ML20127E163
| ML20127E163 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/25/1985 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20127E160 | List: |
| References | |
| PROC-850325, NUDOCS 8505170553 | |
| Download: ML20127E163 (62) | |
Text
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, . i Page 1 of 5 Revision 33 03/25/85 1 ! l
- e. i i LIMERICK GENERATING STATION 3852077840 ,
! EMERGENCY PLAN PROCEDURE INDEX PROCEDURE REV. DATE SIGNED DATE OF LAST j r NUMBER NO. TITLE BY SUPER. PERIODIC REVIEW EP-101 4 Classification of Emercencies 03/25/85 EP-102 7 Unusual Event Resconse 02/25/85 e
- P-103 8 Alert Response 03/12/85 EP-104 8 Site Emergency Response 03/12/85 EP-105 8 General Emergency Resconse d3/12/85 EP-106 3 Written Summary Notification 01/28/85 EP-110 6 Personnel Assembly and Accountability 03/14/85 EP-120 2 Site Emergency Coordinator 12/12/84 EP-201 3 Technical Support Center (TSC) Activation 01/28/85 b EP-202 3 Operations Suppcrt Center
. (OSC) Activation 12/12/84 EP-203 4 Emergency Operations Facility (EOF) Activation 01/28/85 EP-208 4 Security Team 12/12/84 EP-210 3 Dose Assessment Team 12/12/84 i EP-211 2 Field Survey Grouc 03/25/85
} EP-220 CANCELLED i . [ EP-221 ' CANCELLED p$ EP-222 CANCELLED p Y EP-230 5 Chemistry Sampling and t - \- y-Analysis Team ,% 1 Y EP-231 7 Operation of Post- pv Acciderit Sampling Syst 5 (PASS) 01/ ./h EP-232 CANCELLED p. lM"9%n ngug,, l PDR ( . . , . . . . . -- - - - - . . . - - . - . . . . -
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P i 1 LIMERICK GENERATING STATION 1- , -j EMERGENCY PLAN PROCEDURE INDEX I b . l PR.OCEDURE REV. DATE SIGNED DATE OF LAST
- j. NUMBER NO. TITLE - BY SUPER. PERIODIC REVIEW EP-233. 5 Retrieving and Changing l t
j- Sample Filters and i j Cartridgss from the
) Containment Leak Detector l During Emergencies 03/14/85 k
EP-234 5 Obtaining. Containment Gas Samples from the Containment Leak Detector During Emergencies 03/14/85 EP-235 5 Obtaining Reactor Water L Samples from Sample h Sinks Following g Accident Conditions 03/14/85 EP-236- 5 Obtaining Cooling Tower Blowdown Line Water Samples Following Radioactive Liquid F l-Release after Accident Conditions 03/14/85 1, EP-237 6 Obtaining the Iodine / Particulate and/or Gas . Samples from the North Vent Wide Range Gas Monitor (WRGM) 03/14/85
; EP-238 4 Obtaining Liquid Radwaste 1 Samples from Radwaste ,
{. Sample Sink Following . Accident Conditions 12/12/84 . j EP-240' CANCELLED j EP-241 8 Sample Preparation.and i Handling of Highly l Radioactive Liquid -
; Samples 03/14/85 j- EP-242 4 Sample Preparation and
- r Handling of Highly j Radioactive Particulate r Filters and Iodine l- Cartridges 12/12/84 EP-243 5 Sample Preparation and Handling of Highly Radioactive Gas Samples e 12/12/84 EP-244 3 Offsite Analysis of High Activity Samples 03/12/85
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[ P' age 3 of 5 Revision 33 03/25/85 LIMERICK GENERATING STATION E o EMERGEUCY PLAN PROCEDUEE INDEX l PROCEDURE. REV. DATE SIGNED DATE OF LAST NUMBER NO. TITLE - BY SUPER. PERIODIC REVIEW l EP-250 2 Personnel Safety Team 12/12/s4 i EP-251 2- Plant Survey Group 12/12/84 EP-252 4 Searcn and Rescue /First f- Aid Grouc 02/11/85 EP-253 0 Personnel Dosimetry, Bioassay, and Respiratory Protection
~
j Group 12/12/84 j- EP-254 3 Vehicle and Evacuee ) Control Group 02/04/85 EP-255 2 Vehicle Decontamination 12/12/84-EP-260 2 Fire and Damage . Control Team 12/12/84 l { EP-261 2 Damage Repair Group 12/12/84
!~' EP-272 4 Philadelphia Electric Company Officials Phone List 02/04/85
.EP-273 4 Limerick Station Supervision Call List 02/11/85
} EP-275 CANCELLED
) EP-276 5 Fire and Damage J. Team Phone List 01/24/85 i EP-277 6 Personnel. Safety -.
Team Phone List 02/11/85 1 'EP-278 5 Security Team Phone
! List 03/25/85 ! EP-279 4 Emergency Operations ; Facility-(EOF) Group -
l Phone List 01/22/85
- EP-280 6 Technical Support
't Center Phone List 03/12/85-
.EP-282 4 Government and ) Emergency Management
@ Agencies Phone List 01/22/85 i EP-284 4 Company Consultants and Contractors
- f. Phone List 01/22/85 i
EP-287 3 Nearby Public and -
;: Industrial Users of i
Downstream Water 02/11/85 i. 3B -
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Revision 33
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03/25/85 '
.i LIMERICK GENERATING STATION EMERGENCY PLAN PROCEDURE INDEX 3 PROCEDURE REV. DATE SIGNED DATE OF LAST j' . NUMBER NO. TITLE BY SUPER. PERIODIC REVIEW j EP-291- 5 Staffing Augmentation 02/25/85
. EP-292 7 Chemistry Sampling and Analysis Team Phone
'j .
, EP-294 List 03/14/85-5 Dose Assessment Team i Li . -Phone List 02/04/85 2- EP-301 1 Operating the Evacuation 3- Alarm and River Warning
? System 12/12/84 i .j- EP-303 3 Local Evacuation 12/12/84
.. EP-304
- 3 Partial Plant Evacuation 12/12/84 J- EP-305 5 Site Evacuation 03/25/85 o EP-306 1 Evacuation of the 1(
- ! EP-307 2 Information Center Reception and Orientation 12/12/84
- j of Support Personnel 12/12/84 d EP-312 3 Radioactive Liquid
- ( - Release 02/25/85 i EP-S13 2 Distribution of Thyroid i Blocking Tablets 12/12/84 d .EP-314 0 Emergency Radiation i Exposure Guidelines y and Controls 12/06/84 '
a EP-315 4 Calculation of Offsite 1 Doses During a (Potential) 1 Radiological Emergency j Using RMMS in the 1 Manual Mode 03/12/85 i EP-316 2 Cumulative Population - l and Near Real-Time l Emergency Dose l' Calculations for i Airborne Releases
/ Manual Method 12/13/84 t EP-317 3 Determination of ^
Protective Action Recommendations 03/25/85 i- EP-318 1 Liquid Release Dose Calculations Method for , Drinking Water . 12/12/84 I _. . . . . . . ,..m._,_ . ... ..e . . _.. .. ... . . . . _ . . . . . . . . . . ..
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t .-- , - Paga 5 of 5 j - Revision 33 03/25/85 LIMERICK GENERATING STATION kl- EMERGENCY PLAN PROCEDURE INDEX s j .. j PROCEDURE REV. DATE SIGNED DATE OF LAST i NUMBER NO. TITLE BY SUPER. PERIODIC REVIEW 2 EP-319 -1 Fish Ingestion Pathway ' Dose Calculation '12/12/84 EP-325 3 Use of Containment Dose Rates to Estimate l ' Release Source Term 02/27/85 ( .EP-330 4 Emergency Response i Facility Habitability 03/14/85 i- EP-401 2 Entry-for Emergency Repair and Operations 12/12/84 [i EP-410 2 Recovery Pnase Implementation 12/12/84 f EP-500 2 Review and Revision l of Emeroency Plan 12/12/84 3 j .I l' t I b i e 9 j. o }. ( s h W a e
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- EP-101, Rev. 4 L- 3852077850 Pass 1 of 20.
I. VAW/JLP:mla PHILADELPHIA ELECTRIC COMPANY y~gg gg , LIMERICK GENERATING STATION ) EMERGENCY PLAN IMPLEMENTING PROCEDURE l
)
1 EP-101 CLASSIFICATION OF EMERGENCIES 1 t [ 1.0 PARTICIPANTS J 1 i 1.1 Shift Superintendent or designated alternate shall j assume the role of Emergency Director and implement s this procedure, until relieved. 1.2 Station Superintendent or designated alternate shall 3 relieve tne Emergency Director, assume the role of 3 Emergency Director, and continue implementing this procedure, if necessary. . f, 2.0 ACTIONS-IMMEDIATE i 3 CAUTION: I
. l IMPLEMENTATION OF THIS PROCEDURE DOES NOT ! CONSTITUTE IMPLEMENTATION OF THE EMERGENCY I - , PLAN l I4 l
CAUTION: A l THE JUDGEMENT OF THE EMERGENCY DIRECTOR IS ~
- VITAL IN PROPER CONTROL OF AN EMERGENCY AND E
TAKES PRECEDENCE OVER GUIDANCE I. .TH S EMERGENCY PLAN PROCEDURE .
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VAW/JLP:mla 2.1 Emergency Director shall: IF EVENT TRIGGER IS KNOWN TO BE SPURIOUS, DO NOT CLASSIFY EVENT I.E., FALSE HI READING, FALSE CHLORINE MONITOR READINGS ETC. 2.1.1.1 Select categories related to station events or conditions. - Page Number > Hazards to Station Operation 6 Environmental 7 , Loss of Power 8 Personnel Injury 9 Fire 10 Radioactive Release 11 Evacuation of Control Room 12 Damage of Fuel 13 Instrument Failure 14 Scram Failure 15 , Boundary Degradation /LOCA 16 Unusual Shutdown 18 l Loss of Hot or Cold Shutdown Capability 19 Security 20 2.1.2- Beginning at the indicated page in Appendix EP-101, I review the Emergency Action Levels (EALS) for categories selected. . 2.1.3 Classify the event based on the selected category - and EALS. i 2.1.4 If the most severe events or conditions are l classified as an Unusual Event, implement EP-102,
" Unusual Event Response."
