue (at greater than tech spec limits) using a conservative or worst case estimate. Calcu-late the expected integrated doses for the affected sectors by combining the dose projections for releases which have already occur-red and the exposure which would result from the current exposure rates over the period the release is expected to continue. STEP 4: Determine the affected area. STEP 5: Using the data accumulated in the foregoing steps, determine the appropriate protective action recommendation by utilizing Attachments 3, 4, 5 and 12. In addition, recommend activation of the Public Alert & Notification System at. the General Emergency level or at the Site Area level if sheltering or evacuation measures are being recommended. O V NOTE: Attachments 6 and 7 may be used to determine the effectiveness of sheltering. has the estimated evacuation times. STEP 6: Use Form 5790-204-1, to record recommendations and to convey informa-tion to Emergency Director. STEP 7: Advise the Emergency Director to make the recommendation for appropriate off-site protective action. NOTE: If the recommendation is being transmitted directly to the State E0C via telecopier, the Minnesota Team Coordinator will be expecting a telephone call simultaneously or prior to transmittal, as is specified in Corporate EPIP's. The purpose of the call is to explain the basis for the recom-mended protective action. STEP 8: Take steps to verify what protective actions are actually implemented and what populations are affected. STEP 9: If, as a result of continuing assessment, dose projection results or meteorological conditions change significantly, re-evaluate the recommended protective action and, if necessary, update the initial recommendation. Complete checklist. O) c WP/kk

Procedure A.2-204 Revision 2 Page 6 of 19 REFERENCES 1. flonticello Nuclear Generating Plant Emergency Plan 2. f4onticello Nuclear Gencrating Plant Operations fianual 3. NUREG-0654/FEf4A-REP-1 " Criteria for Preparation and Evaluation of Radio-logical Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" 4. USEPA 520/1-75-001 (and subsequent revisions) "fianual of Protective Action Guides and Protective Actions for Nuclear Incidents" 5. Title 10 Code of Federal Regulations Part 50, Appendix E ATTACHMENTS 1. Delay Time from Release in River at Plant to Arrival at Minneapolis Intake 2. (Deleted) 3. Recommended Protective Actions to Avoid Whcle Body and Thyroid Dose From Exposure to Gaseous Plume 4. Guidelines for Protection Against Ingestion of Contamination 5. Recommended Protective Actions (by Accident Phase) 6. Representative Shielding Factors from Gamma Cloud Source, and Selected Shielding Factors for Airborne Radionuclides 7. Representative Shielding Factors for Surface Deposited Radionuclides 8. Example of Of f-Si te Protective Action Recommendation Checklist, Form 5790-204-1 9. Evacuation Time Estimates 10. Thyroid Dose Conversion Factors 11. Radiciodine Concentrations Resulting in 5 Rem Thyroid Dose 12. Recommended Protective Actions for Potential Release Situations 13. Percent of Fuel Inventory in Contaw,ent i WP/kk

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Procedure A.2-204 Revision 2 Page 8 of 19 ATTACHMENT 3 RECOMMENDED PROTECTIVE ACTIONS TO REDUCE WHOLE BODY AND THYROID DOSE FROM EXPOSURE TO A GASE0US PLUME Projected Dose (Rem) t The Population Recommended Actions (a) Comments Whole Body ( l No planned protective actions. ) Previously recommended Issue an advisory to seek shelter protective actions may Thyroid ( 5 (child) and await further instructions. be reconsidered or Monitor environmental radiation terminated, levels. Whole Body 1 to ( 5 Seek shelter as a minimum. If constraints Consider evacuation. Evacuate exists, special unless constraints make it consid 3 tion should impractical. be given ror evacua-Thyroid 5 to ( 25 Monitor environmental radiation tion of children and (child) levels. and pregnant women. Control access. Whole Body 5 and above Conduct mandatory evacuation. Seeking shelter would Monitor environmental radiation be an alternative if levels and adjust area for evacuation were n mandatory evacuation based immediately possi Thyroid 25 and above on these levels. (child) Control access. Projected Dose (Rem) To Emergency Workers Whole Body 25 Control exposure of emergency Although respirators team members to these levels and thyroid prophylaxis Thyroid 125 except for lifesaving missions. should be used where (Appropriate controls include effective to control time limitations, respirators dose to emergency and thyroid prophylaxis.) workers, Thyroid dose Whole Body 75 Control exposure of emergency team should not be the limit-members performing a lifesaving ing factor for lifesav-mission to this level. (Control ing missions. of exposure time will be most effective.) (a) These actions are recommended for planning purposes. Protective action decisions at the time of the incident must take existing conditions into consideration. ) At the time of the incident, officials may implement low-impact protective actions in keeping with the principle of maintaining radiation exposures as low as reasonably achievable. WP/kk

Procedure A.2-204 Revision 2 Page 9 of 19 GUIDELINES FOR PROTECTION AGAINST INGESTION OF CONTAMINATION

• I.

Ground Contamination A. Action Levels 1. Projectedwholebodydoseabovethegrgund 1 Rem. 2. GroundContaginationlevels 200yci/m at t = 1 hr post-accident. NOTE 1 pCi/m = 22,000 dpm/100 cm l l 3. Exposure rate 12 mrem /hr at 1 meter above ground at t = 1 hr post-accidei B. Recommended Protective Actions 1. Evacuation of affected areas. 2. Restriction of entry to contaminated offsite areas until radiation i level has decreased to State approved levels. II. Food and Water Contamination A. Action Levels Concentration in Total Intake Milk or Water via all Pasture (0.5 rem WB or bone: (5 rem WB or bone: Food & Water Grass 1.5 Rem Thyroid) 15 Rem Thyroid) Pathways (Fresh Weight Preventive Level Emergency Level Preventive Emergency Preventive Emergenc: (pCi/1) (pCi/1) (pCi) (pCi) (pCi/kg) (pCi/kg + Nuclide -131 ) Thyroid) 0.012 0.12 0.09 0.9 0.27 2.7 + L s-137 C (Whole 0.34 3.4 7 70 3.5 35 Body) Sr-90 (Bone) 0.007 0.08 0.02 0.2 0.7 7 Sr-89 (Bone) 0.13 1.3 2.6 26 13 130-B. Recommended Protective Actions Preventive Emergency 1. Removal of lactating dairy cows from Isolate food and water from contaminated pasture and substitution its introduction into commerce of uncontaminated stored feed. after considering: 2. Substitute source of uncontaminated a. availability of other water. possible actions; 3. Withhold contaminated milk from market b. importance of particular 1 to allow radioactive decay. food in nutrition; 4. Divert fluid milk to production of c. time and effort to take dry whole milk, butter, etc. action; d. availability of other foods. If other nuclides are present, Reg. Guide 1.109 should be used to calculate the dose to the critical organ (s). Infants are the critical segment of the population. O. +

References:

U.S. Food and Drug Administration, Federal Register, Vol. 43, No. 242, December 15, 1978. j i .i WP/kk

