ML20215A961

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Public Version of Emergency Plan Implementing Procedures, Including Rev 5 to EP-208, Security Team & Rev 8 to EP-291, Staffing Augmentation. Related Correspondence
ML20215A961
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 09/22/1986
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20215A942 List:
References
OL, PROC-860922-01, NUDOCS 8610060301
Download: ML20215A961 (63)


Text

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g 3862101060 Page 1 of 5 Revision 61 09/02/86

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LIMERICK GENERATING STATIOtt EMERGENCY PLAN PROCEDURE INDEI PROCEDURE REV. DATE SIGNED DATE OF LAST ~

NUMBER NO. TITLE BY SUPER. PERIODIC REVIEW EP-101 4 Classification of 03/25/85 10/26/84 Emergencies EP-102 11 Unusual Event Response 07/28/86 10/26/84 EP-102 0 Unusual Event Response 07/28/86 07/28/86 (Appendix 1)

EP-103 14 Alert Response 07/28/86 10/26/84 EP-103 0 Alert Response 07/28/86 07/28/86 (Appendix 1) j EP-104 13 Site Emergency Response 07/28/86 10/26/84 -

EP-104 0 Site Emergency Response 07/28/86 07/28/86 (Appendix 1)

EP-105 13 General Emergency Response 07/28/86 10/26/84

( EP-105 0 General Emergency Response 07/28/86 07/28/86 (Appendix 1)

EP-106 4 Written Summary 04/01/85 10/26/84 Notification EP-110 6 Personnel Assembly and 03/14/85 10/26/84 Accountability EP-120 3 Site Emergency Coordinator 04/01/85 10/26/84 g EP-201 5 Technical Support Center 02/10/86 03/29/85 (TSC) Activation EP-202 5 Operations Support Center 04/01/86 04/01/86.

(OSC) Activation _ e e 9 h t Y.

EP-203 6 Emergency Operations Facility (EOF) Activation C f,b T05/27/86

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l EP-208 5 Security Team 7C\09/U2/86 _ m 60/26/84 3 g g.

EP-210 5 Dose Assessment Team 05/1 86 '18Y26/84 j EP-211 2 Field Survey Group 03/25 85 10/06/a4N 3 EP-220 CANCELLED \IhiM -

t, y g &su l EP-221 CANCELLED EP-222 CANCELLED EP-230 5 Chemistry Sampling and 03/14/85 10/26/84 Analysis Team D

8610060301 860922 PDR p

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( Page 2 of 5 l Revision 61 09/02/86

., LIMERICK GENERATING STATION EMERGENCY PLAN PROCEDURE INDEX PROCEDURE REV. DATE SIGNED DATE OF LAST NUMBER NO. TITLE BY SUPER. PERIODIC REVIEW ,

EP-231 12 Operation of Post-Accident 06/24/86 10/26/84 Sampling Systems (PASS)

EP-232 CANCELLED EP-233 7 Retrieving and Changing 04/01/86 10/26/84 Sample Filters and Cartridges from the Containment Leak Detector During Emergencies EP-234 7 Obtaining Containment 04/01/86 10/26/84 Gas Samples from the Containment Leak Detector During Emergencies EP-235 6 Obtaining Reactor Water 04/01/86 10/26/84 Samples from Sample Sinks Following

, Accident Conditions EP-236 5 Obtaining Cooling Tower 03/14/85 10/26/84 Blowdown Line Water Samples Following Radioactive Liquid Release after Accident Conditions EP-237 8 -Obtaining the Iodine / 04/01/86 10/26/84 Particulate and/or Gas Samples from the North Vent Wide Range Gas Monitor (WRGM)

EP-238 5 Obtaining Liquid Radwaste 04/01/86 10/26/84 Samples from Radwaste Sample-Sink Following Accident Conditions EP-240 CANCELLED EP-241 ~ 10 Sample Preparation and 06/24/86 10/26/84 '

Handling of Highly Radioactive Liquid Samples EP-242 5 Sample Preparation and 03/28/85 10/26/84 Handling of Highly Radioactive Particulate Filters and Iodine Cartridges EP-243 7 Sample Preparation and 06/24/86 10/26/84 Handling of Highly Radioactive Gas Samples

.e Page 3 of 5 l Revision 61 09/02/86 LIMERICK GENERATING STATION EMERGENCY PLAN PROCEDURE INDEX PROCEDURE REV. DATE SIGNED DATE OF LAST NUMBER NO. TITLE BY SUPER. PERIODIC REVIEW EP-244 3 Offsite Analysis of High 03/12/85 10/26/84 Activity Samples EP-250 2 Personnel Safety Team 12/12/84 10/26/84 EP-251 3 Plant Survey Group 04/01/86 04/01/86 l EP-252 8 Search and Rescue /First Aid 09/02/86 07/31/86 Group EP-253 0 Personnel Dosimetry, 12/12/84 12/12/84 '

Bioassay, and Respiratory Protection Group EP-254 3 Vehicle and Evacuee Control 02/04/85 10/26/84 Group EP-255 2 Vehicle Decontamination 12/12/84 10/26/84

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EP-260 2 Fire and Damage 12/12/84 10/26/84 Control Team EP-261 2 Damage-Repair Group 12/12/84 10/26/84 EP-272 CANCELLED EP-273 CANCELLED EP-275 CANCELLED EP-276 7 Fire and Damage 02/10/86 02/10/86 Team Phone List EP-277 9 Personnel Safety 05/12/86 01/09/86 Team Phone List EP-278 7 Security Team Phone List 05/12/86 02/10/86 EP-279 8 Emergency Operations 05/12/86 10/26/84

. Facility (EOF) Group Phone List EP-280 9 Technical Support 05/12/86 02/10/86 Center Phone List EP-282 6 Government and 02/10/86 04/22/85 Emergency Management Agencies Phone List EP-284 6 Company Consultants 05/12/86 02/10/86 and Contractors Phone List EP-287 3 Nearby Public and 02/11/85 10/26/84 Industrial Users of Downstream Water

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i 09/02/86 LIMERICK GENERATING STATION EMERGENCY PLAN PROCEDURE INDEX .

PROCEDURE REV. DATE SIGNED DATE OF LAST NUMBER NO. TITLE BY SUPER. PERIODIC REVIEW ]

l EP-291 8 Staffing Augmentation 09/02/86 09/02/86 EP-292 9 Chemistry Sampling and 12/18/85 04/22/85 Analysis Team Phone List EP-294 9 Dose Assessment Team 05/27/86 01/09/86 Phone List EP-301 1 Operating the Evacuation 12/12/84 10/26/84 Alarm and River Warning ,

System EP-303 3 Local Evacuation 12/12/84 12/12/84 EP-304 3 Partial Plant Evacuation 12/12/84 10/26/84 EP-305 5 Site Evacuation 03/25/85 10/26/84 EP-306 3 Evacuation of the 02/10/86 10/26/84 Information Center EP-307 2 Reception and Orientation 12/12/84 10/26/84 of Support Personnel EP-312 5 Radioactive Liquid 01/09/86 01/09/86 ,

Release EP-313 2 Distribution of Thyroid 12/12/84 10/26/84 Blocking Tablets EP-314 1 Emergency Radiation 03/29/85 12/06/84 Exposure Guidelines and Controls l EP-315 8 Calculation of Offsite Doses 09/02/86 01/09/86 During a Radiological Emergency Using RMMS in the Manual Mode EP-316 4 Cumulative Population and 02/10/86 02/10/86

- Near Real-Time Emergency Dose "

Calculations for Airborne l Releases Manual Method l EP-317 5 Determination of Protective 09/02/86 07/15/86 Action Recommendations EP-318 2 Liquid Release Dose 04/01/85 04/01/85 Calculations Method for Drinking Water EP-319 2 Fish Ingestion Pathway Dose 03/29/85 03/29/85 Calculation EP-325 3 Use of Containment Dose 02/27/85 10/26/84 Rates to Estimate Release Source Term

e I Page 5 of 5 l Revision 61 09/02/86 i

i LIMERICK GENERATING STATION EMERGENCY PLAN PROCEDURE INDEX PROCEDURE REV. DATE SIGNED DATE OF LAST NUMBER NO. TITLE BY SUPER. PERIODIC REVIEW EP-330 4 Emergency Response Facility 03/14/85 10/26/84 Habitability EP-333 1 Adjustment of Wide Range Gas 05/08/85 05/08/85 Monitor Conversion Factors EP-401 3 Entry for Emergency Repair 04/01/86 04/01/86 and Operations EP-410 3 Recovery Phase Implementation 03/29/85 10/26/84 EP-500 2 Review and Revision of 12/12/84 10/26/84 Emergency Plan l

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I e* l 38621013 ; o EP-208, Rav. 5 Page 1 of 11

'i l MJR/jmv i PHILADELPHIA ELECTRIC COMPANY l (- LIMERICK GENERATING STATION f2 EMERGENCY PLAN IMPLEMENTING PROCEDURE i

EP-208 SECURITY TEAM 1.0 PARTICIPANTS a 1.1 Security Team Leader shall assign group leaders, activate the groups, and coordinate the team's activities.  :

i' 1.2 Access Control Group shall perform access control activities.

1.3 Accountability Group shall perform personnel accountability activities.  %

., 1.4 Security Per9onnel shall maintain plant security, j issue emergency dosimetry to offsite support personnel, and assist in the evacuation of personnel '

and personnel accountability.

b 2.0 ACTIONS - IMMEDIATE 2.1 Security Team Leader shall:

2.1.1 Call or assign someone to call required members by using EP-278, Security Team Phon ,

2.1.2 Assign Group Leaders f personnel to the fo 19 h s se

$ fform the duties in Section 3. %qurd he situation:

A. Access Control if g B. Accountability -

AT AN ALERT OR HIGHER CLA I(&Y , SECURITY GATE ON THE 269' ELEVA MfYJRBINE ENCLOSURE SHOULD BE LOCKED. )

1 2.1.3 If informed by the Emergency Director that the Emergency Operations Facility (EOF) is to be I

activated, contact the Access Control Group Leader to have personnel dispatched to the EOF.

