ML20055B171
| ML20055B171 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 05/31/1982 |
| From: | DETROIT EDISON CO. |
| To: | |
| Shared Package | |
| ML20055B158 | List: |
| References | |
| PROC-820531-01, NUDOCS 8207200443 | |
| Download: ML20055B171 (603) | |
Text
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FNRICO FERMI ATOMIC POWER PLANT UNIT NO 2 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX EP. NO. TITLE REVISION 100 Series Classification of Emergencies and Control of Emergency Response 101 Classification of Emergencies 0.B (May 82) 102 Unusual Event 0.B (May 82) 103 Alert 0.B (May 82) 104 Site Area Emergency 0.B (May 82) 105 General Emergency 0.B (May 82) 110 Organization and Responsibilities 0.B (May 82) 111 Recovery Organization 0.B (May 82) O
ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX (CONTINUED) EP. NO. TITLE REVISION 200 Series Emergency Organizations and Organizational Response 201 On-Site Radiological Emergency Team 201-1 Activation 0.B (May 82) 201-2 Functions 0.B (May 82) 202 Personnel Monitoring Team 202-1 Activation 0.B (May 82) 202-2 Functions 0.B (May 82) O
ENRICO FERMI ATOMIC POWER PLANT s. UNIT NO. 2 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX (CONTINUED) EP. NO. TITLE REVISION 203 Fire Brigade 203-1 Activation 0.B (May 82) 203-2 Fire Involving Radiological 0.B (May 82) Hazards 204 Damage and Rescue Team 204-1 Activation 0.B (May 82) 204-2 Disaster 0.B (May 82) 204-10 Search and Rescue 0.B (May 82) 204-30 Evacuation 0.B (May 82) 205 Security Force 205-1 Response for Fire, Disaster, or 0.B (May,82) Radiological Emergency 205-2 Control of In-plant Access for 0.B (May 82) Emergency Response Personnel 205-3 Control of Site Area Access 0.B (May 82) During Fire, Disaster, or - O 205-4 Radiological Emergency Security Emergency During Fire, Disaster, or Radiological C.3 (May 82) Emergency 205-30 Evacuation, 0.B (May 82) 210 Off-Site Radiological Emergency Team 210-1 Activation 0.B (May 82) 210-2 Functions 0.B (May 82) 290 Emergency Notifications 0.B (May 82)
ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX (CONTINUED) EP. NO. TITLE REVISION 300 Series Emergency Facilities 301 Technical Support Center 301-1 Activation 0.B (May 82) 301-2 Support Functions 0.B (May 82) 302 Operations Support Center 302-1 Activation 0.B (May 82) 303 Emergency Operations Facility 303-1 Activation 0.B (May 82) 303-2 Support Functions 0.B (May 82) 303-3 Manual Dose Assessment 0.B (May 82) Calculation Procedure 303-4 Protective Action Guidelines (later) O O
ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX (CONTINUED) EP. NO. TITLE REVISION 400 Series Recovery Actions 401 Reentry 0.B (May 82) 402 Recovery 0.B (May 82) O O
O ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX (CONTINUED) EP. NO. TITLE REVISION 500 Series Miscellaneous 530 Evacuation 0.B (May 82) e c, O
() ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 EMERGENCY PLAN ADMINISTRATIVE PROCEDURES INDEX EPA NO. TITLE REVISION 1 Procedure Preparation, Review, 0.B (May 82) Approval, Ch.ange, Revision, Cancellation, Control and Distribution 2 Periodic Review of Emergency 0.B (May 82) Plan Procedures 3 Review and Revision of Emergency 0.B (May 82) Plan 4 Exercises and Drills 0.B (May 82) 5 Emergency Equipment Inventory 0.B (May 82) O O i '
EP-101 Rev. 0.B ('} ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
CLASSIFICATION OF EMERGENCIES RECORD OF APPROVA D CHANGES
/
d Submitted by _ Supervisor of Rad (ogpgical Emergency Date Response Prepared qs Approved by b Chairman - Liaig6n Committee Date Liaison Committee nssRevision No. Submitted Date Approval Date 1 2 3 4 5 6 7 8 O
_. _ _ _ . . . _ . _ _ . . _ . _ . . . _ . . _ _ _ . _ . . _ _ _ _ _ _ _ _ _ _ . . . . . _ . ~ . . . _ _ . . . 1 .. EP-101 l Rev. 0.B l l a l l ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE i
Title:
CLASSIFICATION OF EMERGENCIES l i l i \ l l i F l { i f 4
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l _. -. I t EP-101 Rev. 0.B CLASSIFICATION OF EMERGENCIES I TABLE OF CONTENTS Page 1.0 Entry Conditions . ..................................... 1 2.0 General Information ................................... 1 3.0 Procedure ............................................. 2 Enclosures Guide to Classifying Emergencies.................... Enclosure 1 Emergency' Action Levels............................. Enclosure 2 Attachments Emergency Team and Security Force Activation j Matrix.......................................... Attachment 1 i 1 I t l 1 f 1
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l s EP-101 O% Rev. 0.B Page 1 1.0 Entry Conditions Any of the following events occur:
- 1. Unusual Natural Phenomena.
- 2. Earthquake, Natural Disaster, Explosion, Aircraft Crash, or Other Disaster.
- 3. Fire on Site.
- 4. Loss of Electrical Power.
- 5. Loss of Alarms or Indications.
- 6. Compromise of Plant Control.
- 7. Reactor Coolant Leakage or NSSS Steamline Break.
- 8. High Radiological Effluent.
(~} 9. Fuel Damage or Abnormally High Area Radiation.
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- 10. Degradation of Safety or Protective System 2.0 General Information 2.1 The Emergency Director shall not delegate the following responsibilities.
2.1.1 Classification or reclassification of the emergency. 2.1.2 Decision to order Plant Area, Protected Area or Site Area Evacuation. 2.1.3 Authorizing emergency response personnel to exceed radiation exposure limits delineated in 10CFR20. 2.2 Ultimate responsibility for assessment of emergency conditions and for directing on-site protective actions rests with the Emergency Director. The judgement of the Emergency Director is paramount in proper control of the emergency and may take precedence over guidelines in this procedure. O~/
l EP-101 Rev. 0.B Page 2 2.3 Classification of an emergency is accomplished by utilizing Enclosure 1 (Guide to Classifying Emergencies) and, if necessary, Enclosure 2 (Emergency Action Levels). Enclosure 1 is a flow chart which shows general symptoms and their classification. Enclosure 1 also references sections of Enclosure 2 to aid in classification of the emergency. The Emergency Director may classify the emergency by using Enclosure 1, or Enclosure 2, or a combination of Enclosure 1 and Enclosure 2. 3.0 Procedure The Nuclear Shift Supervisor shall: 3.1 Ensure that the immediate actions of applicable Abnormal and Emergency Operations Procedures are performed. 3.2 Assess the emergency conditions and determine the type and location of personnel hazards. 3.3 Order an evacuation of unnecessary personnel from those areas with actual or potential abnormal personnel hazards. 3.4 Activate emergency teams as necessary to respond to the emergency conditions (see Attachment 1). 3.5 Using Enclosure 1 (Guide to Classifying Emergencies) , assess plant conditions and classify the emergency. The Section numbers listed in Enclosure 1 refer to the applicable Sections of Enclosure 2 (Emergency Action Levels) which provide additional criteria for classifying each emergency. NOTE: If several emergency events occur simultane ously, the most serious emergency classifi-cation determines the overall classification. 3.6 If the emergency meets the criteria of one of the four emergency classifications, assume the position of Emergency Director and carry out the applicable Emergency Plan Implementing Procedure: Unusual Event EP-102 Alert EP-103 Site Area Emergency EP-104 General Emergency EP-105
I EP-101 Rev. 0.B Page 3 NOTE: The Emergency Director must be alert to degrading emergency conditions. He should keep in mind the criteria for classifying the emergency listed in Enclosure 1 and 'should be especially alert to changes in the applicable indicacions. He must periodically review Enclosure 1 to ensure proper classification of the emergency. 3.7 If the emergency situation is not classified as one of the four emergency classifications, no further actions under the Radiological Emergency Response Plan are required. O O L.__. _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ - _ . _ - _ _ _ - _ - - _ _ - _ _ - - _ _ - _ _ _ - - - _ _ - - - _ - _ _ _ -- - .
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- ft:CH. SPEC. INSTANTANF.OUS LIMITS SECTION Ill.A __ __
UNUSUAL EVENT ! RADIOtJMIICAL F.FFLUENT > 10 TIMES TECH. SPEC. INSTANTANEOUS LIMITS SECTION III.R
- e >* ALERT Fur! HANDLING ACCIDENT RESULTIPKI IN RADIOACTIVE RELEASE TO THE REACTOR HO !!.I)I NG HECTION III.C __
ALERT MAJOR DAMAGE "IU SPElff FUEL IN REACTOR ButlEING SECTION III.D , _ SITE AREA EMERGENCY I PitOJECTED WHOLE BODY DOSC RATE SECTION III.E
- 6 *> SITE AREA FMERGENCY FIEth READINGS SECTION III.F SITE AREA EMERGENCY PHOJECTED DOSE _) I REM WHOLE BODY OR 5 REM THYROID ON SITE SECTION III.G SITE AREA EMERGENCY j PROJECTED DOSE > I REM WHOLE BODY OR 5 REM THYROID AT THE SITE BOUNDARI SECTION IIT.H p GENERAI. EMERGENCY PROJECTED / MEASURED DOSE RATE > I REM /HR WHOLE BODY OR 5 REM /HR THYROID AT THE 4 SITE HOUNDARY OR BEYOND SECTION III.I GENERAL EMERGENCY G >
? tutt UANAbl/HibH MADIAllud i FUEL DAMAGE INDICATION SECTION I.A UNUSUAL EVENT SEVERE IDSS OF FUEL CLADDING SECTION I.B ALERT SIGNIFICANT INCREASE IN RADIATION OR AIRBORNE ACTIVITY LEVELS SECTION I.C ALERT FUEL HANDLING ACCIDENT RESULTING IN RADIOACTIVE RELF.ASE TO REACTOR BLDG. SECTION I!!.C ALggy MAJOR DAMAGE 10 SPENT FUEL IN REACTOR BUILDING. SECTION III.D SITE AREA EMERGENCY
; DEGRADED CORE WITH POSSIBLE LOSS OF COOLABLE GEOMETRY. SECTION I.C SITE AREA EMERGENCY 4
1 9 > IDSS OF TWO FISSION PRODUCT BARRIERS POTENTIAL LOSS OF THIRD BARRIER SECTION 11.0 GENERAL EMERGENCY ] PLANT CONDITION WITH THE POTENTIAL FOR CAUSING LARGE RELEASE OF RADIOACTIVITY j , SECTION II. Pfo/R/S jf_ 4,, , GENEAAL EMERGENCY 9 EQ
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bujy!. 10 Q AMjt}1, W _l@ $ts! % lQ utbuutb LAttly/WUltulVt )Y4llH rers ^i!TOMATIC IN{TIAT!pN FLOW 'D) VESSEL SECTION~~II.A ' UNUSUAL EVENT ECCS MANilAL-NONTEST I,N ITI AT,10N __ _ , _ _F_AILtlHE OF SAFETY HELIEF VALVE 'D} _HESET SECTION !!.B __ , . _ , UNUSUAL EVENT AHNORMAL COOLANT TEMPERATURE OR PHESSURE OUTSIt)E OF TECHNICAL SPECIFICATION _ t}PERATIONAL I.IMITS SECTION,_I_I { _ _ _ __ _ _ _ _ , _ _ UNUSIIAL EVENT _ t]ONTAMINATEI) INJUNED PENSONS HEQtlIRING OFFSITE MEDICAL TREATMENT SECTION II.C ___ UNU30AL EVENT IA)SS OF CONTAINMENT INTECHITY REQti!NING PLANT SHUTDOWN BY TECHNICAL SPECIFICATIONS SENION II.D UNUSUAL EVENT InSS OF ANY ESP SYSTEMS HEOUIRING PLANT SHUT!X)WN BY TECHNICAL SPECIFICATIONS SECTION II.E UNUSUAL EVENT POTENTIALLY SAFETY-DEGRADING EVENT SECTION II.C UNUSUAL EVENT COMPLETE LOSS OF ANY FUNCTION ESSENTIAL FOR PLANT COLD SHUTDOWN SECTION II.H ALERT FAILURE OF RPS M INITI ATE AND COMPLETE A SCRAM AND/OR FAILURE OF MANUAL SCRAM TO BRING THE REACTOR SURCRITICAL SECTION II.1 ALERT G D' EVENTS INVOLVING ACTUAL OR POTENTIAL SURSTANTIAL PLANT SAFETY DEGRADATION SECTION II.J ALERT EVACUATION OF CONTROL ROOM ANTICIPATED / REQUIRED WITH CONTROL OF SHUTDOWN SYSTEMS ESTABLISHED FROM IDCAL STATIONS SECTION II.K. ALERT COMPLETE IDSS OF ANY F1.J NCTION ESSENTIAL FOR PLANT HOT SHUTDOWN SECTION II.L SITE AREA EMERGENCY PLANT TRANSIENT REQUIRING EPS FAILURE M SCRAM (NO CORE DAMAGE) SECTION II.M SITE AREA EMERGENCY EVACUATION OF CONTROL ROOM AND CONTROL OF SHUTDOWN SYSTEMS NOT ESTABLISHED FROM LOCAL STATIONS IN 15 MINUTES SECTIO.1 II.N SITE AREA EMERGENCY MAJOR INTERNAL OR EXTERNAL EVENT CAUSING MASSIVE COMMON UNSAFE DAMAGE SECTION II.T GENERAL EMERGENCY O > 14SS OF TWO FISSION PRODUCT BARRIERS POTENTIAL LOSS OF THIRD BARRIER SECTION II.O GENERAL EMERGENCY PLAfff CONDITION WITH THE POTENTIAL FOR CAUSING LARGE RELEASE OF RADIOACTIVITY SECTION II.K P/0/R/S GENERAL EMERGENCY 9m $$
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J J bu!UL,lQ,M,A W [fl %_,l3.$ M lQ MLALluk (UUL ANI Lt AKAbl/ Sit AMLINL NNL AK HEArrOH ONLANT_ LEAKAGE > TECtf SPEC,8.IMITS SECTION VIII.A _, _ _ _ _ _ _ __ UNUSUAL. EVtMr _ SIGNIFIfANT (> 50 GPM) REACTOR COOLANT I.EAKAGE SECTION VIII.B _. ,_ ALERT STEAMLINE HREAK INSIDE CONTAINMENT SECTION VIII.C , ALERT STEAMLINE DREAK OUTSIDE CONTAINMENT SECTION VIII.D ALENT MSIV MALFUNCTION SECTION VIII.E ALERT HTEAMLINE HREAK OtfrSIDE CONTAINMENT WITHOtfr ISOLATION SECTION VIII.F SITE AREA EMEHGENCY REACTOR COOIANT LEAKAGE > 5,000 GPM (14CA GREATER THAN MAKEUP PUMP CAPACITY) SECTION VIII.C SITE AREA EMEHGENCY p UNUSUAL NAlUNAL PHtNUMtNA UNUSUAL NATURAL PHENOMENA EXPERIENCED OR PROJECTED (EARTHQUAKE DETECTED ONSITE, FLOOD WARNING, TORNADO ONSITE, SUSTAINED WINDS DI5 MPH - g SECTION VII.A UNUSUAL EVENT SEVERE NATURAL PHENOMENA EXPERIENCED OR PROJECTED (EARTHQUAKE > OBE FIDOD APPROACHING DESIGN LEVELS, TORNADO STRIKING FACILITY, RTORM WINDS APPROACHING DESIGN LEVELS) SECTION VIII.B p ALERT SEVERE NATURAL PHENOMENA EXPERIENCED OR PROJECTED (EARTHQUAKE ONSITE EXCEEDING SSE, FLOOD ) DESIGN LEVEL, SUSTAINED WINDS EXCEEDING DESIGN LEVELS, TORNADO STRIKING FACILITY AND CAUSING SIGNIFICANT DAMAGE PLANT NOT IN COLD SHUTDOWN SCCTION VII.C SITE AREA EMERGENCY SEVERE NATURAL PHENOMENA EXPERIENCED OR PROJECTED (EARTHQUAKE, FIDOD, 10RNADO, STORM WINDS) THAT COULD CAUSE MASSIVE DAMAGE AND IDSS OF ECC SYSTEMS
- SECTION II.R GENERAL EMERGENCY MN N5 28- ?:o sd k$
Gulut l0 [L ASSit fING LMLRGlN(It S (OSS OF (LECIR[ CAL, POWLH IJ Ss eW urr-ilft: 61 )W E H S t i T I ON IX.A llNHSilAl. FVENT IJ ISS 4W ON-SITE AC_ l*t) Welt CAPAHlllTY SECTION IX.h LINilSilAl. FVI.NT IJ )S i Of UFVi_il,TF l})WFR < ,l S , M 1, NilTES IJ)S 3 Off NSITP} AC PI) Welt ( _,15 M I NilTES S t:CT I ON I X .8' Al.ERT tJ)SS OF ALL ON-SITE VITAL Inf 41)Wl:R < 15 MINilTES SECTION IX.D _ ,, Al.ERT IJ):b OF OFF-SITE POWl:R > 15 MINtfTt:S IJ)SS OF ONSITE AC POWER > 15 MIN 11TES SECTION IX.E , SITE AREA EMrHGENCY IJ)SS OF ALL ON-SITE VITAL IN: WlWER
- 15 MINilTES SECTION IX.V , ,_
SITE AHEA EMEHGFNCY LQSS OLMRMS_QLINUl[Alj0NS IJ)SS OF ALI. PROCESS EFFLUENT ALAHMS OR INDICATORS REQUIRING Pt. ANT SHUTDOWN g_. ....SECTION X.A, , _ _ __ _ __ __ UNUSUAL EVENT lt)SS_OF ASSESSMENT OR COMM'J N I CATION CAPAnit.ITY SECTION X.B ,_ , ,, _ _ _ UNUSUAL EVENT g M.OST OR ALL A!. ARMS IJ)ST SECTION X.C > ALERT g . MOST OR AI.L ALARMS 14)ST PLANT TRANSIENT INITI ATED Olt IN PROGRESS SECTION X.D _....._.> SITE AREA EMERGENCY COMPR0n[SLQF PL ANL(QNJEQL SECURITY THREAT OR ATTEMPTED ENTRY OR ATTEMPTED SABOTAGE SECTION VI.A UNUSUAL EVENT REQUIRED OR ANTICIPATED CONTROL ROOM EVACUATION CONTROL AT REMOTE SHUTDOWN PANEL ESTABLISHED SECTION II.K g .. > ALERT ONGOING SECURI'rY COMPROMISE SECTION VI.R ALERT g _C_O_NTROL ROOM L.ACUATION REMOTE SNUTDOWN PANEL INOPERARLE SECTION II.N
> SITE AREA EMERGENCY IMMINENT LOSS OF PHYSICAL CONTROL OF PLANT SECTION VI.C SITE AREA ENERGENCY LOSS OF PHYSICAL CONTROL OF Pl. ANT SECTION VI.D GENERAL EMERGENCY
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- g. .. _SEC. TION IV.C INTO V.I T__A l_. AH.E A. S_ _)_. _ PLANT NOT IN C__OI.D SHtiTDOWN _.
- .. .___-.y SITE AHEA EMERGENCY (NI-IJNCONTROI.IlD PLANT FlHt: 740T EXTINGlJISilED HY AUTOMATIC FIRE SUPPHESSION SYSTEM OH FIHC
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- b. Field surveys HeJ1th Phystes Personnel
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i i i . o . ..i t . ..... ..i ) l IJ A.' A t t e sN Ur INDI C A f li sN / d 4 INI e & A i a rc. s ONul rit aN EM t.kGt.N4 'Y ACT 8 4 AN 1.F.V) L j Nt3 B C A l'lON/ j Nt qJkM ATit W I N t'Okot AT I ON 43 I t'oeit a nuel) og i 9 Panet H i l- Pi>U J { C l or
- 1. l ej . Suppresassion 45 mil hat err Level Motor Paner l Hi t-Phu t (ts)
Level, Tech. Spec. Soc. 1.E>.2.4 os Pan.s ! H i l- P60 2 (It ) l.th. Suppression Pool water kucorder Temperature Tech. Spec. (See II.H.2A) l Sec. 1.6.2.L i l _o r. 1.11. Suppression Pemal Spray. Not Applicable Not Applicable Tech. Spec. Sec. 3.6.2.2 1.1). Suppression Paul Coolin.J, Not Applicable Not Appl l ;able Tech. Spec. Sec. 3.6.2.3 e f.E I.!k. Ptimary Containment Not Applicable Not Applicable Isolation Valves & Reactor l Instrument Line Escess ] Flow Check Valves, Tech. 4 Spec. Sec. 3.6.3 h I or j l.ll. Suppression Chamber Not Applicable Not Applicable I)rywell Vacuum Hreakers. Tech. Spec. Sec. 1.6.4.1 or gm 1.lm. Reactor fluilding Not Applicable Not Applicable ,g an Supprussion Chamber vacuum ew l *g Hrcakers, Tech. Spec. Sec. f .".,
- j y 1.6.4.2 a
i OM
- l (Cont **$8 e a. u i
9 1 i j # 1
[ j i l I ! i e at I k. .t fet r Aa j t e *N i & ,/ t i N g ll. (6% est B ites wl) e 1.s C A r l e *N 4 at INis ti AIla W/ 8 N l r ! A i 1 f* e i 4 JN u l T lt 'N LMt Ha.t Ncy Act i 6 aN l t,vt 1 I NI)l C A i I t JN / l N t i nKM A T l ON I Nt I sh M A l'l oN
- n. t c ... i nue.51 g I
!.in. Pr im.s t y Con t a i neme n t Not Applicablo N. .t Applicable l Hyitr o Jen Hua:emah n ne r s ,
rech. S i mt set 1. es . e> . 5 e *
'.1.
1.10 l>r t ana r y Containment Not Applicable Not Applicatste HyIrogen Mamang System,
) Tech. Spec. Sec. 3.6.6.2 l'i.
- 2. E k t ee.11 ng any of tite l 101lowang L.CO's tor Secondary Containment 1 2.la. Secondary Containment Not Applicable Not Applicable Integrity, Tech. Spec.
j sec. 1.6.5.1 ill 2.lb. Secondary Containment Not Applicable N 1t Applicable Automatic isolation Dampers, Tech. Spec. Sec. 3.6.5.2 ill. e 2.lc. St andt>y Gas Trea t ment Not Applicable Not Applicable System. Tech. Spec. Sec. 3.6.5.3 L. . lass of any Engineered Safety la. High Press e Coolant Not Appl! cable Not Applicable l Feature Systems functions injection, .ech. Spec. requiring shutdown by tech- Sec. 1.5.1 nacal specification g
'd.
Ib. Automatic Depressurization Not Applicable Not Applicable i w :s System, Tech. Spec. Sec. m rg I jS l o 3.5.2
$7
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- - - - . - . ... - - - - ~ - . - - . . . . . .n . -- . . . - . _ - - - . ~ . . , . - - -- - - _ . - . . ~ . - - - ~ . . - .--.~.n.- -
4 + l O 9 9 i I i l } ! l t M e Ft.t Nt ' % At } I 4 4 6N 4 t vt t 5 ( ! t Ia. ( C. n. i i ne.-is ) t la st ' A 6 t i sN te IN!'1C A I 18 3N/ IN4ri4fIte CuNulTluN t Mt Mt.t.NCY ACT l a BN 4 t.VP (, I Na a l C A l' 8 4 aNf 1 N P 1 pH M A l' ( ON f 1 Nt ukM %T It DN I
- t. . ( C on t a nuetJ ) E tc. Ca >r e Spray System, Tart-la . Na st Ap[e l i ca ts is* Not App l i c a ta lia S i w e. Sec. 3.%.3.1 ,
L E , lit , now Pruansure C. m i l a ss t. Not Appl icats t.t Not. App i s c ate lir , t injection, T e e t. . Spes . Sec. 1. 5. 3. 2 1*f_ [ L le. Control H<xun t.me rgency . Not Applicable Not Applicablu I FiItration System, Tech. k Spec. Sec. 3.7.2 "f ! It. Control Rod Drive ttousing Not Applicable Not Applicable Support. Tech. Spec. Sec. 3.1. 3.8 l l 2E. Ig. MSIV's, Tech. Spec. Sec. Not Applicable Not Applicable f 5.4.7 SE. th. Isolation Actuation Not Applicable Not Applicable Instrumentation, Tech. I Spec. Sec. 1.3.2 ! l or ! i i
- 11. AC Electric Power Sources Not Applicable Not Applicable g (Refer to 1.oss at Electrical i Power Emergency Section) 6 Tech. Spec. Sec. 1.8.1.1 Sf.
- j gp 13 D.C. Powwa System (Reter Not ApplicaD!e Not Applicable jQ l oo to 1,oss of Electrical Power I
'o
+;
Emergency Sectton) spec. sec. i.e.e. Tech, p o l Om l.. .o- i
" (D
- 4. D J (cont'd) b e
e I ! i , I l 4 i < _. ~ _ _ . . . _ - . - _ . _ -- - . _ . . - - - . - - .. - . - . - - - - - - . - - . . - -- - - - - -- - -- - - - - -
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- t. . (i . ist a si , l p ,.*
Ik. D**e e ajone y bjuapment Ni et. ApplEc.thle Not App ! I c.e h l e C. u b l i n.J Water Sy= tem, l'**i le . Spec. Sec 6.7.l.6
'L , !!. tme r sje nc y U gu l pme n t Ni et App i n c.sta li- Ni it App l i c.e t e l e.
'l '..s r v i ce Water S y rs t em , Tech. Spec. Sec. 1.7.l.4 l!L Am. Ill t a mat e Heat Sink, Tech Not ApplArable Not Appltcable Spec. Sec. J.7.1.4
'.'L In. kHH Service W.s t e r System, Not App i n c.e b l e Not Appincable Tech. Spec. Sec. 1.7.1.8 or I
lo. Hi >1 Worth Minimizer, Not App!tcable Not App!! cable Tech. Spec. Sec. 3.1.4.1
- r. At.nor ma l coolant temperature, 14 Heactor coolant Not Applicable Not. Appilcablu
. . < pr enu s e ou t s tile of temperature exceeds Tech.
t es. h n i c a l spectitration Spec. Sec. 1.4.6.L oper tlon.nl I telt s "L lie. Heactor Pressure aJteater *a. Annunciator Panet Hi l-PbO J ( D- 14 H )
- than 104u pulg, Tech.
- Spec. 1.4.6.2 E i
ab. Indicator Panel H i l - P t> U 2 ( C ) Mr
$mr$'s Panet H 1 1 - P t.0 ) ( C )
v rs s O 4N ee <8 Oc tt O U@ OM res
- 4. 99 b
1 O O O
l l G G , S I P ! ._m _._< . ._,u_ _eaC riim te vu_s t1. i r...it a nu.,i n l & te s: A f l uN Ur INHICAflHN/ [ tN{II[IlNG CONuiTIDN, P.M E ttGE Nt
- Y A4 "I I ( W LLVtl I NHI C A T 1 ON/1 Nt t>hM A T I UN I N P UN M AT l t sN t i
G. uthor plant conditions that L. N% Judgemont Not Applicable Not Applicable w.e r r ant incroased awarunoss . on the p.n r t of the plant upuratin.j ntalt. or Stato l and/or local oft-sito a l author 6ttus or requir=* p l .s n t l Stoutdown un.1e r technical z specaf6catiswa requirements or {' involvo ot he r than normal 1' contrnite<1 nhutdown (e.g., l l cooldown rate onceedinJ I J technical specutication lim t t i, pipe cracking found <1uring l operatton). i Al.ENT H. Completo loss of any function 1. l.oss of tast h Idt M shutdown Not Applicable Not Applicable ossential for plant cold cooling modo loops shutdown
- 1. ra61ure of HPS to initiate 1. Initiating Scram Signal a. Annunciator, Auto Trip Pane! H!!-P60 3( D-7 3 )
and complete a scram and/or Actuator Tripped failure of a manual scram M to bring the reactor sub- - cratscal Pane t H l l- P60 )( D-7 4 ) !