2.1.5 If the most severe events or conditions are i classified as an Alert, implement EP-103, " Alert ! Response." ' 2.1.6 If the most severe events or conditions are ' classified as a Site Emergency, implement EP-104,
" Site Emergency Response." -
2.1.7 If the most severe events or conditions are classified as a General Emergency,. implement EP-105,
" General Emergency Response."
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f 3.0 ACTIONS-FOLLOW-UP U 3.1 If' event is classified as Alert, Site Emergency, or - { General Emergency, the Emergency Director shall: 3.1.1 Periodically evaluate the event classification as [J listed on attached Appendix EP-101. Based upon 3 results of corrective action taken to recover from j' the emergency situation, escalate or de-escalate j the emergency classification. (It is preferable, but net mandatory, to obtain concurrance from the Site Emergency Coordinator and Corporate g Headquarters prior to classification reduction). [ The NRC and appropriate off-site authorities shall ( be informed of the decision to move from one n emergency class to the next. As appropriate, t agencies or personnel listed in checkoff lists of f[ EPs 102, 103, 104, and 105 shall be notified within [ 15 minutes once the emergency level is declared. + 3.1.2 Have a written summary sent to the NRC within eight [ l hours of closeout or de-escalation of the emergency [p clasification in accordance with EP-106, Written Summary Notification. ( ! 3.1.3 When the emergency has been controlled and the power . plant and auxiliaries have been placed in a safe ! [ shutdown condition, only then will a decision be r made as to whether a recov,ery phase is justified. i Enter the recovery phase after the emergency or accident situation is considered-no longer in effect, obtain the concurrence of the Site Emergency [ Coordinator and the Emergency Support Officer at i Corporate Headquarters as required per EP-410, Recovery Phase Implementation. The recovery phase
. is a departure from an emergency situation. The f Site Emergency Coordinator and yourself should '
l evaluate plant operating conditions as well as the ' in plant and out-of-plant radiological-conditions
, when making this decision. Notifications to the j various individuals and agencies that the recovery .
i phase has been implemented is the responsibility of the Site Emergency coordinator. l 4.0 APPENDICES i ! 4.1 EP-101-1 Hazards to Station Operation 4.2 EP-101-2 Environmental - 4 e
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EP-101, Rav. 4 j
- Page 4 of 20 l l VAW/JLP:mla 6
! 4.3 EP-101-3 Loss of Power 4
4.4 EP-101-4 Personnel Injury lf 4.5 EP-101-5 Fire 4.6 EP-101-6 Radioactive Release l 4.7 EP-101-7 Evacuation of Control Room j 4.8 EP-101-8 Damage of Fuel c l 4.9 EP-101-9 Instr'ument Failure j 4.10 EP-101-10 Scram Failure 4.11 EP-101-11 Boundary Degradation /LOCA i l 4.12 EP-101-12 Unusual Shutdown 1 4.13 EP-101-13 Loss of Hot or Cold Shutdown Capability 4.14 EP-101-14 Security s 5.0 SUPPORTING INFORMATION ? 5.1 Purpose e The purpose of this procedure is to provide guidelines for classifying an event or condition into one of four emergency classifications as described in the Emergency Plan. Additionally this 4 procedure details the method to change from one emergency action level to another and to enter the recovery phase, if applicable. i j 5.2 Criteria For Use l' 5.2.1 This procedure shall be implemented whenever the Shift Superintendent becomes aware of conditions ) ; which meet or exceed the Emergency Action Levels in EP-101, Classification Tables. i
! 5.3 Special Equipment i ! None e
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1 - l- - EP-101, Rav. 4 g . Page 5 of 20 t .. l VAW/JLP:mla t. 1 J- 5.4 References ). 1 g 5 . 4 .~ 1 Limerick Generating Station Emergency Plan 1 5.4.2 NUREG 0654 Criteria for Preparation and Evaluation i Rev. 1 of Radiological Emergency Response l j Plans and Preparedness in Support of Nuclear Power Plants
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i 5.4.3 EP-102 Unusual Event Response r
- 5.4.4 EP-103 Alert Response 5.4.5 EP-104 Site Emergency Response 5.4.6 EP-105 General .%ergency Response 2 5.4.7 EP-410 Recovery Phase Implementation
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} Appandix EP-101-1 J Page 6 of 20 4 l VAW/JLP:mla HAZARDS TO STATION OPERATION 4
j. i- UNUSUAL EVENT ALERT
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WHEN BOTH UNITS ARE IN COLD SHUTDONN i l 1. Aircraft crash on-site or 1. Aircraft crash or missile impact unusual aircraft activity over on the Reactor Enclosure, Control the site. Enclosure, Turbine Enclosure, Diesel Generator Enclosure or
- 2. Train derailment within the Spray Pond Pump House.
. site-boundary. . 2. Known explosion damage affecting i 3. Explosion within or near the plant operation.
site boundary. 7 . 3. Toxic, flammable gases or chlorine 1 4. Toxic or flammable gas release detected in the Control Room j 'within or near the site as indicated by 'High boundary. Toxic Chemical Concentration' Alarm or ' Control Room Chlorine Isolation Initiated' Alarm on 00C881. j
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i i SITE EMERGENCY GENERAL EMERGENCY = I- 'WHEN EITHER UNIT IS NOT IN COLD SHUTDOWN
- 1. Aircraft crash or missile impact 3
on the Reactor Enclosure, Control 1 Enclosure, Turbine Enclosure, Diesel Generator Enclosure or
.. . Spray Pond Pump House.
4 4
~i 2. Known explosion damage affecting -
plant operation. i.
- 3. Toxic, flammable gases or o chlorine detected in the 1
[ ' Control Room as indicated by
'High Toxic Chemical Concentration'
( ) i Alarm or ' Control Room Chlorine ! Isolation Initiated' Alarm on 1)! 00C881. I k i* I
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Page 7 of 20 l: l- VAW/JLP:mla ENVIRONMENTAL { UNUSUAL EVENT
-4 4
ALERT I 1. An actual earthquake detected 1. An actual earthquake detected g by the Seismic Monitoring by the Seismic Monitoring j System (00C693) at or below System (00C693) beyond the { operating basis earthquake operating basis earthquake j (.075g). (.075g).
- 2. Tornado strikes the Reactor
- 2. A tornado is observed within or Enclosure, Turbine Enclosure, 1 near site boundary. Spray Pond Pump House, Control 4'
Enclosure or Diesel Generator
- 3. A hurricane is expected to Enclosure.
be in the vicinity of the site. 3. Sustained high winds greater than 70 mph as indicated on i OBC 699. iJ
- i i
O [ SITE EMERGENCY GENERAL EMERGENCY
- 1. Sustained high winds greater 1. Earthquake beyond the safe than 90 mph as indicated on shutdown earthquake (.15g) bl' OBC 699 if either unit is not or other natural disaster which in Cold Shutdown. causes massive damage leading to-other General Emergencies.
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- 2. An actual earthquake detected by the Seismic Monitoring 7 System (00C693) beyond the
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g safe shutdown earthquake (.15g) f -if either unit is not in Cold t Shutdown. o l F e N
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- Appandix EP-101-3 3 Page 8 of 20 l VAW/JLP:mla 4' LOSS OF POWER i
4
, UNUSUAL EVENT ALERT
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- 1. Loss of all off-site power or N/A
.i loss of all on-site AC power j for greater than 60 seconds.
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E 4, __. 4 j SITE EMERGENCY GENERAL EMERGENCY V
- l. Loss of all on-site AC power N/A
{ and loss -of-off-site power q 1 . ( 2. Loss of all safety-related DC power as indicated by: f 4 j a) 250VDC MCC Out of Service alarms J a! and 4 b) 1PPAl D3 Distribution - 1[ Panel undervoltage alarms . .l a 3 'l . j' s I i 1
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- 1. Transportation of contaminated N/A i injured individual from site-to off-site hospital.
N 8. ll . h: a i i SITE EMERGENCY GENERAL EMERGENCY i s N/A N/A i . t ' ? . I i i i l I i e i ..
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EP-101, Rsv. 4 4 App 2ndix EP-101-5 Page 10 of 20 l w. ! N ' VAW/JLP:mla u,7 FIRE 4 *
,n UNUSUAL' EVENT ALERT k.S.. ', s I g ~ 1. Fires involving permanent plant 1. Fire which could make an structures within the protected ECCS inop as indicated by area' lasting 10 mi^nutes or more ' observation.
after s initial attempts to {-
"',M l extinguish it. s4
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s V < .; 5 6-i , S r . t f* f --SITE EMERGENCY, GENERAL ~tSERGENCY
'l. Fire which makes an ECCS 1. Fire which causes massive k
inop andcrequires er causes damage leading to other
, immediate plant shutdown'as General Emergencies, t
i ndicated by observation. > \ 6
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.l . EP-101, Rsv. 4 App 2ndix EP-101-6 RADIOACTIVE RELEASE .Paga 11 of 20 l T VAW/JLP:mla UNUSUAL EVENT ALERT
- 1. Report 1[dicatesliquid i
- 1. Radiological effluents release effluent release exceeds greater than 0.5 mR/hr at site technical specification boundary as indicated by an un-
..'t 3.11.1.1 or 3.11.1.2. controllable release for greater
- than 20 minutes with
- 2. Report indicates gaseous a) North stack effluent radiation l
- j. effluent release exceeds monitor exceeds 1.ON2 uCi/cc or i technical specification i, ;3.11. 2.1 or 3.11. 2. 2 or b) South stack effluent radiation 3.11.2.3 monitor exceeds 1.2N2 uCi/cc.
