ML20090G672
| ML20090G672 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 10/03/1983 |
| From: | IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | |
| Shared Package | |
| ML112410294 | List: |
| References | |
| PROC-831003-01, NUDOCS 8310270019 | |
| Download: ML20090G672 (60) | |
Text
{{#Wiki_filter:.w , TRANSMITTAL /ACKriOWLEDGEMENT MEMO Page 2 of 2 REMOVE INSERT MANUAL CONTENTS REY. DATE REV. DATE
-3.3b 3 5/23/83 4 8/2/83 4.2 0 5/11/81 1 7/14/83 4.3 1 . 10/19/81 2 5/27/83 6.3. 2 12/6/82 3 8/3/83 7.1 0 6/27/83 1 8/16/83
'4.5 0 5/13/82 1 3/15/83 l
t i I t l- __
.l
- 8310270019 831027 - - -
PDR ADOCK 05000331 F pg
--n' >
s. EMERGENCY PLAN ' IMPLEMENTING FROCEDURES
, . s.
REVISION CONTROL SHEET _ Revision No. 18-
' Revision Dat _10/3/E3,_ .
Pare /Proe' Date Rev. Pare /Proe Date Rev. Face / Proc Date Rev. INDEX 10/3/83 10 1.1 3-22-83" '3
-1.2 8-26 .83 4 1.3 .1-13-83 0 2.1 J8-8-83 3 .
2.2 7-14-83 5 2.3 -DELETED 2.4 '6-20-83 ' 0 2.5 7-1-83 0 2.6 7-25-83 0 6-' 2.7 25-83 0 3.1 8-1-83 3
-3.2 8-1-83 4 3.3a 6-6-83 4 3.3b 8-2 4
.4.1 DELETED 4.2 7-14-83 1 4.3 5-27-83 2 4.4 7-30-82 1 4.5 3-15-83 1 5.1 11-24-81 1 5.2- 11-24-81 1 1 6.1 'l-31-83 1 6.2 11-81 0 f 6.3 8-3-83 3 6.4 3-19-83 3
.7.1 8-16-83 1
'.M M k
p-o.. 9
' EMERGENCY PLAN IMPLEMENTING PROCEDURES ,,
INDEX . Dhcument~No. Title 1.1- Determination of the Emergency Action Level 1.2 Notification of the Emergency Response Organization and Offsite
~
Agencies. t vet n erat n of the Operational Support Center
- 2.2 _ Activation and Operation of the Technical Support Center 2.3 DELETED 2.4 - Activation and Operation _of the ORAA 2.5 . Control Room Emergency Response Operation
.r ~2.6 . Activation and Operation of the DAEC Off-Site Radiological _and Analytical Laboratory. (0RAL) 2.7 Activation and Operation of the DAEC Off-Site Decontamination Facility (ODEF) i 3.1 Onsite Radiological Monitoring 3.2 0ffsite' Radiological Monitoring-3.3a Manual Dose Projections 3.3b' Computerized Dose Projections 4.1 DELETED ~
4.2 First Aid, Decontamination and Medical Support 4.3 Rescue and Emergency Repair Work 4.4 , Protective Action Guides and Exposure Limits.
-4.5 Administration of Potassium Iodide (KI) 5.1 Deactivation of the Emergency Response Organization 5.2 Recovery and Re-entry 6.1 Maintenance of DAEC Emergency Preparedrass 6.2 Training and Drills 6.3 Maintenance of Emergency Facilities Equipment and Supplies 6.4 ' Emergency Preparedness Communications Testing
-7.1 Emergency Coordinator Duties
_ Rev. 10 10/3/83 L
O B EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 1.1 Page of SE - DETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 3 . 3 - (:., Date 3/22/83 k' ee*. , 1.0 PURPOSE , 1.1 ' This procedure provides guidelines for determining and revising an - Emergency Action Level (EAL) and provides aids to relate the ..: required emergency response to plant conditions. I 2.0 APPLICABILITY - 2.1 This procedure shall be used by the Operations Shift Supervisor ' -4*" 2 - and the Emergency Coordinator for emergencies at the OAEC as % defined herein for each EAL. Other events not included in these EALs may be classified as a NOTIFICATION OF UNUSUAL EVENT, ALERT, i .m
*- or SITE EMERGENCY at the discretion of the Emergency Coordinator or the Operations Shift Supervisor. -
/
3.0 RESPONSIBILITIES 3.1 Ooerations Shift Suoervisor 3.1.1 Evaluate plant conditions to determine if an EAL has been reached. 3.1'. 2 Initiate actions to return the plant to a safe and stable J I condition. 3.1.3 Initiate the notification requirements as prescribed in EPIP 1.2, " Notification" and initiate evacuation of tha plant for events classified as an ALERT or greater as l prescribed in EPIP 1.3, " Plant and Site Evacuation". - 3.1.4 Function as the Emergency Coordinator, until relieved. t 3.2 Emercency Coo'rdinator 3.2.1 Review the declared EAL and revise as required. 3.2.2 Ensure activation of the Emergency Response Organization, as required.
. -e ". .
e e ,
" t,,db.ik[*[b:D
$ 7:~EBM.: ~ '
a a
' EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 1.1. -
Page- of 52
^
OETERMINATION 0F THE EMERGENCY ACTION LEVEL Revision ~3 3 g
~
Date 3/22/83 1-
'4.0' INSTRUCTIONS 4.1-' Emergency conditions are classified in an ascending order of
. severity as follows:
4.1.1 NOTIFICATION OF UNUSUAL EVENT (Condition Classification A) This class of conditions includes the least severe events requiring offsite notification. This classification shall -
' be declared-whenever events are in progress or have occurred which indicate a potential degradation of the
-level of safety of the plant. In general, no releases of
- radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.
4.1.2 ALERT (Condition Classification B)- . The ALERT condition is the second emergency classification
-in increasing order of severity. This classification shall be declared whenever events _ are in progress or have
~
occurred which involve an actual or ootential substantial degradation of the level of safety of the plant. Limited releases 'of radioactivity may occur. - 4.1.3 SITE EMERGENCY (Condition Classification C) The SITE EMERGENCY condition is the third emergency classification in increasing order 'of severity. Immedi ate
-notification of the public is recommended. This classification snall oe celared wnenever events are-in progress or have occurred which involve actual or likely major failures of those plant functions required for protection of the public. Some significant releases of radioactivity are 'likely.
4.1.4 GENERAL EMERGENCY (Condition Classificat-ion D) The GENERAL EMERGENCY condition is the most severe emercency classification and recuires immediate
. notification of the oublic. inis classificar. ion shall be ceclared whenever events are in progress or have occurred which involve actual or imminent, substantial, core degradation or melting with potential for loss of containment integrity. Significant releases of radioactivity are 'likely.
* ~ ** "l9.\.] *
.a?..jy.mtgt: spy Y;
- 5_
- n .5 %. hem
.o n EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 1.1 Page . of 52 . . . .
DETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 3 Date ~ 3/22/83 4.2 When a suspected emergency condition occurs, the Operations Shift Supervisor shall make the initial ' analysis and determination of the EAL referrring to Attachment 1, " Emergency Action Level" and Attachment 2, " Emergency Action Level Classification Guidelines". The Emergency Coordinator, at his ' discretion, shall review the
-determination for concurrence or revision, either when notified of the condition, or upon arrival' at the site.-
NOTE The instrumentation listed under "Possible Indications" in Attachment 2 may serve as possible indicators of an C EAL; however, the indicated list should not be considered as' all inclusive. 4.2.1 Attachment 1 provides a listing' of the Emergency Action levels and is. formatted to show increasing degrees of severity. 4'.2.2 - Attachment 2, " Emergency Action level Classification Guidelines", is arranged in an index format according to the type of event, plant condition, possible indications and Emergency . Action Level codes. 4.2.3 To determine an EAL, the Operations Shif t Supervisor shall:
- a. Categorize the general type of event, referring to Attachment 1 for quick- reference, as appropriate.
- b. Using Attachment 2,- identify instrumentation or indicators used for interpretation of plant conditions.
- c. Identify the specific plant condition NOTE Contact with the Operations Supervisor or his designee should be accomplished if a question exists as to proper classification of'the plant condition.
- d. Declare the EAL.
4.2.4 Upon declaring the EAL, the Ocerations Shift Supervisor shall log the event, the time declared and the action (s) taken in the Shif t Supervisor's Log.
~
...w- ...
,- , ,. -n-- --. .,- - .,- - -4. - ---, .-- , , - , , , - - . . - , - , - - - - - ,
. er EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP' l1.
Page of 52
- 0ETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 73 Date 3/22/83
~
4.3 Natural or man-caused events shall be considered for determination of an Emergency Action Level
-4.3.1 The EAL Guidelines include specific type:: of events which may require declaration of or revision to .an EAL. Such events include:
- a. Weather conditions such as storms, tornadoes, high
~ '~
winds, blizzards, etc.
- b. Geological or seismic events such as earthquakes, tremors, etc.
- c. Non-radiological accidents, such as fires, airplane .
crashes, explosions, etc.
- d. Attacks or' assaults 4.3.2 Other events not included in these EALs may be classified as a NOTIFICATION OF UNUSUAL EVENT, ALERT or SITE EMERGENCY at the discretion of the Emergency Coordinator.
NOTE In addition, such events may also be of such a nature that a GENERAL EMERGENCY should be declared. However, since pre-determined actions to be taken by local officials include evacuation of personnel, a GENERAL EMERGENCY should not be declared without prior consultation with the Emergency Response and Recovery Director. ,
- a. The primary. consideration for classification of. these events shall be to protect the health and safety of site personnel and the-public.
- b. A brief description of the condition, its classification and any required activation of the Emergency Response Organization for such emergencies shall be noted in the Shif t Supervisor's Log.
4.4 Notification and activation of the Emergency Response Organization to the extent required for the declared EAL shall be accomplished as follows: 4.4.1 The Operations Shift Supervisor shall initiate the notifiction process as prescribed in EPIP 1.2,
" Notification".
h e mrm.m
n o- = EMERGENCY OLAN IMPLEMENTING PROCEDURE EPIP 1.1 Page of 52 DETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 3 Date 3/22/83 4.4.2 The Operations Shif t Supervisor shall initiate plant evacuation for all events classified as an ALERT or greater as prescribed in EPIP 1.3, " Plant and Site Evacuation". 4.5 Reclassification of the EAL shall be authorized by the Emergency Coordinator. The Emergency Response and Recovery Director should be consulted prior to upgrading an event to a GENERAL EMERGEf4CY and prior to downgrading an event to a lower classification. 4.5.1 Reclassification of the event to a higher or lower classification should be based upon the guidance provided in Attachments 1 and 2. 4.5.2 The Emergency Coordinator should consult with the following personnel during such evaluations:
- a. Site Radiation Protection Coordinator .
- b. Control Room Coordinator
- c. Technical Support Center'(TSC) Supervisor
- d. Emergency Response and Recovery Director 4.5.3 Reclassification of the event to a higher level should be considered if:
- a. The condition which precipitated the emergency is deteriorating or has a high potential of doing so.
- b. Unrelated malfunctions or conditions occur which potentially could jeopardize actions planned to restore the plant to a safe condition.
- c. Actions being taken to restore control of the plant do not appear to be effective,
- d. Readiological releases, if occurring, are becoming more severe, or have a high probability of beccming so.
- e. Deteriorating weather conditions or other man caused or natural events occur which may negatively impact the ability of local and state agencies to ensure the safety of the population in the vicinity of the plant.
O
..... _ a .
l
r s.
- O EMERGENCY PLAN IMPLEMENTING' PROCEDURE EPIP 1.1 Page of 52 DETERMINATION OF THE EMERGENCY ACTION LEVEL- Revision -3 Date 3/22/83 4.5.4 The Emergency Coordinator shall ensure that Off Site Agencies are notified of the event reclassification in accordance with EPIP 1.2. -(
NOTE If the EOF has been activated, this responsibility shall be assumed by the Emergency Response and Recovery Director. 4.5.5 Downgrading of an event classified as an ALERT or greater shall be authorized by the Emergency Response and Recovery
- Director,
- a. Downgrading of an event may be accomplished when the condition which constitutes the EAL has been brought under control and no longer poses a threat to the health and safety of plant personnel or the public,
- b. The emergency condition shall be considered under control-when:
- 1) The plant is in a stable state,
- 2) Necessary plant operating equipment is functioning properly, and
- 3) There is no potential for uncontrolled radiological releases.
- c. In considering downgrading of the EAL, the plant and radiological parameters defined in EPIP 5.1,
" Deactivation of the Emergency. Response Organization" should be considered.
4.5.6 Reclassification of an event shall be documented in the Shift Supervisor's Log and the TSC Log. The following information should be recorded:
- a. Date and time of reclassification
- b. New EAL designation c.: Brief summary of plant status and conditions for reclassification.
... w . w m :.a
- j * ~~ '
.. .-1..__.
o w EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 1.1 Page of 52 : DETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 3 Cat e 3/22/83
5.0 REFERENCES
- 1. Duane Arnold Energy Center Emergency Plan
- 2. NUREG 0654, Rev.1.
6.0 ATTACHMENTS
- 1. Errergency Action Levels
- 2. Emergency Action Level Classification Guidelines Approved by: , Date 8 of e
[8 4Wncy Planrrin ator f (
' Approved by: h 3. 9e t q Date 3-J'/ -8.3 ,
Operati g Super sor Q . Reviewed by: /
%(c'wx& Date 3-0W83 ALARA Coordinator g Reviewed by: Date hd 3 operation Committee Cnalrman Approved by: M Date Plant Sup intencent Nuclear ee O
e -e EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 1.1 8 Pags of 52 DETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 3. Date 3/22/83 ATTAOWENT 1 EMERGENCY ACTION LEVEL , PAGE 1 of 10 -
' CONDITION UNUSU AL SITE GENERM.
CLASSIFICATION EVENT (A) ALERT (B) EW RGENCY (C) EERGENCY (D) 1.ReactorCoolantSystem.{ l. Reactor Coolant System ' l.LOCA greater than. 1.LOCA, with failure of 1
.LOCA team rate greater than leak rate greater than makeup capacity. ECCS to perform, le adi ng .
either the unidentified 50 gom but within to core degradation or e (5 gom) or comeined Teen . makeup capa' city; RPV melt in minutes or Spec limits (25 gam), level being maintained, hours. Los s of - but less than 50 gom. containnent Integrity may be imminent
- 2. LOC A, containment ,
perfortrence is i
' unsuccessful af fecting l longer term success of the ECCS. Cou l d lead to core degradation or melt i n several hours wit' containment boundary.
- 2. Main steam line creak 2. Main Steam line break l Main Steam Line- with MSiv malf unction w i t hout i so la t ion.
j Break Outside j Primary causing leakage.
' Containment 1
i
. i, .!. 1
- , y
.. _. .s , ~..
.o __ b EMERGENCY PLAN IMPLEMENTING P."40 C E D U R E EPIP 1.1 -
9 Page .o f 32 ,. DETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 3 Date 3/22/83 ATTAOWENT 1 EMERGENCY ACTION LEVEL PAGE 2 of 10 l i' CONDITION UNUSUAL SITE - GENERAL
! CLAS$1FICAT10N EVENT (A)' ALERT (B) EMERGENCY (C) EE RGENCY (D) i '
i Environmental 2. Airborne effluents 3. Airborne effluents lRatcucs greater than Technical greater than 10 times
'(R; lated to Specification limits as ' Technical Specification
-10dFR20) reported by Health Instantaneous limits Physics. (an instantaneous rate i which, it continued l over 2 hours, would
+
1 result in about 1 mr at the Site Boundary under I average metsc ological j l conditions) as reported by Health Physics. f 3.Liculd Disenarge 4. Liquid Di scharge Etfluents greater than Etf luents greater tnan 10CFR20 Appendlx B 10 times 10CFR20 .{ limits as reported by Appendix B limits as I Health Physics. reported by Health Physics, l-r- iEnvironmental 3. Dose rates are projected 3.Dese rates greater than lRaicas s at the site boundary 1 Rem /br whole body or 5 (Raicted to EPA under adwrse i Rem /hr thyroid are FAGS) meteorology greater than proj ected (based on 50 mr/hr whole body or other plant parameters) 250 mr/hr thyroid for at the site boundary 1/2 hour. unoer actual POTE meteoroloalesi Ecuivalent to a release conoitions. rate of 1.4 CI/sec. fecn NOTE I the Of f Gas Stack er l Eculvalent to a release 9.5x10-5 CI/sec. frem rate of 530 Cl/Sec. fre
- l the of f Gas Stacx or the Reactor Sull eing
}
Ventilation Exhaust 1.85x10"I Ci/Sec. frem l the Reactor Sull ding
-j I System, ventilation Exhaust 3ystem. .}
I
.Y
4 e
~EMEKGENCY PLAN IMPLEMENTING PROCEDUME- EPIP- 1.1 10' Pago of 52 DETERMINATION OF THE EMERGENCY ACT ION LEVEL- Revision 3 - -
Date 3/22/83 ATTAQ4 MENT I EMERGENCY ACTION LEVEL PAGE 3 of 10 . CON 0lTION UNUSUAL SITE GENERAL CLASSIFICATION EVENT (A)- ALERT (B) EERGENCY (C) EERGENCY (D) R lea:es Drywel i Radiation or (Ralsted to EPA Monitor >2.0x104 R/nr These dose rates are PAGs) og coasured in the These dose rates are e nv i rons. o ruasured in the envfrons. ' NOTE og Averace meterological EPA PAGs are projected : condi tions were used to - to be exceeded outside calculate the aoove the site boundary. release rates. Values used:
- 4. Dose Rates are projected 1) Staoliity Class DE at the site boundary 2) Wind Speed 8 moh.
under adverse rnsteorology greater than 500 mr/hr whole body or 2500 nr/hr thyroid for 2 minutes. NOTE
.}
Eaulvaient to a release l e rate of 14 Ci/Sec. from the Of f Gas Stack or 9.5x10-4 Cl/Sec. from the Reactor Building Ventilat ion Exhaust System.
.E These dose rate are measured in the environs CL EPA PAGs are projected to be exceecea outside the site bcundary.
- .2 :
l L l
EMERGENCY PLAN IMPLEMENTING P?t0CEDURE" EPIP 1,1 11 Page ,of 52 , DETERMINATION OF,THE EMERGENCY ACTION LEVEL Revision 3 Date 3/22/83 ATTAOiMENT I ( EMERGENCY ACTION LEVEL PAGE 4 of 10 CONDITION- UNUSUAL SITE GENERAL
-CLASSIFICATION EVENT (A) ALERT (B) EE RGENCY (C) EERGENCY (D)
Environmental 4 other plant conditions Relcasts exist, from unatene (Ratated to EPA source, that make FAGe (Cont) release of large amounts of radioactivity in a short time period I - pos s ib le. I L .j0$ grad 3dFuel 4. Reactor coolant ac*ivity 5. Reactor coolant i l n ttgr i ty greater than Tecnnical activity greater than 300 uct/gm of dose-
~
Specification limits of 1.2 uct/ gm of dose equivalent 1-131 equivalent 1-131 which requires shutdown. 5.Alr Ejector monitor 6. Air Ejector monitor acitivity greater than activity greater than 500,000 ucl/sec or.an 5 cl/see corresponding increase of 100,000 to 16 Isotooes decayed uct/see within a 30 30 minutes. - minute time period.
- 5. Degraced core with -
possible loss of coolacle geonstry. e O
- e. e EMERGENCY PLAN IMPLEMENTING POOCEDURE EPIP 1.1 12 Pags of 52 DETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 3 Date 3/22/83 ATTAOiMtNT 1 EMERGENCY ACTION LEVEL PAG {5of10 CON 0lT10N UNUSUAL SITE GENERM.
_ CLASSIFICATION EVENT (A)- ALERT (B) EERGENCY (C) EERGENCY (0) Loss of 2 of-3 5. Loss of 2 of the Fissica Procuct following 3 fission 3:rricrs product barriers with e potential loss of 3rd barrier: a) RCS Integrity -see S-1 b) Clad Failure - see B-5 c) Containnent Integrity
- 1) see A-12 or
- 2) Orywell Pressee
>56p sig, or
- 3) Oryweli Temperatre
>281*F System /Eculpment 6. Stuck open saf ety or Failuro or relief valve.
Malfunctlon 7 Any ECCS actuation that results in water being I disenarged to the Reactor vessel that is eitner unexpected or is reouireo to recover and maintain RPV water l evel .
- 8. Loss of fire suppression function requiring shutdown by Technical Speci f ications.
- 7. Complete . t oss of any 6.Comolete loss of anv 6. Shutdown occurs cut f unct ion needed for f unc-lon needed for r eq ui s ite cecay heat plant cold shutdown. p la nt ' hot s hutcown. removal systems (e.g. ,
R HR) or non-safety systems heat removal means are rendered un a va i lab le. Core
.fi degradation or melt occurs In about ten hours with subsoQuen*
containnent failure,
^l. f
.. g
- - _ _ - - - - ___ ,e
'e ;,
t (} -/ t s + s
. A.
EMERGENCY FLAN IMPLEMENTING PROCEDURO' , EPIP 1.1
.is N 4
13 4 n Page .of 52 .... - 3 DETERMINATION OF THE EMERGENCI ACTION LEVEL Revision 3-t Date 3/22/83 k t i (. , s ATTA04 MENT 1
~
p,, '
'3 [
EMERGENCY ACTION LEVEL ; PAGE 6 of 10 ) , I CONDI7 ION . UNUSUAL SITE GENERAL. CLAS $1 F ICAT10N EVENT (A) ALERT (B) EERGENCY (C) EERGENCI(D)[ , .. T (Noto C) ! System /Eaulpment 9. Turbine rotating compon- 8. Turbine f ailure causing Failure or ont failure causing casing penetration. Malf unct ion rapid plant shutcown.
^
System /Ecul ement 10. Loss of HPCI and either Falluro or ADS or RCIC ,, Malfunctton , t Loss of ADS logic or ! s t loss of frors than 1 ADS - valve , ,,; Total Loss of any of (Loss of Safety the following S- - m or Core Spray T ~ s Fe..uro LPCI s reculring 'RHR SW , , shutdown ESW In tecorcance SBLC witn Tcennical Standby Gas Treatment Soscifications) ' Loss of Containment Spray capability Loss of both H2 and 02 I Anal yzers i t
. Loss of both Emergency '
Diesel Generators ' s s 1 s i 11.Any comoination of Safety System tallures > that recuire shutdown by Tecnnical SoecifIcations. '
- p. ,
E i
, , 4 N ' 1 4 I I
s N_.i [,,-
' -.'.a ' '
), j i
v.. .m j , f'. a
- EMERGENCY FLAN IMPLEMENTING Ff.0CE0unE EPIP 1.1
^-
[4 ,.M
i Pago 14 of 52 M;' OETERMINATION OF THE . EM ERGE NgY',"ACT 10N LEVEL Revision 3 - .
Date 3/22/83
', ATTAOWENT 1 i EMERGENCY AfTICN LEVEL L 1 /
r ~ PAGE 'T of 10 \[ i
"^
( , CONDtTION UNUSUAL , .j iTE GENERAL' CLASSIFICATION EVENT (A) ALERT (B) r' EMEr.GENCY ' (C) EERGENCY (D) f _ System /Eaul ement 32 doss of primary b. F Failure or contalnnent btegrity M ti f un c* ion as defined in Section 1 (Loss ofg; 1.0, definition 15 of , g Otrr.alnment the Tech. Specs. g a' Integrity)
.f
- 13. Loss'of dependary conta inment ,i ntsgrity as' detInh in Section ,
1.0, defi sition 16 of-the Tech. Specs. System / Equi pment 14. Loss of of f-site power 9. Total Loss of al' i AC 7.Tetal Loss of AC Power; Failure or Poser res+ oration not poss ible Mal f une+ ion - .
, within .15 minutes (Loss of Power)
- 15. Loss of on-site power !
- capabt li ty ~
10.To*al Loss of 125v DC S. Total loss of 125 v CC l Power; Power; restoration not possible eithin 15 I mi nutas System /EQu lpment 11.Fallure of 0.PS to 9. Transient Req uiring 7. Transient (e.g., loss of Failure or initiate and complete operation of shutdown of fsite power) plus Melf unction I a reactor shutdown, systems with f ailure to f ailure of recuisite - (F,PS failure) ; scram (continued power core shutdown systens generat ion, but no core - (e.g., scram or Standby damage Imnedlately Liquid Control Systen). evi de nt ) . I Cout a lead to core melt in several hours with containcent f ailure 5 likely. More severe
' I consequences if pumo
( trip does not f unct ion, t _ 16.Earthquane of 12.Earthauake greater i 10.Eartmouake greater tnan suf ficient magnitude to than OBE. CSE wi f a p la nt n ot i n
?ctural actuate the Seismic cota snutdown.
joccurrences Monitoring System. '
.i . s I w
'y
',t S 5
n-' ~ ' g, _
~ ' ~ ~
_ r ;. Y
.i ^ :,- ' , . I t
3 a g' I J v-r k[ L.t
.'s, g; .a,__.._ . __ _
.p - .*; ,g> *
*~
f , 7,.- s s ts EMERGENCY PLAN iM7"LEMENTING MOCE00RE (i EPl9 1.1 %" ' #gi 15
..- Page .of 52 ,. ;
4j p//,- . / s QN LEVEL Revision 3 DETERMINATION OF Tbt EMERGENCY t.;'J n. -[ c I;.\j.:f:<-.s? t
+
ACT}m (
~, Date 3/22/83 y a m,
f k'
.l' '
\, 4 l '
Jj ATTA04 MENT 1 , j
v f %- L'E EMERGENCY ACTION LEVEL 1 tc> *I\ .
PAGE 8 of to c/
.if,
- s. , ,
i CONDlil0N , UNUSUAL SITE GENERAL
' EVENT (A) ALERT (B) y EMEPGENCY (C) EE RGENCY 10)
CLAS$151CAfl0N
,./
~
I e t t Ne{ ural 17. Coder River level 13. Cedar River level 11,Oed r River level ocuqrences greater than 753'. greater than 157'. gr2ater:tnan 767' or loss of flood [fCorN 't Y' f <
- trotection for safety related structures with plint not in cold y s hutdow n, f
- 18. Cedar River flow less l le. Cedar River flow less 12. Cedar River flow less 4, ther. 200 CFS. than 50 CFS. + pan 13 CFS with plant not in cold shutdown.
/l / , [13. Winds greater than 100 moh' wi th p lant n ot i n I s' .) 4 'i < i h. .
cold snutdown.
't. * .r *
) y 1
- e, 19. Tornado on site 13. Tornado strikes 14. Tornado whlen damages
' f acility causing saf ety rel ated damage. structures and c:rnorcrtises the f unc-I tions of safety systems % l~
Otrar Hazards 20. Unusual aircraf t 16.Alrcraft crash ca 15.Aircraf t crash or Experienced activity over f acility missile impact unici missile impact which tr Pr@jected or crash on slte causes facility- damages safety related demoge. systems or structures with plant not in cold shutdown.-
- 21. Train deralinent onsite
. y'. ,
22.Neary or onsite 17. Explosion onsite whicn 16.Exples ion onsi te unich
< .> ' i < explc lon i causes f acility damage damages safety related
'I af fecting plant structures witn plant
'N. *
.) I operation, not in cold snutdown.
~
(; > 23.Orsite rpease of tdxic 18. Uncontrolled entry of l 17. Uncontrolled entry of or flammaele gases. f toxic cr' flammaele toxic or flammaele
)- i 'gsses into tne gases into critical i facility environs. plant areas where lacn
', of access to the area consti tutes a safety
()' I
, proolem. . Plant not in cold shutcown condition f .
a f i N , . .. . . _ . . ,.
& P EMERGENCY PLAN IMPLEMENTING COOCEDURE EPIP 1.1 16 Pags of 52 DETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 3 Date 3/22/83 ATTACbMENT 1 EMERGENCY ACTION LEVEL PAGE 9 of 10
- CONDITION UNUSUAL SITE GENERAL
, CLASSIFICATION EVENT (A) ALERT (8) EMERGENCY (C)' EERGENCY (0)
R;lcasD or. Loss 19.Any uncontrolled cf Control of Increase in direct R!dicactive radiation levels Matarlais within greater than 1000 the Plcnt times normal.
- 20. Fuel handling accident 18. Major damage to spent
- hat results in f uel f uel in the Reactor damage with the Bu i l di ng . (Secondary release of radio- Conta i nnent ).
activity to the Reactor Building. (Secondary Contain-nont) 19.Unconteelled decrease in Fuel Pool ester l level below fuel level. Events AffectIng 24. Indications or alarms- 21. Loss of all safety 20. Loss of all safety Op: rational on process or ef fluent related alarm and related alarm and Control- parameters not - annunciation capaDil- annunciation cacaellity functional in the Ity; restoration not coincident with plant Control Room whlen possible with 15 tra ns i ent, require plant shutdown mi nu tes.
~
25.SIgnificant loss of assessment or conmun icat lons capabi li ty. Other plant conditions l ! exist that warrant 26.0ther plant conditions 22.0ther plant conditions 21. activation of emergency exist that warrant exist that warrant centers and fronitoring increased awareness or precaut ionary teams or a require plant shutdown activation of TSC and precaut ionary
' under Technical placlog EOF and other notification to the Specifications or key emergency puelle near the site.
InW other than personnel on standby. nor,r. .ontrolled shu h un. j G
-,,--.m 4- ,r. -,,,-~y ,-#c,- ,.w-, -** * - - - - - - - - - - - - ~ ** -w-- - -
e- A EMERGENCY CLAN IMPLE: TENTING FROCE0unE EPIP l.1 17 Page of 52 .. . DETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 3 Date 3/22/83 ATTACHMENT 1 EMERGENCY ACTICN LEVEL 1 PAGE 10 of to CONDITION UNUSUAL $1TE GENERAL CLAS$lFICATION EVENT (A) ALERT (B) E!ERGENCY (C) EMERGENCY (D) Contral Room 23. Evacuation of the 22. Evacuation of the c eltanility- Control Room required Control Room required for any reason. for any reason.
*. Shutdown outside Shutdown outside Control Room Control Roam not initiated, implenented witnin 15 minutes.
Si tustians 27. Transportation of R eq ui ri ng contaminated Injured Off-Sita Individual to the AssIsta. ice ' hospital 28.Securth throat, 24 Confirmed on-going 23. imminent loss of S. Los s of physical attempted sabotage, or Security compromise. physical control of the control of the plant unauthorized forceable plant. entry.
- 29. Fire within the 25. Fire not extinguished 24 Fire compromising the Protected Area that fn 10 minutes in an funct lons of safety
, cannot t>e extinguished area that could af fact systems within 10 minutes by safety related the Fire Brigade enunpment l
l YW 7 N
- W' e t r-+ i*M-7 e 3 -? ? V y-wrWtq -r9 e wr%,M-@ 9 y' T- yp--$----" -w-+kme- - % N rW--
EPIP l.1 o I
, m ATIAQlMENT 2 -e "2 ID4Ef0EICY ACTION EEWL - m o PAE I of 35 CLA55 tFICAll0N GUIDILil(S y. "
_ o z 4
-e D Note: The lastruentetlen IIsted In - r-this column may serve es a possible .
o >
- UeUSUAL SliE masERAL EVENT TYli In41 cation, but they are not necessarily EVENT ABERT (s(ftdNCY EMilE BCV O -
Plasti C080lil0e6 sentIIcieed cause to detemine en E AL. 5 L(EA -e r Reactor Coolant Systoo leak rete Sun, Pump timers on IC2 B result tal in one or x - At " greater than either the asildentified more of the foIItalag alarms on IC04 E 65 gpal or cambinal Tech Spec Iletts "I)rywell floor Drala Sug hl Leak
- g Z y
(25 gpal, twt less than 30 gpe. "Drywell Equipment ftala Sump bl leak" m - and/.s o" o m One or more of the following starms on IC04
- z D
" Dry = ell floor Drain Samup hl hl levela "
*Dryuell Equipment frein Sump hl hl levet* o
- Dry = ell Equipment Drain Sump hl Temp" g "o c
**L
, - m Flos rate calculation f rue FIQ 3707 on ICl9 vs o m z
. time Is yeater than S gym r-1 m The flow rate calculat lon from F1Q 3MS on <
lCl9 vs time eMed to flee rate calculation ",_ from FlQ 3707 on ICl9 Is goater than 25 gpe. Ottar possible InJlcations Drywell Temperature increme as InJIcates on
- f IR 4365 A. II, & C on IC29 Dry. ell Cooler inaperature lacreae as I
i InJlcated on IR 3713 A & B en IC2S o R v m 4 < e - e - e 1 m be O =
% 3 ce N =*
N
- i
% Oe ' = =
\ m 0
s -- O
-s y G N
4 v sI e (.
,8
O e d ~ l e , LPIP 1.8 m AIIAOD8ENT 2 liqEscteCY AGION LEVEL . O E PAGE 2 of 35 CLA351FICAil0N CUI DillE S -4 2-m o n m x z
- n 2 4 ikate: The lastrumentetlon listed In .,' V this column may serve as a possible UI415UAL SITE GENERE o
ladication, but they are not necessarIly EVENT AkfRI EKHGEtCT (M RE NCV Z' 2 EVENT lyfT, PLANT COteli10P6 suf ficleed cause to determine en EAL. o- - m E I LE Alcant. l Reactor Coolant Systen leak rate V . Drywell Floor Drain Sump pumps anJ/or Drywell i greater than 50 gen Imt within Equipannt Erain Sump pumps run e=cessively and BI y [ @ m x makeup capaci ty s ifV level belnj Flow Rato Calculafloes on the orywoII Flour swintained m 4 Crain Sump and Drywell Equipsont Drain sump E d InJlcates total flow la encess of 50 gpm. m ~ n 2 O O _and - m RPV level belaj malsd alnul as Indicatasi on 2 2 LI-4SS9, 4560, 4368, and LR4559/4560 on ICOS. 0 2
< o o-
> m 4
Other Possible ladications n 0 ] Unemplained Containawat pressure lacrease es " , InJI6etal bya al '8vle=ry Cantoinannt tel/le Fruena s terd
- - m ICOS *<
bl Computer points 0103 and 6804 m r-c) tH 4 384 and 4385 on IC29 l r Unexp lained Containaset Air Tongerature . i lacrea.e as InJlcatal bys al TR 4383A,B and C on IC29 bl IR Sil3A ent 8 on IC25 " [ ," $ I 1 4 < - ' e = G 1 1 i* r m.
- u O -
N 3 @ H ~* , e
> n N be -
1 ab u
.O ' + .I g
,1 N s I
's of
o.
& e
- e
" mmomzoy r>g
- x5,mEmz4 zo oo"oC m m" U 1
-.e No ya0e 4 O* a om4mnE 2>U O om gIm mEmnomz0<- yj oZ F <mr
~
aeC en Os u . " LN s e O 8 +* e uNNN%mL a S V L t E e EE R E E Cl Wa E l N E ( G et f L l u N G T N C' 0l C OI i AT E E T D l A C YC SI 4O H. CF
. E l I e t
G 5 I
. R S H
. E A ll ML E C A t
A T 9 uN 51 E MD t + s ly n . r a iraL . e t 5 sy " e d e s A a0 b lpt lb esc En pV wCI t e "ewi d r aci iss n ee u0 of on r t a s e n n opt n e k e c s r I o r0 4 d i e u Y s s I d a n u c e ol ow5 e o4 i s n l d a l ea t s e e l c o or s s art b e , c s l
/ P er a e a9 2 u il e o l l d ia /rn5W l
eC b h t 9 nrv ey o t al 4 r a 2 oeh t v e . s u nI t t r C5 s n e ne p InIC2 e i st at nL 1 O3 n t e o o s a y t s ri C i m m tn miaa su e a nI t r S a lme o n h m o a PM l T 25 em n ,c t n e a a f t l C o 3 ool oe l l 4 um n t d n nl 8 1 T Nf r u lode l a t 6 n led s o o e
. an rmC C v y 8
o t s ea6 i l ( s lot al c 5 y ,A P e3 I n c a c tc s a d b i4 r. Dr 4 a yr yr rD l A
)
Pl O A sili n euIn LnA ra j3 8 a a a m m ). 1 l 87 E I E eid t a u t O 3 S T A A P Th th l s t s y s , la4 OSr rt iia 4 R R y t a5 si cl 5 6 e a f I P*"P ese s t C i I T
)
e S ae4 rl l r
- s l C p v c ab ab l
a C aclel la Inyb M I t y t t c a p a c 6r p - t o u e k il a 0 m 0 0 n C a h T t N r A e L P t a e r g A C L( T . ld f e Y u I n , i T t N n E A o E V CC ( I L _
' !v a{
= I *
- a I-Note: . The Instrumentat ion listed in this column may serve as a possible UtAJSUAL -SITE: CENERA m Indicat ion, tsut they are not necussarily EVENT ALERI EKRGEtCY ER HGENCY j ft Atti Q)HDITIONS sulficient cause' to determine an EAL. ;;j $
E Villi ifPL a m x z - l0CA, with tallure of ECCS to RPV level decreasing and less than + 47.5 as DI 2 O LOCA (Continued) purform. Less of containment Indicated on L14539 and 4540 on IC05 $ i r-Integrity projected, g a Z-RPV pressure descreasing and less than 450 psig ~ as indicated on PI 4563, 4564, 4565, Pit 4563, O and 4564 on IC05 g I m y m E-l " RPV level less than + 46.5" as Indicated on j ,
.j ~'
LI4565 and LR 4566 2 _and o" - o m Containment pressure projected to exceed 56 , psig as indicated on Q g j a) Cunputer Points B103 and 8804 , , Q O l- b) HI 4384 and 4385 on IC29 Q
- 33 or o m z
Drywell tempurature projected to exceed 281*F e 1 as indicated byg a) Dryuell pressure >10 psig for more than 30 g minutes wittout Containnient Spray r capabiiity. b) TR-4383 A, B and C on IC29 c) IR-5715 A, O and C on IC25 . i i o a m m a e a N ECCS Conditions -+ < a2 - e D ! ' (Suo next page for explanation) ,- *
%e o N N 3 -=
- N -
u . N be =* On be
,o 1.
Q un _ w 4 i 6 if 1
= >
EMERGENCY FLAN IMPLEMENTING PROCEDURE .EPIP 1.1 22 Pags of 32 OETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 3 Date 3/22/83 W at 9
.a.
aE. wg 3 Es 03 Bo W E E EE
*W u. a v.
E5 E E3 ! _Et_ gm
' : . . . I
,ld -
- .ft :g-E
,s- 1 s iss .
- 1 k h #I 0 E
-'r**
3.1.! 3E e 2 a s i j 2L 3 .
-gg
,.8!
2.. . oa 88ws-w e. 83 4.l I a ira 1-* W l*2* -{ 3.
- =t-* 4 Egg
-3 *8
- 8,'i.
o aqs*2I-:t*17o.3 2 -Og3*3. v 3 3 3 p 3.e B=o* - 3 s 5. g= = 3 2 . g i gR-8 =e 3 t [.33 3" d %: yfthp b*!;IO57 a 31. r < b 537 8 S: T t!
*RR
^70-
"A E o s3.5
-*st"rai!g*
~1 g l j. t -- -, 5gy g a*
s yi*as : 3EE3 set 251 -* 123g'T1u *C* s y' - 6 e -
=--=--2r= . . s $ bl Eag iff 3 :;; :
1rge 1 13 101 = * % *! p2 :t 2 2 , r$n 2 2122"=3 26 Eu;E =, 2i S d o . 22.- 52* 8 E g:cg:silig.???12;:sg:s
= 9ei 3
**d
%8-
."1 y
233 2;w a 1 g i > Td:
. 8 s
- I -)
k E $- d
- e., -
t
~
e, b d
a , mrmg mzo< ir>z gv m m e,zo- 32oomo S " mi o- .,~ U meee .o* U i f o om4 ax z - oz o Z I,aom o4 >r>U O tm<"r ne< I$ " Oa4e (etSu aa Y
. C MN '
H E - E G 2 N R D E GM E Y C N E E T G I SK H . E T 2 H B f l A L A T U N S E 9 U V N E U 6 0 g 0 y 3 3 l i5 4 F s s6 i r .
- n a p5 n d l h
)
. aL 6 1 a 4 o n R aT e
g 5 8 h 0 l esAs E 2 t 5" 5 M od g n le a p 4 I t e n b e i c n d e d e 6
. t n o n s e a e e r y 4 5 n . e a isd u t s n e c e c
oa m r + 0 a5 u c d i a e T x e x C h 6 in opt n e 4 x e rS p nI a t 5 S n d et r a as a n oi o 0 o h n s 4 CI c c e e e d a n mr 1 o f t o s , C ni r e e t s e e t B t n t E s I d n t S u s d ge 9 s0 le4 6 a ei t ( s a r t e d 9 d i m 2 5 f a i a de n2 e s n C5 2 s4 og9 r y r l e t c aC I t pi l. e5 d 4 n2 u sa b e nr v y e o e c e 0 1 t a nI C l 4 dna , n s sI
.t
.a d p a w o r
n '2 e* r F 3 5 e o eh t st j o 0 nEj o >o n o nNda n nd an g6 d_ a loa s ei C s rt o/ urf l t e r 1 o r C C o a n5 r o p0 . u o ol d n a yt s p 8 5 p e i4 s r c n e 7 9 a a t a u u rt dn 8 g9 aI o e8 e1 2 c l n mb a en s8 e u u C h i r ot 3 sst o in5 eP f d t n h mn ,c e ad 5 i. I u r n s4 r d r a o g u a c 5 sl n n e ru m nt u one s e in4 sd et P n a od t s a y ri y et r b p wt A A 8, a et r L e n0 d oC t e a s v eh n t t a o i t a i d i n xe lea6 t l l s ot i rp ca r epd c I i w rB l l L n c a c i e4 l i sl 5 5 e n d o ed r en u oe b r i u m i c i t d t 8 m el ei8 1 ut o s8 s t d i u b a sif n n u3 et et b 3 7 l d s a l u3 u e r a n a l u eid f h h nI u s ei p4 t ac wy u n p a4 e e s c4 a r4 or i a e t m m vt ei6 i oR T gA r n S T t l i ri aR R t l 1 ina s aC FoH l e n d D mcT T l e a c r p d 5 in4 n e) ) p sa ug i b r i n
) ) i b
e t g) ) wI y
)
a b c V d V P s n d t o a rr so i u M a t ni ab r s P nI P G t l o o s C p D a R R a a N V s l i S M , e e c h g n t a S a i k N m w a O r e I o k u l T f I r u g D e n N p br i O s C t e u n n a T e i c N m l A t n il a u mon an l t f et n s t c o c s ec s n u
, c intl
_ A u a a i _ C s M n
. O n
. L u t
) mk n E
l' Y T . d n e u a o e o S s do da in t t t y u. r a e 1 H i t n n nt e sicn ot a n 4 q-E A o iai u e o V C C M L O S C L. O ( L t %
r T mI O Zot a ,r $ _E rmEm 4
- zO 39aO 7 oC,m mg V ,*-
a i.se u O* nouD O m I Z O o' 4Im xmpO zoy t oH_o* Fm<mr- m,< ni o3 u s s . s 0,4e u]NNeo 5 V C f LC U 8 Li
, E I
1 E L V d N la E L l l G (3 ( U N 0 G Y N ". l C i 0 Cl EDC 2 Al A ,Il R C Y C S t t CI p F E X 1 5 T 4 R 1 5 E4 tA IB 9C A L A i l t N 5 ( J v NE e U o - t ae ly
. h n t p
i D, n l ig o r . r. o 5 5 l 8 i m aL . C, r 0 0 e h 8 t e e s A nno d e gt i e C C f 4 a t l b esE 0 9, R d a t I I S n4 m r t e i c n 3 d A 8 nf n n O sI s r o s e a e 8 t l lo B s oo o o C e n mo g n g s n e h t 4 s u d 7 n ei t S I i o fn n o c. a 4 I ipt n c 4 a ai n iso m r m r n l r01 ld i w oi 6i h m A r C e a o s l 4 d O o d e n n d n 6, e e s >I al 4 s n e n . n c' s E 4 5 truf tr e e n te l a m ei
,n e a ell n o t
e t s eo .i s n T at a l o t w s y-s
. s o s3 e e ra s wWi n J f a
i ae ra t e r al lo2 r t r r e c l I 8 r r r rl l o t p l vy d c t 0 t u s os i t 1 ty t u /w u /o a e lo44 ma i ruhl l nr oeh t s t e o e
. nCiC a d oI i et n a nt on n1 l u i t
tnb/ ot J a r o s e n er I r c a d s4 y 4 r d r n r n es p aJ e e e tad al o$r u of
*. rm eWt n
,e s i t
a c l rl ou n t e n x M noaa u e e amo r t t F c a o d a em a yt s s s oi4 d / s ee n t a u al ta d lb e a L 4 d n sn e e n ml aa s w , l os e1 V gM cT l h e e i ir e s r 4 t rt i lo0 n m1 a n ,c n eos o al l t 25 4 2 s n e 1 e c 3 u e nt o s 'M d I e4 n y a j p n s o f 4 nl l h n oaf e e l,t lei t 1 T N f o I m i S R na m e 4 ioh nt nf
- s. wgA l Rll eoP i trq u i n mw e i. ni gI R d g oS of i l E o n , L s ot l )l s aR t d t a le a s s ms P N 7 a c a c d
. ol miui e
ah s iL W l n d1 e. s al a r o I e I O l ci I l B a iB r m r g l e e 4 o n 8 e 'V lat o e P ur n P A sil e a n r m4 . s u . E l M eid l n u n lo et obi H n u a n i T o t I M afc .t o l A r t t e ,o n S S r. . Th th I s iof ut . i5 e el J a5 %toi A P n I M u t l t aC c o) l t a r t 5 Wi t p e a J tru n 2
. d 0 s, n 0 l
t l S u r l a m ap u 4 a i ia a a I RaM ab O a 1 pt mu rl s t I e rT M e e e la4 o l aS t T M te. o s n e n os . t o f. a n o t o S t al s 4r f l G r i l c a o th f e i N v i t 5 u M .e o h g h 5 f t t t a l O ik e I u ae 6 T 1e
- h. l e
@l . g r n r O t C ni s
T . u e n n N A L ni ncd ale I l P c m .
-. tionI t
a n e e t s 9 c a S t 5 a o e uC I nt lmiw
- i. e l a a e at t l E
P mk nd V a a e m e v e T . e t r en a T d i N E Sn e B n is atlt se V E i. i ut oC n (o aL O C 1
, W e
2 EMEfeGENCY PLAN IMPLEMENTING P"OCEDURE EPIP 1.1 25 Page ,of 52 ,. , DETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 3 , Date 3/22/93 s-w - 49
*g-W 5s aa
- 15 W 58 -
-5 e- 9-
"E
- 3 a
*w W
as-3 E*W I s. a
=
Ed < e IE E' {E
- t . . 2.
. . . 11 a >
; si 1*
- r
. tt.]- tg .
,3 s* r2
$43 s l -^J 1 2 B
.3* 2 i} o$% ! $5 ;
*=. e to .*m a- 2 y .* 2
- 1:
a= a 2 .A 32
, 2;;
= . 2s ;
i 22 308 3.- }23 ,i a
=~a A t-et
=.* to 0i ,1 2: 3 6- 7 0 *
- 1 o'
.4--
Fo ll 1 3 3
...e .t .o 4 :c ~. .- .oz 2 6 -. - .o a
- . *~ ,. . s :=. 3::. 2. ... .,. 2s
-22 2 c, a.-w 2se 2. .
j8:J 2: 2ja 1 2 3 3- ."0E wi t *II *
*1 I
-;s
.a * *
.s a
1;3 18: t 5 *
= l g. t l *a
. y *- 3 &2 j &I 7 }2% =- -
he g a* ~3: 8e as 2 s', at:,-
-i t 22,? 22.~*
. t
= }..!
i*s,3
=s*=*
El* e j
.-- g 7.j -
-z- -2 --s == 4' o.
33I
<* 22?} 31.
~ ~-
-0 it.s t1-o=- !
24 " 2,*1 t1 1* ~: . 3 0 t*; li s .5s:22: 3 =2 o3 .3 2 = 3' 235 = 21 g g s-E <1 as 1, <3
-= z.
22::2 o <3 O I: 1 f*i i8 - 3 %:
- I T ;3 s::
e . i* 9 *} .5 .1: a -2 2: 1-2
- !- EU 81-i i
g :$- : *1 3j is. I ; .:i
*3 =~u
- s 2 53 3:
5$* x-- <. 2
< 2. :
E ss i 5 2-
- .!r .t:ia 8--=
3 =..a 2. 2 s-r 3 .3 3 A
- 2I * *b
.Ti-e.b o4
-e ., , . , - . . . _ v, -, -%,-..------,-,,--,-e.,. - - . , - - - . _
l b > EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 1.l' Pags of 52 0ETERMINATION CF THE EMERGENCY ACTION LEVEL Revision 3 - .* ; i 2 Date 3/22/83 i l W e' ,
- s. =y .
Wg is ;
=
6W . -E. .2
.50 - =
= .
OE 9 , wg- '- 2 i
*E
*g
- =
og
.t W. -
a m - , a > 2 5
- Ed < 1, i.-
. 1
- EE ja <
4 2
. 2 3 1 . 7 . g t Il
-I.
s $ .t t. t I
- t. e.3 2 3
e a ti a
- y a.
. s W.e o v _y aa u
, _3 _
sa . 21._. . _8 . . < _s-e 2 1 _o .. . g E a 1 o o . ta=
... _, 3 E
--< t. * .
. --< g g
2*3% .42 3 ' n !- u2 SI 3
.' E- -
o
- 1=*
to 1 6 35 g. -; ,' 3: . g$$* e5 - 2: 2*, ? e1 2= 2*a T- = je* 3;; 3 i ( 3 -2 4 S w
-*3
. *
- 2:
3 g 6 1 2j ****v
. ! ; 2. .. ==
e.- =
;t23 _. - . - 2. . =. -. s -g a
.a=
"a t-
- 13 a,
2 12 2.s -e' a . 4' *s k 13 aw TE}~*"I*
-I z- - - as 6 u -
t _o3 _,. w
.. .J*232- we 7 ..*J.2B2 . 2 3
- .y; oe - .. -
ao s3 , ygi
> v= = i.
o a _ E g. . 1. o
. .Gm z= 36 = 2. F
. g m. le : og*ea3*l? a o i S ;: ( 327-eg -
g-g,,,g,- t1 ;
=
g j ... J- { z .i
<. . ,- : _ .~~~~ .
_._.,n ,_o :. o 3 _, o
. .. s * = = -.
.e -e ~u -- ,
3
- e esy g g _e _q w , : : 1-**2* 3 o !
j 23 ; ; a z <2 s s s x . X 8 t t2 2 :
.7 2 1 !
J *1 h 5-1 < e w
*: So
=~
3 3* EE -
- :8
-- 5, :.
= 7 w. = s
.L ee -* %
Et 2o
?.
e.g 4 7o i 3 g g~ =_ 6 i
-5 og g*; o- W 2 a
w- ' Se ==- 1e e gg 12-
- s. s-a . I
'J
- ; i t c 2 7 I 2; i537 O 33 3
?! 2 23 .
5 3: 2
-=.
- gj
- ~~
" 8'
.f.
i 9 6 IPIP l.1 g ATIAQsNENT 2 EMEIGEeCV ACTION LEVEL PMi 10 of 35 CL A551FIC All0N CUI DIL i pE S m o I m m A D m- G1 Note: The Instruesnietlon listed in D m
!' this column may serve as a possible UtslSUAL SITE GENERA 3,, . [
Z d ladication, but they are not necessarily IDENT ALERT O(HM NCY EstHENCY EVENT TYfT PLANT CDeclil0N5 suf ficient cause to detennlne en E AL. 'H v o > 2 # Environmental Dose rates are projected at the site Calculatus release rate of l.4 Cl/sec tran ita- C3 Releases boundary under adverse sisteurology off Gas Stack or 9.Sulo-S Cl/sec from the o - 7: E IHelates to greater them 50 mr/hr. whole body or Reactor Dulldinj Vent llat ton Enhaast i EPA PAGsl DO or/hr thyroid for l/2 hour. NOlE y ", the followleg assungstions were used m I or II Stablilty Class AB for release from the Of f m 2 Cas Stach; stahllity : lass fG tor. release [ [ 2 Z Ihese dose rates are seasured la the from the Reactor Building O O , environs. 23 Wind Speal of 0.S mph m I SI Release from only one location or the other [ ]
-< 0 or 4 8 Of f-Gas Sta;k flowrate of 4000 cf m; Reactor Building Ventilat lon Exhaust flas rate et > m U
(PA PAGs are projected to t,e 810.000 cle. O
- 3 exceeJed outside the site boundary. 58 Stan1by Gas Treatsunt System in clarat lon g
+ durinj release trun the O f f-Gas S tack z j e) Tlee since shutdown = l hour , y m 2mIO 4 R/t.r on the Dryw71 Radat ton nani tor on l m ' I 3009 E ' Proj eciel dose rates of 50 mr/hr dele body or 250 as /hr thyroid as instermined ty i Implementat ion of EPIP 3.3, ' Dose Project iosa" L These dose rate are measured at the SIto o N V m t.oundary f ollowing leiplesuntat Ion et EPIP 3.l. 8 e e ] 4
*0ie-Site Radiological Moni toring" e - e V en 1
W N ] Alrtorne E t tluent fletease lastrumuntation y EN4AN of fle ent annl forleg system N
+ pa ."
Stamsby Gas treatawat Syst se flow rate last, s u Rn endg. Ventilat son E hause flus rate Inst. , O
-s 1 *
% un i w a
I '. 4
9 EPIP 1.1 i ATTA0#eENT 2 - EMElGENCY AGION LEWI, PAE lt of 35 CL AS$1F IC All0N GUIDIL i st s m O E m m
-4 . 2 i m o Note: The instrusentat lon listed in , y m.
this column may serve es a poss'4 6e UtafSUAL SiiE GENE R4, - O Indication, but they are not accessarily EVENT ALERI E9ER0E fCY E M ME NCW f EVENT TYli PLANT CopolTION's sulticient cause to determine en EAL, j D o > E nv ir oswent al Dose Rates are projectoi et the site Calculatal release rate of 14 C1/sec from the C4 boundary under adverse seteorology - Off Gas Stack or 9 Sal 0*4 C1/see from the O Heleases j lHelatent to greater than 500 mr/hr whole body or Heector Dullding Ventilation Euhaast D r-
-4 EPA PAGs) 2500 ar/hr thyroid for 2 minutes. N01E I m ICoatinued) The following assumptions were used: "
M w Il Stablilty Class A8 for release from the of e m z Gas Stack; stabillty class f G for release m - n,.s. dme ,et.s are -asured in it.. ero. et.e R.ecur ooiiding g g
- en. f r u..s . 2i Nind si. o. 0.5 m,h =
- 3) Release troe only one locat lon or the of tmer o a w 4) Of f-Gas Stack flowrate ot 4000 cfm; Reactos $
M Bellding ventilation Exhaust $1ow rate of 3* o O EPA PAGs are proJocted to be $ l0,000 cie. -q c
.=ceeded outside the site boundary. 5) Standby Gas Treatment System In opera t Ion 5 $
during releese free the of f-Gea Stech Z
- 6) flee since shutdose - I hour e--
m CC < Projected dose rates of 500 ar/Is etele body m r-or 2500 er/hr thyrold as delesmines by implementat ion of EPIP 5.5, " Dose Project ions- . These dose rates are suasured et the site *
- boundary f ollo=Ing Implementat ion of EPlP 3.1,
%51te HaJtological Moni toring" o a 7 j
1 Airborne E f fluent Release tastremntatloa to e ce ' m1
-e < u2 -
kMEN elljuont auni forismj syste a * *' ' } { see..dby Gas treat-at system slow rate inst. n sidg. v.nt n.iion E h.ust e soe rei. inst. s := c. u . N e N be == co be O 9,
- u.
! N e
l i a e9
9. e l EPIP 1.1 s AIIAO#ENT 2 D4EEEDCY ACfl0N LEWL . PAGE 42 of 35 CLASSif lC All0N GulDE IIES ( .. 6 m i o E i
, m m
.4 m m O Nut es The Instrumentation listed la 3 m this colume may serve as e posskate UN15UAL SiiE ENERA 3 z
h' 4 indicallon, but they are not necessarily EVENT AtERI EN RM NCY [ K RE NCV PLANT COtDITIONS suf ficient cause to def esalne an E AL. -1 D EVENT TYfT -. r-o > z z E nv ircensent al Dose rates greater then i Ree/hr Calculatal release rate of 550 Cl/sec from the 03 Heleases whole body or 5 Res/hr thyroid are dif Gas Stack or 8.8ml0*I Cl/sec from the O - m I projectal (based on other plant Heactor Building Vent flation Eshaust lHelaten$ to i (PA PAGsl parasuterst at the site boundary g y " m under actual meteoroloalcal the f olloutro assumptions were used m E ICont leiued ) conditions. Il Stability Class EE m' z ' l 2) Wind Speal of 8 mph M 2 j or ll Release from only one locat Ion or the saber y Z j 4 3 Of f-Gas Stack flowrote of 4000 cfm; Heactor m These dose rates are measured In Building Ventilat ton Enhaust floe rate of $ d 0 I t he envircem. 110,000 cle.
- 59 Standby Cas Treatsant System la operet Ion > m dura rg release from the Of f-Gas Stack O E 69 Time since shutdown - I hour g Z
M l Projected dose rates of 8 R/hr whole body or e g- ] M i
- 3 R/hr thyrold as determinal by implesuntat lon of EPIP 3.3, " Dose Project lans a m
. -o_r Ihose dose rates are suasured at the site boundary following implementation of EPIP 3.0, "On-$1to Radiological Mont haring
- i Alrtiorne E f fluent Helease lastrumentation i k 8etLN et f luent aun$ tor t ra) sy s t ue . O 33 mm Standt,y Cas treatsunt System flow rate Inst. $$$2
# ~ # 1 Rm Bldg. Vent ilation Enheest flow rate last. en Other plant conditions entst, from Emergency Cuordinator judgment 04 s" O
whatever source, that make releess . of large annunts of redisectivity N 04 -- om in a short time perlod possible. u o 9, y U a M
.. - . ~ . . . . -
6 9 LPIP l.l AftA0ueENT 2 DeEICE8CT A 10sI LEVEL PAE 83 of 35 , (I A550F ICAil0N GUlta lee S O E m m
-4 D m O
- o m E Z Note: The lastruamatetloa listed in .~
this column may serve as a possible 'Z -c UP415UAL $1TE GENfRA EVENT IVIE Indicat ion, but they are not necessar ily (VLNi ALERI (9CHMNCY E94RM NCY y
' PLANT C0041tT1096 - r-sulliclent cause to detenmine an ( AL. 'O Z- Z DegraJed f uel Reactor coolant activity greater Reactor Coolant cheelstry sample results as A4 o -
lat ogr l ty than Tecimical Specificat ton m E reparted by the Radat Ion IYotect ton lletts of 8.2 ucl/ge of dose Departoont based ugen anal yses conductel in N equivalent I-135 edilch relutres j " accorosace with appliceele cps. stetJo=n. m m Z 0,ther Possible Indications 1 -4 m g lacreas ieg Reactor Coolant cosafect ivi ty as O O Indicated on Re; order 2758, 2757 1C04 lacreasieg radiation levels as indica tel on: Z i al MSL Radlet lon Ibni brs l<C 4448A,B,C&D on l O ICM and RR 4449 on 8002 5 O O
. bl Of f Gas fietreatment Radat lun Mont br . j 4 304 on ICIO C,
.o m c) M% HI Red alarm on ICOS
- r*
Air Ejector monitor activity ladicated air ejector activity rete a 1 m 103 m AS < greater than 500,000 ucl/sec or en sa/hr as ladicates on of fgas Pre-treatment kal m lacrease of 100,000 ocl/sec within r-Munt for 4 04 on ICIO. a 30 mirute tlos period, or Indicated air ejector activity rate lacrease el 200 eH/hr wi thin 30 mieute. as isstica tel on ( Of taps We-treatment HaJ pbel tur 4104 on ICIO
- Dther possible ladiceflons O #
lacreasing raJiation levels as indicatel on: e e m' *U 4, O al MM Radiat ion ebel sors $4C 4446A,0,Cau on en
]
IC3t> ashi RR 4446 on 8002 ~ bl 08 0945 Post-treatan.nt Had #bal turs u o 08 3 0 4801 Aall on ICIO ] , ta
- c) Oil Gs 5 tack Rad Nel curs RI 4 816A & B ~
on ICIO m d) M'.L Hb had alarm on 100% O 5 q \n pa e' I .I , a
*t
1 e I mMmnOmzO "r > Z _E r*
- m 4]O
- y Oma$m -D' _e' u"
e*e s
>- ,N s f o
om4mnE
- 3> oz gM e[ E" OmzO
- >oj oz E<$ #e*~e n o3 u m
[ *" e u]~scW S V E l L CN J .
- L i R K E
WLM NM E l E t . L lu G f E N G O 1 I N 0 . G0 A 10 E 1( i 8 S A t R C T C S (l CIF B E E t C5S f I R E A I 5 6 e L B 8 8 DC A t A T 0 N 5 E ' 9 1E 4 a l= Ut V s ily n a n n t R s o o r , s n n o r 4 n 0 aL e s A s a i s a o&0,D fo 01 nt e J o&D 4 A d t e e C, d 4 t l t s E e e t e y0 u e 1 tm s 6 S a c il c n l t t 0 t 8, b > ae t 0, r 1 s e e e c i8 a I aA k
> 8 N
ld s n s n u v cA n er s 4 a a opt n e e o4 s i ni8 n t od 4 o t t n ie o d i n e l l rl o e de en m n oi e c t o e c . io c t u7 d 3 In4 4 t t a e - r e r i t a l a 4 4 M HI s s s 9 e0 lp s s s a n 7 sC sC r - 0 o2 aH 2.d yP f t s e e c a m o eP c S t aR b r 1 is a a r t id y h l e e d a s GY ysCe id c O a
, s r$ CS R O
C iv esg a s sO 2 R t n S it / n R o vy n I i i l l r C t n r e o loeh st t t y n lals r lo na o I t 6 lebn n3 7 a l 2 v t n n o t cr aO l e oI n e e v l letn ot n ea M o O C I r gg e s r f e yt s e l s t e e nl c le o ib or lel o u na 1 1 t s m r n . ib o nM8 eO R d e ma r t l s 2 i f o 5 t a u u n mb a ud ui p l s C hnM4 o 4 e a r a o oO s t ct I s o i n4 t C 4 r l k a l d
> no .
s r r i n4 r O e eIC po l l 2 3 e h a a p m n ,C cH a o oot o c al R teC I a t o4 - c a a a n M o eac no re idal H t nI j t l 1 i t u m n t d P t d C la H sooS t r u i o no t e eh d t d N e t n h st r c aR eifd eH Y ( I a a i t a 1 ML e s lot a c a l c tet al= e e R nr d n al d nH iri h aid P rJ n G s O H l C
- aR a sa o a
P 0 h d 4 t id I t l l sil ci o y ot >t t e t O g o gR a G i H a In04 O gH 1 a a aA s&6Cal iH feu e a n t PlA E E eid t C n c indel e 4 d e s n 6 L 1 fq1 I
- r e l A A P h h n u T t I s r e ot t d en m e mta mS e M3LC3O4ff M00 LS t a
a r o I s S C f aMI O4 O oM d 0 t 1 l L d nS e l l l em e a e a t c r r r o ic er t c rt ) ) r . a poa p co s r l ) i h rl l w t e cd c a b c d / in c a b c* d g e w y n r o t e e e ; a n a Inao n D D C o R rD a l I l e M i t N ^ g n . fo i s r d e s e n t u t o u p n a y s e t aim e r g i r l v r 0 ib S 0 N y t e i s ic co3 d t s a ac eey c 1 tw do p il t r s a h .y e cf o/c e t a o 9 t in lcd t r 0 lute C t m3 n g8 oS s e m n pe T - s N la/ I r o A o tc i a o coeg L out n roh t t t o P c c s d e 0 e e rI el r0 l je d b o3 a t c ni v E t 6 a1 a r go ta a a u e h q lr r e o e o H t e A gt D c l e E u d) P F e T V d t y aw el l i d r t N a g n L V r g t C o o E e a S D l t 3 'a 1*
4 e
'EMECGENCY FLAN IM7tEMENTING P30CEDURE EPIP 1.1 Page of 52 DETERMINATION OF'THE EMERGENCY ACTION LEVEL Revision 3 . . .
Date 3/22/83 w Y9 a-
*g 19 =
e _ sr-
- 3 -
_3 g ,* gj. .---
~v v- = =.
15 .a la ! l
- . l
.- ge_
3 a 2 :1 .
;;3* i=.
is-
-34 3 j js
- g
- g :g j8-ae
- g :[:a 8.: i .: 8 -
2a 3- . 21 ! .3 3 s . i :. . -s
- .a s
.=:3
-8
;a- 2 i..:!
- =u-2_
.:s 2 1;
. t o :a :
2
.w: i
=
=
2nse ww e . s -!!;s 8 r.:
-,8 := . _< m g._* : g *8
., q -v 4=3-
!,2 . .
- F f 1 8 ;;; ' . .
8.*: sa} s 11j45 3gec:w:22-
- - , 4 33. : .y.o . .-1 82 '
2*jg 2 3 :j:.a on s-
--3: : 2._ ;.. ; :-:
i t
,r3-1 .
2 3.
-:, 7. 2 -
- tr> ..= .a.4-sa:-
-- :. _g 11 .r:,:2s --
te g 32
- - -_2 8: - .
3 =. . - - e se is- 4:-a - - - .
-gW 222-
. 3 ;- .53-:-
;<rl ri : s o ,i f e_
sa!g t-
<3 aze.gyeyes.g 3.33g1-s--
---- ,s_ -
- : 4
!, 015$$e
..o 2:s3[s
- 3. ,18 : *5-i'i5
-3.3.:$
- _ - 8 253=E.!jE83:
. 1
-02G *3 , * %
I 35hess!'il j-in
.2-e
.5-
- yjj -
I
-in *
- 2 3. ,h,1 3
- 1 g- .
12 8 8 Y ,81 EL
, a-aa- ,
b- - M
<- 3 E. .$ e s
I ** $.4 3 Ik.% 11 r : :: :: E 3~ t: l l i
- e. b
o EMERGENCY PLAN IMPLEMENTING P 0CEDURE EPIP 1.1 33 Page .o f $2 .. . DETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 3 Date 3/22/83
=
w
.t5 a
a wg WI
- sWw 3 *3 . -
= y 02
*u *I a
W .u v 55 - 18 1
* $5
= 2-2 . . .
g a
~ . $ .
- a 8 )s g a
. 3 - 3
'v: D e a r . .
215.1 i. 8 i I 8 i
- ! I.! i 5 l iI*f 5
} ::; 'id E
- .I
=
I I Ii i 3 3 3 s .t :i j 355: - ru-j;
-g 3
=.-la3 '. :38] *..* [ =3 31 3-M8 .s i ti 8 ao 2--
== mIj! is.8 18.8 3$ 33,2 330, -
[ :2 3.885- ~~
- g31 2 : .
=.
.: I f s
a3.3:;
. pus 2r731
. e. s s .sm J 4y 3 31- 2*1,g$u
-> : t R
3 l'.8g
*:s
- !S.* :jg....-~
t s s t 3
.r*7 w3<- 2: 11
- 5
- m .3:;u.m- -a r:jfS8 sv. :: ::
22:22o,a.
~ -v.5:s
--;- .2 . - >~
a r ez. . o,
. . .= o u,s. u -
g- q.w 2 gg _ - 2
. ag.og x- s . .
y. o I
. V 6
- E6 j i s i' g inizi si ss l j..-:t j.2**r:
e I gsSs = ( t t ? ; ,. .2 , ->32 l
$. o11a r- g 1 , 2
<s.s
*O 5 st.u-i sit
; : ==3 2322-s b e?
EMERGENCY FLAN lt@LEKENTING FCOCEDURE EPIP 1.1 Pego of 52 DETERMINATION OF THE EMERGENCY ACTION LEVEL Revislon 3 .- - - J Date 3/22/83
- w. . <w .
a1 wg v "l - 5*- 33 9 m .= , s -. wu
- v. _
E-v- a -
=
=
. Ee. !
2 l13;
,il aw
,s-
.e s 5:g I
_ 5:i l
.v: . . . 2- .
2 .-: 3. _:
- g 15 :. .:
-s a .
s a g .a 13 . . rm 8 > 2:
=.
4
. 4 3,
. .: ta =;i -
g
- 3. g ;2 y 8
< 1!!2 " t ', g - 1 isi si g isi E !x:! sig
. :2 :. 33 .: m 4 3 *
- i. .
3*. ::
"a =: ; 3*-
Eo R
*!.=
3*ji .: 23 (J - 2 j7%. IIB fi-3: g - E
- to- 33 ' 2 2*j 23E Sag ess 2;: lT: :~ ,.
a i e 3.
.s . 1:
*7 s-2.
=. =1 t'
- 2 13 h*
- -~ as t *t
$2 *T } $' 5'7$ 5';h5E E2
} o
. . 2 2 3 1 5 c- : - y sj g g 3 . 1,: 1:g g- -- 1,. ip3:
- 2 e
io .-
>4 ij . oi 3
3 33 .J of *-
- .* * ,. ** 1' ,
E aij ji* -gj 12 }. l r -- - sa s t
*F .2 .: :
- ;3- 33 :P !!
l .1- *
- 3% 2:
- 8. .r ,1 3 3 33
-u t
1 ii
- -3 3
~
- 5 E2}}:*
- .__.J l
t w nb S
, .y , . . ,-- - - + , - , , , - , . _ , , - , - - , - - , , , , - . , , , -ee.r,-.
--, ,,, e- - - . , , , - - - , , ,
O b m EPIP 1.8 ATTA01MLNI 2 EMC10ENCY ACIION LEVEL o PA1 le of 35 CLASilf lC A110N GUI DIL IE S m m m o M m x z
- O Z 4 Notes The Instrusuntation listed la >
this Column may serve as a possible Ut415UAl SITE ENERE r"- ludicat lon, but t hey are not necessarily EVENI AlLR1 (K RENCY (M RGidCV O EVENT TVM PLANT COfOlTIONS sulliclent Caesse to def ensine an E AL. o - m E Sys tess/ Shutdown occurs but requisite decay Group I isolat ion wi th tot al loss of feet D6 g ," ' E q uipamen t hea t removal system to.g., RitO or syseen I m t allus e or non-safety systens heat remaval means ]
, tall .t ton .re ,en u s.1 e.a.aii .le. C.,r e and /or kz IContlauml) degradation or sett occur la about lot. loss of Ren5. s t.m ;
and /ur m - ten hours with subsoluent contalnawnt total loss of E5W systese o h f ailur e. . anJ /or fotal loss of RWS system "z D O 2 and /or -c O o Any combinallon of the daove systems that m g prevent decay heat resnovel. -1 C ' - n o m SYs t es/ toss of flPCI arul either ADS or RCIC f ailure to satisf actorily couplete All 2 E q wipemen t survell lance test lag in a.cordance ulth the - 8" f a il ur e or toss of ADS logic or loss of more appelcable $1P E MaaIwastlen t enen 9 AOS velve ' - (s4 .A r-lloss of Visual elserVetion setery Total loss of any of the following syst s or Cos e Spray other Possible Indications f.a s ur es LPCI SDLC - Loss of Squib Walve cont inut ty as
, r egel s is=3 RedMW tralicatel bys shutdown in (5W al loss of Indicating IItes on l@5 accordente 50tC b) " Conf irsul ty loss to $quib Valve
- alarm OM 'O M I
wi t h le(.finl* Stathlby Ces Treatment on SCOS. e e m D 4 < n = tai Specti8- * *
- tations) tems of Containannt sprey capability
[ ] 5BGIS- Charcoal bed toepura tur e > 2SS', with p manual str ay inillatent or, it not , 3310' on N :s un Labs of both 112 and 02 Analyzers BC24 ,
" ~~
Dies el Generators "plemel Generator Troubt." N * " on - ! Lces of both Emergericy Diesel alarms on ICOS. Diesel Genera ter Auto.-$ tart u . Genera tors i f ailur e alarms on ICots. Boeml alasms at i k Diesel Genera tors ICVS and 1C94 u u e e c h s9 4
's
s n EMERGENCY PLAN IMPLEMENTING FROCEDURE EPIP 1.1-Page of 52 DETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 3 4 . Date 3/22/83 y . Q, a-
~g W 15
- . 3t-
- g .3 -
- g -'
95 '56
-c v .
t
- 56 1 gs -
$5 *
,l,.t 8
- *ya.
3 7%
.E L t 1 ~.
-g..- .g -=
*3** 2$
=.5 4 =n.
I!!2 lai tTS "a e t $.33 3 3.;1i ' Eo e k j. t 2 -e3 W. li l d8
~
as- ii.2
- *52 bag 24:
Us si'2 US*S a:: - 3 *e V
<co s 't g
i
.s .