Procedure A.2-204 Revision 2 Page 10 of 19 RECOMMENDED PROTECTIVE ACTIONS ACCIDENT PHASE EXPOSURE PATHWAY EXAMPLES OF ACTIONS TO BE RECOMMENDED EMERGEgCY Inhalation of Evacuation, shelter, access control, PHASE gases, radio-respiratory protection, prophylaxis x (0.5 to 24 hours) iodine, or (thyroid protection). particulate Direct whole Evacuation, shelter, access control body exposure Ingestion of Take cows off pasture, prevent cows from milk drinking surface water, discard contaminated milk, or divert to stored products, such as cheese. INTERMEDIATE Ingestion of Wash all produce, or impound produce, PHASE ' fruits and delay harvest until approve substi-tute uncontaminated produce. Ingestion of Cut off contaminated supplies, substitute water from other sources, filter, demineralize. (24 hours to Whole body Relocation, decontamination, access ~ 30 days)

• exposure and control.

inhalation Ingestion of Decontamination, condemnation, or food and water destruction of food; deep plowing, contaminated condemnation, or alterate use of LONGTgRM frorr, the soil land. PHASE either by resus-i pension or uptake through roots. Whole body expo-Relocation, access control, decontamination, sure from deposi-fixing of contamination, deep plowing. (Over 30 days)* tion material or inhalation of resuspended material 1 2 Emergency Phase - Time period of major release and subsequent plume exposure. Intermediate Phase - Time period of moderate continuous release with plume 3 exp sure and contamination of environment. I Long Term Phase - Recovery oeriod. " Typical" Post-Accident time periods. WP/kk

Procedure A.2-204 Revision 2 ~ Page 11 of 19 {] v REPRESENTATIVE SHIELDING FACTORS FROM GAMMA CLOUD SOURCE Shielding Structure or Location Factor (a) Representative Range Outside

1. 0 Vehicles 1.0 Wood-Frame House (b) 0.9 (No Basement)

Basement of Wood House 0.6 0.1 to 0.7 (c) Masonry House (No Basement) 0.6 0.4 to 0.7 (c) Basement of Masonry House 0.4 0.1 to 0.5 (c) Large Office or Industrial 0.2 0.1 to 0.3 (c, d) Building ^ ( i (a) The ratio of the dose received inside the structure to the dose that kl would be received outside the structure. (b) A wood frame house with brick or stone veneer is approximately equivalent to a masonry house for shielding purposes. (c) This range is mainly due to different wall materials and different geometries. (d) The shielding factor depends on where the personnel are located within the building (e.g., the basement or an inside room). SELECTED SHIELDING FACTORS FOR AIRBORNE RADIONUCLIDES Wood house, no basement 0.9 Wood house, basement 0.6 Brick house, no basement 0.6 Brick house, basement 0.4 Large Office or Industrial Building 0.2 Outside 1.0 Taken from SAND 77-1725 (Unlimited Ralease) O v WP/kk

Proccdure A.2-204 Revision 2 Page 12 of 19 REPRESENTATIVE SHIELDING FACTORS FOR SURFACE DEPOSITED RADIONUCLIDES REPRESENTATIVE REPRESENTATIVE STRUCTURE OR LOCATION SHIELDING FACTOR (a) RANGE 1 m above an infinite smooth 1.00 surface 1 m above ordinary ground 0.70 0.47 - 0.85 1 m above center of 50-ft roadways, 0.55 0.4 - 0.6 50% decontaminated Cars on 50-ft road; Road fully contaminated

0. 5 0.4 - 0.7 Road 50% decontaminated 0.5 0.4 - 0.6 Road fully decontaminated 0.25 0.2 - 0.5 Trains 0.40 0.3 - 0.5 One and two-story wood-frame 0.4 0.2 - 0.5 house (no basement)

One and two-story block and 0.2 (b) 0.04 - 0.40 brick house (no basement) House basement, one or two walls 0.1 (b) 0.03 - 0.15 fully exposed: g) One story, less than 2 f t. of 0.5 0.03 - 0.07 basement, walls exposed Two stories, less than 2 ft of 0.03 (b) 0.02 - 0.05 basement, walls exposed Three-orfourstgrystructures, 5000 to 10,000 ft per floor; First and second floors: 0.05(b) 0.01 - 0.08 Basement 0.01 (b) 0.001 - 0.07 Multjstorystructures,10,000 ft per floor: Upper floors 0.01 ( 0.001 - 0.02 ) Basement 0.005 0.001 - 0.015 (^) The ratio of dose received inside the structure to the dose that would be received outside the structure. () Away from doors and windows. Taken from SAND 77-1725 (Unlimited Release) WP/kk

Procedure A.2-204 Revision 2 Page 13 of 19 /~'T ATTACHMENT 8 (,_/ Form 5790-204-1 Revision 3, 12/14/82 Fage 1 of 2 Example of 0FF-SITE PROTECTIVE ACTION RECOMMENDATION CHECKLIST FOR LIQUID RELEASE: 1. Release volume:

Release activity

Delay times: Minneapolis hrs; St. Paul hrs. . Date/ Time of Release: i Protective Action Recommendation: None Secure intakes REC Initials Time Date 2. Communicated release information to Emergency Director. (} REC Initials Time Date FOR AIRBORNE RELEASES 1. Review latest off-site dose projections. REC Initials Time Date 1 l 2. Record plume direction and speed, l plus associated date and time on Page 2 of this form. REC Initials Time Date 3. Indicate recommendations on Page 2 of this form. l REC Initials Time Date i 4. Detach Page 2 and forward to Emergency Director. Review recommendation with same. REC Initials Time Date i i NOTE: After this checklist is completed and is not required for immediate use, it'shall be placed in the appropriate container provided for O Emergency Records. WP/kk ~

Procedure A.2-204 Revision 2 Page 14 of 19 ATTACHMENT 8 (Cont'd.) Form 5790-204-1 Revision 3, 12/14/82 Page 2 of 2 Example of PROTECTIVE ACTION RECOMMENDATION CHECKLIST P S OTE C* '*l' tCTT?: U E r ^ \\T M*? c'2C L !';* (

• g "0TE:

g e '.aen tnis for= is Q

• ,* A -,

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• j s,.'

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1. t 4

zones as follows: s S for sheltering 5* .[ S [forevacuation ' ~ ~

• su tJ 5g e.

p 5 t Date Ti=e Wind direction /soeed At Fros (=pn) P R OTE CT !'. TION SH'LTE?. Sector (s) Mile (s) e.. f Sector (s) Mile (s) NY h CONSIDER EVACL'ATION OF h PREGNA!!T WOME!! A:0 CHILDREN ,f, ,Q W',J,a Y.O W hEVAC"ATIO?: c) Sector (s) Mile (s) 44,j eM:2 /[c 3%.2.%s %y;. ) (%d A Sector (s) Mile (s) 1 6 xx b \\ l ) W ACTIVATE PU3I.IO ALERT & ?'OT!?ICATIO?! SYSTEM h;' Sh g [gi CLOSE MI!:EAPOLIS & ST PA"L WATER INTAK'"S ,f yg'2 (for "anticella liquid releas e ) (?C.Q fp-- @~ C0'TA"INATIN CONT'tCL Sector (s) !'ile ( s ) ( food, water 211k) Sector (s) "ile(3) CCNSIOC1 TERMINATIC CF P'i.')TECT!"E ACTIO';S IN P'CG:tESS 1 Justification for Protective \\ction Deco.=endations: Prearea \\ppr m w E :e r ency Ma nne r/ ;.ne ri;e nc y urector 1 O WP/kk

Procedure A.2-204 Revision 2 Page 15 of 19 ATTACHMENT 9 EVACUATION TIME ESTIMATES