7 l-t- ! c, p a- , } SITE EMERGENCY GENERAL EMERGENCY 1 f 1. Radiological effluent release 1. Radiological effluent release B greater than'50 mR/hr at site greater than 500 mR/hr at site boundary as indicated by . boundary as indicated by an an uncontrollable release for uncontrollable release for greater than 20 minutes with: greater than 20 minutes with: [ a) North stack effluent radiation a) North stack effluent radiation
-monirer exceeds 1.0 uCi/cc. monitor exceeds 10 uCi/cc.
1 t D- 2. Projected whole body dose 2. Projected whole body dose [ greater than .1 rem or thyroid greater than 1 Rem or thyroid dose greater than .5 Rem at or dose greater than 5 Rem at or
- i. beyond the site boundary over beyond the site boundary over .
- course of the event utilizing course of the event utilizing l RMMS procedure calculating RMMS procedure calculating l offsite doses. offsite doses.
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EP-101, Rev. 4 App 2ndix EP-101-7 4 ' Page 12 of 20
\ VAW/JLP:mla EVACUATION OF CONTROL ROOM UNUSUAL EVENT ALERT N/A 1. Evacuation of Control Room 3 anticipated or required with 1 control established at remote shutdown panel.
e l t e e g i j' l p I L. p i j SITE EMERGENCY GENERAL EMERGENCY
- 1. Evacuation of Contol Rcom N/A
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and control of shutdown systems not established from remote shutdown panel in 15 minutes. 0 P f.
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App 2ndix Ep-101-8 r. Page 13 of 20
'I /JLP:mla DAMAGE OF FUEL 1
t UNUSUAL EVENT ALERT I I
- i. 1. Steam Jet Ai'r Ejector Discharge 1. Steam Jet Air Ejector Discharge l L
radiation monitor exceeds radiation monitor exceeds 2.lP4 mR/hr. 2.lPS mR/hr.
- 2. Steam' Jet Air Ejector Discharge 2. I-131 dose equivalent in the r radiation monitor has an un- reactor coolant exceeds 300 uCi/g expected increase of 4000 mR/hr from sample and main steam over-30 minutes. line high-high radiation with
[ resultant scram. !_ 3. I-131_ dose equivalent in the 3. Spent fuel damage resulting in a , reactor coolant exceeds refueling floor area ventilation F 0.2 uCi/g from sample exhaust monitor alarm. i analysis. , 4. Containment Post LOCA Radiation [ Monitors greater than 1P2 R/hr. SITE EMERGENCY GENERAL EMERGENCY l
- 1. Major damage to spent fuel: 1. Containment Post LOCA Radiation Monitors greater'than 1P4 R/hr.
a) Observation of major damage g to spent fuel o_r_ t I b} Water loss below fuel level i in spent fuel pool.
- 2. Containment Post LOCA Radiation j
Monitors greater than 1P3 R/hr. i l ( e 98
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Appandix EP-101-9 )jj l Page 14 of 20 VAW/JLP:mla
; INSTRUMENT FAILURE y
3- . 1 UNUSUAL EVENT ALERT il . .
] l 1. Complete loss of all Main 1. Loss of all annunciators.
J Control Room communication j equipment.
- 2. Significant-less of asscssment p capability in the Main control j Room as indicated by:
1 1 Simultaneous loss of the j plant. process computer and the ERFDS for a period j p I l greater than 24 hours. 1 4 Li 1 i r r k .q. 1 l j - SITE EMERGENCY GENERAL EMERGENCY 1
.) 1. All annunciators lost and N/A -1 plant transient initiated -
or in progress. 4 .l ~~ 1 ,Ik l-II .
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, "I EP-101, Rev. 4 e
Aconndix'EP-101-10 l' - Pace 15 of 20 [f
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@AW/JLP:mla SCRAM FAILURE V -
1, . UNUSUAL ~ EVENT ALERT i I' N/A 1. Failure of the Reactor protection
} system to automatically initiate and complete a scram and } Scram fails to bring Reactor i subcritical as indicated by l
APRM's greater than 4%, one j; minute after scram initiates. 1 l l i. l
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4 l jt l l- SITE EMERGENCY GENERAL EMERGENCY l
; 1. Transient requiring standby 1. Transient requiring standby liquid control system to liquid control system to h initiate with failure to initiate with failure to scram. Failure to Scram scram and Reactor does not
]L is' indicated by APRM'S I become sub-critical. As greater than 4% one indicated by APRM's greater f' minute after a scram than 4% 10 minutes after
! initiates. scram initiates.
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. EP-101, Rov. 4 App 2ndix EP-101-11 Pace 16aof 20 l* .. AW/JLP:mla BOUNDARY DEGRADATION /LOCA
+. PAGE.1 of 2 .
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- UNUSUAL EVENT ALERT 6
- 1. Failure of a main steam relief 1. Scram with small leak as i; valve or ADS valve to close indicated by:
E following reduction of a) Scram alarm and applicable pressure. [- l b) Reactor level less-than -129" and c) Containment pressure greater than 1.68 psig and pressure is increasing.
- 2. Reactor coolant leak rate exceeds 60 gpm total leakage averaged over any 24 hour period as indicate by surveillance
. test report.
E
- 3. High airborne contamination in the Reactor Enclosure as indicated by:
l'
- a) Reactor Enclosure vent exhaust
- 2. Reactor-coolant leak rate RAD monitor A/B or C/D exceeds 30 gpm total Hi-Hi ALARM on 10C800 (20C800) or
-l leakage as indicated by b) 1000 fold increase of airborne --
p surveillance test report. radiation in a major area of , the reactor enclosure as determined by health physics. e i
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-l VAW/JLP:mla {
BOUNDARY DEGRADATION /LOCA i PAGE 2 of 2 ' SITE EMERGENCY GENERAL EMERGENCY ' l.' Scram with LOCA as 1. Scram with LOCA & no ECCS as indicated by: indicated by: a) Scram alarm and a) Scram alarm and b) Reactor level less than -129" b) Reactor level less than -129" and and c) Containment pressure greater c) Failure to bring Reactor level than 13 psig above -129" after 3 minutes and d) Containment pressure greater than 20 psig
- 2. Main steam line break outside 2. Scram with LOCA & Containment containment without isolation Failure as indicated by:
as indicated by: a) Scram with Reactor level less , than -129" and i a) High Main Steam Line Flow (108.7 paid) and b) Reactor Enclosure Vent Exhaust Rad Monitor A/B or C/D Hi-Hi alarm on 10C800-(20C800) b) High Steam Tunnel Temp (165 deg F) and
-c) Main Steam Line Low Pressure (756 psig)
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-Appandix EP-101-12' Page 18 of 20 l VAW/JLP:mla 1
l UNUSUAL SHUTDOWN i UNUSUAL EVENT ALERT
- 1. Controlled shutdown due to N/A failure to meet limiting condition of. operation.
- 2. Shutdown other than ncrmal f controlled shutdown and for the i purpose of placing the plant t-in a safer' condition.
t i 3. Cooldown rate exceeds technical specification-limits. i-( ? t i
# SITE EMERGENCY GENERAL EMERGENCY 6
N/A N/A-l I
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. EP-101, Rsv. 4 App 2ndix EP-101-13 Page 19 of 20 c -l VAW/JLP:mla Y. LOSS OF HOT OR COLD SHUTDOWN CAPABILITY UNUSUAL EVENT ALERT I
N/A 1. Complete loss of the ability to maintain the plant in Cold [ Shutdown this might be indicated by: l-l l a) Main Condenser unavailable and
; b) Loss of RHRSW or c) Loss of shutdown cooling.
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SITE EMERGENCY GENERAL EMERGENCY 1.1. Complete loss of the ability *
- 1) Shutdown occurs but Decay to maintain the plant in Hot Heat Removal Systems not Shutdown if Hot Shutdown available as indicated by:
condition is required as indicated by: p , a) Reactor operating and p a) HPCI and RCIC not available or scram occurs and b) All Reactor vessel relief b) RER shutdown cooling valves inoperable or not available and c) Loss of Suppression Pool c) All SRV's INOP and cooling. d) EPCI and KCIC not , available o I i h \ l l t 4 . l - v4gime . . ese 1stsee e gewemsp age,, eyew.e . , m. g an...# gue . e . , , . . . . , , .. , , , r **;77'*** ***yRC 'Th*?, "i . ,_ . .V. ~ j'* , **'; *1*
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EP-101, RGv. 4 Appendix EP-101-13 Page 20 of 20
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[': VAWMLP:mla SECURITY [i UNUSUAL EVENT ALERT 4 .l 1. Security threat ol .l. Ongoing security comprcmise s [! l Attempted entry ol e Attempted sabotage as b_ illustrated by: e vent 1 - Sabotage or Bomb Threat Event 2 - Intrusion and Attack Threat Event 7 - Suspected Intrusion Event 8 - Actual Intrusion Event 9 - Suspected Bomb or Sabotage i Device Discovered Event 15 - Guard Strike Event 16 - Onsite Hostage Situation s l-SITE EMERGENCY GENERAL EMERGENCY
- 1. Imminent loss of physical 1. Loss of physical control of l control of the plant. the facility.
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, 3852077860 EP-211, Rav. 2 Page 1 of 17 L/ nip PHILADELPHIA ELECTRIC COMPANY 8,3 N
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LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE {, EP-211 FIELD SURVEY GROUP i 1.0 PARTICIPANTS
- 1.1 Field Survey Group Leader shall direct the actions
! of the Field Survey Group members.