. I or
- b. Annunciator.- Manual Trap Pane! H!l-P60 3( D-77 )
Actuator System Tripped and 1 Panel hil-P603(D-75) a
^$ i J. Neutron Flum Monitors IRM/APMM Indicators Panet H l l- P60 3 ( ts )
indicates the reactor is critical
.,p, J. Other plant conditions entst 1. NSS/ED Judgement Not Applicable Not Applicable '
sm :s which warrant pr cautionary
$" . acttvatson of the Technical y ",I g$ Support Center amt platimj ya s ec the Emergency Operations
' o o% racility and other key f" y emergency gersonne l on to '
- Standby
] t
j i l i L"! F d P'l ^28 "* 1LYlil ! tt. (t. o r a naw.1) e iJ Ja A I I L W 4W I N a l t' A f l oN / I N i l l A l' I Ns. 4 t eN4 8 8 t l t oN D M t we d.*dt ' W Al"I' i n sN t.t.V t t. I NIJ I C AT i t sN / I Nt t 1HM A l' j s sN l Nt tahM Af t e)N .I { s, t.vaces.s t n on of Control H w im 1. NS :s /t_t) J us1p rne n t Not App l i c a ts t e Not App l i c a b l e l nt ic a p.s t ed or require 1 with control of si.u t town systems l e s t .sb i t she.1 t r a ma local
! st at nons 1
4
- g. A v t. A t.M t.wi .t Nc y
! t'emaplete I.os s of any tune-
- t. , la. All s.s t o r y se ll. t valvus Ni; t App l i c ata l e Not Applicable i tions essential tor p l .i n t l hot .h u t isown or t
! lb. ' Isot h kHR divtstons inoper- Not Applicable Not Applicablu ablo an Torus Cr>)t ing Modes I tc. hoth kHH ultimate heat Not Applicable Not Applicable sinks knoperable i - and r i
- 2. Inabiltty to insert sutti- IkM/APkM Indicators Panel H i l- P6 0 )( B )
I ctent control rods to bring the reactor subcritical 4
- 1. Inabtitty of the Standby IRM/APHM Indicators Panel H i l- P6 n )( ts )
j LiqJid Control bfStein LO 4 g bring the reactor i subcritical i i and 4 4a. Mann Condenser Cooling Not Applicable Not Applicsble j inoperablo I
.2L i
4 t>. Loss of snakeup capac i t y Not Applicable Not Applicable
\
7m mn t rtwa NCic and CSS p Go yg I O{ g G *O q 'J . NbS/Ed .ludgeins n t a Not App l i c a b l e? Not Applicat,le , 04 o
S a
d. a. O i l
\ O O O
- - . - - . . - , - , . - - - . . - . - _ . . - . - ~ . . ~ - - - . . - , . - - . . . _ - .--.s..-.- ..n E
i G G G t Mt.184.t Ns y An' T l e sh 4 i VF t.5 I i1. I t . eve t l esseen!) l> Nl AT il>N OP [N LJICA f l ON/ g fjATING CtsNulTION L M t.N Gt.NC Y ACTION BAVt L l NisI C AT I ON/ ! N FOk M AT I t sN INFONMAflON M. T r ans ien t. res pa t r i ng sag s r a t t on 1. Fatture to brnng the IMM/APKM Indicators of shutd.swn systems w6th scactor sur> critical with (See ll.L.2.) tantoru to SCHAM (continued the control rods in awe r +3ene r a t s on but we cesru dam e se is immed i a t e ! y ev i d.en t d
- 2. Failure of the Standby IkM/APkM Indleators Control System (See ll.L.3)
^*T
). No indlCation of core damage Not Applicable Not Applicable E
- 4. NSh/Eu Judgement Not Applicable Not Applicable N. Evacuation ut CJntrol room L. NSS/Eu Judgement Not Applicable Not Applicable aa.1 control of shutdown systems not established s'am local stations in 15 minutes e t.t.Nt;H AL EMERGENCY
- o. Loss at two fission product 1. Failure of fuel cladding
- barriers with potential loss and reactor coolant of the third barrier tmundary with potential loss of primary containment, as indicated by the following!
1.1a. Reactor coolant activity Heactor coolant sample analysis shift Chemist
> 300 >Ci/gm dose equivalent I-13%
or 1.lb. Reactor coolant level Heactor water level meter Panet Hit-P60L(C) ( -50 inches for greater than (later) minutes <E
,g Panet Hll-P602(C) ;
l lb *3 Of i ao ,,,, l o 1.lc. High ott gas activity at Off Gas PMMS Recorder twith Panet Hit-P601 k7 CE Steam Jet Air Ejector, cps- Wi/sec conversion chart (nack panet) "g og > 5 Ci/see (Dll-N004A/4H) or
. (cont'd)
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IAK!ATluN LW l Nul L' A T I ON/ j I N r t A f t w o 4 HNiJ[ 8 4M, t.MENGENCY ACTite f.tVP1 INUICAflON/jNPORMArlim lNPONMATION 1 I
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l.4b. NSS/LI) Just.jemern t that Not Applicablu Not Applicable { there as a loss or cun- t teinment spray anit torus I avalin; montes ut kHM 1.*L.
- 1.4c. NSS/El3 Just Jement that Not Applicable Nut Applicable there is a gwatent i a l for ;
loss of containment l 6
."f. i 1.44. Failure of all MSIV's in a MSIV valve p>s i t s on Panet Hil-P60!(A) main steam line to isolate i nst i c a t or '
l
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Panel Hil-P602(A) i 1.4e. A major steam leal 6 outstde See Vllt.F (p. 36 of 44)
- of primary containment without isolation f LL
- 2. Failure of fuel claddin.J and primary containment with patential loss of reactor coolant boundary as indicated by the following:
2.la. Primary coolant activity Reactor Coolant sample
> 300 6Ci/gm dose Analysis (See 11.0.1.14) i equivalent 1-131 ilE.
25 2.Ib. Reactor coolant level <-50 Reactor Water level Meter i j0, inches for greater than (See ll.0.1.lb) zm (later) minutes Jc v 87 l , n o t
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- o. (t ,,n t. a nue.13 1.14. *titus amincates all Valve Po ss e t t on I rkli c a t i+ >n f c mt a a n.ne nt. g enet rat tons (See 11.0.2.2.s) l r o.gu i red for isolatton not j valved off or c!seset isingle t valvo criteria) a 3.lb. Ets/NSS opinion that Not Applicable Not Applicable primJry cont.stnment isolation has not teen achieved M
3.Ja. Drywell toeperaturu Annunctator, Containment Dtv. t greater than 135r 1/11 Temperature High (See i II.O.I.2a) ?
~
or ! l 3.2b. Drywell pressure greater Annunciator Primary Containment ! than 2 psig Pressure High (See !!.U.l.2b) I _or 5 3.2c. Failure at all MSIV's MSIV Valve Posttson Indicator in a Main Steam Line to (see 11.0.1.4J) isolate l 3r 3.2d. A major steam leak See VIII.F (p. 36 of 44) outside of primary contain-ment without isolation an1 i i l 3.3a. NSS/ED }udjement that loss Not Appiscable th)t Applicable l vm of ECCS has occurred > e3 , an I #" s Dr , o -
'M M i
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' e
< m.
"S 3.3b. Reactor water level less Reactor wates tevel Pane t Hi t-P6J2(C) *E t 0,, 8 than level 3 i171.19 o" [
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F e Mt Ns.t wa r Ac t e s em ievtes ! o I t 4 II. U ontanue.3) I t 4 I IJ K' A f t t aN tW thulCAT!uN/ IN a r1 A rius; CONul tit s tMFHGFNCY At'Tita t.t.Ve l. I NHIC A f luN / I NFulaM 4T j uN (NFONMATION
.s . (<'ont e nued ) g Id. High drywe!! pr e s sure . Annunciate.r, Pr t ma r y Con t a i nme n t greater than 2 pang Pressure High (See ! ! . U . l . J ta ) .
a n. Ja. High reactor coislant keector Caw 3 t a n t Sample Analysts activity greater than 300 ISee !!.0.l.la) 1 ed'i/gm equivalent I-I31 l
!!L '
2b. High oft gas activity at Ot t-Gas PkMS Recorder Steam Jet Air Electors, (See II.0.1.lc) I greater than 5 Ci/sec or 1 i l 2c. Primary Containment (later) See !!.O.l.2d atmosphere sample greater than (later) E l 2d. NSS/ED Judgement that Not Applicable Not Applicable l loss of ECCS has occurred H. Small or large II)CA occurs I. NSS/t'D Judgement that a Not Applicable Not Applicable an.1 containment performanco small or large 8.oCA has is unsuccessful affecting occurred longer term success of the t.CCS . Could lead to core and degradatson or melt in several - hours without cru t a i nme n t 2a. High drywell temperature, Annunciators Containment boundary greater than 135*F and Div I/II Temperature High rising (See !!.0.1.2a) or
.o p 2b. Drywe!! temperature has See II.u.l.2a g f3 been risimJ for 1/2 hour eg or longer yy oe
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'l 2 1 82 uncoverin.3 of spent tuel Annunctator, Fuel Pool Pane t Hi l- PbO2 ( L)* l l i ! ( l e n., fuel p< son water Coolis*j Trouhle ledel) I
. 2a. Appropri.ste Nadiation/ .s . Area kadiation Alarm Panut H11-P816(Al j Airtnrno Monitor (Area Indicator for Channels Madiation Monitor Channels IS, 17 or 18 I ') , 17, or IW, or Fuel tw21 Ventflation -
or
! Haitiation Monitor) , ts . Annunciator Fuel Pme t Vent Pane! Hi l-P60 )(1)+ 31 )
f ' Exhaust Hadiation Monitor tJp4Cale
; r
- or 4 t l c. Annunciator Fuel Prwn! Vent Panet H11-P60)(D-35)
Exhaust Radiation Monitor 3 Upscale Trip or 1 I. 4 2h. Area Radiation Survey Field survey Health Physics Personnel ,
) (later) ;
4 or 1 j 2c. Ai r tw>r ne Survey > (later) Field survey Health Physics Personnel 12L l 2d. Surface Contamination Field survey Health Physics Personnet j Survey > (later) 7
! i
- 3. NSS/ED Judgement Not Applicatste Not Applicable vm E. Projected tjose kates la. Whole tx2dy dose rate > 50 (later) ( l a t'e r ) i
,$E mR/hr for 30 minutes I e- wn l t er k N., en
. c -
81 ga ib. > Suo mu/hr for 2 minutes (later) (later c> E 1 ~ w l $ (cont'd) I l. 6
i l t m t H .s N. ' y An ' t i t N t i vt 1.s bll. (i a sfit a ssiaseta ) le at Al'loN t ot' (Nolt AIleiN/ I N I I I A r i Nt; con!)! TION LMt Ht.FNCY Af "T l a W l.t V 6 8. I ND I t' A T lirN / 4 Nt q )RM A II e @d i N t'l BHM A f li sN
- t. . t ( .ent a nued) ist Ja. Th y r oid al.>so r ma t e e 250 (later) (later) mH/he t . >r lo a t raut aes I 2
! Jh. Thyroad di e se r rate i 2500 (later) (laterr) mH/hr f or J mitiutes F. Fseld ke.s 1 L sags (Out s sale Sito 1. s Su mH/hr ime t .n /g amena or Field Survey ka.i t o log s ca l Emergency hisu ri.t.s r y ) (later) cpm Is m16 ne (2u Toim minutes sample) for 30 manutes; or longer 1
- 2. > Suu mH/hr tat t .n/g amm.s or Field Survey kmtiological Emergency (later) cpm (20 manutes Team i sample or equ i v.s t e nt ) tor
'l two minutes J
- 6. Projected l>>so (on site) 1. Wfiolo Hody a i kEM (later) (later)
"f_
- 2. Thyroid b 'a ht.M (later) (lator) i 4 it.Nt H AI. FMENGLNCY H. Projected Ikase ( .a t the site 1. Whole body
- 1 kEM (later) (later) boun1ary "f.
- 2. Thyroid * $ RLM (later) (later) i
- 1. l* r o j ec t e.1 or Modsured th >s e 1. Whoto H< >1 y 4 i HEM /hr (later) (later) j v rn kate (at the situ bousada r y I j$ or las yond ) E j e-O Tm i
- u. cm
- 2. Thyrold > S ktM/hr (later) (later) ev 1
4 < e
*1 p O4 o ** ow N .
tD as. a 1 O O O
,I6i .I .Il flt( l* F.l ,!' I FI ,iLiiiki 4 I jt;!L -
6l ; '!I, n k> il - : I o".e m; O ,
/
- N D - t
) )
I l' 3 0 1 A 1 laNu
't D
( D ( i i e e e e e e e 4 4 e e e BNf A l l l l l l l 0 0 l l i ._ M N b a b a b a b a b a b a b a 6 P 6 P b a b a b a m..
') 1 t
( c c c c c c c - - c c c _ 1 i i i i t l i i i t i i i m l l l l l l l i i l l l WNI p p p p p p p H H p p p . t i p p p p p p p p p p T A A A A A A A l l A A A A e e _. C t t t t t o t o t o t o n a n a t o t o t o o e o N A N N N N N N N P P N N - I h p ig hi gr h it h n t d d d e t o n d e e e )r ti e e v v v np at m v n t n i n i n i ha e n i o e o e o e o rd sr j o e c N i c i c i c i aa b d i O t e t e t e t eo Pi u t e I a r a r a r a bl Hv J a r T v v v v - v A r n r n r n r ,n ,y S r n M e o e o e o e ro rt S s c s o k s i s i s i s o oi H
) b t b t n t c / b t u b t t
__ ao t V o s o a o a o ai r o a N e c c ii i r o c i l t l i l i l ct ct t l I a a a a na nn a a t _ / N u i t s u f i u s i f s u ur nb ue nc r e s u i t u s t t t nc p o l i o i o i o i ni i N T V N V N V N V Av Ae O V A _. S. i O t O r V. t N 1 d 1< b a 2 b L . a b a gb . c. d a o b 4 O N O ( I C A ry ot evi ti t e t s st ai gs e t n e n o pd r o r a i t n ai np e Y sc o a n _ C - en ca n a y r l o r N. n t t o b g t t.s ar nj n p 1, t i fal s tsri i r a, mo m i nn ti w i e m Mt V. acc o ar aso l t. rr a n l a t ud i _. F l cif f e n oat rcu a r _ N a n e U t e o r h ( flh i oes ees nr de t f aat s ni o iut icae C r u bl n is _ A csr lp ria a rue s nl oe ual rn Y inv Tf p To C Auo t Tr N. t G M . E Ele. c M t l a r o b. I r o- I EI d d . u t n e _ i . r e p N i l O c IT Jd I t e U it N7 uc T bej 0 N.D i 4- o
- V, dr N t rp h l a.
s_ v I A L A zr ao i_ 4 H H L A_ S 1T O A_ H N N . U A O i V. I pn*0Ee yc.* w" O% .. 4* j j4
- If ,1 i ! I!l!
i Mt vi .e Ni e ACItoN I t vt 1 s av. I s . .n t t e. .. il ) t/m AriON of lNulCAIloN/ l N ] l l A l I Nr . CONulTloN P M r NGt.NC f VfloN l.t V Fl. I NDIC A T I ON / l NP OkM A f !ON INeukMAf104
- AlLHT
- h. Other h.seards lat i n.j la. Aircraft crash or missile 4 Visual oht.cavatson Not Appitcable
.. m p. r t e nce 1 or pr o j ec t .-it i mp.e c t int o ke.sc t or atu l l o t mj 'l u r le a ne it.a t t it t n.j ,
Austilary hia s lit t ieaj, kadw.aste Hu a i o i n.j , klik Ci simp ! e n , l.mer.jency Operations tacitaty or the Tec h n i c.s I iupport Center U lb. Luplos as so dainaijo Not Applicable Not Applicable
.s t t e c t t r> 3 plant operation L'l Ic. uncontrolled entry of tonic .. Control Room ventilation (laterl or flammablu sj a s anto the Chlorine Detector keactor Hu i le16 n.j , Tu r ls i ne (W23-N412/N41)
. hu i I d i n<j , Auxiltary Hu t id i nij , Radwaste Hu i ld i nij , 3 i kilR Compica, t'me r.je nc y Operations Facility or the b. Observation Not Applicable Technical Support Center K Id. Tu r ta i ne Ca s i n.J Pene t r a t ion Visual Observation Not Applicable SITE ANtA FMENGt.NCY C. Other hazards t=J i n ) emper- 14. DamaJe f rosa aircraft Not Applicable Not Appltcable henced or projected crash, missile impact or emplosion aftectinj redundant safety systems or lunctions or
'O M ma j ,n (b. Entry of uncontrolled Not Applicable ,
Not Applicable o t l ammab le ij a ses into areas mm L' E contatnin3 nuclear safety $7 9g systems or engineered ' g u safety f e.s t u r e s oe h
- ID
( t'ont
- d )
I e O O O
__m_ . _ -_ _ _ -_ . . _,-.._ _ . . . _ .-_ _ _ _ . . . . _ , . _ _ . . _ . . - . . _ . _ _ - . . _ ._.__,_m _- _ _ O - O O 4 4 e 6.Mt.au.t Ne y Afrtam 1.tvtta t tv. (t innt s nustd ) [ i te sC A rie)N (W INIJ (CM t e kN/ ) t.M r. NGE NC Y ACTfuN I .E V Fl. I NillC AT I ON / 8 NFONM A f Ii#N I N rONM A T l Oft {N I r i A I( Na i CONiilTION f I C. (Cont a nue <8) E i Ic. Entry of uncontrolled Not Applicable Not Applicable tou te .3ms into areas containin.) nuclear Safety systems or en.jinetered saluty features where lack of access to the area consti-tutos a safety problem
*"1 i
J. Plant in Operatin.J Not Applicable Not Applicable [ Condition 1, 2, or 3 f i s
- 3. Nss/t u Just.jement Not Applicable Not Applicable {
s e t h 4 L I i i } l f' MM b :5 I an ; on 0 *m M 6 Me 44 > MC 4 > og a<>= 1
- Oe o p een o >*
M e e 15 6 l L t I l 4 L k t P I
- ,- ~~-~,..-c-,s. ,,,--,-,c,_--__-. . _ , - .- - - - - , , -- - - - , , , _ , . . . . . . . . , - , , . _ . . . . . _ . . , 1 - , .-, , ., .-...__... _ . _ _ _ _ _ _ _ . _ . _ . . ~ . .- ._.. . __ _ ___ l .
l l l t M t. H. .t Ni V Ai' l i s pN 3 t vt I s I I V. t I F t. g 1.t M ' A l l oN t at LNOlt A f t e 6N/ I N I I I A l' 1 Ns , a, a INg'QJff EMt ki .t Nt' Y ACT!ON l.t VLI. l Nill C A i l t )N / l NFi 6hM A f it lN , 1 N t t >H M A l' i 4 sN ] .
~
i unti ,u Al. tv t ta l 1 A. linec. ant r o l l uel p i ,e n t ttro 1. tinesin t r o l lcal plant tare. Fire tar i gado lataile r N st Applicable I ne st b r e euglit u nite r control tsy au t i sma t t e fire sta pp r e s - l 9&on fi y s t e ms or plant a gne r sonne l within 10 minutes 1
- 2. NS; J uiljemo n t Ni nt App l i c a ta l e N >t Applicablo Al.t H T H. Fire pat ent ia l l y at t ec t ing 1. Fire with potent ial to Fire fir ig atie leado r Not Applicablu s.s t e t y systems attect n uc l e.s r safety systems or engineereit safety features 1
K
- 2. NSS/ED J udgeme n t Not Applicable Not Applicable
_S[IE AREA t_M t' NGENC Y ] C. Faru comprom sing functions 1. Major fire that attects Fire brigade leader Not Applicible of satety system redun<1 ant safety system trains or functtons 1
- 2. NSS/EI) J udgeme n t Not Applicable Not Applacable om Qe l3 4o it e*
O MM ks to fB M GD G 4 0 m - *
- d II O ni 62 .c) **
& CO e
O O O
D L C/ [d p ht kGtNt 'y Vllem 1.h V D.13 VI.
- _e.s._M__PNa tM I SP. 4 8V 6*l AN r Si t ilH i r Y l A K' A r le #N OV IN!JIC A f lON/
lNI ri A rINEi ('t JNiy T lisN F M E HGE N4 'Y At?T I t IN 1.t V F l. I Nul(" A r I a DN/ I N t a }NM A f it aN 1 N Ft ikM AT l UN liNHSH Al. LV t N] A. 2.a-cu r i t y th rea t , attempted la. Security force declares a Security bupervisor Not Applicable entry or at tempt ed matzstage security contingency event
'If_
l t, . NSS Judgement that a a. Ohbervatton Not Applicable security threat, attempted illegal entry or attempted .r sabotage is ines i ne n t ur has necurred b. Notification received Not Applicable , Al. TWT is , urwp oi ng secu r i t y compre un i me I. Adversaries commandeuring a. Security Supervisor Not Applicable an area of the plant, but not controlling shutdown or capability, or any areas containing nuclear safety b. Otise r v a t ion Not Applicable systems or engineered
- safety features SITE ANEA LMt'RGENCY C. Imminent loss at physical 1. Physical attack on the a. Security Supervisor Not Applicable control of the tacility plant involving imminent occupancy of the Control or~
Room, Auxiliary shutdown panels or other areas b. Observation Not Applicable containing nuclear safety systems or engineered safety features GENENAl. EMENGENCY D. Im s of physical control of 1. Physical attack on the a. Security Supervisor Not Applicable the factlity plant has resulted in unauthorized personnel 3 m cupying the Contro! 5g Room. Auxiliary shutdown b. Observatson Not Applicable ao panels, or any other aE areas containimJ nuclear ,n gm safety systems or engi- ev n neered safety features . r, os o ms ?
, EP-101 Rev. 0.B O
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o =~ r- cww w s es> ; w ee v- = i v -av ? 3 s> n: -z L gw t w I? =w 1 3 J "L
= w v.i. .t. 2:
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= ww
=g w4 w: ev:a 2w .
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- l - :l - - : .
wl =. :l .u I
-- # 1
* < d A i z - .i. s ,
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.. w l
z :
=. :
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-e a
-i
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gw.
. 0 9 a w-l l
2
- 1'
- ora 3w
- z a 4y- w y
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Er losure 2 l Pase 30 et 44 l 1 I I 1
O O O D M LNt.t Ne ^ Y AC I' 14 6N 1.LVtlA V86. I t'on t a nucell j I;C A r lON LW IN13 8 C A T lON/ LNirlAl'iNG CONill TION EMtMGENCY ACTION 11V El. I Nf3f CA r!ONf INFOkM A rluN INFOkMATION H. (C*>nt inued) - Of t , 14. Sustanned wind velocity a. Wind Sp..ed Insicator. (laterl , .jreater than US mph l l64 0- k u u l / p u04 )
- projected or edese r v r 1 I 'll i
j b. National Warather Service Not Applicable i st rE Aura LMr:NGENCY 4 C. Severu natural 14 enuinenon la. Earth <4uake on-site Active Soismic Hecording System Panel (later) ) tar i nj omperienced or encoeding 0.1%J indication, (D)D-k600) i pr o jected with plant not in ) cold shutdown - or 1 1 lb. Lake water level encuedtmj a. (later) (later) l 586.9 feet projected or observed og
,. b. National Weather Service Not Applicable
~
or
}
Ic. Sustained wind velocity a. Wind Speed Indicator, (later) l exceeding 90 mph projected (D40-R001/H004)
; or observed I
, a "L
, b. National Weather Service Not Applicable or id. Tornado st riking Reactor Observed Not Applicable huildimJ. Auxiliary BuildimJ,
,)
J
,8 Turbine Building, Radwaste j' , Building, RHR Complex and 4
causing significant damage s , ,- , and l 4
- 2. elant not in coid shutdo.n Not Agpitcabie Not Applicabie i
- n o r.
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Enclosure 2
- Page 33 of 44 I
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ator Troutile 11 vm jy h. Annunciator Etx, il Start Panel H11-P810(D-27) eg Faiture , , , , oC em O4 M _or W m O u i. Annuneaator Dbv II &lHi LI Pine 1 HI1-PB10(D-39) .O - [ N >t in Auto Penttion " , ( cont ':1) I r I ( l O O O
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IJ N* A f it IN t ot' 8 Nis!C A 7 I e IN/ , I N I l* I A l' 1 Ns . CONDITION LMLNGENCY ACTION 1 LVt:L I NDI C A l'l t eN / I N F6 HtM AT ION I N Ftile M 4 f l a nN k
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a nal [ f ] ' a j. Annune t a t s er Elmi 14 Gener- P.a no l Hl l- Pu l 0 ( D- 2 ) ator Troutste f l 1 l i A. Annune1ator Elm; 14 .s t .s r t Panel H1l-PUIO(D-3) f Failure l 1
- l. Annunciator Div II Etni 14 Panel Hit-P810lD-IS) i Not in Auto Position I AI.t:kT C. Insa ot oft-Site 5%wer an1 1. Loss of 120 kV t)ussess See IX.A.l [
On-St.o AC Power (15 manutes . or Less g [ t i
- 2. loss of 345 kV tsusses See IX.A.2 l
a fVI
- 3. (Ass of all Emergency See IX.H.la
- I utesel Generator ( Etxa)
Hussessi in EA, 12 EH, f 13 LC anet 14 ED 7
- u. Loss of A!! On-Site Vit al I. Loss of J60 Vtx? Husses a. Annunciator Hattery 2 PC Panel Hil-P810(D-72) ut Power (!$ Minutes or Less) Trouble i
! ""'1 , I j ti . Me t.o r (later) (later) and
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- I N I i 1 A l I N. , Ca mis 4 8 8 ON F M r.H t it. NC Y ACf[UN 1.t.Vt 1. !Nuj( A { i s sN /1 Pe t Ora M 41 l DN l INFoMMArloN [
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- t. . Loss or oft-Sate Power a rnt 1. Loss of 120 kV hu s .u s mm IX.A.i un-Sate AC Power (greater t r,an 15 minutest g
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13 EC a rul 14 Eu
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J. Loss ot 24 VDC Husses See IX.n.) 4 mm ' D D
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EP-101 Rev. 0.B EMERGENCY TEAM AND SECURITY FORCE ACTIVATION MATRIX e
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m ergency Team Personnel Monitoring X X X Team Fire Brigade ,X X Damage and Rescue g g g x g x Te.am . 1 X- X X X X X X X X X X Security Force X X X Off-Site Radiological X 2::nergency Team i END Attachment 1 Page 1 of 1
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EP-102 Rev. 0.B ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
UNUSUAL EVENT
. RECORD OF APPROVAL AND CHANGES A.