03 ,
*2 E
Ei . 2*1
$ % 'Ir $
- j*s *
.:. ! .t .
l iti oh1 i i$- e e i 1 - 1 E
- s 52
.17*31:
3
- 1 WO 2 J j' 1
E y El.t1si.25123'35
;1=: 3-
#ff!O 52;;fi:133$
. l
- 22 p.b W *'T-- e -r - -em.w , g wgg y W- w ww- m 9%-w---+,e- ,y v.-,,,e-- y w-f + i--,.w e
- 4 -
EMERGENCY PLAN IMPLEMENTING PROCEDUAE EPIP 1.1 Page -of 52 ... DETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 3 Date 3/22/83 W at W g a5. I
- srw 5 *a -
o!
"E W
E QW _
- t.
t Id 5 e 5: em
~
2C s
~ m
$1 2
. So 2
* ) )
F R, s -3.W 8
- 5. .
a!. 31 %$
=!
11 = I II 2 I F 7 3 3 2 E 0 - I tf
- 2 E 5 3 E -. g s i ,
- 1
- s* ** 2 in so y a a .
=.k *,
; . . g ~ ,;
- I
-8 g% t g **
5er. 2 s blsj ! . bli*s.- bl .& 3
=
3 - 14 [, 7
- 7*3 2
=
5 C 4
. 232 o *
. 82 . 3 P P -@
b 8 aa e js ..- - s
- g*g =
3
-71 ZI.;j: t -3 ill 7 - 12 as :g .- 3 g 2
vo m: a- . l; -. .-9 .8%31 asa leas: .: se5 si e3: e-; as 3. :, : - 1 Ss .e y El? 22%23 22 2 .* :
- 2. 3 33 2 .
33 R* .
** R .3
*21 J_ ii 31 *c2 %
a 8 >. 22 8 .8 C?? y $ '? " 3$' *i 2- 2 g as: :: : an e - 58 28 a o t. 8 E 5 ~2 9 8 8
- t l
l 2 i, l -_ l oy
*2 32 g : :
53 t: '. I
-s~
s bk.Bo*! 3%.*s
- 3==s32-'
*21
- I O
~
\ u_m.
e m mImaomgO< Dr>z {4rm* z4 -[ - vNOOm C2m 3 m% 1 ee eD bo m@0G 4 O MN 6 I e om4- mag zy4 oz k - 4I"
- . mEm"gmzo4 g4.oz -
r mr aG4=ne o.O3 b ' e e oB4G bNNNNWb S V E C L e l. lAN t E G WE N t t E D E DE G ' . L IU ( NG V O ts I C N . G10 AT f i t t Y C C A I
$l (G I l
NF ( 1 E I G $ l I S R E A i ML E C Al t. 9 AT 3 U N g S E A J V 4 t E U ly e e
.ri .
n h h aL n t t e ssE A o o a h lb ec e d e l t is s n e en r la t a e d e d e i w n o e r c c n s l ee o ipt n ot d e
"s id 4 o l t e as c
d an n i a 0 s e l c ta e n s s l 9 l. s d t s e e n e s 8 t a t e n r is a a r e t o C it c 9 o e v a o n c c ad 9 i C5 d l 2 l e d o eaC dI n2 a
- a rere 'l no , o_ i v y v y n r e o o L r n I 2 k .
/ u S C c rl n
oeh t t s nI o < i st t e ma H l s IO n I eB os a o n l r t o i n r o ig a yt s n o 5 t a u u n mb a t e t n p se 5e r t 3 r d B C o l a I tloi a it t cai n 1 23 T f en u m nt
,c I r lm e s a4 u t n ul aM y
n a s m e I s s o f s s . i es t N o u io e n e r od a t t P rs lot t l t h a oP n r B. a a sy c a I r a e 3 E T N 1 l t t p A A it s eS et in c a c o no l s u c l 01 t i dn e4 m3 3 s on e skl C t 8 e 8 l r I sl a a t lalb PA E1 E eid f a u y a u3 p4 t 5 F4 S o G ol u so 1 A h h s r l m l o u t el l a A P T t l d S r c leCaMl I e1R 1 H a ai u ei m h h l wl e irO S w yl ) yw ) ) t o t o y n n o i r p a u p C r ab r ab t N o P" ID D B D A n F s a t n t e n s S en l a N n a O l t I T e) n l t d o *
) n e c M o u y O cn i r
.C yt d
a T r n n N a o o A L imc r i c e P p y s y t t f i f or g 1 or g s e s e s t s t o n o n L i L i s t n tnl ) f r o = y d e t e T t oi n t f nS u oreu ucstoira I in
/
I n n a n N e e t
.E V t
s lp uill f oaa u s n t n Sy (gf aM a tI ( l E (l l f . y 9
< i*
5 1 L 6 g
- 8 mI mo zO<- Dr>z _E -
r gm e - ,O 2MoomoCmm mm=i
- e8 u0 9
ie0e s
- O* ,N 5 .
o em E z3-.e oz oM eh x QOmzOc. ,o4 o
- nsI r = me4 n O3 e u oo4e uNNNhGu S V
- E L C L
e U N E l f f E V E l le R E E L l C M s l uG . E T N C OI O GI .E M A T A T M R Y C SI K C I Nf E E i G s T R s - R l e A E - L B DC A L
' A T 0 N 4 5 E f
e Al I Us D 6 6 ily 0 0 . r . yI rm
- C C I
r e g e e g n a L b y n t r e s A n laa b n ie iy i s a i d e o a s o.p l t sE f s a b e lp e c n a en lp t f t . iss e n e c p r
,t ene ir a p p
u O h ig r inopt n e i oi c oT s t 8 d a l 0 de an oi m r In0 5 ut 5 o i d 0 t In9 4 ou d n a8
'. s s t e
C I t s e e s5 h c 3 k 0 o b n o er a et a s c jC t e o H e 8 o aBC oL laI l l s v y d r C L n n la a r e0 r O v e n r e o m r e r e r n o t r r dn mr d u o e a t Ioeh st t o sem a os r ee m n r de a T w o r n a rr o t e f r P e e yt s t a u u nrolo e f sof st r a f o w t l o o a s s S n mb a el n t to ic s p v 2 3 e n , c r s m s s f n a r n a a d a a 2 O s 2 . 1 T f u m n t p a r I a r r ef lo A C A s N o u a s r T rt 1 E P 2 t ra lot s l i e t ut p .bs yI y n e s l e I S I t l I Oe2 c c r p ue y b S G a c d o ai a ut o n: b O tnn n v PA E E 1 C l eid l sl f t r S t aIr C t aJ snC n aI lea 4 id a e o a o i A h h n u S at sI l l e l r A P. T t I s f tat S n t 5 n e i d r I A t u A o I f oS " o l S = o e D n a h e t e so abl sl s s lebl h
) O t
o l o toA N L B l r e w 6 p o D 0 l e T I t 0 es
- f o f o
_ C T f N o A s L P s o t l a t o T E
, r o n
F ( t os I n T
/n u. ec r at foir N
E t ip lu tu s a s w e V s wl s y q aa o o E t P S I f N I . ll i 8. 4 I l .
;} : j! qi 4 2, 1
- l4, , ;i3 4 %i4d! -
9 m o E m m EPIP 3.1 -4 8 ATIAMNT 2 MfGE8CT AGlW LEWL m O m m PAE 23 of 35 CLA551FC Ail 0el Gul0fLI E S * . b-c z
-e 1D
- r-O >
Not e The lastrumentatlon listed In Z Z this colima may serve as a possible Ur4J5UAL SITE ENERA O indicatlon, but they are not necessarfly EVENT At1RI EE RE NCY EMRE NCI g EVENT IYIT PLANT C0801T4086 1D suf fictert cause to detereth%e'E AL. '* 1 m Systen/ Loss of onsite power capabillty m E Eq uipema t f ailure of both diesel generators to cumplete AIS m surwelliance testing In mcordsace with tre m Z' Iallure or applicable 51P. kN . Malienctton 2 Stoss of o o Otnervation S Po.ori o 13 a IContinu J) E d f ailure to start when requiref $, o O 1oss of one or oore of he f ollowleg Busses ~4 C lA3, lA4, let) or IB4 as inJIuted by: o 2 al Power supply lif es on 1C00 are not lit bl voltage for Bus is sero r-
~"
c) 1C08 alares m 4 "Ev Bus IAS Loss of voltage *
"4KV Bus I A4 Loss of Voltoje=
M;u (L h7-6LC Irans IM5I *v Shr IA303 trip *
'Cu tL TST-6LC Trans 1341 *v Skr IA403 8 Trip" di Bar IA503 open el likt lA401 open o 3 u m e * * * 'O 4 < c -
g - G "O O Os O. b N 3 O
, N =
N *
\ be *
(D W ' O
-e.
9 O N 9 i. l '. 9
,~
k b zO o n O"O' Cpm . . s s,. mxmI mZ -c )[2 % _E,rmE 4
- 2 sq a- .
e ._ ie3* g ,O
- m.
s N P om4- [ 2>9~ - 2 o' 41" mEmWO"ZO #Ota.g . mgr me4'u#oa n u Oo4 - uNN %otn e, e
+
w
~ .
7'
~
S L V C s ~t E e N .
~L l R JNRE E
E L V I
. ,~ ^
~
E D GEK L IU E N G 0 1 7 l N CS a. E 7 ( . i C 0l T E C o. A l I R ,/ A T C SM( < CIF t 0 0 E I 8 G55 I R 9 8. ( A fl A 8 . D (1 - e L _ A T ' UN 5E
&V
'~
s E U y l d 4 n f r , 0 0 e a 0 0t r . 8 eL r e s A 0 la a O fp _ 4 a C lb esE n , se I s 6 c n n o a r iss ne e o a n o 14 o e e o10 20 t - a o e s r w e pt n t u ru n3 4 . s le s l oi h a l e2 g 2 - s e e .~ c o mo s e re l l g' s n e de an m ig n f e ia o5 4 SI r r .e t o n lcbI t t s e et l f e t t l hg n d u s a ra e g id t ' u A n l n a r_ t ro by up ~ r i l il e d e r a tr I a a e o a. im nr e o toeh v y te l t e d r n t n t a / d d i c A d d n a ra t S m guoMe r d na nh p o n S _ f' , d_S I n n t st id c a e d_S aI S a 2 n a8 01 1 a f 4 4 a t t 5 S I i t R l oC > e y t s t a u u n t s G I GI s - - oo
> a c o o mo r 5 m mb a I e r 2 2 t t r l r t r o #
k 5 > a su ,c 2 3 m r r r o l a t n y f f o u B4 l ) t nt o. t 1 0 0 f I o t e - e' t lotoi noi I s l g C i s a v 1 N o 1 P 0 2 (# 4 t re su s at a c P 4 o V 4 o ta r e a r e n e l.o1 1 9 5 4 $ 8 S 4 ( e w n C C I l l a l i b k a e r e b o a l ci A A n 0 1 la H e I si f G G l r r s P ( lA E eid f I l l 3 5 a - - k a s f t e f ob r a l A A P h h Ra l t u s d n n d n l e l e f 2 2 3 5 B b a o s s s V e a o a s 6 S e1 4 J M e s s s 0 s s S t 3 le0 0 lsO C h m a o o o5 L 4 e S e A c A 01 OI t S L L t * " o S a I N n o t ita .s i n o r h m n o g t m t se r t s e r e u o e n e w eb r i w o e S N 0 rI e w l
,m o P P lb
,r 5 l
i o o P rt - e1 C D C D is s -- ' m l oa v o et C n A o ,rl h S v S p 2 O C 2 _ C l m
.C A l t
8 8 t o laor o f n T f f o N ,o e o n ' A f f s L o n abl s s s Iose , P s i ot t s o . as o L e u sl ot e t e L r m r l ol L el r b l a p la ta ss e _ letoi s ,f y t o t o f o eS r D t s s f n f I o e r po -. a i . K t oi r c d e :, .
~
Y u - T n t f
's _.
/e e= ecn o)r n T
N E t se lp su l l u ss wetIa - V s el l o o o ,' E y g a a iPC I _. S iF M t _ 'A , $ _ 7 - I 7 , .
( r.s
~
,- il
' 8 a a
. r' r' s EMERGENCY 'fL AN [et:PLEMENTING MOCEDUME EPIP l.1 M. . -
is i >; A2
) Page of 52 CET[RMINATION OF THE EMERGENCY ACTION' LEVEL Revision' 3
/ Date 3/22/83 t
,f
. Ls . . .
- s. % #. .
1 . 4 r t Q* . L
, . ., I i
y gg a - 1 3 s, Hg. (- - 8_3 - -
= v Hi
-u Elv 3
- v. -
15 E :
.. EB 3 .,
s e 1
-: I -
,m)$ .
1 I. [ il , sa . j
). '38 a -: g 2 21!.
33, 0 - x. .31
'a. - . I.
121.
- . 8 's 's .- 1 :. *!. ! 2: s g *1
-.3 ea a
. ; . . ,s, -.
a -
-2 llf83 k:2]I2]l3
- la *
- 4 5 2 5. 5 5r *il l $Sl\*iI- *i =l-1I .$.
l 3
=R 2
) $:s ~3 y _ f, j . }o }. g 3$3 e
-~r z r
- w=
3 1,5
.e. 3 ,.
f_i2
. s. .} E.a. 1 g
. .- a .
. 33
- to s.2
.. g - 2. .
ge-- 2a. s - sg. _a 3-I ..: i a sm I .
.g.. g -.
.s 3. 3a-x gsg m .-
-g g .- - -
o3
- q. Aii! 3 8 ja 1 2 .--- g _. g.
- o. . -3 ta 3. =g , ;,1 1 ,1 g y }as&E r
.- - ,. -. -- - ..*3 j :E b 7 27 7 al 2 -
i
=,.
1: 1 > t g..2 i . ss* 1 2. 2 I ms 55 %31]t ri k-h
*o}g ..38g* '. ,
5 t.
.. .T *-- .
l l t ;* : *}}2
. 33 .1 12 21'4
- Iv !!
-wa.. 1-E tE -
; sis.tt s
- 1::c-5 s=*
- 22E'
-y_
I t 1 ei
* ,,4
-f a
4 h - e _E
e - EMERGENCY PLAN IMPLEMENTIN
G. PROCEDURE
EPIP 1.1 43 Page ,ot 52 .. . OETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 3 Oste 3/22/83
~
W' #9
'- 5N
*g W
,- d*-
x2
~
o a B_=o g Do o ' a$
"E u
*w 2 .,
asw '
/
g-w - ~ Ed E 9 .- w t ex5, s 35 o i 2 3 -3W
&. W. 8 .* o 2 Ek $ $
- e
=
3*k% 4
' 2 n u
R o C u a a
- t. -
;,.s ..- 2 26
- 2. 1 a,, ,22I
* : 16 3 6, 63 6 ;
.g i a l *, o F g, g5 g.
W e
-ge 2. o t. g.. g- a-saa ss M .6 .s 41 Ssg .rs: a*
.2 2-v?
E" v% 2* ua 26 4f23
*2 39 18 0 g ** 2 :
l-m2 3 3 J K
!J1 . 3e 2:_ 22 2
.u .1 2. . =8 -. -
.1353 . 42 . g s 'E a. * . =. .g j 2- g E=
oa ,g
$ 1'2*. 8% %) e c- .2.5-~* 2s m*
2 ~} e y . r. c 3.. 1 .* .1 - s 6 8 f.71*-* 33 TJ 2 2' a
. : :3 4 .; i, .} 2 3
- 3* it h he i -2
'. :ttab. 22 31 2
- 1 2221
* ,.: .- 2;1
. B
, E Z~
*; t t. i
.s
* " -8 ' 1 *1
- 5. sou$-. .e. ..
Y.
. %. - 1 y s jt *2 -*-.
y lati 3 y ;: :*- '!
- 222%~j- 3y .
l e-E b m'
9 P mImnom [8
- p teyZ i
E {xmz zo e EOgm0Cmm m^_, 8 .e* a> i*o.- Oo- ou t Omemab
- Z 6
oZ 0 jm mxm2om b d >04- oz r",mr a' o_o3 6 9 o$. u%NN oesot
. V S
Ee ACN R E E El E D l i NR G (l L l u ( N G 1 , OI N .C . Gl0 E 3 C Ai A 9 dR 1 V C l 5 ()( 4 ft I S 18 m5A 5 R f l I B 9 MC L L A 8 A T i lA U N l 5E A . U (V PU y ll r . e s eR 4 ( t l b ce n t u t t i u o r w s e e o . t a e p s n t n p e a opt m e a n i e l n i o r r r ol o r p p d a na r . t e r r e t p t s ee e l e d le p e s e r t d r v e D l a e r o v e o e D l e d c l r v y c l e r e nr e o e r R r e oeh t R e t a e l v t a ist e l v e i W. w t a y t s e i v r y t a u u v r e 0 . y e mb a e leQl0 t d 1 e 0 .o t t 2M i L C s n i.c i t e t M . e t M a t e C u mu a r s lotledte r t tu 2 e a T f r s 1l EN o. t rsa c u t 2 en r t cO nl v r d i d ip M 72 c0 ni uI egPa o, p P I ac ic ul e o rC . a a I O l sil r C gP t I o i R R P A eid l t I S r r EI u S r r e e r r M h h n e eal . a n pt u pt T T t I s l a AP eet ke n e tu ke e u a. d d e s e u p p t P moa . i s C e C e t P sao m a v t a CC l CC o s N . . t n 5 .
. ' a S
'3 5
7 7 5 7 ml r p F C 0 F C 0 n e e
- n. foh t 0
2 5 e h h t n u l n n e h t t
, i s o a h h
r et e t t S r e e t c r s N t t a e e u . s s 0 a et t s e e r 1 il e r r g grop urcwon l e l g t d w w m l ied stu o l o 0 le e v o l f C v e e v . e losesht f r r T l i,f e A N l r r e ef ladlo ev i v L P e v v iv o er c i R R R say a r r i R iR , c t l a o r r ei e d lo a d l t e C a d e o r e o C d e C C o s n C _ s) T f eJ V c e n u I I l a r i en M r . L usta V ( t n uo( co
- c. C e
f t % -
.i;g8 *liliIi i
9 y a m EPIP I.1 o E m m ATTAOINENT 2 4 2 PAE 28 of 35 D4EHGDCY ACTIOst LEEL i CLAS$1FIC AT10N GuilJEL 18E S .Q $ 1 Z
. O z 4-gs u Note: . The lastrumentation listed la r- -
O
# Dis column may serve as a possible z z UeU5UAL SLTE EV&NT TVFT indication, Inst they are not necesserll y EVENT GEME1WL PLANT CO*OITIONS g _
At1RI EltRENCY O(NENCV M !- selliclent cause to determine en EAL. Notor.i 4 r* (k:cwrences c.aer ni..r flo. B.ss th.n 13 ces cod., a ids city N.t.r oept. r, ort 1 m with plant not in cold shutdown. cla m I (Continuedl m 3 -4 "y $ o O m z D o n g o o
> m I
O O I
-4 C
- n o m z
,. t* i Winds greater then 100 mph with m ) plant not la cpid shutdown. WisorologIcel lastrummatetion on f%nel IC21 w: C13 m f* 1 I fornaJo on site * " 2 Visual observation. Al9 m 1 m
, o. e ,
=+ < sD **
3 e - e 1 m u O .b 4
% 3 u g -
' N
- Turnado s tr thes lecillty cousing s u "
domaije, Visual obseretlon and assicisted 815 m 1 systa 31 arms "
-o
+
w I, r e t N i l ' \* O 4
, -r
e
- EPIP 1.1 -
AIIAOS4ENT 2 (NEftLIE8CY ACI10N LEWL PAE 29 of 35 CLASSif CATION GullE B ES
. m o E m^ m
-4 n Notes The lastrumentation listed la m .
O this column may serve as a possible UMISUAL $ lie ENERJL E z
~
ladicat lon, but they are not necessarily EVENI ALERI (8(RE NCY (B(RE NCY Q EVENT TYli PLANT CO*0lilONS ,sulficient cause to detenelne an EAL. $ , Naturel Iornado whlCh damages safety relata) Visuel obsofWatlon and asSOCl etal Cl4 z Occarrences structures and compromises the system stares o . ICuntinuedl i m ctlens of safety systens es E D
-A r 1' m m E other unusual aircret t activity over - Commwitcat lens arce Security A20 m r*e sar d s tecility or crash on site x -4 L e ger IenC,J m -*
or Projectal o O m z 3 o m
-c o o
> m Alecret t crash or missile impact Co munications tras Security el6 o, o thlch causes tecili ty damage. Visual Obserwf lon and Ass >Clated
- Systen Alarms
)
O h m z r-m
~m r-I Aircrat t crash or missile impact , Cenemmiceilons tras Security CIS I
which damages safety related systems visual Obwrwilon and Ase>cleted or s tructures ulth plant not la cole Systen Alarms ' , s'.utdown. 1 o m 4 m i en e op e
-e < ao -
o - e 1 en l u 'o 6 , Train derallment onsite Communicat tuns from Security A21 N 2 a*
, n -
+ n .
I
% W -a
, GD W r O
- t.
- T, un
-- . . . ~ . . . N i
e . t
.e
_ n- s-dMERGENCY FLAN I M P L E M E t4 T I N G PROCEDURE EPIP 1,1 Page .of 52 ,. . OETERMINATION OF THE EMERGENCY ACTION LEVEL g,yg,3,3 3 Date 3/22/83 l a W. $ yE g -wea 5= WWw Eu . W ?- .-
-5 "g, a E:s Vg w e a %
y
- 5d I
* $% a 2 2
j 5- . 2 2 N at
&gw
- !a*
3 1. ! 1
- e i.:=nz.. feei
, gz y2 n
-*
- 3 _
a C. - h <. h. W
- 3. **
. .t .o .W W 1 .7
..3
- 5* . .
- n. . 1, 8 3 3o 8
#2 sa ;;;
gg-11 8; .:s .x - _-=
= .
j e.
- s y
-x bs
-es83
.a; a.3
;o 2.s
*35 So1 e
-2*
20 $ 22* o gs *: go
- 51 48%
5% g: 5!J
=
$7 g.
us tg: 26 5
} uI 1
b t.
*23 as g, y
- 2 Ia g I -
je s* :: I ee2 2
- 8 .
; i. F. o;
. . .. vis -!:
y 2 -T :. i * - '3et* ** r C $ 8'; a 2's
's j s a r2 8* *I o 8:~ -2' 25
> -g ::1 3:
1 s'. e 3-2 13
. 32 r ]_i 5
O $Et**c$ t 9e Os
+ + - - ,--w ,y,. p ~-s, e ,,y-a - -,y. g -~ r- 4m-t- -m, --
em. v,--- , ,r- e -e,er,- we ~v -w,, w, sng---
'I a a l EMERGENCY FLAN IMFLEMENTING FAOCEDURE EPIP 1.1 48 Pago of 52 DETERMINATION.0F THE EMERGENCY ACTION LEVEL Revision 3 ' !. i Date 3/22/83 e n t dE W" - ".i 3 -
"g am BW
= .
5 =E W 9:< Es
-e u
*w W. at.
9- a . . 13 3 5 E IE ss e e .
. C.
2,WI. . E. o. 2 - **2-2L.3 t%s E :. t 7.... .!] ' 5' e 2 sr~ :.- .
.Eto .a 2:f* 8 3
%*3 j'j mg "ea 1333 *
$.g -3 e .Y c 5 j 7o
~. 7 1 2ljt
- J .. w. % . .
~g- ji"821 1 *.
- 3ef
*2= 2
; ji. 4
, !!: o *
.- 3: a' j *! a j ,) 1.-
t=i - sa Ssg 2: 13 22 8 12* } E y .E -- tt ts tai E en! t* t*: s
- 1. ,5J)
' 0 53 22; 22- <a oso T g i o.o -h
'8 k- - a a* ,.
- : 33 ;* 2i l ,2 *5
- !2 -*
1-32 22 I:1.i:s 32 sia= si *t "82-: s=2 ksy2*1
=i : 83 --
5"32
- 3 3.1. .t i. l.
r i!- av * *:e ::.
. : : r -] :2 :: .
- . : 2: 22 s -
- 3;=yeJ
_o--o-.. 2s x -u1 1
- 2 .1
~
f
.9 ;.
O e (PSP l.1 AllAOte(NI 2 lleEfGEeCY ACil0N LEVEL PALE 32 of 3S CL A551f ICAll0N GU10lL l eE S * { g m m
-4 m
, m o
- a: m 4 x z Notes The lastruentatlon listed in - O this column say serve as a possible UNJSUAL 511E GENER$ y ladlcallon, but they are not necessarily (VENT AGERT (p(HCENCY [ftRLE NCf
,1 [
l EVENT TYPE PLANT Cosel110N5 suf ticient cause to detennine en ( AL. O > z z 1 5 Release or Fuel handling accident that results visual observation B20 0, j~ Loss of la f uel daeage with the release of M , y Control of redloact $ wily to the Ra Bldg. As reported by the Rallation Prot ect ton x m Radioect l we (Sw;ondary Contelnaonti Departaunt inssed upon the results of surveys .m 4 Materials . anl analyses conJuctal in accordanos al th 'g Z
' g
.ithin tese applicele WPs. m -
y
~
Plant Other Possible indicators h IContinued) AIN indica kers m 2 3 CM4 recorders - o m
-c o n
Najor damage to spent fuel la Rn Visoal observation C16 g A Bldg. 85.condary Contalnamati and -g c As reportel by the Hellbon Prot ection 8 $ Deparlaasnt t,asoJ upon the results of surveys 2 ans analyses con $ucted in accordanao alth t-
- , -sp,iica.ie mP.. m
, Other Poselble ladicators m r-Af+1 Indicators . CN4 recorJers a Uncontrolled decrease la fuel Pool Water level inJacator on Panel IC66 C19
, water level 8,elow fuel level. 37 f t 6 In einleve level ; f uel Pool Coollag Cleanup F 18 ter Trouble 3
Annunciator Penel on IC04 O N i- m
) S e 9 "O J
-f C 10 =
1 e = e "O e LA O b 4 % 3 @ H =* , e N e U
- c
\ ^
AA sO t-t y %,n 4 5 S T 1 i 4
.a
EMERGENCY FLAN IMPLEMENTING PROCEDURE EPIP .1,1 Pego of 52 DETERMINATION OF THE EMERGENCY ACTION t.E V E L Revision. 3 ,. . Date- 3/22/83
.W a! .
W' - 5s zz -
", g 8 r. .
5 *= - .--
-g y o_ - *2 "Wu w *w.
I- m - 2 E3 3 C A h$ % gg _h E S 34 ; % T T
- a. W*$* ; 8 t
- s.
g52 , 5o 2" i 3 % *
- 1. .* *. E 5 8 2
'2 3
- k 7' 2 2 2
. -3 5 t t 'o t e . . t a ' s bl,3 m hl, ?
- 1 1 23i*
;>3 j - 7 -: y
{ J a "a
. to* . "Io a
2_l3*T E E l'
. } 3
. 5 _. $
- a. ' O E8*% *
- I ' - E E * ! E EnI ..
33 I
---. .s I
i f: $. - g 0 - w 0 0 0 o
. s - - a a g
'l
$ ! ;- -3
. t
*-{
- . Es sa 2 ;
*2 2' 2; i *b i
k0 1 *2 '-1 i: , 93 .8 ;. 2 s .jg:
- a. 3 *: =.
I- s-s.22
- 2 is: .:
'It
.i 24,;8
- g2;.
E.* -25
- 52-
?"2 24* 2 2: 2
*1 282 228 ** i 3g i :
'I I
t!r
.t'
_21. 1:1 8* 2 3-2 .8.. b i .1 g ill_i. 86 5
;;2 .334 - *2* 25 1. 3ff 33" *:.* : s'3 2 % w e
* ,2* *"$f
& It s : i 6es I=.g 3:.c s:- .5 I E.
E 1 F8 5 13:= 0 53$3
.0 Os w
e - EMERGENCY PLAN IMPLEMENTING PROCEDURE- EPIP 1.1 Page -of 52 .. . OETERMINATION OF THE. EMERGENCY ACTION LEVEL Revisiog 3 Date 5/22/83 f W at a- 5y. WW zz
*:= dWw 30 .
.y es w2-3 0
*u
>g og
.u 9m w m
=
$5 2 n 2 2 2 E3 1
* $2 ww
~
~
g: e 3
'3d 3
- 2. .. :
a s-
*y.* Ih t e
-3 . 1 St: o-
.o w i v o ,
3I ! i 2 $$ 2 i %
~;*i & L :r ;
i f e 3 r h
.c -i
,- . ,1 7. :. .g W
- 3. *. .t3 o 2s s il 16 ^
-J-V 2 no .
5
=0 2:36 j'
I 1, 3: 12 5 3 3 a
--- . 1
- 2
* -l 2.3 3 ** -* 8 2 o
.6-oT" -
2 8 3 ;- -5Y . -
; j
.37: & & 4 %j
- Ssg 3 -3 ..
26 4333 e r &y :h [g 5 j l 8 i "3 o 3
. t
~ = 8* 2: o u J 5
. al 5
*2 a 3' -:
;8r -
- 2. s-30 2
2:82
- 11 $si 11 *$ *1*
till
- ~
- ?.s.
iB*2
^1*2 o .: 3 1 *2 t' ,
ji- *2. 5, g- i j *1 ;. - - xg ! :, s s* s isa : e dea .li r8 es 02,: =, .:.
- ;s ,
- s- :-2:s. s : :- 2,= 2:
2 : 2 o 1se l 1E==2 -:2 -
- s 2: *:
8.- t *yz} *1 t-t w %s ti 2=* 17 : ~; 3 g c t
- L':
2 t4*2: 2
? %
2, s :0' 1,0: t- 1* i i
^;es. ;24 -*4. 17 3 3
';?2
%'? *: :37 $1 2 it
*7 ti : 1 Ws ua5 2
o =, M - c) .1. a.8s 27-. . t r 8 :. w .
- =o o n.
t 2 I lf m: 8F.Y I 7 32 :::: !
- . :13 - 1~*: ;
5 O . it'*3
*: od- 18
~
- 3 v:
o zo< T!*
-e.
d
.l
< a.
-EMERGENCY PLAN IMPLEMENTING PTOCEDURE EPIP 1.1
$2 Pegs . of 52 DETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 3 'r Date 3/22/83
( w d5 Wg
'- 5s za g w _3 st--
Bo . M e ~ gu
-6 <t W :g -
$. 0 e
5-- r U g.W - e , N d e la* <
$E =
- 2
. t ;-
m IW 8 S { 8" - a. W* --
*E g
..5.5 3.., .
t I I .i i'
'E"'I .k -% $ $ EE
.2
.c h i . ,.
- 3. *.* ,r .h , 3 1 -
m,
.. 3 . a * ..
- a.a 7233 g 3 3 3g 4
=*
.a el21
_s 3 3
.s
- a. I O : 833s I i 3 3 2*.
'b!M <=
fili I I- 3 3!$ _ l e g ! 3 j.. $ $ d 5 u a$ _ . .s t. o o 22 a; .
. g 8
g -
.3 -
i e i 224 2V U 1 j 3 _.
- 3 _& _. .: -
3 3 % r {. y. 3. =. 12 a 2 a u ast 3v. p 1 3 I II' E*I. . j . -
-st :22 ' 3 e l'! {
-o
- 3:i 5
*i I
1 . 1 18 2:3 ar af _3 .. .
.i
.s...
_ !_i 3e .! .* 2 - 22 t . .j 3F.Y :2.g 5 1T*:
- 1
- 0 0 =7 :o . d.
., b of
-l l EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 1.2 Page of 19 NOTIFICATION Revision 4 Date. 8/26/83
.1.0 PURPOSE 1.1 L This procedure.prov' ides instructions for notifying the Emergenc'y Response
- Organization and Offsite Agencies of the declaration of an Emergency Action -
Level-(EAL). 1.2 Additionally, this-procedure also provides guidance associated with NRC notification of significant events as prescribed by 1.2.1 Inspection and Enforcement Information Notice 80-06. 1.2.2 Inspection ana Enforcement Information Notice-80-06, Supplement 1. 1.2.3 Inspection and Enforcement Bulletin 80-15 1.2.4 10 CFR 50.72. 1.2.5 10 CFR 20.403.
.2.0 APPLICABILITY 2.1 This procedure applies to members of the on duty Operations and Security -
.Shif ts and to the Emergency Response Organization upon declaration of an EAL.
2.2 The procedure is also applicble to 0AEC supervisory personnel in those cases where events occur at the DAEC which do not require implementation of emergency planning requirements, but for which NRC notification is required. 3.0 RESPONSIBILITIES 3.1 Ooerations Shift Suoervisor 3.1.1 Initiate the notification process appropriate for the event. 3.1.2 Insure that notifications made to Off-Site Agencies are conducted within 15 minutes of declaring an Emergency Action Level (EAL). 3.1.3 Verify that the NRC is contacted within one hour of declaration of an event. 3.2 Security Shift Suoervisor 3.2.1 Assign communicators as required to conduct notifications. 3.2.2 Advise the Security and Support Suoervisor upon completion of all required notifications and appraise him of problems encountered. 3.3 Emeroency Coordinator 3.3.1 Ensure that initial notifications are made to Off-Site Agencies. Ya
~ EMERGENCY PLAN IMPLEMENTING-PROCEDURE EPIP. 1.2 Page 2 of 19
. NOTIFICATION Revis ion 4 Date 8/26/83
'3.3.2 For all events classified as an ALERT or higher, verify that continuous communications have been established with the NRC.
3.3.3 For events classified as an ALERT or greater, ensure that follow-up communications are made to the Linn and Benton County Civil Defense Offices and the State Office of Disaster Services until relieved of-this function by the EOF. 3.4 Assistant Plant Superintendent - Radiation Protection and Security 3.4.1 Ensure that-the Duty Emergency Response Assignments Special Order is updated and published as required. 3.5 Emeroency Plannine Assistant 3.5.1 Ensure 'that 'the listings in the Emergency Telephone Book are reviewed and. updated as necessary on a quarterly basis. 3.5.2 Verify that the auto dialer system is updated as required to reflect the most current telephone numbers contained in the Emergency Telephone Book. 4.0 INSTRUCTIONS 4.1 GENERAL REQUIREMENTS 4.1.1 All telephone numbers required for notification purposes may be found in the Emergency Telephone Book. 4.1.2 Notification of DAEC, Corporate, and Off-Site Agency personnel, including the NRC, shall be accomplished for all events classified as an emergency.
.a) ~ 0ff-Site Agencies shall be contacted within 15 minutes, as required by 10CFR50, Appendix E, of declaration of an emergency condition or of upgrading an emergency classification.
b) NRC contact shall be made within one (1) hour, as required by 10CFR50.72 of declaration of an emergency condition. 4.1.3 OAEC and Corporate management personne1' and NRC shall also be contacted for any of the events listed on Attachment 1, prescribed in 10CFR50.72.
~
1
~
9
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 1.2 3 of 19 - Page NOTIFICATION Revis ion 4 Date S/26/83 NOTE Some of the events 1isted on Attachment 1 may require
~
implementation of emergency planning requirements, a) NRC contact'shall be made within (1) hour, as required by 10CFR50.72, of the determination that 'such an event has occurred. b) For those events which require reporting in accordance with 10CFR20.403, a verbal and written report shall also be provided within one (1) hour or 24 hours,' as applicable, to NRC Region III. 4.1.4 For events which require implementation of emergency planning - requirements, the notification process will generally be initiated by the Operations Shift Supervisor. 4.1.5 For events which require reporting as defined on Attachment 1 but which do not' require implementation of emergency planning requirements, the notification process shall be initiated as directed by the Plant Superintendent-Nuclear or his designee. 4.1.6 DAEC and Corporate management personnel to be contacted include: a) Plant Superintendent-Nuclear or his designee b) -Director of Nuclear Generation or his designee. NOTE:
- 1) During normal working hours, the standard organizational reporting relationship should be followed in making contacts.
- 2) During off-hours, the Operations Shift Supervisor may elect to contact only the on-call Emergency Coordinator. Further internal contacts may then be made as agreed to.
4.1.7 Off-Site Agencies and local response organizations to be contacted for events which require implementation of emergency planning requirements include: a) Linn and Benton County E0C's - via the respective Sheriff's Offices b) State Office of Disaster Services c) Palo Fire Department - as necessary d) Palo Ambulance Service - as necessary e-
~
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 1.2 4 Page of 19
^'
NOTIFICATION Rev is ion 4 Date 8/26/83 4.1.8 Notification of the Linn and Benton County EOC's of the emergency ciassification and 'any subsequent reciassifiction will be provided
- via the respective County Sheriff's Offices.
a) The respective Sheriff's Offices will notify local civil defense and advise of event classification and re-classification. b) -When the Linn and Benton County E0Cs are staffed, generally not unt11 the SITE EMERGENCY classification is reached, civ11 defense officials will contact the EOF. c) Follow-up notifications shall be provided from the OAEC to the
. . local EOCs via the respective Sheriff's Offices for all events classified as an ALERT or greater unless relievcd of this function by the EOF.
d) If contact by telephone can not be made, backup communications capabilities to be used include the point-to-point radio and IWAS telephone, in that order. 4.1.9 If off-site assistance is required for fire or medical emergencies, notification'of the need for assistance shall be made as follows:
~
. a) Fire Fighting Assistance - The Fire Brigade Leader shall contact the CAS Operator who shall notify Palo Volunteer Fire Department for a'ssistance.
b) Medical Assistance - First-aid personnel on the scene will contact the CAS Operator who shall notify Palo AmDulance Service. NOTE: If additional transportation assistance is required, the CAS
, Operator will make further contacts.
4.1.10 The NRC shall be contacted within one (1) hour of declaration of an emergency condition or determination of any of the events defined' on Attachment 1. a) Fce events classified as a NOTIFICATION OF UNUSUAL EVENT, the Operations Shif t Supervisor will normally make the contact. b) For events ciassified or reciassified as an ALERT or greater, the Emergency Coordinator shall insure that such notification is made and that an open continuous communications path is established, prefereable via the' NRC " Hot Line" (ENS), c) For the events indentified on Attachment I which do not require implementation of emergency planning requirements, NRC contact shall be made as directed by the Plant Superintendent-Nuclear. 1
\
\
.l l
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP- 1.2 Page of 19 '
~
NOTIFICATION Revision 4 Date 8/26/83
' 4.1.11. Upon completion of notifications Attachment 2, " Initial Notification Message", should be forwarced to.the 0perations Supervisor for his review.
a) At the conclusion of his review the Operations Supervisor, should-distribute copies of Attachment 2, as follows:
~
- 1) Send the original to the Control Room, where it should be kept on file for .approximately six- months af ter which it may be discardeo at.his discretion.
- 2) Send a copy to thE Technical Support Supervisor.
b) Should the Operations Supervisor review mentioned in a) result in detecting deviations from procedural guidance he should initiate appropriate corrective actions, this may include additional training, procedural revisions, etc. 4.2 NOTIFICATION'0F UNUSUAL EVENT 4.2.1 During normal working hours the Operations Shift Supervisor shall initiate notification of DAEC and Corporate management by contacting the 0perations Supervisor or his designee, a) Further notification of DAEC and Corporate management will .be conducted following the standard organizational reporting relationship. b) Contact of Off-Site Agencies including the NRC, shall be conducted as directed by the Operations Supervisor. NOTE: Notification to Off-Site Agencies shall be made within 15 minutes of declaring an EAL. c) Communications with Off-Site Agencies shall be documented using Attachment 2, " Initial Notification Message". NOTE: Unless directed otherwise by the Plant Superintendent-Nuclear, no follow-up calls need-be made to Off-Site Agencies. Therefore, as part of the message provided, actions being taken to correct the condition may be discussed and the agency so notified that no further calls are planned. d) Contact with the NRC shall be documented in the Shift Supervisor's Log. O
~
EMERGENCY PLAN IMPLEMENTING PROCEDURE-' EPIP 1.2 6 Page of 19 ,,
~
NOTIFICATION Revis ion 4 Date 8/26/83 4.2.2 During non-normal' working hours, the Operations Shift Supervisor
~shall initiate notification of DAEC and Corporate management by
- contacting the on call Emergency' Coordinator.
~
a) Further notification of'DAEC and Corporate management will be conducted as agreed to. by the Operations Shift Supervisor and on-call Emergency Coordinator. , b) Contact of Off-Site Agencies shall be conducted by the second SRO on shift and documented using Attachment 2. c) If c:ie second SR0 is not available, .the Security Shift Supervisor-
~* mn be requested to make such calls.
d) Contact shall be mace with the NRC as directed by the Operations Shift Supervisor. Such notification will normally be made by a licensed SRO. Documentation of such notification shall be recorded in the Shif t Supervisor's Log. 4.3 ALERT, SITE EMERGENCY OR GENERAL EMERGENCY NOTE: Full activation of the DAEC Emergency Response
. Organization is required for all events classified as an.
ALERT or greater. 4.3.1 The Operations Shif t Supervisor shall direct implementation of EPIR 1.3, " Plant and S ite Evacuation". 4.3.2 During normal working hours, the Emergency Coordinator shall assume all responsibility for contact of Corporate Management and Off-Site Agency personnel. NOTE: Use of~the common pager number to notify the Emergency Resconse Organization need not be done under these circumstances. a) .Such notifications shall normally be made' frem the Technical Support Center, b) Notification to Off-Site Agencies shall be made witnin 15 minutes of. declaring an EAL as required by 10CFRSO, Appendix E. c) Notifications made to Off-Site Agencies snail be documenr.ed using Attachment 2. d) NRC contact and establishment of a continuous ocen communications path with NRC Headquarters as required by 10CFR50.72 shall normally by made from the TSC as prescribed in paragraoh 4.3 .
y a EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 1.2 Page of 19-NOTIFICATION Revision 4 Date 8/26/83 4.3-3
. During non-normal working hours, notification of Corpor. ate Management, OAEC Emergency Response Organization personnel and Off-Site Agencies shall be initiated as follows:
NOTE: If an EAL is declared due to a securii!y related emergency, all notification functions performed by Security Force personnel shall_ be assumed by Operations, a) Upon hearing the evacuation alarm and paging announcement the Security Shif t Supervisor shall dispatch a memoer of the Security
- Force to the Control Room, b) The Operations Shift Supervisor shall ensure that items 2 through 7.of the Initial Notification Message, Attachment 2, is completed and verify that notification of the Off-Site Agencies is initfated. Normally such notification wilI be accomplished by the second SRO on shift as described in paragraph 4.5 of this procedure.
c) The Operations Shift Supervisor shall insure that the Emergency Response Organization Notification Message, Attachment 3, is completed and provided to the Security Force member dispatched to the Control Room, d) The Operations shift Supervisor shall direct notification of key members of the Emergency Response Organization using the group pager telephone. number and pre-plannec message as prescribed in the current Duty Emergency Response Assignments Special Order. NOTE: The group pager message should be repeated twice more at 5 minute intervals each. e) The Operations Shift Supervisor shall also notify or insure that the on call Emergency Coordinator is notified of the event by making direct telephone contact. f) The on call Emergency Coordinator shall notify the Emergency Response and Recovery Director by making direct telephone contact and aopraise him of the situation, the sequence of events, as appropriate, and corrective actions being taken. NOTE: This initial contact should be brief and, if at all practicable, made before traveling to the site.
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 1.2 8 Page of 19
' ^'
NOTIFICATION Revision 4 Date 8/26/83 g) Off-Site Agency contact.shall be accomplished as described in paragraph 4.5. , h) NRC contact and establishment of an open continuous communi-cations path will normally be accomplished by the assigned communicator in the TSC as described in paragraph 4.8. NOTE: Regardless of the situation the Emergency Coordinator - the Operaticns Shift Supervisor until relleved- shall insure the NRC is contacted within 1 hour of declaration of the event. 4.4 Sicnificant Events Recuirino Promot Notification , 4.4.1 Additional events which may not be considered as those which require notification and/or activation of the Emergency Response Organization but which require prompt reporting to the NRC are tabulated in Attachment 1, " Additional Events Requiring Prompt NRC Notification". a) Events which require not only prompt notification of the NRC but also establishment of an open, continuous comunications path are so noted. b) In those cases where an open, continuous comunications path is l~ required to be maintained, activation of the Emergency Response Organh:ation will most likely be required. 4.4.2 Notification of DAEC and Corporate management personnel shall be conducted as follows: a) During normal working hours - see paragraph 4.2.1. l b) During non-normal working hours - see paragraph 4.2.2. NOTE: If activation of the Emergency Response Organization is required, notification shall be conducted as prescribed in paragraph 4.3, including notification of Off-Site Agencies and the NRC. 4.4.3 Contact with the NRC shall be made as directed by the Plant Superintendent-Nuclear. l 4.4.4 In the event that the EMS System is determined to be inoperable, the NRC Operations Center in Bethesda, Md. shall be notified within one (1) hour of such determination. l l
- , a EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP -1.2 Page of l'9 NOTIFICATION Revision 4 E
Date 8/26/83 4.4.5- Events defined in 10CFR20.403 being verbally reported to both NRC Headquarters land Region III .shall also be reported by telegraph, mailgram,'or facsimile to NRC Region III. Written reports shall be prepared so that names 'of. indiviauals who have received exposure to radiation are stated in a separate part of the report. 4.5 Notification of Off-Site Agencies 4.5.1 Unless directed otherwise by the Operations Shift Supervisor, the second SR0 on shif t will provide init tal notification of the event to Off-Site Agencies.
-* NOTE:
Notifications to Off-Site Agencies shall be made within 15 minutes of declaring an EAL. 4.5.2 If the second SR0 is.not avallable, the Operations Shift Supervisor - may direct the Security Shif t Supervisor to make such calls. In such cases: a) The Operations Shift Supervisor will provide the Security Force member, present at the Control Room, with the Initial Notification Message form. b) The Security Force member will provide the message form to the Security Shif t Supervisor who will assign a Security Force member as communicator. 4.5.3 Upon contacting each agency, the Initial Notification Message shall be read to the individual who received the call, confirmed to be- ! understood by the recipient, and the message form annotated to reflect: I a) Time and date.of the contact, b) Name of the individual who received the call. NOTE: I
- 1) Confirmation that the recipient has correctly recorded the l information can be obtained by requesting that the message be read back.
! 2) ~ Call .back verification of these initial notifications _ can be expected frcm the Off-Site Agencies contacted. I l' 4.5.4 Upon completion of all calls, the en call Emergency Coordinator shall be advised upon his arrival on . site. i l m
e . EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 1.2 10 Page of 19
^'
. NOTIFICATION Reviston 4 Date 8/26/83 4.6 Notification of the DAEC Emergency Resoonse Oraanization 4.6.1 The Security Force member returning from the Control Rdom shall provide the Emergency Response Organization Notification Message form to the Security Shift Supervisor.
4.6.2 The Security' Shift Supervisor -shall assign two comunicators to contact members of the DAEC Emergency Response Organization and provide each with a copy of the Emergency Response Organization Notification Message, a) Notification Lists Nos. I and 2 contained in the Emercency
- Telephone Book shall be provided to the communicators, b) Notification of the Emergency Response Organization by the assigned communicators shallcproceed in parallel to enable rapid response by personnel who may be needed at the site.
4.6.3 The Security Force Communicators shall perform the following: a) Telephone, in sequence, the individuals for each emergency position and repeat the Emergency Response Organization NotificationMessage(Attachment 2). b) 'Use the priority established in the respective Notification Lists until all positions have been filled. NOTE: Reference shall be made to the current Duty Emergency Resoonse - Assignments Special Order. Those individuals assigned should be called first, c) Allow approximately 10 rings (about 1 minute) for a call to be answered. d) Log all calls and attempts on the Notification Log form (Attachment 4). , e) Proceed through the enttre sequence identif fed on the respective Notification List. f) If the total number of people required for each emergency position has not been reached, attemot notification of tnese individuals unavail.able during the first calling cycle. ! g) Advise the Security Shift Supervisor of problems encountered and positions which can not be successfully filled. 1 p- i
- s a EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP. 1.2 11 ' -
Page of 19 NOTIFICATION Rev is ion 4 q Date 8/26/83 4.6.4 Upon being advised of the completion of.all calls by the Security Force Communicators and of problems encountered, the Security Shift Supervisor shall report the status to the Security and Support Supervisor or, if not present, the Emergency Coordinator. 4.7 Upon completion of all required notifications, the Security and Support
-Supervisor shall advise the Emergency Coordinator of their completion;and of significant problems encountered.
4.7.1. If the required Emergency Response Organization positions have not been filled, the Emergency Coordinator shall designate temporary personnel reassignments which may be necessary to fill the positions. 4.7.2 If additional support personnel are required and available from the Corporate Emergency Response Organization, the Security and Support t Supervisor shall coordinate such neeos with the Emergency Support Manager. 4.8 Notification of the Nuclear Regulatory Commission (NRC) shall proceed as follows: 4.8.1 Notification of the NRC should occur following activation of the .TSC by the communicator assigned.
~
a) As directed by the Emergency Coord inator or Technical Support Center Supervisor, the communicator shall-notify the NRC of tne declared EAL. b) The time of the initial call and the recipients name shall be recorded in the TSC log. 4.8.2 Notification of the NRC shall be accomplished within one hour of declaration of the event, as prescribed in 10CFR50.72. 4.8.3 Once communications with the NRC have been established, continuous communications must be maintained as prescribed in 10CFR50.72 unless terminated by the NRC. 4.9 Notification of Event Re-classification 4.9.1 The Emergency Coordinator shall ensure that offsite authorities are notified of event reclassification. 4.9.2 If the event is reclassified to a more severe conoition, such notification should be made within 15 minutes. NOTE: If the EOF has been activated, this resconsibility shall be assumed by the Emergency Response and Recovery Director. w - - ~ - - - n ~.. .m--- - .-
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 1.2 12 Page 'of 19 , NOTIFICATION Rev is ion 4 Date 8/26/83
- a. When the event is classified as more severe, contact shall be made with each organization or individual required by the new EAL.
- b. When the event is classified as less severe, contact shall be made with each crganization or individual required by the former EAL.
-4.9.3 Upon deactivation of Emergency Response Organization from events classified as an ALERT, SITE EMERGENCY or GENERAL EMERGENCY, contact shall-be made with each organization or individual providing or coordinating support functions with the Emergency Response
' Organization.
4.9.4 Documentation of such notifications shall be made in the TSC Log.
5.0 REFERENCES
5.1 Iowa Electric Light and Power Company Emergency Response Plan. 5.2 Duane Arnold Energy Center Emergency Plan 5.3 10CFR50.72 5.4 10CFR50, Appendix E.
-5.5 10CFR20.403 5.6 NUREG 0654, Rev. 1.
6.0 ATTACHMENTS
~
- 1. Additional Events Requiring Prompt NRC Notification
- 2. Initial Notification Message Content
- 3. Emergency Response Organization Notification Message Content
- 4. Notification Log
~
~
.Y
- e EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 1.2 Page of 19
~
NOTIFICATION Revision 4 Date 8/26/83
/.
Approved by: N be - DATE: 9 //2- BS Emergency Plannmf Coordinat.cP.
/
Approved by: k1 L DATE: f- /3 '83
, Operatioryr supervisor Approved by:. 472 44/ [/
%ecurity 1.7 DATE:
pervisor y-4 7-/3-83 Reviewed by: /13, Whw - DATE: AL' ARA Coordinator
/
Reviewed by: _~ e /b" /mnaj DATE: f-77-8.7 Operations! Co:cittee Cnairman Approved by DATE: Plant Superintendent - Nuclear e e
. . j l
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 1.2 l Page 14 of 19 'j NOTIFICATION Revis ion 4 f Date 8/26/83 q l ATTACHMENT 1 ADDITIONAL EVENTS REQUIRING PROMPT NRC NOTIFICATION '
- 1. The exceeding of any Technical Specification safety limit. Open, continuous The DAEC Safety Limits are as identified in Tech. Spec.- path required to
. Sections 1.1.A thru 1.1.0,1.2.1, and 1.2.2 and are intended NRC in Bethesda to establish limits below which the reasonable maintenance of the cladding and primary systems is assured.
- 2. Any event that results in the nuclear power plant not being Open, continuous in_ a controlled or ' expected condition while operating or path required to
- shutdown. NRC in Bethesda
- 3. Any act that threatens the safety of the nuclear power plant Open, continuous or site personnel or the security of special nuclear path required to material, including instances of iabotage or attempted NRC in Bethesda sabotage.
4.- Any event requiring initiation of shutdown of _the nuclear Notification only power plant in accordance with Technical Specification within one (1) hour Limiting Conditions for Operation. to NRC in Bethesda
- 5. Personnel error or procedural inadequacy which during normal Notification only operations, anticipated operational occurences, or accident within one (1) hour conditions, prevents or could prevent, by itself, the to NRC in 3ethesda fulfillment of the safety function.of those structures, systems, .and components important to safety that are needed to (i) shutdown the reactor safely and maintain it in a safe shutdown ccndition _ or (ii) remove residual heat following reactor shutdown or (iii) limit the release of radioactive material to acceptable levels or reduce the potential for such release.
- 6. Any event resulting in manual or automatic actuation of Notification only Engineered Safety Features, including the Reactor Protection within one (1) hour System. Actuation of Engineered Safety Features including to NRC in Bethesda the Reactor Protection System which result from and are part of the-planned sequence during surveillance testing does not constitute an event reportable under this item.
- 7. Any accidental, unplanned, or uncontrolled radioactive Notificaticn oniy release. (Normal or expected releases from maintenance or within one (1) hour other operational activities are not included). to NRC in 3ethesda I
, ,e EMERGENCY PLAN-IMPLEMENTING PROCEDURE EPIP 1.2 Page of l'9 't NOTIFICATION Revision 4 Date 8/26/83 g ATTACHMENT 1(continued) .
ADDITIONAL EVENTS REQUIRING PROMPT NRC NOTIFICATION
- 8. Any f atality or serious injury occurring on the site and Notification only requiring transport to an offsite medical facility for . within one (1). hour treatment. Serious injuury is considered to be any injury to NRC in Bethesda that in the judgement -of tne licensee representative will
-require admission of the injured individual to a hopital for treatment or observation for an extended period of time (greater than 48 hours). Injuries that only require treatment andhr medical _ observation at a hospital or offsite medical f acility, but do not meet the conditions specified above, are not reportable under this item.
- 9. Any serious personnel radioactive contamination requiring Notification only extensive onsite decontamination or outside assistance. within one (1) hour to NRC in Bethesda
- 10. Strikes of operating employees or security guards, or Notification only honoring of picket lines by these employees, within one (1) hour to NRC in Bethesda
- 11. In the event that deviation from Technical Specifications Notification only requirements becomes necessary, reasonable action that within one (1) hour departs from a 1icense condition or Technical Specification to NRC Region III.
in an emergency, when such action is immediately needed to protect the public health and safety, is ' permissible, as specificed in 10CFR50.54(x).
- 12. Any event meeting the criteria of 10CFR20.403 for notification, as follows:
NOTE: > Each of the events defined below shall abo be verbally reported to NRC in Bethesda within one (1) hour, a) Exposure of the whole body of any individual to 25 rems verbal & written or more of radiation; exposure of the skin of the wnole not ification with-body of any individual of 150 rems or more of raciation; in one (1) hour to or exposure of- the feet, ankles, hands, or forearms of NRC Region III any individual to 375 rems or more of radiation; or b) The release of radioactive material in concentrations VerDal & writtan m which, if averaged _over a period of 24 hours, would not ification with-exceed 5,000 times the limits specified for such in one (1) hour to materials in Appendix B, Table II; or NRC Region III
o . EMERGENCY PLAN IMPLEMENTING PROCEDURE' EPIP . 1.2 Page' of 19 N TIFICATION ' Rev is ion 4
~
Date 8/26/83 ATTACHMENT 1(continued)
^
ADDITIONAL EVENTS REOUIRING PROMPT NRC NOTIFICATION c) A loss of one working week or more of the operation of Verbal & written any. facilities affected; :or notification with-in one (1) hour to. NRC Region III. d) Damage to property.in excess of $200,000. Verbal & written notification with-in one (1) hour to
- NRC Region III e) Exposure of the whole body of any individual to 5 rems Verbal & written or more of radiation; exposure of the skin of the whole notification with-body- of any individual to 30 rems or more of radiation; in twenty-four (24) or exposure of the feet, ankles, hands, or forearms to hours .to NRC Region 75 rems or more of radiation; or III-
. f) The release of radioactive material. in concentrations Verbal & written which, if ' averaged over a period of 24 hours, would notification with-exceed 500 times the limits specified for such materials in twenty-four (24) in Appendix B, Table II; or hours to NRC Region III g) A loss of one day or more of the operation of any Verbal & written f acilities affected; or notification with-in twenty-four (24) hours to NRC Region III h) Damage to properly in excess of 52,000. Verbal & written not if ication with-in twenty-four (24) hours to NRC Region ;
III.
~
,. . <s , .s - v,
"' ( ,
EMERGENCY PLAN' IMPLEMENTING PROCEDURE 1.2 h { d EPIP 17- -i c 'Page of 19 - NOTIFICATION Rehsion '4 ,
., Date 8/26/83 ,
3 3- s ATTACHMENT 2 , INITIAL NOTIFICATION MESSAGE
- Date/ Time Operations Shift Supervisor
- 1) This is- calling from the Duane Arnold Energy Center.
Caller's name & title *
.2) . An event has occured which is classified as a:
'a) Notification of Unusual Event, a Type A- '
' event.
b) Alert,.a Type B- event. , c)'. Site Emergency, a Type C- event'. 3_ d) General Emergency, a Type D- event. N
- 3) Abnormal radiological releases ARE/ARE~ NOT occuring. , @
-- If occuring:
a) The wind is out of the- . The population of concern is located in area (s) .
.4) Protective measures for the public ARE/ARE NOT recommended. s.
-- If-protective measures are required as a result of performing dose-projections in 'accordance with EPIP 3.3, provide protection action recommendations. .
6). Off-site radiological monitoring IS/;S NOT planned.-
-- If planned: -
a) Emergency Monitoring Teams are being/have been djspatched- ,
, q (l - 6) Direct assistance at DAEC by your agency IS/IS NOT requested. .,
-- If assistance is desired, explain: T
^
L s s
**************************************w****************************w***ww***wwww*
* 'N0TE: *
- riotifications to Off-Site Agencies must be made witnin 15 minutes of *
- declaration of an Emergency Action Level (EAL).
***********wt***********ww**w***************w*****w*ww*********w*ww**w*******www Received by: Linn County Time Benton County Time s f
! Office of Disaster' i Services- Time Initial Notifications Conducted by - l Forward this attachment to Operations Supervisor. / g
--. ,,.~_.-,.- . .. . . _ - _ . _ __ _ , S _ a m - . . . , .fi , _ _ _ ,_ _,
e . EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP- 1.2 18 Page of 19 .. NOTIFICATION Revision a Date 8/26/83 ATTACHMENT 3
~
EMERGENCY RESPONSE ORGANIZATION NOTIFICATION MESSAGE. This is calling -from the DAEC. calier's name ana joo position
- s. (' has occured at An event' classified as an .
i ALERT / SITE EMERGENCY / GENERAL EMERGENCY the DAEC.: 3 A release in progress and heading towards
-15/15 NOT Applicable Town, as Appropriate.
.Use access to the site.
NORMAL / ALTERNATE NOTE: If alternate access routes should be followed, identify the routes to be used or identify areas or sectors to be avoided, 4 t l- Be prepared to provide identification to local law enforcement officials, t Report to the site and assume your assigned emergency response duties, f Please drive cautiously and do not take any unnecessary risks. l q z< s e,
-{
s '.g-f L% . .f
~
,/
,a
.e' o ., .s f /
EMERGERNPLANIMPLENENTING' PROCEDURE EPIP 1.2
- 19 ' '
, ...."' , Page of 19
')
/ NOTIFICATION Revis ion 4 t-
/ !
Date 8/25/83 t I ATTACHMENT 4 . NOTIFICATION LOG , CONTACT MADE NAME EMERGENCY RESPONSE POSITION TIME CALLED YES- N0 t t
?
J I A p
.9-
' r r
=
l 3
- M 6
t' t l t c ? r s N
/ i fg '
) Q ,y, A, .
$ ') ., .a a f. 4^
\ } , .
s , I f) ' ; l , - r " f
+
, !g- r i s'
/
e , Comunicator F J
.*,. s
,,e > - -- -,,e,y eE-+r.--,-,,,-.,-, , , - - . ,,,~yr,.ry,.---,w,r-#,,%,_m,-,w-e,- w ,w,v ,ey,-,+---w w ry,-#w---..w. -~+v- ,e
o o.
~
EMERGENCY PLAN IMPLEMENTING PROCEDURE- EPIP 2.1 ; Page - 1 of-57 -- ;
~
ACTIVATION AND OPERATION OF THE OPERATIONAL- Revision 3 SUPPORT CENTER.(OSC) . 0 ate 8/8/83
?
-1.0 PURPOSE ,
.<=
i This procedure -provides guidance associated .with activation and operation of the Operational Support Center (OSC).
'2.0 ' APPLICABILITY .
-2.1 This procedure 'is applicable to the' 0SC Supervisor, Security Shift
. Supervisor, and DAEC personnel assigned response functions by the Emergency Assignment' Tag Board or who assemble in the OSC'for functional assignments .
which may-be required during an energency.
-* - 2.2 This procedure shall be implemented for all events classified as an ALERT or '
greater and may, at the discretion of the Emergency Coordinator, be ' implemented for an event classified as a NOTIFICATION OF UNUSUAL EVENT.
- 3.0 RESPONSIB'ILITIES
~ 3.1 OSC Supervisor 3.1.1 Supervise the administration of the Emergency Assignment Tag Board 1 and implementation of functions thus assigned which are conducted from the OSC.
4 / 3.1.2 Provide overall ' supervision of personnel who assemble in the OSC, and coordinate. response functions to be provided with key supervisory personnel. located in the TSC, Control Room and off-site including the Off-Site Relocation and Assembly Area (0RAA) Off-Site Radiological Laboratory (0RAL) and.0ff-Site Decontamination Facility (00EF). k 3.1.3 Provide direct supervision for rescue and f decontamination activities - and.all radiological monitoring activities conducted .in the plant.
- 3.1.4 Coordinate, as required, with key supervisory personnel to ensure satisfactory 'perfonnance of repair, first aid and medical support functions, and radiological monitoring of the on and off site
- environs.
. 3.2 Site Radiation Protection Coordinator 3.2.1 Provide technical direction for radiological response functions conducted by personnel assigned in the OSC. 3.2.2 Ensure that'information regarding plant status and response functions either ongoing .or planned is provided to. the OSC Supervisor. . ~ 4 e a e
* *7 r 5r .a ...,yy - p - - ., q,y_.,_, y ,',g pq, ,7, 7,. g 9 , , , . . , , , . , , _
.=. - - - , . - .
.- i
-EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 2 of 57
~ ACTIVATION AND' OPERATION OF THE OPERATIONAL Revision 3 SUPPORT CENTER (OSC) Date 8/8/83 3.3 Security Shift Supervisor 3.3.1 Coordinate with the OSC Supervisor. to provide first aid personnel for rescue activities and reported injuries, and to coordinate the application of off-site medical support and assistance..
13.3.2 ' Coordinate with the OSC Supervisor to insure that emergency response functions are not i:'ipeded by. routine security practices, and provide direction to Security Force pdrsonnel associated with waivers of standard security requirements which are authorized. 4.0 INSTRUCTIONS e 4.1 Initial Activation and Staffing 4.1.1 Upon annunciation of the Evacuation Alarm, required for events classified as an ALERT or greater, as prescribed in EPIP.1.3, " Plant and Site Evacuation", the following actions should be taken to initially activate and staff the OSC during normal working hours, a) All DAEC assigned personnel other than those designated to report to the Control Room and TSC snall report to the OSC. NOTE
- 1) As prescribed in EPIP 1.3, all contract personnel 'on site except those assigned to specific DAEC departments or those who are designated to report to the TSC or SCP, shall. report to the Construction Support Canter.
- 2) All visitors shall be escorted to the SCP.
b) If the nature of the emergency'is a fire and the Fire Alam has also been' sounded, the Fire Brigade shall assemble and initiate action to extinguish the fire as prescribed in the DAEC Fire Plan, c) The lines of communication between the Fire Brigade and the Emergency Response Organization shall be as follows:
- 1) The Fire Brigade Leader should receive technical direction from the Control Room and should maintain communications with the Control Room throughout the fire incident.
- 2) The Fire Brigade Leader.shall assure'that the OSC Supervisor is kept informed of the status .and location of the fire so that he can provide assistance to the Fire Brigade as necessary.
- 3) The Health Physics Technjcian should estaolish communications with the OSC Supervisor informing him of the radiological conditions in the area of the fire.
o b EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 3 .of 57 . . . ACTIVATION AND OPERATION OF.THE OPERATI0'NAL Revisien 3 SUPPORT CENTER (OSC). Date 8/8/83, d) In the event that a fire develops during a declared emergency, the Fire Brigade shall be' briefed by the Site Radiation Protection Coordinator on radiological conditions and also shall be briefed in accordance with the OAEC Fire Plan. - e) If exiting the. Power Block Structure, normal egress procedures should be followed at the Health Physics Access Control Area unless directed otherwise by Health Physics. personnel assigned there. NOTE
. During a plant evacuation, the On-Shift Access Control Foreman should remain at the Health Physics Access Control Area until relieved by a Health Physics Technician assigned by the Emergency Assignment Tag Board.
f) Upon arrival in the OSC, personnel should proceed to the Emergency Assignment Tag Board located as shown in Attachment 1, "0SC Layout", and based upon their individual job classifications, remove tags from the Tag Board in numerical sequence, as further discussed in paragraph 4.3. g) Upon observing or. being advised that al'1 of the tags have been removed, personnel should proceed to the Locker Area and provide assistance, as requested, in establishing- accountability for all personnel who assemble there, as prescribed in EPIP 1.3. h) Additionally, all personnel who assemole in the OSC shall complete a copy of Attachment 2, " Personal Statement Concerning Incident" and return the form to designated Health Physics personnel-at the Health Physics Access Control Area.
.4.1.2 Upon annunciation of the Evacuation Alarm during off-normal hours:
a) Cal 1~ out of selected DAEC assigned personnel .shall be conducted
. as prescribed in EPIP 1.2, " Notification".
b) Personnel who normally would not be called out to augment on-shift staffing but who are on site, should proceed to their assigned assembly locations. c) As personnel arrive on site, they should proceed to their i assigned emergency resoonse center or to the Emergency Assignment Tag Board, as applicable, d) Based upon their individual job classifications, tags .hould be removed from the Tag Board in numerical sequence, as discussed in paragraph 4.3.
~
. a
. El .
4 , EMERGENCY PLAN IMPLEMENTING-PROCEDURE EPIP 2.1
~
Page 4 of 57
~ ACTIVATION"AND OPERATION OF.THE OPERATIONAL' Revision 3 -
SUPPORT CENTER (OSC) Date 8/8/83 o NOTE
- The~ Dosimetry personnel should report to the Site Radiation -
' Protection Supervisor. 'Their function will be to-issue dosimeters, TLDs, and badges to incoming personnel who are
' ' not badged and to obtain exposure records from incoming personnel. >
4.1.3 - The OSC Supervisor should report to'the Security Control Point (SCP) to supervise the activities at the Emergency Assignment Tag Board and-to provide supervision over 'all activities being accomplished in the OSC.
-a). The Health Physics Supervisor should assume the position.of OSC
- = Supervisor, if available, b) If not available, the first alternate listed in the Emergency Telephone Book who is available should assume responsibility as 3-the OSC Supervisor.
't c) A checklist is available for use by the OSC Supervisor and'is - included as Attachment 3, "0SC Supervisor Checklist". 4.1.4- If trained personnel are available, an Assistant OSC Supervisor should be assigned in the OSC,. generally in the Emergency Locker Area
- and TSC, to provide assistance in supervising personnel who ' assemble in the OSC and support activities conducted from that location.
l. a) Normally the Assistant.05C Supervisor should be the first alternate for the OSC Supervisor's position as listed in the Emergency Telephone Book. !- b) If the first alternate is functioning as the OSC' Supervisor, or-is otherwise unavailable, the next alternate who is-available should assume this responsibility. 4.1.5 The OSC Supervisor may elect to appoint. qualified Health Physics personnel to assist in supervising the performance of one or more - critical initial functions to aid in ensuring their correct
. performance.
p . 4.1.6 .The OSC Supervisor shall insure that a record is maintained of pertinent activities which occur in the OSC.- a) This information should be recorded on Attachment 4 "0SC Log Sheet", by the on-shif t Rad Waste Operator' assigned as the OSC Communicator by the Emergency Assignment Tag Board, or by other personnel _ assigned at the discretion of the OSC Supervisor.
~
, .9-1
, . ). ,, w .., w o., - .. . - - . . , . . 4 .p, v -,-,% ,.-w,- ,#.,..m - .,- .-~4,+v.w... -,v%, .- - .,m. , , 4 -,#- e, ,.-.-.*,,-wy,---+e ----,y
'e O EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 P age 5 .of 57 ..
ACTIVATION AND OPERATION OF THE OPERATIONAL . Revision 3 SUPPORT CENTER (OSC) Date 8/8/83 NOTE During off-normal working hours, the on-shift Rad Waste Operator may be required to initiate post-accident sampling activities as prescribed in PASAP 2.0, " Post-Accident Sampling System", if directed to do so by the Operations Shift Supervisor. Upon being relieved of this function by a Chemistry Technician, the Rad Waste Operator should assume his responsibilities as the OSC Communicator, b) Topics to be recorded in the OSC Log are identified on Attachment 5, " Recommended Log Entry Topics". o 4.2 Initial Functional Activities 4.2.1 The Security Shift Supervisor shall initiate activities to establish accountabi}ity for all' personnel on site within the Protected Area. NOTE A checklist is available for use by the Security Shift Supervisor and is included as Attachment 6, " Security Shift Supervisor Checklist". a) Accountability of all such personnel shall be established as prescribed in EPIP 1.3, " Plant and Site Evacuation". b) Security Force personnel should conduct accountability for all personnel who assemble in the OSC. NOTE As necessary,. the OSC Supervisor should designate personnel with no other assigned duties to assist Security Force l members in conducting personnel accountability. L c) If personnel are determined to be missing, rescue activities should be conducted as prescribed in EPIP 4.3, " Rescue and Emergency Repair Work". 4.2.2 A Security Force member shall be dispatched to unlock the Emergency l Response Team Lockers, and then proceed to the TSC to perform I functions required to initially activate the TSC as identified on EPIP 2.2, " Activation and Operation of the Technical Support Center". NOTE A duplicate set of keys for the Emergency Team Lockers is maintained in the Secondary Alarm Station (SAS). l
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 6 of 57 ACTIVATION AND OPERATION OF THE OPERATIONAL- -Revision 3 SUPPORT CENTER (OSC). Date 8/8/83
'4.2.3 - If during non-normal working hours the Evacuation Alarm is sounded, a Security Force member shall be dispatched to the Control Room to i- obtain the Emergency Response Organization Notification Message.
a) The message form shall be provided to the Security Shift Supervisor for use by Security Force personnel to call out the DAEC Emergency Response Organization. . b) Call out1of the DAEC Emergency Response Organization shall. be conducted as prescribed in EPIP 1.2, " Notification", using
' telephone numbers provided in the Emergency Telephone. Book.
. 4.2.4 The Assistant OSC Supervisor should proceed to the TSC to be briefed by the Site Radiation Protection Coordinator.
a) Briefing topics which should be discussed are identified in Attachment 7, " Recommended OSC Briefing Topics". b) The Assistant OSC Supervisor- should review this information with the OSC Supervisor. 4.2.5 The Personal Statement'Concerning Incident forms shall be reviewed as directed by the OSC Supervisor, a) If unexpected or unusual responses are discovered, the individual should be contacted in an effort. to obtain additional information
- or details, as appropriate, b) The OSC Su'pervisor. shall be informed of any unexpected or unusual responses and shall so advise the Site Radiation Protection Coordinator-and, if pertinent, the Security Shift Supervisor.
4.2.6 The OSC Supervisor should establish communications with the TSC and advise the Site Radiation Protection Coordinator when the OSC is fully staffed and ready to perform necessary support functions. NOTE
- 1. The OSC Communicator should initiate communication checks with the TSC, Access Control, Security Control Point,- and Control Roca as directed by the OSC Supervisor.
2.. The primary communications line between these facilities is the dedicated direct ring. telephone. Alternate methods of comunications include:
- 1. .' Normal telephones
- 2. Security / Radiological Radio
- 3. Operations Radio
- 4. Intercom
- 5. Plant Page
- 6. Runners o
-o o
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page. 7 .of 57 .. . ACTIVATION AND OPERATION OF THE '0PERATIONAL Revision 3 SUPPORT CENTER (OSC) Date 8/8/83 4.3 Administration of the Emergency Assignment Tag Board
~
( 4.3.1 Staffing of support positions via the Emergency Assignment Tag Board-will be supervised by the OSC Supervisor and should normally proceed in the following manner: a) Personnel should select in numerical sequence the color coded
~ tags appropriate for their individual job classifications.