I 1 1.2 Field Survey Group Members shall conduct field I surveys and onsite (out-of-plant) surveys. 2.0 ACTIONS - IMMEDIATE 2.1 Field Survey Group Leader (FSGL) shall 2.1.1 Report to che Technical Support Center (TSC) . i 2.1.2 Discuss the situation with the Dose Assessment Team
! Leader. This discussion should include the i potential for release, the magnitude of the radioactive source term, meteorological conditions
( and potential for change, and the number of field 3' survey squads needed. 2.1.3 Coordinate the formation of the necessary number of field survey squads from personnel supplied by the Operations Support Center (OSC). A squad consists
, .of a Health Physics Technician and a driver, t
N. 2.1 4 btain drivers and vehicles from the Fire and Damage g '*feam Leader and have them report to the TSC. sfg . S' Direct field survey squads to obtain emergency
~
dosime g N , n i 2 . tu he H.P. Technicians to secure and i tory the required number of field survey kits i dyradios, and perform equipment checks. The S> ios are located in the Dose Assessment Room in the Technical Support Center and the field survey
;- kits are located in the storage closets in the Personnel Zntry Area of the Technical Support
\0 Center.
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[- j EP-211, Rev. 2 l d' Page 2 of 17 ! 3 REL/ nip l I 1 . 2.1.7 Discuss the situation with each squad, assign each
} squad a unique color designation, and direct them to I specific initial locations.
IF THE FIRST SURVEY POINT IS AN ONSITE LOCATION, I. INFORM THE SQUAD (S) MEMBERS OF ADDITIONAL PRECAUTIONS ASSOCIATED WITH THE POTENTIALLY ELEVATED 7- RADIATION LEVELS. METEOROLO3ICAL CONDITIONS, EXPECTED RADIATION LEVELS, AND OTHER HAZARDS SHALL BE USED TO DETERMINE I THE POSITIONING OF FIELD SURVEY GROUPS. L I 2.1.8 Notify Security Team Leader of the names of field survey squad members so that they will not be-detained upon leaving the site. i - F 2.2 Field Survey Squad Members shall: V 2.2.1 Report to the Field Survey Group Leader (FSGL) at {[ the Technical Support Center or the Personnel Safety [t ~ Team Leader after the EOF has been activated. ( 2.2.2. Obtain a field survey kit and a radio. t : .
) 2.2.3 Break the seal on the field survey kit and check l equipment for operability including source check of p survey equipment. Document equipment checks on EP-E 211-2.
- 4.
IF THE SEAL ON THE FIELD SURVEY KIT WAS ALREADY
$ BROKEN, PERFORM AN INVENTORY OF THE KIT CONTENTS.
[ i 2.2.4 Obtain emergency dosimetry (0-1500 mR and 0-5 R i- Direct Reading Dosimeters (DRDs). Ensure that DRDs are zeroed prior to leaving the TSC. l l 2.2.5 Obtain information from the FSGL on the situation, q plan of action, specific survey locations, and . j necessary. precautions. l ISSUANCE OF A 0-5 R DRD IS NOT TO BE INTERPRETED AS [' AN AUTHORIZATION TO EXCEED STATION ADMINISTRATIVE GUIDELINES. , g ,, 2.2 6 Upon leaving the TSC keep all dosimetry.
! 2.2.7 Ensure that the E-520/HP-270 or equivalent is on and r operating prior to leaving the TSC.
l 2.2.8 Perform communication check of radios with the FSGL ; at the survey vehicle. [ . I w=m+ -
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N . t EP-211, Rav. 2 1' Page 3 of 17 i' s REL/nlp 1
- O - t 2.2.9 Proceed to the first survey point as directed by the 3 FSGL.
A-11 d ]. 3.0 ACTIONS - FOLLOW-UP W 3.1 Field Survey Group leader shall: U- 3.1.1 Maintain communication with and direct the j activities of the field survey squads. Ensure that d the location of each squad on the Field Survey [ display map is updated as necessary. 3.1.2 Obtain field survey results as provided by field . L survey squads and record results on EP-211-5, Field Survey Group Leader Data Record. 3 f 3.1.3 Provide the field survey squads with status updates including: radiological and meteorological g conditions, etc. i
- 3.1.4 , Dispatch the field survey squads to additional i survey locations as necessary.
i [ t 3.1.5 Field Survey Group Exposure Record, Appendix EP-211- } 3, shall be completed as directed by the-Field [ Survey Group Leader. l ti 3.1.6 If the field survey squad members ahd/or vehicles become contaminated inform the Personnel Safety Team Leader. C k' 3.1.7 When advised that the EOF has taken over the Dose Assessment function, inform the field survey squads.
, Perform a formal turnover with the EOF Field Survey Group Leader and report to the Dose Assessment Team i Leader.
i 3.2 Field Survey Squad Members shall - i { If an onsite (out-of-plant) survey is required, take an air sample using a Lapel Air Sampler in 4
- i. accordance with the appropriate steps of HP-428,
} Operation of the Gillan Model NFS ll3AUT Lapel Air ! Sampler, transport the air sampler assembly to the counting room on Elevation 217 of the Radwaste ~
Enclosure to be analyzed, and proceed with the
] remainder of this procedure.
j . 1 3.2.1 while in transit,' ensure that the E-520/EP-270 or i equivalent is on and switched to the lowest appropriate scale. Hold the probe outside the vehicle and have the driver proceed until the j l 1 _ _ . . . . . . _ , . . . _ . . . . . . _ . . . . . . . . - . . . . , . . . . . . _ . . . . _ . . - . . . . . . . . . . . mee p[,.,n ,- e e. . . . , , ..- ,..m,4 ,--......g.. ..w.... . . . .. ,.y . ., ..p. . ~ _- . . _ . ~ . - - . . __ _ ,C . . u~ __1. ; ~ 2, ;_ _- _-. . - _ m _. -. -- -.,, h , _
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EP-211, Rev. 2 Page 4 of 17 REL/ nip specified survey location is reached. Continuousiy monitor the survey instrument while in transit. 3.2.2 When survey location is reached, pull off the road and turn on emergency flashers. Exit vehicle and determine the maximum dose rate at waist height in a 360 degree radius using the E-520/HP-270 or equivalent. Take readings with the probe shielded and unshielded. If the unshielded reading is greater than two times the shielded reading, assume that you are immersed in the plume (as opposed to seeing the effects of skyshine). 3.3.3 Record all results on EP-211-2, Field Survey Group Survey Record, and transmit information to the FSGL by radio. If the radio does not function properly, locateatelephoneandreportsurvey]information.(EOF) [] the Call. (TSC) o r' . ]and ask Field Survey Group Leader. 3.2.4 Take air sample at the " field" survey locations if directed by the FSGL as follows:
. CAUTION ENSURE THAT THE ON/OFF SWITCH IS OFF PRIOR TO CONNECTING THE AIR SAMPLER TO THE VEHICLE BATTERY.
CONNECT RED LEAD TO THE POSITIVE BATTERY TERMINAL
- AND BLACK LEAD TO NEGATIVE BATTERY TERMINAL.
3.2.4.1 Connect terminals of Radeco H809C or equivalent to vehicle battery with engine running as stated above. Place air sampler on an elevated surface, not the ground. 3.2.4.2 Mark filter and silver zeolite cartridge to indicate air flow direction. 3.2.4.3 Orient the air sampler toward the plant and run air sampler for 5 minutes or as directed by FSGL. Record the indicated flow rate on EP-211-4, Field Survey Air Sample Data Record.
\
3.2.4.4 Wh'ile air sampler is running, label one envelope and l
'one small p1'astic bag with the following l infotsation Location, Date, Flow rate, Time On, and 1 Time Off. I AIR SAMPLER SHOULD NOT BE RUN AT GREATER THAN 2.5 cfm. ADV E ICE IS THE CASE.
373
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c . - a.; . .- . - - - -- - - f' .- . EP-211, R3v. 2 ; Page 5 of 17 ' REL/ nip 3.2.5 If so directed by the FSGL take 6 inch and waist level shielded probe measurements using the E-520/RP-270. If the 6 inch reading is greater than the waist level reading, take several disc smears of representative flat environmental surfaces. Using :' caution to prevent the spread of contamination, place smears in labelled envelopes for counting at a : later time. 3.2.6 when you have finished collecting the Air Sample, inform the FSGL that the air sample is ready to be analyzed. Disconnect air sampler, place air sampler in vehicle, and drive to a low background counting , area, as directed by the FSQL. While in transit, ya monitor E-520/RP-270 or equivalent for radiation levels. Note minimum and maximum readings and transmit the location of these readings to the FSGL. t , CAUTION IF BACKGROUND RADIATION LEVELS EXCEED 300 CPM USING , THE E-140N/RP-210 T, INFORM THE FSGL AND MOVE TO I ANOTHER COUNTING AREA WHERE THE BACKGROUND IS LESS l ! , TRAN OR EOUAL TO 300 CPM. . 3.2.7 Remove only the particulate filter from the air sampler head and perform pn analysis of the particulate filter using the E140N/RP-210T with the SR4A sample holder. Record background readings and t sample readings in EP-211-4, Field Survey Air Sample Data Record. Calculate MPC Fraction and record on j EP-211-2. 4 MPC = net CPM (volume) (17) 3.2.8 Run the air sampler for one minute with the silver l t zeolize cartridge in place to purge the cartridge. , 3.2.9 Determine Radiciodine concentration as directed by FSGL using E-140N and section 6.3 of RP-204 " Rapid Assessment of Radiolodine", or by using the SAM 2 ' and the following steps. Record Iodine concentration on EP-211-2. (If using RP-204, l proceed to step 3.2.18). 3.2.10 l Upon arrival at the low background counting area, I set up the SAM 2 or equivalent and allow to warm up I and stabilize, as follows: 3.2.10.1 Connect cable from RD22 probe to " Detector" jack on the front of the SAM-2. O
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7 . EP-211, Rav. 2 I. Page 6 of 17 b REL/nly i l 3.2.10.2 Connect the battery lead to the " Battery" jack on' the back of the SAM-2. Plug other end of lead into j- the socket on the side of the battery jack. 4 i l 3.2.10.3 Set the SAM-2 Controls as follows: " l ! l Stabiliser: OFF l l Count Mode: TIMED 0 [ l Meter Channel: 1 1 j Windows Set as shown on i Calibration Sticker i l Threshold: Set as shown on
- Calibration Sticker
- . l Multiplier
- 210
! l Response: " Midrange" "IN" P l Count Time 5x1 ,
; l Channel 1: In, +
l Channel 2: Off, out N.V.: As shown on the SAM-2 ! Calibration Sticker V
- 3.2.10.4 Switch the " Power" Switch on the back of the SAM-2 j to "ON". Press the " RESET START" button on the i front of the SAM-2 and allow the instrument to count for 5 minutes to warm up.