Submitted by & Supervisor of Radiologi b" Emergency Date Response Preparedness Approved by , Tr, Chairman - Liaiso mittee Date Liaison Revision Committee () No. Submitted Date Approval Date 1 2 3 4 5 6 7 8 O
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EP-102 I Rev. 0.B f ', t 1 : 1 ! i l i 4 f s ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE '
Title:
UNUSUAL EVENT f 6 i N I t ! I 1 I r t ! I I I t I l ', t i f 9 . I i I F I
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1 i EP-102 Rev. 0.B UNUSUAL EVENT TABLE OF CONTENTS Page 1.0 Entry Conditions..................................... l 2.0 General Information.................................. 1 3.0 Immediate Actions.................................... 1 4.0 Follow-up Actions.................................... 3 Enclosures Emergency Response Team Procedure Index........... Enclosure 1 1 Attachments Emergency Team Activation Matrix.................. Attachment 1 Unusual Event Check-off List...................... Attachment 2 I b 4 6
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m EP-102 Rev. 0.B Page 1 1.0 Entry Conditions An emergency condition has been classified as an Unusual Event in accordance with EP-101. 2.0 General Information 2.1 Ultimate responsibility for assessment of emergency conditions and for directing protective actions rests with the Emergency Director. The judgment of the Emergency Director is paramount in proper control of the emergency and may take precedence over guidelines in this procedure. 2.2 Emergency notifications are provided for in step 3.3 of this procedure. Government agencies should be notified as soon as possible, but must be notified within one hour of recognition of the emergency. 2.3 The Unusual Event Check-off List (Attachment 2) is a
<~ helpful guide in ensuring all applicable steps of
(/' this procedure are completed. However, it should not be used in lieu of the procedure. 2.4 The Nuclear Shift Supervisor shall continue to act as Emergency Director until relieved of this respons-ibility by the Superintendent-Nuclear Production (Plant Superintendent) (or his alternate), or until the emergency situation is terminated. The Nuclear Shift Supervisor shall remain in the plant to supervise plant operations. 3.0 Immediate Actions NOTE: The steps in this procedure can be carried out in any order. However, the following order is recommended. i 3.1 Inform on-shift personnel, including security, of the emergency classification. 3.2 Notify DECO personnel of the emergency situation using EP-290 (Emergency Notifications), step 3.1. 3.3 Notify the State of Michigan, Monroe County, and the Nuclear Regulatory Commission of the emergency l situation using EP-290 (Emergency Notifications) step ! 3.1.
EP-102 Rev. 0.B Page 2 3.4 Activate the Emergency Teams as necessary to respond to the Emergency Conditions (see Attachment 1). Off-shift personnel may be called in to supplement the teams. Unless otherwise instructed, the Emergency T<3ms will carry out the steps of the applicable Emergency Plan Implementing Procedures. (See Enclosure 1). Relay the following information to the Emergency Team Leaders:
- 1. Suspected cause of the emergency situation.
- 2. Areas with abnormal personnel hazards.
- 3. Other Emergency Teams which are activated.
- 4. Pertinent plant lineups and corrective actions taken by the Emergency Director.
- 5. Any other information which may be useful to the team leader in performing the team functions.
NOTE: If the primary OSC location is not habitable designate an alternate OSC location. Have signs hung on the OSC doors by Operations Personnel indicating that personnel are to proceed to the alternate location. 3.5 If off-site emergency support is necessary from any of the following:
- 1. Frenchtown Volunteer Fire Department.
- 2. EMTS Ambulance Service.
- 3. Seaway Hospital.
Notify the appropriate organization in accordance with EP-290 (Emergency Notification), step 3.3. 3.6. Order an evacuation of unnecessary personnel from those areas with actual or potential abnormal personnel hazards in accordance with EP-530 (Evacuation). All evacuated personnel must be accounted for within 30 minutes of the evacuation order. O 1
i i 1 EP-102 Rev. 0.B Page 3 3.7 If there is a potential for the release of radio-logical materials greater than technical specification limits: 3.7.1 Have radiological sampling conducted in accordance with EP-201-2 (On-Site RET: Functions) and/or EP-210-2 (Of f-Site RET: Functions) as applicable. 3.7.2 Estimate the off-site dose in accordance with EP-303-3 (Manual Dose Assessment Calculation Procedure). 3.7.3 Order on-site protective actions (use of protective equipment, use of potassium iodide, and/or evacuation (see step 3.6)) as necessary. 3.7.4 If a significant radiological hazard exists off-site or at the site boundary, reclassify (~' s, the emergency, (steps 3.5 and 3.6, EP-101) and, if necessary, recommend protective actions for the public to the State of Michigan, Monroe County, and Canada in accordance with applicable NRC and FEMA guidelines. 4.0 Follow-up Actions 4.1 Place Technical Support Center and Contr ol Room augmentation personnel not notified in step 3.2 on standby by carrying out step 3.4, EP-290 (Em9rgency Notifications). 4.2 Ensure that the follow-up actions of applicable Abnormal and Emergency Operations Procedures are performed. 4.3 Continue to assess the plant conditions. Direct corrective actions as necessary to bring the emergency under control and mitigate the consequences. If significant changes in the emergency situation occur, carry out steps 3.5 and 3.6 of EP-101 (Classification of Emergencies). 4.4 Continue to monitor the progress of Emergency Teams in controlling the emergency. Ensure that additional (~N s
) personnel, support, and equipment are made available as necessary.
EP-102 Rev. 0.B Page 4 4.5 Periodically make follow-up status reports to on-shift personnel. Ensure all operations personnel and emergency response personnel are kept apprised of personnel hazards, plant line-ups, corrective actions, and steps taken to control or mitigate the emergency. 4.6 Periodically make follow-up reoorts to the State of Michigan, Monroe County, and the Nuclear Regulatory Commission using EP-290 (Emergency Notifications) step 3.2. 4.7 A long term relief rotation shall be established to ensure personnel are not required to remain at their assigned positions for an excessive period of time (normally not greater than 12 hours). 4.8 The emergency situation may be terminated if:
- 1. Release of radioactive materials to the environment is under control or has ceased.
- 2. Fire, flooding, or similar emergency conditicas are under control or have ceased.
- 3. Radiation levels in all in-plant areas are stable or are decreasing with time.
- 4. Reactor and associated systems are considered to be in a stable, safe condition.
4.9 If the emergency situation is terminated: 4.9.1 A verbal summary of closecut shall be provided to the State of Michigan, Monroe County, and the Nuclear Regulatory Commission followed by a written summary within 24 hours. 4.9.2 Carry out EP-401 (Re-entry) and EP-402 (Recovery) as applicable. O
l EP-102 Rev. 0.B EMERGENCY RESPONSE TEAMS PROCEDURE INDEX ON-SITE RADIOLOGICAL EMERGENCY TEAM: Activation (EP-201-1) Fire, Explosion or Other Incident Involving Potential Radiological Hazards (EP-201-2) PERSONNEL MONITORING TEAM: Activation (EP-202-1) Functions (EP-202-2) FIRE BRIGADE: Activation (EP-203-1) Fire Involving Radiological Hazards (EP-203-2) DAMAGE AND RESCUE TEAM: i Activation (EP-204-1) Disaster (EP-204-2) O,s Search and Rescue (EP-204-10) Evacuation (EP-204-30) SECURITY FORCE: Response for Fire, Disaster, Evacuation, or Radiological Emergency (EP-205-1) Control of In-plant Access for E:mergency Response Personnel (EP-205-2) Control of Site Area Access During Fire, Disaster, or Radiological Emergency (EP-205-3) Security Emergency During Fire, Disaster, or Radiological Emergency (EP-205-4) Evacuation (EP-205-30) OFF-SITE RADIOLOGICAL EMERGENCY TEAM: Activation (EP-210-1) Functions (EP-210-2) Enclosure 1 O' Page 1 of 1
EP-102 Rev. 0.B O EMERGENCY TEAM AND SECURITY FORCE ACTIVATION MATRIX u
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. Dnergency Team ,
Attachment 1 Page 1 of 1
I EP-102 O~- Rev. 0.B UNUSUAL EVENT CHECK-OFF LIST Immediate Actions
- 1. On-shift personnel notified.
- 2. Security notified.
I
- 3. On-duty supervisor notified.
j 4. Government agencies notified. a) Michigan State Police b) Monroe County Sheriff c) NRC Operations Center . , d) NRC Region III
- 5. Necessary emergency teams activated.
- 6. Off-site emergency support requested.
, a) Frenchtown Volunteer Fire Department b) EMTS Ambulance Service O- c) Seaway Hospital
- 7. Evacuation of affected areas on-site ordered.
- 8. Radiological release involved.
a) Radiological sampling ordered b) Off-site dose projected (estimated)
- 9. Protective actions ordered on-site.
- 10. Protective actions recommended off-site.
Attachment 2 O Page 1 of 2 6
EP-102 Rev, g,y Follow-up Actions
- 1. TSC placed in standby,
- 2. Additional Control Room personnel placed on standby.
- 3. Follow-up actions of Abnormal and EOP procedures completed.
- 4. Assess plant conditions and reclassify if necessary.
- 5. Follow-up reports completed.
a) On-shift personnel b) On-duty supervisor c) Michigan State Police
- d) Monroe County Sheriff e) NRC Operations Center f) NRC Region III
- 6. Long term organization established.
- 7. Emergency terminated.
- 8. Closeout summary completed, a) Michigan State Police b) Monroe County Sheriff c) NRC Operations Center d) NRC Region III
- 9. Reentry / Recovery initiated.
END Attachment 2 Page 2 of 2
EP-103 O Rev. 0.B ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
ALERT RECORD OF APPROVAL AND CHANGES Submitted by _ok Supervisor of Radiologic ~E br@ency Date Response Preparedness Approved by G Chairman - LiaMon Committee Date Liaison R evision Committee O No. Submitted Date Approval Date 1 2 3 4 5 6 7 i 8 i l t
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*itle: ALERT O
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3.0 Immediate Actions..........~..--. . .. .. . . . .................. 1 l 4.0 Follow-up Actions.......;............................ 4 I Encicsures
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O V EP-103 Rev. 0.B Page 1 1.0 Entry Conditions An emergency condition has been classified as an Alert in accordance with EP-101. 2.0 General Information 2.1 Ultimate responsibility for assessment of plant emergency conditions and for directing corrective actions rests with the Emergency Director. The judgment of the Emergency Director is paramount in proper control of the emergency and may take precedence over guidelines in this procedure. 2.2 Emergency notifications to Government agencies are provided for in step 3.3 of this procedure. Government agencies should be notified as soon as possible, but must be notifi2d within 30 minutes of , recognition of the emergency. 2 .*3 The Alert Check-Off List (Attachment 2) is a helpful f7% x_/ guide in ensuring all applicable steps of this procedure are completed. However, it should not be used in lieu of the procedure. 2.4 The Nuclear Shift Supervisor shall continue to act as Emergency Director until relieved of this responsi-bility by the Superintendent-Nuclear Production (Plant Superintendent) (or his alternate), or until the emergency situation is terminated. 2.4.1 When the Plant Superintendent (or his alternate) relieves the Nuclear Shift Supervisor and the Technical Support Center (TSC) is activated, the functions of the Emergency Director shall be shifted to the TSC. 2.4.2 The Nuclear Shift Supervisor shall remain in the plant to supervise plant operations. 3.0 -Immediate Actions NOTE: If the emergency has been upgraded from an Unusual Event, skip those steps which have already been completed. The steps in this procedure can be ("N carried out in any order. However, the following () order is recommended.
EP-103 Rev. 0.B Page 2 3.1 Inform on-shift personnel, including security, of the emergency classification. 3.2 Notify DECO personnel of the emergency situation using EP-290 (Emergency Notifications), step 3.1. Activate Technical Support Center augmentation personnel using EP-290 (Emergency Notifications), step 3.6, and EP-301-1. NOTE: If the primary TSC location is not habitable determine which functions will be moved to the Control Room and which functions will be accomplished in the EOF. Have pre-printed signs hung by the Security Force personnel on the doors of the TSC indicating that personnel are to proceed to the alternate location. As the Technical Support Center is activated, transfer control of all Emergency Response activities not directly related to plant operation to the Technical Support Center. This may take place anytime during the execution of this procedure. 3.3 Notify the State of Michigan, Monroe County, Canada and the Nuclear Regulatory Commission of the emergency situation using EP-290 (Emergency Notifications), step 3.1. 3.4 Activate the Emergency Teams as necessary to respond to the Emergency Conditions (see Attachment 1). Off-shift personnel may be called in to supplement the teams. Unless otherwise instructed, the Emergency Teams will carry out the steps of the applicable Emergency Plan Implementing Procedures. (See Enclosure 1) Relay the following information to the Emergency Team Leaders:
- 1. Suspected cause of the emergency situation.
- 2. Areas with abnormal personnel hazards.
- 3. Other Emergency Teams which are activated.
- 4. Pertinent plant lineups and corrective actions taken by the Emergency Director.
O
\-s' EP-103 Rev. 0.B Page 3
- 5. Any other information which may be useful to the team leader in performing the team functions.
t NOTE: If the primary OSC location is not habitable designate an alternate OSC location. Have pre-printed signs hung on the OSC doors by Operations Personnel indicating that personnel are to proceed to the alternate location. 3.5 If off-site emergency support is necessary from any of the following:
- 1. Frenchtown Volunteer Fire Department.
- 2. EMTS Ambulance Service
- 3. Seaway Hospital. .
Notify the afpropriate organization in accordance with EP-290 (Emergency Notifications) step 3.3. 3.6. Order an evacuation of unnecessary personnel from those areas with actual or potential abnormal personnel hazards in accordance with EP-530 (Evacuation). All evacuated personnel must be accounted for within 30 minutes of the evacuation order. 3.7 If there is a potential for a release of radiological effluent greater than technical specification limits: 3.7.1 Have radiological sampling conducted in . accordance with EP-201-2 (On-Site RET: Functions) and/or EP-210-2 (Off-Site RET: Functions), as applicable. 3.7.2 Estimate the on-site and off-site dose in accordance with EP-303-3 (Manual Dose Assessment Calculation Procedure). 3.7.3 If an on-site radiological hazard exists, order protective actions (use of protective equipment, use of potassium iodide, and/or evacuation (see step 3.6)) as necessary. . 3.7.4 If a significant radiological hazard exists i off-site or at the site boundary, reclassify s_ the emergency, (steps 3.5 and
EP-103 l Rev. 0.B Page 4 ; 1
- 3. 6, EP-101) and, if necessary, recommend actions for the public to the State of Michigan, Monroe County, and Canada in accordance with applicable NRC and FEMA
, guidelines.
4.0 Follow-up Actions 4.1 Place Emergency Operations Facility personnel on standby carrying out step 3.4 of EP-290 (Emergency Notifications). 4.2 Ensure that the follow-up actions of applicable abnormal and Emergency Operations Procedures are performed. 4.3 Continue to assess the plant conditions. Direct corrective actions as necessary to bring the emergency under control and mitigate the consequences. If significant changes in the emergency situation occur, carry out steps 3.5 and 3.6 of EP-101 (Classification of Emergencies). 4.4 Continue to monitor the progress of Emergency Teams in controlling the emergency. Ensure that additional personnel, support, and equipment are made available as necessary. 4.5 Periodically make follow-up status reports to on-shift personnel. Ensure all operations personnel and emergency response personnel are kept apprised of personnel hazards, plant line-ups, corrective actions, and steps taken to control or mitigate the emergency. 4.6 Periodically make' follow-up reports to the State of Michigan, Monroe County, and the Nuclear Regulatory Commission using EP-290 (Emergency Notifications) step 3.2. 4.7 A long term relief rotation shall be established to ensure personnel are not required to remain at their assigned positions for an excessive period of time (normally not greater than 12 hours). 4.8 The Emergency Director may downgrade the emergency classification to an UNUSUAL EVENT if the plant conditions no longer meet the Emergency Action Levels (EP-101) for an ALERT. l l l L
() EP-103 Rev. 0.B Page 5 4.9 The emergency situation may be terminated if:
- 1. Release of radioactive materials to the environment is under control or has ceased.
- 2. Fire, flooding, or similar emergency conditions are under control or have ceased.
- 3. Radiation levels in all in-plant areas are stable or are decreasing with time.
- 4. Reactor and associated systems are considered to be in a stable, safe condition.
4.9 If the emergency classification is downgraded or if the emergency is terminated: 4.9.1 A verbal summary of the downgrade or closecut shall be provided to the State of Michigan, Monroe County, Canada, and the Nuclear Regulatory Commission followed by a written summary within 8 hours. (} 4.9.2 Carry out EP-401 (Re-entry) and EP-402 (Recovery) as applicable. O .
'N EP-103 Rev. 0.B EMERGENCY RESPONSE TEAMS PROCEDURE INDEX ON-SITE RADIOLOGICAL EMERGENCY TEAM:
Activation (EP-201-1) Fire, Explosion or Other Incident Involving Potential Radiological Hazards (EP-201-2) PERSONNEL MONITORING TEAM: Activation (EP-202-1) Functions (EP-202-2) FIRE BRIGADE: Activation (EP-203-1) Fire Involving Radiological Hazards (EP-203-2) DAMAGE AND RESCUE TEAM: Activation (EP-204-1) Disaster (EP-204-2) (f 3) Search and Rescue (EP-204-10) Evacuation (EP-20 4-30 ) SECURITY FORCE: Response for Fire, Disaster, Evacuation, or Radiological Emergency (EP-205-1) Control of In-plant Access for Emergency Response Personnel (EP-205-2) Control of Site Area Access During Fire, Disaster, or Radiological Emergency (EP-205-3) Security Emergency During Fire, Disaster, or Radiological Emergency (EP-205-4) Evacuation (EP- 20 5-30 ) OFF-SITE RADIOLOGICAL EMERGENCY TEAM: Activation (EP-210-1) Functions (EP-210-2) 1 Enclosure 1 Page 1 of 1
EP- 103 Rev. 0.B O V ' EMERGENCY TEAM AND SECURITY FORCE ACTIVATION .%iATRIX e q M O 7 'o 4 ko C E
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Oi j b EP-103 Rev. 0.B ALERT CHECK-OFF LIST Immediate Actions
- 1. On-shift personnel notified.
- 2. Security notified.
- 3. On-duty supervisor notified.
~
- 4. TSC activated. ,
- 5. Government agencies notified.
a) Michigan State Police b) Monroe County Sheriff c) NRC Operations Center d) NRC Region III a) Canada
- 6. Necessary emergency teams activated.
- 7. Off-site emergency support requested.
l a) Frenchtown Volunteer Fire Department b) EMTS Ambulance Service c) Seaway Hospital ! 8. Evacuation of affected areas on-site ordered. l
- 9. Radiological release involved, a) Radiological sampling ordered b) Off-side dose projected (estimated)
- 10. Protective actions ordered on-site.
- 11. Protective actions recommended off-site.
i Attachment 2 Page 1 of 2 l t
1 EP-103 Rev. 0.B Follow-up Actions
- 1. EOF placed in standby.
- 2. Follow-up actions of abnormal and EOP procedures are completed.
- 3. Assess plant conditions and reclassify if necessary.
- 4. Follow-up reports completed.
a) On-shift personnel b) On-duty supervisor c) Michigan State Police d) Monroe County Sheriff e) NRC Operations Center f) NRC Region III
- 5. Long term organization established.
- 6. Emergency classification downgraded or the emergency ,
is terminated.
- 7. Closecut summary completed.
a) Michigan State Police b) Monroe County Sheriff c) NRC Operations Center d) NRC Region III
- 8. Reentry / Recovery initiated.
END Attachment 2 Page 2 of 2 h
EP-104 Rev. 0.B ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
SITE AREA EMERGENCY
, RECORD OF APPROVAL AND CHANGES Submitted by , nM Supervisor of Radiologie g y sncy Date Response Preparedness Approved by 9W Chairman - Liaison Committee Date Liaison Revision Committee No. Submitted Date Approval Date 1
2 3 4 5 ) 6 I 7 i 8 l, O
i l EP-104 Rev. 0.B l l 1 . ENRICO FERMI ATOMIC POWER PLANT l i ! UNIT NO. 2 i i ! Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE . 1 I
Title:
SITE AREA EMERGENCY l Y P I b i t f I p 9 [ l L [ l l'
. 1 1 a i
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4 l l l EP-104 ' Rev. 0.B ' 1 SITE AREA EMERGENCY l TABLE OF CONTENTS Page l . C- Entry Conditions..................................... 1 4 2.0 General Information.................................. 1 3.0 Immediate Actions.................................... 2 t 4.0 Follow-up Actions.................................... 4 i t j Eraclosures Emergency Response Team Procedure Index............. Enclosure 1 (Attachments
' Emergency Team and Security Force Activation
, Matrix............................................ Attachment 1
/ Site Area Emergency Check-off List.................. Attachment 2 e
O
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s i e z l e I L j i l, 1 1
'u EP-104 Rev. 0.B
- Page 1 1.0 Entry Conditions An emergency condition has been classified as a Site Area Emergency in accordance with EP-101.
2.0 General Information 2.1 Ultimate responsibility for assessment of plant emergency conditions and for directing corrective actions rests with the Emergency Director. The judgment of the Emergency Director is paramount in proper control of the emergency and may take precedence over guidelines in this procedure. 2.2 Emergency notifications of Government Agencies are provided for in step 3.3 of this procedure. Government agencies should be notified as soon as possible, but must be notified within 15 minutes of recognition of the emergency. (\/) 2.3 The Site Area Emergency check-off list (Attachment 2) is a helpful guide in ensuring all applicable steps of this procedure are completed. However, it should not be used in lieu of the procedure. 2.4 The Nuclear Shift Supervisor shall continue to act as Emergency Director until relieved of this responsi-bility by the Superintendent-Nuclear Production (Plant Superintendent) (or his alternate) , or until the emergency situation is terminated. 2.4.1 When the Plant Superintendent (or his alternate) relieves the Nuclear Shift Supervisor and the Technical Support Center (TSC) is activated, the functions of the Emergency Director shall be shifted to the TSC. 2.4.2 The Nuclear Shift Supervisor shall remain in
- the plant to supervise plant operations.
2.5 Once the EOF has been activated, the EOF Coordinator . shall relieve the Emergency Director of the following responsibilities: 2.5.1 Notification of and communications with, federal, state and county agencies; t 2.5.2 Off-site radiological environmental sampling;
l I l EP-104 Rev. 0.B Page 2 2.5.3 Recommendations to state and county agencies regarding appropriate protective actions; 2.6 When a Site Area or General Emergency is declared, and the EOF is activated, the Vice President, Nuclear Operations (or his alternate, the Assistant Vice President and Manager, Nuclear Operations) shall establish himself as the Emergency Officer and shall assume overall responsibility for the DECO response to the emergency. The Emergency Director and EOF Coordinator will report directly to the Emergency Officer. The Emergency Officer shall be directly responsible for providing updates and information to the Joint Public Information Team (JPIT) for dissemination to the press and the public. 3.0 Immediate Actions NOTE: If the emergency has been upgraded from an Unusual Event or Alert, skip those steps which have already been completed. The steps in this procedure can be carried out in any order. However, the following order is recommended. 3.1 Inform on-shift personnel, including security, of the emergency classification. 3.2 Notify DECO personnel of the emergency situation using EP-290 (Emergency Notifications), step 3.1. Activate the Technical Support Center augmentation personnel using EP-290 (Emergency Notifications), step 3.6 and EP-301-1. (Technical Support Center: Activation) Activate the Emergency Operations Facility (EOF) and the Joint Public Information Center (JPIC) using EP-290 (Emergency Notifications) step 3.7 and EP-303-1 (Emergency Operations Facility: Activation). NOTE: If the primary TSC location is not habitable deter-mine which functions will be moved to the Control Room and which functions will be accomplished in the EOF. Have pre-printed signs hung by security Force personnel on the doors of the TSC indicating that personnel are to proceed to the alternate location. As the Technical Support Center is activated, transfer control of all Emergency Response activities not directly related to plant operation to the Technical Support Center. This may take place at anytime during the execution of this procedure. As
EP-104 O(_/ Rev. 0.B Page 3 the EOF is activated, transfer those functions outlined in EP-303-2 to the EOF. 3.3 Notify the State of Michigan, Monroe County, Canada (if not already notified) and the Nuclear Regulatory Commission of the emergency situation using EP-290 (Emergency Notifications), step 3.1. NOTE: If the On-Scene State Emergency Operations Center has been established, all communica-tions to the counties and Canada will be made by the State. 3.4 Activate the Emergency Teams as necessary to respond to the Emergency Conditions (see Attachment 1). Off-shift personnel may be called in to supplement the teams.
- Unless otherwise instructed, the Emergency Teams will carry out the steps of the applicable Emergency Plan Implementing Procedures. (See Enclosure 1) .
[\_)/ Relay the following information to the Emergency Team Leaders:
- 1. Suspected cause of the emergency situation.
- 2. Areas with abnormal personnel hazards.
- 3. Other Emergency Teams which are 4ctivated.
- 4. Pertinent plant lineups and corrective actions taken by the Emergency Director.
- 5. Any other information which may be-useful to the team leader in performing the team functions.
NOTE: If the primary OSC location is not habitable designate an alternate OSC location. Have pre-printed signs hung on the OSC doors by Operations Personnel indicating that personnel are to proceed to the alternate location. O
l EP-104 Rev. 0.B Page 4 3.5 If off-site emergency support is necessary from any of the following:
- 1. Frenchtown Volunteer Fire Department.
- 2. EMTS Ambulance Service. .
- 3. Seaway Hospital.
Notify the appropriate organization in accordance with EP-290 (Emergency Notification), step 3.3. 3.6. Order an evacuation of unnecessary personnel from those areas with actual or potential abnormal personnel hazards in accordance with EP-530 (Evacuation). All evacuated personnel must be accounted for within 30 minutes of the evacuation order. 3.7 If there is a potential for the release of radio-logical materials greater than technical, specification limits: 3.7.1 Have radiological sampling conducted in accordance with EP-201-2 (On-Site RET: Functions) and/or EP-210-2 (Of f-Site RET: Functions), as applicable. 3.7.2 Estimate the on-site and off-site doses in accordance with EP-303-3 (Manual Dose Assessment Calculation Procedure). 3.7.3 If an on-site radiological hazard exists, order on-site protective actions (use of protective equipment, use of potassium iodide, and/or evacuation (see step 3.6)) as necessary. 3.7.4 If necessary, recommend protective actions for the public to the State of Michigan, and Monroe County, and Canada in accordance with applicable NRC and FEMA guidelines. 3.8 If a significant radiological hazard exists off-site, reclassify the emergency (steps 3.5 and 3.6, EP-101). O
l s l l N EP-104 P.e v . 0.B Page 5 4.0 Follow-up Actions 4.1 Ensure that the follow-up actions of applicable Abnormal and Emergency Operating Procedures are performed. 4.2 Continue to assess the plant conditions. Direct corrective actions as necessary to bring the emergency under control and mitigate the consequences. If significant changes in the emergency situation occur, carry out steps 3.5 and 3.6 of EP-101 (Classification of Emergencies). 4.3 Continue to monitor the progress of Emergency Teams in controlling the emergency. Ensure that additional personnel, support, and equipment are made available as necessary. 4.4 Periodically make follow-up status reports to on-shift personnel. Ensure all operations personnel and O' emergency response personnel are kept apprised of personnel hazards, plant line-ups, corrective actions, and steps taken to control or mitigate the emergency. 4,5 Periodically make follow-up reports to the State of Michigan, Monroe County, and the Nuclear Regulatory Commission using EP-290 (Emergency Notifications) step 3.2. l 4.6 A long term relief rotation shall be established to ensure personnel are not required to remain at their i assigned positions for an excessive period of time (normally not greater than 12 hours). 4.7 The Emergency Director may downgrade the emergency classification to an ALERT if:
- 1. Plant conditions no longer meet the intent of the Emergency Action Levels (EP-101) for a SITE AREA EMERGENCY, and;
- 2. The actual or potential off-site and on-site radiological hazards are under control or have been eliminated, and;
[
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l (_)s 3. The Emergency Officer concurs,
EP-104 Rev. 0.B Page 6 4.8 The emergency situation may be terminated if:
- 1. Release of radioactive materials to the environment is under control or has ceased.
- 2. Fire, flooding, or similar emergency conditions are under control or have ceased.
- 3. Radiation levels inall in-plant areas are stable or are decreasing with time.
- 4. Reactor and associated systems are considered to be in a stable, safe condition.