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EP-208, Rev. 5

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( 2.1.4 If assembly with accountability is announced,

, perform the following steps:

A. Ensure that the Access Control Group Leader assigns security personnel at the Personnel Processing q center to assist in controlling personnel access.

B. Ensure that security personnel are stationed at the g appropriate personnel exit areas.

C. Activate the Accountability Group to perform personnel accountability checks in accordance with EP-110, Personnel Assembly and Accountability. 1 1

2.1.5 If informed by the Emergency Director that a site I evacuation is going to be declared, perform the

. following:

A. Ensure that the Access Control Group Leader assigns security personnel to the appropriate site access control points and selected offsite assembly area. ,

B. Ensure that the Access Control Group Leader assigns security personnel to the selected personnel exit areas and required protected area access control -

points.

C. Activate the Accountability Group to perform personnel accountability checks in accordance with EP-110, Personnel Assembly and Accountability.

D. Immediately notify the Emergency Director when the Access Control Group is at the appropriate site p access control points and security personnel are at the selected personnel exit areas so that the site evacuation can commence.

2.1.6 Advise the Emergency Director concerning the need '

for support of off-site security agencies, if necessary.

2.1.7 Coordinate the' actions of off-site security agency '

personnel if their assistance is required.

2.1.8 Use checklists in Appendix EP-208-2 as necessary. ,

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, Page 3 of 11 l MJR/jmv k 3.0 ACTIONS - FOLLOW-UP 3.1 Security Team Leader shall:

3.1.1 Review the current status of the emergency.

4 3.1.2 Ensure that the necessary groups are staffed and performing the appropriate sections of this procedure. Augment groups as necessary, by using EP-278, Security Team Phone List.

3.1.3 Keep the Emergency Director updated on status of the i team's activities. i J

3.1.4 Periodically re-evaluate the security situation and make appropriate recommendations to the Emergency Director. ,

3.1.5 Use checklists in appendix EP-208-2 as necessary. <

3.1.6 Implement LGS Plant Protection Procedures as ,

appropriate.

i j 3.2 Access Control Group shall I

THIS GROUP IS COMPRISED OF CONSTRUCTION SECURITY FORCE MEMBERS. THE CONSTRUCTION SECURITY SHIFT

SUPERVISION IS THE APPROPRIATE CONTACT.

i ACCESS TO THE SITE FOR SUPPORT PERSONNEL WITHOUT l LIMERICK SECURITY BADGES DURING AN ALERT, SITE

EMERGENCY AND GENERAL EMERGENCY MAY ONLY BE
AUTHORIZED BY THE FOLLOWING PERSONNEL:

l EMERGENCY DIRECTOR SECURITY TEAM LEADER SITE EMERGENCY COORDINATOR l

3.2.1 Be activated when directed by the. Security Team

, Leader.

3.2.2 Receive instructions via the best means available (telephone, radio, etc.) and obtain traffic vests from the Security stocks.

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l EP-208, Rev. 5 l Page 4 of 11 l l MJR/jmv k 3.2.3 Be dispatched to locations in appendix EP-208-1 tocontrol access: as required.  ;

SECURITY PERSONNEL NEED NOT BE POSTED AT A GATE THAT WILL REMAIN LOCKED DURING AN EMERGENCY.

3.2.4 If the EOF is activated, be dispatched to the EOF to perform the actions in EP-203, Emergency Operations Facility (EOF) Activation.

3.2.5 During assembly with accountability:

a. Dispatch Access Control Group members to the N Personnel Processing Center to control personnel Access. -

3.2.6 During a site evacuation:

a. Control access and vehicle traffic by providing security personnel at 1ccations required by Appendix r EP-208-1, Exit Point Staffing for Site Evacuations, as required.
b. Immediately notify the Security Team Leader when security personnel are stationed at the required r site access control points so the site evacuation can begin.

3.3 Accountability Group shall:

3.3.1 For Personnel Accountability Check without Site Evacuation:

a. Perform a personnel accountability check as detailed in EP-110, Personnel Assembly and Accountability.

3.3.2 For Site Evacuation

a. Report to the Administration Guard Station and perform personnel accountability in accordance with EP-110, Personnel Assembly and Accountability.

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l EP-208, Rev. 5 Page 5 of 11 l MJR/jmv

{: 3.4 Security Personnel shall:

3.4.1 Maintain plant security in accordance with Plant Protection procedures, and as directed by the ,

Security Team Leader.  :

3.4.2 In the event of an Assembly with Accountability and Site Evacuation, assist personnel in the evacuation $

of affected areas and the performance of personnel 4 accountability in accordance with EP-110.

3.4.3 Issue emergency dosimetry as directed by the Personnel Safety Team Leader for incoming personnel per PP-2, Emergency Admittance Procedure.

3.4.4 For assembly with accountability:

a. Assist the Accountability Group with the evacuation of non-essential personnel from the Protected Area.
b. Perform the instructions detailed in EP-110, Personnel Assembly and Accountability. -

3.4.5 For Site Evacuation:

a. Control access to the protected area by providing security personnel at locations required by Appendix EP-208-1, Exit Point Staffing for Site Evacuation, l as required.
b. Perform the instructions detailed in EP-110, Personnel Assembly and Accountability. ',

d

c. Immediately notify the Security Team Leader when i security personnel are positioned and ready at the personnel exit areas.

4.0 APPENDICES ,

a 4.1 Appendix EP-208-1 Exit Point Staffing for Site Evacuation.

4.2 Appendix EP-208-2 Security Team Leader checklists.

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l EP-208, Rev. 5 Page 6 of 11 l MJR/jmv

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5.0 SUPPORTING INFORMATION 5.1 Purpose The purpose of this procedure is to provide guidelines for the activation and conduct of operation for the Security Team.

5.2 Criteria for Use 5.2.1 This procedure shall be implemented whenever; I 5.2.1.1 Personnel assembly is announced; 1 5.2.1.2 Alert or higher classification is declared; 5.2.1.3 Site Evacuation is declared; 5.2.1.4 The Emergency Director deems the team's activation i and operations necessary. y l

5.3 Special Equipment j 5.3.1 Traffic Vests I

5.4 References ,

3 5.4.1 Limerick Generation Station Emergency Plan 5.4.2 Limerick Generating Station Security Plan and Procedures 5.4.3 EP-278 Security Team Phone List 1

5.4.4 EP-110 Personnel Assembly and Accountability J l

, 5.4.5 EP-203 Emergency Operations Facility (EOF)

Activation g

i 5.4.6 PP-2 Emergency Admittance Procedure e

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EP-208, Rev. 5 Page 7 of 11 l MJR/jmv k

APPENDIX EP-208-1 Posting As Required ,

l TSC Exit [

l ADMIN Exit l l PAB #1 North Vehicle Gate l PAB #2 Water Treatment Building ,

l PAB #3 Cooling Tower Gate i

l l PAB #4 South Vehicle Gate l l PAB #5 Maintenance Area Gate l PAB #6 Off Loading Gate i

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. 1 l EP-208, Rev. 5 Page 8 of 11 l MJR/jmv

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APPENDIX EP-208-2 SECURITY INFORMATION ONLY Notice of Personnel Arrival DATE: TIME:

Time of Notice: Time of Arrival:

1. Names of Persotis Social Security Number A. A. 'l B. B.

l C. C.

D. D. q E. E.

F. F.

2. Where personnel are arriving from l '.,
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3. Name of person individuals are to see f
4. Escort 1d by:

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5. Security clearance Basis if unescorted access granted 9

NAME SSN COMMENT A.

B.

C.

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l EP-208, Rev. 5 Page 9 of 11 l

MJR/jmv

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APPENDIX EP-208-2 SECURITY INFORMATION ONLY Notice of Vehicle Arrival '

DATE: TIME: ]

1. Type of Vehicle
2. License Number
3. Company Truck registation number j
4. Name of Driver 1

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5. Helper (If any)
6. Expected arrival time
7. Actual arrival time i

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, l EP-208, Rev. 5 Page 10 of 11 l MJR/jmv ls APPENDIX EP-208-2 SECURITY INFORMATION ONLY )

Injured Person History l!

DATE: TIME: ,

i

1. Name of Person Injured i
2. Social Security Number
3. Payroll Number  ;
4. Home Address <

1

5. Company Injured Person Employed by

, 6. Contamination (If any)

7. How did injury happen?

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8. Where did accident happen? (Location) c Location of gate required for access to protected area
9. Under what circumstances did accident happen?
10. Was ambulance called? (At what time?)
11. Time of ambulance arrival A1. Time of ambulance departure
13. Where was injured taken? (Hospital name) i

l EP-208, Rev. 5 Page 11 of 11 l

MJR/jmv

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i APPENDIX EP-208-2 i SECURITY INFORMATION ONLY Notice of Release '

DATE: TIME:

1. Notice of Site Evacuation l

i A. Ascertain from Dose Assessment Team Leader the plume direction s

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B. Note the course of plume so that gates or posts in the plume path can be evacuated.

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1) Annunciate this information to Operation Security and x Construction Security c
2) Check with Security Forces to make sure that Security Force Members are not in path, make sure all gates, posts in path are locked and secured.
3) Ensure by checking with H.P. that the planned path taken by rover patrols does not take them through plume path.