l [ l IF THE "BATT OK" LIGHT IS NOT LIT, INFORM FSGL. 1 [ ] 3.2.11 Place the Ba-133 check source cartridge against-the 1 end of the RD22 probe and set the count time on the - ! SAM-2 to 2x1 minutes. Press the " RESET START" ! button and count. Record total number of counts on ; j Appendix EP-211-4. l l 3.2.12 Yo establish the background of the counting system, l , exchange a clean silver zeolite cartridge for the i Ba-133 check source and press " RESET START". Record total number of counts on Appendix EP-211-4. { l 3.2.13 Compute the net count rate as follows: S i NET (CPM) = GROSS COUNTS-BKG COUNTS l l 2 I k j and record on Appendix EP-211-4. l l ' h.-.._.,,.....,.,......._...,_..._.._.....,...-....'.... l 8 * ,* p g m _.
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1 . j.- [ EP-211, Rev. 2 j: Page 7 of 17 REL/ nip v f I l 3.2.14 Compare the net count rate to the allowable net , count rate listed on the SAM-2 calibration label. If the measured net count rate is within the range n specified, proceed to 3.2.14 and use the SAM-2 for j 'I-131-determination. IF THE NET COUNT RATE FALLS OUTSIDE OF THE ALLOWABLE RANGE, REPEAT STEPS 3.2.10
} TO 3.2.13 ONE TIME. If results are still 3
j unsatisfactory, inform the Field Survey Group g Leader. f THE BA-133 SOURCE CHECK STEPS 3.2.10 to 3.2.13, MUST [ BE PERFORMED INITIALLY TO VERIFY SATISFACTORY t-OPERATION OF THE SAM-2 COUNTING SYSTEM. THIS CHECK [ NEED NOT BE PERFORMED PRIOR TO COUNTING SUBSEQUENT
, AIR SAMPLES UNLESS THERE IS REASON TO SUSPECT A
[ PROBLEM WITH THE SAM-2 COUNTING SYSTEM. THE
;. BACKGROUND, HOWEVER, MUST BE COUNTED PRIOR TO p COUNTING EACH AIR SAMPLE. l l 3.2.15 Remove the silver zeolite cartridge with the field t sample from the air sampler head and carefully wrap the cartridge in cellophane.
[ 'l 3.2.16 Place the RD22 probe next to the wrapped cartridge and press " RESET START". Record TOTAL number of counts on EP-211-4 when the count is complete. 3.2.17 Calculate I-131 concentration using the equation listed in EP-211-4. I l 3.2.18 Transmit Iodine concentration to FSGL. L l 3.2.19 Rebag the samples for transport back to the site for
. analysis.
l 3.2.20 Await further instructions from the Field Survey Group Leader. l 3.2.21 Before returning to the site, survey self and vehicle for contamination. If contamination is found, inform the Field Survey Group Leader and take the vehicle to the designated Vehicle
- Decontamination Facility.
3.2.22 Bring all environmental samples to the chemistry Control Point in the Radwaste Enclosure and turn them over to a member of the Chemistry Sampling and Analysis Group or as directed by the FSGL. Fill out the necessary data sheets when dropping off sampler. 1 I l 3.2.23 Place all data forms in a clean plastic bag and have a noncontaminated individual bring the bag to the Field Survey Group Leader in the TSC.
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'. .. e . EP-211, R2v. 2
! Page 8 of 17 ,
REL/nlp I. l- 3.2.24 The Health Physics Technician shall inventory the. l field survey kit upon returning to the site and report results to FSGL.
! -4.0 APPENDICES 4.1 EP-211-1, Emergency Exposure Guidelines 4.2 -EP-211-2, Field Survey Group Survey Record
( 4.3 EP-211-3, Field Survey Group Exposure Record f: 4.4 EP-211-4, Field Survey Air Sample Data Record. t 4.5, EP-211-5, Field Survey Group Leader Data Record [ i 4.6 EP-211-6, Field Survey Checklist I k
- 5.0 SUPPORTING INFORMATION i
[ 5.1 PURPOSE I The purpose of this procedure is to provide i: e instructions and guide. lines for the actions of the ! Field Survey Group. f 5.2 Criteria for Use
! 5.2.1 An actual or potential release of radioactive material beyond the site boundary in excess of technical specifications, f 5.2.2 The Field Survey Group shall be activated at the Alert level or as determined by the Dose Assessment Team Leader.
5.2.3 The group members exposure shall be limited to the , guidelines in EP-211-1, Emergency Exposure Guidelines., 5.3 Special Equipment 5.3.1 Radio with 2 Battery Packs 5.3.2 Field survey kits , 5.3.3 Vehicle i . [ 5.3.4 Emergency Dosimetry (0-1500 mR and 0-5 R DRD's)
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- j. FIL/nly i 5.4 References I
i 5.4.1 HP-428, Operation of the Gillan Model HFS ll3AUT
;- Lapel Air Sampler ! 5.4.2 HP-204, Rapid Assessment of Radiolodine i Concentration I 'l I
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; EP-211, Rev. 2 3 Page 10 of 17
- REL/ nip APPENDIX EP-211-1 EMERGENCY EXPOSURE GUIDELINES 1 Projected Whole Body Thyroid Authorized
[ Function Dose Dose By
- 1. Life Saving and -
Emergency ** g Reduction of Injury 75 ren* 375 rem Director 'i
! 2. Operation of Equipment to Mitigate an Emergency **
Emergency 25 ren* 125 rem Director [ i 3. Protection of Health Emergency ** 4 and Safety of the Public 5 ren 25 rem Director
- 4. Other Emergency 10 CFR 20 10 CFR 20 Emergency Activities limits limits Director
(
, 5. Re-entry / Recovery Station Station Activities Administra- Adminis-tive Guide- trative 5
lines Guide-lines N/A
Reference:
EPA-520/1-75-001 Table 2.1
** Such exposure shall be on a voluntary basis i -
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7 . . . . . EP-211, Rev. 2 Page 11 of 17 i' REL/nly i APPENDIX EP-211-2 i FIELD SURVEY GROUP SURVEY RECORD (Page 1 of 2)
, Field Survey Team i ' Team Members:, Dater / /
i k I i INSTRUMENT IivvsruGRY Instrument Type Serial Number Calibration ok Batt ok Response ok l l R0-2A E-520 E-140N NP210T Radeco N-890C SAM II Lapel Air Sampler ,i )
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.'; APPENDIX EP-211-2 .t 'j. FIELD SURVEY GROUP SURVEY RECORD (Page 2 of 2) jl!
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[); R-520/RP-275 !l Date/ Shielded Unshielded MPC Smear- Whole ! :n g Time Time in 6"/weist waist Fraction uC1/cc Results lj Survey Lo.stion of Survey Area Body MR/NR MR/RR Gross B I 131 dpa/100cm2 Exposures I{g tli !a .. 1. I'] I in E 2. ol t Ef, .' I 3. lS I 4. n ! A t *.i 5. .
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L EP-211, R2v. 2 Page 13 of 17 l I~ REL/nlp l i l I < APPENDIX EP-211-3 j: FIELD SURVEY GROUP EXPOSURE RECORD ? i Field Survey Team Date: / / 4 Time: 5 Dose ! Rec'd. Time Spent In j Name (mR) Area (Hrs.) MPC-hours ** I L t (A) HP TECH ) (B) DRIVER k f _( C) OTHER f **MPC-hrs (I 131) = (Detected conc. uCi/cc I 131) (Time in Area) (1.llP8 MPC/uCi/cc
- ** NOTES
- 1. MPC-HOURS ARE CALCULATED USING I-131 AS THE LIMITING ISOTOPE i
- 2. MPC-HOURS ARE ADMINISTRATIVELY CONTROLLED AT 20 MPC-HRS /WK; i
. Exposures >20 mpc-hrs /wk to 40 mpc-hrs /wk can be authorized by j the Personnel Safety Team Leader 7.
t, (A) (B) (C) (A) (B) (C) l Previous Daily Exposures (mR) W/B MPC-hrs, k
- - Exposure from this entry + (mR) W/B MPC-hrs.
Exposure Totals (mR) W/B MPC-hrs. . Remaining Balance (mR) W/B MPC-hrs. i-l- 23. INDIVIDUALS SUSPECTED OF EXCEEDING 10 MPC-BRS/WK ARE REQUIRED TO 1 RAVE A WHOLE BODY COUNT
- 4. DOSIMETRY' RECORDS ARE REQUIRED FOR EXPOSURES > 2 MPC HRS / DAY,
>10 MPC HOURS /HK.
l COPIES TO: - FIELD SURVEY TEAM LEADER; - DOSE ASSESSMENT TEAM LEADER I I E
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EP-211, Rsv. 2
.' Page 14 of 17 REL/ nip I
APPENDIX EP-211-4 L FIELD SURVEY AIR SAMPLE DATA RECORD Date: / / Time: [ Survey Team "
- Location
"~
Sector PART 1 I.. L
- 1. Air Sample " Time On"
- 2. Air Sample " Time Off" l 3. Air Sample Run Time minutes
'4. Air Sample Flow Rate cfm
- 5. E-140N/RP-210T Background cpm
- 6. Particulate Filter Gross Count Rate cpm i 7. Particulate Filter Net Count Rate cpm (net)
- 8. AgX Cartridge Gross Count Rate 'cym
. 9. 'AgX Cartridge Net Count Rate cpm (net) , *10. SAM-2 Ba-133 Check source , counts /2 min. I 11.-SAM-2 Background (clean cartridge) Counts /2 min. i
*12. Ba-133 Net Counts Counts /2 min.