4.9 If the emergency classification is downgraded or if the emergency is terminated: 4.9.1 A verbal summary of the downgrade or closeout shall be provided to the State of Michigan, Monroe County, Canada, and the Nuclear Regulatory Commission followed by a written summary within 8 hours. 4.9.2 Carry out EP-401 (Re-entry) and EP-402 (Recovery) as applicable. I l
E EP-104
\_/ Rev. 0.B EMERGENCY RESPONSE TEAMS PROCEDURE INDEX ,
ON-SITE RADIOLOGICAL EMERGENCY TEAM: Activation (EP-201-1) Fire, Explosion or Other Incident Involving Potential Radiological Hazards (EP-201-2) PERSONNEL MONITORING TEAM: Activation (EP-202-1) Functions (EP-202-2) FIRE BRIGADE: Activation (EF-203-1) Fire Involvina Radiological Hazards (EP-203-2) DAMAGE AND RESCUE TEAM: Activation (EP-204-1) Disaster (EP-204-2)
. Search and Rescue (EP-204-10)
Evacuation (EP-204-30) SECURITY FORCE: Response for Fire, Disaster, Evacuation, or Radiological Emeroency (EP-205-1) Control of In-plant Access for Emergency Response Personnel (EP-205-2) Control of Site Area Access During Fire, Disaster, or Radiological Emergency (EP-205-3) Security Emergency During Fire, Disaster, or Radiological Emergency (EP-205-4) Evacuation (EP-205-30) OFF-SITE RADIOLOGICAL EMERGENCY TEAM: Activation (EP-210-1) Functions (EP-210 -2 ) Enclosure 1 Page 1 of 1 As
EP-104 Rev.0.B O EMERGENCY TEAM AND SECURITY FORCE ACTIVATION MATRIX o u2 5 n 3/ 0/ f 8 2 b
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EP-104 Rev. 0.B SITE AREA EMERGENCY CHECK-OFF LIST Immediate Actions l
- 1. On-shift personnel notified.
- 2. Security notified.
- 3. On-duty supervisor notified.
- 4. TSC activated.
- 5. EOF activated.
- 6. Government agency notified.
a) Michigan State Police b) Monroe County Sheriff c) NRC Operations Center d) NRC Region III e) Canada (if not already notified)
- 7. Necessary emergency teams activated.
- 8. Off-site emergency support requested.
a) Frenchtown Volunteer Fire Department b) EMTS Ambulance Service c) Seaway Hospital
- 9. Evacuation of affected on-site areas ordered.
- 10. Radiological release involved.
a) Radiological sampling ordered b) Off-site dose projected (estimated)
- 11. Protective actions ordered on-site.
- 12. Protective actions recommended off-site.
Attachment 2 Page 1 of 2 O
EP-104 Rev. 0B Follow-up Actions
- 1. Follow-up actions of Abnormal and EOP procedures are complete.
- 2. Assess plant conditions and reclassify.
- 3. Follow-up reports completed.
a) On-shift personnel b) On-duty supervisor c) Michigan State Police d) Monroe County Sheriff e) NRC Operations Center f) NRC Region III
- 4. Long term organization established.
- 5. Emergency Classification downgraded or the emergency is terminated.
- 6. Closeout summary completed.
a) Michigan State Police b) Monroe County Sheriff c) NRC Operations Center d) NRC Region III
- 7. Reentry / Recovery initiated.
END Attachment 2 Page 2 of 2 O
.1 1
v 5-EP-105 O Rev. 0.B l ENRICO FERMI ATOMIC POWER PLANT I UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
GENERAL EMERGENCY RECORD OF APPROVAL AND CHANGES Submitted by M i Supervisor of Radiologica1 Em@ncy Date Response Preparedness Approved by n Chairman - Liaison C W ittee Date Liaison Revision Committee No. Submitted Date Approval Date 1 2 3 4 5 6 7 , 8 i lR. V l
__.. .____.. __________ .. _. _ .. .._ . ___. . ._ _ _. _ _ _ _ ..____-_--. .-_. . .. .. ___. __ _ _ ... _ - _ = 4
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i i EP-105 Rev. 0.B i I i ! i I ! I i ENRICO FERMI ATOMIC POWER PLANT I t j UNIT NO. 2 l l Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
GENERAL EMERGENCY i 1 i i
- 0 4
e i I I l I
4 EP-105 Rev. 0.B n GENERAL EMERGENCY TABLE OF CONTENTS
, Page 1.0 Entry Conditions..................................... 1 2.0 General Information.................................. 1 3.0 Immediate Actions.................................... 2 4.0 Follow-up Actions.................................... 4 l Enclosures Emergency Response Team Procedure Index............ Enclosure 1 Attachments Emergency Team and Security Force Activation Matrix............................................. Attachment 1 , General Emergency Check-off List.................... Attachment 2
,t 8 i i i
O EP-105 Rev. 0.B Page 1 1.0 Entry Conditions An emergency condition has been classified as a General Emergency in accordance with EP-101. 2.0 General Informa ion 2.1 Ultimate responsibility for assessment of plant emergency conditions and for directing corrective actions rests with the Emergency Director. The judgment of the Emergency Director is paramount in proper control of the emergency and may take precedence over guidelines in this procedure. 2.2 Emergency notifications of Government Agencies are provided for in step 3.3 of this procedure. Note that Government Agencies should be notified as soon as possible, but must be notified within 15 minutes of recognition of the emergency. (m') s/ 2.3 The General Emergency check-off list (Attachment 2) is a helpful guide in ensuring all applicable steps of this procedure are completed. However, it should not be used in lieu of the procedure. 2.4 The Nuclear Shift Supervisor shall continue to act as Emergency Director until relieved of this responsi-bility by the Superintendent-Nuclear Production (Plant Superintendent) (or his alternate), or until the emergency situation is terminated. 2.4.1 When the Plant Superintendent (or his alternate) relieves the Nuclear Shift Supervisor and the Technical Support Center (TSC) is activated, the functions of the Emergency Director shall be shifted to the TSC. 2.4.2 The Nuclear Shift Supervisor shall remain in the plant.to supervise plant operations. 2.5 Once the EOF has been activated, the EOF Coordinator shall relieve the Emergency Director of the following responsibilities: 2.5.1 Notification of and communications with, /} \_J federal, state and county agencies; 2.5.2 Off-site radiological environmental sampling;
EP-105 Rev. 0.B h
. Page 2 2.5.3 Recommendations to state and county agencies regarding appropriate protective actions; 2.6 When a Site Area or General Emergency is declared, and the EOF is activated, the Vice President, Nuclear Operations (or his alternate, the Assistant Vice President, and Manager, Nuclear Operations) shall establish himself as the Emergency Officer and shall assume overall responsibility for the DECO response to the emergency. The Emergency Director and EOF Coordinator will report directly to the Emergency Officer. The Emergency Officer shall be directly responsible for providing updates and information to the JPIT for dissemination to the press and the public.
3.0 Immediate Actions NOTE: If the emergency has been upgraded from another classification, skip those steps which have already been completed. The steps in this procedure can be
, carried out in any order. However, the following order is recommended.
3.1 Inform on-shift personnel, including security, of the emergency classification. 3.2 Notify DECO personnel of the emergency situation using EP-290 (Emergency Notifications), step 3.1. Activate the Technical Support Center augmentation personnel using EP-290 (Emergency Notifications), step 3.6 and EP-301-1. (Technical Support Center: Activation) Activate the Emergency Operations Facility (EOF) and the Joint Public Information Center (JPIC) using EP-290 (Emergency Notifications) step 3.7 and EP-303-1 (Emergency Operations Facility; Activation). NOTE: If the primary TSC location is not habitable determine which functions will be moved to the Control Room and which functions will be accomplished in the EOF. As the Technical Support Center is activated, transfer control of all Emergency Response activities not directly related to plant operation to the Technical Support Center. This may take place at anytime during the execution of this procedure. As the EOF is activated, transfer those functions out-lined in EP-303-2 to the EOF.
- c ,; -
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EP-105 w Os Rev. 0.B Page 3 3.3 Notify the State of Michigan, Monroe CoDnty, Canada (if not already notified) and 'the Nuclear Regulatory Commission of the emergency situation using EP-290 m (Emergency Notifications), step 3.1. NOTE: If the On-Scene State Emergency Operations Center has been established, all' communica-tions to the counties and Canada will be made by the State. - 3.4 Activate the Emergency Teams as necessary 'to respond to the Emergency Conditions (see Attachment 1) . Off-shift personnel may be called'in to supplement the teams. Unless otherwise instructed, the Emergency Teams will - carry out the steps of the applicable Emergency Plan Implementing Procedures. (See Enclosure 1) v Relay the following information-to'the Emergency Team Leaders: () 1. Suspected cause of the emergency situation.
- 2. Areac with abnormal personnel hazards. _
- 3. Other Emergency Teams which are activated.
- 4. Pertinent plant lineups and corrective actions taken by the Emergency Director.
~
- 5. Any other information,which may be useful to the team leader in performing the team functions.
NOTE: If the primary OSC location is not habitable
~
designate an alternate OSC location. Have signs hung on the OSC doors by Operations Personnel indicating that personnel are to ' proceed to the alternate location. 3.5 If off-site emergency support is necessary from any of the following: .
- 1. Frenchtown Volunteer Fire Department.
- 2. EMTS Ambulance Service. -
() 3. Seaway Hospital. O
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EP-105 Rev. 0.B Page 4 Notify the appropriate organization in accordance with EP-290 (Emergency Notifications), Step 3.3. 3.6. Order an evacuation of unnecessary personnel from those areas with actual or potential abnormal personnel hazards in accordance with EP-530 (Evacuation). All evacuated personnel must be accounted for within 30 minutes of the evacuation order. 3.7 If an on-site radiological hazard exists, order on-site protective actions (use of protective equipment, use of potassium iodide, and/or evacuation (see step 3.6)) as necessary. 3.8 If necessary, recommend protective actions for the public to the State of Michigan, and Monroe County, and Canada in accordance with applicable NRC and FEMA guidelines. 4.0 Follow-up Actions 4.1 Ensure that the follow-up actions of applicable Abnormal and Emergency Operations Procedures are performed. 4.2 Continue to assess the plant conditions. Direct corrective actions as necessary to bring the emergency under control and mitigate the consequences. 4.3 Continue to monitor the progress of Emergency Teams in controlling the emergency. Ensure that additional personnel, support, and equipment are made available as necessary. 4.4 Periodically make follow-up status reports to on-shift personnel. Ensure all operations personnel and emergency response personnel are kept apprised of personnel hazards, plant line-ups, corrective actions, and steps taken to control or mitigate the emergency. 4.5 Until the EOF is activated, periodically make follow-up reports to the State of Michigan, Monroe County, and the Nuclear Regulatory Commission using EP-290 (Emergency Notifications) step 3.2.
Oh s/ EP-105 Rev. 0.B Page 5 4.6 A long term relief rotation shall be established to ensure personnel are not required to remain at their assigned positions for an excessive period of time (normally not greater than 12 hours). 4.7 The Emergency Director may downgrade the emergency classification as follows: 4.7.1 To a SITE AREA EMERGENCY if:
- 1. Plant conditions no longer meet the Emergency Action Levels (EP-101) for a General Emergency, and;
- 2. The actual or potential off-site radiological hazard is under control or has been eliminated, and;
- 3. The Emergency Officer has conferred with s
the State of Michigan Officials, and;
- 4. The Emergency Officer concurs.
4.7.2 To an ALERT if:
- 1. Plant conditions no longer meet the intent of the Emergency Action Levels (EP-101) for a SITE AREA EMERGENCY, and;
- 2. The actual or potential off-site and on-site radiological hazards are under control or have been eliminated, and;
- 3. The Emergency Officer has conferred with the State of Michigan Officials, and; l 4. The Emergency Officer concurs.
4.8 The emergency situation may be terminated if:
- 1. Release of radioactive materials to the environment is under control or has ceased.
- 2. Fire, flooding, or similar emergency conditions are under control or have ceased.
O J l
EP-105 h Rev. 0.B Page 6
- 3. Radiation levels in all in-plant areas are stable or are decreasing with time.
- 4. Reactor and associated systems are considered to be in a stable, safe condition.
4.9 If the emergency classification is downgraded or the emergency is terminated: 4.9.1 A verbal summary of the downgrade or closecut > shall be provided to the State of Michigan, Monroe County, Canada, and the Nuclear Regulatory Commission followed by a written summary within 8 hours. 4.9.2 Carry out EP-401 (Re-entry) and EP-402 (Recovery) as applicable. O 1 l t
l l l () EP-105 Rev. 0.B EMERGENCY RESPONSE TEAMS PROCEDURE INDEX ON-SITE RADIOLOGICAL EMERGENCY TEAM: Activation (EP-201-1) Fire, Explosion or Other Incident Involving Potential Radiological Hazards (EP-201-2) PERSONNEL MONITORING TEAM: Activation (EP-202-1) Functions (EP-202-2) ' FIRE BRIGADE: I Activation (EP-203-1) - Fire Involving Radiological Hazards (EP-203-2) DAMAGE AND RESCUE TEAM: s Activation (EP-204-1) Disaster (EP-204-2) Search and Rescue (EP-204-10) Evacuation (EP-204-30) SECURITY FORCE: Response for Fire, Disaster, Evacuation, or Radiological Emergency (EP-205-1) Control of In-plant Access for Emergency Response Personnel (EP-205-2) Control of Site Area Access During Fire, Disaster, or Radiological Emergency (EP-205-3) Security Emergency During Fire, Disaster, or Radiological Emergency (EP-205-4) Evacuation (EP-205-30) OFF-SITE RADIOLOGICAL EMERGENCY TEAM: i Activation (EP-210-1) Functions (EP-210-2) , 3 Enclosure 1 s/ Page 1 of 1
EP-105 Rev.0,B (D U EMERGENCY TEAM AND SECURITY FORCE ACTIVATION MATRIX o k y* n w
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( EP-105 Rev. 0.B GENERAL EMERGENCY CHECK-OFF LIST Immediate Actions
- 1. On-shift personnel notified.
- 2. Security notified.
- 3. On-duty supervisor notified.
- 4. TSC activated.
- 5. EOF activated.
- 6. Government agencies notified.
l a) Michigan State Police b) Monroe County Sheriff c) NRC Operations Center ! d) NRC Region III e) Canada (if not already notified) ( ) 7. Necessary emergency teams notified.
- 8. Off-site support requested.
a) Frenchtown Volunteer Fire Department b) EMTS Ambulance Service c) Seaway Hospital
- 9. Evacuation of affected areas on-site ordered.
l 10. Radiological release involved. i a) Radiological sampling ordered b) Off-side dose projected (estimated)
- 11. Protective actions ordered on-site.
- 12. Protective actions recommended off-site.
I i Attachment 2 O' Page 1 of 2 l l
EP-105 Rev. 0.B Follow-up Actions
- 1. Follow-up actions of Abnormal and EOP procedures are completed.
- 2. Assess plant conditions.
- 3. Follow-up reportt ccapleted.
a) On-rhift personnel b) On-outy supervisor c) Michigan State Police d) Monroe Ccanty Sheriff e) NRC Operations Center f) NRC Region III
- 4. Long term organization established.
- 5. Emergency classification downgraded or the emergency is terminated.
- 6. Closecut summary completed.
a) Michigan State Police b) Monroe County Sheriff c) NRC Operations Center d) NRC Region III
- 7. Reentry / Recovery initiated.
END Attachment 2 Page 2 of 2
/ ; EP-110 k) Rev. 0.B ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
ORGANIZATION AND RESPONSIBILITIES RF. CORD OF APPROVAL AND CHANGES Submitted by f Supervisor of Radiol cat Emergency Date Response Preparedn a Approved by Chairman - Liaison Committee Date Liaison (~ Revision Committee v No. Submitted Date Approval Date 1 2 3 4 5 6 7 8
j 1 i i 1 l l l EP-110 1 Rev. 0.B i t l i i ' ENRICO FERMI ATOMIC POWER PLANT ; UNIT NO. 2 I l I j Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
ORGANIZATION AND RESPONSIBILITIES i 4 i
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- EP-110 j Rev. 0.B I ORGANIZATION AND RESPONSIBILITIES
! l 4 TABLE OF CONTENTS ' l t ! Page i 1.0 Purpose............................................... 1 i i 2.0 References............................................ 1 3.0 General Information................................... 1 i i 4.0 Assignments and Responsibilities...................... 2 [ J f
- l 1
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EP-110 O' Rev. 0.B Page 1 1.0 Purpose To describe the organization and responsibilities of l Detroit Edison personnel for implementation of the Enrico l ~ Fermi Atomic Power Plant, Unit 2, Radiological Emergency Response Plan (RERP). 2.0 References 2.1 Enrico Fermi Atomic Power Plant, Unit 2, Radiological Emergency Kesponse Plan. 2.2 Recovery Organization (EP-lll). 3.0 General Information 3.1 In the event of an emergency, personnel responsi-bilities include the following: 4 3.1.1 Taking action to control the emergency. i 3.1.2 Taking action to secure the release of radioactivity. 3.1.3 Securing plant systems in a stable and safe configuration. 3.1.4 Prompt notification of off-site authorities. 3.1.5 Providing current information to off-site authorities and making recommendations for off-site protective actions. 3.2 Communications 3.2.1 Communications are manned on a 24 hour basis. 3.2.2 Initial notifications are made from the Control Room. 3.2.3 When the Technical Support Center (TSC) or the Emergency Operations Facility (EOF) is manned, communication responsibilities are transfered to these facilities. l l O
EP-110 Rev. 0.B Page 2 3.3 Long Term Emergency 3.3.1 Sufficient staffing is provided to ensure the Emergency Organization can operate for an extended period of time. 3.3.2 A long term relief rotation shall be established to ensure personnel are not required to remain at their assigned positions for an excessive period of time (normally not greater than 12 hours). 3.4 If required, personnel designated to fulfill specific responsibilities may be replaced by other qualified personnel. 4.0 Assignments and Responsibilities 4.1 Emergency Officer The Vice President - Nuclear Operations (or his alternate, the Assistant Vice-President and Manager - Nuclear Operations) is assigned as the Emergency Officer. The Emergency Officer is in overall charge of the emergency. Reporting to him are the Emergency Director, EOF Coordinator, and the JPIC Admini-strator. The responsibilities of the Emergency Officer include:
- 1. Ensuring that the full resources of Detroit Edison Company are made available as required to secure the plant systems and to minimize the effects of the incident on plant personnel and the public. This includes availability of other utilities and vendor resources.
- 2. Ensuring information released to the public is
, accurate and directed through proper channels.
- 3. Communications with Corporate Headquarters.
- 4. Establishing the long term emergency and recovery organizations.
O
) EP-110 Rev. 0.B Page 3 4.2 Control Room (CR)
Control Room staffing requirements are described in Enrico Fermi Atomic Power Plant Unit 2 Final Safety Analysis Report (FSAR) . Upon initiation of an emergency, the Nuclear Shift Supervisor or his alternate the Nuclear Assistant Shift Supervisor assumes the duties of the Emergency Director until relieved by the Superintendent-Nuclear Production. 4.2.1 When acting as the Emergency Director, the Nuclear Shift Supervisor is responsible for the following:
- 1. Implementing the immediate on-site corrective and protective actions to bring the incident under control and mitigate its effects.
- 2. Initiating emergency classification.
() 3. Appointing on-site personnel as necessary for assistance with current and continuing emergency control.
- 4. If necessary, authorizing plant and emergency workers to receive radiation doses in excess of normal 10 CFR 20 limits. Emergency exposure limits are described in Health Physics Procedure
- 69.000.15 (Emergency Exposure Limits). '
- 5. Obtaining assistance of support organi-zations as necessary.
l 6. Initiating notifications and protective action recommendations to persons or organizations responsible for imple-menting emergency measures.
- 7. Ensuring that information to be released is accurate and is directed through proper channels.
- 8. Performing initial dose projections and assessments.
I
EP-110 Rev. 0.B Page 4 4.2.2 Nuclear Assistant Shift Supervisor The Nuclear Assistant Shift Supervisor is responsible to the Emergency Director for the following:
- 1. If required, assuming the role of Emergency Director.
- 2. Providing assistance to the Emergency Director at his request.
- 3. Coordinating reports of actions and information from the Nuclear Supervising Operator.
4.2.3 Nuclear Supervising Operator The Nuclear Supervising Operator is responsi-ble to the Nuclear Assistant Shift Supervisor for the following:
- 1. Carrying out necessary corrective actions to mitigate the emergency.
- 2. Reporting actions taken and making recommendations to the Nuclear Assistant Shift Supervisor.
- 3. Assuming responsibilities as Fire Brigade Leader when activated.
4.2.4 Nuclear Power Plant Operator (NPPO) The NPPO is responsible to the Nuclear Supervising Operator for the following:
- 1. Carrying out corrective actions on systems not accessible by controls in the control room.
- 2. Reporting actions taken and making recommendations to the Nuclear Supervising Operator.
The NPPO also serves as a member of the Fire Brigade. O
( O EP-110 Rev. 0.B Page 5 4.2.5 Shift Technical Advisor The Shift Technical Advisor is normally responsible to the Nuclear Shift Supervisor. During an emergency classified as an Alert or higher he is responsible to the Emergency Operations Advisor. His responsibilities are the following:
- 1. Advising the Nuclear Shift Supervisor, Nuclear Supervising Operator, and/or the Emergency Operations Advisor on technical matters concerning the plant during an emergency.
- 2. Performs dose assessment until the TSC or EOF is activated.
4.2.6 Communicator The Communicator is responsible to the Nuclear Shift Supervisor for the following: {)
- 1. Making required notifications and communications as directed.
- 2. Contacting additional support personnel as directed.
The following additional personnel are assigned for an Alert. 4.2.7 Emergency Operations Advisor. The Operations Engineer (or his alternate,- the Assistant Operations Engineer or Operations l Supervisor) is assigned as Emergency Opera-I tions Advisor and is responsible to the Emergency Director for the following:
- 1. Advising the Emergency Director on matters concering plant operations.
- 2. Providing work assignments for Operations Group.
O
EP-110 Rev. 0.B Page 6 4.2.8 Reactor Engineer. The Reactor Engineer (or his alternate, the Assistant Operations Engineer or Operations Supervisor) is responsible to the Emergency Operations Advisor for the following:
- 1. Analyzing conditions affecting core safety.
- 2. Advising the Operations Engineer on all matters relating to reactor core safety.
4.3 Operational Support Center (OSC) The OSC provides an assembly point for shift support personnel to be assigned duties supporting emergency operations. 4.3.1 Operational Support Center (OSC) Coordinator The Maintenance Engineer (or his alternate, the General Foreman or the Senior Engineer) is assigned as OSC Coordinator and is responsible for the following:
- 1. Coordinating the efforts of all Emergency Teams.
- 2. Augmenting Emergency Teams using unassigned or off-shift personnel assembled in the OSC.
- 3. Activating off-shift personnel during back shifts.
- 4. Providing replacement emergency equipment and necessary parts and support for emergency damage repair.
4.3.2 All incoming shift personnel who are not otherwise assigned ~will report to the OSC. 4.4 Technical Support Center (TSC) The TSC will provide information on plant status for use by technical and management personnel in support of the actions being performed in the control room. 1 1
EP-110 Rev. 0.B Page 7 The TSC is activated when an emergency reaches the Alert level and serves as the primary information and communications source to the NRC, OSC, and the Emergency Operations Facility (EOF), and will perform the functions of the EOF until the EOF is activated. 4.4.1 Emergency Director The Superintendent-Nuclear Production (or his alternate, the Assistant Superintendent or Operations Engineer) is responsible for relieving the Nuclear Shift Supervisor as the Emergency Director. The Emergency Director is responsible to the Emergency Officer for the following: ,
- 1. Coordinating and directing the combined activities of Detroit Edison personnel in the control Room, Technical Support Center, Operational Support Center, and elsewhere on owner-controlled property.
- 2. Classifying the emergency.
- 3. Notifying off-site plant, corporate, and government personnel. (Upon activation of the EOF, the EOF Coordinator is the liaison to all off-site agencies).
- 4. Issuing instructions to emergency response teams and ensuring that the appropriate procedures are being followed.
- 5. Directing dose projection and assessment I and recommending off-site protective action measures. (Upon activation of the EOF, the EOF Coordinator is responsible for this function).
- 6. Ensuring continuity of on-site resources.
- 7. If necessary, authorizing plant emergency workers to receive radiation doses in excess of normal 10 CFR 20 limits.
i Emergency exposure limits are described in Health Physics Procedure 69.000.15 (Emergency Exposure Limits). l
EP-110 Rev. 0.B Page 8 4.4.2 Technical Engineer (or his alternate, the Equipment Performance Engineer or the Engineering Supervisor) is responsible to the Emergency Director for the following:
- 1. Providing recommendations to the Emergency Director concerning plant technical matters.
- 2. Providing technical support.
- 3. Providing work assignments for Technical and Engineering Groups.
4.4.3 Nuclear Safety Advisor The General Supervisor-Nuclear Safety and Plant Engineering (or his alternate, the Supervisor-System and Plant Engineering or the Supervisor-Safety and Performance Engineering) is assigned as the Nuclear Safety Advisor and is responsible to the Emergency Director for h the following:
- 1. Advising the Emergency Director on engineering matters.
- 2. Providing work assignments for Nuclear Engineering support groups.
4.4.4 Radiation Protection Advisor The General Supervisor-Health Physics (or his alternate, the Health Physics Supervisor) is assigned as the Radiation Protection Advisor and is responsible to the Emergency Director for the following:
- 1. Performing dose projections with assis-tance from Dose Assessment Team.
- 2. Dispatching Radiological Emergency Teams on-site.
- 3. Evaluating on-site radiological surveys.
- 4. Maintaining personnel exposure records.
.- -. - .- - = _ - _ . _ _
EP-110 Rev. 0.B Page 9
- 5. Evaluating results of off-site environ-mental surveys until activation of the EOF.
- 6. Ensuring that radiation protection equipment, such as dosimetric devices, respiratory protection gear and protective clothing is issued and controlled.
- 7. Advising the Emergency Director concerning radiological protective actions.
- 8. Directing decontamination activities.
- 9. Providing work assignments for radiation protection personnel.
4.4.5 Environmental Assessment Team () Personnel assigned as members of the Environ-mental Assessment Team are responsible to the Radiation Protection Advisor for the following: ]
- 1. Assessing meteorological conditions.
- 2. Performing both on-site and off-site dose assessment and projections.
4.4.6 Radiochemistry Advisor The Supervisor-Radiochemistry (or his alternate) is assigned as the Radiochemistry Advisor and is responsible to the Emergency l Director for the following: I
- l. Directing inplant sampling activities, t 2. Directing Radiochemistry Laboratory l
activities.
- 3. Advising the Emergency Director on radwaste processing, storage and disposal.
EP-110 Rev. 0.B Page 10 4.4.7 Security Liaison Officer The Security Shift Lieutenant (or his alternate, the Nuclear Security Chief) is assigned as Security Liaison Officer and is respor.91ble to the Emergency Director for the following:
- 1. Ensuring that site security is maintained and appropriate contingency measures are implemented.
- 2. Ensuring that security and traffic control measures are in effect for on-site, including traffic direction during an evacuation.
- 3. Establishing and maintaining a security checkpoint at the entrance to the TSC.
4.4.8 Administration and Support Coordinator The Administrator-Nuclear Production (or his alternate) is assigned as the Administration and Support Coordinator and is responsible to the Emergency Director for the following:
- 1. Coordinating logistic support for emergency personnel.
- 2. Advising the Emergency Director and Nuclear Operations Staff on matters relating to logistic support (personnel and equipment).
- 3. Providing documentation support and control including developing and l implementing a program for maintaining long term records. -
- 4. Providing work schedules for Nuclear Operations emergency response personnel.
- 5. Supervising the status board updaters, clerks, communicators, and secretaries in the performance of their duties.