• DISTANCE EVACUATION TIME (MIN)

ZONE SECTORS (MILES) POPULATION BEST/ ADVERSE / CONFIRM M-1 Q-F 0-2 266 10/13/26 M-2 G-P 0-2 509 10/13/26 ~ M-3 Q-B 0-5 1099 22/29/58 M-4 C-F 0-5 1766 22/29/58 M-5 G-K 0-5 4573 22/29/58 M-6 L-P 0-5 1133 22/29/58 M-7 Q-B 0 - 10 2855 42/55/110 M-8 C-F 0 - 10 6609 42/55/110 M-9 G-K 0 - 10 8890 56/73/146 O a-o '-e o - 1o se2o 42'ee'11o Taken from Minnesota Radiological Emergency Response Plan i i O WP/kk

Procedure A.2-204 Revision 2 Page 16 of 19 ATTACHMENT 10 Thyroid Dose Conversion Factors Ratio of a child thyroid inhalation dose to radiolodine concentration, RIC, as a function of time af ter reactor shutdown at which exposure begins and the inhalation exposure duration C 3

RIC,

" P' ' " "8' 8 g C /m3 at which cxposure starts (br) 1.0/hr 2.0/hr 3.0/hr 4.0/hr 6.0/hr 12.0/hr 1.0 5.0E+05 9.8E+05 1.4E+06 1.9Et06 2.8E+06 5.2E+06 2.0 5.6E+05 1.1E+06 1.6E+C6 2.1E+06 3.2E+06 5.9E+06 3.0 6.1E+05 1.2E+06 1.8E406 2.3E406

3. 4 E+06 6.5E+06 4.0 6.5E+05 1.3E+06 1.9E+06 2.5E+06 3.7Et06 7.0-.06 6.0 7.1E+05 1.4E+L6 2.1Et06

2. 8 E+ 06 4.1E+06 7.7E+06 12.0 8.4E+05 1.7E+06 l

2.5E+06 3.3E+06 4.9E+06 9.3E+06 i NOTE: Adult thyroid doses are approximately 50% of child thyroid doses. l O WP/kk

Procedure A.2-204 Revision 2 Page 17 of 19 ( ATTACHMENT 11 Radioiodine Concentrations Resulting in 5 Rem Thyroid Dose Radiolodine concentration in air which would result in a 5 rem thyroid inhalation dose to a child as a function of time after reactor shutdown, (C1/m3)a, at which t exposure begins and the inhalation time Inhalation Time Time after Shutdown, ta 1.0/hr 2.0/hr 3.0/hr 4.0/hr 6.0/hr 12.0/hr (br) Radioindine concentration yielding 5 rem thyroid dose to cht1d (C1/m3) 1.0 1.0E-05 5.1E-06 3.5E-06 2.6E-06 1.8E-06 9.5E-07 2.0 8.9E-06 4.5E-06 3.1E-06 2.3E-06 1.6E-06 8.4E-07 3.0 8.2E-06 4.2E-06 2.8E-06 2.1E-06 1.5E-06 7.7E-07 (% 4.0 7.7E-06 3.9E-06 2.6E-06 2.0E-06

1. 4 E-06 7.2E-07 6.0 7.1E-06 3.6E-06 2.4E-06 1.8E-06 1.2E-06 6.5E-07 12.0 5.9E-06 3.0E-06 2.0E-06 1.5E-06 1.0E-06 5.4E-07 NOTE:

Adult thyroid doses are approximately 50% of child thyroid doses. WP/kk

Procedure A.2-204'* Revision 2 Page 18 of 19 ATTACHMENT 12 Recommended Protective Actions For Potential Release Situations NOTE: Situation is presented in progressively degrading sequence. - Core melt sequence with no significant releases taking place from containment - Large amounts of fission products not yet in containment atmosphere PROTECTIVE ACTION: 2 mile precautionary evacuation - If large amounts of fission products (> gap activity ) are in containment atmosphere PROTECTIVE ACTION: 5 mile precautionary evacuation in 45 - 90 sector downwind and sheltering in other parts of EPZ - If containment failure leading to direct atmospheric release is likely in the sequence but not imminent PROTECTIVE ACTION: precautionary evacuation 5 miles in all directions and 10 miles downwind (45 - 90 sector) - If containment failure leading to direct atmospheric release is judged imminent PROTECTIVE ACTION: recommend sheltering in areas where evacuation cannot be completed before transport of activity to that location A Containment activity may be determined by referring to Al.tachment 13, PERCENT OF FUEL It1 VENT 0RY IN THE CONTAINMENT. The 10% curve represents the gap activity. Plot the point corresponding to the containment monitor reading versus time after shutdown. If the point is above the 10% curve, the containment activity exceeds the gap activity. An alternative method is to samnle containment activity concen-tration and calculate total activity. The gap activity at shutdown is approxi-mgtely 100 meggcuries. The free air volumes of the drywell and torus are 3800 m and 3000 m respectively. 1 O WP/kk

~ Procedure A.2-204 Revision 2 Page 19 of 19 ATT.iC!!MEffT I 1 C't 6 Percent of Tuci Inventory Airborne in the Containment W __ 2001 Fuel Inventery = 100% Noble Cases y + 25% Iodir.e 10 3 j p 1% particulates + h ~ t m 0, N-2004 s v ~ g - ~ 0 l0 g 10% ua 0 4 o to - ii 100 % L gap 3 e 10 2 O.1 i n ~ c t u lo - E 0.01 i c ,q ] $ !M, } 5 1 0.001s s c to -~} o ' 10".' J 4 3 6 7hT10' 2 3 4 3 6)n710' 2 3 4 $ 6 m '1 0* 2 3 4 $b70 10 Time After Shutdn,t (Hrs) t Fuel l Invente:'; Apprcy.i= ate Source and Damage Eqtimate l Peleased l 100. 100% TID-14644, 2004 fuel damage, potential core melt. 50. 50t TID noble gases, TMI source. 10. 101 TID, 2001 NRC gap activity, tctal clad failure, partial ccre uncovered. 3. 31 TID, 2001 WASH-1400 gap activity, =ajer clad failure. 1. In TID, 10% NRC gap, Max. 10% clad failure. .1 .1% TID, 11 NRC gap, 11 clad failure, local heating of 5-10 fuel asse=blies. .01 .011 TID,.it'NRC gap, clad failure of 3/4 fuci element (36 rods). l 10-3 .01% NRC gap, clad failure of a few rods. 10-4 100% coolant release with spiking. 5x10-6 100% coolant inventory release. 10-6 Upper rance of no =al airborne noble gas WP/kk activity in containment. i

Procedure A.2-401 },- Revision 2 Page 1 of 8 l Op. Com. Rev. Req'd. Yes X No Q. A. Review Reg'd. Yes No X ALARA Review Req'd. Yes X No 1 EMERGENCY EXPOSURE CONTROL A.2-401 Prepared by: hh / idb+- ALARA Review: 6d/l/d[uh l'!2 Date L Reviewed by: %2.[id%('J1C Q. A. Review: Revision 0 Date 3/28/81 Operations Commi$ tee Final Review: Meeting Number. //63 Date /.2 /9//1 i Approved by: Y i h-d Date #2 - 14 4 L Op. Com. Results Review: Not Reouired Mtg. # " 949 Date 3/26/81 PURPOSE This procedure provides guidance and criteria for the authorization of personnel exposure 'e

• iation in excess of legal or administrative limits during an emergency.