NOTE
- 1. Color-coding for tag assignments is as follows:
Pink - Health Physics Technicians Orange - Radwaste Operators Red - Rad / Chem Technicians Green - Staff Blue - Instrument Technicians Purple . Electricians Yellow - Mechanic Black --Technical Engineers White - Shift Tecnnical. Advisors
- 2. Staff personnel are those members of the permanent DAEC Staff (exclusive of plant management and the clerical support staff) that upon arriving at the Emergency Assignment Tag Board find their supply of color codsd tags exhausted.
b) Personnel removing tags should print their name and badge number on the Emergency Assignment Tag Board above the tag removed to facilitate simultaneous accountability and preparation of support teams. NOTE All personnel will find on the back of each tag a list of equipment required to perform the work associated with each tag, c) Af ter removal of the tag, personnel should complete the instructions on their tags. NOTE
- 1. A description of the duties and actions identified on each of the tags is included as Attachment 8, " Emergency Assignment Tag Board Duties".
o'
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 8- of 57 LACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 SUPPORT CENTER (OSC) Date 8/8/83
- 2. Personnel requiring self contained breathing apparatus for performance of activities in the Power Block Structure should obtain them from the Health Physics Access Control Area. Personnel requiring such equipment-for activities to be conducted in clean areas of the site or for use off-site should obtain such equipment as directed by the OSC Supervisor.
4.3.2 The OSC Supervisor should be advised following completion of all tasks described on the individual tags. NOTE e The OSC Supervisor may re-assign Tag 30ard duties to be completed by Health Physics Technicians such that the maximum , utilization of available resources is obtained. 4.3.3 Upon arrival of the Health Physics Technician assigned by the Emergency Assignment Tag Board at the Health Physics Access Control Area: a) The Access Control Foreman should proceed to the Emergency Assignment Tag Board, unless previously advised by the OSC Supervisor to remain at Access Control. b) If all of the tags for Health Physics Technicians have been pulled, he should advise the OSC Supervisor of his availability and await further instructions. 4.4 Operation of the OSC 4.4.1 The OSC Supervisor shall maintain responsibility over all personnel in the OSC, including the Construction Suoport Center, a) If due to habitability considerations, evacuation of assembly areas or the TSC is required, personnel shall be relocated as specified in EPIP 3.1, "On-Site Radiological Monitoring". b) If evacuation to the ORAA is required, evacuation shall be accomplished as prescribed in EPIP 1.3, " Plant and Site Evacuation", and EPIP 2.4, " Activation and Operation of the ORAA". NOTE Evacuation of all non-essential personnel from the site is required for events classified as a SITE or GENERAL EMERGENCY. 4.4.2 Activities conducted in support of plant operations by personnel assigned to the OSC shall be coordinated through the OSC Supervisor.
~
~
, o EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 9 .of 57- .
ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 SUPPORT CENTER (OSC) Date 8/8/83 a) On-Site Radiological Monitoring shall be accomplished in accordance with EPIP 3.1, "On-Site Radiological Monitoring". b) Off-Site Radiological Monitoring shall be accomplished in
.accordance with EPIP 3.2, "Off-Site Radiological Monitoring".
c)_ Rescue and repair activities shall be accomplished in accordance with EPIP 4.3, " Rescue and Emergency Repair Work". NOTE
- 1. First aid _ personnel shall be assigned by the Security
- Shift Supervisor as requested by the OSC Supervisor.
- 2. Protective clothing and respiratory protection equipment for such personnel shall be obtained at the Health Physics Access Control Area.
d) First aid decontamination and medical support activities shall be accomplished in accordance with EPIP 4.2, "First Aid, Decontamination and Medical Support". e) Activities of the Fire Brigade shall be accomplished in accordance with the DAEC Fire Plan, and the lines of communication with tne Emergency Response Organization during an emergency, should be as instructed in Steps 4.1.1.c and 4.1.1.d. 4.4.3 The Site Radiation Protection Coordinator should consult with the Radiological Assessment Coordinator in the EOF with respect to activating the Off-Site Radiological Laboratory (ORAL). a) The ORAL should be activated if significant off-site releases are detected, i b) If activation of the ORAL is desired, the Site Radiation Protection Coordinator should initiate activation of the Off-Site Radiological Laboratory in accordance witn EPIP 2.6, " Activation and Operation of the Off-Site Radiological Laboratory". NOTE As a minimum, the ORAL should be activated for events classified as a SITE or GENERAL EMERGENCY. 4.4.4 The OSC Supervisor shall not dispatch personnel into a radiological hazard area until the Emergency Coordinator's authorization has been given. 4.4.5 Prior to allowing tag board personnel to leave the OSC, the OSC Supervisor should ensure the following: S-u
EMERGENCY' PLAN IMPLEMENTING PR0'CEDURE EPIP 2.1 - Page 10 of 57
' ~
ACTIVATION AND-0PERATION OF _ THE OPERATIONAL Revision 3' SUPPORTCENTER(OSC) _Date -8/8/83-a) -Personnel have been br.iefed on. plant conditions, radiological-considerationsLand' precautions, stay times,-access routes, communications requirements,' objectives of the activity, etc. ri' b) ? Personnel have been properly l dressed in. protective clothing and
.have. adequate _ dosimetry and respiratory protection equipment.
i- 4.4.6 : During the performance of their tag assignments personnel shall be L. responsible for. maintaining their own' personal exposures as low .as reasonably. achievable (ALARA) .to the extent _ that it is consistent with accomplishing their . assigned duties.
~
+ '4.4.7 Upon their return to the 0SC, tag board personnel should contact
- the OSC Supervisor, for instructions on how to minimize the spread of contamination, i
.e
- 14.4.8 The OSC Supervisor should insure that persoanel assembled in--the OSC are periodically- appraised of the event status, problems, and actions being taken to restore the-plant to a safe condition.
14.4.9 Where response actions are expected to be required over a long period of- time, the OSC Supervisor shall: i a) Evaluate Health Physics staffing needs and establish a rotating
. work schedule to assure adequate coverage.
b). Identify;the need for and recommend to the Site Radi,ation Protection Coordinator additional Health Physics staff support capabilities and services which should be obtained. b - c) Coordinate, as required, with the Security and Support. Supervisor-
= to -assure that provisions. have been made for continuous coverage fo'r all Emergency Assignment Tag Soard positions, where L . requi red.
4.4.10; 'As plant conditions begin to . stabilize and reclassification of the - emergency to a lower classification is being conducted, the OSC Supervisor shall assist, as requested, in developing a recovery
- plan.
I a)' Recovery planning shall be accomplished as specified in EPIP 5.2,
" Recovery and Reentry".
b) Details regarding use of the OSC as a staging area for reentry and- recovery activities as well as criteria for deactivation of'
. personnel in the OSC, in part or in whole, shall be specified as
- - part of the recovery plan.
e
.1
e e o EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 11 of-57 - - ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3. SUPPORT CENTER (OSC) Date 8/8/83 NOTE , The usefulness of the OSC for recovery efforts may be limited initially due to the radiological consequences of the event. If this is the case, consideration should be given to using the ORAA as a staging area in lieu of the OSC. c) Deactivation of the OSC shall be accomplished upon authorization of the Site Radiation Protection Coordinator and shall coroly with the applicable requirements prescribed in EPIP 5.1,
" Deactivation of the Emergency Response Organization".
5.0 REFERENCES
5.1 DAEC Emergency Plan 5.2 NUREG 0654, Rev. 1 6.0 ATTACHMENTS 6.1 OSC Layout 6.2 Personal Statement Concerning Incident 6.3 OSC Supervisor Checklist 6.4 OSC Log Sheet 6.5 Recommended Log Entry Topics 6.6 Security Shift Supervisor Checklist 6.7 Recommended OSC Briefing Topics 6.8 Emergency Assignment Tag Board Duties w S
. _ . . ,_ --- .- .-.._ --- . ~_.
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 12 of 57 ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 '? SUPPORT CENTER (OSC) Date 8/8/83 Approved by: /* Date: T!879.3 "EmWgenc'y ? TT e r nefor < Approved by: \ \ Date: 9 (14 ( M Healtn Pnysics Supervisor Approved by: Irl, [>zet4 Date: 4"/ O Ra'ci ation P ectioW Supervisor Reviewed by: t. N hte Date: 9 - t 7 - ?' 3 ALARA Coordinator Q Reviewed by:
/
Operations ~Co~mmittee Chairman Date: 4 87-83 Approved by: \ Date: 9'19-83 Plant Superintencent-Nuclear i b
m M E 9 o< u g .4
.- rmM N E* y S s s m m-uu "."
n ogm
- C o?uw '. .
Ndy1gz - g* %mxhE* % g m eag45s -
- mg o" "
u%moQ nENW ox- oga m53w 4$9m= " . o$ raa5, f R E , T T R N Y E R O C EM P TO P TO U AR S B [ e 3 L h O SR ST EN CO CC A R O T t A V m D E L E Ay / / T j S N SE E M D i ICC l I I TSF PE A LVF IUG M Ai Cl QA TO S EP ER M O l l E O O RR I _. R T IS 1 O F
/
- F R w TD NR E R K YEA - C MO / C O N4B l L Et G GIG l RSA N O EST MA # l E l I' R S CRE YE R UOI CS E RPN ll K TP E llMC E0 SU C Y OL GPAO _ iS t o T H T ~ . i RSEL _ C IR1 Hl 4 i eel MR Ut o E COP i EC L _ S lOl0 Y T ~ _ I R ~ U C O E S ' i i '- i ' ; j
e e EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 14 of 57 i ACTIVATION AND OPERATION OF THE OPERATIONAL' Revision 3 ; 1 SUPPORT CENTER (OSC) Date 8/8/83 ATTACHMENT 2 PERSONAL STATEMENT CONCERNING INCIDENT TLD Number Name Badge Number Date of Incident Time of Incident
-Supervisor Department
- What is your affiliation? -
Where were you when notified of the incident? Building Room Please draw a map on-tha reverse side of this page and locate yourself on it with an (X).
.How did you recognize or how were you informed of the incident?
Did you run.or walk? Show route of exit on map. What action did you take at the time of the incident if you did not leave immediately? If so, how much time was involved? At the time.of the incident were you wearing a TLD badge? Yes No Dosimeter? Yes No Time What location on your body were they worn? (i.e., left shirt pocket, rignt side of belt, etc.) Did you see, hear, feel, or smell anything unusual? Yes No If.yes, please describe. } List workers who were in- your area at the time of the incident. Other comments pertaining to the incident: signature Date Time
.V ,
1
, o EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 15 of 57 ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 SUPPORT CENTER (OSC) Date -8/8/83 ATTACHMENT 3 .
OSC SUPERVISOR CHECKLIST , The-following checklist is.available'for use by the OSC Superyisor or. another , individual, so designated, as an . aid in ensuring that emergency response actions are . completed. . In the column labeled " Time", the actual time that sucn items are completed may be recorded. Alternatively, checks may e used or other appropriate notations may , be substituted which will be of assistance to the user.
. TIME ITEM
'l. During normal working hours, assure that an . individual has assumed the position as an " Assistant OSC Supervisor.
- 2. Assign experienced Health Physics personnel to supervise and/or assist others performing selected functions.
. 3. Provide assistance, ~ as requested by the Security Shift Supervisor, to obtain initial accountability for all personnel within the Protected Area. 4.- Assure that an individual is assigned as the OSC Communicator, tnat communications is established with the-TSC and that the OSC Log is ' initiated.
- 5. Direct.0SC Communicator to perform communications check with.TSC, Access Control, Security ~ Control Point and Control Room.
- 6. Supervise administration of the Emergency Assignment Tag Board; reassign personnel, as appropriate, to maximize skills; and provide guidance, where necessary, associated with implementation of assigned
' duties.
- 7. Record nanes of personnel assigned Tag Board functions on the '
attached form, " Operational Support Assignments", if desired, and insure inventory instrument checks and zeroing of dosimeters are accomplished.
- 8. Determine if an on-site radiological . problem exists, and provide direction to personnel who need to exit the building to perform required functions.
- 9. Insure action is initiated to determine the habitability of assembly areas including:
a) Health Physics Access Control Area b) OSC Locker Room c) Emergency Assignment Tag Board / Emergency _ Locker Area _
. ~ . . ._ .-_, - _ _---.--.. .. , , . . - . . , - _ - . _ . . . , . . ~ _ . . , , . . . _ , . , _ . -
EMERGENCY PLAN IMPLEMENTING PROCEDURE _ EPIP. 2.1 Page 16 of 57 Revision 3
' ACTIVATION AND OPERATION OF 'THE OPERATIONAL SUPPORT CENTER (OSC) Date 8/8/83 ATTACHMENT 3 (Continued)
OSCSUPERVISORCHECKLISl TIME ITEM d) Security. Control Point (SCP) e) Construction Support Center
. f)' Technical Support Center g) Hot Lab h) Control Room
- 10. ' Assure that Personal Statement Concerning Incident forms are reviewed, evaluate the results of the review and comunicate areas of concern to the Site Radiation Protection Coordinator 'and/or Security Shift Supervisor, as appropriate.
- 11. Coordinate, as required, with the Assistant OSC Supervisor and Site ,
Radiation Protection Coordinator to obtain information regarding plant status, problems, response options, significant radiological releases in progress, off-site dose rates, plume location and meteorological conditions.
- 12. Conduct ready tobriefing for On andand be dispatched Off-Site Teams,Radiationverify advise the Site that Teams are orotection Coordinator of such readiness.
- 13. Coordinate with the Security Shift Supervisor to obtain qualified first aid personnel for rescue activities and medical emergencies.
- 14. Supervise efforts required to prepare injured / contaminated victims for transport to off-site medical f acilities and assign Health -
. Physics personnel, as required, to accompany such victims to off-site facilities.
- 15. Provide assistance, as requested, by the Technical and Engineering Supervisor- to fann repair teams and assure t tat personnel, so assigned, are properly clothed, have the required dosimetry and the required equipment and supplies, including respiratory protection equipment, s
- , s EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 17 of.57 .
ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 l SUPPORT. CENTER (OSC) Date 8/8/83 ATTACHMENT 3 (Continued) . OSC SUPERVISOR CHECXLIST TIME ITEM -
- 16. Dispatch emergency repair team following conduct of a briefing and receipt of authorization,
- 17. Review the results of radiological monitoring activities and advise e the Site Radiation Protection Coordinator of problems discovered, i unexpected results, etc.
- 18. Coordinate with the' Site Radiation Protection Coordinator and dispatch personnel, as directed, to perform post-accident sampling.
- 19. Coordinate with the ORAA Supervisor and assign 2 Health Physics -
Technicians to activate the ORAA and assist in evacuating personnel.
- 20. Coordinate with the Security Shift Supervisor and ORAA Supervisor for evacuation of personnel fron the site.
- 21. Ensure that personnel assembled in the OSC are appraised of the emergency classification, plant problems, response actions being taken, and the like.
I
- 22. Identify technical assistance and services required to support ongoing radiological monitoring activities and advise the Site Radiation Protection Coordinator of such needs.
l 23. Coordinate with the Security and Support Supervisor to assure that L personnel are scheduled, as raquired, to staff the positions identified on the Emergency Assignment Tag Board. {
- 24. Reschedule' Health Physics Technicians to provide continuous coverage.
- 25. Supervise deactivation of the OSC and assure that emergency equipment
=and supplies are. returned to their proper location, are inventoried, and tool boxes resealed / lockers locked.
- 26. Insure all documentation is collected and provided to the Records Clerk in the TSC.
l / i OSC Supervisor Time / Date l v - a- + ,-e - , ,,..w. , -4 ,-.- r-. , . r.,-,,-- ,-g- r , ,,-,--ewr- y - - , -.v. - , ne-- - -y
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2e1 Page 18 of 57 ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 - SUPPORTCENTER'(OSC) Date 8/8/83 ATTACHMENT 3 (Continued) OSC SUPERVISOR CHECKLIST g OPERATIONAL SUPPORT ASSIGNMENTS OPERAflomAL SLPPORT AS$lGhemf5 JSC SUPERVISOR garg
- ALTERNATE O
Pim i Piset 2 Pim ) Plant 4 PIM S PINK 4 PDen i cloat 6 CRANGE I mA4 & CARO # In-es sat i e-pl ant Assames y Area Personae 6 Rescue & Emer. scattor Emer. aeastor Emer, mens tar - OSC Surve y Surve y Surve w. . Maniterlag Emergenc y Team (Onsites fees I (Ottsite toen 2 (Ottsiten Commescater & Maes tselli t y Resear Leeser Leaeor Leeeer Cata Recoreer
+ ~~
Tid ,- - s, , , 1 i ; , 011P4700 l l fia i l I 6 J q. -- q 's ( . ( RED I RED 2 3 Lug i TELLos i Pufett 1 PURPLE 2 GREEN I GREEN 2 GREDs 3 mA4 & CAa0 s 5emele Count Samoso Cowar Emer. Rosale Emer. Aeoeer Emer. Roself Emer. aseeir Emer, een e for Emer eenster Emer, neas tor - 4 Cnemacas & Cnemecat Instr.smaats amenanicas Electrical Electrica6 fees tonsitet fees I totesitet teen 2 (Of f. Anal ysis Ana6 vses w museer sites meaner 71 4
. HEAct -
Da5PATOs f14 8 LACK I ' 8 LACK 2 SLACK 3 e6LACA 4 SLACK $ OLACK 6 8 LACK f SLACA 8 **ITE 1 eelft 2 seAd & CAAD i Contres Room Rae t alogical Tsc TSC TSC f5C isc isc Tecnnicas fecnascal Comnwicator Data Commuas cator Commwicator Cosenwicefor Comme s cator connescator casununicator Aaviser Advisor if 4
*EAct j ul5PafCM -
fl4
~
l l i
, o EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 19_ of 57 .-
ACTIVATION AND OPERATION OF THE OPERATIONAL . Revision 3 , SUPPORT CENTER (OSC) Date 8/8/83 ATTACHMENT 4 ~
! OSC LOG SHEET Page of DATE
-OSC Supervisor Ass't. OSC Supervisor Recorded By TIME- NOTES / COMMENTS mmmuy
?
l l 9.
o . EMERGENCY PLAN IMPLEMENTING PROCEDURE- EPIP 2.1 Page 20 of 57 ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 SUPPORT CENTER (OSC) Date 8/8/83 ATTACHMENT 5 RECOMMENDED LOG ENTRY TOPICS
- 1. Activation of the OSC. [
, 2. Results of accountability activities and personnel for whom accountability can not be established.
'3. Significant plant status information and event classification /re-classification, e 4. Results of radiological monitoring activities conducted to determine / assure habitability of assembly areas or in support of rescue and repair activities.
- 5. - Conduct of briefings and dispatch of On and Off-Site Radiological Monitoring Teams / dispatch of Rescue or Emergency Repair Teams into the plant.
- 6. Circumstances associated with evacuation of assembly areas or the site and set-up/ activation of the ORAA.
- 7. Requests for support from the TSC or Control Room.
- 8. Performance of post-accident sampling and analyses activities.
- 9. Pertinent comments made by and problems discovered by personnel dispatched into the plant upon their return.
~10. Other information, observations, etc. pertinent to OSC activities; radiological.
considerations; monitoring, sanpling and analyses efforts; security concerns; and management decisions which may be important from a historical perspective. NOTE Radiological survey and analyses results documented, in accordance with standard practices or as specifidd in the EPIPs on the forms provided, need not be reproduced in the OSC Log. g O
EMERcENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 21 of 57 - ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 SUPPORT CENTER (OSC) Date 8/8/83 ATTACHMENT 6 , SECURITY SHIFT SUPERVISOR CHECKLIST
. The following checklist is available for use by the Security Shift Supervisor or another individual, so designated, as an aid in ensuring that "energeacy response actions are completed. In the column labeled " Time", the actual time that such items are completed may be recorded. Alternatively, checks may be used or other appropriate notations may be substituted which will be of assistance to the user.
TIME ITEM e
- 1. If during non-normal working hours:
a) Dispatch a Security Force member to the Control Roon to obtain the Emergency Response Organization Notification Message, b) Assign two individuals as communicators, c) Provide a copy of Notification List 2 to one communicator and a copy of Notification List 3 to the other communicator. d) Provide assistance, as required, in calling out/ notifying personnel identified on each list as prescribed in EPIP 1.2,
" Notification".
e) Upon completion of the notification process, advise the Emergency Coordinator and OSC Supervisor. NOTE If the nature of the emergency requires impleinentation of the Security Contingency Plan, advise the Operations Shift i Supervisor that Security Force personnel are not available to conduct such notifications.
- 2. Check with OSC Supervisor as to plant radiological status before dispatching a Security Force member with an access authorization list to the site boundary to control access to the DAEC.
- 3. Dispatch a Security Force member to perform the following:
a) Unlock the Emergency Lockers adjacent to the Emergency Assignment Tag Board. b) Unlock the TSC. c) Unlock the TSC Communications Roon y .
a . EMERGENCY PLAN IMPLEMENTING PROCEDURE- EPIP ~2.1
.Page' 22 of 57
~'
ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 SUPPORT CENTER (OSC) Date' 8/8/83 ATTACHMENT--6 (Continued)' SECURITY SHIFT SUPERVISOR CHECKLIST
- l. .
TIME ITEM d) Unlock the TSC Emergency Locker. , e) Initiate the TSC HVAC Systen.
.- 4. Prepare'to issue- the fdllowing items to personnel ' assigned by the Emergency Assignment Tag Board:
f-a) _2 Security / Radiological Survey porta-mobile radios with magnetic base antenna-b) 4 Operations radios c) Keys for 3 veh'icles d) The key for the gas pump
- 5. Call out additional Security Force personnel, as required.
- 6. Coordinate with the OSC- Supervisor and assign pers'onnel, as required, to conduct accountability at. the:
a) Emergency Assignment Tag Board b) OSC Locker Room / Health Physics Access Control area c) Construction Support Center
- 7. Dispatch a Security Force member to tour the buildings outside the
' Protected Area and site property area and direct or escort L individuals found to the Security Control Point (SCP). l 8. Conduct initial accountability' for all personnel as prescribed in l
.EPIP 1.3, " Plant and Site Evacuation", within the Protected Area, E and report results to the OSC Supervisor and Security and Support Supervisor. ,
- 9. Authorize deviations from standard Security practices, as appropriate, to promotefrapid response by Emergency Response Organization personnel.
~
v s EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 23 of-57 - - ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 SUPPORT CENTER (OSC) Date 8/8/83 ATTACHMENT 6 (Continued) SECURITY SHIFT SUPERVISOR CHECKLIST TIME. ITEM
- 10. Assign personnel to maintain access control at the following _
locations: a) Control Room o b) TSC c) Construction Support Center
- 11. Coordinate with the OSC Supervisor and assign qualified first aid personnel to Rescue Teams and for medical emergencies which occur.
- 12. Insure that off-site medical authorities are advised when personnel injuries occur which require transport to medical facilities.
- 13. Coordinate with Local Law Enforcement Agency personnel wno establish a roadblock at the four corners to authorize access to the site.
- 14. Upon being advised that activation of the ORAA is planned; refer to EPIP 2.4, " Activation and Operation of the ORAA", and:
a) Assign 2 Security Force members to the ORAA Supervisor, b). Advise the Local Law Enforcenent Agency representative at the four corners of the planned evacuation.
- 15. If evacuation of the site is required, including the SCP and CAS, refer to EPIP 2.4 and relocate badge boards, dosimetry, radios, access authorization lists and keys to the ORAA.
- 16. . Provide assistance, as required,10 deactivating the Emerge'ncy Response Organization including:
a) Secure the TSC HVAC System. b) Relock the TSC Emergency Locker wnen equipment and supplies have
-been returned, c) Relock' the TSC Communication Room and the TSC.
W
4 , EMERGENCY PLAN IMPLEMENTING PROCEDURE .EPIP 2.1 Page 24 of 57
^
' ACTIVATION . AND OPERATION OF' THE OPERATIONAL Revision 3 SUPPORT CENTER (OSC) Date 8/8/83 ATTACHMENT 6 (Condinued)
(SECURITY SHIFT SUPERVISOR CHECKLIST TIME ITEM d) Relock the Emergency Lockers adjacent to the Emergency Assignment Tag Board when equipment and supplies have been returned.
- e. e) Collect all documentation and provide to the Records Clerk in the TSC.-
i 6
/
Security Snift Supervisor Time / Date
~
ft O. EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page- 25. of-57 ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 SUPPORT CENTER'(OSC) Date 8/3/83 ATTACHMENT 7 . ( RECOMMENDED OSC BRIEFING TOPICS
- 1. Liquid and/or Gaseous Effluent release point and Gaseous Effluent release rates.
- 2. Meteorological conditions.
- 3. Urgency associated with off-site monitoring activities.
- 4. Abnormal in-plant radiological conditions O
- a. Area Radiation Monitor (ARM) levels
- b. Containment High Range Radiation Monitor tevels
- c. TSC Ventilation and Area Radiation Monitor levels
- 5. Anticipated rescue or repair activities requiring plant entry.
- 6. Protective measures _ to be implemented for:
- a. Personnel assembled in the OSC.
- b. On and Off-Site Radiological Monitoring Teams.
- c. Personnel requiring access into potential radiological hazard areas.
- 7. Alrgency associated with performance of the initial steps to activate the Off-Site Relocation and Assembly Area (0RAA).
8 .' Urgency associated with staffing the Off-Site Radiological Laboratory (0RAL).
- 9. Plant status information, including:
- a. Emergency classification and basis.
I b. Abnormal shutdown conditions; e.g., f ailure to scram, lack of heat sink, etc. f l c. Emergency Core Cooling System (ECCS) performance.
- d. ' Abnormal auxiliary system status; e.g., AC or DC power proolems, service or I instrument error, etc.
- e. Problems which may cause plant conditions to deteriorate.
- 10. Prioritization of on-site and in-plant radiological monitoring efforts and post-accident sampling and analysis activitie.s.
L
.-.- = -- .
A r EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1. ~p Page 26 of 57 )
^
ACTIVATION AND OPERATION OF THE OPERATIONAL . Revision 3 SUPPORT CENTER (OSC) Date 8/8/83 L ATTACHMENT 8 , EMERGENCY ASSIGNMENT TAG BOARD DUTIES PINK TAG-HEALTH PHYSICS TECHNICIANS . TAG NO.: 1 REPORTING AREA: Emergency Response Team Lockers
- e. ,
ASSIGNMENT:' In-plant Surveys ' s
.g INSTRUCTIONS:. A. Print your name and badge number on the blank provided above the gtag.
B. Obtain an Operations radio from the Security Control Point and perfonn radio check with CAS. C. Gotolockerhl, Shelf #1andobtainandverify operability of the equipment identified on the appropriate inventory list from EPIP 6.3 posted on the inside of the locker door. O. .Or ss in protective clothing. E. Inform the OSC Supervisor that you have' all of your
- required equipment, except the self-contained breathing ,' '
apparatus are standing bys t.L.the Emergency Locker Arep. i , . . and are ready to perform 15-Flant surveys. - Q-N ,
' s
-l'I 4'i,' l F. Wheri Mirected by the OSC Supervisor,' proceed to the -
Health Physics Access Control Area.and obtain a self- ' contained breathing apparatus. 3s . s 3 G. Advise the OSC Supervisor that you have the required , , - ' respir,atory protectjon equipment and are awaiting- y ,s ' further instructions. i , P 3
.I.'
w. ( w [} g x j s 3, . 1 s ~ N
~
\- '
..~ ,
(, y
> I f
i
'N I
.; \ .y
.A -
J u
j' c ,, e u EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 27 of 57 -
. ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 SUPPORT CENTER (OSC) Date 8/8/83 ATTACHMENT 8 '
(Continued) EMERGENCY ASSIGNMENT TAG BOARD OUTIES PINK TAG f HEALTH PHYSICS TECHNICIANS TAG NO.: 2 REPORTING AREA: Emergency Response Team Lockers o ASSIGNMENT: In-plant Surveys v4 INSTRUCTIONS: A. Print yotM name and badge number on the blank provided g above the tag. i . >
#c ; B. Obtain an Operations radic from the Security Control
- Point and perform radio check with CAS.
s .% ?Y
; 3 ' C. Go to locker #1, Shelf #2. and obtain and verify
,, N ' ' ' operability of the equipment identified on the appropriate inventory list from EPIP 6.3 posted on the y
inside of the locker ' door. D. Dress in full protective clothing. E. Inform the OSC Supervisor that you have all of your required equipment, except the self-contained breathing [ apparatus, are standing by at the Emergency Locker Area, and are ready to perform In-Plant surveys. F. When directed by the OSC Supervisor, proceed to the Health Physics Access Control Area and obtain a self contained breathing- apparatus. G. Advise the OSC Supervisor that you have the required respiratory protection equipment and are awaiting further instructions. t
\
,l -
e'
.(. _
e < EMER"ENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 28 of 57 Revision 3 'i-ACTIVATION AND OPERATION OF THE OPERATIONAL SUPPORT CENTER (OSC) '/ Date 8/8/83
/
ATTACHMENT 8 TContinueo). ' EMERGENCY ASSIGNMENT TAG BOARD DUTIES PINK TAG HEALTH PHYSICS TECHNICIANS / TAG NO.: -3 I REPORTING AREA: Emergency Response Team Lockers ASSIGNMENT: Assembly Area Surveys for Habitability INSTRUCTIONS: A. Print your name and badge number on the blank provided above the tag. B. Go to locker #1, Shelf #3 and obtain and verify operability of the equipment identified on the appropriate inventory list from EPIP 6.3 posted on the inside of the locker door. C. Obtain. a self-contained breathing apparatus as directed by the OSC Supervisor. , D. - Inform the OSC Superviser that you are standing by at the Emergency Locker Area and are ready to comence
' assembly area surveys and verify habitability.
E. Perfonn a radiation smear and airborne survey to determine habitability of assembly areas as directed by the OSC Supervisor. NOTE
- 1. If normal ceunting equipment is available, such equipment should be used to analyze smears and airborne filter cartridges.
- 2. . If such equipment is not available, the movable radiciodine analyzer located in the TSC may be used.
s
=
. j m 'l
~
4 ',f
s -a
~
EMERGENCY PLAN-IMPLEMENTING PROCEDURE EPIP 2.1 Page 29 of 57 :
- ' ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 SUPPORT CENTER (OSC) Date- 8/8/83 ATTACHMENT 8 ..
(Continued) EMERGENCY ASSIGNMENT TAG BOARD DUTIES PINK TAG
- HEALTH PHYSICS TECHNICIANS TAG NO.: 3 (continued)
REPORTING AREA: Emergency Response-Team Lockers o ASSIGNMENT: Assembly Area Surveys for Habitability INSTRUCTIONS: F. Record all results (sample time, count time, location and results), using existing RPP forms, etc. j G. Report results to the OSC Supervisor as .they are obtained (include sample time, location, and results). H. Repeat Steps, E, F and G on a periodic basis as directed by the OSC Supervisor.- i l w
.l
a ,
~ EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP ~ 2.1-Page 30 of 57 ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 't SUPPORT CENTER (OSC) Date 8/8/83 ATTACHMENT'8 (Continued) -
EMERGENCY ASSIGNMENT TAG BOARD DUTIES PINK T AG HEALTH PHYSICS TECHNICIANS TAG NO.: 4 REPORTING AREA: Emergency Response Team Lockers ASSIGNMENT: -Personnel Monitoring INSTRUCTIONS: A. Print your name and badge number on the blank provided - above the tag. B. Go to Locker #1, Shelf #4 and obtain the equipment identified on the appropriate inventory list from EPIP 6.3 posted on the inside of the locker door. C. Obtain a self-contained breathing apparatus as directed by the OSC Supervisor.- D. Inform the OSC Supervisor that you are reporting to
' Access Control to relieve the Access Control Foreman.
E. Pass out Personal Statement Concerning Incident forms to personnel in the Locker Room Area, Access Control, and Tag Board Area in the OSC, instruct evacuated personnel to fill = out the form and return to you when completec. F. Provide assistance in surveying and decontaminating personnel evacuating the Power Block Structure who determine that -they are contaminated.- G. Determine if there are any injuries _ or if personnel have been exposed to-high levels of radiation and advise the OSC Supervisor of such conditions.
~
H. Inform OSC Supervisor that personnel monitoring activities have been. completed at Access Control and request permission to proceed to the construction support center to perform steps E and G. I. Review Personal Statement Concerning Incident forms and advise the OSC Supervisor of any pertinent and/or unexpected information.
,e
..- -a.
JEMERGENCY PLAN IMPLEMENTING P'ROCEDURE EPIP 2.1 Page 31 of-'57 - ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 SUPPORT CENTER (OSC) Date 8/8/83 ATTACHMENT 8 ~ (Continued) EMERGENCY ASSIGNMENT TAG BOARD DUTIES PINK TAG HEALTH. PHYSICS TECHNICIANS
-TAG NO.: 5
~
REPORTING AREAi Emergency Response Team Lockers
-e ASSIGNMENT: Rescue' and Emergency Repair Team
' INSTRUCTIONS: A. Prirt your name and badge number on the blank provided above the tag.
4 B. Obtain an Operations radio from the Security Control Point and perform radio check with CAS. C. Go to locker #1, Shelf #5 and obtain and verify operability of the equipment identified on the appropriate inventory list from EPIP 6.3' posted on the inside of the locker door. D. Dress in full protective clothing. - Inform the OSC Supervisor that you have all of your
~
E. equipment, except the self-contained breathing apparatus, are standing by at the Emergency Locker Area, and are ready to perform rescue and emergency repair activities. F. When directed by the OSC Supervisor, proceed to the Health Physics Access Control Area and obtain a self-contained breathing apparatus, s. G. Advise the OSC Supervisor that you have the required respiratory protection equipnent and are awaiting further instructions. O
.9 e
a'-m ,.-. . -y % - , . g. e --.. , , , ,,- --pc -. ,, -p g m9y-- %vy..,-wi.-w ,e3wD- ., y.- ~ p
a . EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 32 of 57 ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 : SUPPORTCENTER(OSC) Date 8/8/83 ATTACHMENT 8 (Continued) EMERGENCY ASSIGNMENT TAG BOARD DUTIES PINK TAG HEALTH PHYSICS TECHNICIANS TAG NO.: 6 REPORTING AREA: Emergency Response Team Lockers ASSIGNMENT: On-Site Radiological Monitoring Team - Team Leader INSTRUCTIONS: _ A. Print your name and badge number on the blank provided above the tag. B. Go to Locker #2, Shelf #1 and obtain and verify operability of the equipment -identified on the appropriate' inventory list from EPIP 6.3 posted on the inside of the locker door. C. L 0btain a self-contained breathing apparatus as directed by the OSC Supervisor. D. Obtain the name of Number 1-Green from the Emergency Assignment Tag Board and await his arrival. E. Notify the OSC Supervisor that the On-Site Radiological Monitoring Team is ready for their briefing, and attend briefing, when scheduled. NOTE If a severe radiological problem exists on site, don protective clothing and mask, as directed by the OSC Supervisor. F. Transport equipment to the vehicle and load the materials. G. Inform the OSC Supervisor that the On-Site Radiological Monitoring Team is prepared to be dispatened and proceed, as directed. NOTE Retain your own dosimetry.
~
~
> 0
' EMERGENCY PLAN' IMPLEMENTING PROCEDURE EPIP 2.1 Page 33 of-57 - ;
ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3-SUPPORT CENTER (OSC) Date 8/8/83 ATTACHMENT 8 ~ (Continueo) EMERGENCY ASSIGNMENT TAG BOARD DUTIES PINK TAG HEALTH PHYSICS TECHNICIANS TAG NO.: 7
. REPORTING AREA: Emergency Response Team Lockers ASSIGNMENT: Off-Site Radiological Monitoring Team A - Team Leader INSTRUCTIONS: A. Print your name and badge number on the blank provided above the tag.
B. Go to Locker #2, Shelf #2 and obtain and verify operability of the equipment identified on the appropriate' inventory list from EPIP 6.3 posted on the inside of the locker door. C. Obtain a self-contained breathing apparatus as directed by_the OSC Supervisor. D. - Obtain the name of Number 2-Green from the Emergency Assignment Tag Board and await his arrival . E. Notify the OSC Supervisor that Off-Site Radiological Monitoring Team A is ready for their briefing, and attend briefing, when scheduled. NOTE If a severe radiological problem exists on site, don protective clothing and mask, as directed by the OSC Supervisor. F. Transport equipment to the vehicle and load the materi als. G. Inform the OSC Supervisor that Off-Site Radiological Monitoring Team A is prepared to be dispatched ano proceed, as directed. NOTE Retain your own dosimetry. O 4
< - - - - , e, . -y--- - r ,- -r,% r-- ---- - y e vv n -- --*=- 1
s <- EMERGENCY PLAN IMPLEMENTING' PROCEDURE EPIP 2.1 Page 34 of 57 ACTIVATION ~ AND OPERATION OF THE OPERATIONAL ' Revision 3 - SUPPORT CENTER (OSC) Date 8/8/83 l ATTACHMENT 8 l _ .(Continueo)
- EMERGENCY ASSIGNMENT TAG BOARD DUTIES PINK TAG l
HEALTH PHYSICS TECHNICIANS TAG NO.: 8 REPORTING AREA: Emergency Response Team Lockers
' ASSIGNMENT: Off-Site Radiological Monitoring Team B - Team Leader INSTRUCTIONS: A. Print your name and badge number on the blank provided above the tag.
i !' B. Go to Locker #2, Shelf #3 and obtain and verify l operability of the equipment identified on the ! appropriate inventory list from EPIP 6.3 posted on the inside of the locker door. l
. C. Obtain a self-contained breathing apparatus as directed
,by the OSC Supervisor.
I D. Obtain the name of Number 3-Green -fren the Emergency l Assignment Tag Board and await his arrival. E. Notify the OSC Supervisor that Off-Site Radiological l Monitoring Team B is ready for their briefing, and i attend briefing, when scheduled. j NOTE f If a severe radiological problem exists on site, ! don protective clothing and mask, as directed by the OSC Supervisor. F. Transport equipment to the vehicle and load the materials. 4 G. Inform the OSC Supervisor that Off-Site Radiological Monitoring Team B is prepared to be dispatched and proceed, as directed. j NOTE Retain your own dosimetry. ( m O k
s e EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 35 of 57 : ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 SUPPORT CENTER (OSC) Date 8/8/83 ATTACHMENT 8 , (Continueo)
-EMERGENCY ASSIGNMENT TAG BOARD DUTIES ORANGE
' RADWASTE OPERATOR
' TAG NO.: 1 REPORTING AREA: Emergency Response Team Lockers e-ASSIGNMENT: Operational Support Center Communicator and Data Recorder INSTRUCTIONS: A. Print your name and badge number on- the blank provided above the tag.
B. Go to' Locker #1, Shelf #4 and obtain and verify operability of the equipnent identified on the appropriate inventory list from EPIP 6.3 posted on the inside of the locker door. C. Obtain a self-contained breathing apparatus as directed by the OSC Supervisor. D. Proceed to the Security Control Point. [ I E. Verify operability of communication equipment in the Security Control Point. F. Inititte maintenance of the OSC Log. G. Assist the OSC Supervisor with communications by functioning as the OSC Supervisor's emanunicator. l~ l H. Inform the OSC Supervisor of all pertinent information received. l - l V
~ EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 36 of 57 ACTIVATION AND OP$ RATION OF THE OPERATIONAL Revision 3 SUPPORT CENTER'(OSC) Date 8/8/83 ATTACHMENT 8
-(Continued) '
EMERGENCY ASSIGNMENT TAG BOARD DUTIES' RED TAG RAD / CHEM TECHNICIAN- , TAG NO.: 1 REPORTING AREA: Hot Lab Area 0 ASSIGNMENT: Sample Counting and Chemical Analysis INSTRUCTIONS: A. Print your name and badge number on the blank provided above the tag. j B. At Access Control obtain a high range dose rate instrument and both SR and 10R dosimeters.- C. Obtain a self-contained breathing apparatus as directed by the OSC Supervisor. D. If the event has occurred on a back-shift, ' locate the Rad Waste Operator 'and relieve him of his responsibility for post-accident sampling activities. E. -Infom the OSC Supervisor that you have assumed responsibility for post-accident sampling activities and inquire as to the necessity for such samples.
- 1) If post-accident sampling activities are necessary <
comence sampling.
- 2) If post-accident sampling activities are not necessary, advise the OSC Supervisor that you are ready to proceed to the Hot Lab, providing the ARM
- is not. upscale or alarming, and upon his authorization, proceed to the Hot Lab.
~
F. Once you are present in the Hot Lab, infom the OSC Supervisor that you are available to perform counting and analysis functions, as needed. G. As directed, proceed to the Off-Site Radiological Laboratory to perform counting and analysis functions, as needed.
~
~
EMERGENCY" PLAN IMPLEMENTING PROCEDURE- EPIP 2.1 Page ~37 of- 57 .- ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 SUPPORT CENTER-(OSC) Date 8/8/83 ATTACHMENT 8 , (Continued) EMERGENCY ASSIGNMENT TAG BOARD DUTIES RED TAG RAD / CHEM TECHNICIAN TAG NO.: 2 REPORTING AREA: TSC, Hot Lab' Area e ASSIGNMENT: Sample Counting and Chemical . Analysis INSTRUCTIONS: A. Print your name and' badge number on the blank provided above the tag. B. Inform the OSC Supervisor that you are proceeding to the Technical Support Center to verify operability of tne Portable Radioiodine/ Particulate Analyzer. C. Inform the Site Radiation Protection Coordinator'of the operability status of the Portable Raoioiodine/ Particulate Analyzer.
-D. Obtain a self-contained breathing apparatus as directed by the OSC Supervisor.
E. Proceed to Access Control and obtain a high range dose rate instrument and both 5R and 10R dosimeters. F. Advise the OSC Supervisor that you .are ready to proceed to the Hot Lab, providing the ARM is not upscale or al arming, and upon his authorization, proceed to the Hot Lab. G. Infonn the OSC Supervisor that you are available to perform counting and analysis functions, as needed. H. As directed, proceed to the Off-Site Radiological Laboratory to perform counting and analysis functions, l as needed. l-l I-i S
a <. EMERGENCY ' PLAN IMPLEMENTING PROCEDURE EPIP 2.1
.Page 38 of 57
. ACTIVATION AND OPERATION OF THE OPERATIONAL . Revision 3 SUPPORT CENTER (OSC) Date 8/8/ 83 ATTACHMENT 8 (Continueo) -
EMERGENCY' ASSIGNMENT TAG BOARD DUTIES
' GREEN TAG STAFF PERSONNEL TAG NO.: 1 REPORTING AREA: ' Emergency Response Team Lockers ASSIGNMENT: On-Site Radiological Monitoring Team - Team Member INSTRUCTIONS: A. Print your name and badge . number on the blank provided abovd the tag.
B. Go- to the Security Control Point (SCP) and:
- 1) Obtain an Operations radio and perform radio check with CAS.
- 2) Obtain keys for a vehicle and the gas pump, unless already checked out.
C. Check with the OSC Supervisor to determine if severe radiological problems exist on-site. NOTE If' a radiological problem exists'on site and if
' directed by the OSC Supervisor, perform items G, H, I, and J, and K-listed below before obtaining the vehicle.
'O. Take the Operations radio, vehicle key and gas pump key with you to the vehicle.
E. Check to see if the vehicle is operable and fill the gas tank, as necessary. F. Park the vehicle outside the fence near the main entrance and return the gas pump key to Security.
~
G. Go to Locker #2, Shelf #4 and obtain and verify operability of the equipment identified on the appropriate inventory list from EPIP 6.3 posted on the inside of the locker door. H. Obtain a self-contained breathing apparatus as directed by the OSC Supervisor.
~
~
4 EMERGENCY-PLAN. IMPLEMENTING PROCE' DURE EPIP 2.1 Page 39 of 57 ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 SUPPORT CENTER (OSC) Date 8/8/83
. ATTACHMENT 8 .
(Continued) EMERGENCY ASSIGNMENT TAG BOARD DUTIES GREEN TAG STAFF PERSONNEL TAG NO.: 1 -(Continued) REPORTING AREA: Emergency Response Team Lockers ASSIGNMENT: On-Site Radiological Monitoring Team - Team Menber INSTRUCTIONS: I. Obtain a 12-volt battery (automotive type) from the Portable Air Monitor cart located in the TSC Camnunications Room. J. Obtain the name of Number 6 - Pink 'from the Emergency Assignment Tag Board and advise him that you are ready for the briefing. K. Attend the briefing conducted by the OSC Supervisor. NOTE If a severe radiological problem exists on site, don protective clothing and mask, as directed by the OSC Supervisor. L. Assist in loading equipment and supplies into the vehicle. NOTE Retain your own dosimetry. F
~
l ..
~
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 40 of.57 Revision 3 ACTIVATION AND OPERATION OF THE OPERATIONAL SUPPORT CENTER (OSC) Date 8/8/83
~
ATTACHMENT 8 (Continued) EMERGENCY ASSIGNMENT TAG BOARD DUTIES GREEN TAG STAFF PERSONNEL TAG NO.: 2 REPORTING AREA: Emergency Response Team Lockers-
. ASSIGNMENT: Off-Site Radiological Monitoring Team A - Team Member INSTRUCTIONS: A .' Print your name and badge number on the blank provided above the tag.
B. Go to the Security Control Point (SCP) and:
- 1) Obtain a Security / Radiological Survey Porta-Mobile radio with magnetic base antenna.
~ 2) Perform a radio check with CAS.
- 3) Obtain keys for a vehicle and the gas pump, unless already checked out.
C. Check with the OSC Supervisor to determine if severe radiological problems exist on site. NOTE If a radiological problem exists on site and if directed by the OSC Supervisor, perform items H, I, J, K and L listed below before obtaining the vehicle. D. Take the Security / Radiological Survey radio, vehicle key .
. and gas pump key with you to the vehicle.
E. Check to see if the vehicle is operable and fill the gas tank, as necessary. . F. Mount the radio antenna on the vehicle. G. Park the vehicle outside the fence near the main entrance and return the gas pump key to Security. H. Go to locker 12, Shelf 45 and obtain and verify operability of the equipment identified on the appropriate inventory list from EPIP 5.3 posted on the inside of the locker door. I. Obtain a self-contained breathing apparatus as directed by the OSC Supervisor. _
~ . . , _ ____ ... .._. .. - - - . - ~
~ EMERGENCY PLAN' IMPLEMENTING PROCEDURE EPIP 2.1 Page 41 of- 57 -
ACTIVATION AND OPERATION OF THE OPERATIONAL . Revision 3
. SUPPORT CENTER (OSC) Date 8/8/83 ATTACHMENT 8 ~
(Continued) EMERGENCY ASSIGNMENT TAG BOARD DUTIES GREEN TAG STAFF PERSONNEL . ,. TAG NO.: 2 (Continued) 1 REPORTING AREA: Emergency Response Team Lockers Off-Site Radiological Monitoring Team A - Team Menber ASSIGNMENT: INSTRUCTIONS: J. Obtain a 12-volt battery (automotive type) fran the Bat {eryRoom. K. Obtain the name of Number 7-Pink from the Emergency Assignment Tag Board and advise him that you are ready for the briefing. L. Attend the briefing conducted by the OSC Supervisor. NOTE If a severe radiological problem exists on site, don protective clothing and mask, as directed by the OSC Supervisor. M. Assist in loading equipment and supplies into the vehicle. . NOTE Retain your own dosimetry. l W
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 42 'of 57 - ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 ' SUPPORT CENTER (OSC) 0 ate 8/8/83 ATTACHMENT 8 (Continuea) - EMERGENCY ASSIGNMENT TAG BOARD DUTIES GREEN TAG STAFF PERSONNEL TAG NO.: 3 REPORTING AREA: Emergency Response Team Lockers
-ASSIGNMENT: Off-Site Radiological Monitoring Team B - Team Memoer INSTRUCTIONS: A. Print your name and badge number' on the blank provided aoove the tag.
B. - Go to the Security Control Point (SCP) and:
- 1) Obtain a Security / Radiological Survey Porta-Mobile radio with magnetic base antenna.
.2) ' Perform a radio check with CAS.
- 3) Obtain keys for a vehicle and the gas pump, unless already checked out.
C. Check with the OSC Supervisor to determine if severe radiological problems exist on site. NOTE If a radiological problem exists en site and if directed by the OSC Supervisor, perform items H, I, J, and K listed below before obtaining the vehicle. D. Take the Security / Radiological Survey radio, vehicle -key and gas pump key with you to the vehicle.
.E. Check to see if the vehicle is operable and fill the gas tar.k. as necessary.
F. Mount the radio antenna on the vehicle. G. Park the vehicle outside the fence near the main entrance and return the gas pump key to Security. H. Go to locker #3, Shelf #1 and obtain and verify operaoility of the equipment identified on the appropriate inventory list from EPIP 5.3 posted on the inside of the locker door.
~
~
I I
)
s > EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 43 of 57 : ACTIVATION AND.0PERATION OF THE OPERATIONAL Revision 3 SUPPORT CENTER (OSC) Date 8/8/83 ATTACHMENT S , (Continued) EMERGENCY ASSIGNMENT TAG BOARD DUTIES GREEN TAG STAFF PERSONNEL TAG NO.: 3 (Continued) REPORTING AREA: Emergency Response Team Lockers ' ASSIGNMENT: Off-Site Radiological Monitoring Team B - Team. Member INSTRUCTIONS: I. Obtain a 12-volt battery (automotive type) from the Battery noom. J. Obtain the name of Number 8-Pink from the Emergency Assignment Tag Board and advise him-that you are ready for the briefing. K. Attend the briefing conducted' by the OSC Supervisor. NOTE If a severe radiological problem exists on site, don - protective clothing and mask, as directed by the OSC Supervisor. L. - Assist in loading equipment and supplies into the vehicle. i NOTE Retain your own dosimetry. l
t 4-EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1-Page 44 of 57 ACTIVATION AND 0PERATION OF THE 0PERATIONAL Revision 3 - SUPPORT CENTER (0SC) Date- 8/8/83 ATTACHMENT 8 (Continued) . . EMERGENCY.' ASSIGNMENT TAG BOARD DUTIES BLUE TAG INSTRUMENT TECHNICIANS TAG NO.: 1 REPORTING AREA: -Emergency Response Team Lockers ASSIGNMENT: Emergency Repair Work. - Instrumentation INSTRUCTIONS: A. Print your name and badge number on the blank provided above .the tag. r B. Go to Locker #3, Shelf #2 and obtain and verify operability of the equipment identified on the appropriate inventory list from EPIP 6.3 posted on the . inside of the locker door. NOTE Inventory of the Instrumentation Tool Kit is not necessary if the seal is intact. If the seal is broken, take an inventory of tools using the inventory list located inside the tool kit. C. Dress in full protective clothing. D. Inform the OSC Supervisor that an Instrument Technician is prepared to be dispatened, to obtain a self-contained breathing apparatus. E. Remain in the 2mergency Locker Area until otherwise directed by the OSC Supervisor. F. Upon receiving an assignment, break the seal on the Instrumentation Tool Kit, check to see' that jou have the necessary tools for the assigned task, and obtain additional tools and equipment, if necessary.
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 - Page 45 of 57 - 3 ACTIVATION AND OPERATION OF;THE OPERATIONAL Revision 3 SUPPORT CENTER (OSC)- Date 8/8/83 ATTACHMENT 8 ~
.(Continued)
EMERGENCY ASSIGNMENT TAG BOARD DUTIES - PURPLE. TAG ELECTRICIAN TAG NO.: 1 REPORTING AREA: Emergency Response Team Lockers ASSIGNMENT: Emergency Repair Work - Electrical INSTRUCTIONS: A. Print your name and badge number on the blank provided above the tag. B. Go to Locker #3, Shelf #3 and obtain and varify operability of the equipment identified on the appropriate inventory list from EPIP 6.3 posted on the
.inside of the locker door.
NOTE Inventory of the Electrician's Tool Kit is not necessary if the seal is intact. If the seal is broken, take an inventory of the tools using the inventory list located'inside the tool kit. C. . Dress in full' protective. clothing. O. Inform the OSC Supervisor that an Electrician is prepared to be dispatched, to obtain a self-contained breathing apparatus. E. Remain in the Emergency Locker Area until otherwise
' directed by the OSC~ Supervisor.
F. Upon receiving an assignment, break the seal on the Electrician's Tool Kit, check to see that you have the necessary tools for the assigned task, and obtain additional tools and equipment, if necessary. O
--,n - - - - -, .---- ,. n , w ,.,
r: E 4 EMERGENCY PLAN IMPLEMENTING' PROCEDURE EPIP 2.1 Page 46 of 57 ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 - - SUPPORT-CENTER (OSC) Date 8/8/83 ATTACHMENT 8 (Continueo) EMERGENCY ASSIGNMENT TAG BOARD-DUTIES PURPLE TAG' ELECTRICIAN TKs NO.: 2 REPORTING AREA: Emergency Response Team Lockers ASSIGNMENT: Emergency Repair Work - Electrical INSTRUCTIONS: A. Print your-name and badge number on the blank provided above the tag. B. Go to Locker #3, Shelf #4 and obtain and verify operability of the equipment identified on the appropriate inventory list from EPIP 6.3 posted on the inside of the locker door. NOTE Inventory of the Electrician's Tool Kit is not necessary if the seal is intact. If the seal is broken, take an inventory of the tools using the inventory. list located inside the tool kit. C. Dress =in full protective clothing. D. Inform the OSC Supervisor that an Electrician is prepared to be dispatched, to obtain a self-contained breathi ng '. apparatus. E. Remain in the Emergency Locker Area until otherwise directed by the OSC Supervisor. F. Upon receiving an assignment, break the seal on the Electrician!s Tool Kit, check to see that you have the necessary tools for the assigned task, and obtain additional tools and equipment, if necessary. l
~ EMERGENCY PLAN-IMPLEMENTING PROCEDURE EPIP 2.1
. Page 47 of 57 - -
- ACTIVATION AND OPERATION OF THEl0PERATIONAL Revision 3 SUPPORT CENTER (OSC) Date 8/8/83 ATTACHMENT 8 _
(Continued) EMERGENCY ASSIGNMENT TAG BOARD DUTIES , i YELLOW TAG MECHANIC 4 TAG NO.: 1 REPORTING AREA: Emergency Response Team Lockers ASSIGNMENT: Emergency Repair Work - Mechanical INSTRUCTIONS: A. ' Print your name and badge number on the blank provided above the tag. B. Go to Locker #3, Shelf #5 and obtain -and verify operability of the equipment identified on the appropriate inventory list from EPIP 6.3 posted on the inside of the locker door. NOTE Inventory of the Mechanical Tool Kit is not necessary if the seal is intact. - If the seal is broken, take an inventory of tools using the inventory list located inside the tool kit. C. Dress in fall protective clothing. l D. Inform the OSC Supervisor that a Mechanic is prepared to i be dispatched, to obtain a self-contained breathing apparatus.
- E. Remain in the Emergency Locker Area until otherwise directed by the OSC Supervisor.
F. Upon receiving an assignment, break the seal on the Mechanical Tool Kit, check to see that you have the necessary tools for the assigned task, and obtain i additional tools and equipment, if necessary. l
.E n
v ---ev - - , . ~ -~v e ,m-., ,m- . , e- ..n.a , - , - ~ - w e n ---em-
a . EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 48 of 57 ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 ; SUPPORT: CENTER (OSC) Date 8/8/83
-ATTACHMENT 8 (Continued)
EMERGENCY ASSIGNMENT TAG BOARD DUTIES BLACK . TAG ' TECHNICAL ENGINEERS JTAG NO.: 1 REPORTING AREA: Control Room ASSIGNMENT: TSC Communicator INSTRUCTIONS: A. Print your name and badge' number on the blank provided above the-tag.. B. Report to the Control Room.
- C. Inform the Operations Shift Supervisor or Control Room Coordinator that you are prepared to assume duties as the TSC Communicator.
D. Provide communications functions, as Ldirected. i l n L l l h I l e" , l
EMERGENCY PLAN IMPLEMENTING PROCEDURE . EPIP 2.1 Page 49 of 57 .. . ACTIVATION AND OPERATION OF THE OPERATIONAL- Revision 3 SUPPORT CENTER (OSC) Date 8/8/83 ATTACHMENT 8 - (Continued) EMERGENCY ASSIGNMENT TAG BOARD OUTIES BLACK TAG . TECHNICAL ENGINEERS ' TAG NO.: 2 REPORTING AREA: Control Room O ASSIGNMENT: Radiological Data (Back Panel) Communicator INSTRUCTIONS: A. Print your. name and badge number on the blank provided above the tag. B. Report to the Control Room. C. Inform the Operations Shift Supervisor or Control Room Coordinator that you are prepared to assume duties as the Radiological Data (Back Panel) Communicator. D. Establish communications with the Site Radiation Protection Coordinator (or his communicator) and provide l radiological data, as requested. I I i I e-
, , , . . , . - . _ , . . , ,m, __.. ._ _ , _ . - . . . _ _ _ . - _
. s-EMERGENCY PLAN IMPLEMENTING PROCEDURE ~ EPIP 2.1 Page 50 of 57
^'
ACTIVATION AND OPERATION OF THE 0PERATIONAL Revision 3 SUPPORT CENTER (OSC) -Date 8/8/83 ATTACHMENT 8-(Continued) EMERGENCY ASSIGNMENT TAG BOARD DUTIES
~ BLACK TAG TECHNICAL ENGINEERS ,
TAG NO.: 3 REPORTING AREA: Technical Support . Center - ASSIGNMENT: , - Control Room " Dedicated" Canmunicator INSTRUCTIONS: A. Print your name and badge number on the blank provided ; above the tag. , l B. - Report- to the Technical Support Center.
~
C. Print your name on the TSC Manning Status Board by the appropriate position title. D. Inform the Technical Support- Center Supervisor that you ' are prepared to assume duties as the Control- Room
" Dedicated" Communicator.
E. ' Provide communications functions, as directed. l 4 i i
~
f
~. - -. -
, o EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP '2.1 Page 51 of 57 --
EAC'IVATION T AND OPERATION OF THE OPERATIONAL Revision 3 SUPPORT CENTER (OSC) .Date 8/8/83 ATTACHMENT 8 - (Continued) EMERGENCY ASSIGNMENT TAG BOARD DUTIES BLACK TAG ' TECHNICAL ENGINEERS TAG NO.: 4
. . REPORTING AREA: Technical Support Center O
ASSIGNMENT: EOF " Dedicated" Communicator INSTRUCTIONS: A. Print your name .and badge number on the blank provided above the tag. B. Report to the Technical Support Center. C. Print your name on the TSC Manning Status Board by the appropriate position title.
~
D. Inform the Emergency Coordinator or TSC Supervisor that 4 you are prepared to assume duties as the EOF " Dedicated" Communicator. E. Provide communications functions, as directed. l l l e i [ l ~ l _ _ . .- _ , - ~ . . . . . _ ,
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page_ 52 of 57
~
.. ACTIVATION AND OPERATION 0F THE OPERATIONAL Revision 3 SUPPORT. CENTER (OSC) Date S/8/83 ATTACHMENT 8 (Continued)
EMERGENCY ASSIGNMENT TAG BOARD DUTIES BLACK TAG TECHNICAL ENGINEERS [ TAG NO.: 5 REPORTING AREA: Technical Support Center ASSIGNMENT: Radiological Data Communicator INSTRUCTIONS: A. Print your name and badge number on the blank provided above the tag. B. Report to the Technical Support Center. l C. Print your name on the TSC Manning Status Board by the appropriate position title, , Inform the Site Radiation Protection Coordinator that O. you are prepared to assume duties as -the Radiological i Data Communicator. E. Provide communications functions, as directed. I l I l l mmm
.: o EMERGENCY PLAN IMPLEMENTING PROCEDURE .EPIP 2.1 Page 53 of.57 '.. .
ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 SUPPORT CENTER (OSC) .Date 8/8/83 ATTACHMENT 8 ~
- (Continued)
EMERGENCY ASSIGNMENT TAG BOARD DUTIES BLACK TAG TECHNICAL ENGINEERS TAG NO.: 6 REPORTING AREA: Technical Support Center - o ASSIGNMENT: Radio Communicator INSTRUCTIONS: A. Print your name and badge number on the blank provided above the tag. B. Report to the Technical Support Center. C. Print your name on the TSC Manning Status Board by the appropriate position title.
-D. , Inform the Site Radiation Protection Coordinator that you are prepared to assume duties as the Radio Communicator.
E. Provide communications functions, as directed. l-t l t .. l-
. - . _ -- .- - - . , . . . . . . _ - - . _ , . - . _ , . _ . - . . . _... . . _ . - _ . _ - ~ _ . ~ . . . .
a .. g EMERGENCY PLAN IMPLEMENTING PROCEDURE i EPIP 2.1 s P age 54 of 57 ACTIVATION AND OPERATION OF THE OPERATIONAL , s [ Revision 3 , L SUPPORT CENTER (OSC) Date 8/8/83 ATTACHMENT 8
-(Continued)'
EMERGENCY ASSIGNMENT TAG BOARD DUTIES BLACK TAG \ TECHNICAL ENGINEERS 4
,' ' k. w" TAG NO.: 7 i s.
i w REPORTING AREA: Technical Supportkbater O ASSIGNMENT: Radio Operator's Assistant 9< ' INSTRUCTIONS: A. , Print your. name and badge number on the blank provided above the tag. B. Report to the Technical Support Center. , ,
, :s ,, ,
C. Print your name on the TSC Manning Status Board by the L -' appropriate position title. 3, . ,. ., j 't 0.g Inform the Site Radiation Protection Coordinator that
! you Operator'sare prepared to assume duties as the Radio Assistant.
- k. Provide communications functions, as directed. .
i
.,- 4
.g
'i t
't ;
\
(
' k g N
%h
^
s
\
x s' -
- y. .. .
p ..
, ,,.+
P: e <
\'s EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1
-, Page 55 of. 57 . . .
[ -( ACTIVATION AND OPERATION OF THE OPERATIONAL SUPPORT CENTER (OSC) Revision 3 Date 8/8/83
-c ATTACHMENT 8 ,.
(Continued) EMERGENCY ASSIGNMENT TAG'30ARD OUTIES bug TM ' TECHNICAL ENGINEERS TAG NO.: 8 REPORTING AREA: Technical Support Center
. 8 ASSIGNMENT; NRC ENS Communicator r 1 Print your name and badge number on the blank provided ;
INSTRUCTIONS: ( . A.above the tag. l B. Report to the Technical Support Center. C. Print your name on the TSC Manning Status Board by the appropriate' position title. O. Inform the Emergency Coordinator or TSC Supervisor that you are prepared to assume duties as the NRC ENS Communicator.
, E. Provide communications functions, as directed.
l i i -
.v.
l . 1: , , ?. l i l ' i-j 5 I' b - c
.y - % _.
- t .
~
( J. _ {- s. t '} ' s
...n..
3 s . L/,, - EMERGENCY PLAN IMPLEMENTING' PROCEDURE EPIP '2.1 Page 56 -of 57 ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 Date 8/8/83
/ ' SUPPORT CENTER (OSC) j/ ATTACHMENT 8 J
. (Continued) ~
.' EMERGENCY ASSIGNMENT TAG BOARD DUTIES WHITE TAG
. SHIFT TECHNICAL ADVISOR TAG NO.: 1 REPORTING AREA: -Technical Support Center
-ASSIGNMENi: Technical Support Staff
~
. INSTRUCTIONS: A. Print your name and badge number on the blank provided above the tag.
B. Report to the Technical Support Center. f' C. -Print your name.on the TSC Manning Status Board by the
?
l~
- approp iate position title.
D. In'fo[rb the Technical and Engineering Supervisor that you are prepared to perform technical engineering activities, as directed.
,oy ,
lg -t g Q r I e P
~ 4
,n
+ t
'f
- cc
- N.
s
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.1 Page 57 of 57 - : ACTIVATION AND OPERATION OF THE OPERATIONAL Revision 3 SUPPORT CENTER (OSC) Date' 8/8/83 ATTACHMENT 8
~
-(Continued)
EMERGENCY ASSIGNMENT TAG BOARD DUTIES WHITE TAG SHIFT TECHNICAL ADVISOR - TAG NO.: 2 REPORTING AREA: Technical Support Center o
- ASSIGNMENT: Technical Support Staff INSTRUCTIONS: A. Print your name and badge number on the blank provided above the tag.
B. Report to the Technical Support Center. C. Print your name on the TSC Manning Status Board by the appropriate position title. D. Inform the Technical and Engineering Supervisor that you are prepared to perform technical _ engineering a;tivities, as directed. 1 9, , O b w + ,- --,s-- , , - , , - , , . ,, . . - - - - . . - . - , .ws,--e - --
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 . Page 1 of 65' ,,' l-1* ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 .z J; Date 7/14/83 ' 19" L .: 1.0 PURPOSE - - . Tnis procedure provides instructions for activation and operation of the Technical Support Center (TSC) to provioe emergency coordination e and technical support during an emergency condition. 2.0 APPLICABILITY 2.1 This procedure shall be implemented upon declaration of an ~""N - emergency classified as an ALERT or greater. It is applicable to all site management and technical personnel assigned to the TSC and/or responsible for the emergency functions of the TSC. s#: 2.2 During an event classified as a NOTIFICATION OF UNUSUAL EVENT, the Emergency Coordinator, at his discretion, may activate the TSC. - 3.0 RESPONSIBILITIES 3.1 Emergency Coordinator _ . 3.1.1 Manage the overall site emergency response and recovery effort. 3.1.2 Notify, coordinate the flow of status information, and provide protective action recommendations to off-site agencies until relieved of this function Dy the Emergency Response and Recovery Director upon activation of the 60F.
'3.1.3 Insure that response activities being conducted by the DAEC Emergency Response Organization are coordinated with those m, being provided by the Corporate Emergency Response Wu Organization.
3.2 Tecnnical Sucoort Center Supervisor , ;. 3.2.1 Insure that the TSC is activated and staffed sufficiently to provide = operations personnel with the required level of technical support. ! 3.2.2 Provide management and overall direction to the TSC staff during emergency response and recovery efforts. 3.3 -Site Radiation Protection Coordinator l 3.1.1 Coordinate and direct radiation protection activities at tne site. r .
. i, n# .. ..@. .. m. h$fli.
n ,. - p , .. . . . ; . . EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 */ MZ
- 'C' y.::.:
Page 2 of 65 , ,3g ACTIVATION AND OPERATION OF THE TECriNICAL SUPPORT CENTER Revision 5 - .
- 1. .: $[p 1
- 6. '
Date 7/14/83 v. fe f gid. pn~
.._..'c,.?g:4
., s ..
3.3.2 Perform dose projection and dose assessment activities and A" 99. supervise the activities of Off-Site Monitoring Teams until % '5cYa relieved of this function by the Radiological Assessment- . 0 ' .,/,7J' Coordinator upon activation of the EOF. . e
-.<!;.))<
3.3.3 Coordinate with the Radiological Assessment Coordinator with " 'p0 respect to defining and inputting radiological and ,
,Wli, meteorlogical parameters into the dose projection computer f.. , . .y .'y progrvn. .J4W.'6 Nie - '
, 8.1 . L::
3.4 Technical and Engineering Suoervisor ..[,' [ - . 3.4.1 Provide supervision and technical direction to the TSC , N.'fNl technical staff associated with analytical and engineering ,
,e-efforts. .
U.,1f y 3.4.2 Coordinate and provide direction, as required, for all .. iD ' . dW repair / corrective action efforts which are undertaken to aid in achieving stable plant conditions and terminating any ,,,' uncontrolled radioactive releases. f.,'.," , j.1,, s 3.4.3 Indentify the need for and coordinate engineering and . fj analysis assistance provided by the Technical and -
% t.- l- '
Engineering Support Supervisor in the EOF, _.;7- ,' 3.5 Security and Supoort Suoervisor ,' 3.5.1 Ensure tnat overall plant security is not degraded and that personnel accountaoility is established and maintained. 3.5.2 Ensure that the administrative and logistical support needs .; , are provided to the DAEC Emergency Response Organization. , 3.5.3 Define and coordinate, as required, additional administrative, logistic and procurement needs with the . . . . Support Services Coordinator in the EOF.. . . ] .} 4.0 INSTRUCTIONS , 4.1 Activation . 4.1.1 The TSC snail be activated and placed into operation for any event classified as an ALERT or greater.
. mee O t *
.D"
. men a
.m
[.fW]Yf
- ,y @' ,
, e ,..<.w.--
v$ EMERGENCY PLAN I'MPLEMENTING PROCEDURE EPIP 2.2 'l P . I. is . Page 3 of 65 , S' ,1.-.; : ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 ;f- ., , R,d. K Date 7/14/83 5 .
'Uh,@$
.ih NOTE . .
.u.
O
- 1) As specified in EPIP 1.3, " Plant and Site _'c ' ~
Evacuation", the TSC may be activated for events ' classified as a NOTIFICATION OF UNUSUAL EVENT at the discretion of the Emergency Coordinator.
- 2) Additionally, personnel designated to report to the "'
TSC may assemble there for accountability purposes upon an evacuation of the plant which may be - conducted due to the localized problem; e.g., an unanticipated airborne release within the Power - .
- Block Structure.
4.1.2 During normal working hours, setup of the TSC Working Area . should be performed by personnel normally assigned office space in the imediate area. - a) In such cases, setup of the TSC should be directed by the ' Support Services Supervisor or, in his absence, the Plant Performance Supervisor, b) Attachment 1, "TSC Layout", is provided as a reference for personnel to use in setting up the TSC Working Area. 4.1.3 During non-normal working hours, TSC setup should be l conducted by personnel assigned positions in tne TSC who first arrive on site. NOTE i In such cases, the TSC Supervisor upon arrival on site should direct TSC setup or may elect to delegate l' such responsibility. 4.1.4 Attacnment 2, "TSC Setup Instructions" are available for use ' Dy personnel involved in activating the facility. a) Security Force personnel shall be dispatched by the Security Shift Supervisor to unlock access doors, as required, and place the TSC Ventilation System in the Recirculation mode. b) The remainder of the setup should be performed as specified by paragraphs 4.1.2 and 4.1.3.
- l.:.N$ .'. ?
- :.". . w : . -
e <!T*~ [ **
, .m. ecque.
~=-('y fE; K t@C=:
r 1-w t m -
--o,- . - - , . . , - , e , - e , 1
. .m: . ,. 7
%q ..+ d..
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 ,
., dy.}j- 4 ..
Page o .; of 65.. ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 ' '.f.#. y! ..NId.9 WE i6 ' ! Date 7/14/83 *; < =:. ~ . 4 is.3
. .e-W.t r;. W:.bC . A +w.s c) The TSC Supervisor snould verify that all activities .N..I'(I.d required to set up and activate the TSC are .
' Ts. M.md satisf actorily accomplished. t -;pcc
.m.. .- w 4.1.5 After the TSC Ventilation System has been placed in the NNYM Recirculation mode, personnel present in the TSC or who
'dd
>'.~s . Y .yW initially arrive should verify that the TSC Radiation Monitors are on-scale, and not trending upscale or . u. >. irme alarming. 7~D F M Qlau:; Y'y, a) If an alarming condition is indicated, an attemot should' MJ,'f,?f.j be made to reset the alarm by depressing the RED reset
- .ff6.%
- outton on the monitors. A. ,#. ,M. .r..
b) If an alarming condition persists, the Site Radiation Tl?,;j.. ; - Protection Coordinator, OSC Supervisor or, if neither are '
. present, the on-snift Health Physics Technician should be contacted and access to the TSC restricted until .
" .gf
. Tr.
habitability of the area, as prescribed in EPIP 3.1, "On- J; *. ;f : . Site Monitoring", can be determined. %]-S
..--s. a. . WM.,.
NOTE O~?'i'v "
,g; .:;,
,.X.
@f'c;' 'It
. If radiological problems exist in the TSC, such problems more than likely, also exist in the OSC and $M %.;
other areas. In such cases, and as directed by the , Emergency Coordinator, . ,
- 1) Personnel specifically identified in EPIP 1.3, .
- " Plant and Site Evacuation", wno normally would be -
assigned in the TSC should report to the Control 2.,: Room. _.. ..
.a
- 2) The initial steps required to setup and activate ,
the ORAA should be completed, as specified in EPIP 9 .. 2.4, " Activation and Operation of the ORAA". Al. . s. , , tig.h.
.' .9' .R;.g;2 4.2 Staffing
..m.
4.2.1 Tne TSC staff organization is identified on Attachment 3, ;2 "UAEC Emergency Response Organization". a) Upon annunciation of the Evacuation Alarm, during normal working hours, personnel designated to staff the ~ supervisory roles and/or supoort functions in the TSC as identified on Attachment 4, "0AEC Emergency Response Urganization Positions" should proceed to the TSC.
- 0 s.. 2, . i l
,. d. M ;9 5 dIhc i
~poM.cc.?;
Y; perm.w;g,
' g' r ;- -
EMERGENCY,DLAN IMPLEMENTING PROCEDURE EPIP 2.2 - Page 5 ~f o 65 - 't Revision 5 i ACTIVATION AND OPERATION Oc THE TECHNICAL SUPPORT CENTER . Date 7/14/83 ..