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3862101070 EP-252, Rev. 8 Page 1 of 12 MJR:rgs PHILADELPHIA ELECTRIC COMPANY '

LIMERICK GENERATING STATION k2 EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-252 SEARCH AND RESCUE /FIRST AID GROUP 1.0 PARTICIPANTS

  • 1.1 Personnel Safety Team Leader shall control the Search and Rescue /First Aid Group's exposure and provide offsite medical support, as necessary.

1.2 Search and Rescue /First Aid Group Leader shall direct operations of the group.

1.3 Search and Rescue /First Aid Group members shall perform rescue operations and administer First Aid.

1.4 Operations Support Center (OSC) Coordinator shall form Search and Rescue /First Aid Groups.

2.0 ACTIONS - IMMEDIATE 2.1 Personnel Safety Team Leader shall:

2.1.1 Contact the Operations Support Cen dinator at the Operations Support Centef;pe QS . ndl direct him to form Search and Reteve'/ Fir d tbup(s).

2.1.2 f: T d:' . is Y t 'h.

Inform the Emergency Di' rector \ hat Search and bde~n' ormed and of their intentions Rescue /First to' Aidenter Group th'e(if pl havef 'ani (fgr search and rescue operations. fg.t) 2.1.3 Obtainemergencyexpostykkkm ~Iromthe Emergency Director if hypTDpriate. If later ,s search and rescue operations are necessary, the 1 Emergency Director may adjust the radiation exposure limits accordingly.

CAUTION IF WAITING FOR EMERGENCY DIRECTOR APPROVAL COULD ENDANGER PERSONNEL, THE SEARCH AND RESCUE /FIRST AID GROUP LEADER MAY DECIDE TO REMOVE INJURED PERSON.

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'l EP-252, Rev. 8 Page 2 of 12 MJR:rgs CAUTION PLANNED RADIATION EXPOSURES SHOULD BE LIMITED TO THE ADMINISTRATIVE GUIDE LEVELS IN APPENDIX .

EP-252-1, EMERGENCY EXPOSURE GUIDELINES.

2.1.4 Recall the Search and Rescue /First Aid Group (s) when search and rescue operations are no longer necessary.

2.2 OSC Coordinator shall:

2.2.1 Select volunteers from available personnel to form Search and Rescue /First Aid Group (s).

Instruct them to report to the Search and Rescue /First Aid Group Leader.

EACH GROUP SHALL CONSIST OF AT LEAST THREE MEMBERS; TWO MUST BE QUALIFIED IN FIRST AID AND ONE MUST BE A HEALTH PHYSICS TECHNICIAN.

I' 2.2.2 Designate the Plant Survey Group Leader or the most qualified person as group leader to remain in the OSC. -

2.3 The Search and Rescue /First Aid Group Leader shall:

2.3.1 Discuss the situation with the Personnel Safety Team Leader. The following information should be obtained prior to performing search and rescue operations:

A. Number of missing persons.

B. Name of individuals.

C. Last known location of individuals. ,

D. The job being worked.

E. Any significant plant conditions that may affect the search and any special instructions.

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l l EP-252, Rev. 8 Page 3 of 12 MJR:rgs 1

2.3.2 Ensure that each member has the necessary respiratory equipment, radsurvey equipment, anti-contamination clothing, and personnel dosimetry if time permits. This material crn be obtained from emergency survey kits at the OSC or from normal HP stocks.

2.3.3 Ensure that groups are equipped with a first aid kit, stretcher and blanket, or can get them enroute. See attached Appendix EP-252-2 for listing of first aid equipment locations in the plant.

2.3.4 Appoint most qualified person in a group to diredt response at the scene i.e. direct actions of the group and communicate with Search and Rescue Group Leader.

2.3.5 Coordinate Search and Rescue /First Aid Groups to minimize duplication of effort and unnecessary radiation exposure.

2.3.6 Attempt to locate missing person (s) by utilizing plant paging system just prior to actually 7 dispatching the search and rescue group (s).

2.3.7 Direct the groups to the last known location of the missing individual. If necessary, expand the search to adjacent areas. Ensure most expeditious routes available are taken to minimize team exposure.

2.3.8 Inform the Personnel Safety Team Leader of the actions of the group (s) and whenever the group locates any missing personnel, and the identity of located personnel.

2.3.9 Report to the Personnel Safety Team Leader the extent of the individual's injuries and recommend '

supplementary medical actions as necessary (i.e., '

hospitalization).

2.3.10 Report to the Personnel Safety Team Leader when the Search and Rescue /First Aid Group has finished its task.

2.4 Search and Rescue /First Aid Group Members shall:

2.4.1 Take direction from most qualified person at the scene.

2.4.2 Locate the missing person (s).

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'l EP-252, Rev. 8 Page 4 of 12 MJR:rgs

( 2.4.3 Determine the extent of the injury and administer first aid as necessary.

IF THE INJURY IS SEVERE, IMMEDIATE MEDICAL TREATMENT IS OF THE HIGHEST PRIORITY AND RADIOLOGICAL CONTROLS ARE SECONDARY.

, 2.4.4 Perform a radiation and contamination survey of the person and subsequently the area.

2.4.5 If offsite medical support is necessary, a member of the first aid group shall provide to the Control Room as soon as practicable, information relating to the identities of those injured, the nature and severity of any injury and whether the injury is contaminated. The Control Room shall document ?.his information on Appendix SE-11-1 and make the necessary offsite notifications. In accordance with SE-ll (Appendix SE-ll-1 is  ;

attached as Appendix EP-252-4).

CAUTION f- RADIATION EXPOSURE AND GROUP MEMBER CONTAMINA-TION SHOULD BE MINIMIZED AS MUCH AS PRACTICAL.

CAUTION IF GROSS EXTERNAL CONTAMINATION IS FOUND, INTERNAL CONTAMINATION SHOULD BE SUSPECTED.

2.4.6 Transport the injured person to a site first aid facility if practicable. If the injured person is going to be transported to an offsite medical facility, it may not be feasible to bring the person to the first aid facility. Instead, move the person to a' safe place which is easily accessible for the transfer to a vehicle and inform Control Room of transfer location.

2.4.7 If injured person is transported offsite, give medical and radiological report to ambulance crew.

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~l EP-252, Rev. 8 Page 5 of 12  !

MJR:rgs b 2.4.8 If the injured person is contaminated, perform the following:

l A. Wear necessary anti-contamination clothing if practicable.

q B. IF INJURY IS NOT SEVERE, DECONTAMINATION i SHALL BE ATTEMPTED.  ;

C. Prepare the person for transportation by 1 covering the contaminated area with a i protective wrap. Avoid excessive wrapping to prevent dehydration of the person.

D. When transporting the victim to an offsite medical facility, a Health Physics Technician shall accompany the victim to the offsite medical facility and a second HP technician shall also report to the hospital. HP technician responsibilities are defined in 2.4.11.

l 2.4.9 Recover any contaminated articles of clothing or other materials that may have been removed from the person for isotopic analysis and disposal.

'"' Recover security badge and return to Security.

2.4.10 2.4.11 The Health Physics Technician (s) accompanying the ambulance is responsible (do not delay transport to accomplish these items) to:

2.4.11.1 Issue ambulance attendants protectiva clothing as appropriate.

2.4.11.2 Take steps to protect the ambulance from contamination (i.e. plastic sheeting).

2.4.11.3 At the hospital, check to* ensure proper steps have been taken to minimize contamination (i.e.

paper on floor).

2.4.11.4 Issue' dosimetry to each medical person who will ~

be near the injured person. ,.

2.4.11.5 Survey ambulance and attendants for contamination.

2.4.11.6 Survey hospital receiving and treatment areas as necessary.

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l EP-252, Rev. 8 Page 6 of 12 MJR:rgs k.)

2.4.11.7 Collect any protective clothing and any potentially contaminated materials (e.g.

herculite, decontamination materials, decontamination liquids) and transport them back to the site for disposal in accordance with site procedures.

IF RADIOACTIVE MATERIALS INCLUDE DECONTAMINATION SOLUTIONS OR BIOLOGICAL MATERIALS, NOTIFY THE PERSONNEL SAFETY TEAM I LEADER AND REQUEST SPECIFIC DIRECTION FOR THEIR DISPOSAL. J s

2.4.11.8 Record results of each survey and deliver a copy l to the Personnel Safety Team Leader.

2.4.11.9 Recover personnel data 1.e., name, address, j social security number, date of birth, dosimeter i identification number and dosimetry for I evaluation in accordance with site procedures.

3.0 ACTIONS - FOLLOW-UP 3.1 Search and Rescue /First Aid Group members shall:

3.1.1 Report results of their actions to the Personnel

(_/ Safety Team Leader.

3.1.2 Follow normal decontamination and disposal procedures when their tasks are complete.

3.2 Personnel Safety Team Leader shall:

3.2.1 Verify the victim's arrival at the medical i facilities.

]

3.2.2 Inform the Emergency Director of results of search and rescue /first aid efforts.

3.2.3 Advise the Emergency Director to inform the Medical Director and Claims / Security as to the identity and condition of the victim (s).

a 3.2.4 Direck a Health Physics Technician to accompany the victim to the hospital and to call when informed by the hospital that his services are no longer needed. Direct the technician to return dosimetry to site to be read and leave survey equipment at hospital.

j 3.2.5 Arrange for inventory and restocking of first aid kits, if necessary.

V

l EP-252, Rev. 8 Page 7 of 12 MJR:rgs

(

4.0 APPENDICES 4.1 EP-252-1 Emergency Exposure Guidelines 4.2 EP-252-2 First Aid Equipment Locations 4.3 EP-252-3 Injured Personnel Report Form 4.4 EP-252-4 Medical Support Group Phone List  ;

I l

5.0 SUPPORTING INFORMATION l

5.1 Purpose The purpose of this procedure is to define the requirements and the actions of the Search and Rescue /First Aid Group.