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' EP-110 Rev. 0.B Page 11 4.4.9 Quality Assurance Advisor - The Supervisor-Operations Assurance (or his alternates, the Assistant Operations Assurance Supervisor or the Senior Operations Assurance Engineer) is assigned as the Quality Assurance Advisor and is responsible to the Emergency Director for the following:
- 1. Maintaining records concerning the
' emergency.
- 2. Assisting in preparation of specific emergency procedures as required.
- 3. Ensuring all quality assurance procedures applicable to the emergency are followed.
4.4.10 Thermal Hydraulics, Mechanical, Electrical and Instrument and Control Engineers are respons-ible to the Nuclear Safety Advisor for advising him on technical plant matters. U'~N 4.4.11 Communicator The Communicator is responsible to the Admin-istration and support Coordinator for the following:
- 1. Making any required notifications and communications as directed
- 2. Notifying additional support personnel as directed.
4.5 Emergency Operations Facility (EOF) The EOF is activated for Site Area and General Emergencies. The EOF is the command post for the coordination of the emergency response actions by off-site organizations, the coordination of off-site radiological and environmental assessments, determining protective actions for the public, and management of recovery operations. 4.5.1 Emergency Oper'ations Facility (EOF) Coordinator l n-s_-
EP-110 Rev. 0.B Page 12 The Manager-Wayne Division (or his alternate, the Director-Customer and Marketing Services Wayne Division) is assigned as the EOF Coordinator and is responsible to the Emergency Officer for the following:
- 1. Coordinating and directing activities in EOF.
- 2. Notification of Government emergency response agencies.
- 3. Recommending protective actions to Government emergency response agencies.
4.5.2 Radiation Protection Coordinator The Senior Health Physicist (or his alternate, the Radiation Chemistry Engineer) is assigned as the Radiation Protection Coordinator and is responsible to the EOF Coordinator for the following:
- 1. Coordinating and directing off-site dose assessment activities.
- 2. Determining survey areas for Radiologica1 Emergency Teams.
- 3. Determining environmental cample media.
- 4. Evaluating results of off-site environmental surveys.
- 5. Advising the EOF Coordinator on protective actions to be taken.
- 6. Directing activities in the analysis laboratory.
- 7. Ensuring proper Health Physics records of the emergency are maintained.
- 8. Coordinating radiation protection for personnel in the EOF.
O l 1
O EP-110 Rev. 0.B Page 13 4 4.5.3 The Radiation Protection Communicator makes any required notifications and communications as directed by the Radiation Protection Coordinator. 4.5.4 Environmental Assessment Team The Environmental Assessment Team is responsible to the Radiation Protection Coordinator for the following:
- 1. Assessing meteorological conditions.
- 2. Performing dose assessment and projections. -
4.5.5 Security Liaison The Senior Administrator-Security (or his alternate, Nuclear Security Coordinator) is assigned as the Security Liaison and is Os responsible to the EOF Coordinator for the following: i
- 1. Coordinating access and egress of off-site personnel to owner - controlled areas.
- 2. Acting as security liaison for security personnel at the Michigan State Police l
Emergency Operations Center, the Joint 1 Public Information Center, and the TSC. l
- 3. Acting as liaison between security operations and the EOF Coordinator.
i
- 4. Establishing and maintaining a security l checkpoint at the entrance to the EOF.
4.5.6 Radiological Emergency Team Coordinator The Wayne Division Dispatcher is assigned as the Radiological Emergency Team Coordinator and is responsible to the Radiation Protection Coordinator for the following: l (G l 1
EP-110 Rev. 0.B Page 14
- 1. Coordinating efforts of the Off-Site Radiological Emergency Teams.
- 2. Assigning survey areas.
- 3. Reporting the results of off-site surveys to the Radiation Protection Coordinator.
4.5.7 Nuclear Operations Advisor The off-shift Nuclear Shift Supervisors are assigned as Nuclear Operations Advisors and are responsible to the EOF Coordinator for the following:
- 1. Providing updated information on the operational status of the plant.
- 2. Advising the EOF Coordinator on the status of plant operations.
4.5.8 Public Information Coordinator The Director-Public Information is assigned as the Public Information Coordinator and is responsible to the Emergency Officer for the following:
- 1. Coordinating public information with the Joint Public Information Team.
- 2. Liaison between the Emergency Officer and the Joint Public Information Team.
- 3. Liaison between EOF and near-site news media center.
4.5.9 EOF Administrator The Director-Administration (or his alternate the Supervisor-Planning) is assigned as the EOF Administrator and is responsible to the EOF Coordinator for the following:
- 1. Providing logistic support.
- 2. Providing documentation control and support.
E 1
\
EP-110 Rev. 0.B Page 15
- 3. Establishing and maintaining a long term record file for the emergency.
- 4. Supervising the establishment of the EOF.
- 5. Supervising the communicators, clerks, status board updaters, and secretaries ~
assigned to the EOF. 4.5.10 The Communicator The Communicator is responsible to the EOF Administrator for the following:
- 1. Making any required notifications and communications as directed.
- 2. Notifying additional support personnel as directed.
4.5.11 Laboratory Technicians O, 1. Analyzing samples collected by the Off-Site RET members.
- 2. Reporting the results of the sample analysis to the Radiation Protection Coordinator.
4.5.12 Liaison to the State
- 1. Coordinating and clarifying communica-tions between the EOF and the State on-scene EOC.
- 2. Apprising State Officials at the on-scene EOC of emergency conditions based on information provided by the Detroit Edison emergency organization.
4.6 Newport Warehouse The Newport Warehouse will be utilized as the assembly point for the Off-Site Radiological Emergency Team (Off-Site RET). All equipment required to support the Off-Site RET will be stored at the Newport Warehouse. An alternate assembly () point may be directed by the Emergency Director.
EP-110 Rev. 0.B Page 16 4.6.1 RET Supervisor A representative from Customer Field Services Group is assigned as the RET Supervisor and is responsible for the following:
- 1. Organizing the Off-Site RET members into teams.
- 2. Ensuring the teams are properly outfitted with the necessary tools and equipment.
- 3. Ensuring the teams establish communica-tions with the RET Coordinator.
- 4. Acting as a liaison between activities at the Newport Warehouse and the RET Coordinator.
- 5. Establishing a rotation schedule for the Off-Site RET.
4.6.2 RET Equipment Coordinator A representative of the Customer and Marketing Services Group is assigned as the RET Equipment Coordinator and is responsible to the RET Supervisor for the following:
- 1. Taking inventory of Off-Site RET kits before and after use.
- 2. Obtaining replacements for defective equipment and depleted supplies.
- 3. Maintaining the Off-Site RET equipment storage area in a neat and orderly fashion.
4.7 Detroit Edison Divisional Organization Emergency Headquarters. Detroit Edison corporate level personnel listed are available via the Divisional Organization Emergency Headquarters located in the corporate offices in Detroit. l l
EP-110 Rev. 0.B Page 17 4.7.1 Executive Vice President-Operations. The Executive Vice President-Operations is responsible for support from the corporate headquarters. 4.7.2 ~Vice President-Operations The Vice President-Operations is an alternate for Executive Vice President-Operations. 4.7.3 Vice President-Engineering and Construction The Vice President-Engineering and Construction is an alternate for Executive Vice President-Operations. 4.7.4 Assistant Vice President-Public Affiars. The Assistant Vice President-Public Affairs ensures coordination of public information releases. END I 1 i l l O l
EP-lll (^T Rev. 0.B \ . ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: . EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
RECOVERY ORGANIZATION RECORD OF APPROVAL AND CHANGES Submitted by - <<Eb, Supervisor of Radiological- Kgdncy_ Date Response Preparedness Approved by 43h Chairman - Liais 3C6mmittee Date
.~ -
Liaison . Revision Committee No. Submitted Date Approval Date ( 1 2 3 4 5 6 7 , s 8 O
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I i j- I l EP-lll l Rev. 0.B l l t i t i l i ' ENRICO FERMI ATOMIC POWER PLANT i ! UNIT NO. 2 i i j Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE I
Title:
RECOVERY ORGANIZATION 1 i { i i l C l I l E F w - = v m m- w w e w e-y,w- w-e,y_ y _ . w re-em+--v-r- -------w-
l i I i EP-lll Rev. 0.B RECOVERY ORGANIZATION TABLE OF CONTENTS Page l.0 Purpose............................................... 1
- 2.0 References............................................ 1 3.0 General Information................................... 1 i 4.0 Assignments and Responsibility........................ 1 i
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O EP-lll Rev. 0.B Page 1 1.0 Purpose To describe the organization and responsibilities of the Recoverv Organization. 2.0 References 2.1 Enrico Fermi Atomic Power Plant, Unit 2, Radiological Emergency Response Plan. 2.2 Organization and Responsibilities (EP-110). 3.0 General Information 3.1 In any Site Area Emergency or General Emergency, the immediate action is to limit the consequences of the incident in order to maximize protection for plant personnel and the general public. Once the immediate corrective and protective actions have established an effective control over the emergency, subsequent actions are part of the reentry and recovery j programs. All actions in this program will be planned and deliberate. 3.2 The Emergency Officer is responsible for determining
~
and declaring an emergency terminated and the plant ready to begin reentry and recovery. 3.3 The recovery plan must be flexible enough to meet the needs of the existing conditions. Detroit Edison and cognizant government officials will, together, draw up l a general plan for reentry and recovery. l 4.0 Assignment and Responsibility 4.1 Recovery Manager The Vice President-Nuclear Operations (or his alter-nate, the Assistant Vice President and Manager - Nuclear Operations) is assigned as the Recovery Manager and is responsible for the following: 4.1.1 Determining and declaring an emergency stable and the plant ready to begin reentry and recovery. 4.1.2 Authorizing funds and the utilization of necessary personnel and equipment to accomplish n) ( the recovery operation. I
l l EP-lll Rev. 0.B Page 2 4.1.3 Notifying off-site authorities, in a timely manner, that a recovery operation will be initiated and indicate any expected or potential impact off-site. 4.1.4 Providing additional off-site notification whenever recovery operations have potential off-site effects. 4.2 Emergency Director The Superintendent-Nuclear Production (or his alter-nate, the Assistant Superintendent) is assigned as the Emergency Director and is responsible to the Recovery Manager for the following: 4.2.1 Authorizing the start of reentry and recovery activities. 4.2.2 Returning to normal operations when approved by the NRC. 4.2.3 Preparing an analysis of the circumstances leading up to and resulting from the emergency, together with recommendations to prevent a recurrence. 4.2.4 Maintaining the plant during the recovery operation. 4.2.5 Developing implementing procedures to support recovery efforts. 4.2.6 Training plant personnel in recovery-related operating and maintenance procedures. 4.2.7 Implementing recovery plans and schedules. 4.3 Emergency Centers Coordinator The Manager - Wayne Division (or his alternate, the Regional Representative-Community Governmental Affairs) is assigned as the Emergency Centers Coordinator and is responsible to the Recovery Manager for providing information to all emergency centers and supervising the performance of dose projections. 4.4 Radiological Protection and Waste Management Coordinator i i
i
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EP-lll Rev. 0.B Page 3 The Radiation Protection Chemical Engineer (or his alternate) is assigned as the Radiological Protection and Waste Management Coordinator and is responsible to the Recovery Manager for the following: 4.4.1 Developing post-accident plans and procedures for sampling contaminated solids, liquids, and gases. 4.4.2 Developing concepts for modification and designs necessary for waste processing. 4.4.3 Supporting off-site sampling programs, dose assessments, dose management, and radiation protection. 4.5 Technical Support and Engineering Coordinator The General Supervisor-Nuclear Safety and Plant Engineering (or his alternate, the Supervisor-Safety and Performance Engineering) is assigned as the ID Technical Support and Engineering Coordinator and is
\s # responsible to the Recovery Manager for the following:
4.5.1 Providing experienced licensed personnel to support plant operations. 4.5.2 Developing post-accident operating procedures necessary to achieve a safe reactor shutdown. 4.5.3 Analyzing and developing solutions for instrumenti.*8.on difficulties and the functions controlled by those instruments. 4.5.4 Analyzing situations and developing solutions necessary to achieve and maintain core stability. 4.5.5 Analyzing and developing input pertinent to plant licensing issues. 4.6 Design and Construction Support Management Coordinator The Director-Nuclear Plant Modification (or his alternate) is assigned as the Design and Construction Support Management Coordinator and is responsible to Recovery Manager for coordinating the design and 1 construction activities in support of recovery actions.
EP-lll Rev. 0.B Page 4 4.7 Technical Liaison and Advisory Support Coordinator The Director-Nuclear Engineering (or his alternate, the General Director-Generation Engineering) is assigned as the Technical Liaison and Advisory Support Coordinator and is responsible to the Recover,y Manager for advising him on technical plant matters. NOTE: This Advisory Support Group is composed of technical and managerial personnel who have sufficient authority to commit to the recovery effort the resources of the organization they represent. 4.8 Recovery Planning and Scheduling Coordinator The Director-Outage Management (or his alternate) is assigned as the Recovery Planning and Scheduling Coordinator and is responsible for the following: 4.8.1 Establishing schedules and priorities which ensure an orderly and progressive work flow. 4.8.2 Controlling and expediting corporate, vendor contract, and governmental commitments. 4.9 Administration and Logistic Support Coordinator The Manager-Materials (or his alternate, the Manager-General Services) is assigned as the Administration and Logistic Support Coordinator and is responsible to the Recovery Manager for providing administrative logistics and communications support for the recovery operation. He is also responsible for developing and implementing a program of long range recordkeeping for all recovery operations. This record file shall be maintained as a legal record of the recovery. It shall as a minimum, contain an overall chronological log of all events and actions taken during the recovery, all Recovery Plan Implementing Procedures, all correspondence relating to the recovery operations, and the minutes of all meetings held on recovery operations. 4.10 Independent Review and Audit Group (IRAG) The members of the IRAG will be assigned in accordance with established corporate / site administrative procedures. The responsibility of the IRAG is to
EP-lll Rev. 0.B Page 5 oversee the activities of the Recovery Organization to ensure all Nuclear Safety aspects of _he recovery operations are satisfied. 4.11 Public Relations Coordinator The Assistant Vice-President - Public Affairs (or his alternate, the Director-Public Information) is assigned as the Public Relations Coordinator and is responsible to the Executive Vice-President-Operations for the dissemination of information concerning the emergency and recovery operations. 4.12 The Quality Assurance Coordinator The Quality Assurance Coordinator is responsible for ensuring.that all quality assurance procedures are properly utilized for all aspects of the recovery operation. r a END i O
EP-201-1 O Rev. 0.B ENRICO, FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
ON-SITE RADIOLOGICAL EMERGENCY TEAM: ACTIVATION RECORD OF APPROVAL AND CHANGES Submitted by 'eb Supervisor of Radiologic 1 TJfergency Date Response Preparedness , Approved by Chairman - Liaisch Committee h Date Liaison O, ' Revision Committee No. Submitted Date Approval Date 1 , 2 3 _ 4 5 6 { 7 8 l n
l l l EP-201-1 Rev. 0.B , i 1 J l ENRICO FERMI ATOMIC POWER PLANT : UNIT NO. 2
- i Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
ON-SITE RADIOLOGICAL EMERGENCY TEAM: ACTIVATION t < l [ i I 4 i i ( i t l a
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l O EP-201-1 Rev. 0.B The following is a list of "laters" contained in this procedure. Section Page Attachment 2 O l ( O
1 _. EP-201-1 4 Rev. 0.B { l ON-SITE RADIOLOGICAL EMERGENCY TEAM - ACTIVATION TABLE OF CONTENTS Page 1.0 Purpose ................................................l 2.0 References ............................................ 1 4 i ) 3.0 Entry Conditions .......................................l
- . 4.0 General Information ................................... 1
, 5.0 Immediate Actions ..................................... 3 1
i Attachments l+ List of Emergency Equipment ...................... Attachment 1 List of Equipment Storage Locations .............. Attachment 2 i t b 'l i 1 1 l
i (
) EP-201-1 Rev. 0.B Page 1 1.0 Purpose To prescribe the steps for activation of the On-Site Radiological Emergency Team (On-Site RET).
2.0 References 2.1 Enrico Fermi Atomic Power Plant Unit 2 Radiological Emergency Response Plan, Section B (On-Site Emergency Organization), Section I (Accident Assessment), Section J (Protective Response), and Section K (Radiological Exposure Control) . 2.2 On-Site Radiological Emergency Team: Function of the On-Site Radiological Emergency Team (EP-201-2). l 3.0 Entry Conditions The On-Site RET shall be activated by the Emergency i Director in the event of an incident with radiological consequences or the potential for radiological
- O consequences.
. 4.0 General Information ! 4.1 The on-shift Health Physics Technician or his alternate, the on-shift Radio-Chemistry Technician, j is the On-Site RET Leader. NOTE: If the Personnel Monitoring Team is activated simultaneously, and only one Health Physics Technician is available, the Emergency Director will specify the priority of actions for the on-shift Health Physics Technician. (If the TSC is activated, the Radiation Protection Advisor will perform this function.) This will preclude the on-shift Health Physics Technician from being expected to be in two places at once. Under these circumstances, off-shift Health Physics personnel may be activated as discussed in Step 5.3.3. 4.2 When the Technical Support Center (TSC) has been activated the On-Site RET Leader shall report to the Emergency Director through the Radiation Protection Advisor. O
.- .- _.._ ., _ ._,____ ,___ ,.m.. _ _ _ - . _ _ . . . . _ , . _ _ _ _ _ _ _ , . .. _ ._.__,_...___-____._,.-- -., - ,- .
EP-201-1 Rev. 0.B Page 2 5.0 Immediate Actions 5.1 When activated the On-Site RET Leader shall: 5.1.1 Immediately contact the Emergency Director and acknowledge the order to activate the Team. Verify the Team assembly location with the Emergency Director, if not already known. 5.1.2 Proceed to the assembly area designated by the Emergency Director. 5.2 When activated, the On-Site RET members report to the OSC or other location designated by the RET Leader. 5.3 When the Team members are assembled the On-Site RET Leader shall: 5.3.1 Contact the Emergency Director and report that the On-Site RET is activated. 5.3.2 Determine the status of the emergency from the Emergency Director, specifically with regard h to the following (if known):
- 1. Suspected cause of the emergency situation.
- 2. Areas with an indication of abnormally high radiation.
- 3. Areas with an indication of abnormally high airborne radioactive contamination.
- 4. Releases or potential releases of radio-activity inside the plant or to the environment.
- 5. Location and extent of fire and/or damage and severity of radiological hazards.
- 6. Areas with other abnormal personnel hazards.
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) EP-201-1 Rev. 0.B Page 3
- 7. If other Emergency Teams are activated.
- 8. Applicable plant lineups and corrective actions taken by the Emergency Director.
5.3.3 Determine if off-shift Health Physics personnel or off-site support is necessary. If so, request support from the OSC Coordinator. If the OSC Coordinator is not activated, the request shall be made to the Emergency Director. 5.3.4 Brief the team members on the status of the emergency. 5.4 If the On-Site RET is only required at one location (for example a fire involving radioactive material) the On-Site RET Leader shall: i 5.4.1 Direct Team members to obtain necessary emergency equipment. Items which are O available are listed in Attachment 1 and are found in storage locations listed in Attach-ment 2. If items are missing or additional equipment is necessary, contact the OSC Coordinator and request additional equip-ment. If the OSC Coordinator is not activated, contact the Emergency Director. 5.4.2 Proceed to the location with the other team
- members and supervise On-Site RET activities, i
j 5.4.3 At the scene, report to the appropriate team leader, as specified by OSC Coordinator or Emergency Director. 5.5 If the emergency is such that members of the Team are required in several different areas, the On-Site RET Leader shall: 5.5.1 Determine what Team efforts are required at the various locations. 5.5.2 Assign Scene Leaders, with sufficient per-sonnel to carry out the RET function at each location. l O l
EP-201-1 Rev. 0.B Page 4 5.5.3 Direct RET Scene Leaders to perform the following:
- 1. Obtain necessary emergency equipment (including radios). Items which are available are listed in Attachment 1 and are found in storage locations listed in Attachment 2.
- 2. Proceed to their assigned locations.
- 3. Supervise On-Site RET activities at each location.
- 4. At the scene, report to the appropriate team leader, as specified by OSC Coordinator or Emergency Director.
- 5. Periodically report back to the RET Leader.
5.5.4 The RET Leader remains at the OSC or proceeds with one of the On-Site RET groups. The RET Leader's whereabouts must be made known to the RET Scene Leaders, Emergency Director, and OSC Coordinator. 5.6 The On-Site RET Leader shall: 5.6.1 Periodically report to the Emergency Director. 5.6.2 If Scene Leaders require additional equipment, contact the OSC Coordinator and request additional equipment. If the OSC Coordinator is not available, contact the Emergency Director. 9
l l 1 ( EP-201-1 Rev. 0.B l HEALTH PHYSICS EMERGENCY EQUIPMENT - OPERATIONS SUPPORT CENTER ITEM QUANTITY
- 1. Set of Emergency Plan Implementing 1 Procedures
- 2. Scott air paks 15
- a. Extra air bottles 30
- 3. Eberline RM14 (frisker) or Ludlum 177 6 (frisker)
- 4. Smears 60
- 5. Plastic bags 60
- 6. Dose rate meter (RO-2) 6
( 7. Dosimeter charger with extra batteries 2
- 8. High-range dosimeters 20
- 9. Air sampler and filters / cartridges 5
- a. Extra air sampler filter heads 15
- b. Particulate filters 200
- c. Silver zeolite cartridges 50
,- 10. Portable area radiation monitor 1
- 11. Survey maps 200
- 12. Log books 10
- 13. Clip boards 10 l
- 14. Boxes of black pens 12 1
- 15. Boxes of grease pencilt 12 Attachment 1 Page 1 of 3
EP-201-1 Rev. 0.B ITEM QUANTITY
- 16. 150 foot rolls of barrier rope 10
- 17. Caution signs and assorted inserts 20
- 18. MSA SCBA with 10 extra bottles 5
- 19. Full sets of protective clothing:
- a. Coveralls 30 prs.
- b. Cloth hoods 30
- c. Plastic shoe covers 30
- d. Rubber shoe covers 30 pr.
- e. Cotton glove liners 30 pr.
- f. Rubber gloves 30 pr.
- g. Surgeons' caps 30
- 20. Partial sets of protective clothing:
- a. Pairs of gloves 50
- b. Pairs of shoe covers 100
- 21. Rolls of 2" masking tape 50
- 22. Boxes of smears 40
- 23. Step off pads 10
- 24. Large plastic bags 50
- 25. Full face respirators with extra filters 10 Attachluent 1 Page 2 of 3 O
EP-201-1 Rev. 0.B ITEM QUANTITY
- 26. Flashlights 5
- a. Extra batteries 10
- 27. Potassium Iodide 5 bottles
- 28. 50 foot extension cords 2 Attachment 1 Page 3 of 3 mlu' u muni
- _ - - ~ . . - -
i j' . , i I 1 ! i i EP-201-1 Rev. 0.B-t 1 ! EMERGENCY EQUIPMENT STORAGE LOCATIONS l i l\ 1-l t b l Y !, (later) J i i
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I. I I j i - 1 i 1 ! l L i i f I i i;
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l END I Attachment 2 Page 1 of 1 !9 i I l I l 1 , a+
t EP-201-2 Rev. 0.B (w) ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
ON-SITE RADIOLOGICAL EMERGENCY TEAM: FUNCTIONS RECORD OF APPROVAL AND CHA ES Submitted by (*( Supervisor of Radiologi l\Ehergency Date ResponsePreparedness,q Approved by Chairman - LiaisoK Committee Date f Liaison Revision Committee No. Submitted Date Approval Date 1 2 l 3 l 4 5 6 7 8 l n v \ l l .
f , EP-201-2 ; Rev. 0.B i 1 t ENRICO FERMI ATOMIC POWER PLANT . I UNIT NO. 2 i Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE l i
Title:
ON-SITE RADIOLOGICAL EMERGENCY TEAM: FUNCTIONS ' i 't O 1 1 i ! l i i i l { t ! t i I 1 \ l l l I i l i o 6 I
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EP-201-2 Rev. 0.B ON-SITE RADIOLOGICAL EMERGENCY TEAM: FUNCTION OF THE ON-SITE RADIOLOGICAL EMERGENCY TEAM TABLE OF CONTENTS Page 1.0 Purpose ............................................... 1 2.0 References ............................................ 1 3.0 Entry Conditions ...................................... 1 4.0 General Information ................................... 2
; 5.0 Immediate Actions ..................................... 2 5.4 Fire Involving Radiological Hazards .............. 3 5.5 Significant Radioactive Spill .................... 5 5.6 Significant Release of Radioactive Liquid ........ 6 5.7 Gaseous Radioactive Release ...................... 8 6.0 Follow-up Actions .................................... 10 t
i I I
_/ EP-201-2 Rev. 0.B Page 1 1.0 Purpose To describe the function of the On-Site Radiological Emergency Team (On-Site RET) in the event of an incident involving radiological hazards. 2.0 References 2.1 Enrico Fermi Atomic Power Plant Unit 2 Radiological Emergency Response Plan, Section B (On-Site Emergency Organization), Section I (Accident Assessment), Section J (Protective Response), and Section K (Radiological Exposure Control) . 2.2 On-Site Radiological Emergency Team: Activation (EP-201-1). 3.0 Entry Conditions The On-Site RET is be activated at the discretion of the O' ' . Nuclear Shift Supervisor or Emergency Director whenever a radiological incident is known or threatens to occur. 4.0 General Information 4.1 The responsibiliities of the On-Site RET include the following:
- 1. Conducting radiation, contamination and airborne radioactivity surveys.
- 2. Assisting the Fire Brigade and Damage and Rescue Team Leaders in briefing personnel concerning expected radiological hazards.
- 3. Assisting the Fire Brigade and Damage and Rescue Team Leaders by computing stay times.
Instructing personnel concerning areas they should avoid so as to minimize their radiation contamination and to limit contamination spread.
- 4. Ensuring that personnel have proper protective clothing and respiratory equipment.
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EP-201-2 Rev. 0.B Page 2
- 5. Ensuring that personnel have issued personnel dosimeters and that dosimeters are zeroed prior to use.
- 6. Establishing controlled areas to limit the spread of contamination. .
- 7. Supervise the clean up of contaminated areas.
- 8. Supervise the decontamination of tools and equipment, as required.
- 9. Performing off-site surveys prior to the activation of the Off-Site RET.