CONDITIONS AND PREREQUISITES A. An emergency condition at the Monticello Nuclear Generating Plant has resulted in radiation levels within the plant greatly in excess of normal levels and special considerations are required for exposure control. 8. It has been determined that individual doses for a job are expected to result in an individual exceeding his/her plant administrative limit. C. Persons authorized to exceed normal limits shall be emergency workers i.e. performing emergency functions. PRECAUTIONS i A. Personnel shall not enter any area where dose rates are unknown and unmeasur-able or when dosimetry is.not immediately available. B. Appropriate dosimetry equipment, which is capable,of measuring the anticipated maximum exposure and type of radiations, shall be worn. C. Extremity dosimeters shall be worn if anticipated that extremity exposure is greater than about five (5) times that of the whole body. 1 PERSONNEL REQUIREMENTS i Radiation Protection Specialist procedure implementation i Radiological Emergency Coordinator - review Emergency Director - approval O WP/kk

Procedure A.2-401 Revision 2 Page 2 of 8 DISCUSSION A. General 1. The exposure of personnel during emergency operation shall be maintained as low as reasonably achievable, and should be maintained less than the administrative guides established in the MNGP Operations Manual Section E.1. 2, and/or less than the Federal radiation exposure standards established in 10CFR20 if practicable. 2. In order to accomplish this objective, administrative means used during normal operations to minimize personnel exposure (such as radiation work permits and ALARA measares) should remain in force to the extent consis-tent with timely implementation of emergency measures. 3. If necessary operations require personnel exposures in excess of the normal limits, or if normal access control and radiological work practices will resuli in unaccept ule delays, the Radiological Emeraency Coordinator may, at his discretion, waive or modify the established exposure control criteria and methods in accordance with the provisions of this procedure. In making such decisions, the Radiological Emergency Coordinator should call upon the expertise of the radiation protection staff onsite, if readily available. B. Authority The Emergency Director has the authority to perform appropriate protective a corrective measures necessary to mitigate the consequences of an accident ano to place the facility in a safe condition. If necessary to affect these measures, the Emergency Director may direct the Radiological Emergency Coordi-nator to approve personnel exposures in excess of normal guides / limits, but not greater than the planned radiation exposure criteria established in this procedure, provided the pre-conditions of such exposure are met. The Radio-logical Emergency Coordinator shall be the only individual besides the Emergency Director authorized to permit emergency exposure. C. Emergency Exposure Criteria The exposure received pursuant to the performance of emergency measures should be commensurate with the significance of the action to be performed ano should be maintained at a level which is as low as reasonably achievable (ALARA). Criteria for emergency exposures are established in Attachment 1. The basis for these criteria are as follows: 1. In order to avoid restricting actions that may be necessary to save lives, it shall be the discretion of the Emergency Director that deter-mines the amount of exposure that will be permitted in order to perform the emergency mission. However, in no case will the exposure be permit-ted to exceed 75 rem. Volunteers will be advised as to the effects of large doses. 2. In situations where the bodies of accident victims are in areas inacces sible because of high radiation field, special planning and remot. recovery devices should be used to retrieve the bodies. Exposure of recovery personnel should not exceed 25 rems. WP/kk

Procedure A.2-401 Revision 2 Page 3 of 8 3. If it is necessary to secure or retrieve equipment related to public 4 d safety, personnel may be allowed to receive up to 25 rem. When the risk is such that life would be in jeopardy or there would be severe ef fects on the health arid safety of the public, volunteers may receive up to 75 rem expe:ure. Volunteers will be advised as to the effects of large i doses. 4. Medical treatment, first aid, ambulance service and decontamination personnel should not exceed 3 rem. D. Considerations and Conditions 1. Personnel receiving increased exposure should be volunteers or profes-sional rescue personnel (eg.: firemen who " volunteer" by choice of employment). I 2. Personnel should be broadly familiar with the consequences of any exposures received under emergency conditions as per Attachment 2. 3. Women in their reproductive years should not take part in these actions. 4. Exposuresundertheseconditionsshouldbelimitedtoonceinalifetime, i 5. Internal exposure should be minimized by the use of appropriate respira-tory equipment, and contamination should be controlled by the use of appropriate protective clothing. 6. Volunteers above age of 45 are recommended. j 4 l E. Post-Exposure Evaluations 1 Personnel receiving exposures under emergency conditions should be restricted l from further occupational exposure pending the outcome of exposure evaluations and, if necessary, medical surveillance. PROCEDURE In the event a planned emergency exposure is necessary, the following actions should be performed. Although it is preferable to perform and document these steps i l prior to the exposure, if necessary, the Emergency Director may verbally authorize i the increased exposure and comolete the documentation at a later time. STEP 1: Complete Section A of the Emergency Exposure Authorization Form, i

1. 5790-401-1, (Attachment 3).

STEP 2: Brief the individual on the radiological and other conditions in the area (or expected in the area), the tasks to be performed, ALARA m0asures applicable to the tasks, contingency measures and effects of acute exposures (if applicable), prior to entry to the affected j area. 1 I STEP 3: Ensure that the individual to receive the increased exposure completes Section 8 of the Emergency Exposure Authorization form. WP/kk ~ - -,,, - - -. - - - - - - - - - - ~ ~ - - - - -

Procedure A.2-401'- Revision 2 Page 4 of 8 PROCEDURE (Cont'd. ) STEP 4: Submit the form to the Radiological Emergency Coordinator for review and the Emergency Director for approval. Completed form should go to Radiological Emergency Coordinator for recording and filing. REFERENCES 1. f1onticello Nuclear Generating Plant Emergency Plan 2. Monticello Nuclear Generating Plant Operations Manual 3. Title 10, Code of Federal Regulations, Part 20 4. NUREG-0654/ FEMA-REP-1, " Criteria for Preparation and Esaluation of Radiological Emergency Response Plans and Preparedness in Support

f Nuclear Power Plants" 5.

EPA-520/1-75-001, " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents" ATTACHMENTS 1. Example of Emergency Exposure Guidelines 2. Example of Effects of Acute Exposures 3. Example of Emergency Exposure Authorization Form l l l WP/kk

Procedure A.2-401 Revision 2 Page 5 of 8 (] ATTACHMENT 1 V Page 1 of 1 EMERGENCY EXPOSURE GUIDELINES Lifesaving / Protection Emergency Of Public Health And (Non-Lifesaving) Safety Activities Activities Whole Body Thyroid Whole Body Thyroid Dose (Rem) Dose (Rem) Dose (Rem) Dose (Rem) Undertaking Corrective Actions 75 25 125 Performing Assessment Actions 25 125 Providing First Aid 75 25 125 Pertorming Personnel Decontamination 3 15 m Providing Ambulance Services 3 15 Providing Medical Treatment 3 15 Performing Search and Rescue Operations 75 25 125 Removal of Injured Persons 75 25 125 Recovery of Dead 25 125 No specific upper limit is given for thyroid exposure since in the extreme case complete thyroid lost might be an acceptable penalty for a life saved. However, this should not be necessary as respirators and/or thyroid protection for rescue personnel are availab!a. It is unlikely that lifesaving guidelines will be necessary if exposures are maintained as low as practicable; however, should they be necessary, guidelines shall be consistent with other ,.s ( ) " Lifesaving / Protection of Public Health and Safety Activities". WP/kk