7
- 13. SAM-2 I-131 field sample Counts /2 min.
l
- Perform initially to verify operation of SAM-2-See NOTE, sec. 3.2.14 PART 2 h
L Determination of I-131 Concentration .
- 1. Air Sample volume:
, Run Time (#3) X Flow Rate (#4) =
cubic feet (ft3) r 2. (#13) (#11)
~ ~ ~ ~ ~ ~ ~
i Counts - Bkg ~ l l l ) _ 2 Minutes _ _ Eff _ _ Volume _ _ 0.95 _ x 1.59 Nil = uCi/cc i _ 2 Min _ _ _ _ _ _ 0.95 _ x 1.59N11 = uCi/cc PART 3 Determination of MPC Fraction (If directed by FSGL) E-140N -(Net CPM)
= 4 MPC i (Volume) (17) f
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Ptga 15 of 17 REL/ nip i l APPENDIX EP-211-5 l' FIELD SURVEY GROUP LEADER RECORD J j Date: / / Time: EST
. I Survey Team " "
1 Location s
! 6" Waist High Sector 4
Area Dose Rate ( ) mR/Hr (shielded)E-520/HP-270 i}. mR/Hr (unshielded) E-520/HP-270 i-() 1
! Direct Frisk of' Air Sample Filters l
1 2
- AgX net epm j Particulate Filter net cpm i
I ! Air Sample Data (Part) MPC Fraction (unidentified) i i
, (I - 131) uci/cc i
l Copies to: Field Survey Team Leader - Status Board Keeper - Dose l Assessment Team Leader
- 5 l
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- REL/nlp i-APPENDIX EP-211-6 j: FIELD SURVEY CHECKLIST
- l. BEFORE LEAVING SITE A) All Equipment accounted for and operable B) Have been briefed on situation, etc.
;. C) Have Emergency Dosimetry and they are zeroed D) Communication check performed E) E520/RP270 is ON
- 2. AT THE SURVEY LOCATION AND WHILE IN TRANSIT A) Looked for and reported location where increasing
,_ radiation levels occurred while still in transit to
' ' specified survey location u
B) Performed air sample using lapel air sampler, if nece.ssary , C) Performed survey using E-520/RP-270 to look for maximum dose rate at waist level in 360 deg. radius D) Survey with E-520/HP-270 with probe shielded and unshielded P J E) Have notified FSGL of arrival and dose rate encountered F) If advised to take air sample:
- 1) Particulate filter and silver zeolite cartridge marked to indicate direction of air flow
- 2) Air Sampler head loaded with filter located outside L of cartridge
- 3) Air Sampler head oriented toward the plant and running
, 4) Flow Rate observed and recorded G) If directed by FSGL, 6 inch gamma readings taken with E-520/RP-270 O
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EP-211, R3v. 2 Page 17 of 17 REL/nlp i' H) If,6;" readings higher than waist level readings, smears taken I) Notified FSGL that Air Sample has been pulled and
. advised'to move to low background counting area and method to be used to analyze sample J) E520/HP270 is ON during transit - looking for and reporting locations of maximum and minimum dose rates i.
l.
- 3) AT LOW BACKGROUND COUNTING AREA A) SAM 2 set up and counting for 5 minutes to warm up i
*B) 2 minute count of Ba-133 check source (for initial analysis only) !: C) Remove and count particulate filter with E-140N/HP-210T 4
l D) Purge Silver zeolite cartridge for 1 minute j E) 2 minute count of clean Silver Zeolite cartridge i F) 2 minute count of Sample Silver Zeolite cartridge 1 2 - j G) I-131 Concentration cal'eulated i
! H) All results recorded and relayed to FSGL y I) Advised to move to new location s J) If advised to return, monitor self and vehicle and j relay findings to FSGL r! K) All samples turned over to Chemistry Sampling & .
$ Analysis Group at 'LRSchemistry Control Point in . f Radwaste Enclosure L L) All forms turned over to FSGL for subsequent dispostion { g
- Perform initially to verify satisfactory operation of SAM-2 counting system only i,
7
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l N EP-278, Rov. 5 i 'f - J l 3852077870 Page 1 of 2 VAW/JLP:rgs t s -s, PUU.ADELPHIA ELECTRIC COMPANY
. LIKERICK GENERATING STATION 3-SS 55 EMERGONCY PLAN IMPLEMENTING PROCEDURE V
EP-278 < GECURITY TEAM PHONE LIST 1.0 PARTICIPANTS 1.1 Security Team Leader calls in team members. 2.0 ACTIONS - IMMEDIAT_E i 2.1 Securi'ty Team Leader shall call pecple from the following list until an adequate number are able to respond in the appropriate groups. 2.2 Security Team Leader Telechone No. E ' Peter Supplee Mark Berner(Cap. of - [ the Guards) l J. A. Basilio l l l Richard Parker (Access Lt.) l Nunan, Marion l Brumm, Marty l ombay, Johnn ,.. I l yter, Russ - i l Security Team Members Securi am Leader shall contact Security Team
.w (% mbar rom the Security Phone list until a N s ent number have been contacted.
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. / I EP-278, R0v. 5 i
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! VAU/JLPtrgc L
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; 3.0 ACTIONS - FOLLOW-UP h ; None Required ~
t
? 4.0 APPENDICES k i r
None 1 L 5.0 SUPPORTING INFORMATION t
~
lg. 5.1 Purpose The purpose of this procedure is to provide h guidelines and information to call in the Security j Team. s j --Sv2 Criteria for Use i I This procedure can be used when the Security Team is to be activated or when people need to be called
~
in. 5.3 Special Equipment L. t-t, None t [ i 5.4 References None 1 k a
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r,__ 1.I~ 1 3 8 5 20 7 78 8 0 EP-305, Rev. 5 ls Page 1 of 5 3 VAW/JLP:mgd PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION 3-35-15 j EMERGENCY PLAN IMPLEMENTING PROCEDURE h L K EP-305 SITE EVACUATION W t t 1.0 PARTICIPANTS u 1.1 Emergency Director shall direct the evacuation of l the site. d j 1.2 Security shall perform accountability of personnel ] during the evacuation. ?
- 1.3 Bechtel/ Subcontractor eersonnel shall evacuate in
( h accordance with Bechtel Evacuation Procedures, l 1.4 Non-essential Unit 1 and Unic 2 cersonnel shall evacuate. ]' 2.0 ACTIONS - IMMEDIATE L 2.1 Emergency Director shall: I 2.1.1 Determine the offsite assembly area based on wind direction, weather conditions, and other pertinent information: Cromby Generating Station or, f merick Airport L ] 2.1. termine route to be used to leave site (i.e. g f main gate or back gate). If wind is from south 1 j
,- consider using back gate, for any other direction ,
consider he main gate. i -
.N 1 g IN DIRECTION IS FROM SOUTHWEST, CONSIDER H
3 N
- f@ FTREk(DMBYGENERATINGSTATION.
IM' CR ANY OTHER WIND lt 'N .: DI$' ?CTION CONSIDER USING LIMERICK AIRPORT. 2 .;
'4 ,,
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I - EP-305, R2v. 5 Pago 2 of 5 VAW/JLP:mgd i 2.1.3 Notify and inform the Security Team Leader of the following information: A. Chosen exit points, routes and selected offsite assembly areas. 1 l B. Implement EP-208, Security Team for Site l Evacuation. l l 2.1.4 Notify and inform the Personnel Safety Team Leader of the following information: A. Chosen exit points, routes and selected j offsite assembly areas. B. Implement the applicable actions in EP-254, Vehicle and Evacuee Control Group. 2.1.5 Notify PEMA or BRP (if on site) that a Site Evacuation is being called. l 2.1.6 Notify chosen assembly area of'the site evacuation: l l l Cromby Sta, tion:Q. _ , , l Pottstown Limerick Airport. l 2.1.7 Evacuate all Co,nstruclion Personne) by c tacting Bechtel Safet t. 'pr Security (_, and direct them to call for a " Total Projec Evacuation" in accordance with Bechtel Evacuation i Procedures, if not already done, and direct them i to report to the selected offsite assembly area
- 1 using the selected routes for leaving the site.
l l 2 .1.'8 Implement the evacuation of the Information Center in accordance with EP-304 Evacuation of the f InformationCenter{ already done .