5.2 Criteria for Use 5.2.1 This procedure shall be implemented whenever personnel are known to be missing or are injured and an Emergency has been declared per EP-101 r Classification of Emergencies 5.3 Special Equipment 5.3.1 Fir'st Aid Kit 5.4 P.eferences 5.4.1 Limerick Generating Station Emergency Plan 5.4.2 NUREG 0654, Criteria for Preparation and Rev. 1 Evaluation of Radiological Emergency Response Plans and Preparedness In Support of Nuclear Power Plants.

5.4.3 SE-ll - Injury 0

l

l EP-252, Rev. 8 Page 8 of 12 MJR:rgs A

APPENDIX EP-252-1 EMERGENCY EXPOSURE GUIDELINES l

l Projected I Whole Body Thyroid Authorized  ;

Function Dose Dose By

1. Life Saving and Reduction of Injury 75 rem
  • 375 rem Emergency **

Director

2. Operation of Equipment to Mitigate an Emergency 25 rem
  • Emergency **

Director

3. Protection of Health and Safety of the Public 5 rem 25 rem Emergency Director

Reference:

EPA-520/2-75-001 Table 2.1

    • Such exposure shall be on a voluntary basis 4

1 r, - . ~..- __ .,

l EP-252, Rev. 8 Page 9 of 12 MJR:rgs s APPENDIX EP-252-2 FIRST AID EQUIPMENT LOCATIONS First Aid Kits Blankets Stretchers Unit 1 Reactor Enclosure 177' Outside Stairway #4 X X X 201' Outside Elevator X 201' Inside Pipe Tunnel X 217' Area 16 Line 18.5 'X 217' Inside Stairway #4 X X X 253' Inside Stairway #4 X X X 253' By Personnel Airlock X X X 283' Corridor near Elevator (509) X 283' Near Fuel Pool Cooling Room (511) X 313' Outside Room 609A X X X 313' Airlock to Fan Room (607) X 313' West of Room 603 X 352' Change Area (701) X X X Unit 1 Turbine Enclosure 200' Near Room 261 X 217' 325A Corridor-aux Equip & Piping (Area 7 Line 13) X 302' Equip Exhaust Filter (621) X 269' Outside Stairway #30 X 209' Outside Room 545 X 269' Inside OSC X X X 200' Inside Stairway #7 X l

1

l EP-252, Rev. 8 Page 10 of 12 MJR:rgs APPENDIX EP-252-2 FIRST AID EQUIPMENT LOCATIONS First Aid Kits Blankets Stretchers 217' Outside Room .'36 X 217' Stairwell #7 X X X 239' Stairwell #7 X X X 254' Stairwell #7 X 269' Inside Control Room X X X 269' Inside Stairwell #7 X X X I 289' Stairwell #7 X X X 304' Stairwell #7 ,

X X X 332' Stairwell #7 X X X 350' Stairwell #7 X X X Radwaste Enclosure i

217' Rad. Chem Lab (418) X 217' Radwaste Control Room (415) X X X 217' Between Rooms 417 & 418 , X 217' Southeast of Room 415 X X X 191' Outside Stairway #2 X 162' Outside Stairway #2 X X X 162' Outside Door 131 X X

l EP-252, Rev. 8 Page 11 of 12 MJR:rgs APPENDIX EP 252-3 INJURED PERSONNEL REPORT FORM (PREPARE IN DUPLICATE)

Injured Person's Name Age -

Badge No. Or Social Security No.

Male Female Type and Location of Injury I

Radioactive Contamination Yes No Level Location Radiation Exposure Estimate Where Did Injury Occur Prepared by First Aid Group Leader SIGNATURE Group Members  ;

l If practicable forward original, with the person, to the site first aid facility or hospital as appropriate.

l

l ..

~ ' ' .. ' ' '

s l EP-252, Rev. 8 Page 12 of 12 MJR:rgs APPENDIX EP-252-4 k I. MEDICAL EVENT INFORMATION Date: / /

1. Inform hospital and Montco Radio Room:
a. Unit 1 or Unit 2 $
b. Name of caller I
c. Number of injured persons 9
d. Nature of injury
e. Is injured contaminated? YES[ ] or NOt J I
2. Inform hospital of estimated time of arrival
3. Inform Montco Radio Room you are requesting an ambulance for transport to hospital.

II. MEDICAL SUPPORT PHONE LIST Time / Initials Primary:

(

Pottstown Memorial Medical Center .l 1600 E. High Street  %

Pottstown, PA 19464 /

Alternate:

l l

, Montgomery Hospital l Powell and Fornance Streets Norristown, PA 19401 (Emergency Room) h /

Radiation Management Corporation /

(Serious Contamination or Exposure

  • multiple contaminated personnel)

Preferred Alternate Beeper Ambulance / "

Contact Monto Radio Room @ Prelude M /

Loca'l Physicians Office Home

  • Sarious Contamination / Exposure is:

Whole Body Exposure greater than 25 REM or skin exposure greater than 150 REM or extremity exposure greater than 375 REM or contamination causing body contact reading of greater than 1 mR/Br or suspected or actual-inhalation or ingestion cf measurable quantities of radioactive material. _ _ _ _ _ _ _ _ . _ . _ _ _ .

az m______._..._. _

~

~. N -

1 1 3862101080 EP-291 Rev. 8 l Page 1 of 7 MJR/mc PHILADELPHIA ELECTRIC COMPANY j LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE h266 j g

~

EP-291 STAFFING AUGMENTATION 1.0 PARTICIPANTS 8

1.1 Shift Clerk or other assigned person shall perform the following procedure.

2.0 ACTIONS - IMMEDIATE 2.1 Shift Clerk or other assigned person shall:

2.1.1 Ask the Emergency Director if the TSC and EOF or the TSC only is to be activated so that this information can be given to the Dose Assessment Team Leade' nd '

Communicators and what groups are to be agt

~

l (~ for transmission to Team Leaders. g . g Event Classification 5 5' : i .

d

- 53s Facilities to be act ted ,v *.

{

TSC i 15 h

Groups to be activated

}

Personnel Safety Team Plant Survey 1st Aid / Search and rescue i Vehicle and Evacuee Control

, Dosimetry, Bioassay &

Respiratory Protection Dose Assessment Team Dose Assessment group Field Survey Technical Support Team I

.i

- , - .- -0 ~ . , . - , _ _ . , . . - . . - - - _ - . . , _ . - , , . , _ , , , . . _ . . , _ _ _ , - - , , _ _ . , . , .

3 .. . _ _ _ _ _ . -- - -----.. _ _ _ __ -

l EP-291 Rev. 8 Page 2 of 7 MJR/mc k

Security Access Control p Personnel Accountability Fire and Damage Fire Fighting  ;

Damage Repair Chemistry Sampling and Analysis 2.1.2 Contact in sequence the personnel listed in Section 2.2. )

2.1.3 Inform each person contacted of the event classification, that they are to respond to their assigned location and what groups under them are to l be activated. If the person is unable to respond, )

. go to the next person on the list. 1

(

2.1.4 Attempt to contact personnel who have pagers, by that method if they are known to be "on the page",

or the phone is busy or there is no answer.

2.1.5 Inform Emergency Director of results including discrepancies.

2.2 Personnel to be contacted are:

2.2.1 SHIFT IEC TECHNICIAN Communicator shall request that the TSC be activated.

(Shift I&C Technician ext. 6 or W )

IEC Technician -

Time By

-(

II

-y . -

- * - , --+ -

--s ,. . . , , _ , , _ _ , . . _ _ . _.

.y . . , . ,

l' EP-291 Rev. 8 Page 3 of 7 MJR/mc 2.2.2 EMERGENCY DIRECTOR I

Disposition-Busy, Time Called No Ans.-Contacted Called By 3 1

~

vices W N .

]

ations eer

(

2.2.3 OPERATIONS ENGINEER Disposition-Busy, Time Called No Ans.-Contacted Called By V

M 9- Q -

- sus ,

d 2.2.4 SHIFT MAINTENANCE SUB-FOREMAN -

Extension 6 or page. Communicator shall request the Maintenance Sub-foreman to call three maintenance mechanics, preferably, one electrician and two machinists or fitters.

Sub-foreman Time By

. (:

O

._ -_ -.._-.__..-O

l- 1__ - . _ _ _ _ - . . _ _ _ . . _ .

p -- -- - - -

f --_ ,-_._ , - _ -

l EP-291 Rev. 8 Page 4 of 7 MJR/mc b 2.2.5 COMMUNICATORS (ONE per facility)

Communicator shall request call in of members for the TSC or EOF as determined by Step 2.1.1. Inform TSC Communicator if Emergency Director has been notified. '

, , , , , w Disposition-Busy, ,.

,  %.,,,, Time Called No Ans.-Contacted Called By

(.

Technical Support g , . , . . I N n1 # '"

l

}

n

~ -

a ns g .

o EOF Communicator ,

name,. qw  :

2.2.6 PERSONNEL SAFETY TEAM LEADER (ONE)

Communicator shall request that the Team Leader call in Group Leaders of groups to be activated and that the Group Leaders call in their groups.

Disposition-Busy, '

Tim,e Called No Ans.-Contacted Called By S3nior Health q

~

GuisiT

=

W -

g, or l

l EP-291 Rev. 8 Page 5 of 7 MJR/mc

. 2.2.7 DOSE ASSESSMENT TEAM LEADER (ONE)

Communicator shall request the Team Leader to call in team and the Field Survey Group Leader, and to report to the TSC or EOF as determined by Step 2.1. I Disposition-Busy, i Time Called No Ans.-Contacted Called By }

Technical Support cist einie. *MS Ph sicist Rad. Prot. M or ,

2.2.8 TECHNICAL SUPPORT TEAM LEADER (ONE)

Communicator shall request call in of Technical Support Team Members.