.c NOTE _ ,
For completeness, Attachment 4 provides a listing of , all DAEC Emergency response Organization positions , including those in the TSC, OSC, and Control Room. b)UnlessdirectedotherwisebytheEmergincyCoordinator, individuals designated, to fill TSC positions, as specified in Attacnment 4 should assemble in the TSC and '-~'." - -- initiate response functions assigned. c) .If an individual designated as a Primary is not on-site, .; the position shall be filled by one of the alternate - - designees identified in the Emergency Telephone Book. g ,, d) If due to absences positions are unfilled, the Emergency Coordinator shall take action, as required, to fill the most critical positions and supplement the assemoled
- staff by further call-out or by contacting the Emergency --
Support Manager in the EOF. e) Should TSC activation be required during non-normal ~ working hours, personnel designated to staff key positions shall be notified and requested to report to the site, as prescribed in EPIP 1.2, " Notification". f) Positions identified witn an asterisk on Attachment 4, "0AEC Emergency Response Organization Positions", represent the augmented shift staff requirements,
~
prescribed by DAEC Emergency Plan, Table B-1. g) Positions identified with a double asterisk on Attacnment 4 are those additional positions for which staffing . comitments were made in tne DAEC Emergency Plan beyond those specified in DAEC Emergency Plan, Table B-1. NOTE Normally, the positions identified in f) and g) above will in'tially be filled. Subsequently, the Emergency Coordinator, at his discretion, may take action to modify the DAEC Emergency Response Organization staffing levels or alignment, as prescribed in paragraph 4.5.18, to maximize response capabilities available for the type of event wnich has occurred. .. a
* '2
- e
~
- .,mwww Y Yh$.
- ~ - - - -
T $- 4 -- --
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 lC. Page 6 of 65
~ ~ '
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 . Oate 7/14/83 . 4.2.2 Individuals shall be assigned to communciations and status ,, recording functions, as follows: , 3,q a) Control Room " Dedicated" Communicator - receive imediate ' plant status updates and problem descriptions, transmit information requests from the TSC to-the Control Room, ,
' ~
and act as the TSC Supervisor's personal communicator.
# '"N b)_ EOF " Dedicated" Communicator - provide unique or specialized plant status information, respond to questions and information requests received from the EOF, ~~
and act as the Emergency Coordinator's personal
- communicator.
c) Radiological Data Communicator - receive information . , regarding metecrlogical, effluent, and process flow . parameters for 'nput into the dose projection program; , _ . transmit request for and receive information regarding plant radiological conditions as indicated by ARMS, - Containment High Range Radiation Monitors, etc.; and act - as the Site Radiation Protection Coordinator's personal communicator, d) Radio Communicator - relay directions and information provideo Dy tne 5ite Radiation Protection Coordinator regarding initial deployment of the Off-Site Radiological Monitoring Teams via the Security / Radiological Survey radio and_ activities conducted by the On-Site Radiological Monitoring Team via the Operations Radio; in addition, relay information provided by the Technical' and Engineering Supervisor concerning in-plant repair and corrective actions; receive radiological _ survey information and monitor rescue, repair and operational communications via the Operations Radio. e) Radio coerator's Assistant - assist the Radio Operator in performance of assigneo function by adsising the Site , Radiation Protection Coordinator and the Technical and t Engineering Supervisor of radio communications, providing L the Radio Operator with messages from the Site Radiation l Protection Coordinator and Tecnnical and Engineering Supervisor to be transmitted and recording of information received.
- i. h j 5 5E:5.;
' ., .4. e : F - I
- . .;etap%ge.4
..*nme MMiT8'.$
~
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 7 of 65 - - Revision 5
~
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER , Date 7/14/83 f-t f) NRC ENS Communicator - monitor conversations and , information being transmitted between ENS extensions 'in , 4 the Control Room and NRC Operations Center in Betnesda, MD. and Glen Ellyn, IL. and provide status information, as directed by the Emergency Coordinator. g) Engineering Information Communicator - transmit detailed tecnnical information regarding plant status and corrective action options being pursued to engineering --- e - personnel located in the EOF, assist in coordinating engineering efforts being accomplished in the TSC with those being accomplisned by personnel in the EOF, and act -
- as the S,ite Design Engineering Supervisor's personal communicator. ,'
-h) Status Board Recorder - record pertinent plant problems and plant status information, as directed by the TSC Suoervisor, on the TSC Status Board to aid in maintaining personnel awareness of pertinent plant information. , .
i) Status Update Recorder - obtain plant and radiological status reports from tne VAX, highlight or otherwise uniquely identify changes from the prior status report, and display transparencies made of the status reports on , the overhead projectors. J. TSC Log Recorder - maintain the TSC Log, as directed by - tne ISC Supervisor. NOTE
- 1) Positions identified in paragraphs 4.2.2(a) through (f) are identified on the Emergency Assignment Tag Board and shall be filled, as prescribed in EPIP 2.1,
" Activation and Operation of the OSC".
. 2) The remainder of the positions, defined in paragraph 4.2.2 as well as those in paragraph 4.2.3, should selected from individual present on site or should filled by personnel called out, as the need is indicated.
4.2.3 Tne Administrative Supervisor should insure that sufficient clerical support is prov.ided in the TSC for the following purposes: a) Messengers (2) - assist in making copies of survey forms, status reports, etc. and perform routine typing and clerical functions, as required.
- :d.ll 3hh0-
_ . 7 - .y 3:;-
. .. M mLv.T_.' ".% 4
- Pf?qt@-qyW;
_ - - . _i S f ' C I
- ~ , , . , . . _ , , , _ _ , ~ . . _ , , -_ _ . ,, -
.y -
.~ .
a . .. 4 l ~ ' ai EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 . d 'Ji. .t.' g Page 8 of 65 L :G.N: \ ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 " h.$ W Wsp , Nik ~ Date 7/14/83.j,. . . .Q
~
J l
*. ..-::.- $?g'?
n:;{ ,1 l b) Switenboard Operator 'fG: M 9i.h,ff;p4j; .fM i c) Document Records Clerk - maintain records of information . .: . .q transmitted. ; aer q c..t.~:;;; v4C i NOTE "UJ I 5
. .y.? a ').f.:
- One of the messengers could possibly' assume this S ..'.
l function. "T.i .. .:.n . %Y .
~
. 4.2.4 The TSC Supervisor shall insure that an accountability check , .. Y is conducted for individuals who report to the TSC and that T;.' V,/;'" ,
- the completed Accountability Check form, provided in EPIP . :.;, .P. ,.Q l.3, " Plant and Site Evacuation", is provided to Security. c ' V.i
;o;,f..-y NOTE .3.... .
. ; v.~ 9i,;
Attachment 5, "TSC Supervisor Checklist", identifies
- key functional responsibilities and tasks which -'5,i should be completed by or under the direction of the :P.E TSC Supervisor. , -1 p'.:
a) A Security Force member should be dispatched to the TSC, as specified in EPIP 1.3, and he shall maintain k'h I a log of personnel who enter and exit the TSC during +.5j the course of an emergency for accountability ' purposes unless directed otherwise by the Emergency Coordintor.
.~
4.2.5 An NRC Site Team will. normally be dispatched from Glen Ellyn, IL., for events classified as an ALERT or greater. 2 - a) The TSC will serve as the b ase of operations for events classified as an ALERT. ,,
- d- 1;d b) The E0F will serve as the base of operations for events classified as a SITE or G'.NERAL EMERGENCY. -. ;- :1
; s.
l 4.2.6 NRC Site Team members inita'ly dispatched who are expected , l to be assigned to the TSC i the event does not escalate *? beyond tne ALERT classifict tion and their DAEC Emergency
. Response Organization counterparts are as follows:
! a) Site Team Leader - Emergency Coordinator
~
b) Protective Measures Coordinator - TSC Suoervisor and Site Radiation Protection , Coordinator ,, l ..
. . c: ~ . g Y{M[d$bItt;$ YWNNYh E3M
.L+
,I
[m
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 I". Page 9 of 65 ,(( . . ,[ ACTIVATION AND OPERATION OF THE TECHNICAL SU,PPORT CENTER Revision 5 -
.'f..E e,_. . ~
- I Date 7/14/83 . f-U -
c f.t .
,s$ .
^
c) Health Physics Assessment Coordinator - Site Radiation ~< '. 4,
!:l -' .l
- Pratection Co~ordinator ,'I ' ' ,
. q, d) Reactor Safety Coordinator - Technical and Engineering . : '- '
Supervisor " a . e) Emergency Response Coordinator - none . NOTE - -~ ! M .' s
- 1) If the event has a very low probability of escalating ", ff*
beyond the ALERT classification, the Emergency .
. Response and Recovery Director may choose to relocate Y :"'
to the DAEC to provide overall management.of Iowa ' GI Electric emergency response activities and interface > with the NRC Site Team Leader, ,
- 2) Additional NRC personnel may be dispatched as members of the initial Site Team contingent. Those .
identified above constitute the minimum. T' , 4.2.7 Additional members of the initial Site Team dispatched who may require access to the TSC include the Federal / State :. - .. Liason Coordinator and the Public Aff airs Coordinator. 1 4.2.8 Upon arrival of the NRC Site Team personnel, a briefing shall be conducted by or under the direction of the Emergency Coordinator which includes the following: a) Piant status, including major proolem areas and corrective actions in. progress or wnich are planned. , b) Radiological problems on site. c) Chronological event sequence, d) Meteoclogical and effluent release information. NOTE Items e, f, g and h, which follow, need not be reviewed in detail if the EOF has been activated since such actions should be reviewed in detail with the NRC during a briefing conducted upon their l arrival at the EOF. l e) Off-site radiological monitoring activities and results. f) Dose projection results and protective action recommendations that have been made.
. 5%l 2.*,.3 5.hIf
- A$."@.$$6W,
, ..."* .i'
\
; 7. .,
EMERGENCY. PLAN IMPLEMENTING PROCEDURE EPIP 2.2 / . Page 10 o. 65 J-
} ,, .
E q ACTIVATION AND-0PERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 l', ' Qc(
.s , . . . .
Date 7/14/83j Q '
. ; -Q, g) Protective actions that have been implemented by off-site .~ Ni authorities in the EPZ. .
f,&vt
. . . . : 9;
, n) Off-site notifications conducted and interfaces . . ' 'l :.
established. -
.? 2
+ gr
- 1) Prognosis of the event. , j ,
R.Aw;.i j) Potential naed for Technical Specification / License ';,.. exemptions. t a < NOTE . -' " ^
# , uj.
If the event has escalated to a SITE EMERGENCY, the Site G Team Leader, Protective Measures Coordinator and < Emergency Response Coordinator will in all likelihood, '
..F c "
depart the site and proceed to the EOF. 4.2.9 Additionally, the NRC Resident Inspector shall be notified - and is expected to-report to tne site. a) The NRC Resident Inspector is expected to be present - . primarily in the Control Room, as indicated in EPIP 2.5, "
" Control Room Emergency Response Operation", but may, at
. his discretion, spend a portion of his time in the TSC. .
b)-The NRC Resident Inspector should norcally provide status updates to NRC Operations Centers in Betnesda, MD. and Glen Ellyn, IL. via ENS extensions located in tne Control Room or TSC. , 4.3 Notification and Communications 4.3.1 Notification of corporate management; off-site agencies including the Linn and 8enton County Sheriffs and the State Office of Disaster Services; and the-NRC shall be accomplished, as specified in EPIP 1.2, " Notification". 1 NOTE During normal working hours, some or all of such notifications may be made from the TSC, as opposed to the Control Room, at the discretion of the Emergency Coordinator.
~
4.3.2 As part of tne Initial Notification Message, protective actions for the health and safety of the public snall be reconnended, if so warranted. .
.:L ll hw]
. =~#W71'5A
, ~
~
- SdNdNb[i!1'k
~
3'4
..5yM $.-.[ y$ dM
. s d. m
-- ~ , - - - - - -,w w. , - , - , , - . , , - - , _ .
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2
. Page 11 of- 65 - -
ACTIVATION AND OPERATION OF THE-TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83
~..-
a) If a release is in progress, an evaluation of projected off-site doses and development of protective action ' , recommendations shall be accomplished, as specified in
- EPIP 3.3a, " Manual Dose Projections", or EPIP 3.3b,
" Computerized Dose Projections", and CPIP 2.1, " Dose Assessment and Protective Action-Reommendations". ,
b) If no release is in progress, protective action recommendations shall be made based upon plant status ' with consideration being given to any evidence of or , potential for deteriorating core conditions, per PASAP 7.4, " Estimation of Potential Release Rate" and EPIP
- 3.3c, " Estimation of Potential Release Rate Based on Containment High Range Radiation Monitors". ,
4.3.3 The Emergency Coordinator shall be responsible for all off - site communications until the E0F has been activated, normally at the SITE and GENERAL EMERGENCY classification, and nas specifically assumed this function. a) Information to be reported regarding the event is identified in CPIP 1.3, " Activation and Operation of the EOF". b) Such information shall' be provided to local, State and Federal E0Cs on a periodic basis and following event reclassification. 2 c)_In addition, upon reclassification of the event, the Linn and Benton County Sheriff's Offices shall be notified. 4.3.4' Upon declaration of an ALERT, an open. continuous communications link shall be established with the NRC, as presecrioed in EPIP 1.2, " Notification", within one hour of
- the event, as required by 10CFR50.72.
a) Normally, the communications path to be used will be the NRC ENS circuit, unless that communications link is not operaole. b) Status information to be reported to the NRC upon initial
~
notification has been defined by the NRC and is included as an attacnment to EPIP 2.5, " Control Room Emergency Response Operation". c) Further information regarding the event, status updates,
~
etc. will normally be provided by the NRC Resident Inspector who will be located in the Control Room or TSC.
. . . .. . . d4.h
- :;7m:-
,-v.-
a . yf=Qy .
.:- ' = .v.-!: ~ .
, . - . - , 4 - , . ,, , _,_-.w.- _ - , . . . . .~. _m_.. . . , _ . . , - - _ , _ _ - - . . ,,, .
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 . Page 12 of 65 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 s ~r - Date 7/14/83 " g _. NOTE - [,. . Upon declaration of an ALERT, ENS Communicators will be . ~ i assigned to the Control Room and TSC. If the event escalates to a SITE or GENERAL EMERGENCY, an ENS Communicato' will also be assigned in the EOF. Specific " - information regarding plant status, however, will , normally be provided by the NRC Resident ~ Inspector from * " the Control Room. 4.4 Status Monitoring and Trending 7
- 4.4.1 Plant status information which is to be initially reported .s has been established in a report format on the VAX.
a) Status information will be entered in the VAX from the Control Room and subsequently be available at the printer terminal in the TSC Communications Room. b) Update reports should be available at approxiamate 15 , minute intervals or as otherwise directed by the Control , Room Coordinator. ; , c) Status report printouts should first be reviewed by the Status Update Recorder and changes from the preceding report and/or new information highlighted or otherwise uniquely identified. d) A transparency should then be made of the status report printout for display purposes in the TSC. e) The original printout report shall be provided to a Document Records Clerk, designated by the Administrative Supervisor, for historical purposes. f) In the event that the computer is unavailable, such reports should be transmitted verbally to the Status Update Recorder. NOTE Forms for use by the Status Update Recorder are contained in EPIP 2.5, " Control Room Emargency Response Operation". 4.4.2 Status information being ' reported, its frequency and report format may be modified at the discretion of the Control Room Coordinator and TSC Supervisor.
.: -- . b
- .=w &q:;:g cw ::n -n -3
~
O.WE b.-:m
.'gg,N...: b
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 13 of 65 - - ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 a) Information to be reported should be based on the typ.e of event, plant conditions deemed to be pertinent and the event phase. , b) The report form on the VAX can be modified, adding or deleting information entries, as is appropriate. c) Additional or supplemental information may be reported verbally to the Status Update Recorder. ~~' 4.4.3 The dedicated telephone circuit between the TSC and Control Room should be used by the Control Room Communicator under
- the direction of the TSC Supervisor for the fQilowing purposes:
a) Verify plant status information received and obtain additional amplifying information, as needed. b) Discuss response actions that are being taken to resolve specific problems encountered. c) Review operational evolutions and repair activities that are planned and report status during their execution. d) Serve as a means for the TSC Supervisor and Emergency Coordinator to talk directly to the Control Room Coordinator. NOTE The TSC Supervisor and Emergency Coordinator may also make use of the intercom when discussing planned response actions and evaluating corrective action options to be i pursued where interests can best be served by talking l simultaneously to key supervisory individuals located in !' the Control Room and OSC. 4.4.4 Radiological status information which is to be recorded and provided to the Site Radiation Protection Coordinator, upon request, throuan the Radiological Data Communicator is identified in $ PIP 2.5, " Control Room Emergency Response [ Operation". l a) Information which is to be available for reporting i includes meteorological, effluent and process flow data for input into the dose projection computer progrm, as well as ARM levels, Containment High Range Radiation i Monitor readings, and related radiological parameters I availaole in the Control Room. i
~
l
~~ . . : _,
, .h j.k ; . ,, ,
f .~';--: * -: ~
yn. EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 .
.f 3 . w M.* ** *
- Page 14 of 65 . . MW:
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 id'h h!MM ' Date m ecMj,m; 7/14/83 g ,.,@,'ffy %. v.s
..w em.7.r.v
-c.r .n;mp.a::,..a b) Pertinent information which also should be available to .(Ebge,g tne Site Radiation Protection Coordinator includes on- sh4 -
site radiological survey and analysis data obtained as
~! .'N [M O:
prescribed in EPIP 3.1, "On-Site Radiological d. Monitoring"; off-site radiological data reported, as-described in EPIP 3.2, "Off-Site Radiological
? AM *
. S. .
Monitoring", and CPIP 2.1, " Dose Assessment and .y. jfll + Protective Action Recomendations"; and post-accident 1 E9.v 0 ' sampling and analysis results conducted in accordance .w m%y' .. E. 4 i with the applicable PASAPs. q6W.M~y+;
. f;:s.m
, ~
NOTE p'%A@.:.#W.1 Upon activation of the E0F a. d n the subsequent assumption 'Jgyf% of off-site monitoring'
. ; W *f. tM Coordinator functions, the Site Radiation . .
Protection s primary focus should be directed i p.gJ ip towards input data requirements to enable the performance iga.py of dose projections and on-site /in-plant radiological < se,5.p
,4:jc. .,%
information. ~ m.. .
- u-p.2:
4.4.5 The dedicated telephone circuit between the EOF and TSC J. M4' should be used by the EOF Communicator under the direction (ajif; i p @fB of the Emergency Coordinator for the following purposes: .g,g g { 3 y.~ ..q. a) Provide amplifying information regarding plant status and 4;N!RM .r' clarify information indicated on the Plant Status report, ' ~f,; : . :.y as requested. Q~g. fg b) Provide imediate updates to tne E0F regarding changing 'I conditions, new information, etc. .
, ; . x.- .
c) Discuss the status of response actions being taken and y .4 _ which are planned. .; , 1 d) Receive information regarding response actions being taken by personnel in the E0F and actions- being taken by [kk "NM9G local, State and Federal agencies and support .Y);a 4. mh.. :.J organizations. 7 J: e) Serve as a means for the Emergency Coordinator to talk ' ' 9f directly to the Emergency Response and Recovery Director. .y NOTE
.i.e-
' '~
This dedicated comunications link can also be used by key TSC Supervisory personnel to talk directly to their v-' counterparts in the EOF. _ 's
.*. ~.. .~.
..~i'[O
~ M.-
N-m g.~.a i
- A.Y ?k
~
. W S ejs* M s.s e- - m
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 - Page 15 of 65 .. ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 A .- Date 7/14/83 4
. . ' .;f
~
TSC SUPERVISORY PERSONNEL COUNTERPARTS IN THE E0F .
.a.
Emergency , Coordinator Emergency Response and - Recovery Director -
, ' ij
_. .y. TSC Supervisor Radiological and EOF i i", Manager * - Site Radiation Protection Radiological Assessment - '58 Coordinator Coordinator - Technical and Engineering Technical and Engineering ,
- Supervisor Support Supervisor Security and Support Support Services Supervisor Coordinator 4.4.6 Trending of important plant parameters will be accomplished, .
as directed oy the Control Room Coordinator in conjunction ~ with the TSC Supervisor. 4.4.7 Trending of key plant and radiological parameters should be accomplished in the TSC, either in lieu of or in-support of - such activities in the Control Room. a) The TSC Supervisor should coordinate the development and maintenance of plant and radiological parameter trends with the Control Room Coordinator and Site Radiation Protection Coordinator, b) Information regarding such trends shall be reviewed with . the key supervisory personnel in the Control Room and EOF. l c) Parameter trending may also be accomplished in the EOF in coordination with that being accomplished in the TSC and - Control Room, d) Parameter trends should be projected ahead and hence,
- serve as a source of information regarding event reclassification and protective action decision making.
4.4.8 Parameters to be considered for trending include, but should not be limited to: a) Nuclear instrumentation; e.g., if shutdown has not been achieved. b) Reactor Vessel water level and pressure. i
, ,1
- 1. 5. i . f,
......a..;
~~
. 3
1 ' :-
- EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 16 of 65 -
ACTIVATION AND OPERATION OF THE TECHNICAL' SUPPORT CENTER Revision 5 , Date 7/14/83 ; , k. c) Containment pressure and temperature. - d) Suppression Pool water level and temperature. ,
^
4;
<-i e) ARM and Containment High Range Radiation Monitor levels. -
f) Radiological effluent concentrations. - -
^ ^ * ' "
4.4.9 Additional plant parameters will be trended, as appropriate, based upon the event and plant condition, as identified by the Control Room Coordinator or TSC Supervisor. ,,
*- 4.5 'Overall Operations 4.5.1 The TSC, under the overall supervision of the TSC -- :
Supervisor, shall perform the following key functions: a) provide assistance to.on-shift operating personnel in determining the optimum method (s) available for terminating the transient and radiological releases that may be in' progress. b) Coordinate, as necessry, engineering, temporary modification, and emergency repair work that will assist in mitigating the consequences of the event. c) Evaluate changes in system and radiological parameters that have occurred or which are projected to occur and recommend relcassification of the event, as warranted, to the Emergency Coordinator. d) Communicate with local, State, Federal _ and corporate organizations, as required, to facilitate application of the combined resources of such support groups and to permit _ decisions regarding protection of the public to be based upon current information. . NOTE l If the EOF is not activated, plant status and radiological information should be provided from the TSC to the Linn and Benton County Emergency operations Centers and the State of Iowa Office of l Disaster Services. l l
~
.~.
. udM. 39ML i
) ....WG 7,., W.- ]. t-I c MN5d8E4 f]
,Y$1 C*M";.4 r = f2?f'." MM';.3 l
~ ^
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 ,.- Page 17 of 65 ~: Revision 5 ' :- ACTIVATION-AND OPERATIOi 0F THE TECHNICAL SUPPORT CENTER . , . ..
. Date 7/14/83 '- ",
4.5.2 Prior to declaring the TSC operational and so informating - tne Emergency Coordinator, the TSC Supervisor should- '
- , \
a) Verify TSC layout and setup, as prescribed in Attachment - -* 1, "TSC Layout" and Attachment 2, "TSC Setup - Instructions", is complete and that req,uired equipment is operable. -
' ' " ' + "
b) Verify that TSC staffing, adequate to enable performance of the required functions, is in place. ,2 NOTE . Attachment 4, "DAEC Emergency Response Organizaiton Positions", identifies all of the key TSC Positions which normally will be staffed upon initial r' , activation. c) Assure that an accountability check has been conducted - for all personnel in the TSC and that the Accountability Check form, provided in EPIP 1.3, " Plant and Site Evacuation", has been provided to Security. d) Assure that access control for the TSC has been established by the Security Shift Supervisor, as specified in EPIP 1.3. e) Insure that updated plant and radiological status information is displayed and available for use oy personnel in ,the TSC. 4.5.3 Upon declaration of an ALERT, the Site Radiation Protection Coordinator shall:
. - .: .n;.Q.4=.;.'
- w=1+=+ 8 f
' ff. MF.. ..F** = .
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page '18 of 65 Revision 5 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Date 7/14/83 a) - Evaluate plant conditions and effluent monitoring systems to determine if a significant release has occurred,-is in progress, or may potentially occur. - , b) Evaluate dose projections 'and protective action recommendations determined by the Operations Shift Supervisor, if already accomplished, or c) Perform dose projections and develop protective action : recommendations, as prescribed in EPIP 3.3a, " Manual Dose Projections", er EPIP 3.3b, " Computerized Dose Projections", and CPIP 2.1, " Dose Assessment and Protective Action Recommendations". d) Modify, if required, and provide protective action recommendations to the Emergency Coordinator for subsequent transmittal to local, State and Federal EOCs. 4.5.4 Following evaluation of the potential off-site radiological consequences, the Site Radiation Protection Coordinator shall: a) Advise the Emergency Coordinator and OSC Supervisor of - the need to conduct off-site monitoring. NOTE Normally, off-site monitoring shall be accomplished for events classified as a SITE or GENERAL EMERGENCY.
~ As a precautionary measure, teams may be dispateched to a " ready" location during an ALERT when the potential exists for a significant radiolocial release from the plant.
b) Provide information regarding the projected or ongoing release to the OSC Supervisor for dissemination to the Off-Site Radiological Monitoring Teams, c) Assume control of the Off-Site Teams upon being advised of their readiness by the OSC Supervisor. d) Upon being authorized by the Emergency Coordinator, dispatch the teams. , l
.\
- 3. . ..{, .
' .N &. .^. 'f.'}
. x.W-WrWMw ! I
*?#Mff$97i j
-+.wxr m n l l
, c l
EMERGENCY PLAN IMPLEMENTING PROCEDURE . EPIP 2.2 Page 19 of 65 - ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 - e) Maintain. control of the Off-Site Teams until relieved of the function by the Radiological Assessment Coordinator in the E0F, as prescribed in CPIP 2.1, " Dose Assessment and Protective Action Reconnendations". 4.5.5 Upon being advised of an event classified as an ALERT, the Emergency Coordinator should report to the Control Room, if not already present, to evaluate the situation whicn exists, ' verify that required notifications have been made or are in progress, as presecribed in EPIP 1.2, " Notification", and initially-determine response options to be pursued.
- a) Upon being advised by the TSC Supervisor that the TSC has been activated, the Emergency Coordinator should .
report to the TSC, brief the assembled personnel and provide direction to the Site Radiation Protection Coordinator and TSC Supervisor as to response actions and tasks to be pursued by TSC staff personnel, b) Responsibilities assigned to the Emergency Coordinator which are prescribed throughout the EPIPs have been consolidated in EPIP 7.1, " Emergency Coordinator Duties". NOTE While the Emergency Coordinator's normal location during an emergency is the TSC, the Emergency Coordinator is free to reloacte to any area he may so choose. 4.5.6 Logistics and administrative support needs shall be provided .. under the overall _ supervision of the Security and Support Supervisor and shall include the following: a) Procurement, expediting and warehouse support. b) Food, clothing and transportation needs. c) Temporary office facilities and communications, typing / word processing and reproouction equipment. NOTE
- 1. Arrangements for support services of this nature should be coordinated with the Support Services Coordinator in the EOF.
. 3. . -
' ..- e.d 7lk..O*'-
g-+.s;.-:
-u-...--.
,_ , . s. , .___....r -
e. I - EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 20 of 65 Revision 5 ACTIVATION.AND OPERATION OF-THE TECHNICAL SUPPORT CENTER Date 7/14)83
- 2. Attachment 9 " Security and Support Supervisor Checklist", identifies functional resposibilities ..
and tasks which should be accomplished by the Security and Support Supervisor. _. 4.5.7. Upon activation, the TSC Log Recorder, under the overall supervision of the TSC Supervisor, shall assume responsibility for maintenance of the TSC L'og, provided as ' Attachment 10, "TSC Log Sheet". a) Log entries need not duplicate information contained in plant and radiological status reports, survey records
- and the like, but should be sufficiently. detailed to ,
enable restructuring of a chronological history of events, response actions, decisions, and important communiques which occur. b) Attachment 11, " Log Entry Topics", identifies typical types of information which should be recorded. c) Otner key supervisory personnel in the TSC may also direct that specific entries be made in the TSC Log, or, , alternatively, insure that infcrmation and decisions I pertinent to their assigned functions are recorded separately using the TSC Log Sheet format. 4.5.8 Additionally, each communicator; i.e., the Control Room, E0F, and ENS communicators should record pertinent communications data transmitted on separate TSC Log Sheet forms. 4.5.9 The TSC Supervisor shall coordinate with the Control Room J Coordinator and take action, as required, to insure that ! personnel in the TSC are appraised of plant status and operational problems being experienced. a) The TSC Supervisor shall provide overall direction the the Technical and Engineering Supervisor regarding . ! problems encountered and response options to be pursued and insure that the Tecnnical and Engineering Supervisor is coordinating response activities engaged in by TSC l staff personnel with the Control Rocm Coordinator and Technical and Engineering Support Supervisor in the EOF. f-f o yo 1
~ .;-na@.5ae :;Mf!~M '
...::= _ ,
l
, e. a EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2-Page 21 of 65 ~ -
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 b) The TSC Supervisor should keep the Site Radiation . Protection Coordinator informed of plant status; problems encountered; response action options being. considered, particularly those 'that may require access to the plant; and parameter trends, which, if not reversed, may result in significant rad.iological changes throughout the plant and/or releases from the plant. 4.5.10 The TSC Supervisor should be advised by the Control Room Coordinator of the need to dispatch operators to local plant areas to. enable performance of operating and monitoring functions. e a) Such notification should be provided in advance, whenever possible. b) The Site Radiation Protection Coordinator should be consulted prior to dispatch to permit evaluation of the potential radiological hazards in accordance with EPIP 4.3, " Rescue and Emergency Repair Work". c) If access is required through or into an area where potention radiological problems exist, the OSC Supervisor shall insure that adequate protective
-clothing and equipment is donned before entry.
NOTE The Site Radiation Protection Coordinator shall determine the protective measures to be employed and whether or not personnel being dispatched should be act spanied by a Health Physics Technician. 4.6.11 To the extent possible, all operation activities should be conducted in accordance with approved procedures, a). Where procedural requirements cannot be met due to abnormal system configuration problems or other conditions which make the procedural steps inconsistent with the basis, TSC staff personnel may oe assigned to assist the Control Room Coordinator in preparing temporary changes or developing temporary procecures. b) The normal administrative practices governing temporary changes to procedures and temporary procedures should be implemented unless'such practices have been waived by the Emergency _ Response and Recovery Director.
. 'W
. _ _ -c___. _
s e EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 22 of 65 ACTIVATI'ON AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 4.5.12 Situations may arise when response actions must be taken by operations personnel, irrespective of procedural , requirements. d a) In such cases, the TSC Supervisor should be informed of such ac' ions taken. b) Where deemed appropriate, TSC staff personnel should be ' directed to review the actions taken and determine if future operational activities may, as a result, be inhibited.
- 4.5.13 Likewise, adherence to Technical Specification requirements 4 should De maintained.
a) In the event that deviation from Technical Specification requirements becomes necessary, reasonable action that departs from a license condition or Technical Specification in an emergency, when such action is immediately needed to protect the public health and safety, is permissible, as specified in 10CFR50.54(x). b) Prior to taking such actions, approval shall be granted, at a minimum, by a licensed Senior Reactor Operator, as specified in 10CFR50.54(y). NOTE Time permitting, the need to deviate from license conditions or technical specifications should be approved by the highest levels of management holding a valid SR0 license as well as by the Emergency Coordinator and Emergency Response and Recovery Director. c) As noted in EPIP 1.2, " Notification", the NRC shall be notified in accordance with 10CFR50.72 or emergency circumstances requiring such protective action before such action is taken, time permitting. NOTE As action planned which is in violation of license conditions and Technical Specifications shall not be taken unless such action is immediately neeced to protect tne public nealtn ano safety, ee O h A N g %* e m ee $
~
- f.sQ* ',. . e .
- f:\
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 23 of 65 ACTIVATION AND GPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 4.5.14 Recommendations with respect to reclassification of the . event shall be provided to the Emergency Coordinator oy the TSC Supervisor and Site Radiation Protection Coordinator. NOTE Upon reclassification of an event to' a SITE or GENERAL EMERGENCY, personnel determined to be non-essential shall be evacuated from the site to the ORAA, as specified in EPIP 1.3, " Plant and Site Evacuation", and EPIP 2.4, " Activation and Operation of the ORAA". a) Recommendations regarding such reclassification based upon plant status may be provided to the TSC Supervisor by the Control Room t,oordinator, or may be basea upon an evaluation of plant conditions conducted by staf f personnel in the TSC. b) Similarly, recommendations based upon in-plant and off-site radiological considerations may also be provided to the TSC Supervisor by the Control Room Coordinator or directly to the Emergency Coordinator by the Site Radiation Protection Coordinator. c) Until the EOF is activated, or as otherwise directed by the Emergency Response and Recovery Director, the Emergency Coordinator shall authorize event reclassification and shall be responsible for notifying off-site agencies of such event classification changes. NOTE In addition to notifying the local, State and Federal EOCs of such reclassification, the Linn and Benton County Sheriff's Offices shall also be notified. d) Additionally,, for all events classified as an ALERT or greatar, a written report shall be developed for distrioution to all off-site EOCs within 8 hours of de-escalation which summarizes the event, response actions taken and in progress by Iowa Electric, and significant problems wnicn require further evaluation before resolution.
~
, . ..J. .l $ .e.) .
- e. _ .' 3 yN1-9-*7 . *
~* . , i EMERGENCY PLAN IMPLEMENTING PROCEDURE ~ EPIP 2.2 Page 24 of 65 ~' ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 4.5.15 When significant changes in plant status occur or when new information relevant to response actions being taken off,- site or support activities being accomplished in the EOF, the Emergency Coordinator 'should insure that all personnel in the TSC are appraised. a) Pertinent' changes /new information should be displayed on the Status Board and additionally, briefings should be conducted, as directed by the Emergency Coordinator, b) The TSC Supervisor shall insure that the Control Room Coordinator is appraised of pertinent developments. c) The Security and Support Supervisor shall insure that pertinent information is also provided to supervisory personnel located in the OSC and ORAA and who then shall disseminate such information to personnel assembled at those locations. 4.5.16 Upon activation of the E0F, the TSC shall be relieved of the . following functions: a) Off-site communications, including follow-up notifications with local, State and Federal agencies. b) Interface with off-site support organizations, industry support groups and contract firms. c) Dose projection and dose assessment activities. d) Off-site radiological monitoring and assessment activities including coordination and interf ace with local, State and Federal organizations involved. e) Development and transmittal of protective action j recommendations for the public within the Emergency Planning Zone (EPZ). ! f) Upgrading. and downgrading of the event classification. i g) Deactivation and connencement of recovery activities. 4.5.17 Also, upon activation of the EOF, the following key communiques shall be made by designated personnel in the EOF, as follows: l l l I.5 ".
... um., , .
?.$b m:mw I
l
t' EMERGENCY PLAN IMPLEMENTING PROCEDURE s\ EPIP 2.2
? i '
Page 25 of 65 ' ' ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 a) The Emergency Response and Recovery Director shall .
. specifically. inform the Emergency Coordinator that the EOF will assume responsibility for all off-site communications and that he has assumed responsibility for;the decision to , notify and recommend protective actions to off-site authorities.
~
b) The Radiological Land EOF Manager shall inform the county, State and Federal Emergen,:y Operations Centers (E0Cs) that the EOF is in operation and that the EOF and off-site dose assessment, radiological monitoring and protective acti.on decision making activities. , c) The Radiological. Assessment Coordinator shall contact the Site Radiation Protection Coordinator to relieve the ' site of tha responsibility for off-site radiological' < monitoring and assessment of activities including dose i .
-projection.
4.5.18 The Emergency Coordinator should periodically assess the adequacy of response actions being taken by the OAEC Emergency Response Organization and support assistance being provided by the'E0F. , m a) Wnere . functional. support capabilities can be imoroved by ' additional manpower 'and/or equipment and/or where ( , additional technical or craft' support is required, the ' Emergency Coordinator shall appraise the Emergency _ Responsa .and Recovery Director. of sucn needs and direct appropriate supervisory personnel to coordinate such ' needs through the Emergency Supporst Manager. in the EOF. b) Wheretheres'pbnseemphasisneedstoberedirecteddue to the type of event, event phase or otner> extenuating conditions, the Emergency Coordinator shall appraise the Emergency Response and Recovery Director of the . conditions and provide recommendaticns -to' modify the , structure of the DAEC or Corporate , Emergency' Response Organization to promote suitable response. 4.5.19 Where response actions will be required' oven a protracted , l period of time, the Emergency Coordinator, stall take action to insure that personnel staffing 'and Shift assignments are j
'made, so that continuous . coverage is apilaale for all ,
required functions and where possible, an Attempt to h. ' equalize personnel experience between shifts shculd be
, ,,, made. ,
,T - ,s .
\ -
~
l > e 9 m s S .
..h _ _ . _ . _ _
_3
i EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 26 of 65 ~ I
, ACTIVATION AND OPERATION OF THE TECHNICAL. SUPPORT CENTER Revision 5 s, .' i-Date 7/14/83
'\ _ , ,
/ ) '-
xs a) Responsibility for insuring that such planning is s ,i ,' accomplished will normally be delegated to the Secur.ity
;' L
> and Support Supervisor.
'~o-
, - b) The, augmented shift staffing guidance, provided in DAEC Emergency Plan, Table B-1, and as indicated on
's Attachment 4, "DAEC Emergency Response Organization
- Positions" should be followed at a min'imum except where ,
s the type of event and/or event phase require alternative
,) staffing levels or permit a relaxation.
c) In' addition to on-site response center staffing. c consideration must be given to DAEC assigned personnel 5 . . . performing functions off-site including the Off-Site
< Monitoring Teams, and personnel located at the ORAA, ORAL and UDEF.
4.5.20 As plant conditions begin to stabilize and reclassification of.the emergency to a lower classification is being
' conducted, action should be initiated to develop a recovery plan.
a) Recovery planning shall be accomplished as specified in EPIP 5.2,-" Recovery and Reentry". b) . Deactivation of both-the DAEC and Corporate Emergency . Response Organizations in part or in whole and transition to the normal operational organization or to a recovery organization shall be specified as part of the recovery plan. NOTE Deactivation should not be accomplished until the requirements of EPIP 5.1, " Deactivation of the Emergency Response Organization", have been met. j kw \
- ;,.. u..;.
Iy . 1! . N'
'\
I v - k-r&&*"d
.:/ r n=:.:
N . ~ . =**_ Q *?!.T :
.J . <
(f \
. yA ,
,n r 6
~
i
F y-1
.1 EMERGENCY PLAN :Ir4PLEMENTING PROCEDURE EPIP 2.2 p
9> '5
. Page 27 'of 65 o
r ACTIVATION,AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 P - Date 7/14/83
/ '
f fy 4.6 Technical Evaluation and Corrective Action Activities . 4.6.1 Based upon the postulated (or known) initiating event and current plant status information, the TSC Engineering Staff, under tne direct supervision of the Technical and Engineering Supervisor shall perform the following
~ functions:
a) Evaluate available options which will aid in terminating the transient and enable the plant to be returned to a
, safe, stable configuration.
s a. Ns f'* ,'[> ' r b) Review as-built drawings, specifications and other engineering data to insure that technical evaluations are conducted with the latest information and that operational evolutions are properly planned.
/
NOTE Attachment 6, " Technical and Engineering Supervisor Checklist", identifies key functional responsibilities and tasks which should be completed by or under the direction of the Technical and Engineering Supervisor. 4.6.2 In attempting to define and develop response options, the Technical and Engineering Supervisor should evaluate key parameter trends to assure that alternatives being considered are: a) Appropriately sequenced, if parameter dependent. b) Unaffected' by interlock logic which may be actuated based i upon existing trends. c) Not dependent on support systems which may not be !. available, based upon projected trends, at some future - eLi : time. ,. be lff 4.6.3 In developing response options, the Technical and L
- Engineering Supervisor shall . coordinate with the Site
- f Radiation Protection Coordinator for tnose options where
.g' access to existing or potentiial _ radiologically hazardous areas may be required.
i 4.6.4' Corrective action options avadable to be taken should be reviewad with appropriate ke) supervisory personnel in the l Control Room, TSC and OSC. l. i
~
l 3 . .:. . l- . ! , ,.j. ' n r: l- .. . . . - . . . l E
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 28 of 65
't ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 a) Where several alternative courses of action exist,
. decisions as to which course to follow will be as ~
directed by the Emergency Coordinator. b) Response options which violate license conditions or Technical Specifications should not be selected unless a waiver of such requirements can be granted.
~
NOTE This does not preclude taking action if such action is immediately needed to protect the health and safety of
- the public. Response actions thus taken are permitted by '
10CFR50.54(x) and (y), as discussed in paragraph 4.5.13. 4.6.5 Where alternative courses of action taken to mitigate the consequences of the event are accomplished by placing systems in abnormal configurations, the effects that such off-normal modes might have on future operational evolutions shall-be evaluated. a) As. appropriate, temporary procedures for off-normal operating modes should be developed. b) The Control Room Coordinator shall insure that operating personnel are briefed upon relief or shift turnover of such temporary procedures which have been implemented. 4.6.6 The Technical and Engineering Supervisor should consult with the Control Room Coordinator to identify temporary modification or emergency repair work which, if accomplished, would assist in mitigating the consequences of the accident or terminating the release. a) Where off-site engineering support is desired to augment efforts underway in the TSC, the Technical and Engineering Support Supervir.or in the EOF should be contacted. b) Emergency repair work to be accomplished shall be conducted as prescribed in EPIP 4.3. 4.6.7 Prior to implementation of response options and emergency repair work, expected changes in plant status and the potential radiological consequences to personnel involved in the activity or to the public should be projected, in accordance with dPIP 4.3.
't
-
- S;.64.lA .
~
Y$$5Y5 b?.5.*
.Mcip%?.ri :
l 1 [~ .j
e . EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 29 of 65 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 a) Should unexpected conditions occur, initiate action to stop the escalation and reevlauate alternative corrective action steps. . b) Should conditions become worse,' recomend escalation of the emergency classification, if appropr.iate. 4.6.8 In restoring the plant to a safe, stable configuration during an event where core degradation has occurred or where significant quantities of radioactive material have been released or are available for release (transport) from the Reactor Coolant System, consideration should be given to minimizing the spread of radioactive contamination to other areas of the plant and containing the radiological hazard to as few systems and as small an areas as possible. a) The Technical and Engineering Supervisor should be alert to this potential and insure that this type of planning for restoration of the plant to a safe configuration is conducted during accident mitigation. b) Such plans should be reviewed with the Control Room Coordinator and procedure's revised or developed, as appropriate, to control such activities. - 4.7 Emeroency Radioloaical Activities NOTE Attachment 7, " Site Radiation Protection Coordinator Checklist", identifies key functional responsibilities and tasks which should be completed by or under the direction of the Site Radiation Protection Coordinator. 4.7.1 The Site Radiation Protection Coordinator shall insure that necessary protective measures are instituted for the l radiological safety of all personnel on site. l l
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 1
~
Page 30 of 65 l ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 -'
'Date 7/14/83
_ 4 a) In the event of a severe or potentially significant event which results in or potentially may result in significant on-site radiological hazards, priority shbuld be given to determining assemly area habitability and assuring continued acceptability thereof, as prescribed in EPIP 3.1, "On-Site Radiological Monitoring". b) If habitability of the assembly areas is unsatisf actory or potentially may be in jeopardy, the Site Radiation Protection Coordinator should recommend, to the Emergency Coordinator,-evacuation of such areas and reassembly at alternate locations. o NOTE
- 1) For all non-essential personnel and for all but the most critical response personnel, the ORAA should be activated, in accordance with EPIP 2.4, " Activation and Operation of the ORAA", providing an off-site release is not progressing towards Palo.
- 2) If the habitability of the ORAA is jeopardized by an off-site release, an alternate off-site assembly location shall be selected by the Emergency Coordinator in consultation with the Site Radiation Protection Coordinator and Emergency Response and Recovery Director. It is recommended that the Off-Site Decontamination Facility I,0DEF), located in Cedar Rapids, be given first consideration as the alternate assembly area.
c) Critical emergency response personnel shall relocate to an alternate location on site, as soeciied in EPIP 1.3,
" Plant and Site Evacuation", and EPIP 3.1, "On-Site Radiological Monitoring".
4.7.2 The Site Radiation Protection Coordinator shall also
-implement the requirements of EPIP 3.3b, " Computerized Dose Projections".
NOTE In the event that the VAX is inoperable, dose projections shall be-accomplished in accordance with EPIP 3.3a,
" Manual Dose Projections".
a) Until the EOF has been activated, the Site Radiation Protection Coordinator shall also implement the requirements of CPIP 2.1, " Dose Assessment and Protective Action Recommendations". m
.. _ 2.
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 31 of 65 ~ - ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 - Date 7/14/83 b) The Emergency Coordinator shall be responsible for . notifying and recomending protective actions to off-site authorities, as specified in CPIP 2.1, " Dose Assessment and Protective Action Recommendations", until relieved of this function by the Emergency Response and Recovery Director. NOTE Until specifically relieved of this function by the Emergency Response and Recovery Director, this responsibility shall not be delegated.
.o
~
4.7.3 Input data required to enable conduct of dose projections includes effluent concentrations and release point process - flow from the KAMAN System, and meteorclogical data; all of which are available in the Control Room anr1 provided to the Site Radiation Protection Coordinator by the Back Panel Communicator, a) The dose projection methodology employed assumes the accident source term specified by TID 14844, " Calculation of Distance Factors for Power and Test Reactor Sites"; hence, unless significant core damage has occurred, the projected dose rates which are calculated should be extremely conservative. b) If a radiological release is in progress, an indication that core damage has occurred will be reflected by activity concentrations detected on the intermediate and nigh range KAMAN Effluent Monitoring System detectors. NOTE l If the effluent activity concentration can still be l monitored using the Normal Range Monitor (Upscale Levels of .05 uCi/cc), the potential off-site consequences for g an elevated-release are slight, assuming Standby Gas Treatment System operation. For a ground level release from the Reactor Building, the IDP program will predict
, excessive Thyroid doses, assuming a 12 hour release
! duration, from 2 to 10 miles. If such is the case: a) Calculate the ratio of iodine to noble gas as measured by the KAMAN System Normal Range Monitor Detectors (Detector #1 for Noble Gas; Detector #3 for iodine). b) Enter the ratio calculated into the IDP program and recalculate projected doses. l
< *ed_ ef - ee .
,-- 4 - ... _
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 32 of 65 ACTIVATION AND 0PERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 -- - Date 7/14/83 c) Determine protective action recommendations, as appropriate, with particular attention directed at projected thyroid doses. - c) If a release is not in progress, an indication of core damage will be reflected in elevated radiation levels detected by the Containment High Range Radiation Monitoring System. NOTE If excessive radiation levels are detected, an indication
- of fuel damage may be obtained by implementing PASAP 7.3,
" Containment High Range Radiation Monitors". A more definitive estimate of core damage may be obtained by drawing and analyzing post accident samples in accordance with PASAPs 2.0, 3.1 thru 3.11, and 7.2.
4.7.4 ~ 0ff-site radiological monitoring shall be directed by the Site Radiation Protection Coordinator until relieved of this function by the Radiological Assessment Coordinator. NOTE If radiological conditions at the plant are of sufficient severity to require any extensive off-site monitoring, I the Site Radiation Protection Coordinator-should I recommend activation of the EOF to the Emergency l Coordinator, regardless of the event classification, and ! transfer this function to the EOF. a).CPIP 2.1, " Dose Assessment and Protective Action Recommendations", provides guidance for directing and l controlling the Off-Site Teams, while EPIP 3.2, "Off-Site I Radiological Monitoring", provides instructions l associated with plume monitoring and tracking for use by monitoring team personnel. l b) Communications with the teams should be conducted using the Security / Radiological Survey Radio System. i, 4
. ,;m p l
,=)-'~.:y'.yu*f nD ', %'ii.1 : :
1
-EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 33 of 65 ACTIVATION AND OPERATION UF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 NOTE _
Instructions associated with operation of the radio are provided as Attachnytnt 8, " Radio Console Operating Instructions". 4.7.5 Projected off-site doses should be recalcul'ated following any significant changes in the radiological effluent or meteorlogical parameters being used or upon receipt of updated plant status information which significantly impacts the duration of the release.
'- 4.7.6 Plant status changes and parameter trends; e.g., increased reactor water conductivity, abnormal SRM indications, increased ARM levels, increasing Containment Hign Range Radiation Monitor levels, and high containment pressure should be considered by the Site Radiation Protection Coordinator in determining the timing and type of post accident samples to be taken.
a) The potential for release of any significant quantity of radioiodine and subsequent substantial impact to off-site environs is based upon the extent to which core damage occurs; therefore, the Site Radiation Protection Coordinator should direct implementation of PASAP 7.3,
" Containment High-Range Radiation Monitors", to determine if fuel damage is indicated.
b) If core damage is indicated or suspected, further post accident sampling should be instituted to better quantify the ratio of iodine to noble gas in ongoing effluent releases or in containment atmospheres which may potentially be released. NOTE
- If further post-accident sampling is instituted, a I more definitive estimate of core damage may be obtained by drawing and analyzing post-accident samples in accordance with PASAPs 2.0, 3.1 through i
3.11, and 7.2. 4.7.7 As a result of sampling and isotopic analysis activities conducted, the effluent release iodine to noole gas ratio may be entered into the computerized dose projection program as opposed to the established def ault values. ! a) If a release is in progress, the most accurate sample media to be analyzed are the particulate filters and charcoal cartrioges from the KAMAN System at tne effluent release point, followed by containment atmospheric analysis. _ l
e l EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 34 of 65
'2 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5
Date 7/14/83 NOTE ( If environmental atmosheric samples are analyzed, Staiidby Gas Treatment System removal efficiency, if applicable to the release point, of 99% should be assumed. b) The least reliable means to be used to determina the effluent release iodine to noble gas rat'io is a Reactor Coolant System sample. 4.7.8 Environmental survey and airborne analysis as well as meteorological information results may be. used to perform
*~ dose projections in lieu of or in addition to effluent release, process flow and post accident analysis results.
a) The determination to use field monitoring data for 4 calculation of projected off-site doses'shall be the responsibility of the Radiological Assessment Coordinator in the EOF, if manned; or if not, then the Site Radiation Protection Coordinator. b) Normally, this method should not be relied upon for accuracy-until a substantial quantity of field survey data has been accumulated. NOTE Field survey data, however, will weigh heavily during post accident evaluation of total man-rem exposure to the public. Consequently, the off-site monitoring ,l activities, prescribed by EPIP 3.2, "Off-Site Radio-logical Monitoring", and CPIP 2.1, " Dose Assessment and Protective Action Recommendations", should be well documented. 4.7.9 During an event sequence which involves a LOCA and subsequent core damage, protective action recommendations must be made based upon a release potential even though an actual release may not be in progress, a) ine primary consideration involved in determining evacuation as opposed to sheltering are containment pressure response, the quantity of radioactivity available for release inside containment and tne ability to recover and maintain Reactor Water Level aoove the top of the active fuel.
-6. . . .
f '. * , u_4
9- 9 EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 35 of 65 ': ACTIVATION AND OPERATION UT THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 b) The' best estimate of the quantity of material available for~ release can be'obtained by analyzing a series of samples of containment atmosphere, providing the atmospnere is being recirculated to promote a homogeneous distribution of radioisotopes throughout. c) The next best quantitative estimate can 'be made by analyzing a series of reactor water samples taken from a flow stream which is recirculating through the core. NOTE
- The potential impact to affected off-site locations can be estimated utilizing PASAP 7.4.
4.7.10 The Site Radiation Protection Coordinator should initiate and conduct trend analysis, as described in CPIP 1.2, " Dose
- Assessment and Protective Action Recomendations", and assist the Radiologial Assessment Coordinator in the performance of this function upon being relieved of off-site radiological monitoring activities.
a) Parameters of interest which can most easily be trended under the direction of the Site Radiation Protection Coordinator-include KAMAN System Effluent Monitor readouts, analyses conducted of effluent stream particulate filters and charcoal cartridges, meteorological data, ARM levels and Containment Hign Range Radiation Monitor levels. NOTE Trend analyses 'of ARM and Containment High Range c Radiation Monitor levels are of dual importance due to their direct impact on response activities within the plant and their significance with respect to determining the quantity of radioactive material potentially available for release off-site. b) Parameters of interest which can most easily be trended by the Radiological Assessment Coordinator include off-l site survey results, results of analyses of airborne sa.nple media collected off-site, and projected dose rates and total exposures. 4.7.11 Radiological monitoring on-site shall be concucted, as required, to support rescue efforts, as well as repair and operational activities required to restore the plant to a safe condition. l v - _.f
j " .:r i EMERGENCY' PLAN IMPLEMENTING PROCEDURE EPIP 2.2 "i@ Page 35 of'65 2$' j ACTIVATION ~ AND OPERATION UF THE TECHNICAL SUPPORT CENTER Revision 5 ~ M k.k-; ' Date 7/14/83 - Yh WD
, "d!
. ? @s D) The best estimate of the quantity of material available ..
' M ,j..t for release can be obtained by analyzing a series of ,
samples of containment atmosphere, providing the .~. f*. Mr
'sy atmospnere is being recirculated to promote a homogeneous r distribution of radioisotopes throughout. .',1.O;.')
c) The next best quantitative estimate can be made by ~ .y' analyzing a series of reactor water samples taken from a JM4c< flow stream which is recirculating through the core. ,',"Ef' ,:r NOTE 7.- d
~ 4 ,, %
- The potential -impact to affected off-site locations ' : ,%sj can be estimated utilizing PASAP 7.4. . . ',,: 1 v,
4.7.10 The. Site Radiation Protection Coordinator should initiate 'l,' ". f.:] and conduct trend analysis, as described in CPIP 1.2, " Dose ~ Assessment and Protective Action Recomendations", and 4
' assist the Radiologia1. Assessment Coordinator in the '
performance of this function upon being relieved of. off-site - 7,, radiological monitoring activities. 1,l a) Parameters of interest which can most easily be trended under the direction of the Site Radiation Protection , , , , Coordinator include KAMAN System Effluent Monitor !- readouts, analyses conducted of effluent stream - particulate filters and charcoal cartridges, " meteorological data, ARM levels and Containment Hign Range Radiation Monitor levels. NOTE Trend analyses of ARM and Containment High Range Radiation Monitor levels are of dual importance due to ~. ' their direct impact on response activities within the t plant and their significance with respect to determining ^: the quantity of radioactive material potentially 7
- available for release off-site. .".
i b) Parameters of interest which can most easily be trended by the Radiological Assessment Coordinator include off-site survey results, results of analyses of airborne sample media collected off-site, and projected dose rates and total exposures. ; 4.7.11 Radiological monitoring on-site shall be conducted, as , required, to support rescue efforts, as well as repair and operational activities required to restore the plant to a safe condition.
~ ~.h5 s-?..;,5 & k E I: % .;e r
l ?*-. $ Y[. .._ [.n*s* ??
=
~
d
- # fa. # -. m 1-I ---
- * - - E e * ._
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 36 of 65 ! ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER _ Revision 5 . . Date 7/14/83 ,. 3 a) The Site Radiation Protection' Coordinator should identify the radiological survey and sampling tasks to be accomplisht:d to the OSC Supervisor who, in turn, should .' . , , provide direct supervision over the activities to be .: , completed. b) Guidance regarding on-site radiological inonitoring activities is provided in EPIP 3.1, "On-Site Radiological , , . . Monitoring". ' 7~ ' - c) Guidance regarding rescue and repair activities is prescribed in EPIP 4.3, " Rescue and Emergency Repair - - Work". d) Guidance regarding personnel decontamination and actions to be taken for serious personnel injuries is provided in EPIP 4.2, "First Aid, Decontamination, and Medical Support". 4.7.12 The Site Radiation Protection Coordinator should insure that the Control Room Coordinator, TSC Supervisor and Technical and Engineering Supervisor are appraised of significant radiological hazard areas within the plant and should provide recomendations to the Emergency Coordinator regarding: a) Radiological concerns associated witn planned response options, repair activities, etc. b) Personnel exposure limit. increase authorization, c) Levels of radioiodines and the advisaDility of administering. Potassium Iodine (KI). d) Reclassification of the event due to on-site radiological j problems and effluent release rates. l e) Evacuation of the site. 4.8 NRC Site Team Activities i 4.8.1 The principal functions of the NRC Site Team related to Iowa Electric emergency response activities include: a) Monitor plant status, events and response actions. b) Assess the level of compliance to plans, procedures, and L Federal regulations, c) Project consequences and develop recommendations to , ,- protect the public health and safety. . , . ... .
-~;...
~
.?h $_ .
*** n- e - - - . _
7 r-* , y g , , ,- -w y-.--%. -7 y,p-- , - - - - - - - - --y
EMERGENCY PLAN ~ IMPLEMENTING PROCEDURE EPIP 2.2 Page 37- of 65 ACTIVATION AND' OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 d) Provide technical support. e) Provide press and public information releases. _ .,
~
4.8.2 The Site Team Leader may be authorized by the NRC Emergency Oirector (Chairman of the NRC) to function as the Director of Site Operations (050). In that capacity, the DSO a) Represents the entire NRC. b) Assumes responsibility for all on-site technical aspects of the Federal response. c) Provides recomendations for protective measures for the public health and safety in coordination witn Iowa Electric. d) Provides recomendations to key State and local agencies in coordination with Iowa Electric. e) Provides advice,' direction and, if necessary, orders. NOTE Authorization for the DSO to implement items c, d, and e must be specifically granted by the NRC Emergency Director.
5.0 REFERENCES
5.1 0AEC Emergency Plan 5.2 NUREG 0654, Rev. 1 5.3 10CRF50.54 5.4 NRC Region III Emergency Response Plan and Implementing Procedures 6.0 ATTACHMENTS 6.1. TSC Layout . 6.2 TSC Setup Instructions 6.3 OAEC Emergency Response Organization 6.4 OAEC Emergency Response Organization Positions 6.5 TSC Supervisor Checklist 6.6 Technical and Engineering Supervisor Checklist , .; y, r . e-.,, . g
..n%L4k5.$.dg 4o
-jygplqq)n
- a.= .mwn--=~e i
)
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 38 of 65 - . ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 6.7 Site Radiation Protection Coordinator Checklist 6.8 Radio Console Operating Instructions 6.9 Security and Support Supervisor Checklist 6.10 TSC Log Sheet 6.11 Log ry Topi s Approved by: / Date: M )S,/f/J () Eilreegefrcy Planni co'ordw efo v Approved by: M[ Rad ation Protaction Sddpervisor e Date: 9 ' f f.3 Approved by: . . , ) Date: 'T L,!ffb As s i st ant' P1 &nt, superi ntendent-Operat i ons Reviewed by: hh..
~ . e I av,e Date: 9-i2.-93 ALA oor ator Q Reviewed by: L. Date: 9-20-97 Operat rise Committ Chairman Approved by: i W Date: 94l, b Plant Superintendent-Nuclear
* 'e
. C.
.y , _ _ .,s. ,- _ . , _ . ,
v _ ,y, _ . _ . . ~ _ . _ , _ _ _ . _ , , . - . _ , _ _ _
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP_ 2.2 Page 39 of 65 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 - Date 7/14/83 Emergency Conmunications
~
- Emergency Coorsinator ATTACHMENT 1 & Dedicated Outside Teleonone
' TSC Supervisor TSC LAYOUT d !WAS Teleonone
.h Tecnntcai & Engineering Suoervisor -
d 20 Station (Headset Equipped) h Site Radiation Protection Supervisor k Teleonones h security & Succort suoervisor Other Telephones NRC. ENS Telechone 6 Comunicator h Ext. 234 & G. E. Dial Com. d NRC APN Telechone 7 TSC Log Recorcer h ' Ext. 228 h Intercom to Access Contbl.'5CP, and Control Room h NRC Reoresentative h Ext. 225 & 214 Note: 20 Station Tele; nones have: Administrative Supervisor @ Ext. 226 1 Control Room h Status Board Recorder @ Ext. 243 l h*lfggh" h Status Update Recorcer @ Ext. 263 [cgp,n,j h Radio Operator's Assistant h Ext. 243, 234, 226 & 263 f 8 g', $,$ 1" , "$8)g 7 Radio, Coerations
*[*
10 additional ext. (Planned) KAMAM AIRSCRNE MACHINE CCMMINICATf0NS 200'4 RAO!ATION MCN. SYSTEM (5.ee Figure 2) RESTROCMS A D @ C*PY MACHINE J' IA
' - - f .h )
SURVEtLANCE CATA FILES KITCHEMETTE - _ lli I ,
. (
' t PLANT CCCL*.ENT t RETE!iTION CENTER @ l rea em v q sorg DCCUMENT CCNTRCL @ {'
(see Figure 2)' I . f
~
CARD FILE & . MICROFILM
@ .h REACTOR .
ENGINEERING b N.5!TE C TEAM TELECCPY F.ACHinE ,e _ OnoinrER CA30 3RinTER
- l l t
R REAcica e @ O .O g NCEL Figure 1, "Overall Layout" h e ew e -e e
. ._ -, - ~: -m
t * . EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 40 of 65 -. ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 ATTACHMENT 1 (Continued) , TSC LAYOUT COMMUNICATIONS ROOM I I BOOKCASE. RADIO CONSOLE .
.. 4 RADI0 IODINE ANALYZER H b6v.
COMPUTER TERMINAL and- g g'MERGENCY PRINTER V LOCKERS -, r - om OVERHEAD PROJECTORS _ l \/ \ A FORTABLE PLANT
$gg N
I 000KCAS,c I AIR MONITOR STATUS RADIOLOGICAL STATUS Tsc WO9 KING AREA
@O@
/h d'
., MAPS REA h STATUS BOARD A A a 4 -
l I ICAL ! STATUS (EMERGENCY STAFF) PLANT' STATUS Figure 2, " Working Area Layout" (Key for above diagram located on preceeding page.) g . . . ...
-,,,----w - g .- g-- - - - , , - - , , - - , , , -,.-e - , , - - - . - , - - - - - , - - -
< v I
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page. 41 of 65
~
'2 ACTIVATION AND-0PERATION OF. THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 l ATTACHMENT ~2 TSC SETUP INSTRUCTIONS.
PERFORMED BY A SECURITY FORCE MEMBER
- 1. Unlock
~ ~
1.1 'TSC 1.2 TSC Communications Room
- 1.3 TSC Emergency Locker
- 2. Activate Emergency Ventilation System 2.1 Log startup time in TSC HVAC Filter Unit Operating Log located in TSC Ventilation Room PERFORMED BY TSC PERSONNEL
- 3. Check to see that a Security Force member completed #2 above.
- 4. Check radiation monitors (Located in the Communications Room) 4.1 Ventilation System 4.2 TSC
- 5. Contact Health' Physics to initiate radiation and airborne sampling activities-if radiation monitors (#4 above) are trending upscale or alarming.
- 6. Move cart containing Portable Air Monitor from the Communications l Room, energize, and initiate sanpling.
- 7. Verify operability of the communications links, as follows:
7.1 Intercom i. 7.1.1 Energize the power supply located in ! the Communications Room, sittin l i the left of the Radio Console, g forto the Intercom. 7.i.2 Check operability of Intercom between TSC and SCP. e
.-;, u.;x d ; ;
..i.
~.:-= .a
,- o EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 42 of 65 ACTIVATION AND OPERATION OF. THE TECHNICAL-SUPPORT CENTER - Revision 5 Date 7/14/83
' ATTACHMENT 2 (Continued) -
TSC SETUP INSTRUCTIONS 7.2 Dedicated telephones between:
~
7.2.1 TSC & EOF 7.2.2 TSC & Control Room 7.2.3 TSC & Access Control
- 7.2.4 TSC & SCP 7.3 Security / Rad Survey Radio to Central Alarm Station (Channel 2 on the radio console located in the Communications Room).
7.4 Plant Operations Radio to Central Alarm Station (Channel 1 on the radio console located in the Communications Room). 7.5 NRC " Hot Line" (red phone) located in the NRC Conference Room (Plant Performance Supervisor's Office) by checking to see if the light on the phone is "on". ! NOTE: If the light is not "on" contact the TSC Supervisor to inquire whether or not a communications check should be performed. Normally, a communications check such as this, ! should not be done until notification of the NRC has been verified. 7.6 NRC (HPN) phone located in NRC Conference Room (Plant Performance Supervisor's Office) by checking to see if the light on the phone is "on". l NOTE: l If the light is ,t "on" contact the TSC Supervisor to inquire wnether or not a communications check should be performed. Normally, a communications check sucn as this, should not be done until notification of the NRC has been verified. 7.7 Facsimile Equipment located in the word processing area to the E0F. l
,' , . ' 4 EMERGEriCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 42 ~of 65 -
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5
- x. Si
~ 'c:.
Date 7/14/83 ,;~ ATTACHMENT 2 (Continued)- , r
- ~
-TSC SETUP INSTRUCTIONS cy J .
. n}
- 7.2 Dedicated telephones between: g, 7.2.1 TSC & EOF-f
'7.2.2 TSC & Control Room N 7 7.2.3 TSC & Access Control , ',i
&. L g.
-* 7.2.4 TSC & SCP g 7.3 Security / Rad Survey Radio to Central Alarm Station ,
(Channel 2 on the radio console located in the c Comunications Room). 7.4 Plant Operations Radio to Central Alarm Station (Channel 1 on the radio console located in the Comunications Room). s: 7.5 NRC " Hot Line" (red phone) located in the NRC Conference Room (Plant Performance Supervisor's -
~
Office) by checking to see if the light on the phone is "on". , NOTE: If the light is not "on" contact the TSC Supervisor to inquire whether or not a comunications check should be performed. Normally, a comunications check such as t.Ms, should not be done until notification of the NRC has been verified.. NRC (HPN) phone located in NRC Conference Room 7.6 (Plant Performance Supervisor's- Office) by checking to see if the light on the phone is "on". NOTE: If the light is not "on" contact the TSC Supervisor to inquire whether or not a comunications check should be performed. Normally, a comunications check sucn as this, should not be done until notification of the NRC has been verified. l l 7.7 Facsimile Equipment located in the word processing area to the EOF.
. .is
-=.,.t%lSNlm:-
.+. ,..
*.e =e /
- -y.ahnyn@!i
- u m w n %m t
g -n _ EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP ' 2.2 Page 43 ~f o 65 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 ATTACHMENT 2 (Continued) . TSC SETUP INSTRUCTIONS 7.8 Eight (8) Emergency Communications Telephones (20 button, dial phones) located i,n the TSC Working Area. (One in the Communications Room).
- 8. Verify operability of the VAX Computer Terminal in the TSC Working Area.
- 9. Energize and verify operation of the Control Room TV monitors.
- 10. Remove materials from tops of desks and tables located in the TSC.
Working Area and the table in the Communications Room, store in boxes, located to the left of the TV monitors, and remove from the area.
- 11. Obtain headsets for Emergency Communications Phones from the Emergency Locker located in the Communications Room.
- 12. Distribute Emergency Communications Phones (20 button, dial phones) and headsets around the TSC Working Area.
- 13. Move table located near the windows in the Communications Room toward the center of the room.
'14. Obtain two (2) overhead projectors from the Emergency Locker, set up on tne table described above, and check operability. (Extra bulbs are located in the Emergency Locker.)
15.. Place support equipment at desks / tables. 15.1 Obtain position notebooks from the bookcase and distribute them to appropriate location. 15.2 Obtain office supplies from the Emergency Locker and distribute to various positions in the TSC Working Area. i e
;- ..=,
L-
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 44 of 65 - ACTIVATION AND-OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 - Date 7/14/83 ATTACHMENT 3
-DAEC EMERGENCY RESPONSE ORGANIZATION .
EMERGENCY COORDINATOR TSC STAFF PLANT SUPERINTENDENT-NUCLEAR . I i
.- TECHNICAL. SUPPORT SITE RADIATION CENTER SUPERVISOR PROTECTION C00RDINATOR ASSISTANT PLANT SUPERINTENDENT-0PERATIONS RADIATION PROTECTION I SUPERVISOR p j TECHNICAL & ENGINEERING SECURITY AND SUPPORT ---
SUPERVISOR SUPERVISOR l l ASSISTANT PLANT ASSISTANT PLANT OPERATIONAL SUPPORT SUPERINTENDENT- SUPERINTENDENT- CENTER SUPERVISOR TECHNICAL SUPPORT RADIATION PROTECTION
& SECURITY HEALTH PHYSICS
- Shift Technical SUPERVISOR Advisors -
I I Technical ADMINISTRATIVE Engineering Staff SUPERVISOR ORAA ORAL /0DEF SUPERVISOR SUPERVISOR
- Maintenance Supervisors- L Administrative Staff ] ]
CONTROL ROOM COORDINATOR OPERATIONS SUPERVISOR SECURITY OPERATIONS SHIFT SUPERVISOR SUPERVISOR k Security Force L Operations personnel
'..%.b.:
5'
'N WiC'.' I
?
- EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2
^ '
Page 45 of 65 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5
. Date 7/14/83
_ ATTACHMENT 4 . DAEC EMERGENCY RESPONSE ORGANIZATION POSITIONS EMERGENCY RESPONSE POSITION PLANT STAFF POSITION Technical Support Center
- Emergency Coordinator Plant Superintendent _ Nuclear
**TSC Supervisor Ass't. Plant Sup't. - Operations
** Site Radiation Protection Coordinator Radiation Protection Supervisor
** Technical and Engineering Supervisor Ass't. Plant Sup't. - Technical Support
** Security and Support Supervisor Security Supervisor
** Administrative Supervisor Support Services Supervisor Radiolooical Support Staff ALARA Coordinator ALARA Engineer VAX Terminal Operator Ass't. Rad. Prot. Supervisor Radiological Data Comm. Assigned by Tag Board Radio Operator- Assigned by Tag Board Radio Operator's Ass't. Assigned by Tag Board Technical Sucoort Staff Maintenance Superintendent Maintenance Superintendent Mechanical Maintenance Supervisor Mechanical Maintenance Supervisor Electrical Maintenance Supervisor Electrical Maintenance Supervisor Maintenance Engineer Maintenance Engineer
- Plant Performance Engineer' Plant Performance Supervisor Tecnnical Support' Engineer Technical Support Supervisor
- Represents the augmented shift staff requirements prescribed in the DAEC Emergency Plan, Table B-1.
** Additional positions for which staff comnitments were made in the OAEC Energency Plan beyond those specified in Table -B-1, of the DAEC Emergency
~
Plan. , 2.. j- -. .
~
- q l
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 46 of 65 l ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 I I Date 7/14/83 ATTACHMENT 4 (Continued) DAEC EMERGENCY RESPONSE ORGANIZATION POSITIONS ,
. EMERGENCY RESPONSE POSITION PLANT STAFF POSITION Technical- Sucoort Staff (Continued)'
Site Design Engineering Supervisor'(2) Supervising Engineer, Nuclear Projects
- Mechanical _ Design Engineer ~ Predesignated Engineer
- Electrical Design Engineer Predesignated Engineer Shift Tecnnical Advisors (2) Assigned by Tag Board DAEC Fire Marshall Predesignated Engineer General Electric Representatives General Electric Site Team Members Bechtel Representative Bechtel Site Manager Comunications/ Status Recording Staff Control Room Communicator Assigned by Tag Board EOF Communicator Assigned by Tag Board NRC ENS Communicator Selected "at 1arge" or called out Engineering Information Communicator Selected "at large" or called out Status Board Recorder Selected "at large" or called out Status Update Recorder Selected "at large" or called out TSC Log Recorder Selected "at large" or called out Clerical Staff Messengers (2) Selected "at large" or called out
- Document Records Clerk Selected "at 1arge" or called out Switenboard Operator Selected "at large" or called out Nuclear Reoulatory Commission Resident Inspector (Note 1) NRC Resident Inspector Site Team (5-7) Dispatened from Region III Offices
...................................... ^
- Represents the augmented shift staff requirements prescribes in the DAEC .
Emergency Plan, Table B-1. ,
. u.y. .
NOTE 1 - May locate in the TSC or Control Room. .-/ 3=yry ;
=::.T:.n 1-
v 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 47 ~f o 65 ' ACTIVATION AND OPERATION OF THE TECHNICAL' SUPPORT CENTER Revision 5 - Date 7/14/83 ATTACHMENT 4 (Continued) _ DAEC EMERGENCY RESPONSE ORGANIZATION POSITIONS EMERGENCY RESPONSE POSITION PLANT STAFF POSITION Operational Support Center
**0SC Supervisor Health Physics Supervisor Ass't. OSC Supervisor Ass't. to Radiation Protection Supervisor Chemistry. Coordinator (Note 2) P1 ant Chemist Rad Waste Coordinator (Note 2) Rad Waste Coordinator I
Warehouse Supervisor (Note 2) Warehouse Supervisor ORAA Supervisor (Note 4) DAEC Fire Marshall ORAL - ODEF Supervisor Plant Chemist
** Security Supervisor Ass't. Security Supervisor Security Shift Supervisor - On-Duty Shift Supervisor
- Health Physics Technicians (8) Assigned by Tag Board
- Environmental H.P. Environmental Technician
?