Procedure A.2-401 ' Revision 2 Page 6 of 8 ATTACHMENT 2 Parje 1 of 1 EFFECTS CF ACUTE EXPOSURES Acute Dose (Rem) Probable Effect 0-50 No obvious effect, except possibly minor blood changes. 80-120 Vomiting and nausea for about 1 day in 5 to 10 percent of exposed personnel. Fatigue but no serious disability. 130-170 Vomiting and nausea for about 1 day, followed by other symptoms of radiction sickness in about 25 percent of personnel. No deaths anticipated. 180-220 Vomiting and nausea for about 1 day, followed by other symptoms of radiation sickness in about 50 percent of personnel. Parely aeath may occur. 270-330 Vomiting and nausea in nearly all personnel on first day, followed by other symptoms of radiation sickness. About 20 percent deaths within 2 to 6 weeks after exposure; survivors convalescent for about 3 months. 400-500 Vomiting and nausea in all personnel on first day, followed by other symptoms of radiation sickness. About 50 percent deaths within 1 month; survivors convalescent for about 6 months. 550-750 Vomiting and nausea in all personnel within 4 hours from exposure, followed by other symptoms of radiation sickness. Up to 100 percent deaths; few survivors convalescent for about 6 months. 1000 Vomiting and nausea in all personnel within 1 to 2 hours. Probably no survivors from radiation sickness. 5000 Incapacitation almost immediately. All personnel will be fatalities within 1 week. O WP/kk

l .~ Procedure A.2-401 Revision 2 Page 7 of 8 / ATTACHMENT 3 Form 5790-401-1 Revision 3, 11/23/82 Page 1 of 2 Example of, EMERGENCY EXPOSURE AUTHORIZATION FORM SECTION A CAUTION: If the E0 has verbally authorized the emergency exposure, complete the documentation at a later time. ~ 1. Name of Individual to Receive Exposure: Social Security Number: 2. Individual Badge Number: Employer /NSP Department: 3. Task (s) to be Performed: 4. Date of Authorization: Authorized Limit: 5. Conditions: Individual is a volunteer or professional rescue person. h) _ Individual is broadly familiar with radiological consequences of exposure. Woman capable of reproduction has been advised not to take part (Reg. Guide 8.13). Individual has not received an emergency exposure before. Dose rates in area known/ measurable. Undertaking corrective actions Performing assessment actions Providing first aid Performing personnel decontamination Providing ambulance services Providing medical treatment Performing search and rescue operations Removal of injured persons Recovery of dead Individual has been briefed per STEP 2 of Procedure A.2-401. 6. Radiation Protection Specialist: Date: Signature AV WP/kk

Procedure A.2-401 Revision 2 Page 8 of 8 ATTACHMEf1T 3 Form 5790-401-1 Revision 3, 11/23/82 Page 2 of 2 Example of EMERGENCY EXPOSURE AUTHORIZATI0ff FORM (Cont'd. ) SECTI0f1 B I have been briefed on the radiological consequences of the proposed emergency exposure, and I have volunteered to perform the emergency actions during which I will receive the emergency exposure. 7. Signature: Date: SECTI0fl C 8. Reviewed: Radiological Emergency Coordinator Date 9. Approved: Emergency Director Date NOTE: After this form is completed and is not required for immediate use, it shall be placed in the appropriate container provided for emergency records. O WP/kk

Procedure A.2-402 Revision 1 Page 1 of 8 Op. Com. Rev. Reg'd. Yes X No Q.A. Review Reg'd. Yes No X (7 ALARA Review Req'd. Yes X No V CONTAMINATION CONTROL A.2-402 /!/L-Prepared by: 6 h I2't. / L ua_ ALARA Review: d"d/Ia 1' e Date // Reviewed by: W C,vC^d M p Q.A. Review: Revision 0 Date 3/29/81 OperationsCommitteeFinalReview: Meeting Nu ber, // v 3, Date /? /4 h.1-J Approved by: i JEAd Date 12 /4f-- Ra_ Op. Com. Results Review: Not Required fdg. # 949 Date 3/26/81 PURPOSE The purpose of this procedure is to provide contamination control guidelines for certain emergency conditions. This procedure applies to those situations involving large spills or release of radioactive material, and/or contaminated personnel. The procedure for onsite monitoring contains a reference to this procedure which ensures implementation when appropriate. The Radiological Emergency Coordinator has the authority to invoke the emergency contamination limits at his discretion. ,A Normal limits will be adnered to as much as possible. CONDITIONS AND PREREQUISITES A. An emergency condition has been declar(d at the Monticello Nuclear Generating Plant as provided by the MNGP Emergency Plan, and B. A radioactive spill, release, or other event has caused significant levels of radioactive contamination, and/or C. There is reason to suspect that personnel may have become contaminated (e.g., portal monitor alarm while personnel are exiting controlled area). PRECAUTIONS A. Personnel entering a contaminated area must be properly attired in protective clothing, respiratory equipment, etc., in accordance with normal plant operat-ing procedures and any Radiation Work Permit (s) that may be in force. B. Medical treatment /first aid to seriously injured individuals and personnel safety always take priority over contamination control measures. C. Definitive detection of inhalation or ingestion of radioactive material depends on positive findings of radionuclides in urine, feces or the body by "whole-body counting" or excreta analysis. It is extremely important to identify " potential inhalation / ingestion" cases so that definitive b evaluation may be initiated. V WP/kk

~ Procedure A.2-402 Revision 1 Page 2 of 8 0. The Health Physics Group is responsible for controlling all food and water supplies at the plant during an emergency, Whenever an evacuation due to radiological conditions takes place, all food and water supplies within the evacuated area will be considered conta...inated and measures will be taken to prevent their use. E. Before any water or food may be consumed, the Health Physics Group must verify that the water / food itself and the eating surfaces are below emergency contamination guidelines for personnel (Attachment 1). Random samples of food / water shall be analyzed for low level contamination on a periodic basis. ORGANIZATION Radiological Emergency Coordinator - in charge Monitoring Section Leader - direct supervision Radiation Protection Specialists - conduct of this procedure DI5CUSSION This procedure is divided into two parts: 1. Radioactive Spill or Release 2. Contaminated Personnel Each part may be implemented separately or both may be implemented in parallel, depetiding on the situation. PROCEDURE NOTE: Document all surveys and measurements using appropriate data forms. RADI0 ACTIVE SPILL OR RELEASE: NOTE 1: This portion of the procedure applies only to a spill or release resulting in significantly elevated levels of contamination in plant or elsewhere on site. l STEP 1: If possible to do so in a safe manner, take immedicte steps to terminate the spill or release. STEP 2: Take steps to mitigate the consequence of the spill or release, e.g., perf orm the following actions as appropriate: a. Inform others in the area. b. Secure ventilation. Inform the Radiological Emergency Coordinator (Emergency c. Director or Shift Supervisor if REC not available). d. Contain the contamint.ted area by barricading, closing doors, etc. WP/kk