( Disposition-Busy, Time Called No Ans.-Contacted Called By I&C Engineer or gineer 2.2.9 CHEMISTRY SAMPLING and ANALYSIS TEAM LEADER (ONE)

Communicator shall request call in of Chemistry Sampling and Analysis Team Members by Group Leader.

. Disposition-Busy, Time called No Ans.-Contacted Called By M E '

M W

= . . - -- .::: : . - _- _ .- ... - . .._ _- _ ._ .__ _

5---.

.. . ..a... .:. . .. . . .

3-l EP-291 Rev. 8 Page 6 of 7 MJR/mc 2.2.10 FIRE AND DAMAGE TEAM LEADER (ONE)

Communicator shall request the Team Leader to call the appropriate Group Leaders and have Group Leader call in Group Members.

Disposition-Busy, No Ans.-Contacted

, Time Called Called By 1

En ineer Maintenance M k

, or W Assistant Engineer Ma tenance I or W 2.2.11 SECURITY TEAM LEADER (ONE)

Communicator shall request the Team Leader to call appropriate Group Leaders and have Group Leaders call in '

personnel. Inform Security Team Leader if EOF is to be activated.

'b Time Called Disposition-Busy, No Ans.-Contacted Called By

~ M

"" W

        • M
      • *M rk) i m -

W j

. N I 13.0 ACTIONS-FOLLOW-UP 3.1 None Required.

  • ... ,-r , .

l EP-291 Rev. 8 Page 7 of 7 MJR/mc k

4.0 APPENDICES -

f None.

5.0 SUPPORTING INFORMATION 5.1 Purpose Q The purpose of this procedure is to provide guidelines and g information necessary to perform staff augmentation.

5.2 Criteria for Use This procedure shall be implemented at an Alert, a Site Emergency or a General Emergency or at the discretion of the Emergency Director.

5.3 Special Equipment '

None.

5.4 References _

f None.

l 4 5

+ ..

'I 3862101090 EP-315, Rev. 8 Page 1 of 15 MJR/MAC/nlp PHILADELPHIA ELECTRIC COMPANY h

. LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE h2 h EP-315 CALCULATION OF OFFSITE DOSES DURING A RADIOLOGICAL EMERGENCY USING RMMS IN THE MANUAL MODE 1.0 PARTICIPANTS 1.1 The Shift Technical Advisor (STA) shall initiate dose calculations as directed by ST-0-104-880-0.

1.2 The Shift Superintendent shall evaluate the dose results, declare the appropriate EAL based on releases, and assist the Emergency Director in making protective action recommendations if warranted.

1.3 .The Dose Assessment Team Leader (DATL) (upon activation of the TSC, and/or the EOF) shall direct

,[ dose calculations, evaluate the results, and assist the Emergency Director with EAL declaration 3 protective action recommendations. g'd p, y, 'r v ~,

{

1.4 The Dose Assessment Team Igemb'ert/wiSI'.perYor , -

functions as directed by thh'DATL.

(INb y. ,E Lgi

.,,. .. ; g 2.0 ACTIONS IMMEDIATE I i..% b 2.1 Answer the following questions: f., ,

1Idph O** I 2.1.1 IsaChemistrysamp\p.u,v&ilable? If yes, attach Chart B of S'..-6-104-880-0.

2.1.2 Is the Datalogger available? If no, go directly to Appendix 1.

2.1.3 Is the RM-ll console available? If no, go directly to Appendix 2.

2.1.4 If you answer no to question 2.1.3, you may need the RM21A to access Vent Flow Data. Go to Appendix 4.

2.2 Logon to the RM21A to estimate offsite doses.

. 2.2.1 Respond to the prompts as directed below or by the DATL.

'l EP-315, Rev. 8 Page 2 of 15 MJR/MAC/nlp

i. Step # RM21A Prompt Operator Response Depress RETURN key until prompted with USERNAME (MCR-in upper right corner)
1. USERNAME Type in Depress RETURN
2. PASSWORD Type in  ;,

Depress RETURN

3. RM21A Options- Enter 6-Emergency Release Level 1 Calculations. Depress RETURN
4. Emergency Enter 3-Class A Model Release Cales. Depress RETURN Calculations Options-Level 2 -
5. Select Run Enter 3 - All Manual Control Table 15 min. data Option Depress RETURN
6. Do you want to Enter Y to verify that the edit / review the default Run Control Table Run Control reflects the desired para-l Table Menu? meters. Go to Appendix 6 for default table, parameter descriptions, available options l and modification instructions. i Depress RETURN.

Enter N if you do not wish to review the run Control Table. 1 Depress RETURN

7. Enter time of Enter Eastern Standard Time (EST) l Reactor trip. (i.e. 04/03/86 09:30) i Enter date Depress RETURN i (MM/DD/YY HH:MM)

I

8. Enter time of Enter Eastern Standard Time (EST) release. (i.e. 04/03/86 09:30) l Enter date. A. Time of release -or- l (MM/DD/YY B. Start of period to be HH:MM) evaluated -or-C. Time of chemistry sample.

Entry must be > Step 7.

Depress RETURN

l EP-315, Rev. 8 Page 3 of 15 MJR/MAC/nlp Ste'p # l RM21A Prompt ' Operator Response

9. Enter remaining Enter an estimate or 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> duration of if unknown. (i.e. depress 1) release (hours) Depress RETURN
10. Data Entry Enter option #2 (percent)

Options Depress RETURN

11. Gaseous Isotope Do you have a Chemistry sample?

Options As answered by DATL Yes-Use Chart B, ST-6-104-880-0 No-Select a representative

" Accident" from Appendix 3A or 3B.

12. Enter isotope Enter # corresponding to isotope selection (1-35) of interest.

Depress RETURN i 13. Enter isotopic Enter % abundance of selected fraction (%) isotope (i.e. 50% = 50.0) of 100% Do calculation with Noble Gases 1st. (Repeat procedure for iodines if directed) Depress RETURN

14. Do you want to Enter Y. Depress RETURN continue Repeat steps 12, 13 & 14 until entering all isotopes are entered; then data? (Y or N) answer N to Step 14.

(If you answer Y by mistake, select any isotope not used and enter zero (0); then answer N for Step 14).

Enter (C) to Enter C. Depress RETURN erase screen and continue

15. Are these Compare these values to Appendix 4 l

values 2A, 2B or chart B and respond acceptable? accordingly. Enter (Y or N).

Depress RETURN.

I

16. Enter gross Select release points (s).

concentration Enter value recommended below (micro-Ci/cc) or one determined by DATL.

l Release Point Data Source NS & WRAM IME076, 2LE076 or 3HE076 NS w/out WRAM Calculate (3GE075, uCi/cc + 6GE075, uCi/cc)

( 2 )

SS Alone Calculate (3GE185, uCi/cc + 6GE185, uCi/cc)

( 2 )

.l EP-315, Rev. 8 i Page 4 of 15 l MJR/MAC/ nip For Iodine Calculation: Use.uCi/cc reported by Chemistry based on cartridge analysis; Methodology suggested by EP-316, Section 2.3 or value determined l by DATL. '

l Step fl RM21A Prompt Operator Response .

17. Enter vent Sources of Data flow rate (cfm) 1. RM-ll console: Process Flow N
2. MCR 00C-691 panel: RYO26-076 Depress MON Depress 0-2-9 Depress ITEM. Record value.
3. RM21A - See Appendix 4
4. Estimate flow based on rates of operating fans.

Enter value. Depress RETURN

18. Enter (C) to Depress C. Depress RETURN erase screen -

and continue

19. Meteorological Use Appendix 5 for source of values.

Data Entry In order of preference:

(~ 1. Datalogger

2. RM21A
3. Control Room Strip Charts
4. National Weather Service # 1-597-0846 A. Ground direction B. Ground sigma For each sensor:

theta '

C. Ground speed Enter value. )

D. Ground delta Depress return temperature E. Elevated direction F. Elevated sigma theta G. Elevated speed H. Elevated delta temperature I. Ambient temperature Enter (c) to Enter C. Depress RETURN erase screen and continue l

l

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

l l -

1 l EP-315, Rev. 8 l Page 5 of 15 '

MJR/MAC/nlp l t

2.3 Generate a hardcopy of the first display. If CURRENT ACTION LEVEL is greater than NO EMERGENCY, take a hardcopy of all subsequent displays. Notify Shift l Superintendent in Main Control Room or Dose Assessment i Team Leader in TSC/ EOF of results. 1 3.0 ACTIONS FOLLOW-UP 3.1 As directed by Shift Superintendent or Dose Assessment l Team Leader: '

3.1.1 Terminate dose calculations -or I

3.1.2 Repeat Step 2.1 -or j 3.1.3 Turnover to TSC/ EOF Dose Assessment Team 4.0 APPENDICES 4.1 Appendix 1: Meteorological Data Collection When

]_ Datalogger Unavailable 4.2 Appendix 2: Rad Data Collection When RM-ll Unavailable 4.3 Appendix 3A: Postulated Isotopic % Abundance for Design Bases Accidents - Noble Gas 4.4 Appendix 3B: Postulated Isotopic % Abundance for Design Bases Accidents - Iodine i l

4.5 Appendix 4: Vent Flow Rate Date Collection Using RM21A [

4.6 Appendix.5: Meteorological Data Collection Resources 4.7 Appendix 6: ACRISO Default Run Control Table Menu i

5.0 SUPPORTING INFORMATION 5.1 Purpose The purpose of this procedure is to provide guidelines to evaluate a potential or actual airborne release using RMMS in the All Manual Mode.

i

_ - , . - . _ . . . . _ _ . ~__ _ - - . . - _. . - - - - - - . . , , _ _ -

l EP-315, Rev. 8 Page 6 of 15 MJR/MAC/nlp

(

5.2 Criteria for Use 5.2.1 This criteria is implemented based on, but can be used independently of, direction received from ST-6-104-880-0. ,

5.2.2 The manual mode of RMMS will allow the e

operator to bypass the use of real time radiological and meteorological data, enabling him to enter data of his own choosing.