- Dosimetry Clerk Dosimetry Clerk
- Rad Waste Operator Assigned by Tag Board
- Chemistry Technicians (2) Assigned by Tag Board
- Mechanical Maintenance (4) (Note 3) Assigned by Tag Board
- Electrical Maintenance (2) Assigned by Tag Board l
- Instrument Technician (1) Assigned by Tag Board
- Represents the augmented shift staff. requirements prescribed in-the OAEC Emergency Plan, Table B-1.
** Additional positions for which staff connitments were made in the DAEC Emergency Plan beyond those specified in Table B-1, of the DAEC Emergency Plan.
NOTE 2 - Initially report to the SCP, then relocate as directed. NOTE 3 - Three (3) for Rad Monitoring Teams; One (1) for in-plant corrective actions. NOTE 4 - Initially report to the TSC, then relocate or divide. ~ m
.~. -
3
. .w yw ~y c - >-
v {
' EMERGENCY PLAN IMPLEMENTING PROCEDUR2 EPIP 2.2 Page 48 of 65
~ ~~
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 ATTACHMENT 4 (Continued)
~
DAEC EMERGENCY RESPONSE ORGANIZATION POSITIONS , EMERGENCY RESPONSE POSITION PLANT STAFF POSITION Control Room
** Control Room Coordinator Operations Supervisor
*0perations Snift Supervisor On-Duty Shift Supervisor
- Ass't. Operations Shift Supervisor 0'n-Duty Ass't. Shift Supervisor
- Shift Technical Advisor On-0uty STA Communications / Status Recording TSC Communiator Assigned by Tag Board Back Panel Communicator Assigned by Tag Board NRC ENS Communicator Selected "at large" or called out VAX Terminal Operator Selected "at large" or called out Plant Status Data Recorder Selected "at large" or called out Nuclear Regulatory Commission Resident Inspector (Note 5) NRC Resident Inspector
- Represents tne augmented shift staff requirements prescribed in the DAEC Emergency Plan, Table B-1.
** Additional positions for wnich staff connitments were made in the DAEC Emergency Plan beyond those specified in Table B-1, of the DAEC Emergency Plan.
NOTE 5 - May locate in the Control Room or TSC. me
--;_ =.. l. r.;:.J. : :._-_
~
j *,'" ~! ff$,';{~ ? _
'*'.. "I TO5tu s
s o l EMERGENCY PLAN IMPLEMENTING PROCEDURE -EPIP '2.2 Page 49 of 65 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 , i ATTACHMENT 5 . TSC SUPERVISOR-CHECKLIST The following checklist is available for use by the TSC Supervisor or another individual, so designated, as an aid in ensuring that energe,ncy response actions are completed. In the column labeled " Time", the actual time that such items are completed may be recorded. Alternatively, checks may be used or other appropriate notations may be substituted which will be of assistance to the user. TIME ITEM O
- 1. During non-normal working hours, supervise setup of the TSC or delegate supervision to another.
- 2. Verify that TSC Radiation Monitor levels are satisf actory, or if not, that action is underway to determine habitability.
- 3. Verify TSC layout and setup has been completed, as required, and that equipment is functional.
- 4. Verify that-TSC staffing is in place.
- 5. Insure that an accountability check has been accomplished as prescribed in EPIP 1.3.
- 6. Assure that access control has been established by Security.
- 7. Insure that updated plant and radiological status infonnation is displayed.
- 8. Notify the Emergency. Coordinator of the TSC's activation.
- 9. Direct the TSC Log Recorder to initiate maintenance of the TSC Log.
l The following items are of an ongoing nature and should be periodically reviewed by the TSC Supervisor as an aid to insure j their conduct.
- 10. Provide assistance, as requested by the Emergency Coordinator, in transmitting status information to off-site agencies until relieved of this function by the EOF.
M
~
' EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 50 -of 65 4- ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 ATTACHMENT 5 (Continued)
TSC SUPERVISOR CHECKLIST TIME ITEM
- 11. Provide assistance, as requested by the Emergency Coordinator, in communicating with the NRC and in conducting briefings of NRC personnel upon their' arrival on site.
- 12. Communicate with the Control Room to obtain the following types of
- information:
a) Plant status b) Problems which are being experienced. c) Parameter trends which become apparent.
- 13. Coordinate with the. Control Room Coordinator to modify Plant Status information being transmitted on the VAX and/or the frequency of such transmittals.
- 14. Coordinate with the Control Room Coordinator to initiate and maintain trends of the following key parameters, as applicable.
a) Nuclear Instrumentation (if not shut down) b) Reactor Vessel water level c) Reactor pressure d) Drywell/ Torus pressure e) Drywell temperature f) Torus water level l g) Torus water temperature h) ARM levels i) Drywell/ Torus High Range Radiation Monitor levels j) Effluent release concentrations
.. . ~: -
- J.) R w y.: '
) "- - ' E*E ,
??~~u,-!S G Q
-V W .l
'EMERGENCYPLANIMPLEMENTIN5 PROCEDURE EPIP -2.2 Page i
51(f65 ACTIVATI0il AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5-7 Date 7/14/83 1 ATTACHMENT 5 (Continued) -
- 3. TSC SUPERVISOR CHECKLIST: x s .
TIM'l,E N, ITEM h 1 1 i5. Coordinate with the Control Room Coor'dinator to define, 'ddithb;' '- ' and maintain' trends of key parameters other tnan those identified
] above .
- 16. Coordinate the maintenance of trends wi h the Tecanical and '- '
Engineering Support Supervisor in the EOF. ., 17'. Appraise the Control Room Coordinator and Emergency Coordinator of . s trends which become apparent and their significance. ' k
\
- 18. Re-evaluate the classification of the emergency based upon plant '
status, problems and projected trends and recommend reclassification , of the event to the Emergency Coordinator, as appropriate.
- 19. Provide assistance, as requested by the Emergency Coordinator, in ~
briefing of personnel assembled in the TSC. g
- 20. Provide direction to the Status Board Recorder regarding information to be displayed on the Status Board.
- 21. Provide overall direction to the Technical and Engineering s Supervisor associated with problems encountered and response ' options
, to-be pursued.
- 22. Ensure that the Site Radiation Protection Coordinator is anpraised of plant status problems, response actions planned which ma{ requir,s entry into the plant, and significant parameter trends. /
23.' Coordinate with the Control Room Coordinator and Site Radf ation \ s
, Protection Coordinator for dispatch of operators into the plant.4 j?4. Appraise the Control Room Coordinator of the dispatch of rescue,ar.d u l .;; repair team personnel. '( ] y
( , 25,. Coordinate with the Technical and Engineering Supervisor to reassign ) , personnel to' assist the Control Room Coordinator in making temporary i x changes to procederes and/or developing temporary procedures. s
- -g
\ s,.,..x 1 .
i 5 s b eve
.. s g -
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 , Page. 52 of 65
~ ' !
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 ATTACHMENT 5 (Continued) v' TSC SUPERVISOR CHECKLIST TIME ITEM
- 26. Insure that response actions taken in violation of procedural requirements are reviewed to insure future operational evolutions will not be inhibited.
[ 27. Paview the need for modifying Technical Specification requirements
- with the Control Room Coordinator and Emergency Coordinator.
f approve deviations from license conditions or
- 28. Time Technicalpermitting,ications Specif taken where'such action is imediately L needed to protect the public health and safety.
s
- 29. Provide input to the Emergency Coordinator regarding areas where
,7
- Q fuptional support improvements 'are desirable and/or modification to K, , g thefDAEC, Emergency Response Organization are desired.
- 30. Assist 'the Security and Support Supervisor, as required, to develop
' shift schedules for continuous coverage.
x)' M,3
- 31. As directed by the Emergen'cy Coordinator, assist in the development s' N M '"
s l of recovery planning as prescribed in EPIP 5.2. J 32,, Coordinate with the Control Room coordinator and recommend
' deactivation to the Emergency Coordinator in accordance with the
" 'r3uidance- provided in EPIP 5.1.
j s,\ 7p y [ CUMMEpTSi '\ "
- h, , i '
V) V , , . .
-yy-g Y, y 0
,y dli
\ N A\
l e v
+
/
( TSL dupervisor time / Date
*p ,
t-- , g ~}- f s j' '4,, ( ( l<
\.y..j Y ;\[ m, m _
n' ._ _ .
F W t> EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 53- of 65 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83
?
. ATTACHMENT 6 .
f/ TECHNICAL AND ENGINEERING SUPERVISOR CHECXLIST The*following checklist is available for use by the Technical and Engineering Supervisor or another individual,-so designated, as an aid in ensuring that emergency response actions are completed. In the column labeled " Time", the actual time that such items are completed may be recorded. Alternatively, checks may be used or Other appropriate notations may be substituted which will be of assistance to the user.
*' . TIME ITEM f
1." Verify assembly of an adequate technical staff in the TSC to
' include, at a minimum:
a) Plant Performance Engineer (Core Thermal Hydraulic) b) Mecnanical Design Engineer l c) Electrical Design Engineer j .
- 2. Review plant status and problems being experienced with the TSC r
> Supervisor and initiate evaluation of response options which Will l] - aid in restoring safe conditions.
c 3. Coordinate with the Technical and Engineering Support Supervisor in the EOF and provide guidance regarding engineering and analyses
\ t / , ,
.' activities to be accomplished in the EOF.
- 4. Discuss repair and corrective actions options being evaluated with
> the Control Room Coordinator and Site Radiation Protection Coordinator and recommend options to be pursued.
- 5. Ensure that documents and resources being used to evaluate plant conditions and planned response options are current.
- 6. Racommend to the Emergency Coordinator waiver of normal administrative practices governing engineering and repair / corrective action activities which, if implemented, will enable more rapid response without compromising safety.
N
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2. 2' Page 54 of 6S
~~ '
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 , t _ ATTACHMENT 6 (Continued)
-TECHNICAL AND ENGINEERING SUPERVISOR CHECKLIST TIME' ITEM
- 7. . Coordinate, as required. .with QA/QC personnel .'regarding waivers of -
normal practices which have been approved, to insure that such ! actions are-documented.
- 8. Insure that key parameter trends are considered during evaluations -
conducted of response options to insure that options Deing considered will be acceptable when implemented.
- 9. . Evaluate repair team makeup and reconstitute,' as appropriate, to mar.imize expertise to De applied.
- 10. Insure that repair team members are briefed regarding technical activities to be conducted, precautions to be taken, and the like.
- 11. Coordinate with the T5C Supervisor to reassign personnel, as required, to directly support the Control Room Coordinator with procedure revision, development of temporary procedures and the like.
- 12. Determine or project changes in plant status or conditions which should result upon implementation of response option.
- 13. Upon implementation of response options, if the anticipated changes are not observed:
a) Initiat'e actions to stop or recommend cessation of the activity. .; b) . Recommend reclassification of the event, if' appropriate, to the TSC Superviosr, if unexpected conditions become apparent. c)_ Initiate actions to pursue or evaluate other response activities. I
-1 t
am
~
e
o
- EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 55 o
'f 65 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 ATTACHMENT 6 (Continued) .
TECHNICAL AND ENGINEERING SUPERVISOR CHECKLIST TIME ITEM .
- 14. Coordinate with the Control Room Coordinator to evaluate the means to be used to restore the plant to a safe condition while, at the same time, minimizing the expansion of the radiological hazard area where indications exist that core degradation has occurred.
- 15. Provide assistance, as requested by the TSC Supervisor, in evaluating proposed revisions to license conditions and Technical Specifications where deviation from such requirements will be beneficial to plant recovery yet not impact the health and safety of the public.
COMMENTS:
/
Tecnnical and Egnineerthg Supervisor Time / Date
e
'l EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 56 of 65 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 -
Date 7/14/83 ATTACHMENT 7
~
SITE RADIATION PROTECTION COORDINATOR CHECKLIST The following checklist is available for use by the Site Radiation Protection Coordinator or another. individual', so designated, as an aid in ensuring t. hat emergency response actions are completed. In the column labeled " Time", the actual time that such items are completed may be recorded. Alternatively, cnecks may be used or otner appropriate notations may be substituted wnich will be of assistance to the user.
- TIME ITEM'
- 1. Evaluate plant conditions and effluent monitorin determine if a significant radiological release:g instrumentation to a) Has occurred b) Is in progress c) Potentially may occur
- 2. Evaluate the results of initial dose projections, if any conducted by the Operations Shift Supervisor or protective action recommendations made.
2.C.
- 3. Perform initial dose projections and develop protective action recommendations.
- 4. Advise the Emergency Coordinator of projected off-site doses and protective action recomendations wnich should be transmitted to local, State and Federal E0Cs.
- 5. Ensure action has been initiated, to initially determine the acceptability of assembly area habitability.
- 6. Advise the Emergency Coordinator and OSC Supervisor of the need to conduct off-site radiological monitoring.
- 7. Provide information regarding the projected off-site radiological conditions to the OSC. Supervisor for subsequent dissemination to members of both On-Site and,0ff-Site Radiological Monitoring Teams.
o
. .i L it - ,
_- )
, o EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 57 of 65 -
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 ATTACHMENT 7 (Continued) , SITE RADIATION PROTECTION COORDINATOR CHECKLIST TIME ITEM ,
- 8. Verify that the following positions in the TSC and Control Room are manned. and that personnel- assigned are f amiliar with i.5eir function, plant status, and response actions being taken:
a) Radio Operator e b) Assistant Radio Operator c) Radiological Data Communicator d) Back Panel Communicator e) ALARA Coordinator f) VAX Terminal Operator
- 9. Upon being advised of the readiness of the Off-Site Teams by the OSC Supervisor, take control of the Teams and dispatch when authorized by the Emergency Coordinator.
- 10. Coordinate with the Radiological Assessment Coordinator in the E0F and turn over control of the Off-Site Teams upon activation of the EOF.
The following items are of an ongoing nature and should be reviewed l periodically as an aid in insuring that required emergency response functions are conducted.
- 11. Coordinate with the TSC Supervisor and Radiological Assessment
[' Coordinator to initiate and maintain trends of key radiological i. l-parameters -including: a) Effluent concentrations b) Effluent release point particulate filters and charcoal cartridges analyses 3
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page' 58 of 65
~
ACTIVATION AND .0PERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 ATTACPMENT 7 (Continued)
~
SITE RA0IATION PROTECTION COORDINATOR CHECKLIST TIME ITEM c) . Meteorological data, as appropriate d) Containment High Range Radiation Monitor levels
, e) ARM levels f) Off-site survey results at selected locations g) Off-site sample media results h) Projected doses at sel,ected locations
- 12. Evaluate on-site radiological parameters, survey and sample analyses results, plant conditions and trends of.significant parameters being monitored and provide recommendations to the Emergency Coordinator regarding:
a) Event reclassification b) Evacuation of personnel
- 13. Coordinate with the Technical and Engineering Supervisor, as necessary, and provide input to response options being pursued.
- 14. Provide direction to the OSC Supervisor rega: ding: ,
a) Verification of assembly area habitability b) Surveying and ssmpling tasks tn be accomplished c) Protective measures to be employed for personnel being dispatched into~ known or potential radiological hazard areas.
- 15. Evaluate projected exposures to personnel who may be involved in rescue, repair, or operational tasks in known or potential radiological hazard areas and a) Recommend authorization.of exposure level increases to the Emergency Coordinator, as required.
o) As necessary, suoervise administration of Potassium Iodide in . accordance with EPIP 4.5. g , 4
, e.
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 59 ~of 65 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 ATTACHMENT 7 (Continued) . SITE RADIATION PROTECTION COORDINATOR CHECKLIST TIME ITEM , c) Coordinate with the Tecnnical .and Engineering Supervisor regarding alternative response options where potential personnel exposures are excessive.
- 16. Insure that personnel are briefed regarding potential radiological hazards protective measures to be taken and limits to be observed prior to their being dispatched into the plant.
- 17. Initiate post accident sampling based upon plant status indication that may be indicative of fuel damage in an effort to determine if l core degradation might have occurred.
- 18. Initiate post accident sampling to aid in evaluating the source term of ongoing or potential radiological releases considering the following types of samples:
a) Effluent release point particulate filters and charcoal cartridges. b) Drywell and Torus atmosphere c) Reactor Building atmosphere d) Reactor Coolant e) Torus water
- 19. Coordinate with the Radiological Assessment Coordinator and perform dose projections following:
a) Significant changes in effluent releases b) Changes in meteorological conditions c) Significant changes in estimated duration of releases in progress d) Changes in source term isotopic distribution
. - .=.
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 60 of 65 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 ATTACHMENT 7 (Continued) SITE RADIATION PROTECTION COORDINATOR CHECKLIST TIME ITEM
- 20. Coordinate with the Radiological Assessment-Coordinator to sa.er l off-site radiological survey results as an input parameter in calculating release rates and projected- doses.
- 21. Brief the Assistant OSC Superviser on the topics _ listed in EPIP 2.1,
- Attachment 7, " Recommended OSC Briefing Topics".
COMMENTS: f l l t i
/
Site Raatation Protection Coordinator Time / Date i
, e EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 61 of 65 ..
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 ATTACHMENT 8 RADIO CONSOLE OPERATING INSTRUCTIONS
- 1. Energize by turning the On-Off switch, located on the horizontal pNel adjacent to the selected channel speaker, to the On position.
- 2. Verify the following switch positions:
a) Channel 1 (Operations Radio) volume switch located on the vertical panel is in mid-position. Channel 2 (Security / Radiological Survey Radio) volume switch b) located on the vertical panel is in mid-position. c) Channel 3 (Point-to-Point or Mutual Aid Radio) volume switch located on the vertical panel is in mid-position. d) Unselected cnannel volume switch located on the vertical panel is turned to maximum clockwise position. e) Volume switch on the horizontal panel adjacent to the selected channel speaker which regulates volume on the selected channel is in mid-position. f) Speaker Mute push button is up (red indicating light out) to enable monitoring of radio traffic. g) Push buttons are out (red indicating mute lights out) on the vertical panel for Channels 1, 2, and 3.
- 3. Conduct radio transmissions, as follows:
a) Depress the Channel Select push button on the horizontal panel for the desired transmission frequency (Channel 1 for the Operations Radio, Channel 2 for the Security / Rad Survey Radio). NOTE DAEC will generally not transmit on Channel 3. b) Pick up handset, depress button in the handset and talk. NOTE'
- 1) When handset is picked up (out of its cradle), the l
selected channel speaker is muted. Hence, radio traffic on the selected channel. can only be heard on
, the handset.
- 2) When handset button is depressed, only transmission can be accomplished; no selected channel-traffic can be received. j
- i=-
c , EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 62 of 65 . , ,
. ACTIVATION AND'0PERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 ATTACHMENT 8 (Continued)
RADIO CONSOLE OPERATING INSTRUCTIONS c) To listen for response using the handset, release the handset button. d) To listen for response using the selected channel speaker, return the handset to the cradle. e) To adjust volume on the selected channel, rotate the volume switch,
- located adjacent to the selected channel speaker in the horizontal panel, clockwise for increased volume or counterclockwise for decreased volume.
- 4. Radio traffic on the unselected channels will be heard through the speaker on the right sice of the veritical panel. To reduce the volume, perform the folicwing:
a) Depress the Mute Switch push buttons on the vertical panel for the unselected channels. This will allow transmission to be heard but at a lower volume and/or; b) Rotate the channel volume switch located on the vertical panel counterclockwise which achieves the same results as above, and/or; c) Rotate the Unselected Volume Switch located on the vertical panel in the counterclockwise direction. This will reduce the volume for rsdio traffic on all unselected channels. 5 Conduct transmissions on tha intercom, as follows: NOTE This feature should be used when communicating between facilities (i.e., radio console base stations). a) Depress and hold down the Intercom push button on the horizontal panel. b) Pick handset out of the cradle and talk. NOTE
- 1) Do not depress the switch in the handset. If the switch is depressed, the transmission will be broadcast as if normal radio traffic.
I 2) When the handset is picked up (out of its cradle), . the selected channel speaker is muted. Radio traffic .
~ }
will then only be heard via the handset. I of i y , . - -. _. _ . - _ .7, _. ..
, a EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 63 of 65 -
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 ATTACHMENT 9 ,
' SECURITY AND SUPPORT SUPERVISOR CHECKLIST The following checklist is available for use by the Security and Support
~ Supervisor or another individual, so designated, as an in erisuring that emergency response actions are completed. In the column labeled " Time", the Lactual- time that such items are completed may be recorded. Al ternatively, cnecks may be used or otner appropriate notations may be substituted which will~be of assistance to the user.
- ITEM TIME.
- 1. Provide assistance, as required, in determining initial accountability.
~2. Coordinate, as required, with the OSC Supervisor and Security Shift Supervisor for rescue activities.
- 3. Coordinate,. as necessary, the application of DAEC and Corporate resources in the following areas:
a) Administration _ b) Procurement c) Transportation d) Communications
' e) Food and clothing .
I f) Temporary facilities i
- 4. as required, in activating the ORAA and Provide assistance,f in the evacuation o non-essential personnel from the site.
. 5. Provide assistance, as required, in maintairing supervisory ' personnel located in areas other than tne TSC aware of plant status, response actions being taken, problems, and the like.
- 6. Develop staffing plan for continuous coverage wnere protracted staffing will be required and coordinate, as
' _necessary, with plant supervisory personnel. NOTE Attach separate page with comments.
/
decurity ano support aupervisor i tme/Uate
& p-_. - - , , . -.>w g.. g ,pr-.,-- - ., _ -,--p.- - p.,e m- %- a w- w- ,-y w .-wy- -v r -w-
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page' 64 of. 65 .. . ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 5 Date 7/14/83 ATTACHMENT 10 TSC LOG SHEET Page of 0 ATE TSC SUPERVISOR RECORDED BY TIME NOTES / COMMENTS l 1 i-l. I i l' l I~ I I l _
- - - ~ , . ..
L
, e EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.2 Page 65 of 65 -
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER ~ Revision 5 Date 7/14/83 ATTACHMENT 11 . LOG ENTRY TOPICS
- 1. ' Activation of the TSC and assumption of responsibilities.
- 2. Event classification and escalation /de-escalation basis.
3.* Off-site agency / support arganization notifications and synopsis of discussions. 4.* Protective Action Recommendations provided by Iowa Electric and synopsis of discussions / disposition by local and State. officials. 5.* Vendor contacts and recommendations provided regarding problems discussed.
- 6. Significant plant status .information.
' 7. Problems being experienced and recommendations provided by Operations regarding response actions to be taken.
- 8. Recommendations regarding problem resolution provided to Operations and response actions taken.
- 9. Dispatch of rescue and repair teams and actions taken/ problems-discussed.
-10. Authorize increased exposures.
- 11. - Emergency management directives / policies issued by the Emergency Coordinator.
12.- NRC communications and synopsis of discussions.
- 13. Deactivation and reentry decisions.
- 14. Other information, contacts, etc. pertinent to response actions, i
corrective action options, radiological conditions, engineering determinations, and management directives or actions which may be important from a historical perspective.
- Upon activation of tne EOF, these items will be recorded in the EOF Log.
t m O
, a EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.4 Page 1 . of 9 . .
ACTIVATION AND OPERATION OF THE ORAA Revision 0 Date 6/20/83 l.0 PURPOSE . This procedure provides instructions for activation and operation of the Off-Site Relocation and Assembly Area (0RAA). 2.0 APPLICABILITY 2.1 This procedure shall be implemented upon declaration of an event classified as a SITE or GENERAL EMERGENCY or for other events which result in the need to evacuate the site. 2.2 This procedure applies to members of the plant staff and other on-site personnel followiog a site evacuation. 3.0 RESPONSIBILITIES 3.1 Security Shift Supervisor 3.1.1 Designate Security Force personnel to assist in traffic control on owner controlled or leased areas. 3.1.2 Designate Security Force personnel to assist the Assistant OSC Supervisor in maintaining accountability. 3.2 ORAA Supervisor 3.2.1 Verify that actions required to physically place the ORAA into operation are accomplished. 3.2.2 Supervise the evacuation of personnel to the ORAA. 3.2.3 Provide management and overall direction to relocated personnel at the ORAA. 3.2.4 Coordinate support activities which may be provided by personnel at the ORAA. 4.0 INSTRUCTIONS 4.1 Evacuation from the DAEC 4.1.1 The Emergency Coordinator shall contact the ORAA Supervisor uoon determining that an evacuation from the site should be conducted due to deteriorating plant conditions or as required. w s--
.p,. --.-- - , . , - - - - - ,y - ,g en --9
- ' 9 EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.4 Page 2 of 9
~ ' ' !
ACTIVATION AND OPERATION OF THE ORAA Revision 0 Date 6/20/83 NOTE Preferably, this contact.and. subsequent activatio'n activities required to set up the ORAA should be accomplished prior to the need to evacuate the site. a) An evacuation of non-essential personnel from the site is required for events classified as a SITE' or GENERAL EMERGENCY. b) Evacuation of all personnel from the site wno cannot be adequately. protected from radiological hazards may also be required under severe accident conditions; e.g., those personnel.
- who are suspected to have a sensitivity to Potassium Iodide (KI).
4.1.2' If neither the designated ORAA Supervisor nor any of the alternates are available, tne Emergency Coordinator shall appoint an individual to execute the assigned functions.
-4.1.3 Evacuation from the OAEC shall be supervised by the ORAA Supervisor with the assistance of the OSC Supervisor and Security Supervisor.
~
a) Attachment 1, "0RAA Activation Checklist", should be used by the ORAA Supervisor to prepare tne ORAA for arrival of evacuees from the'DAEC. b) .In addition to the checklist, the ORAA Supervisor shall maintain a log of all pertinent activities involved in evacuating personnel from the site and activating tne ORAA. 4.1.4 The ORAA Supervisor shall~ coordinate with the OSC Supervisor to assign two Health Physics Technicians to assist in activating tne ORAA and evacuating personnel from the site. a) One Health Physics Technician should be dispatened to initiate - activation of the ORAA, in accordance with Section 4.2 of tnis procedure. b) At the discretion of the ORIA Supervisor, additional members of the Plant-Staff may be assigned to assist in this effort. -[ 4.1.5 The ORAA Supervisor shall coordinate with the Security Shift Supervisor and assign two members of the Security Force to assist in the evacuation,-one of which should accomoany the Healtn Physics Technician mentioned above to the-0RAA with the Palo Key Ring. 4.1.6 The ORAA Supervisor should contact the Palo Town Council Representative listed in the Emergency Telephone Book to aavise that an evacuation from the OAEC is planned.
, n EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.4 Page 3 .of 9 ,, ,
ACTIVATION AND OPERATION OF THE ORAA Revision 0 Date 6/20/83 4.1.7 The Security Shift Supervisor shall advise the Local Law Enforcement Agency (LLEA) individual stationed at the four corners of the planned evacuation, a) The LLEA should be requested to provide traffic control on public roads in Palo in the vicinity of the Palo School. b) The LLEA should be advised of the planned evacuation route. 4.1.8 The ORAA Supervisor, the second Health Physics Technician and the second Security Force member should lead the evacuation from the DAEC to the ORAA. NOTE Preferably, prior to initiating the evacuation, the ORAA i Supervisor will have been advised by the Health Physics Technician at the ORAA that the facility is ready to accept evacuees. a) Personal transportation should be used and, to the extent possible, the number of vehicles leaving the site should be minimized. b) The route (s) to be used for evacuation are shown in EPIP 1.3, Attachment 4, " Site Evacuation Routes". 4.1.9 If evacuation of the Security Control Point (SCP) is required, the Security Shift Supervisor should ensure that the following items are removed from the SCP and relocated at the ORAA: a) The stcrage boards used for dosimetry and security badges including TLD's, dosimeters and badges. b) All radios an'd emergency access key rings. c) All access lists and accountability lists. 4.1.10 Evacuating vehicles will normally approach the ORAA from the north, a) The Security Force Member previously dispatched to the ORAA will be stationed at the north end of the ORAA parking lot to direct venicle parking. b) DAEC Security Force personnel should limit their involvement in traffic control to the ORAA parking lot. c) LLEA personnel will maintain traffic control on the county road from Palo to the DAEC. g - -
,-,-----a ye-,+ y-
~
1 EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP- 2.4 Page 4 of 9
~ ' '
ACTIVATION AND OPERATION OF THE ORAA Revision 0 Date 6/20/83 4.1.11 A check point / monitoring station will be set up at the northwest corner of the ORAA property. a) At this station, a Security Force Memoer will check in and record the. names of personnel from the plant. b) If radioactive releases from DAEC are in progress or have occurred, vehicles will be monitored by Health Physics personnel and directed to clean or contaminated parking areas, as appropriate. NOTE e. Contaminated vehicles shall remain in the contaminated parking area until decontaminated or.until the contamination has decayed to levels acceptable for uncontrolled release, as specified in RPP' 5.3, " Personnel,-Equipment and Materials Access to Controlled and Posted Areas".
~
4.2 Activation of the ORAA 4.2.1 The overall building floor plan and surrounding general area is shown in Attachment 2, "Off-Site Relocation and Assembly Area". 4.2.2 Initial access to the f acility should be gained by way of the front entrance, through the gymnasium to the locker. room located to the left of the stage. NOTE A list of the equipment and supplies maintained at the ORAA is contained in EPIP 6.3, " Maintenance of Emergency Facilities, Equipment and Supplies". 4.2.3 The following tasks should be accomplished by the Health Physics Technician to activate the ORAA: , a) Set-up the portal monitor in the hallway leading to the gymnasium entrance just beyond tne er.tryway to tha locker room and turn on the power. b) Place paper or plastic on the floor in the _ hallway from the outside door, adjacent to the locker room, to the portal monitor to minimize the potential spread of contamination. c) Install the two (2) comercial telephones and verify their operability. m
,yp ea.w, , .,,,y-.-=c-#._ - , - ,. - - . . . - - , , - , , - , ,w -
w
~ EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.4 Page 5 . o.f 9 ,
ACTIVATION AND OPERATION OF THE ORAA Revision 0 Date 6/20/83 d) Inform the ORAA Supervisor that the setup of the facility has been completed. - 4.3 Ooeration of the ORAA 4.3.1 Following activation of the ORAA, the ORAA Supervisor should periodically contact the Site Radiation Protection Coordinator , regarding changes in radiological or meteorological conditions which may impact the continued haottability of the ORAA. 4.3.2 The gymnasiun will function as tne assembly area at the ORAA.
- a) Arriving personnel should enter the f acility using the door adjacent to the locker room on the northeast side.
b) Personnel will be monitored by stepping into the portal monitor and waiting for the GREEN (Safe) or audible alarm and RED ( Alarm', light to be illuminated. c) If the RED light is illuminated and the " audible alarm" is heard, personnel shall be redirected to the locker room for further evaluation and decontantination. d) If the GREEN light is illuninat9d, personnel shall pass on through the portal monitor into the gymnasium. 4.3.3 Personnel showing positive indications of contamination will be handled as follows: a) If contamination is on the clothing, the contaminated clothing will be removed, bagged and tagged with the owner!s name. If the person'is then found to be clean, he will be provided with j clean, temporary clothing (e.g., coveralls) and directed into l the gymnasium. b) If remaining clothing or the individual himself is found to be contaminated, he will be decontaminated to the extent possible using paper towels, waterle'ss hand cleaner, etc. and provided with clean, temporary clothing (e.g., coveralls). When adequately decontaminated, he will be directed into the gymnasium. NOTE If further decontamination is necessary, such personnel shall be transported to the Off-Site Decontamination Facility. 4.3.4 Copies of the " Personal Statement Concerning Incident" form, provided in EPIP 2.1, should be distributed to all evacuated personnel, if not already completed at the OSC, and the completed copies collected before personnel are released.
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.4 Page 6 -of 9 't ACTIVATION AND OPERATION OF THE ORAA Revision 0 Date 6/20/83 4.3.5 The ORAA Supervisor shall contact the Security and Supppet Supervisor to determine if personnel assembled in the gynnasium should be permitted to go home, standby at the ORAA, or return to the plant. 4.3.6 If personnel are to be released: a) The ORAA Supervisor should advise those personnel to be released of the location of the plume, if any, and areas to avoid within the EPZ.
- b) Dosimetry should be collected from all such personnel prior to their departure.
4.3.7 If additional vehicles are needed to facilitate release of personnel from the ORAA, the ORAA Supervisor should advise the Security and Support Supervisor at the TSC who should then contact the Support Services Coordinator in the EOF to make the necessary arrangements. 4.4 Receipt of Off-Site Monitoring Samole Media 4.4.1 As directed by the Radiological Assessment Coordinator, the Off-Site Monitoring Teams may temporarily lehve samples at the ORAA. 4.4.2 Samples should be stored in a f ashion such that they do not pose a personnel exposure hazard. 4.4.3 If desired by the Radiological Assessment Coordinator, personnel from the ORAA may be requested to deliver these samples to the Off-Site Laboratory at 1205 lith Street S.W. in Cedar Rapids. NOTE Normally, a vehicle will be dispatched from Cedar Rapids to obtain any ,such samples. 4.5 Use of the ORAA as a Staging Area for Reentry 4.5.1 The ORAA is -available as a staging area to support recovery and re-entry efforts at the DAEC. 4.5.2 Details regarding operation of the ORAA as a staging area will be developed as part of the overall recovery planning effort. 4.5 Deactivation of the ORAA 4.6.1 The ORAA Supervisor shall direct deactivation of the ORAA upon being" authorized by the Security and Support Supervisor.
"p+ --
= o EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.4 Page 7 of 9 - :
ACTIVATION AND OPERATION OF THE ORAA Revisicq 0 Date 6/20/83 4.6.2 Deactivation shall be accomplished in accordance with the requirements of EPIP 5.1, " Deactivation of the Emergency Response Org anization" . 4.6.3 The ORAA Supervisor shall insure that the following activities are accomplished upon deactivating the ORAA: a) Inventory equipment and supplies and restock them, as necessary, b) Per#crm any necessary decontamination of the facility. e c) Conduct housekeeping activities, as necessary, to clean up the facility.
5.0 REFERENCES
5.1 Duane Arnold Energy Center Emergency Plan 5.2 NUREG 0654, Rev. 1 6.0 ATTACHMENTS 6.1 ORAA Activation Checklist 6.2 Off- . de tion and A --tly a ea
/ -,
Approved by: A DATE: _ jf k/963
~
x::nergency eianni M I Approved by: 2/td [dttnd kadiation Fratectiorvaup rvisor DATE: fMO Approved by: /s 4, __ L p - DATE: i
/3[b 5egurity hupefvfsof~
Q ,. ! Reviewed by: /
/L h a v-- DATE: N/c/t 3 n'e n vooroinator j O
i Reviewed by: dj/ DATE: ?/V? i OperatAons commptee Ccairman Approved.by: DATE: piant -nuc l e ar aupyintence
.- - - ., y ,, y .,. -www g --- -- -e r - - - - - - -
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.4 Page 8 of 9 - Revision 0 ACTIVATION AND OPERATION OF THE ORAA Date 6/20/83 ATTACHMENT 1 ORAA ACTIVATION CHECKLIST ..
- 1. Coordinate with the 050 Supervisor to assign two Health Physics
- Technicians to assist in activating the ORAA and evacuating personnel from the DAEC (Section 4.1.4).
2.. Coordinate with the Security Shift Supervisor '6 t assign two Security Force Members to assist in the planned evacuation (Section 4.1.5).
.3. Advise the Palo Town Council Representative of the planned evacuation from the DAEC to the Palo School. -(Section 4.1.6) e
- 4. Verify that Local Law Enforcement Agencies have been advised of the planned evacuation (Section 4.1.7).
I
- 5. Dispatch a Health P1ysics Technician and a Security Force Member to commence set up of.the ORAA (Sections 4.1.4 and 4.1.5).
NOTE. The following activities should be accomplished by personnel dispatched to the ORAA in 5 above. . 5.1 Take the Palo Key Ring (Section 4.1.5). . 5.2 Set up and energize the portal monitor (Section 4.2.3). 5.3 Paper the hallway and stage -(Section 4.2.3) 5.4 Install and verify operability of the two (2) commercial phones (Section 4.2.3) 5.5 Set up a check point at the northeast corner of the ORAA Parking . Area (Section 4.1.11). 5.6 Advise the ORAA Supervisor that, set up of the facility is complete.
- 6. If evacuation of the SCP is necessary, insure that Security Force personnel take the following items to the ORAA (Section 4.1.9).
6.1- Storage boards for dosimetry and security badges including TLDs, dosimeters, and badges. 6.2 Radios and emergency key rings. 6.3 Access and accountability lists.
- 7. Lead the evacuation to the ORAA accompanied by the second Health Physics Technician and Security Force Members. (Section 4.1.3).
OP.AA Supervisor. Date
~
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.4 Page 9 of 9 - - ACTIVATION AND OPERATION OF THE ORAA Revision 0 Date 6/20/83 ATTACHMENT 2 . OFF-SITE RELOCATION AND ASSEMBLY AREA 8B EMERGE!!CV i 9 LOCKERS TELEPHONE JACKS 4 3&4 4 STAGE ej
,ca m t
/
PORTAL MO'iITOR 1 1
- SLEACHERS BLEACHERS --
N GYM PARKING PARKIt:G 3 CLASSRCOM MENS T . I RCOM , e 'L s'L a 2 ; f LADIES + l I COUNCIL CLA'SSRCCM KITCHEN RCOM W FRO'iT CHAMEERS g;7;;.;;g
= Number of key on Palo Key Ring used 'o open that particular door.
4 a EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.5 Page 1 of 29 . , , CONTROL R00M EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83 1.0 PURPOSE This procedure provides guidance associated with implementing emergency preparedness requirements in the Control Room upon determining that the plant is in an unexpected operational condition. 2.0 APPLICABILITY This procedure is applicable to on-shift operating personnel ft,r any event wnen the plant is not in an expected mode of operation and to the Emergency Response Organization personnel designated to report to and perform response functions in the Control Room for events classified as an ALERT or greater. 3.0 RESPONSIBILITIES 3.1 Operations Shift Suoervisor 3.1.1 Take action, as specified in Emergency Operating Procedures or as otherwise may be required, to restore the plant to a safe condition within the limitations prescribed in the DAEC Operating License and Technical Specifications. 3.1.2 Evaluate plant conditions, initially classify the event and
- recommend reclassification of the event based upon plant status and/or projected trends.
3.1.3 Develop initial protective action recommendations, as appropriate, and initiate notification of Iowa Electric and off-site agency personnel. 3.1.4 Initiate evacuation of the plant, as required, and insure accountability for all operating personnel on shift. 3.2 Control Room Coordinator 3.2.1 Provide technical assistance and direction, as necessary, to the Operations Shift Supervisor to restore the plant to a safe condition. 3.2.2 Verify that personnel in the TSC and that tne NRC are kept fully infor:ned as to plant status, problems, operational activities in progress and projected conditions. 3.2.3 Coordinate support activities conducted by personnel in the TSC and OSC with the TSC Supervisor.
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.5 Page 2 of 29
. CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83 4.0 INSTRUCTIONS 4.1 Event Classification ,
4.1.1 Upon determining that the plant is in an unexpected operational condition, the Operations Shift Supervisor shall evaluate plant conditions using guidance contained in EPIP 1.1, " Determination of the Emergency Action Level", and, as warranted, classify the event in one of the four emergency categories, a) Contact'should be made with the Operations Supervisor or Duty
, Emergency Coordinator for clarification, as may be warranted.
~ b) Additionally, Technical Support staff personnel may be contacted for advice regarding event classification and/or reporting requirements. NOTE Attachment 1, " Shift Supervisor Checklist", should be used by the Operations Shift Supervisor to insure that all required actions are completed. 4.1.2 In addition to unexpected plant operational coriditions being categorized in onemay cond.tions which of four emergency result categories, in declaration other unexpected of an emergency which are identified in EPIP 1.1 are included as Attachment 2,
" Additional Conditions Requiring Emergency Classification".
4.1.3 If the determination is made that the event need not be classified as an emergency, the Operations Shift Supervisor snould review EPIP 1.2, " Notification", to determine if the event requires prcmot notification of the NRC, in accordance with 10CFR50.72. 4.1.4 If classified as an emergency, the Operations Shift Supervisor shall inititte notification, as discussed in paragraph 4.2. a) The Operations Shift Supervisor snall function additionally as the Emergency Coordinator- and Site Radiation Protection Coordinator until relieved of such function by appropriately qualified personnel, b) Key functions assigned to the Emergency Coordinator and Site Radiation Protection Coordinator which should be comoleted during initial activation are prescribed on Attachment 1, " Shift Supervisor Checklist". 4
)
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.5 Page 3 of 29 ~ I CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83 4.2 Notification 4.2.1 Notification of DAEC, Corporate and off-site agency personnel, including the NRC, .shall be accomplished, as specified in EPIP 1.2,
" Noti f icat ion" .
EK - During non-normal working hours, notification of off-site authorities will normally be accomplished by the second SRO on shift.
. 4.2.2 As part of the Initial Notification Message to off-site authorities the Operations Shift Supervisor is required to recommend protective actions for the health and safety of the public, if so* warranted.
a) An evaluation of projected off-site doses and development of associated protective action recommendations should be accomplished if a radiological release is in progress, using EPIP 3.3a, " Manual Dose Projections", or EPIP 3.3b,-
" Computerized Dose Projections".
b) If no radiological release is occurring, protective action recommendations, based upon plant conditions, should be made for events classified as SITE or GENERAL EMERGENCY where the potential clearly exists for significant off-site releases. I NOTE For example, the potential for a significant off-site release may not be immediately appeent as a result of a sustained loss of AC power (Total loss of AC power for >15 minutes), an event classified as a SITE EMERGENCY. However, such a potential is much more apparent as a result of a transient which should result in a scram, but doesn't (Transient Requiring Operation of Shutdown Systems with Failure to Scram), an event also classified as a SITE EMERGENCY. 4.2.3 Protective action recommendations provided by the Operations Shift Supervisor are defined in EPIP 3.3a, " Manual Dose Projections", and shall normally consist of sheltering in the affected areas unless: a) Confirmation of dose . rates at either the site boundary or 2 mile radius is accomplished, or b) Clear indications exist that ECCS performance and primary containment integrity are in jeopardy.
' *
- e-3-c'p-e+r+5 UW' r w--g y w-v- - mtg-
e EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.5 Page 4 of 29
't CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83 4.3 Plant Evacuation and Response Center Manning 4.3.1 For all event's classified as an ALERT or greater, a plan't evacuation shall be conducted as prescribed in EPIP 1.3, " Plant and '
Site Evacuation". NOTE , As noted in EPIP 1.3, plant evacuation may also be appropriate for other situations, as well. 4.3.2 Upon annunciation of the Evacuation Alann, all Operations
- Departnent personnel on-site should recort to the Control Rocm, whether or not assigned on-shift dutie.
a) During normal working hours, personnel assigned to the CAEC other than those assigned to the Operations Department shall l report to the Operational Support Center and Technical Support l Center, as prescribed in EPIP 2.1, " Activation and Operation of the Operational Support Center", and EPIP 2.2, " Activation and Operation of the Technical Support Center". b) If the event occurs during other than normal working hours, personnel shall ' tut called out to staff the required Emergency l Response Organization positions, as prescribed in EPIP 1.2, "Notific ation" . 4.3.3 The Shift Technical Advisor (STA) should report to the Control Room, if not already present, to assist in the evaluation of plant conditions and to provide assistance, as requested by the Operations Shift Supervisor, to mitigate the consequences of the event, terminate any transient in progress and restore the plant to a safe condition. 4.3.4 The Operations Supervisor shall report to the Control Room to function as the Control Room Coordinator, providing advice and direction, as required, to the.0perations Shift Supervisor and assuming responsibility for communications and interf ace with personnel located in the TSC and with the NRC. 4.3.5 Additional personnel designated to report to the Control Room for communications and status reporting functions are, as follows: a) TSC Communicator b) Radiological Data (Back Panel) Connunicator c) NRC ENS Communicator d) Plant Status (VAX Terminal) Cannunicator e) Plant Status Data Recorder .
~' ' ' ' ' ' '
'e O EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.5 N. Page 5 of 29 -
CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83 ME , t Individuals to fill the positions defhed by 4.3.5(c) through (e) dove should be selected from among staff
, 5 personnel available on-site or called out, as required, 4 ^;. under the direction of the Control Room Coordinator.
'4'.3.6 The Operations Shift Supervisor or Control Room. Coordinator may direct that additional' 0perations Department personnel be contacted for operating,' monitoring and comunications functions.
7
. .. 4.3.7 In addition to operations and engineering personnel reporting to the Control Room for the functions identified, the NRC Resident
-/
Inspector is expected to report to the Control Room to independently evaluate plant status and response actions underway and to insure that NRC Emergency centers in Bethesda, MD. and at Regica III in Glen Ellyn, IL. are kept fully informed of the t h'5 situation.
~
4.3.8 The Operations Shift Supervisor shall insure that an account -
- ability check is made for all emergency response personnel assigned A. ,
to the Control Room and all operations personnel on-shift, and
'i insure that the Accountability Check- form, provided in EPIP 1.3,
" Plant and Site Evacuation", is provided to Security.
'a) A Security Force member should be dispatched to the Control Room as specified in EPIP 1.3, " Plant and Site Evacuation", to a maintain access control during an emergency.
b) The Security Force member shall maintain a log of personnel who enter and exit the Control Room during the course of an emergency for accountability purposes unless directed otherwise by the Emergency Coordinator. s 4.4 Comunications and Status Monitoring 4.4.1 The TSC and Back Panel Communicator positions, discussed in paragraph 4.3.5, are identified on the Emergency Assignment Tag Board and during initial activation, should be filled by engineering personnel. s T a) Personnel .so ' assigned s uld inform the Operations Shift s Supervisor or Control Room Coordinator, if present, of their assigned position upon arrival in the Control Room. 3 b) Individuals who fill the remaining comunicator and status reporting functions should be selected by the Control Room Coordinator and also, should advise the Ooerations Shift Supervisor or Control Room Coordinator, if present, of their arrival in the Control Room. 4 ___m . _ . _ _ _
e
\ .
EMERGENCY PLAN IMPLEMENTING PROCEDURE w EPIP 2.5 Page of 29 CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 - - -
+
Date 7/1/83 c) Following initial activation, the Control Room Coordinator and/or Operations Shift Supervisor sh)uld insure that the ( required communications and data recording / transmission s functions are bei.ng executed satisf actorily, reassigning personnel, and/or appointing others, as necessary.. 4.4.2 Plant status information which is to be initially reported has been established in a report format on the VAX and is included as l Attachment 3 " Plant Status Report". a) The Plant Status Datt. Recorder should obtain an initial set of I readings 'using Attachment 3, " Plant Status Report", review tnem
-with the Control Room Coordinator and provide the data sheet to the VAX Terminal Operator.
b) The VAX Terminal Operator should input the data into the computer program and notify the terminal operators in the TSC and the EOF of the report's availability, as described in EPIP 3.3.b, " Computerized Dose Projections",
^
c) Update reports shou 1d be provided at approximate 15 minute intervals or as otherwise directed by the Control Room Coordinator. 4.4.3 Status info'rmation being reported, its frequency and report format may be modified at the discretion of the Control Room Coordinator and TSC Supervisor. a) Information to be reported should be based on the type of event, plant < conditions deemed to be pertinent and tne event onase. b) The' renort form on the VAX can be modified, adding or deleting information entries as is appropriate. c) Alternatively, the Plant Status Data Recorder or VAX Terminal Operator may report such information verbally to both the TSC and E0F status recorders. 4.4.4 The dedicated telephone circuit between the Control Room and the TSC should be used by the TSC Communicator uncer tne direction of the Control-Room Coordinator for the following purposes: a) Provide amplifying information regarding plant status and clarify information indicated on the Plant Status Report, as necessary. b) Provide immediate updates to the TSC regarding cnanging conditions, new information, etc. c) Identify problems that are rencountered and discuss actions unicn can be taken for their resolution.
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.5 Page 7 ofj29 ,, CONTROL ROOM ' EMERGENCY RESPONSE OPERATION : Revision 0 Date 7/1/83-d) Discuss operational evolutions and repair activities which are
. planned and report status during execution. -
e) Serve as a means .for the Control Room Coordinator to talk directly to the TSC Supervisor and Emergency Coordinator. NOTE - The Control Room Coordinator may also make use of the intercom when discussing problems and status where interests can best be serYed by talking simultaneously to seVeral key supervisors in the TSC and OSC. o 4.4.5 The ENS circuit shall be used to initially notify the HRC of emergency conditions. a) As identified in EPIP 1.2, "Notffication", and as specified in 10CFR50.72,'such initial notifications shall be accomplished within 1 hour of the occurrence of the event. b) If an event is classified as an ALERT or greater, once notified, the ENS circuit. shall remain open and shall be. manned by the ENS
. Communicator or at the option of the NRC, tne NRC Resident Inspector, to enab.le continuous communications with the NRC.
NOTE Normally, the NRC Operations Center in Bethesda, MD. will establish a communications link via the ENS to NRC Region IIL0ffices in Glen Ellyn, IL. so that-the DAEC, Region III and Headquarters are able to communicate simultaneously. c) Status information to be reported to the NRC upon initial notification has been defined by the NRC and is included as Attachment 4, "NRC Event Notification Information". NOTE I Information being reported to NRC may be annotated on the attachment at the discretion of the Operations Shift Supervisor or Control Room Coordinator. d) Further information regarding the event, status updates, etc. will normally be provided by the NRC Resident Inspector wno will be located in the Control Room or TSC.
9, = EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP .2.5 Page g of 29
~
Revision 0 CONTROL ROOM' EMERGENCY-RESPONSE OPERATION Date 7/1/83 NOTE Upon activation of the TSC and the EOF, ENS communicators will.be assigned at those locations; hcwever, specific information regarding plant status will normally be provided 2 by the NRC Resident Inspector from the ENS extension in the Control Room. . 4.4.6 Radiological and meteorological information shall be provided to the Site Radiation Protection Coordinator through a direct-ring (Black) telephone located on Panel 1C22 by the Radiological Data (Back Panel) Communicator. a) Status information to be provided as input into dose projection calculations includes meteorological information, effluent monitor readings and process system flows. b) Effluent monitor information and process flows should be obtained from the Kaman System console located in the Control Room. NOTE
- 1) Instructions for operation of the Kaman System console are included as Attachment 5, "Kaman System Information Retrieval" .
- 2) Information may also be obtained from the console located in the Radiochesistry Laboratory.
c) '&.teorological infonnation to be provided includes wind speed (in miles per hour), wind direction (tne directica from which the wind is bicwing, in degrees) and 21,T (the difference in ' ' temperature between sensors located at 165 and 35 feet in *F). NOTE For releases from the Reactor Building Stacks or Turbine Building, raport wind speed and direction at the 35 feet elevation. Otherwise, report the data at the 165 foot elevation. d) 21T can be both negative or positive and should be determined by reading point 2 on the outside air temperature recorder on Panel 1C22 or by subtracting the indicated temperature at the 35 ft. level from the indicated temperature at the 165 ft, level, ots. 3 and 1 on the outside air temperature recareer on Panel IC22. w l
)
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.5 Page _g o'f 29 CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83 NOTE
- 1. As an alternata, wind speed, wind direction and AT can be obtained by selecting 28 on the Process Computer Video Demand C(,asole.
- 2. Meteorological .information and weather forecasts may also be obtained from the NWS First Order Station Flight Services 4 (Cedar Rapids Airport) and NWS Forecasting Station (Des Moines) using the telephone numbers provided in the Emergency Telephone Book.
e) Additional radiological information to be provided by the Back Panel Communicator upon request of' the Site Radiation-Protection Coordinator includes Area Radiation Monitor (ARM) and Containment High Range Radiation Monitor readings. 4.4.8 . The Back Panel Comunicator should obtain an initial set of-readings identified on Attachment 6, " Radiological Status", upon arriving at the Control Room and reporting to the Site Radiation Protection Coordinctor, a) The radiological and meteorological parameters should be ' monitored and reported at a frequency specified by the Sito Radiation Protection Coordinator. b) Additionally, when changes are detected and/or trends become apparent, the Site Radiation Protection Coordinator and Control Room Coordinator should be aovised. 4.5 Trending-4.5.1 Trending of important plant parameters will be accomplished as directed by the Control Room Coordinator in conjunction with the TSC Supervisor. 4.5.2 Parameters to be considered for trending include, but should not be limited to: a) Nuclear instrumentation; e.g., if shutdown has not been ' achieved. b)~ Reactor vessel water level end pressure. c) Contair. ment pressure and temperature. d) Suppression Pool water level and temperature. e) ARM and Containment Hign Range Radiation Monitor levels, f) Radiological effluent concentrations. -
a i c EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP- 2.5 Page 10 of 29 CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83 , 4.5.3 Recorders installed in the Control Room shculd be used to the maximum extent possible. To enable more accurate trending, the recorder may be placed on high speed. 4.5.4 Additional plant parameters will be trended, as appropriate, based upon the event and plant condition as identified by the Control Room Coordinator or TSC Supervisor. NOTE Parameter trending should also be accomplished in the TSC and the EOF, as prescribed in EPIP 2.2, " Activation and Operation of the TSC", CPIP 1.3, " Activation and Operation ' of the EOF", and CPIP 2.2, " Technical Support Coordination". The Controi Room Coordinator should be advised of trends noted. 4.6 Emergency Response Activities 4.6.1 The Control Room Coordinator shall insure that the TSC Supervisor is kept informed of plant status and problems which are discovered. a) The Control Room Coordinator should review problems and corrective action options with the Technical and Engineering Sucervisor and provide input regarding options to be pursued, actions to be taken, and so forth. b) The Control Room Coordinator shall also insure that NRC personnel in the Control Room are kept appraised of plant status, problems, corrective action options being pursued and
, response actions underway.
4.6.2 Response actions underway and being planned to counter problems which become apparent, terminate the transient and mitioate the consequences of the event should be reviewed witn the TSC Supervisor, a) TSC operations, engineering, and maintenance personnel shall provide support for such efforts, as directed by the Technical and Engineering Supervisor. b) Where alternative response action options are avaliable, the Emergency Coordinator shall select the option to be pursued. 4.6.3 In responding to off-normal conditions and restoring the plant to an acceptable operating mode, procedural requirements should Le followed to the extent that plant conditions are consistent with the procedural' basis, a) In those cases where adherence to procedural requirements can not be maintained, the Control Room Coordinator should be informed. - d w e
\ ., a EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.5 ~
Page of 29 f 17 CONTROL ROOM EMERGENCY RCSPONSE OPERATION- Revision 0 Date 7/1/83 1 ( b) The normal' administration practice governing temporsey changes to procedures should be implemented unless such practices have been waived by the Emergency Response and Recovery Director. NOTE
- 1) If time does not permit, response actions should be initiated to terminate the transient and mitigate the consequences of an accident, irrespective of procedural requirements.
- 2) In such cases, actions taken should be logged in the Control Room Log.
- 4. 6. 4- Likewise, adherence to Technical Specification requirements should be maintained.
' a) In the event that deviations from Technical Specification requirements becomes necessary, reascnable action that departs from a license condition or technical specification in an emergency, when such action is immediately needed to protect the public health and safety, is permissible, as specified in - 10CFR50.54(x). b) Prior to taking such actions, approval shall be granted, at a minimum, by a licensed Senior Reactor Operator, as specified in 10CFR50.54(y). c) As noted in EPIP 1.2, " Notification", the NRC shall be notified, in accordance with 10CFR50.72, of emergency circumstances requiring such protective action before such action is taken, time permitting. NOTE Time permitting, the need to deviate from license conditions
= or technical specifications should be approved by the highest levels of management holding a valid SRO license, as l
well as by the Emergency Coordinator and Emergency Response l and Recovery Director. 4.6.5 The Control Room Coordinator, with the assistance of tne Operations Shift Supervisor, should recommend reclassification of *.he evant to the Emergency Coordinator via the TSC Supervisor based upon plant I status and projected conditions indicated by parameter trenos, system operating configurations and system / equipment limitations which are being approached. i pgge w ~-w w -. g --m-evwg e.. Mg 7'~-n T F *w - ' -' *.-+7N - ' T
> a EMERGENCY PLAN IMPLEMENTING PROCEDURE _ EPIP 2.5 Page 12 of 29 Q0NTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83 1
4.6.6 Based upon the event, the Operations Shift Supervisor may require that operators be dispatched from the Control Room to areas of the plant to conduct operating and monitoring functions. a) The Control Room Coordinator should insure that the TSC Supervisor is advised, in advance when possible, of all such personnel being dispatched. , b) Prior to dispatch, Area Radiation Monitor-(ARM) levels should be checked to insure that the routes to be used and areas where personnel are being dispatched are habitable.
'- c) Time permitting, an estimate of the total exposure to be received should be made as prescribed in EPIP 4.3, " Rescue and Emergency Repair Work".
d) If access is required through or into an area where potential radiological problems exist, the 05C Supervisor shall insure that adequate protective clothing and equipment is donned before entry. NOTE The Site Radiation Protection Coordinator shall determine the protective measures to be employed and whether or not personnel being dispatched should be accompanied by a Health Physics Technician. e) Personnel being dispatched should be provided with an Operations Radio to enable continuous communications with personnel in the-Control Room. 4.6.7 The Control Room Coordinator should consult with the TSC Supervisor to insure that Control Room personnel are aware of the dispatch of any personnel on site, such as rescue and repair activities, on-site monitoring, etc.
. a) As plant status changes, and7or problems are discovered, the Control Room Coordinator shall insure that the TSC Supervisor is advised.
b) If such conditions may ootentially affect personnel already dispatched, the Control Room Coordinator snould advise the TSC Supervisor of the potential proolems. c) During sucn time when personnel have been dispatched into the plant, the Control Room Coordinator shall verify that the Back Farel Comnunicator closely monitors the appropriate in-plant and effluent radiation monitor levels and scoraise both him and the Site Radiatio,n Protection Coordinator of any changes or trends. 0
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.5 Page of 29 CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83 4.6.8 Where response actions may extend over a protracted period of time or when additional operations personnel .are required to adequately. conduct response and recovery activities, the Control Room Coordinator shall make provisions- for continuous coverage by realigning personnel shift assignments and shift schedules. 4.6.9 In restoring the plant to a safe, stable configuration during an event where core degradation has occurred or wnere significant quantities of radioactive material have been released or are available for release (transport) from the Reactor Coolant System, consideration should be given to minimizing the spread of radioactive contamination to other areas of the plant and containing the radiological hazard to as few systems and as small an area as possible. a) The Control Room Coordinator should consult with the TSC Supervisor and verify that TSC staff personnel, under the direction of the Technical and Engineering Superv1sor,-evaluate options available to aid in this effort. b) Control Room personnel should be alert to this potential and appraise the Operations Shift Supervisor and Control Room Coordinator of such potential problems. NOTE j
- 1) No action should be taken to defeat system operation or operate systems in an off-normal manner to acnieve this objective if, in doing so, the health and safety of the public could be jeopardized.
I 2) Likewise, no such action should be taken, even if the health and safety of the public would not be affected, if such action violates Technical Specification requirements until relief from such requirements is requested and so granted.
- 3) Notwithstanding the above, where action is imediately needed to protect the public haalth and safety, such action shall be taken as permitted by 10CFR50.54(x) and l
(y), as discussed in paragrpn 4.6.4. l 4.6.10 The Control Room Coordinator shall evaluate plant status, key paramaters and the ability to maintain the plant in a stable, safe condition and advise the TSC Supervisor of his readiness to deactivate emergency response personnel in the Control Rocm. a) Deactivation should not be accomplished until the requirements of EPIP 5.1, " Deactivation of the Emergency Response Organization", have been met.
t e EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.5 Page 14 of 29 ,y CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83 b) Deactivation and restoration of the plant to an operating condition following a significant event shall be accomplished in accordance with a recovery plan, developed as specified in EPIP 5.2, " Recovery and Reentry".
5.0 REFERENCES
5.1 DAEC Emergency Plan 5.2 HUREG 0654, Rev. 1
- 5.3 10CFR50.54 5.4 IE Information Notice No. 83-34 5.5 NRC Region III Emergency Response Plan and Implementing Procedures 6.0 ATTACHMENTS 6.1 Shift Supervisor Checklist 6.2 Additional Conditions Requiring Emergency Classification
'6.3 Plan: Status Report 6.4 NRC Event Notification Information.
l 6.5 Kaman System Information Retrieval 6.6 Radiological Status Approved by. 2 Date:
/Af M /8; /946
~'
Emergency P1 ngCoordgtor Approved by: kl7Ao-1 Date: 9 - 2 ,2 - 9 3 Operatlog5upervisor e Reviewed by: kb M4s ALArta t.coroinator Q Date: 7 -/ 9 9.3 l Reviewed by: bb~O Operations Co~mm1tt/e Cnairman Date: Pb i fkT Approved by: M der Date: Y!/! PlantSupfrintencep-auclear .
D A EMERGENCY PLAN IMPLEMENTING PROCIDURE EPIP 2.5 - .. . Page o 29 15 CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83 ATTACHMENT l-OPERATIONS SHIFT SUPERVISOR CHECKLIST The following checklist .is available for use by the Operations Shift Supervisor and the Control Room Coordinator or an individual, so designated, as an aid in ensuring that emergency response actions are completed. In the colunin labeled " Time", the actual time that such items are' completed may be recorded. Alternatively, cnecks may be used or other appropriate notations may be substituted which will be of assistance to the user. TIME- ITEM
- 1. Determine emergency classification and/or report requirements.
a) Evaluate plant conditions and classify as an emergency using the guidance in EPIP 1.1, if warranted. QZC. b) Determine if prompt notification of NRC is required as specified in EPIP 1.2.
- 2. If not classified as an emergency, but prompt notification is required, initiate notification.
! If classified as an emergency, continue on with the following items.
- 3. If classified as an emergency:
a) If an ALERT, initiate plant evacuation as prescribed in EPIP 1.3.
*b) If during non-normal working hours, an abnormal radiological release is -in progress, perTorm dose projection as prescribed in EPIP 3.3a or EPIP 3.3b.
*c) Determine protective action recommendations as prescribed in EPIP 3.3a during non-normal working hours based upon:
- 1) Total projected exposures (release in progress) 2)Potentialforsignificantrelease(elevatedradiationlevels inside containment plus hign containment pressure).
- During normal working hours, b) & c) to be performed by the Site Radiation
-Protection Coordinator.
v --- ~ g 4 - - < - - - - e-,m-v v m ,w- , v
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP- 2.5 Page 16 aof 29 - : CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83 ATTACHMENT 1 (Continued) ' OPERATIONS 5HIFT SUPERVISOR CHECKLIST TIME ITEM
- d) Obtain Initial Notification Message form and fill in the required information, as prescribed in EPIP 'l.2. .
e) Conduct required notifications of off-site agencies from the Control Room f) Provide infcrmation to the Emergency Coordinator if notification is to be accomplished from TSC.
- 4. If during non-normal working hours the event has been classified as an ALERT or greater, obtain the Emergency Response Organization Notification Message form, fill in required information and provide to Security as prescribed in EPIP 1.2.
- 5. Insure that NRC notification is conducted, and -infonnation provided as described in Attachment 4, within 1 hour of the event and, if
~
classified as an ALERT or greater, that an open continuous communications path to'NRC is established and maintained (prefersoly via the ENS). If classified as an ALERT or greater, continue on with the following items.
- 6. ' Verify that the following additional energency response positions are manned ~in the Control Room:
a) Control Room Coordinator b) TSC Communicator c)BackPaneldommunicator d) ENS Communicator
- e) VAX Terminal Operator
- f) Plant Status Data Recorder *
- 7. Take action, as reauired, to obtain additional operators. ,
- 8. Conduct accoutability check as prescribed in EPIP 1.3. i
- To be selected frcm available personnel or called out, as required. ,
1 g _ ,, , 4 -wr w m_ , , . .,c, y 9%g ,,w, ,r ,y- g- g 7m-vg y-9,._m %9-,, y y-. , ,
- y, y- , - - -- -----3
a a EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.5 Page ' o~f 29 7 CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83
-ATTACHMENT 1 (Continued)
OPERATIONS SHIFT SUPERVISOR CHECKLIST TIME ITEM
- 9. Verify that access contr01 has been established..
- 10. Review initial plant status information to be entered on VAX for subsequent transmittal to TSC & EOF.
- 11. Verify that initial radiological status has been recorded and that Back Panel Communicator is in communiction with the Site Radiation Protection Coordinator.
- 12. Initiate trending of key parameters; such as, a) Nuclear Instrumentation (if not shutdown) b) Reactor vessel water level c) Reactor pressure d) Dyrwell/ Torus pressure e) Orywell Temperature f) Torus water level g) Torus water tenperature.
h) ARM levels
- 1) Drywell/ Torus High Range Radiation Monitor Levels j) Effluent release concentrations
- 13. Determine additional parameters to be trended, if not listed above, and initiate trending.
The following items are those of an ongoing nature; hence, may be accomplished more than once by the Operationsn 5'ift Supervisor or Control Room Coordinator.
- 14. Recomrend event reclassification based upon a) Plant status b) Projected trends c) System / equipment operating limitations m
EMERGENCY PLAN IMPLEMENTING PROCEDURE- EPIP '2.5 - Page 18 43f 29 ?- CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83 3i. ATTACHMENT 1 (Continued) OPERATIONS SHIFT 5UPERVISOR CHECKLIST TIME ITEM
- 15. If the event is reclassified to an ALERT or greater, review and insure all prior items are performed, or reconduct, as appropriate.
-16. Provide information to the TSC Supervisor-regarding:
. a) Changes in plant status and key parameters b) Problems which are discovered
~
c) Information regarding parameter trends
- 17. Provide input to-the Technie:al and Engineering Supervisor regarding:
a) Planned operational evolutions b) Operational response actions c) Corrective action options to resolve problems identified
- 18. Insure that NRC is kept informed of plant status, problems and response actions being taken or planned.
4-
- 19. Verify that procecural and Technical Specification requirements are being followed, or if not possible:
a) Temporary procedure changes or temperary. procedures should be developed for those situations not addressed in existing procedures, , or Provide direction 1to Operations personnel, as required, and inform the b) TSC Supervisor of response actions taken in violation of procedural requirements. c) Provide direction to and approval of, response actions taken which depart from license or Tech. Spec. requirements where action is immediately required to protect the public health and safety and inform both-tne TSC Supervisor and the NRC of actions taken. d)_ Identify Technical Specification changes which may be desired to the TSC Supervisor. I
- 20. Coordinate with the TSC Supervisor for dispatch of operators. ,
l T
a - EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP- 2.5 Page 19 of 29
~ ^ . ' CONTROL ROOM EMERGENCY RESPONSE 0?ERATION Revision 0 Date 7/1/83 ATTACHMENT 1 (Continued)
OPERATION 5 5HIFT SUPERVISOR CHECKLIST .1 TIME
- ITEM
- 21. Verify that.the Site Radiation Protection Coordinator is advised of
- status changes and radiological- trends, particularly when personnel have been dispatched into actual or potential radiological hazard area
- 22. Make provisions for continuous Operations Shift coverage and coordinat with the Security and Support Supervisor.
. 23. Evaluate means to be used to restore the plant to a safe condition in light of minimizing the subsequent radiological hazard ared and review with the TSC Supervisor.
- 24. Evaluto as specified plantinstatus,5.1 EPIP and recommend deactivation to the TSCparameters and Supervisor COMMENTS:
l
/
Operations Snift Supervisor Time /Date Contr)1 Room Coordinator- Time Date e - . . - - ,,-g ..-,-r,4y , - . - - , *.y...v-- .. r, --,- vv-.-,5 ,
EMERGEdCY PLAN IMPLEMENTING PROCEDURE EPIP 2.5 Page 20 of 29
. s .
~
CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83-ATTACHMENT 2 ADDITIONAL CONDITIONS REQUIRING EMERGENCY CLASSIFICATION a) Abnormal gaseous and liquid effluent release rates.
- b) Unexpected or uncontrolled releases of radioactivity within the pl ant.
c) Abnormal Reactor Coolant System radiciodine concentrations. d) Fire Suppression System malfunctions, e) Natural occurrences including earthquakes, floods, river water flow, and tornados. f) Man-caused hazards such as aircraft activity or crashes on site, explosions and releases of toxic or flammable gases. g) Situations wnich may require off-site support organization
' assistance such as medical emergencies, security contingencies and fires on site.
4 e
a > l EMERGENCY PLAN' IMPLEMENTING PROCEDURE EPIP 2.S Page 21 of 29 - CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83 ATTACHMENT 3 _ PLANT STATUS REPORT EMERGENCY CLASSIFICATION: REPORT TIME: EVENT CODE: EVENT CODE DECLARATION TIME: REPORT DATE: REACTIVITY CONTROL All Rods In (Y/N): SBLC System (Operable / Actuated): SRM's Operable (Y/N): REACTOR VESSEL WATER LEVEL Normal range (Y/N): Increasing, Decreasing, or Stable (I/0/5): Indicated Level In Inches: ECCS STATUS HPCI Operable, Inservice, or Bad (0/I/B): RCIC Operable, Inservice, or Bad (0/I/B): ADS Operable, Actuated, or Bad (0/A/P): LPCI Operable, Inservice, or Bad (0/1/B): Core Spray Operable, Inservice, or Bad (0/I/B): REACTOR VESSEL DEPRESSURIZATION/C00LDOWN Reactor Pressure (PSIG): Isolated (Y/N): Cooldown in Progress (Y/N): Cocidown Rate (Deg F/HR): PRIMARY CONTAINMENT Isolated (Y/N): Drywell Pressure (PSIG): Drywell Temperature (Oeg F): Drywell Ventilation Off or In Service (0/I): Containnent Spray Operable, In Service, or Bad (0/I/B): Torus Water Level Normal, High, or Low (N/H/L): Torus Water Temp (Deg F): . l Torus Water Recire (Y/N): SECONDARY CONTAINMENT Isolated (Y/N): SBGT System Operable, Inservice, or Bad (0/I/B): ELECTRICAL POWER Offsite Power Unavailable /In Service (U/I): Diesel Generator #1 Operable /In Service / Bad (0/I/B): Diesel Generator #2 Operable /In Service / Bad (0/1/B): REACTOR COOLANT CHEMISTRY SA.iPLE TIME: Gross Activity Micro C/ml Total Ioaine Micro C/ml Micro C/mi I 131 -
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.5 Page 22 of 29 CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83 ATTIG E NT 4 EvFiii i(;i te ALATIQi , TIE G TOTIFICATICN: EVENT TIE NO ZOE: tPC REGICN: CATE: / / ET Ct4J. EAX PUEER: M OT ; FACILITY m GG441ZATION: Cf4.LER'S t@E: EVENT CLASSIFICATI0VRE0VIRED TOTIFICATICNS
- 1. AERT RDO 6. TPR6PCRTATICN EER RID SITE /REA EMERGE!CY E0 w QZ EtS/4. DERGEtCY tRR wi
.nLi dIU. tWE MJ. OTHER t0TIFitnituo
- 7. 50.72 (tCN-EMEREtCY) RDO
- 2. PHYSICf4. SECLRITY/SWECURG RDO w IAT
- 8. LIFLWS RELEASE RDO (C0 & IAT f0T REQUIRED Fm SQt EEYfS)
F.0 FE% wt rHS
- 3. t0TIFICATIOi 7 (NUSUAL EW.NT RDO EPA T FEMA
- 4. OTHERt0TIFICATIONS: ED(DAYS):
- 5. CG+11SSIONERS/ASSISTRUS BRIEFED, LSE FEM Qi it:. VERSE ERIEFItG TIME:
2CM R REFCTm EVENT: RESDE?E ItFGED: ; PCWER PRIM 10 EVENT 7 PO4R AT TIME 7 PIKRT? 1 TRIP? itilTIATItG SIGR7 SifETY itkzGTIW G F.CC52 I?tiilATiiai SIGW.? F5 /CTmTIOR LCO /CTION aTAlcmit t j EVENT MIPTION/CT4JSE: .
- nevixitic nu .rocat Miirr ):
OTrER .%IR fRTLc.MS? R1#ED /CTIQ6/PPISS RELEASESh I CUTSIT /GCY m PERSONEL TOTIFIED BY LICENSEE:l STATE (S) LIA urr.cx W $r AL,ch; PtiASE C;t! 2;C< '41Tri /44Y CHt4GES m ;CDITIOR ItFJyATICI i I l II I I II
--s-y w r ----n- .y a-_9g-. --.w-,,...,,y ,g,.yyy-,-
_.,.mpw,_,.., y---+-- w
,,,7gw,,p, 9, ww,pw,,,%%,q e,_,,___ -iww_e,._,,w,,- ,-q w--.- ~
e > EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.5 Page 23 .of 29 ,, CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83 ATTACHMENT 5 ( KAMAN SYSTEM INFORMATION RETRIEVAL
. 1. OBTAINING RELEASE RATE AND PROCESS FLOW INFORMATION Radiological and process flow information needed to complete. dose projections is release rate in uCi/cc and process flow rate in efm. This data from the Kaman System can be obtained using the database display for the sanple skids (normal or accident range) and appropriate gaseous detector (normal, intermediate, or high range).