4.2 The routine radiation exposure limits of Health Physics Procedure 61.000.05 (Radiation, Contamina-tion, and Airborne Guides and Limits) shall not be exceeded unless specifically authorized by Health Physics personnel. The 10CFR20 limits shall not be exceeded unleds specifically authorized by the Emergency Director. Emergency exposure limits are delineated in Procedure 69.000.15 (Emergency Exposure Limits). 4.3 Contaminated equipment shall not be removed from a controlled area until released by Health Physics Personnel. 4.4 If the TSC is activated, the On-Site Ret Leader will report to the Emergency Director through the Radiation Protection Advisor. 5.0 Immediate Actions 5.1 The On-Site RET Leader shall activate the On-Site RET in accordance with EP-201-1 (On-Site RET: Activation). 5.2 The designated On-Site RET members shall: 5.2.1 Obtain necessary equipment as directed by the On-Site RET Leader. 5.2.2 Proceed to the scene and report to the appropriate Emergency Team Leader. O
)
EP-201-2 Rev. 0.B Page 3 NOTE: The Fire Brigade Leader is responsible for coordinating the actions of all Emergency Response Teams reporting to the scene of a fire. If the Fire Brigade is not activated, the Damage and Rescue Team Leader will be in charge at the scene. The Frenchtown Fire Depar-tment may be activated to augment the Fire Brigade. Fire Department personnel receive only limited training, and must be closely supervised to minimize radiological problems. 5.2.3 In the event of a fire involving radiological hazards, efforts to control spreading radio-active contamination shall not impede steps in controlling a serious fire or reducing damage. This is a judgment which must be made by the Team Leader depending on the specific , situation. 5.3 If an emergency involves contaminated / injured personnel, the actions of Health Physics Procedure 69.000.10 (Radiological / Medical Emergency) shall be followed. 5.4 General i 5.4.1 If possible, perform a quick general radiation survey. 5.4.2 If the area is expected to have significant . airborne contamination, recommend that Scott [ Air Paks be used. As soon as time permits, i determine the actual airborne contamination levels. Less restrictive respiratory equip-ment can then be recommended, if permissible. 5.4.3 Perform a quick contamination survey. If l necessary, establish a controlled area. 5.4.4 Assist in briefing personnel concerning radiological hazards. 1O
I I l l EP-201-2 Rev. 0.B Page 4 5.4.5 Compute stay times and instruct personnel concerning areas they should avoid so as to minimize their radiation exposure and contamination. CAUTION: The routine radiation exposure limits of Health Physics Procedure 61.000.05 (Radiation, Contamination, and Airborne Guides and Limits) shall not be exceeded unless specifically authorized by Health Physics personnel. The 10CFR20 limits shall not be exceeded unless specifically authorized by the Emergency Director. Emergency exposure limits are deline-ated in Procedure 69.000.15 (Emergency Exposure Limits). 5.4.6 Ensure that personnel have proper protective clothing and respiratory equipment. 5.4.7 Ensure that personnel are issued personnel dosimeters and that dosimeters are zerced prior to use. 5.4.8 Assist in supervising the actions of personnel so as to minimize radiation exposure. 5.4.9 Assist in supervising the actions of personnel so as to minimize the spread of contamination, as necessary. Recommended steps include the following:
- 1. Only essential equipment should be brought into contaminated areas.
- 2. All equipment used in contaminated areas should be treated as potentially contaminated. Equipment should not be removed from controlled areas until released by Health Physics personnel.
- 3. Route fire hoses so as to avoid areas of loose surface contamination or spilled radioactive materials.
O
\/ EP-201-2 Rev. 0.B Page 5
- 4. Avoid dragging fire hoses and equipment through areas of loose surface contamination or spilled radioactive materials.
- 5. Avoid using a direct stream from fire hoses, if possible, and avoid hitting loose surface contamination or other radioactive materials with a direct stream. Use spray or fog nozzles where possible.
- 6. Avoid areas of higher contamination levels or areas where more highly radioactive materials are located, in favor of low-level contamination areas or areas where low-level radioactive materials are located.
() Treat all water in controlled areas as 7. potentially contaminated. 5.5 In the event of a significant radioactive spill, the RET Scene Leader shall carry out the following: CAUTION: Only qualified personnel shall operate any valves, switches, or other equipment necessary to accomplish the prescribed actions. 5.5.1 Stop the source of the spill, if not already accomplished. 5.5.2 Isolate the area encompassed by the spill.
- 1. Set up boundaries to identify the spill area.
- 2. Rope off the affected area if possible.
5.5.3 Minimize exposure to personnel. l 1. Remove any potentially contaminated personnel from the spill area. V
EP-201-2 Rev. 0.B Page 6
- 2. Set up a controlled access area in accordan::e with Health physics Procedure 61.000.35 (Posting for Radiological Control) to minimize radiation exposure or contamination.
5.5.4 Secure any ventilation blowing on the area to minimize airtorne radioactivity. 5.5.5 Determine rad iation contamination, and airborne radioactive contamination leve:2. 5.6 In the event of a significant release of radioactive liquid to the environment the RET Leader shall carry out the following: 5.6.1 Direct team members to obtain water samples if the liquid release has entered, or potentially entered, the waters of Lake Erie.
- 1. Fermi I potable water intake.
- 2. City of Monroe water intake.
5.6.2 Instruct Team members on the following:
- 1. Obtaining necessary transportat' ion for access to all survey areas.
- 2. Obtaining necessary instrumentation and equipment for surveys.
- 3. Obtaining necessary radios for l communication. .
- 4. Surveys and samples to be obtained.
5.7 In the event of a gaseous radioactive release to the environment the RET Leader shall carry out the following: , s 5.7.1 Instruct Team members on the following: l l 1. Obtaining necessary transportation for access to all survey areas. 1
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EP-201-2 s Rev. 0.B Page 7
- 2. Obtaining necessary instrumentation and equipment for surveys.
- 3. Obtaining necessary radios for communications.
- 4. Surveys and samples to be obtained.
- 5. Making periodic reports to the Team Leader.
- 6. Maintaining records of all samples taken.
5.7.2 Team members shall perform the following:
- 1. Change effluent filters and cartridges and obtain effluent gas samples.
6.0 Follow-up Actions () 6.1 The On-Site RET Leader shall: 6.1.1 Maintain communications with all On-Site RET Scene Leaders. 6.1.2 Keep the Radiation Protection Advisor informed of the status of the emergency, RET efforts, and any radiological consequences of the incident, especially with regard to the following:
- 1. Areas and occurrences with significant radiological conditions.
- 2. Contaminated personnel and the status of l any decontamination efforts.
l~ - . s 3. Sample and survey results.
- 4. Establishment of controlled areas.
- 5. Recommendations for clean-uo of contam-inated areas and removal of potentially contaminated water. ,
a O
EP-201-2 Rev. 0.B Page 8 6.2 The RET Scene Leader shall: 6.2.1 Keep the On-Site RET Leader informed of the status of the emergency and RET efforts at the scene. 6.2.2 Carry out instructions of RET Leader. 6.2.3 Supervise the decontamination of emergency equipment and areas. 6.2.4 At the conclusion of On-Site RET efforts, direct an inventory of On-Site RET emergency equipment used at the scene.
- 1. Any missing equipment shall be recovered or replaced.
- 2. Any damaged equipment shall be repaired / replaced and reported to the General Supervisor - Health Physics.
- 3. All equipment shall be checked for proper operability, serviced, or repaired as necessary (batteries replaced, filters replaced, etc.) and restowed in proper storage locations.
END
EP-202-1 Rev. 0.B ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDUP.E
Title:
PERSONNEL MONITORING TEAM: ACTIVATION RECORD OF APPROVAL AND CHA S Submitted by .r Supervisor of Radiologic Endergency Date Response Preparedness Approved by n Chairman - Liaison y mmittee Date
. Liaison Revision Committee O' No. Submitted Date Approval Date 1
2 3 4 5 6 7 8 O
O EP-202-1 Rev. 0.B ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
PERSONNEL MONITORING TEAM: ACTIVATION O l O
O EP-202-1 Rev. 0.B l The following is a list of "laters" contained in this procedure. Section Page Attachment 2 O
; O
i EP-202-1 Rev. 0.B l PERSONNEL MONITORING TEAM: ACTIVATION TABLE OF CONTENTS Page 1.0 Purpose ................................................l 2.0 References ............................................ 1 l l 3.0 Entry Conditions ...................................... 1 1 4.0 General Information ................................... 1 5.0 Immediate Actions ..................................... 2 , Attachments, List of Emergency Equipment ...................... Attachment 1 List of Emergency Equipment Storage Locations ....Atta'chment 2 l 6
EP-202-1 Rev. 0.B Page 1 1.0 Purpose To prescribe the steps for activating the Personnel Monitoring Team (PMT). 2.0 References 2.1 Enrico Fermi Atomic Power Plant Unit 2 Radiological Emergency Response Plan, Section B (On-Site Emergency Organization), Section I (Accident Assessment) , Section J (Protective Response), Section K (Radiological Exposure Control), and Section L (Medical Support) . 2.2 Personnel Monitoring Team: Functions (EP-202-2). 3.0 Entry Conditions The Personnel Monitoring Team shall be activated at the discretion of the Nuclear Shift Supervisor / Emergency
/~N Director in the event of:
- 1. A Plant Area Evacuation.
- 2. A Protected Area Evacuation.
- 3. A Site Area Evacuation.
- 4. A Visitors Center Evacuation.
4.0 General Information 4.1 The on-shift Health Physics Technician or his alternate, the on-shift Radio-Chemistry Technician, is designated as the Personnel Monitoring Team Leader. NOTE: If the On-Site Radiological Emergency Team is activated simultaneously, the Emergency Director will specify the priority of actions for the on-shift Health Physics Technician. (If the TSC is activated, the Radiation Protection Advisor will perform this func-tion). This will preclude the on-shift Health Physics Technician from being expected to be in two places at once. Under these circum-stances, off-shift Health Physics personnel will be activated as discussed in step 5.3.3. O
EP-202-1 Rev. 0.B Page 2 4.3 If the TSC is activated, the PMT Leader shall report to the Emergency Director through the Radiation Protection Advisor. 5.0 Immediate Actions 5.1 When activated, the PMT Leader shall: 5.1.1 Immediately contact the Emergency Director and acknowledge the order to activate the Team. Verify the Team assembly location with the Emergency Director. 5.1.2 Proceed to the location designated by the Emergency Director. 5.2 When activated, the PMT shall report to the assembly area (s) or the scene as directed by the PMT Leader. 5.3 When the Team members are assembled the PMT Leader shall: 5.3.1 Contact the Emergency Director and report that O the Personnel Monitoring Team is activated. 5.3.2 Determine the status of the emergency from the Emergency Director, specifically with regard to the following (if known):
- 1. Suspected radiological conseq'uences of the emergency situation.
- 2. Location of the evacuation assembly area (s).
- 3. Number and locations of personnel with contamination or excessive radiation exposure.
5.3.3 Determine if off-shift Personnel Monitoring Team personnel or off-site support is necessary and request support from the OSC Coordinator. If the OSC Coordinator is not activated, the request shall be made to the Emergency Director. O
EP-202-1 Rev. 0.B Page 3 5.3.4 Brief Team members on the status of the emergency as determined in step 5.3.2. 5.4 If the Personnel Monitoring Team is only required at one evacuation assembly area the PMT Leader shall: 5.4.1 Direct Team members to obtain necessary emergency equipment. Items which are
. available are listed in Attachment 1 and are found in storage locations listed in Attachment 2. If items are missing or additional equipment is necessary, contact the OSC Coordinator and request additional equipment. If the OSC Coordinator is not activated, contact the Emergency Director.
5.4.2 Proceed to the location with the other members-and supervise the activities. Report to the appropriate team leader. g 5.5 If the emergency is such that members of the team are required at several assembly areas, the PMT Leader shall: 5.5.- Determine what Team efforts are required at the various locations. 5.5.2 Assign PMT Scene Leaders, each with sufficient personnel to carry out the PMT functions at each location. NOTE: The PMT Leader can assume the role of PMT Scene Leader at one of the locations. He still retains responsibility for overall control of PMT efforts. However, such control may best be exercised from the OSC, using radio communications. 5.5.3 Direct Scene Leaders to perform the following:
- 1. Obtain necessary emergency equipment.
Items which are available are listed in Attachment 1 and are found in storage locations listed in Attachment 2.
- 2. Proceed to their assigned assembly areas.
O
- , - - ~ _
EP-202-1 Rev. 0.B Page 4
- 3. Supervise On-Site PMT activities at each location.
- 4. At the scene, report to the appropriate team leader.
- 5. Periodically report back to the PMT Leader.
5.6 The PMT Scene Leaders shall: 5.6.1 Obtain necessary equipment. If items are missing or additional equipment is necessary, contact the PMT Leader. 5.6.2 Proceed to assigned assembly area. 5.6.3 Carry out the steps of EP 202-2 (Personnel Monitoring Team: Functions). 5.7 The PMT Leader shall: 5.7.1 Periodically report status to the RET Leader. 5.7.2 If Scene Leaders require additional equipment, contact the OSC Coordinator and request additional equipment. If the OSC Coordinator is not activated, contact the RET Leader. O
i t EP-202-1 Rev. 0.B HEALTH PHYSICS EMERGENCY EQUIPMENT - PMT i QUANTITY I ITEM REQUIRED
- 1. FRISKER (Eberline RM-14 or Ludlum 177) and pancake probe (3). 2
- 2. Dose rate meter (E520 or RO2) 1
; 3. Box of smears 6
- 4. Envelopes for smears 100 1 5. KI 5
. 6. Paper coveralls (sets) 10
- 7. Shoe Covers 100 pair l
i O ( l Attachment 1 Page 1 of 1 0
EP-202-1 Rev. 0.B EMERGENCY EQUIPMENT STORAGE LOCATIONS (later) END Attachment 2 Page 1 of 1
EP-202-2 Rev. 0.B [%_J'l ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
PERSONNEL MONITORING TEAM: FUNCTIONS RECORD OF APPROVAL AND CHANGES Submitted by ( Supervisor of Ra gical Emergency Date Response Prepar. Approved by Chairman - Liaison Committee Date Liaison (T Revision Committee '\_) No. Submitted Date Approval Date 1 2 3 4 _ 5 6 7 8 r'd
i e 4 i j l l i
- EP-202-2
) Rev. 0.B i t i i i i i i l ENRICO FERMI ATOMIC POWER PLANT 1 j UNIT NO. 2 i Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE l l
Title:
PERSONNEL MONITORING TEAM: FUNCTIONS l r b r t V
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EP-202-2 Rev. 0.B PERSONNEL MONITORING TEAM - FUNCTIONS - TABLE OF CONTENTS 2 Page 1.0 Purpose ............................................... 1 t l 2.0 References ............................................ 1 3.0 Entry Conditions ...................................... 1 4.0 General Information ................................... 2 5.0 Immediate Action: ..................................... 2 5.3 Plant Area or Protected Area Evacuation .......... 3
- 5.4 Site Area Evacuation ............................. 4 5.5 Visitor's Center Evacuation ...................... 5 l
6.0 Follow-up Actions ..................................... 7 l Attachments
'~'
Record Form: Disposition of Evacuees............ Attachment 1 Log: Disposition of Evacuees.................... Attachment 2 l l l l l A i l
O - EP-202-2 Rev. 0.B Page 1 1.0 Purpose To prescribe the functions of the Personnel Monitoring Team (PMT). 2.0 References 2.1 Enrico Fermi Atomic Power Plant Unit 2 Radiological Emergency Response Plan, Section B (On-Site Emergency Organization), Section I (Accident Assessment), Section J (Protective Response), Section K (Radiological Exposure Control) , and Section L (Medical Support) . 2.2 Personnel Monitoring Team: Activation (EP-202-1) 2.3 Radiological / Medical Emergency (69.000.10) . 3.0 Entry Conditions The PMT shall be activated at the discretion of the i () Emergency Director in the event of:
- 1. Plant Area evacuation.
- 2. Protected Area evacuation.
- 3. Site Area evacuation.
- 4. Visitor's Center evacuation.
4.0 General Information 4.1 The responsibilities of the PMT in the event of an incident involving radiological hazards are the following: 4.1.1 Surveying personnel for contamination. 4.1.2 Supervising the decontamination of personnel. 4.1.3 Assisting the On-Site RET, if necessary, in the performance of its duties. 4.1.4 Assisting the Security Force, as necessary, in j accounting for personnel following an evacuation. l l
EP-202-2 Rev. 0.B Page 2 4.2 If possible, contaminated personnel without serious injuries who require of f-site medical assistance, shall be decontaminated prior to their removal from the site. If it is not possible to decontaminate the personnel without aggravating the injury or delaying proper medical attention, PMT members shall only take sufficient steps to minimize the spread of the radioactive contamination without delaying medical attention. 5.0 Immediate Actions 5.1 The PMT Leader shall activate the PMT in accordance with EP-201-1 (Personnel Monitoring Team: Activation). 5.2 The designated PMT members shall: 5.2.1 Obtain necessary equipment as directed by the PMT Leader. 5.2.2 Proceed to the assembly area or the scene as directed by the Team Leader. 5.3 In the event of a Plant Area or Protected Area evacuation, upon arrival at the assembly area the PMT Leader shall: 5.3.1 Survey the assembly area. If radiation levels are greater than 10 mR/hr or if airborne contam-ination levels are greater than 10 times the permissible limit, notify the RET Leader and recommend an alternate assembly area. 5.3.2 Instruct the evacuees to remain at the assembly area until released by the Personnel Monitoring Team. 5.3.3 Determine the extent of personnel contamination. 5.3.4 In the event of personnel with injuries, radioactive contamination or excessive radiation exposure carry out the appropriate steps in Procedure 69.000.10 (Rad iological/ Medical Emergency). O i
EP-202-2 Rev. 0.B Page 3 5.3.5 Report to the RET Leader the status of any personnel suffering from injuries, radioactive contamination, or excessive radiation exposure. 5.3.6 Assist Security to record names, social security numbers, addresses for non-employees, badge numbers for employees, and disposition for all personnel on log sheets provided in Attachment
- 2. This log will be used to account for all evacuees.
5.3.7. For all personnel who are contaminated, injured, or suffering from excessive radiation exposure, complete " Disposition of Evacuee" form shown in Attachment 1. 5.4 In the event of a Site Area evacuation, upon arrival at the assembly point, the PMT leader shall: w 5.4.1 Assign Scene Leaders and direct members, with the necessary equipment to the Security Building, warehouse 19, the site assembly area at the Newport Warehouse, or any designated alternate assembly area. 5.4.2 Instruct Scene Leaders assigned to the Security Building and Warehouse 19 to perform the following:
- 1. If any Protected Area evacuees are contaminated:
- a. Issue these individuals " clean" anti-contamination clothing.
- b. Obtain their names and badge numbers,
- c. Contact the Scene Leader at the assembly area, inform him of the situation, and relay the evacuees' names and badge numbers.
O
EP-202-2 Rev. 0.B Page 4 5.4.3 Instruct Leader's assigned to the assembly area to perform the following:
- 1. Instruct evacuees to remain at the off-site assembly areas until approval for their release is obtained from the Personnel Monitoring Team.
- 2. In the event there are personnel with injuries, radioactive contamination or excessive radiation exposure carry out the appropriate steps in Procedure 69.000.10 (Radiological / Medical Emergency).
- 3. Record names, social security numbers, company affiliation, home phone numbers, and disposition for all personnel on log eheets provided in Attachment 2. This log will also be used to account for all evacuees.
- 4. For all personnel who are contaminated, complete a " Disposition of Evacuee" form shown in Attachment 1.
- 5. Keep the Emergency Director informed of the status of evacuees at each assembly area especially with regard to:
- 1. Number of evacuees.
- 2. Contaminated personnel.
- 3. Injured personnel suffering from excessive exposure to radiation or toxic chemicals, or contaminated.
- 4. Missing personnel.
5.5 In the event of an evacuation of the Visitors Center, the PMT Leader shall: 5.5.1 If the evacuation of the visitors Center is in conjunction with a Site Area Evacuation:
- 1. Carry out appropriate steps of Section 5.4.
O
EP-202-2 Rev. 0.B Page 5
- 2. Direct personnel to monitor the visitors at the assembly area. Visitors should receive j careful attention to ensure that they are properly monitored and that applicable records are thorough and complete.
5.5.2 If only the visitors Center is evacuated and monitoring ijt required, direct the members of the Personnel Monitoring Team to obtain necessary equipment and report to the assembly area. 5.5.3 Upon arrival at the assembly point the Personnel Monitoring Team Leader shall: 1.. Survey the assembly area. If radiation levels are greater than 10 mR/hr or if airborne contamination levels are greater than 10 times the permissible limit, notify gs the RET Leader and recommend an alternate
- t. ) assembly area.
- 2. Determine the extent of personnel contamination.
- 3. In the event of injured personnel, or personnel with radioactive contamination or excessive radiation exposure, carry out the appropriate steps in Procedure 69.000.10 (Radiological / Medical Emergency).
- 4. Inform the RET Leader if there are any personnel suffering from injuries, radioactive contamination, or excessive radiation exposure.
- 5. Assist Security to record names, social security numbers, badge numbers, addresses for non-employees, and disposition for all personnel on the log sheets provided in Attachment 2. This log will also be used l to account for all evacuees.
- 6. For all personnel who have been contam-inated, complete the " Disposition of Evacuee" form shown in Attachment 1.
EP-202-2 Rev. 0.B Page 6 6.0 Follow-up Actions 6.1 The Personnel Monitoring Team Leader Leader shall instruct the Scene Leaders to perform the following: 6.1.1 Collect personnel. dosimetry for processing. 6.1.2 Supervise the decontamination of personnel. 6.1.3 Assist Security to ensure " Disposition of Evacuee" forms have been completed with the proper information. 6.1.4 Order the release of evacuees after obtaining permission from the Personnel Monitoring Team Leader. 6.2 The Personnel Monitoring Team Leader shall: 6.2.1 Review " Disposition of Evacuee" forms and forward them to Security. 6.2.2 Prior to authorizing the release of any evacuees, obtain permission from the RET Leader for their release and brief the evacuees on the emergency situation including any radiological hazards which may be encountered. 6.2.3 Maintain accurate records of all contaminated personnel. 6.2.4 At the conclusion of PMT efforts, direct an inventory of PMT emergency equipment used at the scene.
- 1. Any missing equipment shall be recovered or replaced.
1
- 2. Any damaged equipment shall be repaired /
replaced, and reported to the General Supervisor, Health Physics.
- 3. All equipment shall be checked for proper operability, serviced, or repaired as necessary (batteries replaced, filters replaced, etc.) and restowed in proper storage locations.
1 EP-202-2 Rev. 0.B RECORD FORM DISPOSITION OF EVACUEE
- 1. Name: Social Security:
Last First MI i
- 2. Badge No. Date of Birth:
- 3. Address: (For.non-employee only):
i I 4. Dosimeter Type: Serial: Reading:
- 5. Surface Contamination Level:
,' Instrument / Serial:
- 6. Disposition Detained (Reason):
Released Date: l Time:
- 7. Remarks:
2 (For Information Center Evacuees, include auto license number.) 1 i 2 3 Recorded by: Reviewed by: l 1 i I i t Attachment 1 i Page 1 of 1 i
E ' ,, n ' i A? ot o d, a N O I T I S O P S I D O N E G D A B S E R I E L ES C YE A OS V LS E PE MR F ED O D NA iN O N O I T I S O P . S O I N D Y F T O I R G 1 1 O C L E S L A I C O S E M A N
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~ EP-203-1 (~ Rev. 0.B ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
FIRE BRIGADE: ACTIVATION RECORD OF APPROVAL AND CHANGES Submitted by rO Date Supervisor of Radiolo 'cg}fEmergency Response Preparednes Approved by fIh Chairman - LiaD(on Committee Date Liaison N Revision Committee No. Submitted Date Approval Date 1 2 3 4 5 6 7 8 O
EP-203-1 O Rev. 0.B ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
FIRE BRIGADE: ACTIVATION O O
EP-203-1 Rev. 0.B FIRE BRIGADE:_ ACTIVATION TABLE OF CONTENTS Page 1.0 Purpose............................................... 1 2.0 References............................................ 1 3.0 Entry Conditions...................................... 1 4.0 General Information .................................. 1 5.0 Immediate Actions..................................... 2 6.0 Follow-up Actions..................................... 6 1 t i s l f
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EP-203-1 i Rev. 0.B Page 1 1.0 Purpose To prescribe the steps for activating the Fire Brigade. 2.0 References 2.1 Enrico Fermi Atomic Power Plant Unit 2 Radiological ' Emergency Response Plan, Section B (On-Site Emergency Organization) and Section K (Radiologicel Exposure control). 2.2 Fire Brigade: Fire Involving Radiological Hazards (EP-203-2). 2.3 Plant Fires (20.000.22). 2.4 Applicable Fire Pre-Plans. 2.5 Selection and Use of Respiratory Protection Equipment (65.000.20).
~
2.6 Radiological / Medical Emergency (69.000.10). 3.0 Entry Conditions The Fire Brigade shall be activated by the Emergency Director in the event that:
- 1. An alarm from a plant fire or combustion product detector sounds.
- 2. A fire or explosion is reported to the Nuclear Shift Supervisor.
4.0 General Information 4.1 As a minimum, the' Fire Brigade consists of the j following shift, personnel:
- 1. Fire Brigade Leader (licensed operator).
- 2. Two (2) non-licensed operators.
- 3. One (1) shift Nuclear Instrument Repairman.
- 4. One (1) shift Radiation Chemistry Technician.
-EP-203-1 s
Rev. 0.B . ' Page 2 l 4.2 If necessary, the Fire Brigade'shall be augmented by the Frenclitown Volunteer Fire Department. 5.0 Immediate Actions , 5.1 When a'ctivated, the Fire Brigade Leader shall: 5.1.1 Immediately contact the Emergency Director / Nuclear Shift Supervisor in the Control Room and acknowledge the order to a;tivIte the Fire Brigade. Verify the assemLiyslocation with the Emergency Director / Nuclear Shif t Supervisor. 5.1.2 Proceed to the Operational Support Center (OSC) or other location designated by the Emergency Director / Nuclear Shift Supervisor. 5.L When activated the Fire Brigade membersishall report to the OSC, or other location designated by the Emergency Director / Nuclear Shift Supervisor. 5.3 The Fire Brigade Leader shall: - 5.3.1 Contact the Emergency Directo.-/ Nuclear Shift Supervisor and report that the Fire Brigade is assembled. 5 . 3 ., 2 Determine the status of the emergency from the Emergency Director / Nuclear Shift Supervisor, specifically with regard to the following:
- 1. Suspected cause of the fire.
- 2. If an evacuation has been ordered.
- 3. Location, extent, and class of the fire.
- 4. Severity of radiological hazards.
- 5. Areas v:t other abnormal personnel hazar@i.
- 6. If c .ta r evergency Teams are activated.
- 7. Fire protection system lineups. -
O 1
.s rT EP-203-1 Rev. 0.B Li ,)
Page 3
- 8. Corrective actions taken by the Emergency Director / Nuclear Shift Supervisor.
NOTE: If the fire involves radioactive material or is in a radiation area or controlled contamination area, refer to EP-203-2 (Fire Brigade: Fire Involving Radiological Hazards) for additional guidance. Follow the guidance in EP-203-2 and carry out the steps of this procedure concurrently. 5.3.3 If it is obvious from the initial report that assistance from the local volunteer fire department will be necessary, recommend to the Emergency Director / Nuclear Shift Supervisor that the Frenchtown Volunteer Fire Department be notified. NOTE: The Emergency Director / Nuclear Shift Supervisor will notify the Frenchtown Volunteer Fire Department, f 5.3.4 Determine the applicable procedures to be used i in fighting the fire from the following:
- 1. Plant Fires (20.000.22).
- 2. The appropriate Fire Pre-Plan for the particular zone.
- 3. Fire Brigade: Fire Involving Radiological Hazards (EP-203-2).
5.3.5 Brief Fire Brigade members on the status of the emergency as determined in step 5.3.2. 5.3.6 Direct Fire Brigade members to obtain necessary equipment from the OSC and report to the scene of the fire. If items are missing or additional equipment is necessary, contact the OSC Coordinator and request additional equipment. If the OSC Coordinator is not activated, contact the Emergency Director. 1O l
l EP-203-1 Rev. 0.B i Page 4 NOTE: If the area is expected to have airborne contamination, have Fire Briqcde members don Scott Air Paks. 5.3.7 Inform the Emergency Director / Nuclear Shift Supervisor that the Fire Brigade is activated and proceeding to the scene of the fire. 5.3.8 If a Member of the Security Force has not reported to the scene of the fire for personnel traffic control and extra communications, contact the Emergency Director / Nuclear Shift Supervisor and request that an MSF report to the scene. 5.4 At the scene of the fire, the Fire Brigade Leader shall: 5.4.1 Direct fire-fighting efforts. Fire-fighting actions shall be carried out in accordance with the procedures listed in step 5.3.4. 5.4.2 If there are injured personnel:
- 1. Immediately inform the Emergency Director / Nuclear Shift Supervisor.
NuTE: The Emergency Director / Nuclear Shift Supervisor will dispatch the Damage and Rescue Team to assist with injured personnel.