4 5.2.3 Operation of RMMS in the manual mode is useful for investigating offsite doses during Emergency Plan exercises (i.e., in the event that radiological or meteorological data are unavailable in the real time mode.)

5.3 Special Equipment 5.3.1 RM-21A Consoles and User Guide 5.3.2 RM-ll Consoles and User Guide 5.4 References 5.4.1 Letter fro , Project Engineer, Bechtel San Francis o Power Division, to GA Technologies dated June 16, 1983. Document Control No. 157678. Subject Job No. 8031, Philadelphia Electric Company, Limerick Generating Station, Units 1 and 2, Startup System No 99H. Radiation Meteorological Monitoring System MCA Break Down by Isotope P.O. 8031-M-256 d 5*4.2

. EP-316, Cumulative Population and Near Real-Time Emergency Dose Calculations for Airborne j Releases - Manual Method l

5.4.3 ST-6-104-880-0, Gaseous Effluent Dose Rate  !

Determination l i

1 l

l EP-315, Rev. 8 Page 7 of 15 MJR/MAC/nlp APPENDIX 1 MET. DATA COLLECTION WHEN DATALOGGER UNAVAILABLE Step # l RM21A Prompt Operator Response Depress RETURN key until prompted with USERNAME (in upper right corner in MCR).

1. USERNAME Type in Depress RETURN
2. PASSWORD Type in , Depress reset page l Depress RETURN
3. RM21A Options Type in 4 - Met. Data Coll. &

(Level 1) Frocessing. Depress RETURN

4. Met. Data Coll. & Type 4 - Met. Data Processing Processing (Level 2) Depress RETURN
5. Met. Data Processing Type 3 - Review current averages.

Options - Level 3 Depress. RETURN

6. Met. Data Options Typdf27 'l'5 mBacidata.

Depress RETURN

7. Report on Type N. Depress reset page.

Printer? Depress RETURN. Copy met values printed on screen.

Reserve as bases for results.

8. Do you wish to Type N continue work with this option?
9. Is the RM-ll Y - Depress RETURN 2 times.

,available? Go to Appendix 2, step 3.

N Depress RETURN. Repeat until you get back to Level 1. Go to Secti'no 2.1.3 of Actions Immediate.

1

.l EP-315, Rev. 8 Page 8 of 15 MJR/MAC/ nip APPENDIX 2 RAD. DATA COLLECTION WHEN RMll UNAVAILABLE Step # RM21A Prompt Operator Response Depress RETURN key until prompted with USERNAME -

1. USERNAME Type in <

Depress RETURN

2. PASSWORD Type in Depress RETURN

~3. RM21A Options Enter 3 - Rad Data Collection (Level 1) & Processing. Depress RETURN

4. Rad. Data Coll. & Enter 2 - Rad. Data Processing Proc. Opt. (Level 2) Depress RETURN '
5. Rad. Data Processing Enter 6 - Channel History Options Level 3 Depress RETURN
6. Channel History Enter 3 - 15 min. EFFLUENT Options-Level 4 Release Rate. Depress RESET n'~

Depress RETURN

7. Edit, List, Enter I. Depress RETURN Inquiry, Plot
8. 15 min. Channel Enter 5 - Full Data Report History Data Range for single channel Depress RETURN 0

Channel History Name Enter full alpha-numeric code for channel of interest Depress RETURN

10. Start date and time (i.e. 04/03/86 09:30) enter; Depress RETURN
11. End date and time (i.e. 04/03/86 10:30)

Enter; depress RETURN Take a hard copy of the screen Depress RETURN

12. 15 Min. Channel Return to step 8 and History Data Range repeat sequence if data is required for the redundant channel. If you do not wish to continue, depress RETURN twice.
13. Channel History Enter 1 - Depress RETURN Data Options Go to Step 2.1.4 of Actions Immediate

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

~

l EP-315, Rev. 8 Page 9 of 15 MJR/MAC/nlp

(

APPENDIX 3A POSTULATED ISOTOPIC % ABUNDANCE FOR DESIGN BASES ACCIDENTS - NOBLE GASES (REFERENCE 5.4.1)

Main Off gas Air Control Steam Treatment Ejector Fuel Rod Line . System Line Handling RM21A f Noble Gases Drop Break LOCA Failure Failure Accident

4. Kr 83m .2407 .9285 1.231 .414 1.217 9.4N4
5. Kr 85m .5924 1.634 3.833 .958 1.136 .4134
6. Kr 85 .0202 6.35N3 .121T .132 .732 1.837
7. Kr 87 1.1474 5.065 6.901 1.68 7.01 6.89NS
8. Kr 88 1.5839 5.193 9.463 3.87 7.17 .128 Kr 89 2.0952 21.67 11.71 6.84N2 16.33
11. Xe 131m .0101 5.18N3 7.67N2 .289 5.4N3 .2891
12. Xe 133m .0781 .7766 .4091 1.065 .1046 1.739
13. Xe 133 3.068 2.18 16.58 72.21 2.96 81.32
14. Xe 135m 2.906 6.363 15.88 3.21 7.64
15. Xe 135 .812 5.865 4.597 14.68 7.99 14.23 Xe 137 4.327 28.63 15.094 .139 22.29 l
17. Xe 138 8.281 21.67 14.101 1.26 25.39 H3 62.36 CH 12.472 TOTAL 99.99 99.98 99.99 99.97 99.27 99.95 8

I

! EP-315, Rev. 8 Page 10 of 15 MJR/MAC/ nip APPENDIX 3B l

POSTULATED ISOTOPIC % ABUNDANCE FOR DESIGN BASIS ACCIDENTS - IODINES (REFERENCE 5.4.2)

RM21A# 34 35 ACCIDENT I-131 I-133 Control Rod Drop 30.29 69.71 Instrument Line Break .1205 87.95 Main Steam Line Break 12.71 87.29 LOCA 17.16 82.84 Feed Water Line Break 19.95 80.05 Offgas Treatement Sys. Fall X X Air Ejector Line Failure X X Liquid R/W Sys. Failure 58.04 41.96 Fuel Handling 46.82 53.18 l

l l

l EP-315, Rev. 8 Page 11 of 15 MJR/MAC/ nip

(

APPENDIX 4 l

l VENT FLOW RATE DATA COLLECTION USING RM21A RM21A Prompt Operator Response RM21 A Options - Level 1 Enter 3 - Rad Data Collection and Processing Depress RETURN Rad Data Coll. & Processing Enter 2 - Rad Data Processing Level 2 Depress RETURN Rad Data Processing Enter 6 - Channel History Options Level 3 Depress RETURN Channel History Data Enter 4 - 15 min. vent flow Options - Level 4 Depress Reset Depress RETURN Edit, List, Inquiry, Plot Enter I. Depress Return 15 Min. Channel History Enter 5 Data Range Depress RETURN Channel Name Enter alpha-numeric code for any channel on the release point of interest Depress RETURN Start Date and Time (i.e. 04/03/86 12:00)

Depress RETURN End Date and Time (i.e. 04/03/86 12:00)

Depress RETURN Take copy of Screen Depress RETURN 3 times Channel History Data Enter 1. Depress RETURN Options Go to Step 2.2 of Actions Immediate

) E 15, R:v. 8 Page 12 of 15 MJR/MAC/nlp APPENDIX 5 -

METEOROLOGICAL DATA COLLECTION RESOURCES Strip Charts RMMS MANUAL 1. DATALOGGER DATALOGGER 2. RM-21A 3. SENSOR Channel No. &

Met. Prompts Abbreviation Parameter Name Primary Secondary Ground Direction 0 30'Dir./ TlDRL 30'DIR/ (0)*, 159'DIR/ (15)

WDI Ground Sigma Theta 0 30'DIR/ TlDRL 30'DIR/ (0), 159'DIR/ (15)

WDI/DEV Ground Speed 1 30' Speed TISPL 30' Speed (l), 159' Speed (16)

WSI Ground Delta T 6 266'-26' T TlDT U-L 266'-26' T(6), 300'-26' T(23)

DTI ElGveted Direction 2 175' DIR./ Tl DRI 175' DIR/ (2), 304' DIR/ (20)

WD2 Elsvated Sigma Theta 2 175' DIR./ Tl DRI 175' DIR/ (2), 304' DIR/ (20)

WD2/DEV Elevated Speed 3 175' Speed TISPI 175' Speed (3), 304' Speed (21)

WS2 Elevated Delta T 7 266'-26' T TlDT U-L 266'-26' T(7), 300'-26' T(23)

DT2 Elevated Amb. Temp. 10 26' Ambient T2 AT L 26' Ambient (10), 26' Amb. T (24 TRl

  • Channel number from Data-logger in parenthesis ().

Wind Charts '

wind Speed - red - (0-100 mph) full scale Sigma theta - black - (0-100 mph) full scale Wind direction - red - (0-360-180) full scale

l EP-315, Rev. 8 Page 13 of 15 MJR/MAC/nlp APPENDIX 6 ACRISO DEFAULT RUN CONTROL TABLE MENU Verify that the default Class A run-time parameters are representative. Refer to Appendix B to explain each parameter _

and provide instructions to modify.