On the database display, the cfm process flow is labeled as AVG P-FLOW and the release rate to be used is labeled 1-MIN AVG and is. listed as uCi/cc. An example of a typical display has been provided as Figure 1 to this attachment. For the release information, enter on the Kanan keyboard the necessary command for the gaseous channel in use, as follows. When entering commands, use the space bar between the number corresponding to the Skid (Number 1 through 10) and the number corresponding to the Detector (Number 1 or 2). For the Turbine Building Vent enter 2 1 Database (key) Normhl range skid, normal detector or 1 1 Dat abase Accident range skid, intermediate detector or i 1 2 Dat abase Accident range skid, high detector l For Reactor Building A Vent enter 4 1 Database (key) This is the normal range skid, normal range detector. or l l 3 1 Database Accident range skid, intermediate detector of l- 3 2 Dat abase Accident range skid, high actector l w '
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.5 ; Page 24 of 29 , l CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83 ATTACHMENT 5 (Continued) )
~
KAMkN SYSTEM INFORMATION RETRIEVAL For Reactor Building B Vent enter 6 1 Database (key) Normal range skid, normal detector or 5 1 Database Accident range skid, intermediate detector or l 5 2 Database Accident range skid, high detector l For Reactor Building C Vent enter 8 1 Database (key) Normal range skid, normal detector or 7 1 Database Accident range skid, intermediate detector of 7 2 Database Accident range skid, high detector For Offgas Stack enter 10 1 Database (key) Normal range skid, normal range detector or 9 1 Database Accident range skid, intermediate detectcr or 9 2 Database Accident range skid, high detector Note that the even number skids are designed for monitoring in the normal range, whereas, the odd number skids are designed to monitor high level releases. L
. +
j EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.5 Page 25 .o.f 29 ,. 1 CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83 ATTACHMENT 5 (Continued) . KAMAN SYSTEM INFORMATION RETRIEVAL In recording release concentration-(uCi/cc) information on Attachment 5,
-" Radiological -Status" selet the skid and detector which provides data nearest the mid-range of the detector, if at all possible.
- 2. OBTAINING TRENDING INFORMATION Occasionally, it is importnat to know if effluent concentrations are trending up or down. This can be accomplished by calling up a radiation level trend display
' for the appropriate skid, detector, and time desired. The last 30 one-minute, ten-minute, one hour or one day averages can be displayed as desired. The command for these displays is as follows: (See Figure 2 and 3 for examples.)
Monitor # Channel # Trend Desired (1-10) (1 or 2) M (for 1 min.) Rad or Level T (for 10 min.) Trend or Key H (for 1 hour) or D (for 1 day) Ex amples: 4 1 H Rad Level The first two nunbers (41) designates the Reactor Trend Key Building Stack A Normal Range Skid and detector. H instructs the mini-computer that hourly average radiation level information is desired. The Rad Level Trend Key results in the display _ of hourly averages for each of the last 30 hours. 9 2 M Rad Level The first two numbers (9 2) designates the Offgas Trend Key Stack High Range skid and detector. The M instructs the mini-computer that one minute averages of the radiation level information is desired. The Rad Level Trend Key results in the display of one minute averages for each of the last 30 minutes.
l e s 1 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.5 i Page 26 of 29 .. CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83 ATTACHMENT 5 (Continued) KAMAN SYSTEM INFORMATION RETRIEVAL
;* .As.g2 ;, wt tg . av. % - narnese,sa o s wa, 8C. LI l
* *&t6 46 v &ta r s &
, N6ee-sc & s/ s 44 ,*t: . Anf i I
N CURR J -a t *8 AVG s 1 -*4 R AVG s * ^ = ' u 'i
' 43 (PU) s (CPM) a < ar. . -- 19-v1. 4, .ww a 7=
TTx -.n- 1-C f avg s _ila>==:n j j avg p-rLOW s "".T"f"IE'T1 *NT 3-%CW s N if'Tff2!!"fCMI MIGH LIVCt. a ,H!cH PeC3 s MIGH *TMP s t vum:w abr37 LIVC1. a '. 0 W PerJ s :-: Low TE.M P a h ; === . 2 Rait INCR .s LCW ft.Qu a
%.rm e d. a ReO LEVEL *N SAMP FLOW s M PROC FL*w aN
'L".'*MITEN'M PVRGE SURATION (SCO)
- M AUT0=TE.37 PCR!CD (HCURS) sM l MERE!*E CXPCC E3 aM RC3PONSE aM PCRO (NIN) sM
*I!i s ti n u m " : 53R5===
;- . -m g LAE* CHCCK s LEVEL z .
Z " L. J 6-JT .LAAM s th a w LEV C1. a --- ?YPC *. 6 6 M - acrissarrath - 94Ja ve6 a no suA Esy;a a rec ;te 4 c 44,. .90gg a no 7% A.JEs d as a r -w Ja a ces
.bgMT LVL s NC CHW JOURCE a NO ALARMS QFT a NO CHCCX 70 VACC GN S we maft *NCR z NO MIGH VLf3 s NO PunPS CN s@
w!GH PRCJ s NQ LOW VL77 s NO 4970-7Z37 QN 2 roe L;w 89CJ s NO OC7%C7CR 3 NQ gICH ?I!1P s NO ACTIVC MCCC aG
.3W ?C?'P W NO t.J W FL3d 5 NO Cz Sar a NO
#40 UN!?fauCZ/CC Ra?g INCRsay/TCC CrtnerJ/ cpm PAAAMCTER UN!?S Crr=rt. uina renP=CtatC> Pntszes! r ouscrn 14:41 ma
.ie 1
l Figure 1, " Typical Data Base Display" _ , _ . . . . , , _ , - . , _ . - - y- - y -- , ,m ,-
- *.i ,f ~ -
__ - - - * ,-, -_.,.r y w e,_._e_, , - , - . - - -
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.5 Page 27 of 29 .- CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/S3 ATTACHMENT 5 (Continued) . KAMAN SYSTEM INFORMATION RETRIEVAL
;;..as.g3 g w i w;, -32 .o+%- -.eesarms .- e_ v.w r_. - r eee se. n zmar wit?sw.)*C-of w ; ;,, a3.*4C-4*
t- 94 t-95 C-44 C-40 t-4? q44 u . 1
.3 r-4* 1 i 2.DeC-47
* .34E-47 3
- 3. Pm C*47 '
- 2.44E-47:5
- 319*C-47 4
.tEC-47 7
- 4.ISC-47 1
- 3.44C-47 9 3.64C-47 10 .
2.71r-17 11
*.4GE=47 1"
*.205-47 iT 3.30E-47 1*
3.33C-4* 1h
*.43C-47 th .
4.21E-47 17
*.03C-47 th 6.*1C=47 11 4.3Cf=4* 00 3.**E-4* *:
*.F)C=47 *.*
3.JfE-47
*.2:E-47 0%
3.I?C-47 ~K
*. *4 C-4 7 *h
*.43C-47 07 3.2:E-47 0?
- 3. 2 5 e:-47 *.?
*.7TE-47 30 Outsr a n O . ,-. ~ a
,,--.,-...,..,,,o_,.,,.....a... - n w, a;m.i.4 _ , , . _
Aa v&nt a non- t r. e sw-nan a.was-s7 j - Asas t*v*t 3E==M . l [ Figure 2, " Example Normal Range Reactor Building Stack A Radiation Level i Hour Average Trend
- , ~ - . - - ~ - - - - , -. v,-,-- wy , -.--- ,- ..-,-m .-,..-.,,-,,---,,.--.~------,-r,--,,q-
,---,.m-< n- e n
,, , 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE EPI? 2.5 Page 28 of 29 CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/82 ATTACHMENT 5 (Continued)
KAMAN SYSTEM INFORMATION RETRIEVAL
..rp?=*.>=C-4r
- '.se-e3 1 *::*s MIGM a3.*4C-4*
e C-4* C-46 C-4 5 C-4* C-43
@6a e.. .
2.34C=4? 1 2.45E-4* 0
*.*3E=47 3
, 5.12Z-47 *
*.43C-47[S 6.14C-4*i4 4.30E=47' ?
- 3.772-47 'S
*.1*E-47 1 3.5:E=4? 1C
- 1
- C =4 7 11 4.*3C-47 1'
- 21 E*47 12
*. 9 2 t*47 th *.471-47 15
- f. 9 9C*4 7 it 4.54C-47 1:'
3.fft-47 11
- 13Z-47 1S -
1:2iiS
*.92E-47 *c- *.72C-47 *. *.3*Z=47 * .
- 3.Est=47 *T
*.99C-47 08
^4. 4 9t==l ? ~7
+.11 E-4 7 *2
.OtZ-47 *.3
*.11 E-4 7 2C
!.;C37
& M i=. rv -
r _-- : n . . > : r= w e i s , . . , . .r- y , . . ,_ __i; . sM's v .-- w s r -s uWW
-.=m- -'
m.i..... -= arhu m m ma.4 w. nr
- A6&e As VENT & tsQn=&& & 44 & =n a te a.4al.-w?
14:42 M Figure 3, " Example High Range Offgas Stack Radiation Level 1 Minute Average Trend
=
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.5 Page 29 _o,f 29 , , CONTROL ROOM EMERGENCY RESPONSE OPERATION Revision 0 Date 7/1/83 ATTACHMENT 6 ( RADIOLOGICAL STATUS RELEASE POINT PROCESS FLOW INFORMATION Release Effluent Monitor Occurring Readings- Average YES NO N I H Process . Off-Gas Stack Flow Turbine Bldg. Vent'l Exh. Reactor Bldg. Vent'l Exh. b b uCi/cc. b b b cfm b b uCi/cc b b b cfm b ON OFF uCi/cc IN0P cfm STANDBY TREATMENT SYSTEM STATUS A TRAIN B TRAIN METEOROLOGICAL DATA 35 ft. 165 ft. ,, Wina speea AT e Wind Direction (from) degrees degrees AREA RADIATION MONITOR LEVELS (all in mr/hr) RT 9168 RT 9171 RT 9158 RT 9170- RT 9175 RT 9174 RT 9167 RT 9163 RT 9179 RT 9169 RT 9164 RT 9151 RT 9176 RT 9153 RT 9152 RT 9177 RT 9178 RT 9154 RT 9173 RT 9180 RT 9162 i RT 9157 RT 9166 RT 9172 l ! RT 915G RT 9159 RT 9161 ! RT 9155 RT 9160 RT 9165 The physical location of each ARM is identifiea in an Attchment to EPIP 4.3 Containment High Range Radiation Monitors Drywell Monitor #1 R/hr Torus Monitor #1 R/hr
#2 R/hr #2 R/hr l
l Uaa..en c 2 I' Recorded By Time /Date / y y -rw----,ww g-,v.,v,w- - -ep- , v.---r- -w,g,y--,r---++-y-,w-,------,,yvn,,,,,,pvr-+yw,---
EMERGENCY PLAN IMP'.EMENTING PROCEDURE EPIP 2.6 Page 1 of 15 ACTIVATION'AND OPERATION OF THE DAEC OFF-SITE Revision 0 RADIOLOGICAL AND ANALYTICAL LABORATORY (ORAL) Date 7/25/83 1.0 PURPOSE
~
This procedure provides instructions for the activation and operation of the Off-Site Radiological .and Analytical Laboratory (ORAL) located at 1017 12th Avenue . S.W. in Cedar Rapids. The ORAL is intended.to be utilized to radiologically analyze air filters and iodine cartridges, and environmental type ' samples (e.g. water, and soil) .in the event of an emergency at 0AEC. 2.0 . APPLICABILITY 2.1 This procedure shall be implemented upon declaration of an event classified as a SITE or GENERAL EMERGENCY or for other events which result in the need
- to analyze samples in the ORAL.
2.2 This procedure applies to members of the Radiation Protection Department, including Chemistry Technicians and selected members of the Department Management. 3;0 RESPONSIBILITIES 3.1 Site Radiation Protection Coordinctor 3.1.1 Determine the potential need for processing samples at the ORAL. 3.1.2 Recommend activation of the ORAL to the Emergency Coordinator. 3.2 Emergency Coordinator 3.2.1 Authorize activation of the ORAL. 3.3 ORAL /0DEF Sucervisor i 3.3.1 Verify that actions required to pnysically place the ORAL into
- t operation are accomplished.
3.3.2 Coordinate and supervise support activities provided by personnel at the ORAL. 3.4 Radiological Assessment Coordinator 3.4.1 After the EOF has been activated and the ORAL has been made operational, and after the RAC has assumed responsibility for the off-site Monitoring Teams, the RAC will then also have responsiblity for the ORAL. c -
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.6 Page 2 of 15 Revision 0 ' ': ACTIVATION AND OPERATION OF THE DAEC OFF-SITE RADIOLOGICAL AND ANALYTICAL LABORATORY (ORAL) Date 7/25/83
'4.0 INSTRUCTIONS 4.1- LActivation of the ORAL 4.1.1 Notification of ORAL Personr.el (a) The Site Radiation Protection Coordinator ~ upon determining the potential need for processing sampTes at the ORAL should take the following actions:
(1) Recommend activation of the ORAL to the Emergency Coordinator. e NOTE THE ORAL SHOULD BE ACTIVATED FOR A SITE OR GENERAL EMERGENCY, 3UT MAY BE ACTIVATED FOR EVENTS OF LOWER CLASSIFICATION, AT THE DISCRETION OF THE EMERGENCY COORDINATOR. (2)_ Subsequent to receiving authorization from the Emergency-Coordinator, contact the ORAL /0DEF Supervisor and advise him of the impending activation cf the ORAL. NOTE
> ACTIVATION ACTIVITIES REQUIRED TO SET UP THE ORAL SHOULD BE ACCOMPLISHED PRIOR TO THE NEED TO ACTUALLY PROCESS SAMPLES IN THE ORAL.
(3) Request the ORAL /0DEF Supervisor to. contact the OSC Supervisor to staff the ORAL. (Normally, -two Chemistry technicians will be required.) 4.1.2' Personnel Access to ORAL (a) The ORAL is located on the second floor of the IE Systems Protection Warehouse located at 1017 12th Avenue S.W. (See Attachment 6.1, " Travel Routes to the ORAL and 0]IF) . (b) Entry .to the ORAL should only be made frem the exterior entryway on the 12th Avenue side of the building. NOTE THE KEYS FOR THE ORAL AND ODEF ARE MAINTAIHED AT THE SECURITY CONTROL' POINT (SCP) AND IN THE RADIATION PROTECTION GROUP. (c) All persoanel delivering samples to the ORAL should deliver samples to the Sample Receipt. and Preparation Laboratory. (See Attachment 6.2, " Floor Plant of' the ORAL /0DEF). i.d). Personnel should not take any samples directly into the Counting Room. -
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.6 Page 3 ,of 1S ,
- ACTIVATION AND OPERATION OF THE DAEC 0FF-SITE Revision 0 RADIOLOGICAL AND ANALYTICAL LABORATORY (ORAL) Date 7/25/83 4.1.3 ORAL Ooerational Arranaements (a) The ORAL /0DEF Supervisor will make necessary arrangements to have all laboratory radiation detector systems made operational as soon as possible after activation of the ORAL.
(b) Existing commercial telephone cannunications between the ORAL and DAEC and EOF will be checked. NOTE THE USE OF PORTABLE RADIO COMMUNICATIONS (E.G., WALXIE TALXIES)
- WILL NOT BE PERMITTED FRCM WITHIN THE ORAL SINCE SUCH RADIOWAVE FREQUENCIES WILL INTERFERE WITH THE PROPER OPERATICM OF THE RADIATION DETECTION SYSTEMS.
(c) The ORAL Chemistry j Technicians will verify the operability of all portable raciation survey meters in use at the ORAL. (d) The ORAL Chemistry Technician will prepare a " Contaminated Area" step-off pad -in the doorways between the Sample Receipt and Preparation Laboratory and the Counting Room and the hallway leading into the facility. 4.1.4 Notification of ORAL Ooerability 4.1.4.1 The ORAL /0DEF Supervisor should notify the Site Radiation Protection Coordinator at the DAEC and the Radiological Assessment Coordinator at the ECF when the ORAL is staffed and the laboratory and radiation detection systems are operational. 4.2 ORAL Operational Procedures , 4.2.1 Receipt of Samples from DAEC (a) In accordance with EPIP 3.2, "Off-Site Radiological Monitoring", personnel collecting samples are responsible for assuring that each sample is packaged in a plastic bag and sealed to prevent potential spread of radioactive contamination. l l l l l
=
l I l _ ,, _ , , _
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.6 Page 4 of 15
.- ACTIVATION AND OPERATION OF THE DAEC OFF-SITE Revision O
~ RADIOLOGICAL AND ANALYTICAL !.ABORATORY (ORAL) Date 7/25/83 (b)' Also, in accordance with EPIP 3.2, personnel collecting samples are responsible for properly identifying each sample; to include the following -information:
- 1) sample description
- 2) sample-collection loca, tion i
- 3) date of sampling
- 4) time of sampling
- 5)- name of individual collecting sample
- 6) gamma radiation level at contact with sample container.
(c) All samples shall be delivered directly to the Sample Receipt and Preparation Laboratory of the ORAL. 4.3 Samole Preparation 4.3.1 The following actions should be taken by the ORAL Chemistry Technici an: (a) All sample identification information should be recorded on Attachment 6.3, "0RAL Sample Log Fonn", and the DATA ID number marked on the sample's plastic bag. (b) All sample-preparation or aliquoting for counting should be completed in.the chemical fume hood. (c) Each sample prepared for counting should be repackaged in a *
" clean" plastic bag. Care must be taken to mark the sanple's DATA'ID number on the new plastic bag.
4.3.2 As necessary, the chemical preparation of a sample will be canpleted using standard chemistry procedures as described in the-DAEC Plant Chemistry Procedures.
e EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.6 P age 5 of 15 , ACTIVATION AND OPERATION OF THE DAEC' 0FF-SITE Revision 0 RADIOLOGICAL AND ANALYTICAL LABORATORY (ORAL) Date 7/25/83 4.3.3 All samples prepared for counting should tenoorarily be stored in the shielded storage cabinet located in thg Sample Receipt and Preparation Laboratory. Samples prepared for counting should not be stored in the Counting Room. 4.4 Sample Analysis 4.4.1 The ORAL Chemistry Technician should c'mplete o sample analysts as described in the following instructions: (a) P.A.S.A.P. 8.7, " Gamma Analysis of Air Sampling Media and Swipe Samples Using the Canberra HPGe Detector Systen." (b) P.A.S. A.P. 8.8, " Gamma Analysis of Liquids Using the Canberra HPGe Detector Systen". (c) P.A.S.A.P. 8.9, " Gamma Analysis of Bulk Samples Using the Canberra HPGe Detector Systen." (d) P.A.S.A.P. 8.10, " Alpha / Beta Analysis of Air Filters and Swipe Samples Using the Tennelec LB 1000 Detector System." (e) P.A.S.A.P. 8.3, " Operating Instructions for the Emergency Radioiodine Counting Systen". 4.4.2 Sample preparation should be completed in accordance with standard chenical procedures as described in the DAEC Plant Chenistry Procedures (See Section 5.0, References) 4.4.3 If it is desirable to save a sample for any reason, such samples should be marked "SAVE", and should be placed inside the shielded storage cabinet located in the Sample Receipt and Preparation Laboratory. , l 4.4.4 After a sample has been counted and all results have been detennined to be satisf actory, the sample should De marked for
" DISPOSAL", and then the sample should inanediately be returned to the Sample Receipt and Preparation Laboratory for disposal.
Samples should not be stored or kept in the Counting Room. l Disposal of any sanple should not be canpleted unless authorizeo by the ORAL /0DEF Supervisor. l-4.4.5 After a solid sample (e.g., air filter, soil, swipe, iodine
-cartridge, vegetation, etc.) has been counted and satisfactory results have been obtained, the solid sample may be placed in the approved waste container located in the Sample Receipt and Preparation Laboratory for disposal'.
i
+,r*
9gwr , m - +-;-, m y- - , -, _ ,.9 ,. ,,,_.-,a_ .y s .--yy g-- -_ g y ,y-_,.--p , ,m, ,- 99 y.pg 9m,
- e EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.6 Page 6 of 15 ACTIVATION AND OPERATION OF THE DAEC 0FF-SITE Revision 0~~
l i RADIOLOGICAL AND ANALYTICAL-LABORATORY (ORAL) Date 7/25/83 4.4.6 All liquid samples may be disposed .of by pouring the liquid into the chemical fume hood drain which is connected directly to a hign integrity polyethylene storage bottle. Under no ci'rcumstances should any liquids be put into the solid waste container. NOTE WHEN THE 10 GALLON STORAGE BOTTLE BECOMES FULL, ITS CONTENTS MAY BE EMPTIED INTO THE LARGER 500 GALLON STORAGE TANK AS DISC'JSSED IN PARAGRAPH 4.6.4 BELCW. , 4.5 Documentation of Results_ 4.5.1 All counting data arti sample analysis results should be recorded on the Attachment 6.4, "Sampie Analysis Report Form" or on Attachment 6.5, "0RAL Alpha / Beta Report Form". In addition, the printout for each sample analysis should be kept on file in the ORAL. 4.5.2 All sample results will be verbally communicated to the Radiological Assessment Coordinator at the EOF, or as necessary, to the Site Radiation Protection Coordinator at the DAEC, as soon as possible. 4.6 Liquid Waste Transfer 4.6.1 Liquid radioactive waste will be generated as liquid samples or from the preparation of samples for counting in the ORAL. Such radioactive liquid waste should be discarded only in the chemical fume hood drain. This drain is connected directly to a 10 gallon nigh-integrity polethylene storage bottle located directly underneath the fume hood. 4.6.2 Radioactive liquid wastes should not be disposed of in the sink or
- toilet located in the restroom outside of the ORAL.
4.6.3 As necessitated by the volume of emergency operations involving - liquid samples, the ORAL Chemistry Technicians will monitor and record the liquid wa:te levels in both ten (10) gallon storage tanks; i.e.,: (a) The 10 gallon bottle fcr the laboratory sink, (b) The 10 gallon bottle for the chemical fume hood, 4.6.4 As the smaller 10 gallon storage bottles become full, the radioactive liquid may either be: (a) Transferred directly into the larger 500 gallon storage tank; or, (b) Properly packaged as required by DAEC Rad Waste for transport to DAEC for ultimate processing and disposal.
1
. l EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.6 l Page 7 of 15
- ACTIVATION AND OPERATION OF THE DAEC 0FF-SITE Revision 0 RADIOLOGICAL AND ANALYTICAL LABORATORY (0RAL) Date 7/25/83 4.7 Licuid Waste Storage and Discharge 4.7.1 As the 5b0 gallon storage tank becomes full, sampling and analysis of the contents will be completed in accordance with P.A.S.A.P.
8.11, " Radioactive Waste Control and Disposal from the DAEC Off-Site Radiological and Analytical Laboratory (ORAL) and the Off-Site Decontamination Facility (0DEF)". .
- NOTE RADI0 ACTIVE LIQUID WASTES SHOULD NOT BE DISCHARGED INTO THE CEDAR RAPIDS SANITARY SEWAGE SYSTEM UNLESS WRITTEN AUTHORIZATION HAS BEEN
- GRANTED BY THE SITE RADIATION PROTECTION C00RDINATCR OR THE DAEC RADIATION PROTECTION SUPERVISOR.
4.8 Solid Waste Packaging and Discosal 4.8.1 Solid radioactive waste will be packaged and disposed of as detailed in P.A.S.A.P. 8.11, " Radioactive Waste Control and Disposal from the DAEC Off-Site Radiological and Analytical Laboratory (0RAL) and the Off-Site Decontamination Facility (00EF)".
- 4. 8.'2 Unless otherwise specified by DAEC Rad Waste, all solid radioactive waste will be packaged in approved DOT specification containers (e.g., 55-gallon steel drum).
4.8.3 When a waste container becomes full, it will be inspected to ensure that there are no liquids and then it will be properly sealed. 4.8.4 A radiation survey will be completed, and the contact and 3 foot from container radiation levels should be recorded on a label and affixed to the container, as required. , 4.8.5 A loose contamination swipe of the container should be completed, and counted for both alpha and beta / gamma radiation. All swipe results should be recorded on Attachment 6.5, "0RAL Alpha / Beta Report Fonn". I 4.S.6 The waste container may then be moved out of the Samole Receipt and { Preparation Laboratory via the warehouse freignt elevator and temporarily stored in the designated area in the basement of the facility. 4.8.7 The storage area wil'1 be designated as a temporary " Radioactive Materials Storage Area" and properly posted, as required in 10CFR Part 20. t -w , v.- -
,, ,p m,, -
,y--- -+- e--- ,--w.ww .
.wrr w.
. a EMERGENCY PLAN IMPLEMENTING PROCEDURE-EPIP 2.6 Page 8 of 15 Revision O ':
ACTIVATION AND GPERATION OF THE DAEC OFF-SITE RADIOLOGICAL AND ANALYTICAL LABORATORY (ORAL) . Date 7/25/83 NOTE THIS TEMPORARY STORAGE AREA SHOULD BE ESTABLISHED IN CLOSE' PROXIMITY TO THE ODEF 500 GALLON STORAGE TANK. 4.8.8 DAEC Rad Waste will be requested to have.the waste containers properly labeled, and then picked up for transport back to DAEC for ultimate disposal.
~
4.9 - Radiological Monitoring of the 0RAL 4.9.1 Radiological surveys for both radiation levels and for loose e contamination (i.e., both alpha and beta / gamma radiation) should be conducted at the direction of the ORAL /0DEF Supervisor, as necessary, in the Sample Receipt and Preparation Laboratory, and in the Counting Room of the ORAL. 4.9.2 During the emergency operation of the ORAL, such radiological surveys should be completed at least once a day. 4.9.3 All radiological survey results should be recorded, and kept on file in the ORAL. 4.10 Deactivation of the ORAL 4.10.1 Deactivation Resoonsibility a) The ORAL /0DEF Supervisor will deactivate the ORAL upon authorization of both the Site Radiation Protection Coordinator at the DAEC and the Radiological Assessment Coordinator in the EOF. b) The ORAL Chemistry Technicians will then proceed to adjust the
- radiation detection systems to their routine status. (See P.A.S.A.P. 8.12, " Routine Maintenance of the OAEC Off-Site Radiological and Analytical Laboratory").
c) Prior to shutting down any detector system, a " background" count should be taken to monitor for any potential detector contamination. 4.10.2 Resucoly of the ORAL-a) The ORAL /00EF Supervisor will be responsible for assuring the completion of the resupply of the ORAL, as necessary. (1) Chemical and laboratory supplies must be reinventoried and restocked, as necessary. m _._______________.a
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.6 Page 9 of 15 , , ACTIVATION AND OPERATION OF THE DAEC OFF-SITE Revision 0 RADIOLOGICAL AND ANALYTICAL LABORATORY (0RAL) Date 7/25/83 (2) P-10 Counting Gas for the Tennelec L31000 Detector System must be inventoried. At least one. extra full tank should be available. (3) Liquid Nitrogen (LN2) for the Canberra HPGe Detector System must be inventoried and resupplied as necessary. (4) Miscellaneous supplies and forms must be reinventoried and restocked, as necessary. 4.10.3 Sunnary Report of ORAL Activities e a) The ORAL /00EF Suyrvisor will be responsible for preparing a ' summary report of ORAL activities conducted during the
-emergency activation period, b) This summary report should include a final report of all sample results as processed in the ORAL, including sample log forms and all reporting forms.
5.0 REFERENCES
5.1 Duane Arnold Energy Center Emergency Plan 5.2 PASAP 8.1, " Operating Instructions for the Canberra HPGe Detector System" 5.3 PASAP 8.2, " Operating Instructions for the Tennelec LB 1000 Alpna/ Beta Detector System" 5.4 PASAP 8.3, " Operating Instructions for the Emergency Radiciodine Counting System" 5.5 PASAP 8.11, " Radioactive Waste Control and Disposal from the OAEC Off-Site
- Radiological and Analytical Laboratory (ORAL) and the Off-Site Decontamination Facility (ODEF)"
5.6 RWH 10.0 " Dry Waste Segregation, Processing, and Handling". 5.7 PCP 3.0 " Guidelines for the Use of the Procedures for Chemical Reagent Preparations" 5.8 PCP 6.11 " Gross Water Activity" 5.9 PCP 8.1 " Gross Ganma Counting" 5.10 PCP.8.1 " Iodine Cartridge Counting" 5.11 PCP 8.4 " Preparation of Counting Standards" 5.12 PCP 9.1 " General Considerations for Counting Radioactive Samples and Recording Results"
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.6 Page 10 of 15 Revi sion 0- - ~: ACTIVATION AND OPERATION OF THE DAEC OFF-SITE RADIOLOGICAL AND ANALYTICAL LABORATORY (ORAL) Date 7/25/83 5.13 PCP 10.8 " Radioactive Liquid Release Analysis ana Documentation" 5.14 PCP 10.13 " Collection and Analysis of Effluent Monitor Particulate Filters and Charcoal Cartridges" 5.15 RPP 7.1 " Radiation Surveys" 5.16 RPP 7.3 " Radioactive Contamination Surveys" 5.17 RPP 10.1 " Transportation of Radioactive Materials Off-Site" 5.18 RPP 10.2 " Receipt of Radioactive Material" e 6.0 ATTACHMENTS 6.1 Travel Routes to the ORAL and 00EF 6.2 Floor Plan of the ORAL /00EF 6.3 ORAL Sample Log Form 6.4 ORAL Sample Analysis Report Form 6.5 ORAL Alpha / Beta Report Form Approved by e Date 9 4 9.7 V /
-... gency F ning Cooro g r Approved by: 41d [ctub Date h- 73 -73 Cnemistry C rainaty Approved by: kJ1Ek hhprs4 Date VfA Radiatiorf Protepion Sugfirvisor Reviewed by: , #M Date 9!LS / <f 3 r
ALARAgoorci Q Reviewed by: i hw d Date S f /- @ Operations Committee Gnairman Approved by: Date 9'l9-$3 Plant Superintencent - Nuclear f l l
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP. 2.6 l Page 11 ,of 15 ,, , ACTIVATION AND OPERATION OF THE DAEC OFF-SITE Revision 0 RADIOLOGICAL AND ANALYTICAL LABORATORY (ORAL) Date 7/25/83 ATTACHMENT 6.1 TRAVEL ROUTES TO ORAL /00EF a
\
s, e , ECGEWOCD RD. (- ELUS BLVD 380
""E IE argsygE
\ ICM ,
- b. N IRD AVE 19TH sTR M CAEC 10 TH sTR rwe '
u EY - MT VERNON
, JOHNsCN AVE
[ '*y
/
[ 33, (eTs =cp uofesT\[* IS' ,Q ,
-sso sTa i2mvE , ,,
Syg 12THAVE [ g h - istw ave gi Asm 4&A
. . sin -eewuc sTa --
f WILsCN AVE /
/ A I
- so CRAL& CCEF j ENE'5/s".'7s'el 298 7666
_ - - - - - . - - . , - , - - - --m -,w -- - ,-u. w m--- __y- -
e i
- _ .. . .. g5 3 s :- m t GE M MAIN ELEC1RacAL PAIEL ICI Av 3w y Mgypogong 10WER $
D $10HAGE E p O D gg
~
M D -- - - T. 2 N fil wayEg > >. 3 COUNilNG 20004 3Assett RECEIPT a $m . - < , PREPARATION LAEL o - g g w. O M'I _ O O 2 N VAULT tettssa4 _
% ]
B
- EqM R
~ ' " ' " ~ ~ - ' 3
- a FlacE Hoop 2
\
o . -
- se *
= e HPGe DETECTCH p f g ]
ns a,uu.
. g g 3, N **" a =^ = = " "c= R #p
]! Pali,' -
71 v fit b
~
WAMHOUSE AfqEA e
, OFF-SITE RADIOLOGICAL 8 ANALYTICAL o m u m LABORATORY (ORAL) 8 DECONTAMINATION FACILITY %2a"
.- ~
(ODEF) 8
=a ~~
0? . m E '!, - G . A . 6. 99
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.6 Page 13 of 15
~~ '
2 ACTIVATION AND OPERATION OF THE DAEC OFF-SITE Revision 0 RADIOLOGICAL AND ANALYTICAL LABORATORY (ORAL) Date 7/25/83 ATTACHMENT 6.3 DAEC 0FF-SITE RADIOLOGICAL AND ANALYTICAL LABORATORY _(ORAL) SAMPLI LOG FO Sample Collection Location Date Time Taken Date/ Time Number and Sample Identification Sampled Sampled By Analysis Exposure Requested Completed Rate Analysis 6 m m t I m aums m. f m 6 f
-,~-,--w-,,mn-,w, -m-- w-n,,,,-r-w-~~,-,.,--.,--n--.-e-,.-
. . l EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.6 )
P age 14 of 15 ACTIVATION AND OPERATION OF THE DAEC OFF-SITE- Revision 0 ~ ': '
- RADIOLOGICAL AND ANALYTICAL LABORATORY (0RAL) Date 7/25/83 ATTACHMENT 6.4- ,
DAEC 0FF-SITE RADIOLOGICAL AND ANALYTICAL LABORATORY (ORAL) SAMPLE ANALYSIS REPORT FORM IDATE: REPORTED BY: Sample Sample Sample Activity Radioisotope Spectrum Number. Description Size * (Radioisotopes-uCi) Concentration ** Recorded on Tape / Start No.
~
i l
* .Use actual size analyzed; air in ce; liquid in ml; bulk in g
** Divide Activity by Sample Size: air in uCi/cc; liquid in uCi/ml; bulk in uCl/g r
O
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.6 Page 15, of 15 ., ACTIVATION- AND OPERATION OF THE DAEC 0FF-SITE Revision 0 RADIOLOGICAL AND ANALYTICAL LABORATORY (ORAL) Date 7/25/83 ATTACHMENT 6.5 . ORAL ALPHA / BETA REPORT FORM
.O 23 e
2:*
. . *= ..
8 :
.28 fi ai*
'23 3 82*
t : . E
.b $ E j 323 .
s .:= '
*J " i:4
- ~ :
- : .- 3 2 S .if :
5 ; ; :S ,
=
2 : -
- = ...
-~
- s u.2 8
e .. 3 - 3 II ;* G= 2 *2 :: 3
=<-
E
- e e a f
! . ... -3 . . c* 'il 22 : 2:3 3. 7
~ * *
- i. .
l .=
. = : :: _
I 1, 1 . 1 . . G. Io l ll : 72 i **
.a i s .
, .6
' i I
.o
- i l l
i j .o.! = <
. l e
+ . j
.! =! -
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.7 Page 1. ,of 10 .. ,
- ACTIVATION AND OPERATION OF THE DAEC OFF-SITE Revision 0 DECONTAMINATION FACILITY (0DEF) Date 7/25)83 1.0 PURPOSE This procedure provides instructions for the activation and operation of the Off-Site Decontamination Facility (00EF) located at 101712th Avenue S.W. in Cedar Rapids. The ODEF is intended to be utilized to decontaminate personnel in the event the decontamination facilities at DAEC are not available.
2.0 APPLICABILITY 2.1 This procedure applies to members of the plant Health Physics staff, as well as selected menbers of Radiation Protection Departnent Management which may be _ designated to staff the 0DEF following a site evacuation. 2.2 This procedure shall be implenented for events which may result in the need to decontaminate personnel off-site. 2.3 The ODEF should normally be activated for a Site or General Energency. 3.0 RESPONSIBILITIES 3.1 Site Radiation Protection Coordinator 3.1.1 Determine the potential need for processing personnel for decontamination in the ODEF. 3.1.2 Recommend activation of the ODEF to the Emergency-Coordinator. 3.2 Emeroency Coordinator 3.2.1 Authorize activation of the ODEF. 3.3 ORAL /0DEF Supervisor 3.3.1 Verify that actions required to physically place the ODEF into operation are accanplished. 3.3.2 Coordinate and supervise support activities of the ORAL and ODEF technici ans. 3.3.3 Coordinate support activities provided by personnel at the ODEF and between OSC and ORAA. 3.4 Radiological Assessment Coordinator 3.4.1 After the EOF has been activated, and the ORAL has been made operational, and after the RAC has assumed responsibility for the Off-Site Monitoring Teams, the RAC will then also have l responsibility for the ODEF.
+--g+.p, -.- , - + . - - , , - - , > - , . + ,s.- -. my ,-_. , -m-, y v -.,..__ 9 m , , -*- - , +-- p , ,wqy- g --+-e.-- ,
-w~7w-
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.7 Page 2 of 10 l ACTIVATION AND OPERATION OF THE DAEC OFF-SITE Revision O ' - ': DECONTAMINATION FACILITY (0DEF) Date 7/25/83 l 4.0 INSTRUCTIONS 4.1 Activation of the ODEF 4.1.1 Notification of CDEF Personnel (a) The Site Radiation Protection Coordinator, upon determining the potential need for processing personnel for decontamination at the ODEF, should take the following actions: (1) Recommend activation of the ODEF to the Emergency Coordinator. NOTE THE ODEF SHOULD BE ACTIVATED FOR A SITE OR GENERAL EMERGENCY, BUT MAY BE ACTIVATED FOR EVENTS OF LOWER CLASSIFICATICN, AT THE DISCRETION OF THE EMERGENCY COORDINATOR. (2) Subsequent to receiving authorization from the Emergency Coordinator, contact the ORAL /0DEF Supervisor and advise him of the impending activation of the ODEF. NOTE ACTIVATION ACTIVITIES REQUIRED TO SET UP THE ODEF SHOULD BE ACCOMPLISHED PRIOR TO THE NEED TO ACTUALLY PROCESS PERSONNEL FOR DECONTAMINATION IN THE ODEF. (3) Request the ORAL /0DEF Supervisor to contact the OSC Supervisor to staff the ODEF. (Nonnally, two Health Physics technicans will be required.) , 4.1.2 Personnel Accers to ODEF (a) The ODEF is located on the second floor of the IE Systems Protect. ion Warehouse located at 1017 12th Avenue S.W. (see Attachment 6.1, " Travel Routes to the ORAL and ODEF). (t) Entry to the ODEF should only be made from the exterior entryway on the 12th Avenue side of the building. NOTE i THE KEYS FOR THE ORAL AND ODEF ARE MAINTAINED AT THE SECURIT CONTROL POINT (SCP) AND IN THE RADIATION PROTECTION GROUP. (c) All contaminated personnel should go directly to the Waiting Area located in the basenent of the ODEF for processing.
I EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.7 Page 3 of 10
^I ACTIVATION AND OPERATION OF THE DAEC OFF-SITE Revision 0 '
DECONTAMINATION FACILITY (ODEF) Date 7/25/83-4.1.3 ODEF Operational Arranoements (a) The ORAL /0DEF Supervisor will make all necessary arrangements to have the ODEF opened and prepared to process personnel as soon as possible upon activation. (b) Existing canmercial telephone communications between the ODEF and the OSC at DAEC will-be checked. NOTE THE ORAL TELEPHONE SYSTEM ii1LL BE USED FOR ODEF. (c) The 00,EF Health Physics Technicians will set-out soap, towels, and clean clothing in preparation for processing contaminateo personnel. (d) The ODEF Health Physics Technicians will prepare a
" Contaminated Area" step-off pad in the hallway entrance to the ODEF.
(e) The ODEF Health Physics Technicians will verify the operaoility of all radiation detectors (i.e., portable radiation survey meters). 4.1.4 Notification of ODEF Operability (a) The ORAL /0DEF Supervisor should notify the OSC and ORAA Supervisors that the ODEF is staffed, and that the ODEF is operational and ready to process contaminated personnel. (b) The ORAL /0DEF Supervisor should coordinate as necessary with the OSC and ORAA Supervisors to receive contaminated
- individuals at the ODEF.
4.2 ODEF Operational Procedures 4.2.1 Processing Contaminated Personnel (a) All contaminated personnel should sign-in at the ODEF (see Attachment 6.2, "00EF' Sign-In Form".) Oth!r forms, such as the Personal Statement form may also be required, and the following information should be required:
- 1. Name
- 2. Social Security Number
- 3. Address
. 4. Telephone 9
EMERGENCY PLAN ICLEMENTING PROCEDURE EPIP 2.7 Page 4 of 10 ACTIVATION AND OPERATION OF THE DAEC 0FF-SITE Revision O , DECONTAMINATION FACILITY-(ODEF) Date 7/25/83 (b) If a site evacuation is made directly fran DAEC to the ODEF, the ODEF Health Physics Technicians will survey all personnel ( to detennine the extent of personnel contaninat' ion in order to establish the priority for processing personnel to minimize exposures and to prevent the spread of contamination to off-site areas. (c) The contaminated individual will renove all personal clothing and place it in a plastic bag. This bag should be sealed and marked with the individual's "NAME". An ODEF Health Physics Technician will survey each personal clothing item, and separate, package and label all contaminated items, as e appropri ate. 4.2.2 Personnel Decontamination (a) The flow for processing con-jaminated personnel at the ODEF will be from the Waiting Area in Ithe basement to the Change Room - area, through the shower, to the monitoring and dressing rocm. Personnel will then exit the ODEF via the freight elevator ano loading dock doorway. (See Attachment 6.3). (b) All personnel decontamination will be conducted in accordance with standard DAEC procedures (See RPP 12.1, " Personnel Decontamination"), unless the ORAL /00EF Supervisor is directed otherwise by the OSC Supervisor. (c) Usually, the contaminated individual will be monitored by the ODEF Health Physics Technician, and informed of any skin areas to receive special decontamination efforts. (d) The contaminated individual will then enter the shower stall and using soap and water, should wash his entire body with
- special emphasis on the skin areas identified as needing decontanination. (See RPP 12.1 " Personnel Decontamination".)
(e) Upon exiting the shower stall, the individual will again be monitored by the ODEF Health Physics Technician for any residual skin contamination. (f) If residual contamination still remains, and as directed by the ODEF Health Physics Technician, the individual will reenter the shower stall and complete further decontamination of the affected skin areas. (g) After receiving approval from the ODEF Health Physics Technician that the decontamination process has been satisfactorily completed, the individual may then complete drying and enter the dressing rocm. l
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.7 l Page 5 of 10 ,, Revision 0 ~ l ACTIVATION AND OPERATION OF THE DAEC 0FF-SITE DECONTAMINATION FACILITY (0DEF) Date 7/25/83 (h) The individual may then redress in either clothes provided by IE or in his/her personal clothing (but only if.the personal clothing has been surveyed and " cleared" by the ODEF Health Physics Technician). (i) Any follow-up bioassay or whole-body counting of the individual will be detennined by the ORAL /0DEF Supervisor, and will be completed in accordance with est'ablished procedures (See RPP-9.1, " Bioassay Prograns" and 9.3, " Calibration and Operation of the Bio-Nuclear Whole-Body Counter".) 4.2.3 Records (a) All reports and documentation of skin contamination levels for each individual processed in the ODEF should be completed on a fonn such as Attachment 6.2, "0DEF Sign-In Form" under the
" Remarks" column. Such records should be maintained on file in the ODEF.
(b) Copies of all records should be sent to the Site Radiation Protection Coordinator and the OSC Supervisor. 4.2.4 Liquid Waste Disposal (a) All liquid waste generated at the ODEF (i.e., the wster frem the shower stalls and sink) will drain directly into a 500 gallon high-integrity polyethylene storage tank. (b) As necessitated by the volume of emergency operations at the ODEF, the ODEF Health Physics Technician should monitor and record the liquid waste level of the 500 gallon stcrage tank. (c) As the 500 gallon storage tank becomes full, sampling and i analysis of the contents will be completed. The procedures as
- I, detailed in P.A.S.A.P. 8.11, " Radioactive Waste Control and Disposal fran the DAEC Off-Site Radiological and Analytical Laboratory (ORAL) and the Off-Site Decontamination Facility (ODEF)" should be followed.
NOTE Radioactive liquid wastes should not be discharged into the Cedar Rapids Sanitary Sewage System unless written authorization has been grantad by the Site Radiation Protection Coordinator. 4.2.5 Radiological Monitoring of the ODEF (a) Radiological surveys for both radiation levels and for loose l contamination (i.e., both alpha and beta / gamma radiation) should be conducted as necessary during the operation of the l- ! ODEF. _
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.7 Page 6 of 10 ACTIVATION AND OPERATION OF THE DAEC OFF-SITE Revision O ' - : DECONTAMINATION FACILITY (ODEF) Date 7/25/83 (b) During the energency operation of the ODEF, such radiological surveys should be completed at least once each day. (c) All radic'ogical survey results should be recorded using appropriate Site survey forms, and kept on file in the ODEF. 4.3 Deactivation of the ODEF 4.3.1 Deactivation Responsibility l (a) The ORAL /0DEF Supervisor will deactivate the ODEF only upon the i approval of the Site Radiation Protection Coordinator. NOTE The OSC and ORAA Supervisors should be contacted and their concurrence obtained prior to deactivation of the ODEF. (b) The ODEF Health Physics Technician will then proceed to shut-down the radiation detectors, clean up the ODEF, and complete radiological surveys of the ODEF. 4.3.2 Resupply of the ODEF (a) The ORAL /0DEF Supervisor will verify that the entire f acility has been properly cleaned up and preparation made for - restocking. (b) Soap, towels, and clean clothing must be inventoried and restocked, by the ODEF Health Physics ,tecnnicians, as necessary. , 4.3.3 Sumary Report cF ODEF Activities , l (a) The ORAL /0DEF Supervisor will be responsible for preparing a l stenay report of ODEF activities conducted during the emergency o activation of the ODEF. t I
5.0 REFERENCES
5.1 Duane Arnold Energy Center Emergency Plan j 5.2 PASAP 8.11, " Radioactive Waste Control and Disposal from the DAEC Off-Site l Radiological and Analytical Laboratory (ORAL) and the Off-Site Decontamination Facility (0DEF)". l 5.3 PCP 10.8 " Radioactive Liquid Release Analysis and Documentation" 5.4 RPP 7.1 " Radiation Surveys" 5.5 RPP 7.3 " Radioactive Contamination Surveys" i l l
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.7 Page 7 of 10 ,
~
ACTIVATION AND OPERATION OF THE DAEC 0FF-SITE Revis'on 0 DECONTAMINATION FACILITY (ODEF) Da.te 7/25/83 5.6 'P 12.1 " Personnel Decontanination" 6.0 A~ "S 6.1 Travel Routes to ORAL and ODEF 6.2 Cff-Site Decontamination Facility (ODEF) Sign .In Form. 6.3 Floor Plan for ORAL /0DEF. . Approved by: W Date 9!f4 7 J
'Jnergendy P' a n3 ~^ 1'npr /
i Date Sl AllM Approved by: \ n.. A 1 ^- - Health Physics Supervisor Aproved by: If/ z2/4rt4 Date f8
/
Raciatiin Protylon Supervisor Reviewed by: k r mfa Date 7[26)g3 ALARA Coorainator Q Reviewed by: I ,me Date M-27-83 Operations Committee Chairman Approved by: Date 9'19 63
- Plant Superintendent - Nuclear 1
l
. , , g - ------g-,- -----_v., - . - -
, 4
$mkiM< ?N 3E$mEm$m$n mQ m~
o ,
,5
- $ c x$ 5 O3 o .
%4 2 4 g* $ o o"m $1- E2 o $ m S
= ea,N1p 9 i
3r821 = ? s O 'l $ U <. 3 ,,, e$ ygo $ L g Yir m~~ 4s<
- r NOt- g ose o .
R T S H T e 9 1 R . I R E E V A R 2S T HS T Sll li? T I t i T S D E t T v z'- S 6 I t w V- 3 H T- 3 A O Ae T 8- H O Tu S 0 1 T 2 i s
~ -
- Ic i 2 ,
0 0 3 R #,A EEW1 '## t 7 ., , 0 O k I
.J T ),
g \ e T i t l38FES86 W$6 DE7766-i g T
)'
s T- s 6
. \ S [
e OVA 3t9M' spS , p i . o &6t33 i o
#~ L2E 1*
,& i , -
2 A1 4 t D 1- R 101 1 V t E E O0114 s t S
^v =
I a !' i L t 1 n E 8 ai E / h'e' n E N E V A H T V i M A G 0 V I 0 N E o O i s V w S i A E N E E t 4 G V 6 f D V O A A 0, 1 S E T **E i [ ,
-/t W C /.
E - A D - O (( T\ 4 9
1
, . 1
' EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 2.7 Page 9. , of 10 ,,
ACTIVATION AND OPERATION OF THE DAEC 0FF-SITE Revision 0 DECONTAMINATION FACILITY (0DEF) Date 7/25/83 ATTACHMENT 6.2 0FF-SITE DECONTAMINATION FACILITY (ODEF) SIGN-IN FORM ADDRESS TELEPHONE REMARKS NAME SOCIAL SECURITY NUMBER h 4 i i i 4W~'" * 'rw,as y ay,m y. ._,,. -, p, _
9 IT1
> 3 O
- 2 El 4 M sz "
o F O ~~g >. MA20 ENTRANCE Ops les FLDOR O 80e712m Ave. S K Q - (Mast ELEC1H4 CAL PANEL 2 O 3
~
~ _ H u m hESTHOQht O LA gyi D $ioHAGE q p O
w at
~D M D ~"~'" ""'
[ O
=D g
- z 4
y m WAIER 2 O 8#" u
> n o Col 54flNG ROOM SAMPLE RECEIPT & N DLUCH >
z O O G ~ ~ O - FY1 WAULT 84t[4SeeG $ i
~
4 R ?? baM IHit m EEM NQ 2 I og O O tio it O - - === y g g p , O q b sile4 AGE
\ HPGsECTLCius Fi f
hh $,gFillEM pg
/
, g a gugT _
.ima:CnA tumeEucE
~
WAhLHOUSE AhEA 5' <m 5' " Q-r OFF-SITE RADIOLOGICAL a ANALYTICAL {*" LABORATORY (ORAL) B DECONTAMINATION l~ACILITY . s 8 (ODEF) D 5 .'" e " 5 . A e e9
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1
. .Page 1 of 1g - -
ON-SITE RADIOLOGICAL MONITORING Revision 3 Date - 8/1/83 l.0 PURPOSE . This procedure provides instructions for performing radiological monitoring activities during an emergency including determination of habitable areas, in-plant and on-site radiological monitoring, and post-accident sampling. 2.0 APPLICABILITY 2.1 This procedure is applicable to the Site Radiation Protection Coordinator, Chemistry Technicians, the OSC Supervisor, Health Physics Technicians and other On-Site Monitoring Team personnel involved in on-site radiological monitoring activities. 2.2. This procedure should be implemented for events classified as an ALERT or
. greater, and may be implemented upon activation of the OSC for an event classified as a NOTIFICATION OF UNUSUAL EVENT.
3.0 RESPONSIBILITIES 3.1 Site Radiation Protection Coordinator 3.1.1 Provide direction to the OSC Supervisor regarding radiological monitoring activities to be conducted and protective measures to be implenented for personnel on site. 3.1.2 Determine the need for post-accident sampling, identify the samples to be obtained and evaluate the results of such sampling activities. 3.1.3 Appraise the Emergency Coordinator of on-site radiological conditions; protective measures to be implemented including evacuation of the assembly areas or the site, as required; and evaluations of the results of post-accident sampling. 3.1.4 Dispatch the On-Site Radiological Monitoring Temn, direct the activities to be accomplished and evaluate the results of monitoring activi ti'es. 3.2 OSC Supervisor 3.2.1 Direct implementation of radiological monitoring activities on site, evaluate the results of survey and airborne sampling activities conducted in the plant and appraise the Site Radiation Protection Coordinator of the results and proDiems wnich exist. 3.2.2 Insure implementation of' protective measures defined by the Site Radiation Protection Coordinator. t o o L.
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1 Page 2, of 19 ,, ON-SITE RADIOLOGICAL MONITORING Revision 3 Date - 8/1/83 3.3 Emercency Coordinator 3.3.1 Authorize reclassification of the event based upon on-site
' radiological conditions or recommend reclassification to the Emergency Response and Recovery Director if the E0F is manned.
3.3.2 Authorize evacuation of selected plant areas including evacuation of the site as may be recommended by the Site Radiation Protection Coordinator. 3.3.3 Authorize increased personnel exposure limits, as required, based upon recommendations provided by the Site Radiation Protection
. Coordinator.
4.0 INSTRUCTIONS - 4.1 Determination of Assembly Area Habitability 4.1.1 The assembly areas of concern at the DAEC include the following:
- a. Control Room
- b. TSC
- c. OSC, which includes the Locker Room, Security Building, the Health Physics Access Control Area, the Construction Support Center and interconnecting passageways.
'd. Hot Lab 4.1.2 Initial determinations of habitability for the Control Room, TSC and Hot Lab should be accomplished by insuring that the radiation levels being detected by the permanently installed radiation monitoring system are normal.
- a. As discussed in EPIP 2.5, " Control Room Emergency Response Operation", the Back Panel Communicator shall record the indicated radiation levels monitored, by the Area Radiation Monitoring (ARM) System which includes GM detectors located in i the Control Room and Hot Lab, and forward this information to the Site Radiation Protection Coordinator.
NOTE l l Attachment 1, " ARM Locations", provides a listing of the installed Area Radiation Monitors throughout the plant,
- including their locations and ranges.
~
.7
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1 I Page 3 of 19 .- ON-SITE RADIOLOGICAL MONITORING Revision 3 Date - 8/1/83
- b. As specified in' EPIP 2.2, " Activation and Operation of the TSC",
the three TSC radiation monitors (two monitoring the ventilation intake duct work and one in the TSC general area) shall be observed by personnel upon initially activating the TSC. 4.1.3 If radiation levels 'being monitored in the above areas are greater than normal, the Site Radiation Protection Coordinator should be advised and. protective measures instituted, as may be required. NOTE
- 1) If the monitors are alarming, the Site Radiation Protection Coordinator may recommend evacuation of such areas to the Emergency Coordinator.
- 2) If monitor levels are higher than normal, priority should th given to radiation survey and sampling activities in those areas so as to determine their acceptability for continued access.
4.1.4 The OSC Supervisor shall initiate radiation survey and airborne sampling of the OSC and Construction Support Center, or other areas, based upon the priority assigned by the Site Radiation Protection Coordinator. The following activities will be conducted by Health Physics Technicians assigned by the Emergency Assignment Tag Board. a) Area radiation surveys shall be conducted and documented as prescribed in RPP 7.1, " Radiation Surveys". b) Radiation contamination surveys shall be conducted and documented as prescribed in RPP 7.3, " Radiation Contamination Surveys", c) Airborne radioactivity surveys shall be conducted and documented as prescribed in RPP 7.4, " Airborne Radioactivity Surveys". 4.1.5 The results of such survey and sampling activities shall be reviewed by the OSC Supervisor, and their degree of conformance to normal DAEC Administrative Guidelines determined. a) Normal personnel external and-internal exposure limits in effect are prescribed in RPP 2.1, " Personnel Exposure Limits". b) Standard area contamination limits to be observed are prescribed in RPP 6.1, " Area Classification". NOTE Limits prescribed by the above RPPs have been partially reproduced in EPIP 4.3, " Rescue and Emergency Repair Work." S,
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1 Page 4 of 19 , ON-SITE RADIOLOGICAL MONITORING Revision 3 Date - 8/1/83 4.1.6 Survey and sampling activities prescribed. in paragraph-4.1.4 should be conducted in the Control Room, TSC, and Hot Lab if increasing trends are detected by the installed radiation monitors or as may be
. otherwise directed by the Site Radiation Protection Coordinator.
4.1.7 If an assembly area is determined to be uninhabitable or not suitable for long term habitability. a) Non-essential personnel should be evacuated to the ORAA, as prescribed in EPIP 2.4, " Activation and Operation of the ORAA". b) Essential personnel shall be relocated to another assembly area
- determined to be safe, or occupancy times established for the affected areas and relief shift assignments made so that essential functions can be conducted on a continuing basis.
4.1.8 If evacuation of one or more assembly areas is required, essential personnel should be relocated to an alternate area, as follows: Primary Area 1st Alternate 2nd Alternate a) Control Room as required to achieve safe shutdown b) TSC Centrol Room ---------- c) 0SC TSC Control Room d) Construction Support Center OSC CRAA e) Hot Lab Off'-Site Radiological Laboratory NOTE
- 1. When selecting _ " essential" personnel, consideration should ~
be given to the minimum shift staffing requirements defined in NUREG 0654, Rev. 1, Table B-1 and identified in EPIP 2.2, " Activation and Operation?'of the TSC". v
- 2. Guidance regarding TSC personnel considered to be essential is contained in EPIP 1.3, " Plant and Site Evacuation".
~
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1 Page 5 of 19 '? ON-SITE RADIOLOGICAL MONITORING Revision 3 Date - 8/1/83 < 4.1.9 Follow-up monitoring of assembly areas should be conduct.ed as directed by the OSC Supervisor. a) Survey and sampling activities to be conducted and their frequency should be based'upon the potential radiological hazards which can be expected as a result of plant conditions, as well as the results of prior monitoring activit'ies and the capability of installed instrumentation, in those arcas where instrumentation is provided, to detect changes in radiological conditions. b) In defining the type, frequency and location of monitoring activities to be conducted, consideration should be given to changing radiological conditions, such as; changing meteorological conditions, increases in effluent release rates, changes in the isotopic distribution of the release and increases in radiation levels throughout the plant. 4.1.10 .The results of such monitoring activities shall be reviewed by the OSC Supervisor, and the Site Radiation Protection Coordinator advised of any problems or adverse trends detected. a) 1he Site Radiation Protection Coordinator should provide guidance to the OSC Supervisor regarding further monitoring activities to be conducted and protective measures to be instituted for personnel in those areas; for example, use of protective clothing and respirators, implenentation (or modification) of occupancy times, administration of KI, etc. b) The Site Radiation Protection Coordinator shall recommend evacuation of selected assembly areas or of the site, and, as appropriate, relocaticn of essential personnel to alternate assembly areas on site. NOTE
- 1. Use of personnel protection and limiting stay time should only be considered for Control Room and TSC personnel.
- 2. Evacuation of non-essential personnel is required for a SITE o GENERAL EMERGENCY.
4.2 In-Plant Radiological Monitoring 4.2.1 Radiological monitoring activities inside the plant shall be conducted to support required response actions, including: a) Rescue activities, as prescribed in EPIP 4.3, " Rescue ano Emergency Repair Work". l
EMERGENCY PLAN. IMPLEMENTING PROCEDURE ~' EPIP - 3.1 b' , Page 6 of 19 , ,
~
- 0N-SITE RADIOLOGICAL MONITORING Revision 3 s Date - 8/1/83 b)~ Emergency repair and damage control activities, as prescribed in
. EPIP 4.3. .
c) Operational response activities conducted in the plant, as
- -prescribed in EPIP 2.5, " Control Room Emergency Response
- f. Operation", 'and .EPIP.2.2, " Activation and Operation of the s- Technical Support Center".
o d) Post-accident sampling and analysis activities, as prescribed in paragraph 4.3.
,e e) , Reentry activities conducted during initial . recovery efforts, as
- prescribed in EPIP 5.2, " Recovery and Reentry".
r* cc , 4.2.2 A Health Physics Technician should. accompany each rescue, repair and reentry team upon initial entry into an area where an actual or potential radiological hazard exists. r t a) As discussed in EPIP 4.3, " Rescue and_ Emergency Repair Work", repair activities may be conducted during the course of several staged entries; therefore, entries subsequent' to the initial s s entry may be conducted without the presence of a Health Physics Technician. (n3 ~e b) - The determination as to whether or not a Health Physics Technician shall accompany a repair team or an operator into the . Plant and remain in their presence shall be made by the Site Radiation Protection Coordinator.
-4.2.3 The OSC Supervisor shall provide guidance to the Health Physics Technician as to the radiological conditions to expect and monitoring activities to be conducted.
4.2.4 Prior to dispatch of personnel into an' actual or potential radiological hazard area, a) The OSC Supervisor shall insure that required protective clothing is donned properly. , b) Respiratory protection equipment, if required, has been checked and determined to be operable, and the user is aware of equipment -:y operating limitations. c) Dosimetry of sufficient range is being worn to adequately monitor whole. body and extremity doses, where applicable. d) Equipment and supplies anticipated to be required for the M' assignment are. available and, as necessary, checked to insure operability. o 4 N 'z 4 ,# ., . , - _ _ , . . . . . . _ . _ _ _ _ _ . _ - . , . , , , _ ... . _ _ _ _ , , _ , , , _ - _. ~ v , - - -
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1 Page ,7 of 19 . . , ON-SITE ~ RADIOLOGICAL MONITORING Revision 3 Date - 8/1/83 e) An Operations Radio has been.obtained and a radio check satisfactorily conducted with CAS. - e f) Briefings have been conducted, to the extent required, so as to insure that personnel are aware of the function (s) to be performed. 4.2.5 Upon being dispatched, the Health Physics Technician, if present, should, in addition to monitoring dose rates and total exposures: a) Provide guidance to team members regarding precautions to be taken to minimize their total exposure. b) Advise the OSC Supervisor of unexpected radiological conditions encountered. NOTE If communications difficulties are experienced with the Operations Radio, the plant paging system or telephone system should be used in that order of priority. 4.2.6 The OSC Supervisor should, as time permits, monitor the activities of in-plant personnel utilizing the network of security cameras in the Central Alarm Station (CAS). 4.2.7 Upon egress from the plant, the Health Physics Technician should provide guidance, as required, in discarding p. otective clothing and in the performance of personnel monitoring and decontamination, if required, prior to passing through the Health Physics Access Control Area. 4.3 Post-Accident Samoling j 4.3.1 The OSC Supervisor shall be advised by the Site Radiation Protection l Coordinator of post-accident sampling and analysis activities to be ! conducted. I NOTE l l Attachment 2, " Post-Accident Sample Capabilities", identifies the types of samples which may be required and can be obtained. [. 4.3.2 If a particulate filter and charcoal cartridge samole from the KAMAN Effluent Monitoring System is to be obtained for analyses, a) The Site Radiation Protection Coordinator should determine which cartridge (s) are to be obtained and the radiation level of the cartridge, as monitored by the KAMAN System. W
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1 Sage 8 of ig ON-SITE RADIOLOGICAL MONITORING Revision'3 Date - 8/1/83 b) The OSC Superv'isor .should be advised of the projected radiation 12vels and review with the Site Radiation Protection Coordinator appropriate radiological protective measures to be taken.
' NOTE' Calculations have been completed which verify that the -
samples listed in Attachment 2 can'be retrieved without exceeding 10CFR50,. Appendix A, GDC-19, exposure levels of 5 rem to the whole body. Nevertheless, proper protective measures for personnel involved in sampling activities should be taken. 4.3.3 Based upon the expected dose rates, an estimate should be made of 1!he total exposure to be received while obtaining and analyzing a sample and exposure limit increases authorized, if required, as specified in EPIP 4.3, " Rescue and Emergency Repair Work". i 4.3.4 The OSC Supervisor shall designate the Health Physics Technician (s) to obtain the samples and conduct a briefing consisting of, at a minimum, the expected radiological hazards, protective measures required and pertinent procedural requirements. a) Sample retrieval from the Off-Gas Stack should be accomplished in accordance with PASAP 6.1, " Emergency Procedures for Effluem Sample Retrieval". b) Sample retrieval from the Reactor Building Stacks and Turbine Building Vent should be accomplished in accordance with PASAP 6.0 and RPP 13.2. NOTE Prior to dispatching personnel into the Power Block Structure, the Control Room Coordinator should be advised and Emergency Coordinator authorization received. c) Grab samples from the Reactor Building should be obtained as prescribed in PASAP 7.0, " Manual Reactor Building Effluent Grab Sample Procedure". 4.3.5 ' Post-accident sampling conducted at the Post-Accident Sample System station should be conducted by Chemistry Technicians in accordance witn PASAP 2.0, " Post-Accident Sampling System". 4.3.6 Personnel dispatched to remote locations to obtain samples should maintain communications with the OSC, advising-the OSC Supervisor of any unusual phenomena observed.
EMER'GENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1.
~
Page 9 of 19 ON-SITE RADIOLOGICAL MONITORING Revision 3 Date - 8/1/83 4.3.7 As time permits, the OSC Supervisor should monitor the activities of sampling personnel utilizing the network of security cameras in the CAS. . 4.3.8 Analyses of samples and documentation of results should be conducted using the 3.0 PASAP series and PASAP 7.2, ". Interpretation of Post Accident Sampling System Results". 4.4 ~ On-Site Radiological Monitoring 4.4.1 Personnel shall be assigned to the On-Site Monitoring Team by the appropriately numbered tags' on the Emergency Assignment Tag Board, as specified in EPIP 2.1, " Activation and Operation of the OSC". a) As noted in EPIP 2.1, the OSC Supervisor may elect to reassign personnel initially assigned to the Ter.ms so as to take maximum advantage of the capabilities and experience of personnel available to perform radiological monitoring functions. b) Activities to be completed by personnel assigned to the On-Site Team prior to being dispatched are identified on the associated tags and referenced checklists. 4.4.2 In making preparations for conducting monitoring activities: a) The Site Radiation Protection Coordinator shall evaluate location and magnitude of the projected on-site dose rates, as specified in EPIP 3.3b, " Computerized Dose Projections", relay this information to the OSC Supervisor and identify the sequence of monitoring activities to be conducted.
~
NOTE If the VAX computer is inoperable, dose projections may be made using EPIP 3.3a, " Manual Dose Projections". b) The OSC Supervisor shall brief the Team with this information, as well as the precautions to be taken, and insure that the team members are appropriately dressed, have the required dosimetry, t l and have checked out the operation of their equipment. NOTE EPIP 3.2, "Off-Site Radiological Monitoring", contains guidance, limitations, precautions, etc. associated with field monitoring activities similar in scope to those mentioned above. Reference should be made to this procedure when briefing On-Site Monitoring Teams.
+ .
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1 - Page 10 of 19 . . . ON-SITE RADIOLOGICAL MONITORING Revision 3 Date - 8/1/83 4.4.3 The On-Site Team may be directed to change out the particulate filters and charcoal cartridges at the environmental monitoring stations located on-site prior to, following and/or during the time when a release is in progress, a) The particulate filters and charcoal cartridges located at both stations on site should be changed. - NOTE When changing out charcoal cartridges, they should be
, replaced with Silver Zeolite cartridges.
b) Directions to each air sampler are provided in Attachment 3, "On-Site Environmental Air Sample Station Locations". 4.4.4 The OSC Supervisor shall advise the Site Radiation Protection Coordinator when the On-Site Team is ready to be dispatched. 4.4.5 The OSC Supervisor ~ shall _ assume control of the On-Site Team, and dispatch them after insuring that the Security Shift Supervisor has been advised. 4.4.6 The following surveys will normally be conducted and documented in accordance with the acc, ipanying procedure: a) Radiation survey in accordance with RPP 7.1. b) Radiation contamination surveys in accordance with RPP 7.3. , c) Airborne radioactivity surveys in accordance with RPP 7.4 NOTE Instructions for obtaining a low volume air sample and Un uheE NIe frov*ideh $YYakghpY4".51n9 a Portable survey [ 4.4.7 On-Site Monitoring cersonnel should maintain communications with the ! Radio Operator in the TSC via tne Operations Radio. 4.4.8 As time permits, the OSC Supervisor should monitor the activitie? Of On-Site Monitoring Team personnel utilizing the network of security cameras in the CAS. ! 4.4.9 Upon completion of the survey and as directed by the Radio Operator, Team members shall return to the OSC, observing all control point l requirements, and report to the OSC Supervisor for further instructions. I - l
s EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1 Page ' 11 of 19 ! ON-SITE RADIOLOGICAL MONITORING Revision 3 Date - 8/1/83 4.5 Air Sampling (Low Volume Samoles) .
'4.5.1 Load the air sampler with appropriate filters.
NOTE Use of Silver Zeolite cartridges is reconnended when obtaining low volume air samples to detect radioiodines. 4.5.2 Perform a radiation survey on the radiator of the vehicle. 4.5.3 Raise the hood on the vehicle and leave the vehicle running. 4.5.4 Connect the air sampler to the battery, ensuring the red lead goes to the positive terminal. 4.5.5 Turn the air sampler "0N". a) Take precautions to prevent contamination of the sampler, b) The sampler should be held approximately waist high. 4.5.6 Obtain a 1, 5 or 10 cubic foot air sample, as instructed. . NOTE Normally, a'10 cubic foot air. sample will be obtained in those areas where dose rates are low, i.e., <5 mr/hr. A1 cubic foot sample will be taken if dose rates are high, i.e.,
> 200 mr/hr.
4.5.7 ~ Record information regarding the sample on Attachment 5, " Air Sample Identification a. 4.5.8 Remove the sample from the sampler, taking precautions to prevent sample contamination. l a) Place the sample in a plastic bag, attach the Air Sample Identification label and seal the bag, b) Position the sample in the vehicle to minimize exposure. ,- NOTE The filter paper and Silver Zeolite cartridge should be stored separately. 4.5.9 Evaluate the filter cartridge with a portable survey instrument, determine the airborne activity concentration, record the results, and report same to the TSC (or EOF), as follows:
- ....._ - __-. - .- , , - . _ . , , - . - . _ - - . .. . , - - , - - , . +
= .
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1 Page 12 of 19 ' ON-SITE RADIOLOGICAL MONITORING Revision 3 Date - 8/1/83 NOTE
^
~
Sample evaluation must be conducted in a low background area; therefore, the Team may be required to travel to another location in order to evaluate the sample. a) Record the count rate or dose rate, as a,ppropriate, using either an E-140 or an open window R0-2. b) Using Attachment 4, " Air Activity Chart", convert the survey instrument reading to airborne activity concentration based upon the sample volume drawn. O 4.6 Documentation and Routing of On-Site Monitoring Activities 4.6.1 Documentation of radiological monitoring activities and post accident sampling results should be provided to clerical personnel in the TSC where three copies of each document shall be made. NOTE As conditions warrant, the Site Radiation Protection Coordinator and the OSC Supervisor may need this documentation insnediately; therefore,. they should be allowed to review the documentation before it-is forwarded to the Records Clerk. 4.6.2 The original should be retained by the Document Records Clerk in the TSC. 4.6.3 The Site Radiation Protection Coordinator and the OSC Supervisor should be provided one copy each of all documentation. 4.6.4 The other copy should be distributed, as follows: a) Habitability surveys - Health Physics Access Control Point b) In-Plant surveys - Health Physics Access Control Point I c) Post-Accident Sampling results - Hot Lab d) On-Site monitoring activities - Health Physics Access Control Point 5.0 REFEFENCES 5.1 OAEC Emergency Plan 5.2 NUREG 0654, Rev. 1 6.0 ATTACHMENTS 6.1 " ARM Locations" 6.2 " Post-Accident Sample Capabilities" _
~
6.3 On-Site Environmental Air Sample Station Locations
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1 Page ' 13 of 19 ~: ON-SITE RADIOLOGICAL MONITORING Revision 3 Date - 8/1/83 6.4 Air Activity Chart _ . 6.5 Air Sample Identification Approved By: . Date: a d,[27 /983 ' ! -TinergenCy Pla'n g Cbeedina w ff Approved By: ( aw Date: 9[\9f$6
- i Health Physics Supervisor
~
Approved By: b/fd b31,yrA . Date: 9!/1!f3 RaaiationPgtectiond5upervisor Reviewed By: 2 '-- wa n , . Date: 9/&L/3-3 ALARA Goorcinator g Reviewed By: o u n a _J Date: 'f-E7- 93 Cnairman,tOperations Committee Approved By: Date: 9'19'b3 Plant 5uperintencent - Nuclear i
, ,, , - - . . . - - - . ~ . ,- ,. . . . - - . . -
; EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1 Page 14 of 19 ..
ON-SITE-RADIOLOGICAL MONITORING' Revision 3
^
Date .8/1/83 ATTACHMENT 1 ma ARM LOCATIONS
- Reactor Building Units Numoer Location Elevation Range (mR/hr) Descriotion
- 1. RT 9168 North CRD Module Area 757'6" 10 103 Outside airlock to Access Control
- 2. RT 9170 CRD Repair Room 757'6" 10 103 Northwest wall, behind door e
- 3. 'RT 9167- . South Equipment Railroad 757'6" 10 103 West wall, near inner Access RX.B1 Truck Lock Door South CRD Module Area 757'6" 10 103 South wall, near airlock
.4. RT 9169
- 5. RT 9176 TIP Cubicle 757'6" 100 - 104 North wall, inside cage area Cleanup Phase Separators- 786'0" 100 - 104 East wall of CU Phase
- 6. _RT 9177 Separator Room Work Area
- 7. RT 9173 Cleanup System Resin 786'0" 10 103 East wall of CU Discharge
!. Mixer Pump Room Handling Area
- 8. RT 9157 Cleanup Heat Exchangers 786'0" 102 - 106 Inside airlock to RWCU Heat Exchanger Room 876'0" 102 - 106 Inside Door to RWCU Pump
- 9. RT 9156 Cleanup Recirculation Pump Area Room
- 10. RT 9155 Cleanup Demineralizer 812'0" 102 - 106 East wall of Filter Work Area Demin. Room
- 11. RT 9171 Ventilation-Equipment Area 812'0" 10 103 Inside 2nd airlock door to Rx. Bldg. Exhaust Fan Room Condensate Phase Separator 833'6" 10 103 Inside door, along west
- 12. RT 9175 wall of Cond. Phase Sep.