- 2. Administer life-saving first aid until the Damage and Rescue Team assumes this responsibility. Assistance may be required from the On-Site RET in evaluating injured personnel for contamination. The actions of Health Physics Procedure 69.000.10 (Radiological / Medical Emergency) shall be followed for contaminated / injured personnel.
- 3. Evaluate the need for medical assistance.
- 4. If on-site or off-site medical assistance appears necessary, inform the Emergency Director / Nuclear Shift Supervisor.
O
^
1 l
) EP-203-1 Rev. 0.B Page 5 NOTE: The Emergency Director / Nuclear Shift Supervisor will dispatch on-site or off-site medical assistance.
5.4.3 If off-site assistance is required to fight the fire, recommend to the Emergency Director / Nuclear Shift Supervisor that the Frenchtown Volunteer Fire Department be notified. 5.4.4 If there are radiological hazards, obtain assistance from the On-Site Radiological Emergency Team. Carry out the steps of EP-203-2 (Fire Brigade: Fire Involving Radiological Hazards). 5.4.5 Coordinate actions of the Fire Brigade, the Volunteer Fire Department, and any other Emergency Response Teams reporting to the scene of the fire. () 5.4.6 Keep the Emergency Director / Nuclear Shift Supervisor informed of the status of the fire. The Emergency Director / Nuclear Shift Supervisor shall be specifically informed of the following:
- 1. Exact location of the fire.
- 2. Extent of fire, smoke, radiological i hazards, and other hazards to personnel I
(such as damaged or unsafe equipment, electrical hazards, water on floor, etc.).
- 3. When the fire is out.
- 4. Extent of damage to equipment and systems and impact on plant operation and safety.
- 5. Recommended corrective actions such as isolating plant systems, deenergizing equipment, interrupting electrical power to portions of the plant, or removing equipment from service.
1 l
EP-203-1 Rev. 0.B Page 6 6.0 Follow-up Actions The Fire Brigade Leader shall: 6.1 Keep the Emergency Director / Nuclear Shift Supervisor informed of the status of fire-fighting actions. The following specific reports should be made:
- 1. When the fire area has been inspected for possible restart.
- 2. Extent of equipment and/or system damage.
6.2 Review the following information with the Damage and Rescue Team Scene Leader: 6.2.1 Background information, including apparent cause and extent of fire. Point out those areas which may have suffered heat, smoke, or water damage even though not obviously blackened or burned. 6.2.2 Current status of Fire Brigade follow-up actions, including evolutions which have been directed or are planned but not yet carried out. 6.2.3 Assessment of impact on plant operations and safety. 6.2.4 Present fire detection and fire protection system lineups. 6.2.5 Corrective actions recommended to the Emergency Director / Nuclear Shift Supervisor such as isolating plant systems, deenergizing equipment, interrupting electrical power to portions of the plant, or removing equipment from service. l 6.2.6 Extent of smoke, radiological hazards, or other I personnel hazards, (such as damaged or unsafe equipment, electrical hazards, etc.). NOTE: The Damage and Rescue Team is responsible for assessing fire damage and reporting to the Emergency Director. l 1
O EP-203-1 Rev. 0.B Page 7 6.3 When the fire area is judged safe enough for a damage inspection, permit the Damage and Rescue Team to survey the area. 6.4 Remain in charge at the scene and coordinate actions of Emergency Response Personnel. The Fire Brigade Leader-is not relieved of this responsibility until directed by the Emergency Director / Nuclear Shift Supervisor to delegate the responsibility to another designated person or to close out emergency response efforts. i O i l END
EP-203-2 Rev. 0.B ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
FIRE BRIGADE: FIRE INVOLVING RADIOLOGICAL HAZARDS RECORD OF APPROVAL AND CHANGES Submitted by ,49L _ Supervisor of Radio 'al Emergency Date Response Preparedne Approved by A Chairman - L on Committee Date Liaison Revision Committee [~)/ x- No. Submitted Date Approval Date 1 2 3 4 5 _ 6 7 i 8 i l l 1 l
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l [ \
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l
I l EP-203-2 Rev. 0.B ENRICO FERMI ATOMIC POWER PLANT-flNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
FIRE BRIGADE: FIRE INVOLVING RADIOLOGICAL HAZARDS O
EP-203-2 Rev. 0.B FIRE BRIGADE: FIRE INVOLVING RADIOLOGICAL HAZARDS TABLE OF CONTENTS Page 1.0 Purpose............................................... 1 References............................................ ~1 2.0 3.0 Entry Conditions...................................... 1 4.0 General Information................................... 1 5.0 Immediate Actions..................................... 2 I 6.0 Follow-up Actions..................................... 5 l Attachments List of Emergency Equipment........................ Attachment 1 l i T
N- EP-203-2 Rev. 0.B Page 1 1.0 Purpose To prescribe precautions to be followed by the Fire Brigade in fighting a fire involving, or possibly involving, radiological hazards. 2.0 References 2.1 Enrico Fermi Atomic Power Plant Unit 2 Radiological Emergency Response Plan, Section B (Onsite Emergency Organization) and Section K (Radiological Exposure Control). i 2.2 Radiation, Contamination, and Airborne Guides and Limits (61.000.05). . 2.3 Emergency Exposure Limits (69.000.15). 2.4 Fire Brigade: Activation (EP-203-1). 2.5 Use of Protective Clothing (65.000.10). 2.6 Selection and Use of Respiratory Protection Equipment (65.000.20). l 3.0 Entry Conditions The Fire Brigade has been activated for any of the following circumstances:
- 1. A fire occurs in a contaminated area or an area where radioactive material is maintained.
- 2. A fire occurs in a radiation area or high radiation area.
- 3. A fire occurs in an area of high airborne activity.
- 4. A fire occurs in a potentially contaminated system.
4.0 General Information 4.1 The Fire Brigade Leader shall coordinate with the on-l Site Radiological Emergency Team (On-Site RET) in l assessing radiological hazards in fighting any fire. o 1
l EP-203-2 Rev. 0.8 Page 2 4.2 The routine radiation exposure limits of Health Physics Procedure 61.000.05 (Radiation, Contamination, and Airborne Guides and Limits) shall not be exceeded unless specifically authorized by Health Physics personnel. The 10CFR20 limits shall not be exceeded unless specifically Director. authorized Emergency exposure by the Emergency limits are delineat'ed in Procedure 69.000.15 (Emergency Exposure Limits). 4.3 Contaminated personnel shall be decontaminated by the On-Site RET prior to their release. 5.0 Immediate Actions 5.1 The Fire Brigade Leader shall: 5.1.1 Carry out the Immediate Actions of EP-203-1 (Fire Brigade: Activation). 5.1.2 Verify with the Emergency Director that the On-Site RET is activated. NOTE: The On-Site RET will be activated by the Emergency Director whenever there is a fire involving radiological hazards. The On-Site RET is responsible for conducting radiation, airborne, and contamination surveys, establishing controlled areas to limit the spread of radioactive contamina-tion, estimating stay times, cleaning up radioactive contamination areas, decontam-inating emergency equipment, evaluating personnel fcr contamination, and, if . necessary, decontaminating personnel. 5.1.3 Assisted by the On-Site RET, brief Fire Brigade members on the radiological hazards, including the following:
- 1. General radiation dose rates.
- 2. Location of high radiation levels.
- 3. Expected radioactive materials.
- 4. Location of especially hazardous materials.
O
O EP-203-2
'\ s/ Rev. 0.B Page 3
- 5. Airborne contamination levels.
Instruct Fire Brigade members concerning proper stay times and areas they should avoid so as to minimize their radiation and contamination exposure. 5.1.4 Ensure that Fire Brigade personnel have proper protective clothing and respiratory equipment. NOTE: If the area is expected to have airborne contamination, have the Fire Brigade members don Scott Air Paks. 5.1.5 Ensure that Fire Brigade personnel are issued personal dosimeters and that the dosimeters are zeroed prior to use. 5.2 At the scene of the fire, the Fire Brigade Leader shall: () 5.2.1 Direct fire-fighting efforts, as discussed in EP-201-1 (Fire Brigade: Activation). 5.2.2 Assisted by the On-Site RET, supervise the actions of Fire Brigade members so as to minimize personnel radiation and contamination exposure. NOTE: The routine exposure limits of Health Physics Procedure 61.000.05 (Radiation, Contamination, and Airborne Guides and
- Limits) shall not be exceeded unless specifically authorized by Health Physics t
personnel. The 10CFR20 limits shall not be exceeded unless specifically authorized by the Emergency Director. Emergency exposure limits are delineated in Procedure 69.000.15 (Emergency Exposure l Limits). l 5.2.3 Supervise the actions of Fire Brigade members so as to minimize the spread of radioactive contamination, as necessary. O O
EP-203-2 Rev. 0.B h Page 4 Recommended steps include the following: NOTE: Efforts to control spreading radio-active contamination shall not impede steps in controlling a serious fire. This is a judgment which must be made by the Fire , Brigade Leader depending on the j specific situation. l
- 1. Only essential fire-fighting equipment should be brought into contaminated areas.
- 2. Treat all equipment used in contaminated areas as potentially contaminated. Do not remove the equipment from controlled areas until released by On-Site RET personnel.
- 3. Route fire hoses so as to avoid areas of loose surface contamination or spilled
- radioactive materials. ,
l i
- 4. Avoid dragging fire hoses and equipment through areas of loose surface contamina-tion or spilled radioactive materials.
i
- 5. Avoid using a direct stream from fire hoses if possible, and avoid hitting loose surface contamination or other radioactive materials with a direct stream. Use spray or fog nozzles where possible.
- 6. Avoid areas of higher contamination levels or more highly radioactive materials in favor of low-level contaminated areas or areas where low-level radioactive materials are located.
- 7. Treat all water in the controlled area as potentially contaminated.
5.2.4 If the Frenchtown Volunteer Fire Department is activated:
- 1. Repeat steps 5.1.3, 5.1.4, and 5.1.5 for Fire Department personnel.
O
O EP-203-2 kmsl Rev. 0.8 Page 5
- 2. Coordinate with the On-Site RET and the Fire Chief responding with the Volunteer Fire Department so as to minimize radiation and contamination exposure of personnel.
- 3. Coordinate with the Fire Chief so as to minimize the spread of radioactive contamination (see step 5.2.2).
NOTE: Volunteer Fire Department personnel receive only limited training in contamination control. Unless they are properly supervised, Fire Department personnel can greatly complicate any radiological problems. 5.3 Fire Brigade members shall: 5.3.1 Take steps as directed by the Fire Brigade ( , Leader to minimize radiation exposure and prevent personal contamination.
- 1. Fire protection clothing will serve as any needed anti-contamination clothing.
i
- 2. Scott Air Paks will serve as needed respiratory protection in a high airborne radioactivity situation.
- 3. Minimize time in radiation areas as l directed by the Fire Brigade Leader and the On-Site RET.
5.3.2 Minimize the spread of contamination. 5.3.3 Treat fire-fighting equipment used in contaminated areas as potentially contaminated. 6.0 Follow-up Actions 6.1 The Fire Brigade Team Leader shall obtain assistance from the On-Site RET in evaluating equipment and personnel for possible radioactive contamination. O l l l
l l EP-203-2 Rev. 0.B Page 6 NOTE: The On-Site RET retains the responsibilities listed in step 5.1.2. 6.2 Fire Brigade and Frenchtown Volunteer Fire Department personnel shall: 6.2.1 Remain in the fire area after the fire is extinguished. If the fire is in a high radiation area it may be necessary to move to an area near the scene that is of a lower radiation level. 6.2.2 Leave all potentially contaminated emergency equipment in the controlled area established by the On-Site RET. Equipment is not to be removed until released by On-Site RET personnel. 6.2.3 Exit the controlled area as directed by the On-Site RET. 6.2.4 Surrender personal dosimeters after exiting all radiation areas to On-Site RET personnel and be surveyed for contamination by On-Site RET personnel. 6.2.5 If contaminated, proceed as directed by On-Site RET personnel for decontamination. 6.3 At the conclusion of fire-fighting efforts, direc* n inventory of Fire Brigade emergency equipment. 6.3.1 Any missing equipment shall be recoveied or replaced. 6.3.2 Any damaged equipment shall be repaired or replaced and reported to OSC Coordinator. 6.3.3 All equipment shall be checked for proper operability, replaced or repaired as necessary (batteries replaced, filters replaced, etc.) and restowed in proper storage locations. O
() EP-203-2 Rev. 0.B .i LIST OF EMERGENCY EQUIPMENT IN OSC QUANTITY ITEM QUANTITY AVAILABLE
- 1. Fire protection clothing:
- a. Yellow turnout coats 12
- b. Boots 12 pr.
- c. Fire-fighter gloves 12 pr.
- d. Fire hats 12
- e. Fire-resistant pants with suspenders 12 pr.
- 2. Portable lights (with extra sets of batteries)
- a. Flashlights (5 cell) 5
- b. Six volt lantern 1
- 3. Portable extinguishers:
i j a. CO 2 3 j b. Chemical (40# ansul) 1
- 4. Scott Air Paks
- a. Without speak-easy 8
- b. With speak-easy 6 l
- 5. Scott Air Bottles 32 i
- 6. Hand Truck 1
! 7. Trauma II First Aid Kit 1
- 8. Sets of Air Splints , 2 l 4
- 9. Life Lines (50 ft)
- 10. Mask Cleaning solution with Bucket 1
- 11. MSA Air Bottles 4
? I l ( () Attachment 1 Page 1 of 3 I i
EP-203-2 Rev. 0.B h LIST OF EtiERGENCY EQUIPMENT IN FIRE PROTECTION EQUIPMENT LOCKER QUANTITY ITEM QUANTITY AVAILABLE
- 1. Fire axe 1
- 2. Wrecking bar 1
- 3. Canvas tarps 2
- 4. Bolt cutters 1
- 5. MSA Air Packs 5
- 6. tiSA Air Bottles 6
- 7. Sets of Rain Gear 3
- 8. Small Valve Wrenches 2
- 9. Medium Valve Wrenches 2
- 10. Air Jack 1
- 11. Assorted Pliers, Screwdrivers and Fuse Pullers
- 12. Administrative Supplies Attachment 1 Page 2 of 3 I
() EP-203-2 Rev. 0.B ; LIST OF EMERGENCY EQUIPMENT . IN FIRST AID AND STRETCHER LOCKERS QUANTITY ITEM QUANTITY AVAILABLE
- 1. Trauma II First Aid Kit l-
- 2. 2 Bottles of O2
.3. O 2 Regulators 2
- 4. Blankets 4
- 5. Plastic Stokes Stretcher 2
- 6. Fire Extinguisher
- a. CO 2 3
- b. Chemical (409 ansul) 9 O
i i i i 4 l l j END , ,() Attachment 1 Page 3 of 3 j l !.,.--.-..- . ~ , _ _ _ . _ . . . _ . . _ , . _ . _ _ _ . _ _ , _ _ _ _ _ _ _ _ . _ _ . _ _ , _ _ _ _ _ _ _ _ _ _
EP-204-1 Rev. 0.B ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
DAMAGE AND RESCUE TEAM: ACTIVATION RECORD OF APPROVAL AND CH NGES Submitted by .( Supervisor of Radiolo ca't'Eme rg ency Date Response Preparedne s Approved by <) Chairman - Liai5on Committee Date Liaison I) Revision Committee
/ No. Submitted Date Approval Date 1
2 3 4 5 6 7 8 cx L/ '
_ = - - . _ . _ _ _ . __. ~_ --...-. _.-.__.._.- - ._.-- -. _ _ . - . - . .._- . i ! 1
+
EP-204-1 1 Rev. 0.B i i L I' i r ENRICO FERMI ATOMIC POWER PLANT i UNIT NO. 2 l Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE 1
Title:
DAMAGE AND RESCUE TEAM: ACTIVATION (D L I
g EP-204-1 Rev. 0.B DAMAGE kND RESCUE TEAM: ACTIVATION _TA.BLE OF CONTENTS Page 1.0 Purpose............................................... 1 2.0 References............................................ 1 3.0 Entry Conditions...................................... 1 4.0 General Information................................... 1 5.0 Immediate Actions..................................... 2 6.0 Follow-up Actions..................................... 6 Attachments List of Emergency Equipment........................ Attachment 1
r 4 O EP-204-1 Rev. 0.B Page 1 1.0 Purpose i To prescribe the steps for activating the Damage and Rescue Team. 2.0 References 2.1 Enrico Fermi Atomic Power Plant Unit 2 Radiological Emergency Response Plan, Section B (On-Site Emergency
- Organization), Section K (Radiological Exposure Control), and Section L (Medical Support).
2.2 Radiological / Medical Emergency (69.000.10). 2.3 Damage and Rescue Team: Disaster (EP-204-2). 2.4 Damage and Rescue Team: Search and Rescue (EP-204-10). 2.5 Damage and Rescue Team: Evacuation (EP-204-30). 3.0 Entry Conditions ( The Damage and Rescue Team shall be activated when any of the following occur:
- 1. Plant Area Evacuation.
- 2. Protected Area Evacuation.
- 3. Site Area Evacuation.
- 4. Personnel injury.
- 5. Any disaster which results in personnel injury, l missing personnel, or plant damage.
- 6. As directed by the Emergency Director.
4.0 General Information 4.1 A licensed operator shall be designated by the Nuclear Shift Supervisor / Emergency Director as the i Damage and Rescue Team Leader. lO
I l l EP-204-1 Rev. 0.B Page 2 4.2 The responsibilities of the Damage and Rescue Team are the following: 4.2.1 Providing first aid to injured personnel. 4.2.2 Performing search and rescue. 4.2.3 Controlling a radiological release or the release of a toxic substance, and performing emergency repairs to stop the release. 4.2.4 Assessing damage to plant equipment and systems. 4.2.5 Making emergency repairs to damaged equipment and systems. 5.0 Immediate Actions 5.1 When activated the Dac3ge and Rescue Team Leader shall: 5.1.1 Immediately contact the Emergency Director and acknowledge the order to activate the Team. Verify the Team assembly location with the Emergency Director. 5.1.2 Proceed to the Operational Support Center (OSC) or other location designated by the Emergency Director. 5.2 When activated the Damage and Rescue Team shall report to the OSC or other location designated by the Emergency Director. 5.3 The Damage and Rescue Team Leader shall: 5.3.1 Contact the Emergency Director and report that the Damage and Rescue Team is assembled. 5.3.2 Determine the status of the emergency from the Emergency Director, specifically with regard to the following (if known):
- 1. Suspected cause of the emergency.
O
. J
(,,/ EP-204-1 Rev. 0.B Page 3
- 2. Number and location of injured personnel, and the severity of the injuries.
- 3. If an evacuation has been directed and the location of the assembly area.
- 4. If there are missing personnel.
- 5. Extent of damage to equipment or plant systems.
- 6. Location and neverity of any radiological hazards.
- 7. Areas with other abnormal personnel hazards.
- 8. If other Emergency Teams are activated.
- 9. Pertinent plant lineups.
l 10. Corrective actions taken by the Emergency i [\- Director. l l 5.3.3 If it is obvious from the initial report that medical treatment other than first aid is required, recommend that on-site or off-site medical assistance be obtained, i 5.3.4 Determine if off-shift Damage and Rescue Team personnel or off-site support is necessary. If so, request support from the OSC Coordinator. If the OSC Coordinator is not activated, the request shall be made to the Emergency Director. 5.3.5 If there are radiological hazards, ensure that the On-Site Radiological Emergency Team (On-Site RET) is activated. NOTE: The On-Site RET will be activated whenever there are radiological hazards involved. The On-Site RET is responsible for conducting radiation, airborne and contamination surveys, establishing controlled areas to limit lO 1 - - .-
l l l l EP-204-1 Rev. 0.B Page 4 the spread of radioactive contamina-tion, estimating stay times, cleaning up radioactive contamination areas, decontaminating emergency equipment, evaluating personnel for contamination, and, if necessary, decontaminating personnel. 5.3.6 Brief the Team Members on the status of the emergency as determined in step 5.3.2. 5.3.7 If necessary the Emergency Director shall contact the Secondary Alarm Station (SAS) Operator and have a Member of the Security Force (MSF) report to the scene. If an MSF does not report to the scene, and his assistance is required, contact the Emergency Director and request an MSF report to the scene for traffic and access control and extra communications. 5.4 If the Damage and Rescue Team is only required at one location, (for example, the scene of an explosion) the Damage and Rescue Team Leader shall: 5.4.1 Direct Team members to obtain necessary emergency equipment. Items which may be necessary are listed in Attachment 1. If items are missing or additional equipment is necessary, contact the OSC Coordinator and request additional equipment. If the OSC Coordinator is not activated, contact the Emergency Director. 5.4.2 Proceed to the location with other Team Members and supervise Damage and Rescue Team activities. 5.5 If the emergency is such that members of the Team are required in several different areas, the Damage and Rescue Team Leader shall: 5.5.1 Determine what Team efforts are required at the various locations. O
EP-204-1 O' Rev. 0.B Page 5 5.5.2 Assign Damage and Rescue Team Scene Leaders, each with sufficient personnel to carry out the following actions at each location:
- 1. Administer first aid.
- 2. Conduct search and rescue.
- 3. Perform damage assessment.
- 4. Effect damage repair.
- 5. Control a radiological release or a release of a toxic substance, and perform emergency repairs to stop the release.
NOTE: The Damage and Rescue Team Leader can assume the role of Damage and Rescue Team Scene Leader at one of the locations. He still retains responsibility for over-all control of the Damage and Rescue Team efforts. However, Os such control may best be exercised from the OSC. 5.5.3 Direct Scene Leaders to perform the following:
- 1. Obtain necessary emergency equipment.
- 2. nroceed to their assigned locations.
- 3. Supervise Damage and Rescue Team activities at each location.
- 4. Periodically report back to the Team Leader.
5.6 The Damage and Rescue Team Scene Leaders shall: 5.6.1 Obtain necessary equipment. If items are missing or additional equipment is necessary, contact the Damage and Rescue Team Leader. 5.6.2 Proceed to their assigned locations. O
EP-204-1 Rev. 0.B Page 6 5.6.3 If an MSF has not arrived at the scene and is required, contact the Damage and Rescue Team Leader. 5.6.4 Periodically report to the Damage and Rescue Team Leader. 5.7 The Damage and Rescue Team Leader shall: 5.7.1 Periodically report to the Emergency Director, giving the status of Damage and Rescue Team efforts based on Scene Leader reports. 5.7.2 If additional equipment is required, contact the OSC Coordinator and request the additional equipment. If the OSC Coordinator is not activated, contact the Emergency Director. 6.0 Follow-up Actions 6.1 The Damage and Rescue Team Leader shall: 6.1.1 Obtain assistance from the On-Site RET in evaluating areas or equipinent for contamination, establishing controlled areas, performing equipment and area decontamination, evaluating personnel for contamination, and, if necessary, performing decontamination. 6.1.2 Maintain communications with all Damage and Rescue Team Scene Leaders. 6.1.3 Keep the Emergency Director informed of the status of the emergency, especially with regard to the following:
- 1. Status of treating injured personnel.
- 2. Status of search and rescue efforts.
- 3. Status of damage assessment.
- 4. Recommend corrective actions such as isolating systems, deenergizing equipment, or removing equipment from service.
O
EP-204-1 Rev. 0.B , Page 7 ' 6.2 The Damage and Rescue Team Scene Leaders shall keep the Damage and Rescue Team Leader informed of the status of the emergency and Team efforts, especially with regard to the items delineated in step 6.1.3. 6.3 At the conclusion of Damage and Rescue Team efforts, the Damage and Rescue Team Leader shall direct an inventory of Team equipment.
- 1. Any missing equipment shall be recovered or replaced.
- 2. Any damaged equipment shall be repaired / replaced and reported to the OSC Coordinator.
- 3. Any contaminated equipment shall be left in controlled areas until released by On-Site RET personnel.
- 4. All equipment shall be checked for operability, serviced or repaired as necessary (batteries replaced, filters replaced, etc.)
and restowed in proper storage locations. i l O 4
\
u EP-204-1 Rev. 0.B LIST OF EMERGENCY EQUIPMENT , > QUANTITY ITEM QUANTITY AVAILAllLE
- 1. Fire protection clothing: }, '
i L. Yellow turnout coats 12
- b. Boots 12 pr.
- c. Fire-fighter gloves 12 pr.
- d. Fire hats 12
- e. Fire-resistant pants with suspenders 12 pr.
- 2. Portable lights (with extra sets of batteries) s
- a. Flashlights (5 cell) 5
- b. Six volt lantern 1
- 3. Portable extinguishers: ~ ,'
- a. CO 2 3
- b. Chemical (409 ansul) 1 >
1
- 4. Scott Air Paks - *
- a. Without speak-easy '8
- b. With speak-easy 6 1:
- 5. Scott Air Bottles -32 '
- 6. Hand Truck 1
- 7. Trauma II First Aid Kit 1 l -
- 8. Sets of Air Splints 2 'X s t
- 9. Life Lines (50 ft) 4
- 10. Mask Cleaning solution with Bucket 1 __
- 11. MSA Air Bottles 4 l
l l Attachment'1 O , Page 1 ofs 3 1 E s a i e
EP-204-1 Rev. 0.B s LIST OF EMERGENCY EOUIPMENT IN FIRE PROTECTION EQUIPMENT LOCKER QUANTITY ITEM OUANTITY AVAILABLE
- 1. Fire axe 1
- 2. Wrecking bar 1
- 3. Canvas tarps 2
- 4. Bolt cutters 1
- 5. MSA Air Packs 5
- 6. MSA Air Bottles 6
- 7. Sets of Rain Gear 3
- 8. Small Valve Wrenches 2
- 9. Medium Valve Wrenches 2
- 10. Air Jack 1
- 11. Assorted Pliers, Screwdrivers and Fuse Pullers
- 12. Administrative Supplies Attachment 1 Page 2 of 3 :
i O EP-204-1 Rev. 0.B LIST OF EMERGENCY EQUIPMENT IN FIRST AID AND STRETCHER LOCKERS QUANTITY ITEM QUANTITY AVAILABLE
- 1. Trauma II First Aid Kit 1
- 2. Bottles of 02 2 i
! 3. 02 Regulators 2
- 4. Blankets 4 i
- 5. Plastic Stokes Stretcher 2
- 6. Fire Extinguisher
- a. CO 2 3
- b. Chemical (404 ansul) 9 i
'O l l l l l l END Attachment 1 Page 3 of 3 I
EP-204-2 [~] V Rev. 0.B ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
DAMAGE AND RESCUE TEAM: DISASTER RECORD OF APPROVAL AND HANGES Submitted by (* Supervisor of Radio ib61 Emergency Date Response Preparedn
/
Approved by 4[3 Chairman - Liarson Committee Date Liaison O Revision Committee No. Submitted Date Approval Date 1 2 3 4 5 6 8 O
l -i ! 1 7 EP-204-2 Rev. 0.8 1 i. I l 1 I , I ENRICO FERMI ATOMIC POWER PLANT l t !' UNIT NO. 2 i 4 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
DAMAGE AND RESCUE TEAM: DISASTER ,
. l h
I . I ! l t 9 i t
I 4 L t
; s 1 i
EP-204-2 > Rev. 0.B - 8 ! DAMAGE AND RESCUE TEAM: DISASTER i TABLE OF CONTENTS I, Page i ~ 1.0 Purpose............................................... 1 , 2.0 References............................................ 1 1 ! 3.0 Entry Conditions...................................... 1 l ) I 4.0 General Information................................... 1 5.0 Immediate Actions..................................... 2 1' i 6.0 Follow-up Actions..................................... '3 1 I I I I t l l l i 1 u f I
I ' b
\m,/ EP-204-2 Rev. 0.B Page 1 1.0 Purpose To prescribe the actions and responsibilities of the Damage and Rescue Team in the event of any disaster.