9 Site: Limerick Unit: U1 User:

Date: Time:

ACRISO RUN CONTROL TABLE 1 Item Description Selection (Values)

, l 1. Meteorological Data Manual

2. Data File Type 15 minute
3. O Data Source Manual
4. Vent Flow Data Manual
5. Maximum Downwind Distances (miles) 10.0
6. Output media Plot
7. Background map selectors Cities Rivers, lakes, oceans Roads State boundaries Counties
8. Report Options X/Q isopleth Depleted X/Q isopleth Deposition X/Q isopleth Skin isopleth Gamma isopleth Itihal. thyroid isopleth Milk thyroid isopleth Project gamma & thyroid Summary report
9. Release Point for X/Q Output 1
10. Isopleth contour spacing 1,1,1,2,2,2, l 11. Gamma Dose Calculation Semi-infinite
12. Off-site Gamma Dose Adjustment Factor 1
13. Off-site Iodine Dose Adjustment Factor 1
14. Active Release Points 1
15. Title change Dose Calc - Most Recent 15 min. Data (@ EM)

l EP-315, Rev. 8 Page 14 of 15 MJR/MAC/nlp APPENDIX 6 (Cont'd)

ACRISO RUN CONTROL TABLE PARAMETER DESCRIPTIONS All items listed in the Run Control Table are explained below l with instructions to modify. Once an item is modified, request a print of the Menu to verify the change, then depress RETURN until -

you get to Step f.

I Modification  !

Item Description Selection (Values) Instructions

1. Meteorological 1. Most recent I Data 2. Historical  ;
3. Manual entry j i
2. Data File Type 1. 15-minute j
2. 15-minute workspace

! 3. 1-minute

3. Q Data Source 1. Routine MCA & Effluent
2. Accident MCA & Effluent-D.B.A
3. Manual Q File Data
4. Vent Flow Data 1. Routine Collection  !
2. Manual Entry
5. Maximum Downwind Maximum value = 50 distance (miles)
6. Output Media 1. Plot 1
2. Print II
7. Background Map 1.- Cities Selectors 2 - Rivers, lakes and oceans 3 - Roads l 4 - State Boundries 1 5 - Wind spider 6 - Counties 7 - Emergency response planning areas 8 - TLD Site, 9 - Air sampling site ,5 10- Emergency sampling site ,

11- Ludlum site 1 12- County emergency centers '

13- Offsite monitor location 14- Text 15- Survey point 1

16- Water sampling site 17- General environmental

monitoring site l

18- Offsite Monitor Speed & Direction 19- Offsite Monitor Dose

l EP-315 Rev. 8 Page 15 of 15 MJR/MAC/nlp APPENDIX 6 (Cont'd)

Modification Item Description Selection (Values) Instructions

8. Report Options Available Reports 1 - X/Q isopleth 2 - Depleted X/Q isopleth 3 - Deposition X/Q isopleth 4 - Skin isopleth 5 - Gamma isopleth 6 - Inhalation thyroid isopleth 7 - Milk thyroid 8 - Project gamma / thyroid 9 - Summary report 10- Project dose summary
9. Release Point for LGS Gaseous Release Points X/Q Output 1 - North Stack 2 - Unit 1 South Stack 4 - Hot Maintenance Shop
10. Isopleth Coutour Edit option not available Spacing
11. Gamma Dose 1. Semi-infinite Calculations 2. Finite
12. Offsite Gamma Maximum value = 99.89 Dose Adjustment Factor
13. Offsite Iodine Maximum value = 99.89 Dose Adjustment '

Factor

14. Active Release LGS Gaseous Release Points 1 - North Stack 2 - Unit 1, South Stack 4 - Hot Maintenance Shop
15. Title Change Select Run Table Control Types
1. Dose Calc. - Most recent 15-Min. Data (8 EM)
2. Dose Calc. - Most recent 1-Min. Data (9 EM)
3. Dose Calc. - All Manual 15-Min. Data
4. Dose Calc. - Historical 35-Min. Data, Normal MCA
5. Dose Calc. - Most Recent 15-Min. Data, Manual MCA
6. Dose Calc. - Most Recent 15-Min. Data, Semi-Infinite
7. Dose Calc.-Default Run Table

,. 3862101100 EP-317, Rev. 5 Page 1 of 12 MJR/cmb PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE h2 f EP-317 DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS 1.0 PARTICIPANTS 1.1 Dose Assessment Team Leader or Shift Technical Advisor shall determine protective action recommendations based on dose projections and is responsible for making the protective action recommendations to the Emergency Director or Site Emergency Coordinator.

1.2 Site Emergency Coordinator, if activated, or Emergency Director shall provide recommenylatichs i the Pennsylvania Bureau of Radiat,iorrP(o'tectio( [

directly to the counties if 1.he stats'.can contacted. I ~~

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' . _.5 . i s ' % + (bg, I (~- f- )Y 2.0 ACTIONS-IMMEDIATE Ly, -. r

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2.1 Dose Assessment Team Leader or Shif t T,4cttriIca $, .

Advisor shall: 5.'-

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2.1.1 DETERMINE PLUME EXPOSURE PATHWAY' PROTECTIVE ACTION RECOMMENDATIONS BY DOING THE FOLLOWING:

2.1.1.1 Obtain the dose rate estimates, expected duration of release and windspeed from Appendix EP-316-3 Summary Sheet or RMMS output. Proceed to EP-317-2 Protective Action Recommendation Worksheet.

Enter plume centerline dose rates (R/hr) for site boundary, 2 miles.and 5 miles in appropriate columns for item (la), whole body, and (lb), -

thyroid. If rapid EP-316 calculation is done (EP- g 316 Section 2.1.1,1) the resultant site boundary dose rate must be ratioed to obtain estimated 2 mile and 5 mile dose rates. Multiply Site boundary dose rate by .4 and .2 for 2 miles and 5 miles respectively.

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EP-317, Rev. 5 Page 2 of 12 MJR/cmb i

I.t is assumed that projected doses calculated and l protective actions recommendations determined from  ;

this data at

' I A) the site boundary, applies to 0-2 mile  ;

region and is effective for 360 degrees <

around the plant,

, B) the 2 mile radius, applies to the 2-5 ,

mile sector in a downwind wedge, and 1 C) the 5 mile radius, applies to the 5-10 mile sector in a downwind wedge.

The Downwind wedge is a function of the dispersion of the plume and should be determined by evaluating the plume width.

g 2.1.1.2 Enter the expected duration of release (t) and

[ multiply by items la and lb to get projected dose.

2.1.1.3 Select evacuation time estimate for existing conditions and enter as item 3. {

' LONGEST ESTIMATES IN EACH CATEGORY ARE PROVIDED ON 1 WORKSHEET.

2.1.1.4 Determine time until exposure begins as indicated on worksheet and enter as item 4.

2.1.1.5 Subtract item 4 from item 3 and compare to duration of release (t). The smaller of the two is the Evacuation Exposure Time in hours, item 5.

2.1.1.6 Calculate Evacuation Exposure Dose by multiplying the whole body dose rate (la) and thyroid dose rate (1b) for each location by item 6 the Evacuation Exposure Time for each location.

This is the exposure the population would receive while being evacuated. i 2.1.1.7 Calculate shelter dose by multiplying whole body ,

(la) and thyroid (1b) dose rates by duration (t) l and Protection Factor as indicated in items 7a and j 7b L

A Protection Factor of .75 was used to determine the whole body shelter dose, the average in Pennsylvania is .71. (See reference 8.) Thyroid shelter dose assumes this Protection Factor for inhalation periods of < 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

l EP-317, Rev. 5 Page 3 of 12 MJR/cmb i

2.1.1.8 Evaluate projected dose (item 3), evacuation exposure dose (item 6) and shelter dose (item 7) for 0-2 miles, 2-5 miles and 5-10 miles with respect to protective action guidelines as 1 indicated in section 8. Appendix EP 317-1 provides the EPA guidelines for guidance.

2.1.1.9 Discuss recommendations with the Emergency Director, or if activated, the Site Emergency i Coordinator, to ensure they are informed of the proposed recommendations before they are made to ]

government authorities.

2.1.1.10 Using Appendix EP-317-5 summarize protective action recommendations and mark affected areas on map as  !

i indicated.

2.1.1.11 Update recommendations to the Emergency Director or ,

if activated the Site Emergency Coordinator as new g data becomes available or conditions change.

2.1.2 Dose Assessment Team Leader shall determine the ingestion exposure pathway protective action recommendations.

ACCIDENTS NOT REQUIRING PROTECTION AGAINST DIRECT EXPOSURE MAY STILL WARRANT CONCERN FOR THE INGESTION EXPOSURE PATHWAY THROUGH MILK.

2.1.2.1 Obtain Milk Ingestion Thyroid Dose Projection from the manual or computer dose calculations.

2.1.2.2 Compare Milk Ingestion Thyroid Dose Projection with Appendix EP-317-3 Ingestion Pathway Protective Action Recommendations.

2.1.2.3 Discuss and suggest protective action recommendations with the Site Emergency Coordinator, if activated, or the Emergency Director.

2.2 Site Emergency Coordinator, if activated or -

Emergency Director shall:

2.2.1 Provide recommendations to the Pennsylvania Bureau i of Radiation Protection.

. a. If an Alert or Site Emergency has been declared without prior emergency classification, indicate that no protective actions are necessary for immediate notification in EP-103 Alert Response or EP-104 Site Emergency Response.

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l EP-317, Rev. 5 Page 4 of 12 MJR/cmb t

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b. If a General Emergency has been declared without prior emergency classification and BRP or PEMA are not available, provide the recommendation to shelter the full (360 degrees) EPZ to the counties through Notification Call List in EP-105 General Emergency Response. (Protective action recommendations made directly to Pennsylvania _

counties should reflect.PEMA's philosophy of recommending the same protective action for the full (360 degrees) EPZ.)

or If a General Emergency has been declared with prior classification, use Appendix EP-317-5 Protective Action Recommendation Summary or use Appendix EP-317-4 Protective Action Recommendations based on plant conditions for additional inputs in decision making.

i 2.2.2 When possible, provide background information for

! protective action recommendations to state l

representatives.