Pumps Room 855'0" 10 102 West stairway wall,
-13. RT 9163 Refuel Floor-North End Refuel Refuel Floor-South End 855'0" 10 102 North stairway wall,
- 14. RT 9164 Refuel New Fuel Storage Area 855'0" 10 103 North end of Storage 15.'RT 9153 Pit at Instrument panel
~ cWith remote- readout (Control Room), Panel #1C-11 -
.i m _
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1 Page - 15 of 19 ': l I ON-SITE RADIOLOGICAL MONITORING Revision 3 Date - 8/1/83 l ATTACHMENT 1 (Continued) _ ARM LOCATIONS *
- Reactor Building Units Number Location Elevation Range (mR/hr) Description 16..RT 9178 Spent Fuel Storage Pool 855'0" 100 104 N.E. rail around Fuel Pool
- 17. RT 9180 Waste Collecting Tank Area 737'0" 100 _ 104 S.E. Corner Room, North wall inside second door
- 18. RT 9166 Radwaste Pump Room 716'9" 10 103 S.W. Corner Room, along south wall near corner Turbine Building Units
'19. RT 9159 Reactor Feedwater Pump Area 734'0" 10 103 North Condenser Bay wall
- 20. RT 9160 Turbine Lube Oil Area 734'0" 10 103 East corridor wall
- RT 9158 Condensate Pump Area 734'0" 10 103 Mounted on girder near Condensate Pumps
- 22. RT 9174 Sump Area 734'0" 10 103- Acid & Caustic Tank, S.E.
Corner of Turbine Bldg.
- 23. RT 9179 Turbine Front Standard 780'0" 100 - 104 Along east shield wall at offset Radwaste Building Units
- 24. RT 9151 Radwaste Control Room 786'0" 10 103 South wall, near door
- 25. RT 9152 Sample Tank and Pump Floor 786'0" 10 103 North wall of Centrifuge Room 26 RT 9154 Radwaste Drumming Area 757'6" 10 103 At middle of west wall Other Units
- 27. RT 9162 Control Room (west wall) 786'0" 10 102 Control Building
- 28. RT 9172 Radiological Chemistry 7860" 10 103 Control Sidg., west wall Laboratory of hot lab 20 RT 9161 Macnine Shop 757'6" 10 102 Machine Shop Building 3u. RT 9165 Site Entry and Exit 757'6" 10 102 Entrance to Admin. Bldg.
*With remote readout (Control Room), Panel #1C-ll _
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1 ,? 'Page , 16 of.ig U ON-SITERADIOLbGICALMONITORING Revision 3 ,t-
~
Date - 8/1/83 ATTACHMENT 2 POSTdCCIDENTSAMFLECAPABILITIES A., High Range Effluent Monitoring (KAMAN) System particulate and io' dine filter cartridges can be drawn from:
- 1. Off-Gas Stack
- 2. Reactor Building Stack (s)
- 3. : Turbine Building Vent System Post Accident Sampling System
~
B.
- 1. A pressurized Reactor Coolant System sample from the Jet Pump flow sensing instrument lines A depressurized Reactor Coolant System sample from the RHR Heat Exchanger 2.
discharge line when RHR.is in the Shutown Cooling mode of operation
- 3. A Suppression Pool sample from the RHR Heat Exchanger discharge line when RHR is in the LPCI, Torus Cooling, or Test mode of operation
- 4. A Drywell atmospheric' sample from the Containment Atmosphere Monitoring System analyzer sample lines
- 5. A Suppression Pool atmospheric sample from the Containment Atmosphere Monitoring System analyzer sample lines.
- C. Reactor . Building grab samples can be taken from the backup sampler located on the Turbine Building roof.
I EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1. Page ' ~17 of 19 ON-SITE RADIOLOGICAL MONITORING Revision 3 Date - 8/1/83 _ ATTACHMENT 3 _ ON-SITE ENVIRONMENTAL AIR SAMPLE STATION LOCATIONS SAMPLER # 16 (TLD # 16) SOUTH PLANT SAMPLER Follow -the outer perimeter fence, past the COOLING TOWER $. Turn right off the intake road heading toward the Off Gas Stack. nead for the MET T0WER.- The Air Sampler is located at the base of the MET TOWER. The TLD is locatea oehind the Air Sampler. Water station (rain gauge) present.
, SAMPLER # 15 (TLD # 15) NORTH PLANT STATION
- Note the padlock type substation key unlocks this gate.
Turn left on gravel ~off north parking lot. fake the north gravel road (alternate emergency route to chain link fence - 1/2 mile). Use poptype key to unlock the fence. Approx. 80 yrds. past fence turn left into pasture entrance marked by a
" FARM MEMBER" sign. Air Sampler is located at 2nd utility pole. Pole is also marked with rusty sign "N0 TRESPASSING". Air Sampler is on the west side of the pole. TLD on the fence line approx.15 - 20 ft. south of the sampler, i
o 9 y : e -' y -argy=r+ y y =*
+w -
- - - - ---e -r - 5 y
EMERGENCY PLAN IMPLEMENTIflG PROCEDURE EPIP - 3.1 Page 18 of 19 ON-SITE RADIOLOGICAL MONITORING -Revision 3 Date - 8/1/83 ATTACHMENT 4
- -AIR ACTIVITY CHART E-140 or R0-2 '
COUNT COUNT COUNT RA7E RA7E RA7E . (CPMI Ift3 Sft3 10ft 3lI (CPM)lIft 3 lSft3l11Cft3llItCPM) Ift3 Sft3 10ft3 100 3.18E-3 6.365-9 3.18E-9 5700 1.31E-6 3.53E-7 1.31E-7 23K 7.32E-6 1.46~.6 7.225-7 - 200 6.36E-8 1.27E-3 5.36E-9 5300 1.35E-6 3.69E-7 1.35E-7 24K 7.54E-6 1.53E-6 7.54E-7 300 9.54E-8 1.91E-8 9.54E-9 5900 1.33E-6 3.75E-7 1.SSE-7 25K 7.95E-6 1.59E-6 7.95E 7 400 1.27E-7 2.54E-8 1.27E-8 6000 1.91E-6 3.32E-7 1.91E-7 25K 3.27E-6 1.65E-6 3.27E-7 500 1.59E-7 3.13E-3 1.59E-8 5100 1.94E-6 3.88E-7 1.94E-7 27K 8.59E-6 1.72E-6 3.59E-7 o 6CO 1.9CE-7 3.32E-8 1.9CE-8 5200 1.97E-6 3.94E-7 1.97E-7 23K S.91E-6 1.7EE-6 3.91E-7 700 2.22E.7 4.451-8 2.23E-3 6300 2.00E-6 4.00E-7 2.00E-7 2?K 9.23E-6 1.35E-6 9.23E-7 800 2.54E-7 5.09E 3 2.55E 5400 2.04E-6 4.07E-7 2.04E-7 3CK 9.54E-6 1.91E-6 9.54E-7 900 2.26E-7 5.721-8 2.36E-3 6500 2.07E-i 4.14E-7 2.07E-7 31K 9.35E-6 1.97E 6 9.35E-7 1000 3.18E-7 6.35E-8 3.1SE-8 6500 2.1CE-6 4.20E-7 2.1CE-7 32X 1.01E-5 2.04E-6 1.02E-6 1100 3.49E-7 6.99E-8 3.5CE-6 6700 2 13E-6 4.25E-7 2.13E-7 3X 1.05E-5 2.1CE-6 1.05E-6 1200 3.31E-7 7.64E 8 3.825-8 5300 2.16E-6 4.33E-7 2.15E-7 34K 1.03E-5 2.15E-6 1.CRE-6 1300 4.13E-7 8.27E-8 4.14E.8 5900 2.20E-6 4.39E-7 2.20E-7 35K 1.11E-5 2.23E-6 1.11E-6 1400 4.45E-7 3.91E-a 4.4EE-8 7000 2.23E-6 4.45E-7 2.23E-7 36K 1.15E-5 2.29E-6 1.15E-6 1500 4.77E-7 9.54E-8 4.77E-8 7100~ 2.25E-6 4.52E-7 2.25!-7 37K 1.13E-5 2.35E-6l1.131-6 1600 5.09E-7 1.02!-7 5.09E-8 7200 2.29E-6 4.58E-7 2.29E-7 32K 1.21E-5 2.415-6l1.21E-6 1700 5.40E-7 1.08E-7 5.41E-3 7300 2.32E-6 4.54E-7 2.32E-7 39K 1.24E-5 2.43E-6 1.24E-6 1800 5.73E-7 1.15E-7 5.73E 8 7400 2.35E-6 4. 71E-7 2.35E-7 4CK 1.27E-5 2.54E-6 1.27E-6 1900 6.04E-7 1.21E-7 6.04E-a 7500 2.39E-6 4.77E-7 2.39E-7 411 1.30E-5 2.61E-6 1.30E-6 2000 6.35E-7 1.27E-7 6.36E-a 7500 2.41E-6 4.34E-7 2.42E 7 42K 1.34E-5 2.57E-6 1.34E-6 2100 6.6EE-7 1.34E 7 6.53E-8 77C0 2.45E-6 4.90E-7 2.45E 7 , 43K 1.33!-582.74E-6tl.37E-6 2200 6.99E-7 1.33E-7 6.99E-8 7?CO 2.4EE-6 4.96E-7 2.4AE-7 : 44K 1.4CE-Sl2.3CE-6l1.40E-6 2300 7.31E-7 1.46E-7 7.32E-6 7900 2.51E-6 5.03E-? 2.51E-7l 45K 1.43E 5 2.35E-611.43E-6 2400 7.63E-7 1.52E-7 7.64E-3 5000 ; 2.55E-6 5.09E-7 2.!!I-7L 46K 1.46E-5 2.9:1-6l1.455-6
'2500 7.95E-7 1.59E-7 7.95E-3 3100 2.53E-6 5.15E-7 2.58E-7 47K 1.!CE-5 2.99E-611.5CE-6 2500 3.27E-7 1.55E-7 8.27E-3 3200 2.51E-415.225-7 2.51E-7 aaK 1.53E-5' 3.05E-6il.53E-6 2700 3.5EE-7 1.72E-7 3.59E-3 3300 2.54E-615.23E-7 2.54E-7 49K :.55E-5 3 J2E-ill.55E-6 2.57E-6 5.34E-7 2.57E-7 1.59E-5 3.13E-6i'. 59E-6 ZSCO S.9CE-7 1.73E-7 S.91E-3 1400 SCK 2900 9.22E-7 1.35E 7 9.23E-31 3500 2.70E-6 5.4CE 7 2.7 E-7 51K 1.525-513.:!E-6ti.52E-6 3CCO 9.54E 7 1.91E-7 9.54E-81 2500 2.74E-6 5.47I-7 2.74E-7 52K 1.55E-513.31E-6il.55E-6 3100 9.35E.7 1.97E-7 9.35E-3, 3700 2.77I-5 5.54E
- 2.77E 7 5K 1.59E-3 3.37E-6l1.69E-6 3200 1.0;E.6 2.C4E-7 1.0 1-7 3300 2.30E-6 5.5CE.7 2.30E-7 54K 1.72E-5]3.43E-6l1.7:E-6 i
3300 1.04E-6 2.10E-7 1.05E-7 3900 2.33E-6 l 5.55E-7 2.33E-7 55K ' i.75E-5 3.49E 6 1.75E-6 3400 1.CEE-6 2.15E-7 1.08E-7 9000 2.35E-615.73E-7' 2.35E-7 56K 1.73E-i 2.55E-6 1.73E-6 3500 1.11E-6 2.23E-7 1.11E-7 9100 2.89E-6 5.79E-7 2.90E-7 57K 1.31E-5 3.53E-6 1.311-6 3600 1.14E-6 2.ZSE-7 1.15E-7 9200 2.92E-6 5.35E 7 2.93E-7 53K 1.35E-5 3.59E-6 1.3EE-6 3700 1.17E-6 2.35E 7 1.1SE-7 9300 2.96E-6 5.32E-7 2.96E-7 59K 1.38E-5 3. 75 E-6 1.33E-6 3800 1.2CE-6 2.42E-7 1.21E T 9400 2.90E-6 5.93E-7 2.99E-7 SCK 1.91E-5 3.3 1-4 1.91E-6 3900 1.24E-6l2.48E-7 1.24E.7 9500. 3.0ZE-6 5.04E-7 3.021-7 61K 1.94E-5 3.3SE 6 1.94E-6 4000 1.27!-6 2.54E-7 1.27E-7 9600 3.05E-6 6.11E-7 3.05E-7 52K 1.97E-5 3.942-6 1.97E-6 4100 1.3CE-6 2.51E-7 1.3CE-7 9700 3.03E-6 5.17E-7 3.09E-7 53K 4.011-si".00E 6 4200 1.3:E-612.57E-7 1.34E-7 9300 3421-6 5.2*E-7 3.12E 7 54K' 2.00I-5l4.07E-si2.04E-6 2.04E-5, 4300 1.35E-6 2.74E-7 1.37E-7 9900 3.15E-6 6.3.!-7 3.;5E-7 55K Z.07E-514.14E-612.07E-6 4400 1.4CE-5 2.79E-7 1.4CE-7 10K 3.13E-615.35E-7 3.!!E-7 . 55K 2.1;E-514.20E-612.;;E-6 1.43E-6 2.35E 7 1.43E-7 11K 3.5CE-615.99E-7 3.5CE 7i 57K 2.12E-il4.25E-612.1 E-6 45QQ 40W 1.46E-6 2.93E-7 '. 46E-7 12K 3.322-617.54E-7 3.3:E-71 52K 2.15E-514.3:E-6i2.15E-6 4700 1.!CE-6 2.99E-7 1.49E-7 13K 4.14E-4l3.2?I-7 4.14E-71 59K 2.20E-514.39E-612.20E-6 4800 1.52E 6 3. 5E-7 1.53E-7 14K 4.45E-6fa.91E-7 4.45E-71 7rK 2.M E-ita.45E 4 2. ME-6 1.55E-7 15K 4.77E-619.54E 7 4.77E-71 3, ir . : -:i :. ..:-o w. :::-o 4900 1.55E-6i3.1:E-7 , 5000 1.59E-613 ; E-7 1.59E-7 15K 5.09E-6J1.;2E-6 5.3?E-71 ::-3/9r!3.15E-515.35E 613.13E 6 5100 1.52E-613.25E 7 1.52E-7 -17K 5.41E-611.03E-615.41E-71 10-i/hr ,3.3:E 5 6 7.54E-613.32E-6 5200 1.55E-613.31E 7 1.65E-7 ;EK 5. 7;E-s i l .15 E-6 l 5. ;3E- 7 ? . ;!-A /h r 4.77E-5j9.54E-614.77E-6 19K 5.04E-6 '. 21E-616.04E-7l 0-A/hr 5.25E-5 J.:7E-5.6.;5E-6 53C0 1.59E-613.37E 7 1.59E-7 54C0 1.721-613.44E 7 1.7:E-7 ::K 5.35E-i 1.NE-615.3sE7ll':5-A/5r.7.95E-sil.59E-si7.95E-6 55C0 1.75E-613.5 E 7 1.75E-7 21K 6.55E-6,;.34E-616.63E-7!!30.-A/hr 9.54E-5!;.91E-519.54E-6 i 56C0' 1.*3E-613.56E-711.75E-71 22K 5.99E-6l1.4CE-6l5.99E-71[5;rA/hr'1.59E-4{3.1SE5{1.19E-5 Applicable for open window measurements at contact with a Silyer Zeolite Cartridge. ~ e
.(Ci/m3 or uCi/cc)
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1 Page ~ i9 of 19 i ON-SITE RADIOLOGICAL MONITORING Revision 3 Date - 8/1/83 ATTACHMENT 5 ( AIR SAMPLE IDENTIFICATION AIR SAMPLE . I I SAMPLE LOCATION DATE/ TIME ON / DATE/ TIME OFF / SAMPLE FLOW RATE CFM SAMPLE COLLECTED BY l l 1 I l - i
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 Page ~~ l of 26 0FF-SITE RADIOLOGICAL MONITORING Revision 4 Date - 8/1/83 1.0 PURPOSE _ This procedure provides guidance associated with the performance of off-site radiological monitoring activities during ~ an emergency. , 2.0 APPLICABILITY , 2.1 This procedure is applicable to the Site Radiation Protection Coordinator,
' 0SC Supervisor and Off-Site Radiological Monitoring Teams personnel during events classified as an ALERT or greater when an actual release is in progress or when the potential exists for a significant release in the future.-
2.2 Guidance associated with directing and controlling the activities of Off-Site Monitoring Teams and coordinating such activities with those being accomplished by local, State and Federal agencies is contained in CPIP 2.1,
" Dose Assessment and Protective Action Recommendations".
NOTE It is expected that the majority of the radiological monitoring activities described in this procedure will be conducted under the direction of the Radiological Assessment Coordinator in the EOF, since events which result in any significant release should be classified as a SITE or GENERAL EMERGENCY; hence, requiring activation of the EOF. 3.0 RESPONSIBILITIES 3.1 Site Radiation Protection Coordinator 3.1.1 Initially dispatch and direct the activities of the Off-Site Radiological Monitoring Teams until relieved of this function by the Radiological Assessment Coordinator. 3.1.2 Evaluate radiological monitoring data reported by Off-Site Teams and provide recommendations to the Emergency Coordinator regarding event reclassification and recommended protective action until relieved of this function by the Radiological Assessment Coordinator. j 3.1.3 Coordinate with the Radiological Assessment Coordinator for turn over i of the Off-Site Teams and provide assistance, as requested, in evaluating radiological monitoring results. 3.2 0SC Suoervisor ,. 3.2.1 Insure that the Off-Site Radiological Monitoring Teams are properly equipped to enable performance of required monitoring functions and that the teams are briefed prior to departure.
- t*
l
4 . EPIP - 3.2
~
EMERGENCY PLAN IMPLEMENTING PROCEDURE Page ,, 2 of 26 ,, OFF-SITE RADIOLOGICAL MONITORING . Revision 4 Date - 8/1/83 3.3 Radiological' Assessment Coordinator
~
3.3.1 Direct the off-site radiological monitoring and analyses efforts conducted by Iowa Elect-1c personnel and coordinate such activities with those being accomplished by the State of Iowa. 3.3.2 Evaluate the results of computerized dose projection calculations and the results of off-site radiological monitoring activites in order to determine the consistency between predicted and actual off-site impacts, and to ensure adequate characterization of the plume. 3.3.3 Assist the Radiological and EOF Manager in formulating protective -* action recommendations based upon on-going or potential radiological releases and the results of off-site radiological monitoring activities ano trends which tacome apparent in the data analyzed. 3.3.4 Coordinate with the Site Radiation Protection Coordinator regarding activation of the Off-Sitt Radiological and Analytical Laboratory and for the utilization of other available radiological analyses facilities for analysis of field sample media. 3.3.5 Provide information to and coordinate off-site radiological monitoring and dose assessment activities with Federal agency and support organization representatives assigned responsibility for assessing the off-site impact of a severe radiological event at the DAEC. 4.0 INSTRUCTIONS 4.1 Team Preparation and Discatch. 4.1.1 Personnel should be assigned to the Off-Site Monitoring Teams by the appropriately numbered tags on the Emergency Assignment Tag Board as specified in EPIP 2.1, " Activation and Operation of the Operational Support Center". a) As noted in EPIP 2.1, the OSC Supervisor may elect to reassign personnel initially assigned to the Teams so as to take maximum advantage of.the capabilities and experience of personnel available to perform radiological monitoring functions. j b) Activities to be completed by personnel assigned to the Off-Site Teams prior to being dispatched 'are identified on the associated Tags and referenced checklists. l N
EMERGENCY PLAN IMPLEMENTING PROCEDURE- EPIP - 3.2 Page - - 3 of 26 : 0FF-SITE RADIOLOGICAL MONITORING Revision 4 Date - 8/1/83 4.1'. 2 -In making preparations for conducting monitoring activities:
~
a);.The Site Radiation Protection Coordinator shall ~ evaluate the'
- location and magnitude of the projected off-site plume if a
'elease is in progress as specified in EPIP 3.3b, " Computerized r
. Dose Projections" and provide recommendations to the Emergency Coordinator regarding the need to. conduct off-site monitoring -and
. dispatch of the; Teams.
NOTE
- 1. Off-Site Radiological Monitoring is . required for events classified as a SITE.or GENERAL EMERGENCY and should be considered as a precautionary measure during an ALERT.
; 2. If.the VAX Computer is'not. operational, dose projections may be made using EPIP 3.3a, " Manual Dose Projections".
b) Additionally, the Site Radiation Protection Coordinator shall pass on this information to .the OSC Supervisor and, at the same time, shall review the briefing information, as identified on Attachment 1, " Radiological tionttoring Team Briefing Topics", with the OSC Supervisor. c) -The OSC Supervisor shall insure that the Team members are appropriately dressed, have their required dosimetry, normally consisting of a 0-200 mrem and 0-5 Rem dosimeter and their TLD, and have checked out the operation of their equipment. f NOTE The Health Physics Technician from each Team shall ensure that portable instrumentation is within calibration and has been source checked. d) The OSC Supervisor should conduct the Team briefing, reviewing material previously discussed with the Site Radiation Protection
-Coordinator and dispatch the Teams to their vehicles.
l 4.1.3 'Upon' completing their vehicle checkout, including fueling the
- vehicle, if required, and loading their equipment in the vehicle, the Team should contact the OSC Supervisor and advise him of their readiness to be dispatched off-site.
NOTE
- 1. If for some reason an adequate number of functioning vehicles L cannot-be obtained, the OSC Supervisor should be advised, who in turn should advise the Site Radiation Protection Coordinator.
l
e s EMERGENCY PLAN' IMPLEMENTING PROCEDURE EPIP - 3.2 Page ,, 4 of 26 ,, 0FF-SITE RADIOLOGICAL MONITORING Revision 4 Date - 8/1/83 2.- The Emergency Coordinator may authorize the use of personal vehicles.:or if time permits, may elect to have.the Security and Support Supervisor coordinate with the Emergency Support Manager to secure additional vehicles. 4.1.4 'The Site' Radiation Protection Coordinator shall be advised by the OSC Supervisor of the readiness of the Teams.to be dispatched, and that responsibility-for further-Team communications _should be transferred i to the Radio Operator in the TSC. 4.1.5 Upon~ receiving authorization for dispatch from'the Emergency Coordinator, the Site Radiation Protection Coordinator should:
. a) Advise the Security and Support Supervisor that the Off-Site -
Teams are to be. dispatched. b) Instruct the Radio Operator to' advise the teams that they are under the control of the TSC and that all further communications are to be conducted with the TSC. c) Instruct the Radio Operator to dispatch the Teams to the preselected locations,. if still appropriate, ~or to an alternate location to either await further instructions for monitoring or to initiate monitoring activities. NOTE i The Security and Support Supervisor should coordinate egress , of monitoring teams .from DAEC with DAEC Security personnel and members of Local Law Enforcement Agencies, as appropriate.
-4.2 Plume Detection and Monitorino Precautions i
4.2.1 The_ presence of a radioactive plume should be detected by observing increasing count rates or dose rates on survey instrumentation in use. a) Upon observing an increase in count rates or dose rates, the Team should advise the TSC of their location and annotate their map to i, reflect the edge of the plume. b). Team members may elect to don their protective clothing and respiratory protection equipment. 4.2.2 To determine if the plume is on the ground, open and closed window surveys should be made.
~
- /
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 Page __ 5 of 26 : OFF-SITE RADIOLOGICAL MONITORING Revision 4 Date - 8/1/83 NOTE z For the E-140, place hand over the window for closed window surveys. a) A high open/ closed window ratio indicates that the team is in the plume. b) A low open/ closed window ratio indicates that the plume is overhead or is approaching the team. 4.2.3 Upon determining the presence of the plume on the ground,
contamination of the internal surfaces of the vehicle and of survey instruments can be minimized by:
a) Closing the vehicle windows; b) Placing the air conditioning system on Maximum. NOTE This will recirculate the air from the interior of the vehicle without adding any "make-up" air. 4.2.4 Once the Team has exited the plume: a) -The windows should be re-opened in an effort to purge the interior of the vehicle of any contamination which may be present. b) The map should be annotated to reflect the edge of the plume. c) Additionally, the map should be annotated to reflect the location and magnitude of the maximum dose rate observed while traversing the plume. 4.2.5 If abnormally high dose rates persist even after it is expected that the plume has been exited, perform a radiation survey of the vehicle. NOTE Caution should be observed near the air cleaner and radiator since as a result of their functions, they most likely will be the source'of the high radiation levels. a) Dose rates within the vehicle may be of sufficient magnitude to preclude use of the vehicle for further monitoring activities.
EMERGENCY PLAN IMPLEMENTING PROCEDURE 'EPIP- - 3.2 Page , 6 of 26 ,, OFF-SITE RADIOLOGICAL MONITORING Revision 4 Date.- 8/1/83 b) If s'uch is the case, the TSC (or EOF if control has been-transferred to the EOF) should be contacted regarding action to be taken. c) If continued use of the vehicle is desired for some period of time, it may be necessary to leave the vehicle to obtain accurate survey data.
-4.2.6 Unless othemise directed,-Off-Site Teams should stop and reverse their direction upon detecting radiation levels of 500 mR/hr.
a) Maps being used by the Team should- be annotated to identify. such location (s). b) The .TSC (or' EOF) should be advised of this situation and action being taken by the Team. 4.3. Radiological Monitoring hetivities 4.3.1 The Off-Site . Teams _ shall proceed to the initial off-site reference locations, as directed. a) Attachment 2, " Area Map", or a similar mn should be used to plan the travel route to the assigned location. b) Survey instrumentation should be operating on the lowest range available to enable initial detection of radioactivity. 4.3.2 Upon reaching the initial reference locations, the Teams shall report to the TSC and advise that they are standing by for further directions.- a) Off-site radiological monitoring will initially be accomplished under the direction of the Site Radiation Protection Coordinator. b) Upon activation of the EOF this responsibility will be assumed by the Radiological Assessment Coordinator. NOTE Instructions regarding coordination of this turnover are. contained in CPIP 2.1, " Dose Assessment and Protective Action. Reconsnendations". 4.3.3 ' The Off-Site Teams may be directed to change out the particulate filters and charcoal cartridges at the environmental monitoring stations located off-site in the downwind direction prior to, folicwing and/or during the time when a release is in progress. I
e a. EMERGENCY PLAN IMPLEMENTING PROCEDUREL - EPIP 3.2 , Page . - - 7 of 26 0FF-SITE RADIOLOGICAL MONITORING Revision 4 Date - 8/1/83 a) . If at all possible, all of the particulate filters and charcoal cartridges in the affected area (s) should be changed. b) Directions to each of the air samplers are provided in Attachment
- 3. "Off-Site Environmental Air Sample Station Locations".
NOTE Sample stations located on-site are identified in EPIP 3.1, "On-Site Monitoring". 4.'3.4 Upon being directed to proceed to another location-to perform
* - radiological surveys and/or obtain an air sample, action shall be taken as follows:
a) Record the date, time and locations, both "from " and "to" on Attachment 4, " Emergency Monitoring Log". b) Observe count rate or dose rate instrumentation and take precaution as specified in paragraph 4.2 if the plume is detected, c) Report radiological data as requested and provide additional radiological information which is pertinent; e.g. plume edge, maximum dose rates, etc. d) Record radiological monitoring results on Attachment 4. NOTE Instructions for obtaining air samples are provided in paragraph 4.4. 4.3.5 In addition to annotating maps-used by the Off-Site Teams to reflect plume edges as well as the location and magnitude of maximum dose < rates observed while traversing the plume, additional notations shall be made which reflect: a) Survey locations and results. b) Air sample locations and results. 4.3.6 Team members should be alert to local conditions or situations which may not be reflected on maps in use or which could not be anticipated by personnel involved in directing and controlling Team activities. a) Examples include locations of members of the public who appear to be remaining in high dose rate a'reas, accidents, isolated homes when further radiological surveys should be obtained, and the like.
*- v--- % --w-,-- in , , --- --, w, ,,-,n.. ,-, y- ..v..,,.w-, w , y- , ...%, ,.,-y- ,
EMERGENCY PLAN IMPLEMENTING PROCEDURE- EPIP - 3.2-Page 7- of - 26 0FF-SITE RADIOLOGICAL MONITORING Revislo'n4
-Date - 8/1/83 a) If at all possible, all .of the particulate. filters and. charcoal cartri.dges in the affected area (s) should be changed.
b)' ; Directions to each of the air samplers are provided in Attachment . 3, "Off-Site Environmental Air Sample Station Locations". NOTE , Sample stations located on-site are identified in EPIP 3.1, "On-Site Monitoring". 4.3.4! Upon being directed to proceed.to another location to perform e radiological surveys and/or obtain an air sample, action shall be taken as follows: a) Record the date, time and locations, both "from " and "to" on Attachment 4, " Emergency Monitoring Log". b) Observe count rate or dose rate instrumentation and take precaution as .specified in paragraph 4.2 if the plume is detected. c) Report radiological ' data as requested and provide additional radiological information which is pertinent; e.g. plume edge, maximum dose rates, etc. d) Record radiological monitoring results on Attachment 4. NOTE Instructions for obtaining air samples are provided in paragraph 4.4. 4.3.5 In addition to annotating maps used by the Off-site Teams to reflect plume edges as well as the location and magnitude of maximum dose rates observed while traversing the plume, additional notations shall be made which reflect:
- a) Survey locations and results.
b) Air sample locations and results. 4.3.6 . Team members should be alert to local conditions or situations which may not be reflected on maps in use or which could not be anticipated by personnel involved .in directing and controlling Team activities. a) Examples include locations-of members of the public who appear to be remaining in high dose rate areas, accidents, isolated homes when further radiological surveys should be obtained, and the like. ' 1 6 wr s- w == - 4 e w 29 g- m ,- - +-y- w- - = - - - - - . e w--w-- --ee--m==P w-*&y -
. .. I EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 Page ,, 8 of 26 ,,
~
OFF-SITE RADIOLOGICAL MONITORING Revision-4 Date - 8/1/83 b) This infomation including recommendations for further action should be reported to the TSC (or E0F). - c) Additionally, information' of this nature should be recorded by the Team. NOTE , Recording of information of this nature as well as recording of as much radiological information as is possible by the Off-Site Teams will weigh heavily during post accident evaluation of total man-rem exposure to the public.
. Consequently, off-site monitoring activities should be documented as well and as extensively as is possible.
4.3.7 Team members should periodically check their pocket dosimeters and ~ record the readings and time on Attachment 4, " Emergency Monitoring Log". 4.3.8 Team members should not exceed the DAEC Administrative exposure
~ limits unless authorized.
NOTE The mecahnics by which authorization is obtained for monitoring team members to increase their exposure levels is contained in CPIP 2.1, " Dose Assessment and Protective Action Recommendation". 4.3.9 While conducting surveys, Health Physics Technicians should take actions, as necessary, to minimize the contamination of survey equipment. 4.4 Air Samoling (Low Volume Samoles) 4.4.1 Load the air sampler with appropriate filters. NOTE Use of Silver Zeolite cartridges is' recommended when obtaining low volume air samples to detect radioiodines. 4.4.2 Perform a radiation survey on the radiator of the vehicle. 4.4.3- Raise the hood on the vehicle and leave the venicle running. 4.4.4 Connect the air sampler to the battery, ensuring the red lead goes to the positive terminal.
s . EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 Page 9 of 26 Revisio~n4 0FF-SITE RADIOLOGICAL MONITORING Date - 8/1/83 4.4.5 Turn the air sampler "0N".
~~
a) Take precautions to prevent contamination of the s' ampler, b)' The sampler should be held approximately waist high. 4.4.6 Obtain a 1, 5 or 10 cubic foot air sample, as instructed. NOTE Normally, a 10 cubic foot air sample will be obtained in those areas where dose rates are low, te; < 5 mr/hr. A1 e cubic foot sample will be taken if dose rates are high, ie; > 200 mr/hr. 4.4.7 Record information regarding the sample on Attachment 5, " Air Sample Identification". NOTE The filter paper and silver zeolite cartridge should be stored separately. 4.4.8 Remove the sample from the sampler, taking precautions to prevent sample contamination. a) Place the sample in a plastic bag, attach the Air Sample Identification label and seal the bag. b) Position the sample in the vehicle to minimize exposure. 4.4.9 Evaluate the filter cartridge with a portable survey instrument, determine the airborne activity concentration, record the results, and report same to the TSC (or E0F) as follows: NOTE . l Sample evaluation must be conducted in a low background area; therefore, the Team may be required to travel to another location in order to evaluate the sample. I a) Record the count rate or dose rate, as appropriate, using either an E-140 or an open window R0-2. l b) Using Attachment 6., " Air Activity Chart" convert the survey instrument reading to airborne activity concentration based upon the sample volume drawn. 4.4.10 Deliver samples as prescribed in paragraph a.6. I l
~
~
.1 l
l
e s EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 Page -. 10 of-26 .. : 0FF-SITE RADIOLOGICAL MONITORING Revision 4 Date - 8/1/83 4.5 Environmental Sanoling , 4 4.5.1 As directed by-the Radiological Assessment Coordinator, team members should initiate selected environmental sampling activities including the following: a) Surf ace Water Sampling in accordance with Environmental Sampling Procedure (ESP) E4.3-1.3.A,' " Surf ace Water Sampling". b) Milk Sampling in accordance with ESP E4.3-1.15, " Milk Sampling". c) Vegetation Sampling in accordance with ESP E4.3-1.8,
" Vegetation Sampling".
d) Soil Sampling in accordance with ESP E4.3-1.7,
" Soil Sampling".
NOTE It is expected that the contract firm responsible for DAEC's routine environmental sampling program would conduct the bulk
^*
of these activities. 4.5.2 Deliver samples as prescribed in paragraph 4.6. 4.6 Transportation of Samoles to the Off-Site Radiological. and Analytical Laboratory (ORAL)
.4.6.1 As directed by the Radiological Assessment Coordinator, environmental sample media should be transported to the ORAL by one of the following means:
a) Samples may also be taken directly to the ORAL by the monitoring teams, if they are operating in close proximity to the ORAL. b) Samples may be taken to a Traffic Control Point (TCP) (see Attachment 7, " Traffic Control Points") where they will be picked up by DAEC personnel and transported to the 0RAL. NOTE Based on the sequence of events or at the discretion of the Radiological Assessment Coordinator prudence may dictate deviation .from means mentioned in a) or b). If this is the
~
case samples should be delivered as directed by the Radiological Assessment Coordinator. e
~-
s . , EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 Page -- 11 of 26 ; 0FF-SITE RADIOLOGICAL MONITORING Revision 4 Date - 8/1/83 4.6.2 If samples were delivered to a.TCP, as mentioned in b) above, the mechanism for implementing this option, should be as f6110ws, a) Upon determining the need to-transport samples from the
. ' Monitoring Teams to the ORAL, the Radiological Assessment Coordinator should contact the ORAA Supervisor (if the ORAA is activated) or _the Site Radiation Protection Coordinator and request that he dispatch a " Sample Runner'.
b) The Sample Runner's name and badge number should be recorded in the appropriate Supervisors Log. 1 c) Prior _ to dispatching the Sample Runner, the ORAA Suoervisor or tha Site Radiation Protection Coordinator should ensure that, the Sample Runner has been properly briefed regarding:
- 1) TCP selected for sanple pick up.
NOTE The TCP designated for environmental sample media transfer should be selected such that it will minimize the amount of time the Monitoring Team (s) will have to suspend plume monitoring activities.
- 2) Route (s) recommended for travel to the TCP to avoid the plume.
- 3) Location of and traval route to the ORAL. (See Attachment'8,
" Travel Routes to the ORAL").
d) The Supervisor briefing the. Sample Runner should ensure .that he has his personnel dosimetery with him. In addition to his normal pocket dosimeter it is recommended that the sample runner also De
. given a 0-5R pocket dosimeter.
e) If one is available, a radio should be provided to the Sample
' Runner and a radio check conducted. !
f) The Radiological Assessment Coordinator should advise the Security and Support Supervisor in the TSC of the planned transport of samples to the ORAL, informing him of the same items mentioned in part c) of this paragraph. g) The Security and Support Supervisor should coordinate with Local Law enforcement Agency personnel to ensure that untimely delays at TCP are avoided. M
L-EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 Page - . 12 of 26 . . . 0FF-SITE RADIOLOGICAL MONITORING Revision 4 Date - 8/1/03 h) The Radiological Assessment Coordinator should advise the Monitoring Team (s) of the TCP selected for the trdnsfer of environmental sample media. i) Upon receiving authorization from the Radiological Assessment Coordinator the ORAA Supervisor should dispatch the sample runner, j) Once the Sample Runner and Monitoring Team (s) have reached the TCP, samples should be transferred to the Sample Punner's vehicle by the Monitoring Team Leader. Samples should be located in the vehicle such that the exposure to the Sample Runner will be
- minimized.
NOTE At all times the Sample Runner should avoid handling any samples. k) The Sample Runner should proceed to the ORAL to deliver samples. 4.6.2 Once at the ORAL samples should be handled by the ORAL Chemistry Technicians. 4.7 Documentation of Radiological Monitoring Data 4.7.1 Radiological monitoring data gathered at the off-site areas shall be recordedonAttachment4,"EmergentMonitoringfog". . . ,
- ~
4.7.2 Entries shall include the following information, as applicable: 2,
; /
a) Radiation levels in mR/hr or R/hr. . . _ ,
%' , i s
b) Airborne activity concentrations in uCi/cc. -- '
~
f c) location of survey. r ,
._r, d) Date and time of survey. '_ ' %- . .5 (( / , .
e , , , e) Identification of the Monitoring T'ehs members. *
,/
~
e ~~~- J . f) Initials of the individual recording the data. y ;-[ , j-
- ,.+.
g) Readings of pocket' dosimeter's worh d.uring the survey by Team, b-members. .,- - , <-< ' ; h) PertinentobservationsbyMonitor$ ean meders',' includin .'* ' physical hazards. - > ~ - '
)
I 7 l
. - - _ . - - , , , - - - - - .. ,,,y --.s...,
^
s . EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 Page,, 13 -of 26 ,,
~
OFF-SITE RADIOLOGICAL MONITORING Revision 4 Date - 8/1/83 4.7.3 ' 'The Emergency Monitoring Logs and any other pertinent notes should be provided to the OSC Supervisor upon returning to the plant and subsequently provided to-the Document Records Clerk in the TSC.
5.0 REFERENCES
5.1_ DAEC Emergency Plan . 5.2 NUREG 0654,' Rev. 1 6.0 ATTACHMENTS 6.1 Radiological Monitoring Team Briefing Topics 6.2. Area' Map 6.3 Off-Site Enviromental Air Sample Station Locations 6.4 Emergency Monitoring Log 6.5 Air Sample Identification 6.6-. Air Activity Chart.
~='c,
,~ ' 6.7' Traffic Control Points n, ,,
'; , 'fr.8 Trav515Ro es to the OR proved~~
By. -
,tTergiincy Pl .
//h)Lhg b ordi g Date: 9 43
/
,h. / / Approved By: (ktv .
Healtn Fnysics Supervisor -
=_v ^ Date: 9[A9 f M fI ,
/~ .
Approved By: J M2d ., Date: 5'd <.7 5 l Radiation Protection. Supervisor Reviewed By: 4 Date: 7 9 - 5~ h ALARA Coo vn,ator. O g h ,. p Reviewed By: */ @M
! Date: 9-3d-82 J ' taairntani ,0perations Commitrea
, N :s - ;
$ ,);
Q 3 0 'S '3 h(( , Approved By: - t .
- Date.
Plant hgerintencent - t6tcjear
!, .. . /'
, n ,. . .-.- -
> ~
I,'" ' s a /, , L/
- v h-.
'h I f,,.
4 ~L, uu v_t - - j, _ _ _, j:W
,, _,n _ ._, _ _ ._
e 3;
- _
mi. EMERGENCY. PLAN IMPLEMENTING PROCEDURE EPIP - 3.2
- Page -- 14 of 26 .:
OFF-SITE RADIOLOGICAL MONITORING Revision 4 Date - 8/1/83. ATTACHMENT 1 , RADIOLOGICAL MONITORING TEAM BRIEFING TOPICS y 1. Meteorological Information, including: Hind speed . Wind direction ~
- 2. Radiological Information - if a release is in progress:
Release Point
- Release rate Projected-dose rates at preselected locations Plume width Affected sectors / area
- 3. Location to which Teams will initially be dispatched, routes to be used to avoid
, radiological hazard -areas if such exists, and tasks to be accomplished.
- 4. Plant status, problems and. to the extent capable of being projected, the duration of time until either a release begins or is stopped.
~5. : Documentation requirements.
' 6.' Protective measures to be employed.
- 7. Reporting requirements, including, for example:
Radiation survey readings Airborne sample estimates Unusual or unexpected problems or situations which may' impact the ability to perform monitoring functions . Observations of actions taken by local, State or Federal assistance groups or l the public
- 8. Location (s) for delivery of samples.
- 9. Precautions to be observed upon enteriq the plume and as appropriate, in high
[. . radiation fields.
- 10. Communications protocol to be observed under normal and " emergency" situations.
- w. _
y , L' _if
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 Page 15 of 26 0FF-SITE RADIOLOGICAL MONITORING Revision 4 - Date - 8/1/83 ATTACHMENT 2 4 "* \; a A 2 7 ., . q. ..
.\ :r. ,
. .r".
, , , 2 ,
./.
4 .
=
l ! kl l k l,,/.hl ~;h @ ,l },j, d@'l (( , l l x xiw s w.os~ s
.,y q s :, VI I l i l
s n u .s ,% . . J l II II l= _= I I -I*1, NMLMs P}7*?/ JAW /0 l IIM6W.7@thip. ' k l I li Q A., tA:M> . is% ._
. . . . ~
% g kR~, llN q. g~rx.'.f.._Q_. T . . . , - f_ _
k , II MhC7S i %. 3 D i4 %4L.;3K'G E lVd N .
?MWM C & M24%:2*GWALW./I3 T-
_I N .h.:.d:ti..si. i
% ? $ ! N K 7$b%;ggjgTr /' Q. % M $ 5 % [ M c $
_i P MMW%1 \' /sfeM@ d, ) U
.tus.q
- p. a, tsw pc/ryz 3 yL. : - . -
y p mj .u g--q p. .,A;. ,. 4. . lC W..,. . l~ m ;=li N O @ M .'w a
= s I'$@e.4 I It. A l
=- - *
. o g i.3 "
_J L , L.NWX w%$$EMWNJMM?g! i . W@ .L 4. -X 12
- h py R W @i g gnaRE varJ']i 1 @ W / l e LF3 l
' % [G ' / -
l . _i .th . ./s_ _
- f. 3 af Cet ..M_?
9 /~Q, h,, w. M5.= ms -af w w Q"n"(,
-1 " . I Yl kk_ k ? ~ b k, R W % b s$%( M$= j-
'* l sl [ tnt:mys%h % Qa_mz N_
i l I o i =rMEJ T ~,t b1Cf m!' M l ! igtv- Al ie M . M 7.TO E M M-ym ;el2= =r .;I- - A 7 ;: ._ -g. ;;;. 7-- l -5Eih. S: , ,, - w e - w- ....-3 f ,- .
-'-'d ( ,;_,,E!
..i. . J-. /
I
'@l h ' . k 1..fI' T' '
Te; j; jpFt,,,*,,, ! \I i y\j[M," C=2, U k-h _ l, I / l. .@ 3 i , ,,,, If I l i\ ! ! , ! s .'=-N Yi-;c=, *
. . = = ,- =_ y ?
o
= 4 eg 9 7,
? .* y= ==
..=~
. e EMERGENCY PLAN IMPLEMENTING PROCEDURE- EPIP - 3.2
- Page -- 16 of 26 t OFF-SITE RADIOLOGICAL MONITORING Revision 4 Cate - 8/1/83 ATTACHMENT 3 ,
OFF-SITE ENVIRONMENTAL AIR SAMPLE STATION LOCATIONS
. Area 3 Sampler #6 (TLD # 6)
Center Point Station At 4 Corners, leaving the DAEC, turn right onto W36. Remain on W36 for approximately 9 miles to Center Point, crossing the Cedar River at Lewis Access.
- At T inters.ection in Center Point, turn right onto Tr-der Street. Go 2 blocks on Trader Street to Main Street. Turn left onto Main Street and continue on Main Street for 8 blocks. Turn right onto Vine Street. Travel to stop sign, turn left onto Franklin Street. Go 1/4 mile and then turn right onto Grubbs Street (E-16).
Continue on Grubbs Street (E-16) for approximately 1/4 of a mile. Turn rignt off Grubbs Street (E-16) just past substation into driveway. Air Sampler is located' on the south side behind the substation. Sampler #14 (TLD # 14)
-Substation on E-16 From Center Point Station, continue East on E-16 approximately 51/2 miles, passing the Alice Church. The substation is located at the intersection of E-16 and W-45 county roads. .(Watch for sign for Troy Mills and Central City turnoff.)
Air Sampler is located at substation on the right (south) side of E-16. Sampler 713 (TLD # 13) Alburnett Samoler From E-16 and W-45 intersection (location of substation on E-16), continue east on E-16 for 3 miles. Turn right onto W-58 and follow W-58 south for 3 miles to Alburnett. Enter Alburnett on Main Avenue. Take the 1st left onto North Street. Follow North Street around the curve. Air Sampler is located on the left hand side of street on a power pole with street light attached. The pole is located approximately 15 ft. from edge of road before the railroad crossing. Sampler #11 (TLD # 11) Toddville Samoler Take W-58 (Main Ave.) south through' Alburnett. Travel 4.5 miles on W-58; turn right on E-34. Travel approximately 3 miles on E-34 to stop sign at intersection l of Hignway 150 and E-34. Go straignt on E-6W to Toddville. Enter Todaville, staying on E-6W, cross the bridge. Air Samole is located one block from bridge on the rignt hand side of E-6W on power pole.
.I
EMERGENCY PLAN IMPLEMENTING PROCEDURE -EPIP - 3.2 Page 17 of 26
~
Revisio'n 4 'I 0FF-SITE RADIOLOGICAL MONITORING Date - 8/1/83 ATTACHMENT 3 (Continued)
~
0FF-SITE ~ ENVIRONMENTAL' AIR SAMPLE STATION LOCATIONS Area 4 Sampler #4 (TLD # 4) . Samoler at Don Johnson's House Leave Palo on 1st Street. . Turn left onto Highway 94. Follow Highway 94 for approximately .8 mile. Take a left onto Chain Lakes Road (E36). Follow Chain
& Lakes Road until you come to a T. Turn right at T. Go approximately 1/4 of a a mile and then turn. at first left onto another gravel road. Follow gravel road to first intersection (approximately 1/2 mile). Take a right at T intersection. Don Jonnson's home is the 3rd residence on the left hand side of road (.1 mile from intersection). Turn left into driveway. Air Sampler is located on a power pole on right side of driveway.
Sampler #11 (TLD # 11) Toddville Samoler Take a left out of Don Johnson's driveway. Go .5 mile to 4-way intersection. Take a left at intersection. You are now on E6W. Follow E-6W for approximately 2.5 miles. Take a right at T intersection remaining on E6W. Follow E6W for approximately 1 more mile. At the T intersection, take a right. Air Sampler is located on a power pole 2 blocks from T intersection on the left side of E-6W. Sampler #3 (TLD # 3) Hiawatha Sampler Follow E6W through Toddville - heading North. Take a rignt at intersection of E6W and Highway 150. Take 150 to Blairs Ferry Road. Turn right, heading West, ento Blairs Ferry Road. Follow Blairs Ferry Road to 6th Ave. Turn right onto 6th Ave. . Go 1 block to intersection of 6th Ave. and Willman St. Air Sampler is located l within concrete building at Substation. Must enter througn locked door on east side of concrete building using a canpany key. l t l l
~
p i .*
, a EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 Page -- 18 of 26 ..
OFF-SITE RADIOLOGICAL MONITORING Revision 4 Date - 8/1/83 ATTACHMENT 3 (Continued) , OFF-SITE ENVIRONMENTAL' AIR SAMPLE STATION LOCATIONS Area 5 Sampler #1 (TLD # 1) Prairie Creek Substation From I-380 and Wilson Avenue interchange, take I-380 South to 30E intersection. Take 30E to C Street Road Exit. Go North on C Street Road, pass FMC
* (approximately 1 mile) to Central lowa Power Coop, IE Light and Power (Prairie Creek). Go to Guard Gate and through gate to reach sampler. Facing guard gate, Air Sampler is located on right side, on fence, approximately 50 yards from guard gate.
Sampler #3 (TLD # 3) Hiawatha Sampler From Prairie Creek Substation, take C Street to Highway 30W to I-380 north. Take I-380 north to Blairs Ferry Road Exit. Take Blairs Ferry Road west to 6th Avenue. Turn right onto 6th Avenue. Go 1 block to intersection-of 6th Avenue and Willman Street. Air. Sampler is located within concrete building at substation. Must enter through locked door on east side of concrete building using a company key. Sampler #2 (TLD y 2) Marion Substation' From Hiawatha Sampler, reverse direction and return to Blairs Ferry Road. Take Blairs Ferry Road east, crossing Council Street, C. Avenue and 8th Avenue, to T stop (Blairs Ferry Road and Marion Blvd.) . Thomas Park is located at T. Turn left onto Marion Blvd. Turn right at 1st stop light onto ist Street. Turn left from ist Street onto 3rd Avenue. Continue on 3rd Avenue to lith Street. Turn right onto lith Street. Take lith Street 1 block to 2nd Avenue. Air Sampler is locked l-in the substation; use company key. l l l l l ~ i .;
i . EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 Page ,, 19 of 26
.7 0FF-SITE RADIOLOGICAL MONITORING Revision 4 Date - 8/1/83 ATTACHMENT 3 (Continued) 0FF-SITE ENVIRONMENTAL AIR SAMPLE STATION LOCATIONS Area 6 Sampler #5 (TLD # 42)-
Palo Substation At 4 Corners near DAEC, turn left. Enter Palo on lst Street. Go through town on 1st Street, crossing the bridge. Take right on gravel road after bridge and before Tri-County Dairy. Substation located on right. Sampler locked in
. substation; using company key.
Sampler #7 (TLD # 7) Shellsburg Substation leave Palo on 1st Street; turn right onto Highway 94 Stay on Highway 94 for 4 miles. Turn right onto W26. Take W26 for approximately 2 miles to Shellsburg. In Shellsburg, turn left onto Commercial Street. Sampler is located on a utility pole on the left hand (south) side of Commercial Street. The pole is located across the street from the concrete silos near the end of Com' m ercial Street. Sampler #10 (TLD # 10) Atkins Substation From Shellsburg Sampler on Commercial Street, reverse direction, taking Commercial Street to W26. Turn right onto W26. Take W26 south approximately 7 miles to Atkins. Turn left at stop sign at intersection of W26 and E44 Take E44 into Atkins. Turn lef t onto Main Street at stop sign. Go 3 blocks north. Turn left onto ist Street. Remain on 1st Street for approximately 3/4 of a block; turn left at the Water Tower. Air Sampler is located on the right side of sidewalk on a utility pole, directly north of the water tower. l l I l l 1
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 Page -. 20 of 26 : OFF-SITE RADIOLOGICAL MONITORING Revision 4 Date - 8/1/83
~
ATTACHMENT 3 (Continued) . 0FF-SITE ENVIRONMENTAL AIR SAMPLE STATION LCCATIONS Area 7 - Sampler #7. (TLD # 7) Shellsburg Leave Palo on 1st Street; turn right onto Highway 94. After 4 miles,- turn right onto W26. Take W26 for approximately 2 miles to Shellsburg. In Shellsburg, turn
- left onto Commercial Street. Sampler is located on a utility pole on the left hand (south) side of Commercial Street. The pole is located across the Street from the concrete silos near the end of Canmercial Street.
Sampler #9 (Tid # 9) To Urbana From Shellsburg, Sampler continue on Commercial Street to Canton Street. Turn right onto Canton Street. _ Follow Canton Street which becomes W26. Take W26 north out of Shellsburg heading toward Urbana. Continue on W26 for 4.5 miles, passing church on left hand side of_ road. Turn right onto gravel road. Air Sampler is located on right hand side of gravel road on the 1st utility pole from the corner. Sampler #8 (TLD # 8) Urbana
'From Air Sampler #9, continue north on W26 for approximately 4.6 miles to Urbana.
Turn right at stop sign. Turn left at Urbana Christian Church, heading towards Center Point on E2W. Follow E2W .to the 1st cemetery on right hand side of road. . Air Sampler is located on utility pole near main gate of cemetery. Sampler #6 (TLD # 6) Center Point From Urbana Sampler, continue on E2W (Center Point blacktop) for 5 miles to Center Point, crossing I-380 en route. Enter Center Point on Green Street. Turn left at first_stop sign onto Main Street; go 2 blocks north on Main Street. Turn rignt onto Vine Street. At stop sign turn left onto Franklin Street. Go 1/4 mile on Franklin Street; turn right onto Grubbs Street (E-16). Follow E-16 for approximately 1/4 of a mile. Turn right off of E-16 just past substation into driveway. Air Sanpler is located on the south side behind the substation. t s
~
O,
, .g EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP -
3.2 Page . 20 ~of 26 , OFF-SITE RADIOLOGICAL MONITORING Revision 4 Date - 8/1/83-ATTACHMENT 3 (Continued) . 0FF-SITE ENVIRONMENTAL AIR SAMPLE STATION LOCATIONS Area 7 Sampler #7 (TLD # -7) . Shellsburg i
' Leave Palo on 1st Street; turn right onto Highway 94. After 4 miles, turn right onto W26. Take W26 for approximately 2 miles to Shellsburg. In Shellsburg, turn
.* left onto Commercial ^ Street. Sampler is located on a utility _ pole on the lef t hand (south) side of Commercial Street. The pole is located across the Street from the concrete silos near the end of Commercial Street.
1 Sampler #9 (Tid # 9) To Urbana-From Shellsburg, Sampler continue on Commercial Street to Canton Street. Turn right onto Canton Street. Follow Canton Street which becomes W26. Take W26 north out of Shellsburg heading toward Urbana. Continue on W26 for 4.5 miles, passing church on left hand side of road. Turn right onto gravel road. Air Sampler is located on right hand side of gravel road on the 1st utility pole from the corner. Sampler #8 (TLD # 8) Urbana From Air Sampler #9, continue north on W26 for approximately 4.6 miles to Urbana. Turn right at stop sign. Turn left at Urbana Christian Church, heading towards Center Point on E2W. Follow E2W to the 1st cemetery on right hand side of road. Air Sampler is located on utility pole near main gate of cemetery. Sampler #6 (TLD.# 6) l i Center Point From Urbana Sampler, continue on E2W (Center Point blacktop) for 5 miles to Center
. Point, crossing I-380 en route. Enter Center Point on Green Street. Turn left at first stop sign onto Main Street; go 2 blocks north on Main Street. Turn right onto Vine Street. .At stop sign turn left onto Franklin Street. Go 1/4 mile on Franklin Street; turn right onto Grubbs Street (E-16). Follow E-16 for
~
l approximately 1/4 of a mile. Turn right off of E-16 just past substation into
- driveway. Air Sampler is located on the south side benind the substation.
e O ip-*n ><pr- .y w a m-e 4+y wre-.m----,e--w y r-*y-m , - - -i y ys ,-y-s #4y wg.p g m 79, q.--yy e--v+- tt4- T -w w
i mxmm M 2o< O hz zmgxm24
- xD mxomg:c lr m*Q T I 4N
(* Oo3D D4( NH oN $ n E 4m x y oroD - g2-( 2o=~ ox 2O 3 . o1, - - :(<an4Os 2D u- A oDt(ot p o 3 4 cNH%0w 2,44=_19xm21- a s k r a F) m e I I t c ___ R e
/
I' l . . IC t e A( C u_ la a
- eN o I
f t l a I I 5 l p m _ e _ a l S . . p ) e m ) r s a e i 8t S Vi A V ( r i A C I
- w o
m d -
- n
" i I
I
" W d
e
- s o
H w l A o C L d I i n W s n G U L i g n I N- _ - - - - - - O e p d G t t 4 l R a e I t- _ - - -
- - - l s
a i y i l l r e s v r m _ l t l e _ i ol e m I t n e - . H i I Y s o I g- _ - - -
- - - _ 9 C D d
s _. t- - l E Gt i l a n I _ - - - -
. - _ i g
n . t o d - i s e a l [ r m e - e l R P I n H o d e a n u R i o D t . l a l a _ m a v , r C i o r f r n e A _ i
. l m _
t o i h _. n N c
) ) e t
~
g H s l a _. T I es a p ( ( r i s _ t r i ~ . r r s e D ~ . e e n S ~ d b I a m n a ~ e e y o l l M e i ~ a v e t m m r p a a u y c a e e S T o n e T f L r f i e s'
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 ' Page 22 of 26 ^ 0FF-SITE RADIOLOGICAL MONITORING Revisio~n4 Date - 8/1/83 ATTACHMENT 5
~
AIR SAMPLE IDENTIFICATION AIR SAMPLE SAMPLE LOCATION
- 'DATE/ TIME ON /
DATE/ TIME OFF / SAMPLE FLOW RATE CFM SAMPLE COLLECTED BY m
. EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 P age , , 23 Of 26 ,,
OFF-SITE RADIOLOGICAL MONITORING Revision 4 Date - 8/1/83 ATTACHMENT 6 AIR ACTIVITY CHART E 140 or R0-2 COUNT COUNT ~ COUNT itA7E RATE l l
'fCPM Ift3 Sft3 10ft3 fC N Ift3 Sft3 10ft3I lf RATE CN I Ift3 I Sft3 10ft3 100 3.18E-8 5.36E-9 3.1SE-9 57C0 1.31E-6 3.63E-7 1.31E-7 23K 7.32E-6 1.45E-6 7.32E-7 200 6.36E.8 1.27E-8 5.36E-9 5800 1.35E-6 3.69E-7 1.85E-7 24K 7.54E-6 1.53E-6 7.64E-7 350 9.54E-8 1.91E-8 9.54E-9 59C0 1.33E-6 3.75E-7 1.33E-7 25K 7.95E-6 1.59E-6 7.95E-7 400 1.27E-7 2.54E-8 1.27E 8 5000 1.91E-6 3.32E-7 1.91E-7 25K 8.27E-6 1.65E-6 3.27E-7 SCO 1.59E-7 3.15E-8 1.59E-8 6100 1.94E-6 3.88E-7 1.94E-7 27K 8.59E-6 1.72E 3.59E-7 600 1.9CE-7 3.3H-8 1.9CE-8 6200 1.97E-6 3.94E-7 1.97E-7 23K 8.91E-6 1.75E-6 3.91E-7
- 700 2.22E-7 4.45E-8 2.23E-8 6300 2.0CE-6 4.0CE-7 2.00E-7 29K 9.23E-6 1.35E-6 9.23E-7 800 2.54E-7 5.09E-8 2.55E.8 6400 2.04E-6 4.07E-7 2.04E-7 3CK 9.54E 6 1.91E-6 9.54E-7 900 2.86E-7 5.72E-8 2.3EE-8 6500 2.07E-3 4.14E-7 2.07E-7 31K 9.35E-6 1.97E-6 9.35E-7 1000 3.1sE-7 6.3EE-8 3.18E-8 6600 2.1CE-6 4.2CE-7 2.10E-7 32K 1.01E-5 2.04E-6 1.02E 6 1100 3.49E-7 6.99E-8 3.5CE-8 57C0 2.13E-6 4.25E-7 2.13E-7 32K 1.0$E-5 2.1CE-6 1.05E-i t -1200 3.81E-7 7.64E-8 3.821-S 5800 2.16E-6 4.33E-7 2.1SE- 7 34K 1.03E-5 2.15E-6 1.08E-6 1300 4.13E-7 8.27E-8 4.14E-8 6900 2.20E-6 4.39E 7 2.20E-7 35K 1.11E-5 2.235-6 1.11E-6 1400 4.45E-7 S.915-8 4.45E-8 7000 2.23E-6 4.45E-7 2.23E-7 36K 1.15E-5 2.29E-6 1.15E-6 1500 4.77E-7 9.54E-8 4.77E-8 7100 2.25E-6 4.52E-7 2.25E-7 37K 1.13E-5 2.35E-6l1.13E-6 1600 5.09E-7 1.02E-7 5.09E-8 7200 2.29E-6 4.58E-7 2.29E-7 38K 1.215-5 l 2.41E-631.21E-5 1700 5.4CE-7 1.0SE-7 5.41E-8 7300 2.32E-6 4.64E-7 2.33-7 39K 1.24E-5 2.48E-6 1.24E-6 1800 5.73E-7 1.15E-7 5.73E-8 7400 2.35E-5 4. 71E-? 2.35E.7 4CK 1.27E-5 2.54E-6 1.27E-6 1900 6.04E-7 1.21E-7 6.04E-8 7500 2.39E-6 4.77E-7 2.39E-7 41K 1.30E-5 2.51E-6 1.30E-6 2000 5.36E-7 1.27E-7 6.35E-8 7500 2.41E-6 4.34E-7 2.42E-7 42K 1.34E-5 2.57E-6 1.34E-5 2100 6.68E-7 1.34E-7 6.68E-8 7700 2.45E-6 4.9CE-7 2.45E-7 43K 1.38E-3 2.74E-6 1.37E-6 2200 6.99E-7 1.39E 7 6.99E-8 7800 2.48E-6 4.96E-7 2.4aE-7 44K 1.40E-5 2.30E-6 1.40E-6 2200 7.31E-7 1.46E-7 7.32E-6 7900 2.51E-6 5.03E-7 2.51E-7 45K 1.43E-5 2.35E-6 1.4 3E 2400 7.53E-7 1.52E.7 7.64E-8 2000 2.55E-6 5.09E-7 2.55E-7 46K 1.46E-3 5 93E-6 1.46E-6 2500 7.95E-7 1.59E-7 7.95E-8 3100 2.53E-6 5.15E-7 2.58E-7 47K 1.5CE-5 2.99E-6 :1.50E-6 2500 8.27E-7 1.65E-7 8.27E-8 3200 5.22E-7 2.51E-7 48K 1.53E-5l3.0!E-6L1.53E-6 2700 8.53E-7 1.72E-7 3.59E-3 3300 2.51E-6}5.23E-7 2.54E-61 2.54E-7 49K 1.55E-513.1M-6l1.55E-6 2S00 . 3.9CE-7 1.72E-7 S.91E-8 8400 2.57E-6 !.34E-7 2.67E-7 SCK ' 1.59E-513.13E-6il.59E-6 2900 9.22E-7 1.SEE-7 9.23E-8 8500 2.70E-6 5.40E-7 2.70E-7 51K 1.521-5l3.25E-611.52E-6 3000 9.54E-7 1.91E-7 9.54E 8 3600 2.74E-6 5.47E-7 2.74E-7 52K 1.!!E-Si3.31E-6l1.55E-6 3100 9.35E 7 1.97E 7 9.35E-8 3700 2.77E-6 5.54E-7 2.77! 7 53K 1.59E-5 3.37E-6 1.59E-6 3200 1.01E-6 2.04E 7 1.02E-7 3300 2.3CE-6 5.5CE-7 2.30E-7 54K 1.72E-5 3.43I-6 1.72E-6
[ 2300 1.04E-6 2.10E-7 1.05E-7 8900 2.33E-6 5.66E-7 2.33E-7 55K 1.75E-5 3.49E-6 1.75E-6 3400 1.CSE-6 2.15E-7 1.08E-7 90C0 2.36E-6 5.73E-7 2.36E-7 56K 1.73E-5 3.56E-6 1.75E-6 3500 1.11E-6 2.23E-7 1.11E-7 9100 2.89E-6 5.79E-7 2.90E-7 57K 1.31E-5 3.63E-6 1.31E-6 3600 1.14E-6 2.29E-7 1.15E-7 9200 2.92E-6 5.85E-7 2.93E-7 53K 1.35E-5 3.69E-6 1.85E-6 3700 1.17E-6 2.35E-7 1.1SE-7 93C0 2.96E-6 5.92E-7 2.96E-7 59K 1.38E-5 3.*5E-6 1.33E-6 3800 1.2CE-6 2.421-7 1.21E-7 9400- 2.99E-6 5.98E-7 2.99E-7 50K 1.91E-5 3.3 3-6 1.91E-6 l 3900 1.24E-6 2.48E-7 1.24E-7 95C0 3.02E-6 5.04E-7 3.02E-7 61K 1. 94 E- 5 3.SSE-6 1.94E-6 4000 1.27E-6 2.54E-7 1.27E-7 9500 3.05E-6 6.11E-7 3.0!E-7 62K 1.97E-5 3.94E-6 1.97E-6
- 4100 1.3CE-6 2.511-7 1.3CE-7 9700 3.03E-6 5.17E-7 3.09E-7 53K 4.01E-612.0 3 6 4200 1.33E-6 2.67E-7 1.34E-7 98CC 3.12E-6 5.24E-7 3.125-7 54K 2.00E-5l4.07E-6l2.04E-6 2.04E-5, 4300 1.35E-6 2.74E-7 1.37E-7 9900 3.15E-6 5.3.E-7 3.15E-7 55K 2.07E-5 4.14E-612.07E-6 4400 1.40E-6 2.79E-7 1.4CE-7 1CK 3.18E-6 5.36E-7 3.15E-7 56K 2.10E-5 4.20E-612.1;E-6 4'QO 1.43E-6 2.35E-7 1.43E 7 11K 3.5CE-6
- 5.99E-7 3.50E-T 57K 2.1 E-5 4.25E-612.13!-6 48v0 1.46E-6 2.9;E-7 1.46E-7 12% 3.321-617.54E-7 3.3M-7 52K 2.16E-564.3:E-612.15E-i 4700 1.5CE-6 2.99E-7 1.49E-7 13K 4.14E-6l3.2;E-7 4.14E-T h 59K 2.20E-514.39E-6l2.0 % 6
, 4800 1.52E 6,3.0!!-7 1.53E 7 14K 4.45E-618.91E-7 4.45E-71l m 2.23E.5t4.*5E-M 2.22E-6 4900 1.56E-6 3.13-7 1.55E-7 15K 4.775-611.54E-7 ::a, e ae ::.-o 5. . .:-n m : - 50C0 1.59E-6 3.15E-7 1.59E-7 15K 5.09E.6 1.03 -6 4.77E-7Il*0-A/5c!3.15E-566.35E-613.3E-6 5.09E-71 51C0 1.621 6 3.2fE-7 1.52E-7 17K 5.41E-6 1. !E-615.41E-7111 -A a r 3.3:E-567.54E 6i3.3 5-6 5200 1.65E-6l 3.31E 7 1.55E-7 15K 5.7;E-6 1.15E-615.73E-7!!15d /hr 4.77E-5i!.54E-6 4.7'I-6 1:00 1.59E-613.37E-7 1.69E-7 19K 6.04E-6 1.21E-6l6.04E-7 j:0-A/5r 5.25E-Sil.27E-5 6.25E-6 5400 1.72E-6 3.44E-7 1.7:1-7 20K 5.26E-6 1.27E-615.35E-7 .2!M/9r7.95E-5h.59E-5t'.ME-6 550C 1.*5E-6 3.50E-7 1.7?E-7 21K 6.5 5! 6 i ' .34E-6 l6.5 5E-7. ! 20-A /*tr 9.5 4E-5 i '. 91E-S l9.5 2E-6 5600 1.78E-6 3.56E 7:,1.73E-7l 22% 6.99E-6l1.40E-6l6.99E-7ll50rA/hr 1.59E-4{3.15E-5l1.59E 5 l L ApplicaDie for Open window measurements at contact with a Silver ZeClite Cartridge (Ci/m3 or uCi/cc) ,f
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 Page ,,L24 of.26 ,, OFF-SITE RADIOLOGICAL. MONITORING Revision 4 Date --8/1/83 ATTACHMENT 7
-TRAFFIC CONTROL POINTS
- TCP-1 3 miles north of Center Point on Hwy #150 and 2 miles east.
TCP-2 3 miles east of Center Point on county E-16 and 3 miles north. TCP-3 4 miles east.of Center Point on County.E-16 and 3 miles north. TCP-4 5 miles east of Center Point on County E-16 and 1 mile north. TCP-5 6 miles ~ east of Center Point on County E-16. TCP 6 1/4 miles east of Center Point on County E-16 and 1 mile south. TCP-7 11/2 miles west of Alburnett and 11/2 miles north. TCP-8 West edge of Alburnett on County Road. TCP-9 South of Alburnett on County W-58 to first road west. TCP-10 1 mile sout, of Alburnett on County W-58. TCP-11 2 miles scutn of Alburnett on County W-58 and 1 mile east. TCP-12 3 miles south of Alburnett on County W-58 at the junction of County W-58 and County E-34. TCP-13 3 miles south of Alburnett on County W-58 and 1 3/4 miles east. TCP-14 2 1/2 miles north of the junction of Hwy #151 and Hwy #13 at the junction of County W-60 and Hwy #13. TCP-15 11/2 miles north of junction Hwy #151 and Hwy #13 on Hwy #13. TCP-16' 1 mile north of junction Hwy #151 and Hwy #13 on Hwy #13. TCP-17 Junction-of Hwy #151 and Hwy #13. i- TCP-18 31/2 miles north of the junction Hwy #13 and Hwy #30 on Hwy #13 at junction of County E-48 and Hwy #13. l TCP Junction Hwy #13 and Hwy #30. TCP-20 Southeast edge of Cedar Rapids at the junction of County W6E and Hwy 430. TCP-21 1 mile east of the junction of Hwy #218 and Hwy #84 on County E70 at the junction of County E-70 and County W-54. TCP-22 Junction of I-380 and. Hwy #30. TCP-23 Junction of Hwy #84 and Hwy #218. . TCP-24 2 miles west of Hwy #218 on Hwy #84 at the junction of Hwy #84 and County E-66. TCP-25 1 mile southeast of Cedar Rapids on Hwy #149 at its junction with Beverly Road. TCP-26 West edge of Cedar Rapids on Hwy #30 and Stoney Point Road. TCP 2 miles northeast of Cedar Rapids on Hwy #94 at its junction with County E-44
-TCP-28 1 mile west of Cedar Rapids on Hwy #30 and 13/4 miles north.
TCP-29 1 mile west of Cedar Rapids on Hwy #30 and 1 mile north. TCP-30 2 miles west of Cedar Rapids on Hwy # 30. TCP-31 3 miles west of Cedar Rapids on Hwy #30. TCP-32 4 miles west of Cedar Rapids on Hwy #30. TCP-33 1 mile south of Atkins on Hwy #279. TCP-34 1/4 mile west of Atkins on E-44 at the junction of E-44 and W-26. TCP-35 1 1/4 miles west of Atkins on E-44 and 1 mile north. TCP-36 2 1/4 miles west of Atkins on E-44 and 2 miles north.
- Meteorological conditions will determine direction of travel, and manning of traffic control points.
O
EPIP - 3;2
~
EMERGENCY PLAN IMPLEMENTING PROCEDURE Page - - 25 of 26 - 0FF-SITE RADIOLOGICAL MONITORING Revision 4 Date - 8/1/83 ATTACHMENT 7 - TRAFFIC CONTROL POINTS
- i TCP-37 2 miles east of Newhall on E-44 and 3 miles north.
TCP-38 1 mile east of Newhall on E-44 and 4 miles north. TCP-39 6 miles north of Newhall on County W-14. TCP-40 7 miles north of Newhall on County W-14 at the junction of W-14 and E-30. TCP-41 8 miles north of Newhall on County W-14. TCP-42 9 miles north of Newhall on County W-14
-TCP-43 2 miles southeastLof Vinton on County E-24 at the junction of E-24 and W-14.
TCP-44 3 miles southeast of Vinton on County E-24 and 1 mile north.
-TCP-45 1 mile south of Urbana on W-26.
TCP-46 'l mile southeast of Urbana on E2W. TCP 1 mile northwest of Center Point and one mile north. TCP-48 21/2 miles north-of Center Point on Hwy #150 and 1 1/2 miles west. TCP-49 2 1/2 miles north of Center Point on Hwy #150. 1 I f I - ? .** I
. - - , ~. .. . . . - - . . _ . . - _ _ _ . _ _ _ , - . - . - . - _ . . . _ . , , - - , _ _ - -
W EMERGEHCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 Page 26 of 26 2 0FF-SITE RADIOLOGICAL MONITORING Revisfoh 4 Date - 8/1/83 ATTACHMENT 8 TRAVEL ROUTES TO THE ORAL bk%s s. EDGEWOOD RD. s
\
ELUS BLVO 380 TTAVE IST AVE i
' \.. I t". 2NDNE
\ TOWER 0 \ 3RD AVE 19TH STR M TO DAE '
10 TH STR
; [AW
' N, 1 \ MT VERPCN 8
JCHNSCN AVE ( f, 8I"[$TR 7 v' -3RD STR
/ eT9 ave _-AyosSr.\ '1 33, izm ave ' -
mmAvr t4r T# Mi m Ta ave - i' ;w WA ' l
/ wtLSCN AVE 7
[/ - .sTw "ewtm Sm l [ N l 380 ORAL & CCE. 101712TH AVE SW PHONE *. 399-7885 l- 398-76E6 i I O, I
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 3.3b Page 1 of 16 Computerized Dose Projections Revision 4 ~ ~ ' ! Date 8/2/83 1.0 PURPOSE This procedure describes the use of the IDP and EOF dose projection programs for calculating the downwind dose rates resulting form radioactive releases following an emergency- at DAEC. - NOTE USE OF THE MANUAL DOSE PROJECTION METHOD IS DESCRIBED IN EPIP 3.3a, " MANUAL DOSE PROJECTIONS". 2.0 APPLICABILITY e This procedure will be used by the Site Radiation Protection Coordinator,
' the Radiological Assessment Coordinator and by other emergency response personnel assigned to operate the IDP/ EOF programs.