a ~ Procedure A.2-402 Revision 1 Page 3 of 8 PROCEDURE (Cont'd.)- e. ~If personnel were contaminated or are suspected to be, and must be moved, consider having them don clean, protective clothing to a contain the contamination. STEP 3: Monitor the area to determine the extent of the contamination spread. Smear and radiation / airborne surveys should be in accordance with normal plant procedures. Report conditions through supervisory channels. 9 STEP 4: Properly barricade and post the area in accordance with normal plant procedures and the guidelines in Attachment 1. Inforn OSC Coordinator j and update plant area status maps at OSC. j CONTAMINATED PERSONNEL STEP 1 Monitor personnel suspected of being contaminated. Use an RM-14 with HP-210 probe or equivalent instrumentation and detector., STEP 2 If contamination is found: j a. Attempt to reduce skin contamination levels to background by 4 employing normal decontamination procedures. Applicable limits are shown in Attachment 1. b. Contaminated clothing should be decontaminated, confiscated or modified to reduce contamination levels to the levels specified for skin. c. If circumstances make decontamination impracticable, clean protective clothing may be employed to minimize the spread of contamination. 1 d. Record survey results for individuals found to be contaminated. 1 I-STEP'3: If inhalation of radioactive material is suspected, determine if the individual is a potential inhalation case as follows: 3 NOTE 1: Exposure to airborne contamination, whether the employee was or was not using respiratory protective equipment, l places him in the group of " potential inhalation cases". NOTE 2: A positive Geiger-Mueller or alpha survey or a positive smear survey in the area of the nose and mouth places the employee in the category of " potential inhalation i cases". a. Smear sterile moistened cotton tipped applicator cently about the openings of the nose (not deep in the nose) and 2 then count. Detectable radiation places the individual in i the category of a " potential inhalation case". WP/kk i a ,-.m- -v- , =. v .-w .w--- ,,w t-

Procedure A.2-402 '- Revision 1 Page 4 of 8 b. All persons considered as " potential inhalation cases" will be given a body burden analysis. STEP 4: If ingestion of radioactive materials is suspected, determine if the individual is a potential ingestion case as follows: NOTE: A positive Geiger-Mueller or alpha survey or a positive smear survey in the area of the mouth places an individual in the group of potential ingestion cases. a. Smaar a sterilo cotton tipped applicator within the mouth and count. Alsc. have the individual gargle with one ounce of water for 30 seconds, collect water and count. A positive result from either sample places an individual in the group of potential ingestion cases. b. All individuals considered to be in the " potential ingestion group" will have body burden analysis initiated as in the potential inhalation group. STEP 5: Report all results to the Radiological Emergency Coordinator and assure that individuals requiring followup analyses, decontamination, etc., are properly attended to. REFERENCES O 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. Emergency Contamination Guidelines 2. Example of Personnel Contamination Record 3. Example of Nasal Smear Test Data 4. Example of Contamination Control Checklist - Spills and Releases 5. Example of Contamination Control Checklist - Personnel O WP/kk

Procedure A.2-402 Revision 1 Paga 5 of 8 6/ ATTACHMENT 1 Page 1 of 1 s CONTAMINATION LIMIT GUIDELINES Transferrab}e Fixed (dpm/100 cm ) (cpm W/HP-210) Normal Limits Personnel, Clothing, & < 100 0 y < 100 Unrestricted Area < 10 a Clean Area < 100.0 y < 1000 < 10 a Unposted Parts of < 500 p y ( < 2.5 mr/hr) Controlled Area < 50 a Emeraency Limits Personnel < 100 0 y < 100 < 10 a (') Food & Eating Areas < 100 p y < 100 (On-Site) < 10 a Clean Area < 5000 0 y ( < 2.5 mr/hr) < 500 a Equipment Released < 2200 p y < 1000 To Unrestricted < 220 a Area Personal Clothing < 1000 0 y < 1000 < 100 a V WP/kk ^

Procedure A.2-402'- Revision 1 Page 6 of 8 ATTACHMENT 2 Form #5552 Revision 0 PERSOfif1EL C0f1TAMIf4ATI0tl RECORD 07/18/75 NAME COMMENTS: EMPLOYER JOB TITLE Part Before Decon After Decon of Smearable Fixed Smearable Fixed Date Time Body dom com dpm cpm Initials i M. A Is yy Yh ^ h.-;(kh\\ -a p> 1 sm?$ :50 qw-- e WP/kk

Procedure A.2-402 Revision 1 Page 7 of 8 / i ATTACHMENT 3 L]

1. 5566 NASAL SMEAR TEST DATA Revision 1 7/7/78 Area Individual Net a

Name Date Time Was In CPM OPM A gy;*' -h e A Abbb'%Y

5. y 9v W

ex(J ) ^' Q l i t

• If > 1000 dpm af ter 4 hours decay, perform Body Burden Analysis (BBA).

i l WP/kk i l

Procedure A.2-402 Revision 1 Page 8 of 8 ATTACHMENT 4 Form 5790-402-2 Revision 1, 12/11/81 Page 1 of 1 Example of CONTAMINATION CONTROL

SUMMARY

CONTAMINATED PERSONNEL POTEl4TIAL POTENTIAL FRISK RESULTS INHALATION INGESTION INDIVIDUAL BETA-GAMMA ALPHA CASE (YES/N0) CASE (YES/NO) DISPOSITION o/gs# Completed: Radiation Protection Specialist Date Reviewed: Radiological Emergency Coordinator Date NOTE: When this form is completed and not required for immediate use, transmit to the Health Phyeics Group Leader for filing. WP/kk

Procedure A.2-422 Revision 0 Page 1 of 5 Op. Com. Rev. Req'd. Yes 4 No Q.A. Review Req'd. Yes No x ALARA Review Req'd. Yes X No , STACK IODINE / PARTICULATE SAMPLING AND ANALYSIS Procedure A.2-422 Date 7[t?!/L Prepared by: 6 .<rrwALARA Review: Ce /d c+m-Reviewed by:NdidML-Q.A. Review: M 8 7/A d W Date 1/2. T/f2__ Operations Committee Final Review: Meeting Numbe : //ho Date 7/29/rx Approved by: )M Date / ') - /- P 2-I Op. Com. Results Review: AG/ /buder/ Mtg. # k/co Date 7/29 /r2 - C PURPOSE The purpose of this procedure is to provide special instructions, precautions, and guidance for collection, handling and analysis of stack iodine / particulate samples during and following an emergency at Monticello Nuclear Generating Plant. CONDITIONS AND PREREQUISITES Actual er potential radiological conditions are such that special methods and/or precautions are necessary in order to collect and analyze samples under conditions which may present a much greater than normal radiation hazard to individuals O-performing the sampling and analyses. Unless directed otherwise, this procedure should be used in lieu of routine sampling and analysis procedures whenever an Alert or higher emergency classification is declared. ORGANIZATION AND RESPONSIBILITIES Emergency Director - Overall responsibility Rb'/CSL - Responsible for assigning sample priority and frequency and results review. Chemistry Technicians - Responsible for sample collection, analysis and results reporting. PRECAUTIONS A. Exposures of sampling and analysis personnel shall be in accordance with l A.2-401, " Emergency Exposure Control". l. B. Exposures to all personnel due to sampling and analysis operations should be maintained as low as is reasonably cchieveable. Techniques such as temporary shielding, remote handling and sample dilution prior to analysis should be considered to reduce exposure to personnel. O WP/kk I