3.0 Action - Follow-Up 3.1 Dose Assessment Team Leader shall:

3.1.1 Periodically re-evaluate the situation to determine

if changes in suggested protective action recommendations are needed.

i 3.1.2 Periodically update the Site Emergency Coordinator or Emergency Director.

3.2 Emergency Director or Site Emergency Coordinator shall:

3.2.1 Periodically update state officials on dose projections and actual field measurements.

4.0 APPENDICES -

4.1 EP 317-1 Table of Protective Action Recommendations 4.2 EP 317-2 Protective Action Decision Making Worksheet 4.3 EP 317-3 Ingestion Pathway Protective Action Recommendations 1

a EP-317,'Rev. S' l '

Page 5 of 12 MJR/cmb k

4.4 $P-317-4 Protective Action Recommendations Based on Plant Conditions 4.5 EP-317-5 Protective Action Recommendation Summary 5.0 SUPPORTING INFORMATION 5.1 Purpose The purpose of this procedure is to provide guidelines for determining protective action recommendations to be made to appropriate state or local authorities.

5.2 Criteria For Use 5.2.1 Dose projections from RMMS or from EP-316, Cumulative Population Dose Calculations for i

Airborne Releases are available.

5.2.2 A General Emergency is declared (without

~'

escalation through Alert or Site Emergency) in accordance with EP-101 " Classification of Emergencies."

5.2.3 An Alert, Site Emergency or General Emergency has been declared in accordance with EP-101

" Classification of Emergencies" and neither Pennsylvania Emergency Management Agency.

5.3 Special Equipment ,

l None 5.4 References 5.4.1 Limerick Generating Station Emergency Plan Section 6.4.1.2.C 5.4.2 Limerick Generating Station Cmergency Plan Appendix H 5.4.3 EP-316 Cumulative Population Dose Calculations for Airborne Releases 5.4.4 Pennsylvania Department of Environmental Resources Bureau of Radiation Protection Plan for Nuclear Power Generation Station Incidents,Section VIII.

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EP-317, Rev. 5 Page 6 of 12 MJR/cmb

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5.4.5 U.S. Food and Drug Administration, 21 CFR Part 1090 5.4.6 SAND 77-1725, Public Protection Strategies for Potential Nuclear Reactor Accidents: Sheltering Concepts with Existing Public and Private Structure 5.4.7 EPA-520/1-75-001, Manual of Protective Action i

Guides and Protective Actions for Nuclear Incidents.

5.4.8 EP-101 Classification of Emergencies 5.4.9 EP-315 Calculation-of Offsite Doses during a (Potential) Radiological Emergency Using RMMS in the Manual Mode 5.4.10 Reactor Safety Study, Appendix VI, WASH 1400, October 1975 5.4.11 I.E. Information Notice No. 83-28, Criteria for Protective Action Recommendations for General Emergencies.

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l EP-317, Rev. 5 i Page 7 of 12 MJR/cmb

!I APPENDIX EP 317-1 TABLE OF PROTECTIVE ACTION RECOMMENDATIONS Projected Dose (Rem) to the Population Recommended Actions (a) Comments ,

Whole body <1 No planned protective actions. Previously (b) State may issue an recommended protective -

advisory to seek shelter actions may Thyroid <5 and await further instructions. be reconsidered or Monitor environmental radiation terminated.

levels.

Whole body 1 to <5 Seek shelter as a minimum.(d) If constraints exist Consider evacuation. Evacuate special consideration Thyroid 5 to <25 unless constraints make should be given it impractical. for evacuation of Monitor environmental children and pregnant radiation levels. women.(c)

Control access.

Whole body 5 and Conduct mandatory evacuation. Seeking shelter above Monitor environmental radiation would be an levels and adjust area alternative if

thyroid 25 and for mandatory evacuation. evacuation were not above based on these levels. immediately possible.

Control access.

(a) These actions are recommended for planning purposes.

Protective action decisions at the time of the incident must take existing conditions into consideration.

(b) At the time of the incident, officials may implement low-impact 4

protective actions in keeping with the principle of maintaining radiation exposures as low as reasonably achievable.

(c) It is intended that family units remain intact during any

, ovacuation.

. (d) Shelter is to be with ventilation control.

Ventilation control means turning off ait conditioners or fans, closing doors or windows thus preventing access of outside air.

i Proceed to basement if available.

Reference:

EPA-520/1-75-001 1

EP-317 Rev. 5 Page 8 of 12 MJR/ cab APPENDIX 317-2 Protecttwo Action Area 0-2 miles 2-5 miles 5-10 miles distance of interest site boundary 2 miles 5 miles

1. Enter centerline dose rate in R/hr . . , .
  • tt '

la whole body la Ib thyroid Ib calculated at time =

2. Multiply espected duration of release "t" in hours (hrs)* by whole body and thyroid dose rates to get projected doses 2a whole body projected dose 2a 2b thyroid projected dose 2b
3. Enter evacuatton time esttaste in hours for emisting weather condition Normal Adverse 0-2 2.92 3.75 2-5 4.50 6.16 -

5-10 4.83 6.75

4. Enter Time untti esposure begins, If release has begun a distance of interest (mt)- time release (hrs) mindspeed (mph) has been in progress If release has not begun, a distance of interest (ml) + time untti release (hrs.) 4.

windspeed (mph)

5. Evacuation Esposure Time = smeIIer of or 5.

release duration "t" Item 3 - Item 4

6. Calculate Evacuation Esposure Dose (Rom) 6a. whole body = Item 5 m item la 6a.

l___ ........__ ... __ __... ______________ _________ .... ...__.

6b. Thyroid = Item 5 m item 10. 6b.

7. Calculate Shelter Dose (Rem) 7a. whole body = ttom 2a a .75 7a.

7b. Thyroid = if t < 2 hrs: ttem 2b a .75 7b.

If t > 2 hrs, item Ib (t-0.5)

O eee

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l EP-317 Rev. 5 Page 9 of 12 MJR/Cmu

8. Compare dose projections to protective action guides
  • IF THEN RECOMMENDATIONS Circle one for each mone (0-2) (2-5) (5-10) i Projected whole body dose (Item 2a) is No action No action No action No action l

less than I rem AND projectro thyrold dose (Item 2b) is less than 5 rem Whole body shelter dose (Item 7a) is l

less than 5 rem and thyroid shelter Shelter Shelter Shelter Shelter i

cose (Item 70) is less than 25 rem Wnote body shelter dose (! tem 7a) is l equalto or greater thr: a . rom Shelter Shelter Shelter Shelter l

and less than whole befy evacuation dose (Item La) AND thyrold shelter dose (Item 7b) is equal to or greater than 15 rem and less than thyroid evacuation dose (Item 6b)

Whole body shelter dose (Item 7a) is equal'to or greater than 5 rem Evacuate Evacuate Evacuate Evacuate and whole body evacuation dose (Item 6a) is less than whole body shelter dose ANO shelter dose (Item 7b) is equal to or greater than 25 rem and thyrold evacuation dose (Item 6b) is I less than thyroid shelter dose i

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  • If duration of release is espected to be greater than two hours and projected doses escoeded EPA protective action guides. BRP philosophy is to order evacuation.

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EP-317, Rev. 5 Page 10 of 12 MJR/cmb APPENDIX EP-317-3 INGESTION PATHWAY PROTECTIVE ACTION RECOMMENDATIONS Preventive PAG Response Level Recommended Protective Action Projected Thyroid 1. Remove all lactating dairy Ingestion Dose uncontaminated stored feed and water.

1.5 Rem Emergency PAG Response Level Recommended Protective Action Projected Thyroid 1. Isolate contaminated food Ingestion Dose: products and prevent introduction into commerce.

15 Rem 2. Determine whether condemnation or other disposition is appropriate after consideration of the food products in question.

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EP-317, Rev. 5 g

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MJR/cmb

! APPENDIX EP-317-4 PROTECTIVE ACTION RECOMMENDATIONS BASED ON PLANT CONDITIONS l[( PROTECTIVE ACTION ) l RECOMMENDATIONS 'NEEDED j  ; .,

= .

p S THERE UBSTANTIAL COR YES DAMAGE IN PROGRESS OR NO PROJECTE0? (ACTUAL OR POTENTIA FOR 10 4 R/HR. IN CONTAINMENT)

)  ?

o IhMET YES SUG TED l CONTAINMENT RECOMMENDATIONS FAl{Up{g{R OF 00SE

' NDERWA ASSESSMENT TEAM

? LDR. OR S.T.A.

RECO MEND ,

SHELTER FOR -

NO AREAS THAT CAN'T BE EVACUATED

, BEFORE PLUME ARRIVAL TIME  :

EVACUATE OTHEkS gg 2-5 MILES I

ONTAINMEN RAD MONITOR NO l REATER}HA."

5 x 10 ,

R/HR

?

YES g-4 o

' . . PCSSIBLE RECOMMEC [F POSSIBLE RECOMMEND EVACUATION OF 5 MILE EVACUATION OF 2 MILE RADIUS,10 MILES RADIUS, 5 MILES DOWNWIND DOWNWIND 1P 1P

EP-317, Rev. 5 Page 12 of 12 MJR/cmb k APPENDIX EP-317-5 Protective Action Recournendation Susenary Sheet j Time k'indspeed sph Direction

  • Area Protective Actions . (Froe) 0-2 miles 2-5 miles 5-10 miles 3 N NNW NNE .

l 4 NW NE-

! 10 un.as i

ENE i

2 W I

{

l WSW ESE SW SE

! 55W . $$$ -

5 Mark affected areas .
shelter evacuation i

These protective actions are based on plant status or .

dose projections ef fsictive at time

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