] if -not l 2.1.9 When the Security Team Leader 'is ready, direct the {
ACTIVATION OF THE ALARM in accordance with EP-301, j Operating the Evacuation and River Warning System. ACTIVATE BOTH THE SIREN AND THE RIVER WARNING
~
MESSAGE. PROPRIETARY e
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EP-305, Rev. 5 Paga 3 of 5 VAW/JLP:mgd e , l 2.1.10 When the alarms are silent, ANNOUNCE EVACUATION as 4 follows:
" ATTENTION ALL PERSONNEL. THIS (IS)(IS NOT) A DRILL. THIS (IS)(IS NOT) A DRILL. THIS IS A SITE EVACUATION. DESIGNATED EMERGENCY RESPONSE PERSONNEL REPORT TO ASSIGNED ASSEMBLY AREA. ALL OTHER PERSONNEL EVACUATE THE SITE IMMEDIATELY. ALL EVACUATING PERSONNEL SHALL RE-ASSEMBLE AT (CROMBY l GENERATING STATION) (THE LIMERICK AIRPORT). THIS (IS)(IS NOT) A DRILL. THIS (IS)(IS NOT) A DRILL.
l 2.1.11 Activate alarms again. l l 2.1.12 Repeat announcement. Make announcement on Unit 2 page . l 2.1.13 Direct the workers at the RMC Facility on Fricks l LockRoadtoevacuate{g )) l 3.0 ACTIONS - FOLLOW-UP l l 3.1 Security shall: , , . _ . _ 3.1.1 Perform account' ability of personnel in accordance with EP-110, Personnel Assembly and Accountability. l 3.1.2 Inform the Emergency Dir'ector of unaccounted for personnel. 3.2 Emergency Director shall: l 3.2.1 Direct the Personnel Safety Team Leader to f initiate search and rescue operations for any l unaccounted for personnel in accordance with ! EP-252, Search & Rescue /First Aid.
- 3.3 Bechtel/ Subcontractor (Unit 2) Personnel shall
- ,
i ! 3.3.1 Evacuate in accordance with Bechtel Evacuation { Procedures, using personal vehicle to leave the i site, b , 3.4 Non-Essential Unit 1. personnel shall: 3.4.1 Exit the protected area through the Administration Guard House or Technical Support Center Guard House by depositing security badges and dosimetry into containers, and re rt to the selected
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EP-305, Rsv. 5 Paga 4 of 5 VAW/JLP:mgd 3.4.2 Follow vehicle evacuation routes as directed by Security personnel. 3.5 Designated Emergency Resoonse Personnel shall: 3.5.1 Report to their_ designated assembly area in j accordance with Appendix EP-110-1, Emergency .; Assembly Areas.
)
1 4.0 APPENDICES .i - . i None. ' 3, 1 - 1
- 5.0 SUPPORTING INFORMATION i a 1
5.1 Purpose
~
The purpose of this procedure is to define the i actions to be performed if a site evacuation is ] required. 5.2 Criteria For Use
]. 5.2.1 This procedure should be implemented by the- . Emergency Director at his discretion or when an
'i ' actual or potential radioactive release exceeds j l that specified as an Alert or Site Emergency level 1 in EP-101, Classifications of Emergencies. L
, The Emergency Director should consider the ; following when deciding to evacuate the site:
4 5.2.1.1 The decision to evacuate personnel as a protective j action should be based on the determination that 1 it will result in the lowest personnel exposure in comparison with other protective action options. . 1 5.2.1.2' Consider the dose rates at the personnel assembly , areas, onsite, and along evacuation routes, number
. of personnel onsite, and the potential for j mitigating or terminating the emergency prior to ; personnel receiving exposures in excess of the ; protective action guides.
1 4 I i e
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l ',... EP-305, R&v. 5 Paga 5 of 5 VAW/JLPtmgd t ( 5.2.1.3 Initiate site evacuations before or after the i passage of the release, and when practical, evacuation routes shall be given to lead personnel
- away from the path of the plume.
i j 5.3 Special Equipment j None 5.4 References 4 5.4.1 Limerick Generating Station Emergency Plan i l 5.4.2 NUREG.0654, Criteria for Preparation and Evaluation of i Rev. 1 Radiological Emergency Response Plans and i Preparedness in Support of Nuclear Power i Plants. i l 5.4.3 EP-252 Search and Rescue /First Aid Group 5.4.4 EP-101 Classification of Emergencies v 5.4.5 EP-110 Personnel Assembly and Accountability EP-208 4 5.4.6 Security Team i
; 5.4.7 EP-254 Vehicle And Evacuee Control Group 5.4.8 EP-301 Operation of the Evacuation Alarm and River Warning System ,
i 5.4.9 EP-306 Evacuation of the Information Center i i y i bz ,
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. l . 3 8 5 207 7 8 90 EP-317, Rev. 3 Paga 1 of 13 h l VAW/JLP:rgs l
l PHILADELPHIA ELECTRIC COMPANY L LIMERICK GENERATING STATION -J5 5 EMERGENCY PLAN IMPLEMENTING PROCEDURE i 4 l EP-317 DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS l j 1.0 PARTICIPANTS 1.1 Dose Assessment Team Leader or Shift Technical Advisor shall determine protective action recommendations from dose and/or ground deposition l projections. i' 1.2 Site Emercency Coordinator, if activated, or Emercency Director shall provide recommendations
! :o the Bureau of Radiation Protection or directly to the counties if the state cannot be contacted.
7 j 2.0 ACTIONS - IMMEDIATE 2.1 Dose Assessment Team Leader or Shift Technical Advisor shall: l 2.1.1 DETERMINE PLUME EXPOSURE PATHWAY PROTECTIVE ACTION RECOMMENDATIONS t l 2.1.1.1 Obtain the information from Appendix EP-316-3 } Summary Sheet or RMMS output. b Use Appendix EP-317-6 Protective Action - { { g Recommendations under good weather conditions or Appendix EP-317-7 Protective Action Recommendations under adverse weather conditions l l g to getermine recommendations when projected . o It'e doses are greater than 1 Rem whole body, 5 i A (9 ( e thyroid. [. pendix EP-317-1 Plume Exposure PathwEy } i , 5t ,[* Protective Action Recommendations, Appendix EP-4 fkg 317-2 Bureau of Radiation Protection Philosophy
- .,y for Protective Action Options, Appendix EP-317-3 Evacuation Time Estimates and Appendix EP-317-4 Whole Body Shielding Factors are provided as supporting information for the flow charts.
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] s 2.1.1.4 Discuss and suggest protective action recommendations with the Site i
Emergency l Coordinator, if activated, or the Emergency { Director.
. 2.1.2 FOR INGESTION EXPOSURE PATHWAY PROTECTIVE ACTION RECOMMENDATIONS:
ACCIDENTS NOT REQUIRING PROTECTION AGAINST DIRECT
.. EXPOSURE MAY STILL WARRANT CONCERN FOR THE INGESTION EXPOSURE PATHWAY THROUGH MILK.
9 2.1.2.1 Obtain EP-316 or RMMS Milk Ingestien Thyroid Dose 4 Projection. + 2.1.2;2 Compare Milk Ingestion Thyroid Dose. Projection Appendix EP-317-5 Ingestion Pathway Protective Action Recommendations. 5 2.1.2.3 Discuss and suggest protective action recommendations with the Site Emergency l Coordinator, if activated, or the Emergency j Director. 2.2 Site Emergency Coordinator, if activated, or k- . Emergency Director shall: i s. { , IF AN ALERT OR SITE EMERGENCY HAS BEEN DECLARED j WITHOUT PRIOR EMERGENCY CLASSIFICATION, INDICATE ? THAT NO PROTECTIVE ACTIONS ARE NECESSARY FOR b l IMMEDIATE NOTIFICATION IN EP-103 ALERT RESPONSE OR 3 EP-104 SITE EMERGENCY RESPONSE. F f IF A GENERAL EMERGENCY HAS BEEN DECLARED WITHOUT l PRIOR EMERGENCY CLASSIFICATION AND BRP OR PEMA ARE NOT AVAILABLE, PROVIDE THE RECOMMENDATION TO SHELTER WITHIN THE 2 MILE RADIUS AND 5 MILES DOWNWIND OF THE PLANT TO THE COUNTIES BY THE NOTIFICATION CALL LIST IN EP-105 GENERAL EMERGENCY j RESPONSE. F 2.2.1 USE APPENDIX EP-317-8 PROTECTIVE ACTION RECOMMENDATIONS BASED ON PLANT CONDITIONS FOR ADDITIONAL INPUTS IN DECISION MAKING. . j 2.2.2 If possible, hold a meeting with government i representatives to provide background information 1 for protective action recommendations. - 2.2.3_ Provide recommendations to the Pennsylvania Bureau a of Radiation Protection. 1 l j. 1 i' - _ . , , . . . . - - . ]
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l 3.0 ACTION - FOLLOW-UP . I t- 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. S. 3.1.2- Periodically update the Site Emergency Coordinator or Emergency Director. I i [ 4.0 APPENDICES 3; I 4.1 EP-317-1 Plume Exposure Pathway Protective Action Recommendations 4.2 EP-317-2 Bureau-of Radiation Protection Philosophy for Protective Action Options 4.3 EP-317-3 Evacuation Time Estimates
- 4.4 EP-317-4 Whole Body Shielding Factors l 4.5 EP-317-5 Ingestion Pathway Protective Action Recommendations I 4.6 EP-317-6 Protective Action Recommendation under I adverse weather conditions
- [ 4.7 EP-317-7 Protective Action Recommendations under jP l good weather conditions r
- 4.8 EP-317-8 Protective Action Recommendations Based
! on Plant conditions 1
5.0 SUPPORTING INFORMATION k [; 5.1 Purpose { The purpose of this procedure is to provide guidelines for determining protective action p recommendations to be given to the Bureau of ( Radiation Protection. 4 l 5.2 , Criteria For Use l 5.2.1 Dose projections from RMMS or from EP-316, Cumulative Population Dose Calculations for Airborne Releases are available.
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]. .
_l- VAW/JLP:rgs-
. 5.2.2 An Alert, Site Emergency or General Emergency has ; been declared with an actual or potential release
[ of radioactive gaseous material. i s 5.3 Special' Equipment x None
, 5.4 References l
1 5.4.1- Limerick Generating Station Emergency Plan Section
; 6.4.1.2.C s
{ 5.4.2 Limerick Generating Station Emergency Plan i Appendix H j
- 5.4.3 EP-316 Cumulative Population Dose Calculations j for Airborne Releases 5
l
- 5.~4.4 Pennsylvania Department of Environmental Resources
}' Bureau.of Radiation Protection for Nuclear Power Generation Stations Incidents, Section VIII h
1 5.4.5 U.S. Food and Drug Administration, " 21 CFR Part 1090 { h 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 Guides and Protective Actions for Nuclear j Incidents 5.4.8 EP-101 Classification of Emergencies h k .