Procedure A.2 422 Revision 0 Page 2 oi' 5 PRECAUTIONS (Cont'd.) C. When actual or potential radiation levels so warrant, high range portable survey instruments, and self-reading dosimeters shall be provided to ) sampling and analysis personnel to permit rapid assessment of high exposure rates and accumulated personnel exposure. Alarming dosimeters should also be considered. D. Appropriate extremity dosimeters should be provided and worn when handling samples whi(.h themselves represent high level radiation sources. REMARKS 1. Prior to sampling, notify the Control Room and advise Shift Supervisor of your intentions. 2. Two-man teams should be used to obtain a post-accident sample when passible. EQUIPMEf4T REQUIRED Radector III or equivalent Pair of tongs (or other remote handling device as appropriate) Filter set with silver zeolite filters loaded if one set already removed PROCEDURE NOTE 1 Obtain key #9 from R.P. Coord. to access stack. STEP 1 Verify that the Hot Lab South hood exhaust is functioning (use small piece of paper to check air flow), if not contact Radiological Emergency Director and continue. STEP 2 Go to the Control Room and set the timer on Stack Wide Range Gas Monitor Channel "A" according to the following chart. Note process flow (item 029 and use the non-zero sample flow items 028 or 033). Activity Timer Setting (1E4 pCi/sec 5 minutes >1E4 pCi/sec (1E5 pCi/sec 90 seconds >1ES pCi/sec (1E6 pCi/sec 30 seconds 31E6 pCi/sec 10 seconds STEP 3 Don all protective clothing, equipment and dosimetry devices as required by the OSC Coordinator. STEP 4 Proceed to the stack sample area as directed by the Emergency Director or his designee while observing Health Physics precautions. STEP 5 Close the four valves on the Grab Sample Filter apparatus. Disconnect and remove the Grab Sample filter holder. Replace previo"s set if already removed. WP/kk

Procedure A.2-422 Revision 0 Page 3 of 5 O PROCEDURE (Cont'd.) U CAUTION: During filter holder changeout monitor radiation levels to ensure letels are below 200 mR/ hour. If levels are above 200 mR/hr, use remote handling device to minimize exposure. STEP 6 Proceed to the hot lab and place the filter set into the south hood. STEP 7 Connect the sample filter holder to the purge air fitting in south hood of hot lab. Open fully the plant air supply valve in the hood and purge the filter holder set into the hood for about 2-3 minutes. If instrument air is not available, use compressed air from the compressed air cylinder located in the Hot Lab. STEP 8 Measure the contact dose rate from the iodine filter. If { 10 mR/hr proceed to STEP 10. STEP 9 If ) 10 mR/hr at contact then measure the dose rate at 1 foot. Calculate ~ the pCi/cc as I-131 using the equation below. Proceed to STEP 11. I-131 pCi/cc = 420 pCi/mR/hr x dose rate (mR/hr) + sample vol (cc) STEP 10 Place the iodine filter into a labeled poly bag and count on the Ge(Li) System for { 1000 seconds. When the count is complete bsV) analyze the resulting spectrum. STEP 11 Calculate tne iodine release rate via the stack. (Use a sample flow of.06 cfm low flow or 1.6 cfm high flow and a process flow of 4300 cfm if WRGM inoperative.) STEP 12 Place the iodine filter into the shielded storage area. STEP 13 Place the particulate filter in a labeled petri dish. STEF 14 Measure the contact dose rate of the filter. If { 10 mR/hr, proceed to STEP 16. STEP 15 If the measured dose rate is > 10 mR/hr measure the dose rate of the filter at one foot. Calcillate the particulates activity in pCi/cc using the equation below. Proceed to STEP 17. Particulate pCi/cc = 610 pCi/mR/hr x dose rate (mR/hr) + sample vol. (cc) STEP 16 Place the particulate filter in a labeled petri dish and count on the Ge(Li) System for { 1000 seconds. When the count is complete analyze the resulting spectrum. STEP 17 Calculate the release rate for particulates from the stack. (Use a sample flow of.06 cfm or 1.6 cfm high flow and a process flow of 4300 cfm if WRGM inoperative.) p\\.) WP/kk

Procedure A.'2'422 Revisian 0 Page 4 of 5 PROCEDURE (Cont'd. ) ~ STEP 18 Place the sample into the shielded storage area. STEP 19 Provide the release rate information to the Radiological Emergency Coordinator and submit the checklist to the Chemistry Section Leader or Radiological Emergency Coordinator. STEP 20 Install fresh silver zeolite cartridge and particulate filter into filter holder. O O WP/kk

Procedure A.2-422 Revision 0 Page 5 of 5 h) Form 5790-422-1 V Revision 0, 5/27/82 Page 1 of 1 Example of STACK IODINE / PARTICULATE ANALYSIS CHECKLIST Initial 1. Hot lab hood readied. 2. Grab Sample Timer set min /sec. 3. Protective clothing and dosimetry. 4. Removed filter set. Time Noted ( hrs, Date: ) 5. Sample to hot lab and purged. 6. If iodine filter { 10 mR/hr, collect spectrum. If ) 10 mR/hr after one hour then calculated iodine activity = pCi/cc 7. Analyze spectrum, calculate release rate. i (Iodine release rate = pCi/sec.) n 8. If particulate filter { 10 mr/hr; collect spectrum. If > 10 mR/hr then calculated particulate activity pCi/cc = 9. Analyze spectrum, calculate release rate. (Particulate release rate = pCi/sec) 10. Provided results for Chemistry Section Leader or Radiological Emergency Coordinator. l l Performed by: Date Reviewed by: CSL or REC Date NOTE: After this checklist is completed and is not required for immediate l use, it shall be placed in the appropriate container provided for l Emergency Records. l l (d WP/kk

~ ~ Procedure A.2-423 Revision 0 Page 1 of 5 Op. Com. Rev. Reg'd. Yes Y No 7 Q.A. Review Req'd. Yes No { ALARA Review Req'd. Yes No ~ %J ~ REACTOR BUILDING VENTS IODINE / PARTICULATE SAMPLING & ANALYSIS Procedure A.2-423 cc, -ALARA Review: (>b/ 'd Datea[27 IL Preparedby.[Ni ReviewedbyN [# Q.A. Review: Ah/ /kt M Date 7/28/f2_ OperationsComitkeeFinalReview: Meeting Number: /)c e Date 7//9/52 _ -4 n -6fM Date / *1 - / - ? t_ Approved by: $ 3 Op. Com. Results Review: 44& [vfui-,/ Mtg. # //c c Date 7/97/11 6 PURPOSE The purpose of this procedure is to provide special instructions, precautions, and guidance for collection, handling and analysis of reactor building vent iodine / particulate umples during and following an emergency at Monticello Nuclear Generating Plant. CONDITIONS AND PRERE0VISITES Actual or potential radiological conditions are such that special methods and/or precautions are necessary in order to collect and analyze samples under conditions 7(V which may present a much greater than normal radiation hazard to individuals ) performing the sampling and analyses. Unless directed otherwise, this procedure should be used in lieu of routine sampling and analysis procedures whenever an Alert or higher emergency classification is declared. ORGANIZATION AND RESPONSIBILITIES Emergency Director - Overall responsibility REC /CSL - Responsible for assigning sample priority and frequency I and results review. Chemistry Technicians - Responsible for sample collection, analysis and results reporting i l PRECAUTIONS l A. Exposures of sampling and analysis personnel shall be in accordance with l A.2-401, " Emergency Exposure Control". l B. Exposures to all personnel due to sampling and analysis operations should be maintained as low as is reasonably achieveable. Techniques such as temporary shielding, remote handling and sample dilution prior to analysis should be considered to reduce exposure to personnel. ( 1q,- l WP/kk A