3.0 RESPONSIBILITLES 3.1 Site Radiation Protection Coordinator 3.1.1 Perform dose projection calculations until the EOF is manned. 3.1.2 Initially evaluate the results of dose projection calculations. 3.1.3 Initially identify the need for field survey data to backup projected dose calculations. 3.2 Emergency Coordinator 3.2.1 Initially advise local and State authorities of the results of dose projection calculations and provide protective action recommendations as required. 3.3 Radiological Assessment Coordinator 3.3.1 Perform dose projection calculations. 3.3.2 Provide protective action recommendations as required.
+
o
s e EMERGENCY PLAN IMPLEMENTING PROCEDURE . EPIP 3.3b Page 2 of 16 Computerized Dose Projections Revision 4 --
- 1 Date 8/2/83 4.0 INSTRUCTIONS NOTE
~
THE IDP AND EOF PROGRAMS ARE ESSENTIALLY THE SAME COMPUTER PROGRAM BUT THEY USE DIFFERENT MEMORY STORAGE AREAS OF THE VAX COMPUTER. IDP AND EOF ARE THE COMPUTER USER AREA NAMES AND PASSWORDS FOR ACTIVATING THE SYSTEM. .THE IDP (INITIAL DOSE PROJECTION) PROGRAM IS OPERATED BY SITE PERSONNEL AT DAEC AND THE E0F (EMERGENCY OPERATIONS FACILITY) PROGRAM IS OPERATED BY CORPORATE PERSONNEL AT THE EOF IN THE IOWA ELECTRIC TOWER. THEIR SEPARATION PERMITS INDEPENDENT OPERATION T0 e MAINTAIN DATA ENTRY CONTROL. 4.1 Starting the Program 4.1.1 Turn on the VAX computer terminal by flipping the black toggle switch, on the back of the video display, to the up position. The printer-terminal in the TSC or EOF may be turned on by flipping the white power switch, on the frame stand, to the on position. 4.1.2 Wait a few seconds and hit the RETURN key. IDP users will skip the next step (4.1.3), as it is for EOF users only. 4.1.3 Pick up the telephone receiver of the telephone next to the terminal, pull the left-most cradel button up as f ar as it will go (it is white, where the other one is clear). Listen for a normal dial tone and then dial the VAX data line phone numoer, as listed in the Emergency Telephone Book. Af ter one ring, a shrill sound can be heard. Upon hearing this sound, carefully press the white cradel button down to its nonnal position, BUT NOT ALL THE WAY DOWN! Place the receiver on the table. If the EOF printer-terminal is used, there is no special cradel button but there is a voice / data switch. Dial the Vax data line pnone number with the switch in the voice position. As soon as you hear the shrilT sound, flip the voice / data switch to data position and place the phone back on the cradel. 4.1.4 Hit the RETURN key 4.1.5 oromot answer udtKNAME: ivP (dur for Corporate) hit RETURN key. 4.1.6 oromot __ answer en33nuku: Aur (cur ror corporate) hit RETURN key. b
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 3.3b Page 3 of 16 Computerized Dose Projections Revision 4 ' ' ~ ' Date 8/2/83 NOTE YOU WILL NOT SEE THE LETTERS BEING ENTERED ON THE SCREEN AS YOU DID IN STEP 4.1.5, 30 BE CAREFUL WITH YOUR KEY STROKES. 4.1.7 You are now in the program. Special messages may appear on the screen concerning administrative items that are of importance to the Iowa Electric data processing organization. If present, these messages are unlikely to affect your immediate use of the program. NOTE IF FOR SOME REASON THE COMPUTER PROGRAM IS e RENDERED IN0PERABLE USE EPIP 3.3A, " MANUAL DOSE PROJECTIONS", TO ESTIMATE OFF-SITE DOSE RATES. 4.2 Initial Use 4.2.1 prompt answer Adt YOU Uhlied A HAKUGUPY N TERMINAL (Y/N): Hit RETURN key. Answer the hardcopy prompt with a Y if you are using a printer-terminal . I 4.2.2 The IDP Program will show the following: orompt answer UU IUU M Ait e IU f RUN IDP7 Y/N Hit RETURN key. ( The E0F Program will show the following: promot answer l MA5itR MENU LIST 2 MENU CHOICE: The master menu is your key to mobility throughout the program. Choice 2 is the most important and frequently used mode. The body of this procedure describes this mode. The other eight I modes are briefly described in AttacNnent 1. l l
-9 y w 3 er nr -----T e- w- g- --
- Tr' v - - we w- + --m+a+-
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 3.3b Page 4 of 16 Computerized Dose Projections Revision 4 Date 8/2/83 4.2.3 promot answer 00 fou wisn io ust snY vr it THE INPUT DATA FROM A PREVIOUS CASE (Y/N) . Hit RETURN key. The Previous Case prompt is answered in the affirmative only if the user is ' aware o'f the entry of data at some earlier time that is suitable for present use. For initial use the prompt will be answered with a N. 4.2.4 Input data can now be entered. This information is listed and annotated in Attachment 2. most of the prompts are self-
- expl anatory.
4.2.5 promot answer DO YOU WANT ThE OUTPUT TO GO N TO THE TSC PRINTER (Y/N)?: hit RETURN key. This option will be answered in the affirmative if the Radiological Assessment Coordinator (RAC) desires to share his output with the Site Radiation Protection Coordinator, in order to compare results. 4.2.6 promat answer n0W MANY COPit5 TO YOU 1 WANT (1, 2, 3.....)?: l hit RETURN key. f NOTE l l E0F PERSONNEL WILL WANT TO ANSWER THIS PROMPT l WITH 2, AS THE RADIOLOGICAL ASSESSMENT COORDINATOR AND RADIOLOGICAL AND E0F MANAGER EACH WILL NORMALLY DESIRE COPIES OF THE OUTPUT. Calculations will not be perforbed and output will be displayed.
~
4.2.7 To stop scrolling, use the NO SCROLL key on the terminal. The output inclues the following information: General Information - repeat of some key input data Release.Information - ~ release rates by individual source & total Dose Information - X/Q, dose rates and doses for the site boundary, 2 miles, 5 miles,10 miles, and maximum elevated X/Q downwind distances.
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 3.3b Page 5 of 16 Computerized Dose Projections Revision 4 , , , , Date 8/2/83 - Protective Action Recommendations - specific actions to take as a result of these calculations. 4.2.8 If you should need to break from the program to start anew, nold the CONTROL key down and hit the C key once. promot answer 5 LOG hit RETURN key twice. promot answer 5 IDP (or EOF)
- hit RETURN key.
You have now reentered the program anew. Repeat Steps 4.2.1 thru 4.2.6. 4.3 Continuing Use 4.3.1 When the output ends a prompt will request whether you iesire to continue. Hit RETURN key and the following will be displayed: For the IDP Program: - orompt answer iYet: n:LF iue - For Heip witn 10F Progr am 10F LOG - To Log Off the Computer System IDP - Re-Run the IDP Program For the EOF Program: l oromot answer master menu list 2 YOUR CH0 ICE: hit RETURN key. 4.3.2 Repeat instructions in Steps 4.2.1 and 4.2.2. l 4.3.3 oromot answer l 00 YOU W15n IO USE ANY Y OF THE INPUT DATA FROM THE PREVIOUS CASE (Y/N) Hit RETURN key.
> m --, a e - - - c- -
- e y *- . ------
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 3.3b Page 6 of 16
' Computerized Dose Projections Revision 4 --
Date 8/2/83 4.3.4 oromot answer INPui 0 r0it Libi 0F tuli istM5 1 1 TO START CALCULATION OR NUMBER OF ITEM TO EDIT (2-36) , hit RETURN key. a) If you enter 0 at this prompt, you will be given a numbered list of all input edit items. This list is described in Attachment 2. b) If you enter 1, you will immediately go into dose calculation and output printout. c) If you enter 2-36 you will be shown the appropriately numbered input item and you can enter a new value. 4.3.5 You will now repeat steps 4.2.5 thru 4.2.7 4.4 Terminating the Program 4.4.1 For the IDP Progran: When you reach Step 4.3.1, type LOG and hit RETURN key. This will tenninate the program and log you off the computer. For the EOF Program: Upon eventual return to master menu, select choice 9 and hit RETURN key. This will terminate the program and log you off the computer. 4.4.2 EOF video terminal users will put the phone receiver back on the phone cradel . 4.4.3 Shut off the terminal by flipping the black toggle switch, on the back of the video display, to the down position. Printer-terminals will be shut off by flipping the white power button, on the frame leg, to the off position. 4.5 Accessing and Eliminating Sum Tables Each distinct set of input data causes a sum table list file to be produced and saved in computer storage. In the EOF Program, these files can be seen by selecting choice 4 from the master menu prompt. The IDP Progran, however, will not directly give you a listing of the sum table list file. You must get a directory from the operating system cursor. 1
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 3.3b Page 7 of 16 Computeriz:d Dose Projections Re"ision 4 - Date 8/2/83 As an example, the seventh version looks like this: SUMTABLE.LIS;7 The computer will- always use the latest version of the sum table (your last run of the program). If you want to use a sum table other than the latest one, see Attachment 3. Occasionally, too many sum tables will be created for the limited space available in your computer user area. This wil1 result in an OPEN FAILURE error. When this occurs, obtain the assistance of a system
~
expert to eliminate unwanted sum tables, and make room for new ones. 4.6 Program Verification
- In order to assure the user that the progran is functioning properly, Attachment 4 lists a sample input set of values and the corresponding output release rate. If the user is uncertain that the progran is functioning properly, he may input those values and see if the computer produces the same output.
NOTE IF VERIFICATION FAILS, USE EPIP 3.3A, " MANUAL DOSE PROJECTIONS", INSTEAD OF THE COMPUTER.
5.0 REFERENCES
- 1. DAEC Emergency Plan
- 2. IELP Corporate Emergency P1an
- 3. EPA 3.3a
- 4. EPA Protective Action Guides l 5. TEC Report No. : R-82-002 Interim Class A Model j 6.0 ATTACHMENTS
- 1. Other Functions of the EOF Program
- 2. Input Edit Items
- 3. Accessing Sum Tables l
l 4. Program Verification l
l EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 3.3b Page 8 of 16 Computerized Dose Projections Revision 4 ~~ L Date 8/2/83 l Approved By: Date: /uM3 /f dT saergency P gning cooretflator ug, " Approved By: , , 7 /i [.h7/ 73. r Date: 1/ / - Raoi4tionProjection4upervisor Reviewed By: - g4 Date: 8/s/83 ALARA Cooroinator Q
, Reviewed By: Date: 84 Cnairman, ' Operations Committee ,
Approved By: ff, Date: [ 83 Piant Super?tencent/ - ttuclear
/
l l t I
' EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 3.3b Page 9 of 16 Computerized Dose Projcctions Revision 4 ' ' '
Date 8/2/83 t ATTACHMENT 1 Other Functions of the EOF Program The purpose of the attachment is to briefly describe E0F master menu selections opher than choice 2 (which is described in the body of this procedure). This attachment does not apply to IDP users even though the term IDP is used in the menu titles. CHOICE 1 - HELP WITH THE IDP PROGRAM This choice will simply describe the IDP/ EOF program in narrative form. CHOICE 3 - PRINT YOUR LATEST IDP RUN This choice will repeat the output that you just calculated. CHOICE 4 - COPY THE LATEST HP IOP DATA FOR YOUR OWN USE This choice will make a file copy of the latest sum taDie list file and display your user area directory. CH0 ICE 5 - SEE LATEST HP IDP DATA RUN - VT100 This choice will load the most resent sum table list file and display its output on the video tenninal . CH0 ICE 6 - SEE LATEST HP IDP DATA RUN - HARDCOPY This choice is the same as choice 5, except you will receive a printout of the run. i y swy w- -m - -- w
~
a , EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 3.3b Page 10 of 16 Computerized Dose Projections Revision 4 Date 8/2/83 CHOICE 7 - EXAMINE CURRENT PLANT STATUS INF0 This ' choice will enable you to see what are the current plant operational and radiological parameters. .Upon selecting this choice you will be shown-another menu as follows:
'P = PRINT the emergency status on the system lineprinter V = VIEW the emergency status data on a video terminal .
T = TYPE the emergency data on the current user terminal L = LOGUFF the system
- R = RETURN to normal timesharing ($ prompt) or calling menu Plant status is nothing more than an electronic notepad system. THERE IS NO DIRECT CONNECTION.WITH PLANT INSTRUMENTATION FOR REAL TIME INPUT. This information is entered manually in the Control Rom thru menu option T. However, data entered from the site IDP will be visible on the Corporate EOF program. This is the only mode in which the IDP and EOF user areas will overlap in sharing data.
Menu option R will return you to the master menu. CH0 ICE 8 - EXIT THIS MENU AND RETURN TO THE OPERATING SYSTEM This choice allows you to terminate the program without loging off the computer. It will give you an operating system cursor (5). From that cursor you may execute a wide range of operating system connands. It is suggested that the casual user avoid this choice unless he has full understanding of operating system commands. CHOICE 9 - LOG 0FF THE COMPUTER SYSTEM ! As described in section 4.4, this is the standard method of terminating use of tne program and canputer tenninal . i e l' ~
g _A EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 3.3b Page 11 of 16 Computerized Dose Projections Revision 4 _. .. . Date 8/2/83 ATTACHMENT 2 Input Edit Items The purpose of this attachment is to list edit items that are input int ~o the computer program. The item number corresponds to edit prompt number. No. Item Response Notes O summary of edit items 0 execution'- not input 1 calculate 1 exeuction - not input 2 recorded by name person using program 3 calculation number number number of run 4 wind direction degrees direction FROM 5 wind speed mph
- 6 delta T deg F/165 ft see
- note
- next page 9 time since shutdown hours 10 field rate determination Y/N if field data exists 11 Rx Bld A stack conc. uCi/cc 12 " "
A range NIH Normal Inter. High 13 " " B conc. uCi/cc 14 " " B range NIH 15 " " C conc. uCi/cc 16 " " C range NIH 17 " " A " flow CFM 18 " B 19 " " C 20 Offgas Stack conc. uCi/cc 21 " " range NIH 22 " " flow CFM 23 Turbine Exhaust conc. uCi/cc 24
, range NIH 25 " "
flow type C or % select type of flow 26 flow CFM or % 27 SGTS on? Y/N standby gas treatment 28 release duration hours usually an estimate 29 Iodine % - ground fr ac . % default value is .3 30
- elevated frac. % SGTS on/off.3/.003 31 release rate from field Y/N if field data exists 32 time of measurement hours answer if 31 is Y 33 distance of measurement meters answer if 31 is Y 34 exposure rate .
mr/hr answer if 31 is Y 35 additional locations (3) miles 36 release rate overide Ci/sec This input allows you to force a specific release rate rather than letting the computer calculate one basec on information from items numoered 11 to
- 26. Tnis is ideal for complying wich the requirements of PASAP 7.4 wnere certain release rates will oe assumed that are not built into the IDP/ EOF program.
s e EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 3.3b Page 12 of 16
- Computerized Dose Projections Revision 4 -- --
Date 8/2/83 ATTACHMENT 2 (Cont'd)
- NOTE
- IF METEOROLOGICAL DATA IS NOT AVAILABLE FROM THE PLANT, IT MAY BE OBTAI'NED FROM THE FLIGHT SERVICE STATION IN CEDAR RAPIDS AND/0R THE NATIONAL WEATHER SERVICE IN DES M0INES (PHONE NUMBERS ARE LOCATED IN THE EMERGENCY TELEPHONE BOOK). THE COMPUTER USES DELTA T IN UNITS OF DEGREES FARENHEIT PER 165 FEET. SOURCES OTHER THAN THE PLANT MET TOWER MAY USE OTHER UNITS WHICH MUST BE CONVERTED. THE FOLLOWING CHART MAY BE USED AS AN ALTERNATE METHOD IN DETERMING THE DELTA T TO USE FOR COMPUTER INPUT:
Wind DAY T I M E - SOLAR RADIATION NIGHT T I~M E Speed clear or (mph) Strong Moderate Slight Overcast thin overcast overcast
<5 -2 -2 -2 -1.2 1 2 5- 7 -2 -2 -1.2 1 1 2 7-10 -2 -1.2 -1.2 1 1 1 0-13 -1.2~ 1 1 2 1 1 > 13 -1.2 1 1 2 1 1
7 EPIP 3.3b l EMERGENCY PLAN IMPLEMENTING PROCEDURE --' ' Pace 13 of 16 ' Computerized Dose Projections Revision 4 - Date 8/2/83
~~
/2 ATTACHMENT 3' Accessing Sum Tables , .
I
'./
~
- s
~
The purpose of the attachment is to briefly describe the manner in which the user may , load and run a sum table other than the most current one. < ,. ,
- 1. Hit CONTROL and C keys simultaneously. , ,, ,r J
2. When the operating system cursor ($) appears,; type DIR and hit RETURN. ,,
/'.- '/ .
- 3. Find the SUMTABLE.LIS;# file on the directory wnich hus the largest version number -
(#). ,.
;t - .
d/t
~
- 4. Find the SUMTABLE.LIS version that you desire to view. /
- 5. Rename the desired SUMTABLE.LIS file to a versin nunber one largeb than the large'st-one on your directory. <
o' , . For example. SUMTABLE.LIS;34 is the latest file and you wi,sh to view l ~/ , SUMTABLE.LIS;22. e ., type: RENAME SUMTABLE.LIS;22 TO SUMTABLE.LIS;35 ,, hit RETURN. ' '.
- 6. Hit RETURN again to obtain USERNAME prompt and reneter tne IDP/ EOF progrem.
- 7. When you see the Previous Case prompt, answer Y. The progr$n will use tne file with the larges version number.
- 8. After viewing the data, it is reconnended that you~ return to'the operating system cursor and rename the version back to its original version number. ,
P r8
/
l e t-
~ 6 ,
i /
.s
./
r ,e
/
d r f 4
-v.- - - .
y -, , ; .~~ - q .. , - g - , g i h."> J
~!',T*iERGENCY t.
PLAN IMPLEMENTING P,ROCEDURE _' EPIP 3.3b
- 4'~ --
Page 14 of 16 I~ Computeri zed'Dosfe:pegj ections Revision 4 -. - .t Ie ~ t
.M# ' .. Date 8/2/83 a , ,1 -
, AT,TACHMENT .t
- 4. ,
, f
. - p Pro,pam.Verificat,1on
;j.
r , The purpose of the/a*.tachment' is>q.;o list a,shpie set of it.put data and corresponding output to enabIle,p'c~Jser to verify whether or'n6t phe program is functioning properly. ff I. METEOR 0LO,GICAj. DATA lJl l 4 WIND DIRECTION (degrees) -- 270.0 5 WIND SPEED (mph) ---------- 8.0 6 DELTA T (degrees) --------- 1.20 lJ
*** MISCELLANEOUS INPUT ***
9 TIME SINCE SHUTDOWN (hr5) - 1.00 > 10 USE ONLY EIELD f EXPOSUSE RATES FOR DETERMINING O! THE RELEASE RASES (Y/.*i) --- N i 1, .
.J /
II. RELEASE DATA i '
- t. ,
; f+',
j ' A. Reactor Building Stac,ks 7,, , , j b 11 " A" STACK" CONCENTRATION , :- 7'------------1.00E-06 uCi/cc s 12- "A" STACX RANGE (HI/IhT/NOR) --- '---------H - 1 13 " B" STACK CONCENTRATION ------------------l.00E C36 uCi/cc
, 14
-"B" STACK RANGE (HI/ INT /fdR)
C------------H '
.~
0 15 "C" STACK CONCENTRATION - ^----------------l.00546 ' ' uCi/cc 16 "C" STACK /AANGE (HI/ INT /NOR) --- '---- ' .LH.
-h
,, , ,- 17
" A" STACK. FLOW RATE ----------------------6. 00E+04, CFM
'18 " B" STACK FLOW RATE ----------------- ~ L-5. 50E+04 CFM 19- "C" STACK FLOW RATE ----------------------0.00E,,00 CFM f.
B. OFFGAS STACK ;' '
'>/ 20 ----- '
*21 0FFGASSTACKCONCENTRATION------4------1.00E-06uCi/cc 0FFGAS STACK RANGE (HI/ INT /NOR). f H
.22 0FFGAS STACK FLOW
~
%------4s.00E+03 CFM C. TURBINE EXHAUST ,
23 - . TURBINE EXHAUST CONCENTRATION -0.00E+00 uCi/cc
, . 24 - ' TURBINE EXHAUST RANGE (H1'4hT[NOR) ---- ,-H -
i/ 25 ' TURB INE EXHAUST FLOW ---------.s---------f.-0.06E,+00 CFM TURBINE E W UST FLOW PERCENT 't.00 4
- 0. MISCELLANEOUS DATE 27 STANDBY GAS TREATMENT FOR OFFGAS EXHAUST AVAILABLEk
. ( Y / N ) - - - - - - - - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - Y r 28 ---1 29 DUR ATION OF RELEASE ( hr s) ----------------------- / , ,77 RATIO OF-IUDINE T0. TOTAL ACTIVITY FOR GROUND LEVEL RELEASE ----------------------------- 'J.00E-01 30 RATIO,OF IODINE TO TOTAL ACTIVITY FOR ,
F j AH;ECEVATED RELEASE ,------- d----------- ,-------- y 3.00E-03 l- r o - IL, / r
/ .
t ~ (
, .? ,
'i m 9 u _
!p g
, i, - - , -
I e
- EMERGENCY PLAN IMPLEMENTING PROCEDURE. EPIP 3.3b Page 15 of 16 Computerized Dose Projections Revision 4 ,, . . ,
j Date 8/2/83 ! 1 ATTACHMENT 4 (Continued) III. FIELD EXPOSURE DATA l 31 USE FIELD EXPOSURE RATE MEASUREMENTS? * (Y/N)--------------------------------------N ;
*** ANALYSIS LOCATIONS ***
35 ADDITIONAL LOCATIONS FOR CALCULATIONS. LOCATION # 1 (meters) ---------------------8.05E+02 LOC ATION # 2 (meters) ---------------------1. 61E+03 LOCATION # 3 (meters) ---------------------2.41E+03 36 RELEASE RATE MANUAL OVERRIDE OPTION, CURRENT VALUES ARE: REACTOR BUILDING RELEASE RATE -------------0.00E+00
- OFFGAS STACK RELEASE RATE -------------0.00E+00 TURBINE BUILDING RELEASE RATE -------------0.00E+00 TOTAL GASE0US RELEASE RATE -------------0.00E+00 I
INPUT 0 FOR LIST OF EDIT ITEMS 1 TO START CALCULATION OR NUMBER OF ITEM TO EDIT (2-36) 1 _, 00 YOU WANT THE OUTPUT TO GO TO THE TSC PRINTER (Y/N)?: Y THE LATEST IDP CALCULATION WILL PRINT ON THIS TERMINAL . . . HOW MANY COPIES DO YOU WANT (1,2,3. . .)?: 1 l l l t F'- , - -
o e e
~
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 3.3b Page 16 of 16 i Computerized Dose Projections Revision 4 . .. 1 Date 8/2/83 i iii. 00SE INFORPAT40N Ooin nino Location , ( Site Accitional Locations X/V douncar y 2ml Sei lumi #1 s2 s3
- 1. Olstance to location, motors 10u90.0 490.0 3215.0 504 $ .0 1o090.0 604.5 1009.0 2413.3 (miles) (10.00) (0.30) (2.uol (3.00) (lu.00) (U.50) (1.00) (1.50)
- 2. Normall zoo con-contration, A/V, 8 sec/m3, bround level release 3.59E-vo 1.036-03 o. led-us 1.37E-us S.396-uo 4.90E-04 1.74E-04 9.30E-05 9
- 3. Normali and con-centration, X/V, sec/m3, flevateo release 4.73E-07 u.Qud+00 1.42E-lz 3.o3E-us 4.756-07 0.00d+u0 1.40E-20 o.756-le
- 4. nnole Dod y cose rate, seem/nr S.7vs-03 1.uoE-02 o.3od-04 1.026-u4 3.796-05 S.03E-03 1.79d-03 9.80E-04
- 5. nnole ood y cose mrom 1.u2E-04 1.o7E-02 1.13E-us 2.u76-04 1.025-04 a.916-03 3.17E-03 1.73E-03
, o. Tn roic cose l commitment, mrom 2.uoE-u4 3.79E+00 2.28E-ul S.81E-02 2.0cE-02 1.51E+0u o.4tE-01 3.51E-01 l , 7. Total Pl une =ictn meters (miles) 4099.9 91 .o 495.7 1127.6 2099.9 14 2 .9 26o .2 362.9 (1.31) (0.06) (u.31) (u.70) (1.51) (0.09) (u.17) (0.24)
- e. P!'.rne arrival l time, nr 1.2Si+00 3. ele-02 2.50d-ul o.23E-ul 1.2SE+00 0.256-02 1.2SE-01 1.eed-ul 1
l
a EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 4.2 Page ,.1 of 8 ,, FIRST AID, DECCNTAMINATION AND MEDICAL SUPPORT Revision 1 Date - 7/14/83 1.0 PURPOSE This procedure provides overall guidance associated with the treatment of injured and/or contaminated individuals during an emergency. 2.0 APPLICA8ILITY This procedure is applicable to key Emergency Response Organization supervisory personnel, rescue team personnel, individuals who may administer first aid . treatment and Health Physics Technicians involved in personnel decontamination efforts during events classified as an ALERT or greater.
- 3.0 RESPONSIBILITIE1 3.1 Security Shift Supervisor 3.1.1 Insure that off-site medical authorities are advised of the need for medical assistance. .
3.1.2 Verify that personnel designated to provide first aid treatment are knowledgeable in the techniques that are expected to be needed. 3.1.3 Provide direction, as necessary, in the application of first aid techniques. 3.2 OSC Supervisor 3.2.1 Supervise the performance of personnel monitoring and decontamination activities. 3.2.2 Supervise the preparations for and dispatch of injured and/or contaminated personnel to off-site medical f acilities for treatment. l 3.2.3 Appraise the Site Radiation Protection Coordinator of problems experienced in decontamination of personnel and/or treatment of
' injuries and progress being made, l
f 3.3 Site Radiation Protection Coordinator ' 3.3.1 Advise the Emergency Coordinator of any reporting or event l classification requirements, as defined in EPIP 1.1, " Determination l of the Emergency Action Level", and EPIP 1.2, " Notification". 3.3.2 Insure that the Medical Consultant is advised of contaminated L personnel transported to Mercy Hospital for further decontamination I and/or treatment of contaminated injuries. 3.3.3 Insure that the Emergency Room physician at Mercy Hospital is advised l in advance that personnel with injuries and/or wno require decontamination are being transported from the site. ( - l I t
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 4.2 Page 2 of 8
i FIRST AID, DECONTAMINATION AND MEDICAL SUPPORT Revis1ori ~ 1 Date - 7/14/83 3.3.4 Provide overall guidance to the OSC Supervisor, as required, for personnel decontamination and treatment of injuries wher) contamination is present. -
3.3.5 Appraise the Emergency Coordinator of the problems experienced in decontamination of' personnel and/or treatment of injuries where assistance is or may be required from off-site medical authorities. 3.4 Emeroency Coordinator _ 3.4.1 Advise the Emergency Response and Recovery Director of the actions being taken in response to any personnel injuries and/or personnel
- decontamination which require off-site medical assistance.
3.4.2 Insure that the NRC Operations Center is notified within one hour of any f atality or serious injury on-site requiring transport to an off-site medical facility for treatment, as required by 10CFR50.72 and prescribed in EPIP 1.2, " Notification". 4.0 INSTRUCTIONS 4.1 Recovery of Injured Personnel 4.1.1 During rescue operations conducted in accordance with EPIP 4.3,
" Rescue and Emergency Repair Work", when individual (s) reported to be missing are found and require medical or ambulatory assistance, a) The extent of injuries should be determined and the OSC Supervisor advised via the Operations Radio System. .
NOTE
- 1. During plant emergencies the Emergency Coordinator shall be advised of all injuries.
- 2. If off-site medical assistance is required, contact shall be made by the CAS Operator as discussed in paragraph 4.3.
b) If injuries are evident, treatment priorities shall be based upon the ,mdiological and medical condition of the injured party, as specified in EPIP 4.3. c) Application of first aid, including preparations made to preclude further injury prior to relocating severely injured personnel, I will normally take precedence over radiological considerations. d) Unless instructed otherwise during the briefing or during subsequent conversations, the injured party should be returned by the rescue team to the Health Physics Access Control area.
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 4.2 Page , 3 of 8 FIRST AID, DECONTAMINATION AND MEDICAL SUPPORT Revision 1-l Date - 7/14/83 NOTE First aid treatment'will normally be provided at the First Aid Room in the OSC; however, for severely injured victims,
- first aid techniques may have to be provided at other locations in the plant while awaiting medical support assistance. * .
4.1.2 If during subsequent re-entries into the plant to conduct repair, damage control and corrective action activities a personnel-injury occurs which requires medical or ambulatory assistance, the Technical and Engineering Supervisor shall be advised of such need by another
- member of the repair team via the Operations Radio, or alternately, the paging system or plant telephones.
!- NOTE Since Operations Radio consoles are located at the CAS, SCP, TSC, OSC and Control Room, all appropriate emergency response < ' centers will be advised of a personnel injury problem simultaneously, if transmission is conducted via the
-Operations Radio.
l a) A determination should be made of the nature and extent of I injuries as quickly as possible and the OSC Supervisor advised of the injury status, as well as, the location of the injured l party. l l b) A determination as to whether or not the repair effort should be
' continued or aborted shall be made by the Technical and Engineering Supervisor based upon discussions and judgment of the Repair Team Leader.
l l c) The victim should be administered first aid and returned to the l Health Physics Access Control Area by personnel on the scene, if available and knowledgeable in first aid techniques, or by qualified first aid personnel dispatched from the OSC. I 4.1.3 If first aid personnel need to be. dispatched, the Site Radiation l Protection Coordinator shall determine whether or not a Health Physics Technician should accompany them considering: a) The similarity of the ingress route to the location of the t injured party with the route used by the repair team ano radiation levels monitored during that entry. I
A P EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 4.2 Page 4 of.8
~
FIRST AID, DECONTAMINATION AND MEDICAL SUPPORT Revision 1 Date - 7/14/83 b) The availability of the Health Physics Technician assigned to the repair team to attend to rescue activities, should.it be determined that the repair effort is not to be aborted. 4.1.4 Subsequent dispatch of rescue personnel and conduct of rescue activities shall be performed, as described in EPIP 4.3, " Rescue and Emergency Repair Work". . 4.1.5 The OSC Supervisor should inform the Site Radiation Protection Coordinator of the state of injured personnel and personnel decontamination efforts. a) The Site Radiation Protection Coordinator should review EPIP.1.1,
" Determination of the EAL", and EPIP 1.2, " Notification", and advise the Emergency Coordinator of any event reclassification or -
10CFR50.72 reporting requirements. b) The Emergency Coordinator should insure that required NRC l' notifications, if any, are made and so appraise the Emergency Response and Recovery Director. l c) In addition, the Emergency Coordinator should appraise the Emergency Response and Recovery Director of pertinent details'
- concerning the' injured or contaminated individuals and actions which have been initiated or planned.
4.2 Personnel Surveying and Decontamination 4.2.1 If there is no injury but the individual is contaminated above acceptable levels for uncontrolled areas, decontamination will' be conducted as pe- RPP 12.1, " Personnel Decontamination", as r necessary.- i I -4.2.2 If contamination is within acceptable levels for uncontrolled ' areas, the injured victim should be taken to the First Aid Room for treatment and subsequent transfer, if necessary. L
. 4.2.3 An individual who is contaminated and who also has minor injuries l
l consisting of cuts or breaks in the skin shall receive immediate first aid, covering those areas with bandages to aid in precluding internal contamination. a) Decontamination shall follow first aid treatment but only to the extent necessary to reduce the spread of contamination during transfer to Mercy Hospital. b) Personnel contamination records shall be prepared in accordance with the requirements defined in RPP 4.3, " Personnel Contamination Records", and RPP 4.4, . " Reporting Requirements".
e A EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 4.2
- Page .5 of 8 ..
-FIRST AID, DECONTAMINATION AND MEDICAL SUPPORT Revision 1 Date - 7/14/83 NOTE In general, injuries .shall take precedence to contamination considerations during any emergency.
'4.2.4 Health Physics personnel should provide guidance and monitor the effectiveness of decontamination efforts which normally are to be accomplished at decontaminati)r f acilities provided at the Health Physics Access Control Area.
NOTE
- 1) Where open wounds are present coincident with contamination, decontamination of areas adjacent to the wound must be accomplished so as not to disturb the wound area.
- 2) Decontamination of open wounds will normally be accomplished '
under the direction of medical support personnel. 4.2.5 An individual who is contaminated and so seriously injured that decontamination cannot be performed, shall be given immediate first aid.
~
a) The victim may be wrapped in a blanket or plastic to limit the spread of contamination and await transfer to Mercy Hospital. b) If the contamination is of such a level to create an added hazard to the victim, first aid personnel with assistance from Health Physics personnel may remove the individual's clothing, if possible. 4.3 Off-Site Medical Assistance i 4.3.1 Off-site medical support shall be provided by the following , organizations: L a) Palo Fire Department , b) Area Ambulance i c) Mercy Hospital, Cedar Rapids d) University of Iowa Hospital, Iowa City 4.3.2 Transportation of patients who are contaminatea or wno may potentially be so should be arranged through Area Ambulance. 4.3.3 If Area Ambulance plans on dispatching a helicopter: a) Advise the dispatcher if an off-site release is in progress and, if so, the direction of the plume.
,3 , . -- - -
-- ., y- , , r - ---- , - , . , , - - -
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 4.2 Page -- 6 of 8 ...
~
FIRST AID, DECONTAMINATION.AND MEDICAL SUPPORT Revision 1 Oate - 7/14/83 b) If the event occurs during darkness, insure that flares are lit at the helipad and the helipad ls illumianted with. search lights. , 4.3.4 Notifi' cation of such support organizations should be accomplished - from CAS and the Emergency Co'ordinator so advised. a) The Emergency Coordinator shall notify the Emergency Response and Recovery Director, if not previously accomplished, that assistance from off-site medical facilities has been requested and should provide a brief update regarding the status of the patient and actions that have been accomplished. b) If the injury is compounded by potential or actual radiological problems, the Site Radiation Protection Coordinator shall insure that follow-up ' contact is made with Mercy Hospital so as to provide specific information regarding the extent of the radiological problem. NOTE i A review should be made of the victim's medical file, if available, _ and medical support personnel advised of any pertinent information which may be recorded. c) .The Site Radiation Protection Coordinator shall also insure that Iowa Electric's Medical Consultant is appraised of personnel injury cases which involve potential or actual personnel contamination. 4.3.5 Follow-up contact with off-site medical -authorities, including the Medical Consultant, shall be provided during an emergency condition classified as an ALERT or greater by the Insurance and Risk Manager, as prescribed in CPIP 2.5, " Insurance and Claims". 4.4- Transportation of Injured Personnel to Medical Treatment Location _ 4.4.1 The injured party or party requiring medical assistance shall be l loaded onto the transport vehicle. l 1 4.4.2 Dosimetry devices, protective clothing and other equipment, as appropr_iate, shall be provided for use by ambulance personnel. 4.4.3 The OSC Supervisor shou,ld select at least one Health Physics Technician; two, if possible, to accompany contaminated victims transported from the site to the local medical facility so that ; l guidance and assistance to medical support personnel, can be provided, as required, to limit the spreaa of contamination. l l
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 4.2 Page -- 7 of 8 : FIRST-AID, DECONTAMINATION AND MEDICAL SUPPORT Revision 1 Date - 7/14/83 NOTE ,
- 1. If two Health Physics Technicians are available, considerat' ion should be given to dispatching one ahead to the victim, if highly contaminated, and to aid medical support
> personnel in establishing contamination control measures.
- 2. The OSC Supervisor should make provisions for transporting j' the Health Physics Technician (s) back from off-site medical facilities to the DAEC.
, 4.4.4 The OSC Supervisor should advise the Site Radiation Protection Coordinator of the departure of' injured or contaminated personnel from the site and this information relayed, in turn, to the Emergency Coordinator and Emergency Response and Recovery Director.
4.5 Medical Treatment
-4.5.1 Upon being advised of a severe injury which -involves a contaminated patient, the Iowa Electric Medical Consultant should make himself available to the Emergency Room Staff for:
a) Advising medical personnel regarding measures to be taken to handle contaminated victims. b) Coordinating all hospital activities and consulting with experts on radiation injuries and effects, as required. c) Directing and controlling the administration of radio-protective drugs. 4.5.2 Medical treatment for the injury and decontamination of open wounds should be accomplished by medical support personnel. l 4.6 Follow-up Monitoring and Analysis Activities l 4.6.1 A Whole Body Count should be conducted for those individuals who may l have been internally contaminated, in accordance with RPP 9.1,
" Bioassay Program".
4.6.2 The Site Radiation Protection Coordinator, in coordination with the Medical Consultant, should determine if further evaluations, including more detailed bioassays and medical examinations, are warranted and arrange for their conduct, if appropriate.
5.0 REFERENCES
5.1 DAEC Emergency Plan 5.2 NUREG 0654 Rev. 1 l
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 4.2 Page 8 of 8 FIRST AID, DECONTAMINATION AND MEDICAL SUPPORT Revisich~l Date - 7/14/83 6.0 ATTACHMENTS None Approved By. pl Date: })bjtsh/8,/98.5 M gency Plan' Toor N Q 'Vg~ Approved By: MhM iiacia'; ion Protectioti supervisor Date: 8 Reviewed By: h 4 ,, # Date: si'//9/v3 ALARA Coordinator Q Reviewed By: /,[/[O Date: /!P) OperatYons Commit / tee Chairman Approved By: Date:
-Nuclear PlantSup[intende l
I l
e s EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.3 _, ,, Pace 1 of 16 RESCUE AND EMERGENCY REPAIR WORK Revision 2 Date 5/27/83 l.0 PURPOSE This procedure provides guidance associated with rescue and emergency repair team preparation and activities. 2.0 APPLICABILITY , This procedure is applicable to key Emergency Response Organization personnel located in the Control Room, TSC and'05C and to personnel involveo in rescue and emergency repair team activities.
. 3.0 RESPONSIBILITIES 3.1 Security Shift Suoervisor 3.1.1 Advise the Security and Support Supervisor of the identity of the individual (s) for whom accountability cannot be determined and last known whereabouts.
3.1.2 Coordinate with the OSC Supervisor to provide First Aid personnel for rescue activities. 3.2 Security and Sucoort Supervisor 3.2.1 Provide assistance, as required, to the Security Shift Supervisor to determine the last known whereabouts of personnel for whom accountability cannot be established. 3.2.2 Coordinate with the Operational Support Cent Suoervisor, Security Shift Supervisor and Site Radiation Protect in Coordinator to insure that 'a rescue team (s) is prepared for disoitch.
- 3.3 Control Room Coordinator 3.3.1 Identify corrective actions / maintenance tasks to the Technical and Engineering Supervisor which, if performed, should assist in mitigating plant conditions and/or the consequences of the event.
3.3.2 , Insure that radiolooical information pertinent to rescue and repair team activities is provided to the Site Radiation Protection Coordinator as well as changes in radiological carameters being monitored or projected chances due to station conditions. 3.3.3 Coordinate with the TSC Suoervisor prior to dispatching personnel to locations where local ~ operational response actions may be required. k
, , - - - - --,u - , ,-
4 . EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.3 Page 2 of 16 , RESCUE AND EMERGENCY REPAIR WORK Revision 2 Date 5/27/83 3.3.4 Coordinate, as necessary, with the TSC Supervisor to maintain an . awareness of the status of corrective actions in progress by repair teams which have been dispatched and rescue activities which may be ~ in prooress. 3.4 . Technical and Enoineerino Suoervisor . 3.4.1 Coordinate with the Control Room Coordinator to determine plant conditions, equipment malfunctions, and repair / damage control efforts which should assist in mittaating the event- and establishino stable conditions. o 3.4.2 Provide direction to engineering and maintenance personnel and define the actions which should be taken to successfully conduct repair / damage control activities. 3.4.3 Provide direction to the OSC Super visor regarding the . formation of emergency repair teams. 3.4.4 Brief emergency repair team personnel regarding repair /damace control activities to be conducted, precautions to be taken durino the course of repair / damage control efforts and communications requirements upon being dispatched. . 3.5 Site Radiation Protection Coordinator S 3.5.1 Evaluate plant conditions and radiological hazards which exist or which potentially may-be encountered by rescue and recair teams and by personnel who may be dispatched to locations where local operational actions may.be required. 3.5.2 Estimate whole body and thyroid exposures based upon the Drocosed rescue and repair activities and' existing radiological conditions ana initiate actions, if warranted, to increase the authorized exoosure , limits, implement emeraency ' exposure authorizations, and acminister Potassium Iodide. 3.5.3 . Brief rescue and emergency repair team personnel regardinq
! radiological hazards which exist or wnich potentially may be encountered and provide cuidance regarding orecautions to be taken and limits that shall not be exceeded.
3.6 OSC Suoervisor-3.6.1 Coordinate with the Security Shift Superv ser and Tecnnical and Engineering Supervisor to form the rescue and repair teams, when required.
e a EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.3 -. -. ~ Page 3 of 16 RESCUE AND EMERGENCY REPAIR WORK Revision 2 Date 5/27/83 i 3.6.2 If the projected exposures to rescue and repair team aersonnel are in excess of 100FR20.101 limits, insure that team personnel are advised of the projected exposures and ve.'ify that each team member is volunteering for the projected assignment. 3.6.3 Verify that rescue and emergency repair team members are briefed regardino the activities to be performed, potential hazards which exist, and precautions to be taken durino the planned rescue and repair activities. 3.7 TSC Supervisor o 3.7.1 Provide overall direction and assistance, as required, to the Control Ronm Coordinator and Technical and Engineering Suoport Supervisor in developing and implementing repair / corrective action plans. 3.7.2 Coordinate the dispatch of personnel to locations where local operational response actions may be reouired with the Control Room Coordinator, Site Radiation Protection Coordinator, and Emeroency Coordinator. 3.7.3 Verify that the Control Room Coordinator is appraised of the status of rescue and repair team activities. 3,8 Eneroency Coordinator 3.8.1 Authorize increases in personnel exposure limits and imolement ation of emergency exposure criteria. 3.8.2 Authorize the dispatch of rescue and repair teams. 3.8.3- Verify that the Emergency Response and Recovery Director is acoraised l of the status of rescue and repair team activities. I 4.0 INSTRUCTIONS 4.1 General Reouirements ! 4.1.1 Rescue and emergency repair teams shall - t be dispatched without th ? prior approval of the Emergency Coordinator. l 4.1.2 The TSC Supervisor shall be informed, in advance whenever possible, of the dispatch of personnel to locations wnere local operational response actions are required. 4.1.3 An evaluation of projected exposures to team members shall be made crior to dispatch. a) Individual exposure limit increases, to the extent recuired, may be authorized by the Site Radiation Protection Coordinator providing such limits do not exceed those defined by 10CFR20.101.
., - , - - , ,n. - n. - , - -
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.3 Page 4 'of 16 RESCUE AND EMERGENCY REPAIR WORK Revision 2 Date 5/27/83 NOTE _ c The DAEC Administrative limits and limits defined by 10CFR20.101 are prescribed in RPP 2.1, " Personnel Exposure Limits", and are partially reproduced on Attachment 1, " External Exposure Limits". b) If exposures in excess of 10CFR20.101 limits are projected for team members, the Emergency Coordinator may authorize exposures up to the limits specified on Attachment 1, " External Exposure Limits", in accordance with 10CFR50.47(b)(11), providina that team members are volunteers. NOTE
- 1) The Emergency Response and Recovery Director should be advised of the increased exposure limits prior to their authorization.
- 2) Guidance ' associated with implementation of emergency exposure limits is provided in RPP 13.1, " Radiation Emergencies".
4.1.4 Individuals assigned to rescue and emergency repair teams shall take reasonable precautions to maintain their exoosures as low as possible, consistent with ALARA considerations and job assignment. a) Respiratory equipment shall be fitted and determined to be functioning properly, as prescribed in RPP 8.1, " Respiratory Protection Program". b) Area radiation surveys shall be conducted as prescribed in ! RPP 7.1, " Radiation Surveys", and team memcers shall Dosition themselves to minimize their own exposures due to localized ho: l spots. c) Personal dosimetry shall be checked periodically, as specified in RPP 3.2, " Obtaining and Using Personnel Dosimetry", so as to monitor the total dose received and to insure that the exposure limits established are not exceeded. 4.1.5 Prior to dispatch of rescue and emergency repair teams, briefinos shall be conducted wnich cover at a minimum: a) The activity to be performed. I b) The specific area where the activity is to be cerformed. NOTE l For rescue activities, the area designated may only be a best estimate.
e- n EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.3 -- -. Page 5 of 16 RESCUE AND EMERGENCY REPAIR WORK Revision 2 Date 5/27/83 c) Router tc be used to gain access to the area. d) Estimated radiation levels in the specific area and radiation levels estimated to be encountered alona the route. e) Authorized exposure limits for team members ano dose rate limits which should not be exceeded, f) Communications requirements and methods. g) Specific technical and administrative requirements associated with cerformance of the activity. h) Precautions to be taken during performance of the activity. 4.2 -Rescue Ooerations 4.2.1 If accountability for all personnel within the Protected Area, as prescribed in EPIP 1.3, " Plant and Site Evacuation", can not initially be established, one or all of the following actions should be taken in an . effort to locate the missing individual (s) and determine if rescue operations are required, a) -Contact emergency response center supervisory personnel to determine if the individual (s) is/are, in fact, oresent. b) Contact the individual's direct supervisor and personnel witn whom the individual was working to determine the job assianment and ascertain "last-known" whereabouts. NOTE Tne Personnel Statement.Concerning Incident form orovided with EPIP 2.1, " Activation and Operation of the Operational Support Center", may provide infonnation regarding last known whereabouts. c) Check the security computer system for location and time of the employee's last entry or exit. d) Check the RWP access logs maintainea at the Health Physics l ! Control Access Area. e) Attemot contact of tha indivioual(s) using the olant osaina i I system. I '4.2.2 Based upon the most probable locations where individuals deter-ined to be missing may be located, an assessment of cotential radiclocical exposures should be conducted. l [ _
.-_ ~ _ . , _ . . _ _ . ___. _ _ , . .
. -EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.3 5 'o'f 16 Pace RESCUE AND EMERGENCY REPAIR WORK Revision 2 Date 5/27/83 a) If no significantly increased radiation levels are. indicated by the Area Radiation Monitors ( ARMS), projected exposures can be estimated by reviewing the latest survey forms, RWPs and ARM readings coupled with estimated time to conduct rescue activities.
b) If significant radiation levels are i'ndicated, ie, Hi Hi or
. upscale ARM indications and/or elevated Containment High Rance Radiation monitor readinas, an estimate of projected exposures can be made by reviewing the Shielding Study or reviewing the results of accident analyses contained in Chaoter 15 of the UFW
*, coupled with estimated time to conduct rescue activities.
NOTE A listing of the ARMS, their locations and ranges is provided on Attachment 2, " ARM Locations". 4.2.3 In estimating projected exposures consideration needs to be given to ingress / egress routes and expected dose rates which may be encountered en route. NOTE Operations personnel should be consulted when evaluating ingress / egress routes due to their familiarity with physical layout considerations and awareness of how such routes may be impacted due to changing plant conditions. 4.2.4 The Site Radiation Protection Coordinator shall propose cnanges to the established DAEC Administrative limits, if warranted. a) Approval authority for such increased limits shall be as specified in paragraph 4.1.3. b) The increased limits, the individuals to whom such limits acoly and the name of the individual who authorized such limits shall be documented in the TSC Supervisor's loc. NOTE During an emergency, the normal process of requesting and approving increased exposure limits, prescribed in RPP 4.1,
" Personnel Exposure Records", need not be followed.
4.2.5 The exposure records of personnel assigned to the rescue team should l be reviewed to insure that the projected exposure to ce received durina rescue activities will not result in any memoer of the team l exceeding the limits defined by 10CFR20.101. i a) Team membershio should be modified if personnel assigned are approaching such limits. I
. o EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.3 -- s .~
Page 7 of 16 RESCUE AND EMERGENCY REPAIR WORK Revision 2 Date 5/27/83 b) Team membership shall be comprised of volunteers if projecteG exposures for the proposed rescue activities will cause personnel exposures to exceed limits specified in 10CFR20.101. NOTE Documentation that individuals so assigned are volunteers and that they understand the risks and limits established for the i assignment shall be recorded in the TSC Supervisor's log along l with the names of the volunteers. , c) If significant airborne iodine activity is anticipated, j j consideration in EPIP 4.5, " should be givenoftoPotassium Administration thyroid blocking Iodide (, KI)". as prescribed NOTE l Guidance with respect to implementation of emergency exposure limits and use of volunteers is contained in Attachment 3,
" Guidelines Regarding Selection of Volunteers".
4.2.6 Rescue teams should be comprised of the following cersonnelt a) One Health Physics Technician, b) Two individuals, knowledgeable in first aid techniques. c) Additional personnel as specified by the Security and Suoport Supervisor to support search and rescue activities. 4.2.7 Prior to dispatch of a rescue team, the OSC Supervisor shall ensure that a briefing, as described in paragraph 4.1.5, is conducted, a) The Site Radiation Protection Coordinator or his designee should brief team personnel regarding expected radiological hazaros, limits which are applicable, considerations associated with injured personnel who may be contaminated with open wounds and/or in high radiation fields, and communications recuirements. b) The Security Suoervisor should check to insure that first aio personnel have equipment and supplies expecteo to be necessary and are f amiliar with techniques which may be recuired. I 4.2.8 Communications between the rescue team and the OSC Supervisor should be conducted usina the'0perations Radio. NOTE Backup systems include the plant paging system and standard telephone. m
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.3 Pace 8 of 16 ~: RESCUE AND EMERGENCY REPAIR WORK Revision 2 Date 5/27/83 4.2.9 The OSC Supervisor will then dispatch and direct the rescue teams ' upon being authorized by the Emeroency Coordinator. NOTE l Authorization for dispatch of the team shall be recorded in the OSC Supervisor's-log. 4.2.10 While en route, the Health Physics Technician shall: a) Monitor ahead of the team to detect areas 6f high radiatien. o b) Monitor total dose for each team member. NOTE Health Physics personnel should perform monitoring functions only and will not be involved in actual rescue activities. 4.2.11 Upon locating the missing individual (s): a) The extent of injuries, if any, should be determined. b)1 The OSC Supervisor shall be advised. 4.2.12 If no injuries were sustained, the individual shall be escorted back to the OSC. 4.2.13. If injuries are evident, treatment priorities shall be b= sed on the radiological and the medical condition of the injured. a) Such determination should be made jointly bete,een the Health , Physics Technician and First Aid personnel, b) If both the injury and level of radiation is life threatening, the victim should first be relocated to a " safe" radiation area, then first aid treatment administered. NOTE i As a general rule, consideration should be given to innediately relocating a victim if the radiation level is >25 R/hr. c) If the injury is life threatening but the level of radiation is not, immediate first aid treatment should be Drovided. d) If the injury is not life threatenino, priority should he 3iven to relocating the victim to a safe area, oreferably the First Aic Room, before administerina first aid. l 1
o o EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.3 -- .
~
Page 9 of 16 RESCUE AND EMERGENCY REPAIR WORK Revision 2 Date 5/27/83 4.2.14 Unless directed otherwise curing the briefinq or durino subsequent l connurications with the OSC Supervisor, rescue teams 'should return with the injured to the Health Physics Access Control area. 4.2.15 Additional medical treatment and documentation of injuries, radioloaical problems and the like shall be performed, as prescribed in 'EPIP 4.2, "First Aid, Decontamination, and Medical Suoport". 4.3 Emeroency Reoair 4.3.1 Equipment malfunctions, operational trends and proposed corrective e actions should be transmitted to the TSC Supervisor and Technical and Engineering Supervisor by the Control Room Coordinator, as prescrited in EPIP 2.2, " Activation and Operation of the TSC". 4.3.2 Corrective action options which may include emergency repair and damaoe control activities should be evaluated and developed by the Technical and Engineering Supervisor. 4.3.3 For those response options which will reouire personnel access into radiation areas in the plant, an assessment of the potential radiological exposures should be conducted, as prescribed in paragraohs 4.2.2 and 4.2.3. NOTE l In planning the repair / damage control effort, ALARA considerations may dictate staging the activities in several steps; hence, multiple entries, ie., a reentry for assessment purposes, another to place shielding or conduct the initial j l action steps, and another to perform or complete the activity. 4.3.4 The benefit to be derived by accomplishing the proposed repair /damace control activity should be evaluated considering: I a) The magnitude and/or duration of the potential or actual radiological release if the repair / damage control activity is not performed. b) The associated del'ay or inability to establish control of the l plant and/or restore stable conditions. l c) The maonitude of the projected exposure to the oublic calculated in accordance with PASAP 7.4, " Estimation of Potential Release Rate", and EPIP 3J3. d) Exposures received by skilled personnel durinc cerformance of tne ! I I activity wnich may make them unavailable for further assignments. w 3 1
a . EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.3
^ '
Pace 10 'of 16 RESCUE AND EMERGENCY REPAIR WORK Revision 2 Date 5/27/83 4.3.5 Where severa'l courses of action can be taken, the Emergency Coordinator shall determine which option is to be pursued. N,!g,T,E, l Standard practices in effect at the D,AEC should,be employed during emergency repair / damage control activities, unless:
- 1) Approval of the Emergency Response and Recovery Director is obtained.
. 2) Deviation from such standard practices are documented as non-conformances under the direction of the Manager,-Quality Assurance. 4.3.6 If the course of action selected will result in emergency reoai. teatr personnel exceeding the OAEC Administrative exposure limits, such limits should be changed, as prescribed in paracraph 4.2.4 4.3.7 ' Personnel initially assigned to emergency repair work by the Emergency Assignment Tag Board, defined in EPIP 2.1, " Activation and Operation of the OSC", include: a) One Mechanic, one Instrument and Controls Technician and two Electricians. b) Additionally, one Health Physics Technician should be assigned for emergency repair work if work must be accomolished in a radiation area.
-4.3.8 The Technical and Engineering Supervisor should verify that individuals to be assigned to emergency repair work by the Emercency Assignment Tag Board are appropriately qualified to execute the desired activities.
4.3.9 The composition of emergency repair teams should be modified based upon the considerations defined in paraaraph 4.2.5 and 4.3.8. a) The T.echnical and Engineering Supervisor shall redesianate, as necessary, the individuals to be assigned. b) The OSC Suoervisor shall insure that personnel so identified are available and ready for such assignment. 4.3.10 Prior to dispatch of an emergency repair team, the OSC Suoervisor shall ensure that a briefing as described in caracraoh 4.1.5 is conducted. a) The Site Radiation Protection Coordinator or his desionee shoub brief team personnel recardina expected radi.ological hazards and i l limits which are applicable. ~ , i i I
. o EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.3 ,, ,,,
Page 11 of 16 RESCUE AND EMERGENCY REPAIR WORK Revision 2 Cate 5/27/33 b) The Technical and Engineering Supervisor or his designes should insure that team personnel understand the repair or damage i control functions to be performed, actions to take if other than expected conditions are discovered, and communications requirements. 4.3.11 Communications between the emergency reoai- team and the Technical and Engineering Suoervisor should be conducted using the Operations Radio. NOTE o Backup systems include the plant paging system and standard telephone. 4.3.12 The OSC Supervisor shall dispatch the emergency recair team upon receiving authorization from the Emergency Coordinator. NOTE Authorization for dispatchment of the team shall be recorded in the OSC Supervisor's log. 4.3.13 Monitoring shall be performed by the Health Physics Technician, as specified in paragraph 4.2.10. 4.3.14 Emergency repair or damage control activities shall be conducted in l accordance with the instructions provided during the briefina. l i a) Problems encountered or unexpected conditions discovered should i be reported to the Technical and Engineering Supervisor. b) The Technical and Engineering Supervisor snall coordinate emergency repair team activities, as required, with the Control Room Coordinator. 4.3.15 Upon completion of emergency repair / damage control activities or as otherwise directed, emergency repair team memoers snall return to the OSC. a) Normal radiation protection practices shall be observed at the access area unless otherwise directed by the OSC Supervisor. T-'r w W V ry- y y
a . EMERGENCY-PLAN IMPLEMENTING PROCEDURE EPIP 4.3 Pace 12 'of 16 ^~ ! RESCUE AND EMERGENCY REPAIR WORK Revision 2 Date 5/27/83 b) Decontamination, if required, shall be performed in accordance with the requirements defined in EPIP 4.2, "First Aid, Decontamination, and Medical Support". 4.3.16 Eme,gency repair and damage control activities conducted shall be documented in the TSC Supervisor's log.
5.0 REFERENCES
5.1 Duane Arnold Energy Center Emercancy Plan . 5.2 EPA Protective Actions Manual 5.3 Radiation Protection Procedure 13.1, " Radiation Emergencies". 6.0 ATTACHMENTS 6.1 Attachment 1 - External Exposure Limits l I 6.2 Attachment 2 - ARM Locations I i 6.3 Attachment 3 - Guidelines Regarding Selection of Volunteers Aoproved by: DATI: m h, /f 8 3 EneMency Planni Cooroinator 4 y ' Aoproved by: N 'k . .' ' ' I- >s- DATE: Radiation Protection Supervisor O Approved by: i.[ DATE: r, /w/p 3 Assistap Flant Superintencent-Technical Support / Reviewed by: <- twe DATE: /,/ t 7 / p 3 ' ALARA Cooroinator Q y/ f3 Reviewed by: vbb/ s committee DATE: L.n a i rma<1, voeratiop Acoroved by: DATE: 7 f 3 P1 ant huoerintencent - Nuciear
. o EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.3 -. . . .
Page 13 of 16 RESCUE AND EMERGENCY REPAIR WORK Revision 2 Date 5/27/83 ATTACHMENT 1 EXTERNAL tXFubunt LIMITS Habitability Administrative 10CFR20.101 EPA Limits (l) Exposure Exposure Guidelines (3) Limits (2) Limits (2) d 24 hour / day Occupancy 6 mrem /hr 12 hour / day Occupancy 12 mrem /hr
, 8 hour / day Occupancy 19 mrem /hr _
Per Day 150 mrem Per Week 300 mrem Per Quarter 1 rem 3 rem (4) Per Year 0.5 rem 5 rem Note (4) _ Airborne 1 X 10-9pC1/cc. _ Contamination 1000 dpm/100cm2 -( 250 dpm/100cm2 oc To reduce hazard potential to acceptable level 25 r m To save : lives NOTES: (1) For further information refer, to RPP (2) -For further information, including standard requirements acolicable to authorizing increased limits, refer to RPP 2.1, " Personnel Exposure Limits"; RPP 4.1, " Personnel Exposure Records"; and RPP 13.1, " Radiation Emeroencies". (3) For further information, refer to Chapter 2 of the Manual for Protective Action Guide and Protective Actions for Nuclear Incidents. (4) Imolementation of such increased exposure limits is depenoent uoan each individual's exposure history and total whole body occupational dose to date. For further information, refer to RPP 2.1, " Personnel Exposure Limits". (5) In addition, limits for projected thyroid dose have been estaclished, as follows: Emeroency Repair Work 125 rem Life Saving Activities No Soecific Uoper Limit For further information, refer to RPP 13.1, " Radiation Emergencies". 2 ? --we w" w , ~ w ,y v w"- wwA a-vw ' y -ve-
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.3 Page 14 'of 16 ': RESCUE AND EMERGENCY REPAIR WORK Revision 2 Date 5/27/83. ATTACHMENT 2 , ARM Locations
- Reactor Buildino Units j Number Location Elevation Ranoe(mR/hr) Descriotion
- 1. RT 9168 North CR0 Module Area 757'6" 10 103 Outside airlock to Access Control CR0 Repair Room 757'6" 10 103 Northwest wall, behind
- 2. RT 9170 o door South Equipment Railroad 757'6" 10 103 West wall, near inner
- 3. RT 9167 Access RX.81 Truck Lock Door South CR0 Module Area 757'6" 10 103 South wall, near airlock
- 4. RT 9169 757'6" 100 104 North wall, inside caoe
- 5. RT 9176 TIP Cubicle area
- 6. RT 9177 Cleanup Phase Separators 786'0" 100 - 104 East wall of CU Phase Work Area Separator Room
- 7. RT 9173 Cle'anup System Resin 786'0" 10 103 East wall of CU Discharca Mixer Pump Room Handling Area
- 8. RT 9157 Cleanup Heat Exchangers 786'0" 102 - 106 Inside airlock to RWCU Heat Exchancer Room
- 9. RT 9156 Cleanup Recirculation 876'0" 102 - 106 Inside Door to RWCU Pumo 1 Pump Area Room
- 10. RT 9155 Cleanup Demineralizer 812'0" 102 - 106 East wall of Filter Work Area Demin. Room
- 11. RT 9171 Ventilation Equipment Area 812'0" 10 103 Inside 2nd airlock door to Rx. Bldg. Exhaust Fan Room i
Condensate Phase Separator 833'6" 10 103 Inside door, along west
- 12. RT 9175 Pumps wall of Cond. Phase Sec.
Room 855'0" 10 102 West stairway wall,
- 13. RT 9163 Refuel Floor-North End Refuel 955'0" 10 102 North stairway wall,
- 14. RT 9164 Refuel Floor-South End Refuel
- 15. RT 9153 New Fuel Storage Area 855'0" 10 103 North end of Storace Pit at Instrument canel
*With remote readout (Control Room) -
a O EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.3 Page 15 ~o'f 16 RESCUE AND EMERGENCY REPAIR WORK Revision 2 Date 5/27/33 l
.. ATTACHMENT 2 (Continued) .
l ARM Locatiens* Reactor Buildino Units , Number location Elevation Range (mR/hr) Descriotion
- 6. RT 9178 Spent Fuel Storage Pool 855'0" 100 - 104 N.E. rail around Fuel Fool Waste Collecting Tank Area 737'0" 100 - 104 S.E. Corner Room, North
- 17. RT 9180 wall inside second door O
716'9" 10 103 S.W. Corner Room, alona I
- 18. RT 9166 Radwaste Pumo Room south wall near corner Turbine Buildino Units Reactor Feedwater Pump Area 734'0" ~10 103 North Condenser Bay wall ;
- 19. RT 9159 I Turbine Lube Oil Area 734'0" 10 103 East corridor wall
- 20. RT 9160 Condensate Pump Area 734'0" 10 103 Mounted on girder near
'1. RT 9158 Condensate Pumps Sump Area 734'0" 10 103- Acid & Caustic Tank, S.I. !
- 22. RT 9174 Corner of Turbine 31do.'
l l Turbine Front Standard 780'0" 100 - 104 Along east shield wall at j
- 23. RT 9179 j offset Radwaste Suilding Units ,
786'0" 10 103 South wall, near coor
- 24. RT 9151 Radwaste Control Room Sample Tank and Pump Floor 786'0" 10 103 North wall of Centrifuge
- 25. RT 9152 Room Radwaste Drumming Area 757'6" 10 103 At middle of west wall
- 26. RT 9154 ,
Other Units 786'0" 10 102 Control Building
- 27. RT 9162 Control Room (west wall) 786'0" 10 103 Control Sida., west wall
- 28. RT 9172 Radiological Chemistry Laboratory of hot lab 757'6" 10 102 Machine Shoo Building
- 29. RT 9161 Machine Shop ;
Site Entry and Exit 757'6" 10 102 Entrance to Admin. 310a.
- 30. RT 9165
*With remote readout (Control Room)
e . EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.3 Page 16 o~f 16 ': RESCUE AND EMERGENCY REPAIR WORK Revision 2 Date 5/27/83 ATTACHMENT 3 , GUIDELINES REGARDING SELECTION OF VOLUNTEERS
- Rescue personnel should be volunteers or professional rescue personnel who !
volunteer by choice of employment.
- Rescue personnel should be broadly familiar with consequences of the I exposure. l l
o - Women capable of reproduction should not take part in these actions.
- Volunteers above the age of 45 should be selected.
l l
- Internal exposure should be minimized by the use of the best available i
; respiratory protection (positive pressure self-contained breathing apparatus) and contamination should be controlled by the use of protective clothing.
- Exposure under these conditions shall be limited to once in a lifetime.
1
- Persons receiving exposures as indicated should avoid procreation for a few !
months.
- Medical follow-up should be considered depending on the magnitude of the !
exposure. l NOTES l
- 1. Exposure limits in excess of those permitted in 10CFR20.101 should be authorized only as a last resort. j
- 2. Dose limits can not be specified but must be commensurate with the significance of the. objective and held to as low as is reasonably achievable.
- 3. It is compatible with the risk concept to accept exposures leadino to doses in excess of those permitted for routine occupational duties, when .
involved in a major accident for tne following activities: l a) Measures to circumvent substantial exposures to population groups. j l b) Recovery of victims /saving of a life. ! 4 Maximum limits for planned whole body emergency doses to personnel are as follows: a) 25 rem (25,000 meem) to reduce hazard potential to acceotable levels. b) 75 rem (75,000 mrem) to save lives. .
e ' EMERGENCY PLAN' IMPLEMENTING PROCEDURE E?IP 4.5f .
'l Page ~ ~l of 6 t Revision 'e ADMINISTRATION OF POTASSIUM IODIDE (KI) 1 ,,
! /
Date 3/15/,23 , ,;-,
. - \ i t
?
'! ,f '
1.0 PURPOSE . ,
+
l.1 This procedure provides guidance for recommending a'nd '- ,superv/ising / ./_ ,'7' administration of potassium iodide (KI). , . ,- ,d
.f -
. y c f p '
,',- f 2.0 APPLICABILITY , ,
~ ~
2.1 This procedure applies to onsite emergency workers whose estimated tothi - absorbed dose to the thyroid from inhaling airborne radiciodine could ' , ' ' exceed 25 rem. r
,l 3.0 RESPONSIBILITIES ', '!
~
C 3.1 Site Radiation Protection Coordinator y .'l', 4 3.1.1 Verify that personnel who may require admin stration of KI have completed the form entitledr" Medical Questi annaire: Iodine d
/
h Sensitivity." T' 3.1.2 Make recommendations to the.. Emergency Coordinator for - i administration of KI. >'hi , f N
'. : , i t . 's 3.1.3 Supervise the administration of KI. , <
,(,
t/ t e. 3.2 Emergency Coordinator
~
. . . /.
3.2.1 AuthorizetheuseofKIwhenceemed'appdsoriate. [-
; .}'.'
l 4.0 INSTRUCTIONS 4.1 The. Site Radiation Protection Coordinator sh'ould evaluate /.he projected individual thyroid doses which may be received to determine if the dose to the thyroid may exceed 25 rem. , N01E g Doses to the thyroid from the inhalation of radiciodine can be- 1 estimated :using Attachment'1, " Projected Cumulative Do'sts to the Thyroid."' ( / 4.2 The indivictual's Medical Questionnaire-11 dine Sensitivity form shMid he reviewed to insure that an adverse react >on to iodine has not beer, ,- experienced nor is projected. ' * [ [ i -
'h0TE t ,
This form is included in RPP 3.2,'Obtain ng and Using Personal' the course' of General Dosimetry", Employee Training and(GET).should be c.ompleted durin'g/ , f g ' 1 \,
\f a L u d 1 i h
. yry- d ,_
- . . - - . - - - . - - _m. . . _ . g, _._.,) !. , , . _ _,
,, ~#, g '* ,, i p-EMERGENCY PcAN IMPLEMENTING PROCEDUl%2 /~ EPIP 4.5
.r' Page .2 of 6
{j fm g ..
$ f.
- f. , ,,s . ADMINI,STRAlION OF r*0TASSILM IODIDE,3NI)
~
Revision 1 s (
,,b 7
,g
/\4 Date 3/15/83
/ -
e 4.2.1 The tiodine questionnaire sh uld be maintained in the individual's
'/ -
j er onrbj Expp5ure Record" file folder.
'I~" I 4.2.2 If.a raction to dodine h indicated on the form or if no form
./
/can be located, the. indivfdual should not be selected for an f (l'
; /. / assignment which 6 y result in'a dose to the thyroid of 25 rem.
e i t'
, ,,a NOTE/ t
. ', </
e */ ./Indfviduals who may exhibit an'ady;se reaction to iodine should x ,1 tre evacuated from any area where sitch a dose may be projected. 4.3 If th projected dor' to the thyroid exceeds 25 rem and if the form indicates no adverse reaction 4.3.1 Obtain approval from the Emergency Coordinator to initiate a dose j ( regimen of KI. -- 4.3.2 Provide the individual to be administereci KI with a copy of Attachment 2, "The Food and Drug Administration Approved Package InsV t", for review. . j i ( 4.4 Eae. individual to be provided KI shall be issued one tablet. ij - - ff'4.4.1 A~ supply-of KI is stored in the First Aid Facility located in the
- f~ C f. . f Operational Support Center. In addition, each off-site monitoring team is provided with a bottle of KI tablets.
a) KI has an approved shelf-life with the expiration date listed on each bottle. , g ' '. ,
- c. b) To ensure that the KI supply is valid, these dates will be
- inspected during the inventory of the first aid room and the
, !, emergency cabinets and the bottles replaced as necessary.
..e ,
t
.r. L e E
- 4. 4.2 The information required by Attachment 3, " Potassium Iodide Issue Report", shall be filled in.
!t. r ,
,l ,
f 4.4.3 'The Medical Consultant shall be advised within 24 hours of all t ,. i f , individuals who have initiated the dose regimen of KI.
<4. 5 The dose regimen of KI chould not be continued for a ceriod of time in 7
3 excess of 10 days unless directed otherwise by the Medical Consultant. 4.5.1,"If the dose to the thyroid is determined to be less than 25 rem, g 4 continuation of the dose regimen normally will not be necessary. 4.5>.2-)Ifthedosetothethyroidisconfirmedtobegreaterthan25 l yem, the Medical ConsuTcant shall be advised. I r (
, ( 4 gt ,
'~
\ ,
, ;j
< .u - a.
l 1 ,.
, i
e o EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP _ . 4.5 .. Page 3 of 6 ADMINISTRATION OF POTASSIUM IODIDE (KI) Revision 1 Date 3/15/83
~
5.0 REFERENCES
5.1 Duane Arnold Energy Center Emergency Plan 5.2 Iowa Electric Light and Power Company Corporate Emergency Response Plan - 6.0 ATTACHMENTS i 6.1 Projected Cumulative Doses to the Thyroid 6.2 The Food and Drug Administration Approved Package Insert 6.3 Potas "- Todide (K i Ir!o Report D Approved b Date /e6 3 O/
' Emergency P i ng h njsg8f-Approved by l}1) 0ffm Radialtion Pr ctionppervisor Date S Y SS Reviewed by /b_ < m 1v Date S/c//93 [
ALARA Coordinator (g Reviewed by: h Date /6![3 Operations ommittee Chairman Approved by /ft/( p Date !M 3 Plant Sup intende Nuclear 2 w - - - e , w
L. * - t i l EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.5 -- j- Page 4 of 6 ADMINISTRATION OF POTASSIUM IODIDE (KI) Revision 1-Date 3/15/83 ATTACHMENT 1 PROJECTED CUMULATIVE DOSES TO THE THYROID 10* . -7
-i l
\
x, m N
,ieiei . . , ii.ti .
)j
\ h (N I ( : I llaault i l I !1IIli I -:
,- (
\l hIll s ! llll l
. \ \ - .
_.10 -2
.fg s k s \ % ., l 1k-,
! " ~ ~ .'
- g. -
. ~.4
,a 7-'
s , ',.], s , !g ) N %_ N. . ,1, o se . .i i .
\ I kl i Nt f 1 *M N \_ l t ii91i I
( \j f\l l 1\j 11 ~N,I\l \11!!Ilchild1 -2 a- .\ IN NJilM K
, s N NIII :,;*i' s s s..
\ - _
x\ s :\ N It\ lx N~~ . k
. 71,:_s i pr y 7-
~
i <
.' . 6 I g , .s s. .s ._- s , - s ~ LJ l a Ni N . N1. N e Na1 i e \r.4' v s
g m ql g I \ h i N i (N I fk a \ l 'i i i IN I M*8 \ -: j
,, < N klMllN.NI \ l NIIIN#. i\ h I I
I.',\ s s s s N %q ,s ,
-}}