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; , l EP-317, Rev. 3 Page 5 of 13 I VAW/JLP:rgs APPENDIX EP-317-1
-l p PLUME EXPOSURE PATHWAY PROTECTIVE ACTION RECOMMENDATIONS
! Projected Dose 5 .. '(REM) to the Recommended p Population Actions (a) Comments
~Whole. body <1' No planned protective Previously recommended
, actions.(b) protective actions 1
State may issue an may be reconsidered advisory to seek or terminated. l Thyroid <S shelter and await [ ' further instructions. i Monitor environmental L radiation levels. Whole body 1 to <5 Seek-shelter as a If constraints exist, I minimum. Consider special consideration i Thyroid 5 to <25 evacuation. Evacuate should be given for j unless constraints evacuation of children
; make it impractical. and pregnant women.(c) ? Monitor environmental ! , radiation levels.
j control access. l Whole body 5 and above Conduct mandatory Seeking shelter would l'
; evacuation. Monitor be an alternative if I environmental radiation evacuation were not l Thyroid 25 and above levels and adjust immediately possible, area for mandatory j evacuation based if on these levels. ! Control access.
i (a) These actions are recommended for planning purposes. Protective , action decisions at the time of the incident must take existing conditions into consideration. ) a j (b)-At the time of the-incident, officials may implement low-impact . 1 protective actions in keeping with the principle of maintaining radiation exposures as low as reasonably achievable. . J (c)'It is intended that family units remain intact during any l evacuation. ;
Reference:
EPA-520/1-75-001 h i
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9' - -l . EP-317, Rev. 3 Page 6 of 13
] VAW/JLP:rgs i
i APPENDIX EP-317-2 I BUREAU OF RADIATION PROTECTION PHILOSOPHY FOR PROTECTIVE ACTION OPTIONS A The most appropriate protective action for a particular j situation will depend on the magnitude of the release, duration
; of the release, wind speed, wind direction, time of day and
- transportation constraints. This discussion of options does not
; obligate the staff to select any one particular option.
Selection of an option is a judgment dependent upon the-situation. F 1.0 Evacuation This option will be considered when: l 1 J-
- a. A core melt accident is underway, which involves or is expected to involve a loss of containment integrity by melt through or by direct release to the atmosphere; or,
- b. Projected doses are expected to approach or exceed j 1 Rem whole body or 5 Rem to the infant thyroid;
,I or, !' c. Release-time is expected to be long (greater than 2 hours).
l d. Evacuation could.be well under way before plume , arrival, based on wind speed and travel conditions.
~
- e. Substantial dose savings can be made by. avoiding exposure to residual radioactivity (surface 1 deposition), and/or, p . f. Evacuation appears to be.the best option available.
2.0 Sheltering l l * 'l j This option implies that people in the potentially - , affected area shelter themselves in a building that can j L be made temporarily somewhat airtight. The structure-may ! i be one's home, a commercial building, or public building. l- In the general climate of the Commonwealth, any building which is reasonably winter worthy will suffice, with windows and doors tightly closed. The objective is isolation from potentially contaminated outside air. A
. l reasonably tight building is adequate for 2 hours ! protection from inhalation hazards.
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, -l EP-317, Rav. 3 Page 7 of 13
.l VAW/JLP:rgs
; This option will be considered when:
- a. Projected doses are expected to approach 1 Rem whole body or 5 Rem to the infant thyroid, but not exceed 5 Rem and 25 Rem respectively and
- b. The combination of warning time, plume arrival time j
. and release time is not long enough to effect i ! evacuation; or, i
- c. Evacuation cannot be effected so as to avoid a i significant fraction of. expected exposure; and/or, i
- d. Sheltering appears to be the best option available.
3.0 Thyroid Prophylaxis For virtually every significant accident at a nuclear power station, the release of radiciodines with the , associated risk of thyroid exposure will present the greatest demand for protective action. The usefulness of certain compounds containing stable iodines as agents to l block thyroidal uptake of radioiodines has been widely
- recognized for some time. Potassium iodide (KI) has been I approved by FDA for this application.
g 4 The Department of Health is responsible for development
- of the Commonwealth's policy on thyroid protective drugs.
4.0 Respiratory Protection Conventional methods of respiratory protection use half-face and full-face respirators and self-contained breathing apparatus. These methods are widely available for use by emergency workers. Their effectiveness depends not only on the type used, but also on the users understanding of correct fit and respirator limitations. This option obviously cannot be applied to the general public. k w~.-=m.. ., -
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l' EP-317,.R3v. 3 Pcga 8 of 13^ l VAW/JLP:rgs APPENDIX EP-317-3 [t -' l EVACUATIOli TIME ESTIMATES-(A) } e j l ANALYSIS AREA FAIR WEATHER ADVERSE WEATHER l 8, l 0-2 Mile Radius l N 2 hrs 55 mins 3 hrs 45 mins i S 2 hrs 50 mins 3 hrs 30 mins i i
! l 0-5 Mile Radius
.j-p NW 4 hrs 30 mins 6 hrs 10 mins i E 3 hrs 30 mins 4 hrs 45 mins j SW 2 hrs 50 mins 3 hrs 55 mins ] S 3 hrs 45 dns 5 hrs 10 mins i l l 0-10 Mile Radius NW 4 hrs 45 mins 6 hrs 30 mins E 4 hrs 50 mins 6 hrs 45 mins i. SW 3 hrs 4 hrs 5 mins - S 4 hrs 30 mins 6 hrs 15 mins (a) Most conservative estimate for evacuation times during fair and adverse-weather as reported in Table 6.1 from reference 5.4.2. L e P h' p G
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. l EP-317, Rsv.'3
. Paga 9 of 13 l VAW/JLP:rgs APPENDIX EP-317-4
].' WHOLE BODY SHIELDING FACTORS i Shielding l Structure of Location Factor (a) f, Outside 1.0 1 I Vehicles: 1.0 s e l . Wood-frame: house (b) 0.9 l (no basement) I g Basement of wood house 0.6 Masonry House (no basement) 0.6 Basement'of masonry houst 0.4 Large office or industrial 0.2 building' (a) The. ratio of the dose received inside the structure to the dose
-l that 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. I
Reference:
SAND 77-1725 (Unlimited Release)- e l 3 e
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-EP-317, Rsv. 3 Paga 10 of 13
- l VAW/JLPargs l APPENDIX.EP-317-5 4~
i l INGESTION PATHWAY PROTECTIVE ACTION RECOMMENDATIONS I l Preventive PAG Response Level Recommended Protective Action 1 .4 Area Deposition 1: 1. hemove,all lactating dairy l cows'and substitute i .045 uCi/m 2 uncontaminated stored feed j and water. y- or-1 [ [V Projected Thyroid Ingestion Dose: [ [ l 1.5 Rem i
-l Emergency PAG Response Level Recommended Protective Action t;
f _ -Area Deposition 2: 1. Isolate contaminated food I a products and prevent i
.45/6.2 uC1/m2 introduction into commerce.
Projected Thyroid 2. Determine whether Ingestion Dose: condemnation or other C disposition is appropriate
. 15 Rem after consideration of the !- food products in question.
E . [. ]e l 1. .As calculated by EP-316, Cumulative Population Dose. Calculations; Response levels vary from concentrations specified by FDA Guidance j- due.to different dose conversion methodologies. - t I l 2. Levels represent infant / adult response levels. l p I
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9 p - -- _ _ _ _ -- l' I EP-317, Rev. 2 Page 11 of 13 g I - VAW/JLPargs l
' l APPENDIX EP-317 '6 PROTECTIVE ACTION RECOMMENDATIONS " " ' " "
; UNDER ADVERSE WEATHER CONDITIONS I
; DCTIE %-
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EP-317, Rev. 2 Page 12 of 13
- 1 -
VAW/JLPargs l l 1 I l l I APPENDIX EP-317-17 PROTECTIVE ACTION RECOMMENDATIONS
' I !
l UNDER GOOD WEATHER CONDITIONS I 1 I ' i I DETW. CommOMBs '
'i' I I WHOLE BODY PROJECTED DO K > 1IEM OR TMOID PmMECTED DOSE > 5 NEM 800 I
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j- EP-317, Rev. 2 1 Page 13 of 13
) . . VAW/JLPargs i
{ APPENDIX EP-317-8 I PROTECTIVE ACTION RECOMMENDATIONS BASED ON PLANT CONDITIONS i lf( PROTECTIVE ACTION RECOMMEN0ATIONS NEE 0E0 j
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. r a N f S THERE y UBSTANTIAL COR ij YES OAMAGE IN PROGRESS OR NO
', PROJECTE0? (ACTUAL OR POTENTIA 3 FOR 18 4 R/HR. IN
- ! CONTAINMENT) 1
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, n 1 i S THER USE i IMMINENT SUGGESTED 3j CONTAINMENT YES RECOMMEN0ATIONS j FA UE .OF 00SE j N -
ASSESSMENT TEAM 7 LOR. OR S.T.A.
', RECO MENO SHELTER FOR !-~ NO AREASTHAT CAN'T
- ' BE EVACUATED '
9 BEFORE PLUME l
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? EVACUATE OTHEkS i IS 2-5 MILES l I ONTAINME : 3 RA0 MONITOR NO , j REATER THA ! 5 x 18' ;
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l YES ! ! & v l l [F POSSIBLE RECOMMENO ' [F POSSIBLE RECOMMENO EVACUATION OF 5 MILE EVACUATION OF 2 MILE RADIUS,18 MILES RADIUS, 5 MILES . ! 00WNWINO DOWNWIND v i ! 1P 4P I. .
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