Procedure A.2-423 Revision 0 Page 2 of 5 PRECAUTIONS (Cont'd.) C. When actual or potential radiatisn levels so warrant, high range portable survey instruments, and self-reading dosimeters shall be provided to sampling and analysis personnel to permit rapid assessment of high exposure rates and accumulated personnel exposure. Alarming dosimeters should also be considered. D. Appropriate extremity dosimeters should be provided and worn when handling samples which themselves represent high level radiation sources. E. Plenum effluent is sampled on the 1001' level of the reactor building. Two matters to be considered are the route to the sample point and how to handle the sample filters. The problem of getting to 1001' reduces to a problem of getting to the 985' level, above which radiation levels are tolerable. It seems that the best way to approach the RB Vent WRGM is to enter secondary containment via the M.G. Set Room on 962'. From the air lock on 962', it is important to move as quickly as possible to the stairs in the northeast corner and to climb as fast as possible to the next level, 985'. Continue up the northeast stairs to the 1001' level and from there on the radiation levels permit a slower pace. The filters could be a problem if removed from the filter holder and handled directly. We do not expect the whole body dose rate to be significant compared to levels encountered enroute to and from the sample stations. Precautions should be taken, however, after exiting contain-ment. It may be necessary to access 1027' to obtain vent flow readings. The route is to reach 1001' as described above then cross to the south side of th building through the fuel pool surge tank room and then climb to 1027' via tt southwest stairs. REMARKS 1. Prior to sampling, notify the Control Room and advise Shift Supervisor of your intentions. 2. Two-man teams should be used to obtain a post-accident sample when possible. EQUIPMENT REQUIRED Radector III or equivalent Pair of tongs (or other remote handling device as appropriate) Filter set with silver zeolite filters loaded if one set already removed PROCEDURE NOTE 1 Obtain Vital Kev #211 and Key #145 from Shift Supervisor to access emergency sample route. STEP 1 Verify that the Hot Lab South hood exhaust is functioning (use small piece of paper to check air flow), if not contact Radiological Emergency Director and continue. O WP/kk k

Procedure A.2-423 Revision 0 Page 3 of 5 I i PROCEDURE (Cont'd.) G STEP 2 Go to the Control Room and set the timer on Vent Wide Range Gas Monitor Channel "A" according to the following chart. Note process flow (item 029 and use the non-zero sample flow item 028 or 033). Activity Timer Setting < 1E4 pCi/sec 5 minutes > 1E4 pCi/sec < 1ES pCi/sec 90 seconds > IES pCi/sec < 1E6 pCi/sec 30 seconds > 1E6 pCi/sec 10 seconds SIEP 3 Don all protective clothing, equipment dosimetry devices as required by the OSC Coordinator. STEP 4 Proceed to the vent sample area as directed by the Emergency Director or his designee while observing Health Physics precautions. STEP 5 Close the four valves on the Grab Sample Filter apparatus. Disconnect ar.d remove the Grab Sample filter holder. Replace previous sei. if already removed. CAUTION: During filter holder changeout monitor radiation levels to ensure levels are below 200 mR/ hour. ( ) If levels are above 200 mR/hr, use remote handling device to minimize exposure. STEP 6 Proceed to the hot lab and place the filter set into the south hood. STEP 7 Connect the sample filter holder to the purge air fitt.ng in south hood of hot lab. Open fully the plant air supply valve in the hood and purge the filter holder set into the hood for about 2-3 minutes. STEP 8 Measure the contact CMse rate from the iodine filter. If < 10 mR/Fr proceed to STEP 10. STEP 9 If > 10 mR/hr at contact then measure the dose rate at 1 foot. Using the equation below, calculate the pCi/cc as I-131. Calculate the rdlease rate via the R.B. vents assumir.g a 120,000 CFM vents flow *. Proceed to STEP 12. 1-131 pCi/cc = 420 pCi/mR/hr x dose rate (mR/hr) + sample vol. (cc) Use 120,000 CFM if flow rate indicators on 1027' Reactor Building are inaccessible, in which cu e the flow rate based on actual readings should be used. ,m ~ J WP/kk t. A

Procedure A.2'423 Revision 0 Page 4 of 5 PROCEDURE (Cont'd. ) STEP 10 Place the iodine filter into a labeled poly bag and count on the GeLi System for 1 1000 seconds. STEP 11 When the count is complete, analyze the resulting spectrum. Run the SAVCAL Program to get the iodine release rate via the R.B. vents *. Use 120,000 CFM unless the flow indicators on 1027' Reactor Building are inaccessible, in which case flow rate based on actual readings should be used. STEP 12 Place the iodine filter into the shielded storage area. STEP 13 Place the particulate filter in a labeled petri dish. STEP 14 Measure the contact dose rate of the filter. If i 10 mR/hr proceed to STEP 16. STEP lj, If the measured dose rate is > 10 mR/hr, measure the dose rate of the filter at one foot. Using the equation below calculate the particulate pCi/cc. Calculate the release rate via the R.B. vents in pCi/sec.* Proceed to STEP 18. Particulates pCi/cc = 620 pCi/mR/hr x dose rate (mR/hr) + sample vol. (c Use 120,000 CFM unless the flow indicators on 1027' Reactor Building are inaccessible, in which case the flow rate based on actual readings should be used. STEP 16 Place the particulate filter in a labeled petri dish and count on the GeLi System for i 1000 seconds. When the count is complete, analyze the sper.trum. STEP 17 Run the PART Program to obtain the release rate for particulates from the RB vents *. Use 120,000 CFM unless the flow indicators on 1027' Reactor Building are inaccessible, in which case the flow rate based on actual readings should be used. STEP 18 Place the sample into the shielded container in the sample storage area. STEP 19 Provide the release rate information to the Radiological Emergency Coordinator and submit the checklist to the Chemistry Section Leader or Radiological Emergency Coorc;inator. STEP 20 Install fresh silver zeolite cartridge and particulate filter into filter holder. O WP/kk k

Procedure A.2-423 Revision 0 Page 5 of 5 /3 Form 5790-423-1 V Revision 0, 05/27/82 Page 1 of 1 Example of REACTOR BUILDING VENTS IODINE / PARTICULATE ANALYSIS CHECKLIST Initial 1. Hot lab hood readied. 2. Protective clothing and dosimetry. 3. Replace 1 filter set. (Time Noted: hrs, Date ) 4. Sample to hot lab and purged. 5. If iodine filter 1 10 mR/hr; collect spectrum. If > 10 mR/hr then calculated iodine activity pCi/cc = 6. Analyze spectrum, calculate release rate. (Iodine release rate pCi/sec) 7. If particulate filter i 10 mR/hr; collect spectrum. ( If > 10 mR/hr, then calculated particulate activity pCi/cc = 8. Analyze spectrum, calculate release rate. (Particulate release rate = pCi/sec) 9. Provided results to Radiological Emergency Coordinator or Chemistry Section Leader. Performed by: Date Reviewed by: CSL or REC Date 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. /'M WP/kk -}}