2.0 References 2.1 Enrico Fermi Atomic Power Plant Unit 2 Radiological Emergency Response Plan, Section B (On-Site Emergency Organization), Section K (Radiological Exposure Control), and Section L (Medical Support). 2.2 Damage and Rescue Team: Activation (EP-204-1). 2.3 Damage and Rescue Team: Search and Rescue (EP-204-10). 2.4 Radiological / Medical Emergency (69.000.10). 2.5 Radiation, Contamination, and Airborne Guides and Limits (61.000.05).
- 2.6 Emergency Exposure Limits (69.000.15).
3.0 Entry Conditions The Damage and Rescue Team shall be activated for any disaster which results in personnel injury, missing personnel, or plant damage. 4.0 General Information The Damage and Rescue Team is responsible for the following:
- 1. Providing first aid to injured personnel.
- 2. Performing search and rescue.
f
- 3. Controlling a radiological release, or the release of a toxic substance, and performing emergency repairs to stop the release.
- 4. Assessing da.nage to plant equipment and systems.
- 5. Making emergency repairs to damaged equipment and rs systems.
, N ,) 1 1 L
EP-204-2 h Rev. 0.B Page 2 CAUTION: The routine exposure limits of Health Physics Procedure 61.000.05 (Radiation, Contamination, and Airborne Guides and Limits) shall not be exceeded unless specifically authorized by Health Physics personnel. The 10CFR20 limits shall not be exceeded unless specifically authorized by the Emergency Director. Emergency exposure limits, which require Emergency Director approval, are delineated in Health Physics Procedure 69.000.15 (Emergency Exposure Limits). 5.0 Immediate Actions 5.1 The Damage and Rescue Team shall report to the Operational Support Center (OSC), or an alternate location, when directed by the Emergency Director. 5.2 The Damage and Rescue Team Leader shall: 5.2.1 Activate the Damage and Rescue Team, in accordance with EP-204-1 (Damage and Rescue Team: Activation). 5.2.2 Determine from the Emergency Director the status of the emergency. 5.2.3 Brief the Damage and Rescue Scene Leaders on the status of the emergency as determined in step 5.2.2 above. 5.3 The Scene Leaders shall: 5.3.1 Direct necessary first aid for victims in accordance with Health Physics Procedure 69.000.10 (Radiological / Medical Emergency). 5.3.2 Immediately report the names of victims and the injuries sustained by them, to the Damage and Rescue Team Leader. 5.3.3 If necessary, request outside medical 1ssistance from the Damage and Rescue Team Leader. 5.3.4 Take steps to minimize personnel exposure. O l
)
s_/ EP-204-2 Rev. 0.B Page 3 CAUTION: If any Team members will exceed the < routine exposure limits of Health Physics Procedure 61.000.05 (Radiation, Contamination, and Airborne Guides and Limits) and no Health Physics personnel are assigned to the Group, contact the Damage and Rescue Team Leader prior to exceeding those limits. The Damage and Rescue Team Leader can obtain authoriza-tion. If Health Physics personnel are assigned, they can give authorization. 5.3.5 If there are radiological hazards obtain assistance from the On-Site Radiological Emergency Team (On-Site RET). 5.3.6 If personnel are reported missing, perform search and rescue in accordance with EP-204-10 (Damage and Rescue Team: Search and Rescue). 5.3.7 Assess damage to affected systems and (('%j) equipment and report the following to the Damage and Rescue Team Leader:
- 1. Status of damage assessment.
- 2. Affected systems and equipment.
- 3. Impact on plant operations and safety.
- 4. Recommended corrective actions.
- 5. Extent of radiological or other personnel hazards.
5.3.8 Perform any immediate repairs or isolations to affected systems and equipment as directed by the Emergency Director. 6.0 Follow-up Actions The Damage and Rescue Team Leader shall: 6.1 Keep the Emergency Director informed of the status of the emergency and Damage and Rescue Team efforts.
EP-204-2 Rev. 0.B Page 4 6.2 Direct Team members who were required to enter areas of radioactive contamination to perform the following: 6.2.1 Leave potentially contaminated equipment not required for the transport of any injured personnel in the contaminated area until released by Health Physics personnel. 6.2.2 Exit the contaminated areas as directed by the On-Site RET. 6.2.3 If contaminated, proceed as directed by On-Site RET personnel for decontamination. 6.3 Ensure that all follow-up actions of EP-204-1 (Damage and Rescue Team: Activation) are completed. O I END l
- I EP-204-10 O' Rev. 0.B ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2-Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
DAMAGE AND RESCUE TEAM: SEARCH AND RESCUE RECORD OF APPROVAL AN CHANGES Submitted by r( Supervisor of Radiolohltal Emergency Date Response Prepared s Approved by n l Chairman - Lhgison Committee Date Liaison C) Revision Committee No. Submitted Date Approval Date 1 2 4 3 l 4 5 6 7 8 l l g- -, ---- _ ,_ . . . _ . - . - ._ _ v_--- . -_ -_ -_ _ _ _ _ _ _
a (..._.-.._..-------- - - -.- - _ - . . - - .-. - . .- . . _ . - - I i i l l , l i EP-204-10 Rev. 0.B 1 4 1 i i i r r i i ENRICO FERMI ATOMIC POWER PLANT i UNIT NO. 2 - l I l Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE l s
Title:
DAMAGE AND RESCUE TEAM: SEARCH AND RESCUE e I I l 0 t Ir r L I
e I l EP-204-10 ' Rev. 0.B 4 l DAMAGE AND RESCUE TEAM: SEARCH AND RESCUE I i l TABLE OF CONTENTS ! I Page 1.0 Purpose............................................... 1 . 2.0 References............................................ 1 ; 3.0 Entry Conditions...................................... 1 I: i 4.0 General Information................................... 1 l 5.0 Immediate Actions..................................... 2 : e 6.0 Follow-up Actions..................................... 4 i m i i
EP-204-10 Rev. 0.B Page 1 1.0 Purpose To prescribe the procedures for the Damage and Rescue Team in conducting search and rescue efforts. 2.0 References 2.1 Enrico Fermi Atomic Power Plant Unit 2 Radiological Emergency Response Plan, Section B (On-Site Emergency Organization), Section J (Protective Response), Section K (Radiological Exposure Control), and Section L (Medical Support). 2.2 Damage and Rescue Team: Activation (EP-204-1). 2.3 Radiological / Medical Emergency (69.000.10). 2.4 Radiation, Contamination, and Airborne Guides and Limits (61.000.05). 2.5 Emergency Exposure Limits (69.000.15). , (-}
\_) 2.6 Airborne Radioactivity Survey Techniques (63.000.30).
! 3.0 Entry Conditions The Damage and Rescue Team shall perform search and rescue operations when directed by the Emergency Director in the event: i
- 1. Individuals are known or suspected to be trapped and/or injured within an accident area.
- 2. Subsequent to an evacuation, personnel are unaccounted for.
4.0 General Information The Damage and Rescue Team is responsible for the following:
- 1. Searching for, and rescuing missing personnel.
- 2. Providing first aid to injured personnel.
- 3. Transporting injured personnel for on-site medical treatment or for further transport by ambulance.
i fS U
EP-204-10 Rev. 0.B Page 2 CAUTION: The routine exposure limits of Health Physics Procedure 61.000.05 (Radiation, Contamination, and Airborne Guides and Limits) shall not be exceeded unless specifically authorized by Health Physics personnel. The 10CFR20 limits shall not be exceeded unless specifically authorized by the Emergency Director. Emergency exposure limits, which require Emergency Director approval, are delineated in Health Physics Procedure 69.000.15 (Emergency Exposure Limits). 5.0 Immediate Actions 5.1 The Damage and Rescue Team shall report to the Operational Support Center (OSC), or an alternate location, when directed by the Emergency Director. 5.2 The Damage and Rescue Team Leader shall: 5.2.1 Activate the Damage and Rescue Team, in accordance with EP-204-1 (Damage and Rescue Team: Activation). 5.2.2 Determine from the Emergency Director or the Secondary Alarm Station (SAS) Operator the names of any missing personnel and any other additional information about them or their whereabouts. 5.2.3 Determine from the Emergency Director if there are any personnel hazards which may affect search and rescue efforts. 5.2.4 Designate Search and Rescue Groups as necessary.
- 1. Assign a minimum of two personnel per Group.
- 2. Assign one person in each Group as the Group Leader.
- 3. Assign a minimum of one radio per Group.
- 4. Assign specific search areas to each Group.
O
's EP-204-10 Rev. 0.B Page 3 5.2.5 If necessary, obtain permission from the Emergency Director for specified volunteers to exceed 10CFR20 exposure limits.
CAUTION: If personnel are expected to exceed exposure limits of 10CFR20 these personnel must be volunteers. 5.2.6 Brief search and rescue personnel on the following:
- 1. Names of missing personnel and any additional information available on their whereabouts.
- 2. Personnel hazards, including high radiation, high airborne activity, fire, smoke, steam, wreckage, etc.
- 3. Required protective and emergency
/~' equipment.
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- 4. Exposure limits and stay times.
5.2.7 Report names and condition of any injured personnel to the Emergency Director. 5.2.8 Contact the Emergency Director to obtain off-site medical assistance if required. 5.3 The Damage and Rescue Team Group Leaders shall: 5.3.1 Report the progress of search and rescue efforts by portable radio, to the Team Leader every 5 minutes. Report which portions of the assigned search areas have been covered. 5.3.2 Take steps to minimize personnel exposure. 5.3.3 Administer necessary first aid to victims in accordance with Health Physics Procedure 69.000.10 (Radiological / Medical Emergency). 5.3.4 Immediately report injuries sustained by victims to the Damage and Rescue Team Leader. a
EP-204-10 h Rev. 0.B Page 4 5.3.5 If necessary, request outside medical assistance from the Damage and Rescue Team Leader. 5.3.6 If the rescued victim is injured and can be moved, transport him to the area designated by the Damage and Rescue Team Leader. Continue to administer necessary first aid until relieved by medical personnel. CAUTION: Prompt treatment for serious or potentially serious injury has priority over decontamination efforts, treatment for excessive radiation exposure, or movement of the victim. 6.0 Pollow-up Actions The Damage and Rescue Team Leader shall: 6.1 Ensure all assigned areas are searched and that all h missing personnel are accounted for. 6.2 Direct Group members who were required to enter areas of radioactive contamination to perform the following: 6.2.1 Leave potentially contaminated equipment not required for the transport of any injured personnel, in the contaminated area until released by On-Site RET personnel. 6.2.2 Exit the contaminated areas as directed by the On-Site RET. 6.2.3 If contaminated, proceed as directed by On-Site RET personnel, for decontamination. 6.3 Ensure that all follow-up actions of EP-204-1 (Damage and Rescue Team: Activation) are completed. END O
4 EP-204-30 Rev. 0.B O~- ENRICO FERMI ATOMIC POWER PLANT UNIT *.!O. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
DAMAGE AND RESCUE TEAM: EVACUATION
~
RECORD OF APPROVAL AND C GES Submitted by O S Supervisor of RadiologicalJmergency Date Response Preparedness Approved by Chairman - Liaiso mittee Date i Liaison Revision Committee No. Submitted Date Approval Date 1 2 3 4 5 l 7 8 l l O l
- - . . - - - - . . - . . - . - . . - - - - ~ - - - . - - - - . _ . . ~ _ - - _ . = . . . . . --
i ! 'l ! EP-204-30 Rev. 0.B i
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- 1 1
! i I i P d i i 1 ENRICO FERMI ATOMIC POWER PLANT
- 1 UNIT NO. 2 j Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
DAMAGE AND RESCUE TEAM: EVACUATION i iO t i l l ; I, 4 l I i s )6 I h
i
! EP-204-30 Rev. 0.B !
I DAMAGE AND RESCUE TEAM: EVACUATION t i TABLE OF CONTENTS Page ! l , 1.0 Purpose............................................... 1 l 1 2.0 References............................................ I 1 3.0 Entry Conditions...................................... 1 1
- 4.0 General Information................................... 1 j 5.0 Immediate Actions..................................... 2 i
6.0 Follow-up Action...................................... 3 l. l l 4
+
i 1 I l. i l
[(,,/ EP-204-30 Rev. 0.B Page 1 1.0 Purpose To prescribe the actions to be performed by members of the Damage and Rescue Team in the event of an evacuation. 2.0 References 2.1 Enrico Fermi Atomic Power Plant Unit 2 Radiological Emergency Response Plan, Section B (On-Site Emergency Organization), Section J (Protective Response), Sectirn K (Radiological Exposure Control), and Section L (Medical Support). 2.2 Damage and Rescue Team: Activation (EP-204-1). 2.3 Damage and Rescue Team: Search and Rescue (EP-204-10). 2.4 Radiological / Medical Emergency (69.000.10). 3.0 Entry Conditions l ' h(~N 3.1 The Damage and Rescue Team is activated in the event of:
- 1. A Plant Area Evacuation
- 2. A Protected Area Evacuation
- 3. A Site Area Evacuation.
l 4.0 General Information 4.1 A , Plant Area Evacuation is the supervised evacuation of a specific area of the plant by all unnecessary personnel to another designated, safe area inside the Protected Area. 4.2 A Protected Area Evacuation is defined as the supervised evacuation of all unnecessary personnel from the Protected Area to Warehouse 19 or the Security Building. 4.3 A Site Area Evacuation is defined as the supervised evacuation of all unnecessary personnel from any site facility, including, but not limited to, the Protected Area, the Visitors Center, the General d
EP-204-30 Rev. 0.B Page 2 Training and Orientation Center, the Nuclear Operations Center, Fermi 1, or any other occupied area within the owner-controlled area, to the Newport Warehouse or alternate assembly area. 4.4 In an evacuation the Damage and Rescue Team is responsible for assisting injured personnel, performing search and rescue, assessing damage to plant equipment, and performing necessary actions to prevent further damage to affected equipment. 5.0 Immediate Actions 5.1 The Damage and Rescue Team members shall report to the Operational Support Center (OSC), or an alternate location, when directed by the Emergency Director. 5.2 The Damage and Rescue Team Leader shall: 5.2.1 Activate the Damage and Rescue Team in accordance with EP-204-1 (Damage and Rescue Team: Activation). 5.2.2 Contact the Emergency Director and determine the status of the following:
- 1. Injured personnel and their location.
- 2. Missing personnel.
- 3. The need for damage assessment.
- 4. The need for damage repair.
5.2.3 Divide Team members and aproint Group Leaders as necessary to proceed to the evacuation assembly area or the scene of the emergency to carry out team functions. 5.2.4 Make reports to the Emergency Director on the status of the following:
- 1. Injured personnel.
- 2. Missing personnel.
- 3. Damage to systems or equipment.
b)\_s EP-204-30 Rev. 0.B Page 3 J 4. Necessary repairs or isolations performed on systems or equipment. 5.3 The Damage and Rescue Team members shall perform the following, as required: 5.3.1 Provide first aid to injured personnel in accordance with Procedure 69.000.10 (Radiological / Medical Emergency). 5.3.2 In the event of missing personnel, perform search and rescue in accordance with EP-204-10 (Damage and Rescue Teams Search and Rescue). 5.3.3 Assess damage to plant systems or components. 5.3.4 Provide emergency repairs or isolations to systems or components. 5.3.5 Make reports to the Damage and Rescue Team Leader on the status of the items listed in O 5.2.2. 6.0 Follow-up Action 6.1 Thc Damage and Rescue Team Leader shall keep the Emergency Director informed as to the status of:
- 1. Injured personnel and the need for any outside medical support.
- 2. Missing personnel.
- 3. System or equipment damage.
- 4. Repair or isolations performed on affected equipment.
6.2 The Damage and Rescue Team Leader shall ensure that all follow-up actions of EP-204-1 (Damage and Rescue Team: Activation) are completed. END p > (_ /
0
- 1 EP-205-1 Rev. 0.B i
ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 ! Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
SECURITY FORCE: RESPONSE FOR FIRE, DISASTER OR RADIOLOGICAL EMERGENCY RECORD OF APPROVAL AND C GES ! Submitted by f3 Supervisor of Radiolo aTEmergency Date ] Response Preparednes Approved by G Chairman - LiaiscWi Committee Date Liaison l Revision Committee
- No. Submitted Date Approval Date i 1 2
l i 3 4 , 5 l 6 7 8 I O
I i j EP-205-1 ' Rev. 0.B
)
i ? I I ! i i l s f I ENRICO FERMI ATOMIC POWER PLANT ' i UNIT NO. 2 l i l J Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE i
Title:
SECURITY FORCE: RESPONSE FOR FIRE, DISASTER i OR RADIOLOGICAL EMERGENCY ! ii I 3 F b e i i l I
- "- - ---ve--+__------ *-wwe-%..w - -...i ---m.ymm.ym.-.pem a+n g- --& -i- wwm y-m mw y+-wi
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! EP-205-1 i j Rev. 0.B I i SECURITY FORCE: RESPONSE FOR FIRE, DISASTER OR ; ! RADIOLOGICAL EMERGENCY TABLE OF CONTENTS l Page 1.0 Purpose ............................................... 1 l 2.0 References .............................................l 1 1 1 30 Entry Conditions ...................................... 1 4 4.0 General Information ................................... 1
- 5.0 Immediate Actions ..................................... 2 6.0 Follow-up Actions ..................................... 8 a
h i I 1 l i i l i
. - - - - _ . - - - - - . , _ , , . . _ . . - - - - . , - , , - . . - - , , _ - -. ,_n. . _ , . . , _ . . , , , , , . _ , _ . . _ _ . - . , . . _ , . - . , _ - . _ . _ _ _ . . _ , ,, _ . , . , . . , , , , , ,.
1 EP-205-1 s_/ Rev. 0.B Page 1 1.0 Purpose To prescribe the actions to be performed by the Security Force in event of a fire, disaster, or radiological emergency. l l 2.0 References l 2.1 Enrico Fermi Atomic Power Plant Unit 2 Radiological Emergency Response Plan, Section B (Onsite Emergency Organization) and Section J (Protective Response). 2.2 Enrico Fermi-Unit 2 Contingency Plan Implementing Procedures. 2.3 Security Force: Control of In-Plant Access for Emergency Response Personnel (EP-205-2). 2.4 Security Force: Control of Site Area Access during Fire, Disaster, or Radiological Emergency (EP-205-3). l () 2.5 Security Force: Security Emergency during Fire, Disaster, or Radiological Emergency (EP-205-4). 2.6 Security Force: Evacuation (EP-205-30). 3.0 Entry Conditions Any of the following events occur:
- 1. The Nuclear Shift Supervisor or Emergency Director declares an Unusual Event, an Alert, a Site Area Emergency, or a General Emergency.
- 2. Security Emergency involving fire, disaster, or radiological hazards.
- 3. Plant Area Evacuation.
- 4. Protected Area Evacuation.
- 5. Site Area Evacuation.
4.0 General Information The Security Force's responsibilities in the event of a i fire, disaster, or radiological emergency are as follows: t I
EP-205-1 Rev. 0.B Page 2
- 1. Providing in-plant access control for Emergency Response Teams into areas to which they normally do not have access (special access).
- 2. Controlling owner-controlled area access.
- 3. Maintaining proper security in event of a Security Emergency.
- 4. Accounting for personnel in the event of a Plant Area Evacuation, a Protected Area Evacuation, or a Site Area Evacuation.
- 5. Providing alternate communications and back-up assistance for the Emergency Response Team at the scene.
5.0 Immediate Actions 5.1 The Central Alarm Station (CAS) Operator shall: 5.1.1 Notify all Members of Security Force (MSF) using the radio. 5.1.2 If notified of RERP implementation by the Nuclear Shift Supervisor or Emergency Director, carry out EP-205-2 (Security Force: Control Of In-Plant Access for Emergency Response Personnel). 5.1.3 Monitor the scene of the fire or disaster and the surrounding area by closed circuit television (CCTV) , if possible. 5.1.4 Carry out the procedures in References 2.2 through 2.6 as directed by the Security Shift Lieutenant. 5.2 The Secondary Alarm Station (SAS) Operator shall: 5.2.1 As soon as possible, determine the emergency classification from the Emergency Director or Security Shift Lieutenant. I 1 I
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O EP-205-1 Rev. 0.B Page 3 & .x N (\* x 5.2.2 Di,spatch MSF to: ,a 1.. The OSC is act as Security Coordinator, , see section 5.10
- 2. The TSC, when activated, for ACO (Access Control Officer) duties, see section 5.11
- 3. The EOF, when activated, for ACO duties, see section5.12 5.2.3 If directed by the Nuclear Shift Supervisor or Emergency Director, carry out EP-205-2 (Security Force: Control'of In-Plant Access for Erce,rgency Response Personnel).
5.2<4 Obtain information on entrance points and routes to be followed by off-site response personnel from the communicator in the Control Rodm (or in the TSC, if the TSC has been activated).
- 5.2.5 Determine the number of off-site response- '. +
personnel expected.to arrive. N, ' 5.2.6 -Notify. Corporate Security (the Senior Administrator-Security or his designee), that it may be necessary to activate,off-shift
, security personnel. <
\
5.2.i Direct the Access Control Offic r (ACO) at the 4 i owner-controlled area entrances 'to halt access \ , s-to,the site to all but responding off-site' l emergency response personnel, in accordance ..
}'
with EP-20N-3 (Security Force: Conerol of ' i ./ Site Area Access duc'ing Fire, Disaster;'or Radi logical Emercency). 5.2.8 Di rec t the ACO ab the Security Building to
- haft access to the Protected Area to all but I responding off-site emergency response l personnel,in accordance with EP-205-3 l (Security Force
- Control of Site Area Access
( during Fire, Disaster, or Radiological Emergency). , { 5.2.9 Carry out the procedurjs in Refbrences 2.2 through 2.8 as directed by the Security Shift {s_)x Lieutenant. f
EP-205-1 Rev. 0.B Page 4 5.3 The Security shift Lieutenant shall: 5.3.1 Report to the SAS and then, if the TSV is activated, in the absence of the Nuclear Security Chief proceed to the TSC, or other designated location, as directed by the Emergency Director until relieved by the Nuclear Security Chief or his alternate. 5.3.2 Verify with the SAS operator that a fire, disaster, evacuation, or radiological emergency has occurred. 5.3.3 Contact che Emergency Director. 5.3.4 Determine the status of the emergency from the Emergency Director, specifically with regard to the following:
- 1. The classification of the Emergency (Unusual Event, Alert, Site Area Emergency, General Emergency).
- 2. If Emergency Response Teams are activated and will require access to plant areas for which special access is required.
- 3. If the incident has caused or could cause loss or degradation of security systems hardware, (as for example, due to fire, flooding, steam leak, etc. or due to Emergency Response Team efforts to control the incident).
- 4. If there are hazards to personnel (radioactive contamination, radiation, smoke, fire, dangerous chemicals, damaged or unsafe equipment, electrical hazards, steam, leaking high pressure liquid or gas, etc.).
- 5. If any type of evacuation has been ordered or is planned (Plant Area, Protected Area, or Site Area).
O
(V s EP-205-1 Rev. 0.B Page 5
- 6. If off-site emergency response personnel are expected to arrive on-site, such as ambulance team, local volunteer fire department, medical support personnel, or off-site Radiological Emergency Teams.
- 7. If authorized government or off-site support personnel are expected to arrive on-site, in addition to those expected to staff the Emergency Operations Facility (EOF), Nuclear Operations Center (NOC),
or designated media briefing location.
- 8. If unauthorized members of the public or news media personnel are expected to arrive at the site.
5.3.5 Determine if off-site assistance is necessary and request support from the Corporate Security Management (the Senior Administrator-3 Security or his designee). Personnel may be 2 required to support the following:
- 1. Escorts for both owner-Controlled Area facilities and Protected A:ea facilities.
- 2. Traffic control for an evacuation.
- 3. Traffic control for on-site access for Emergency Response Personnel.
5.4 The Security Shift Lieutenant shall assign Members of the Security Force (MSF) as necessary to carry out Security Force functions. Direct personnel to carry out the following, as applicable: 5.4.1 If Emergency Response Teams require access to plant areas for which special access is required, direct the SAS Operator and the CAS Operator to carry out EP-205-2 (Security Force: Control of In-Plant Access for Emergency Response Personnel) . Emergency Response Teams which may be activated include the following: -
- 1. On-site Radiological Emergency Team
- 2. Personnel Monitoring Team (x-'/) 3. Fire Brigade
- 4. Damage and Rescue Team
EP-205-1 Rev. 0.B Page 6 5.4.2 If a loss or degradation of security system hardware occurs, direct the MSF to carry out EP-205-4 (Security Force: Security Emergency during Fire, Disaster, or Radiological Emergency). If the efforts of Emergency Response Teams are hampered by restricted access, it may be necessary to direct "open access". 5.4.3 Supervise the admission of responding off-site personnel and direct MSF to admit authorized personnel, in accordance with EP-205-3 (Security Force: Control of Site Area Access during Fire, Disaster, or Radiological Emergency), if any of the following occur:
- 1. Off-site emergency response personnel are expected to arrive.
- 2. The event is classified as a Site Area Emergency or General Emergency (the EOF is expected to be staffed).
- 3. Authorized government or off-site support personnel are expected to arrive on-site, in addition to those who will staff the EOF.
Additional off-shift security force personnel may be necessary. 5.4.4 If authorized persons or news media personnel are expected to arrive at the NOC:
- 1. Supervise access to the owner-Controlled Area. (If the EOF is activated, the Senior Administrator-Security will assist with access to the Owner-Controlled Area.)
- 2. Direct MSF to control access in accor-dance with EP-205-3 (Security Force:
Control of Site Area Access during Fire, Disaster, or Radiological Emergency). O
' EP-205-1 Rev. 0.B Page 7 5.4.5 If a Plant Area Evacuation is required:
- 1. Direct the CAS or SAS Operator to account for personnel, in accordance with EP-205-30 (Security Force: Evacuation) and to report the results to the Security Shift Lieutenant.
I l 2. Immediately report the names and last known location of any missing personnel to the Emergency Director. If the TSC is activated, report to the Security i Advisor. I 5.4.6 If a Protected Area Evacuation is required:
- 1. Direct the CAS or SAS operator to account for personnel in the plant, in accordance with EP-205-30 (Security Force:
Evacuation), and to report the results to the Security Shift Lieutenant.
- 2. Direct the ACO's at the Security Building (primary access portal) and Warehouse 19 (alternate access portal) to account for personnel, in accordance with EP-205-30 (Security Force: Evacuation), and to report the res'ults to the SAS Operator and the Security Shift Lieutenant.
- 3. Immediately report the name's and last known location of any missing personnel to the Emergency Director. If the TSC is activated, report information to the Security Advisor.
5.4.7 If a Site Area Evacuation occurs:
- 1. Direct the CAS or SAS Operator to account
' for personnel in the plant, in accordance l with EP-205-30 (Security Force: Evacuation), and to report the results to the Security Shift Lieutenant.
- 2. Direct the ACO at the owner-controlled l
-area access to account for personnel, in accordance with EP-205-30 (Security l
l Force: Evacuation), and to report the l['- results to the SAS Operator and Security Shift Lieutenant.
i EP-205-1 Rev. 0.B Page 8
- 3. Immediately report the names and last known location of any missing personnel to the Emergency Director. If the TSC is activated, report information to the Security Advisor.
- 4. Notify Corporate Security (the Senior Administrator-Security or his designee) that it may be necessary to activate off-duty security personnel.
5.5 When the TSC is activated, the TSC Security Advisor shall: 5.5.1 Contact SAS for an update on the emergency and ascertain security requirements. 5.5.2 Assist the Emergency Director with security matters,as necessary, to include the following:
- 1. Ensure adequate MSF are available for the emergency.
- 2. Maintain Access Control &
Personnel Accountability for the protected and vital areas.
- 3. Verify security related emergencids and/or escorts.
- 4. Provide the Emergency Director with necessary information concerning security and personnel accountability, as necessary.
- 5. Provide access clearance into the protected area for essential personnel.
- 6. Control access into the TSC.
O
O G EP-205-1 REV. 0.B Page 9
- 7. Update the EOF Security Advisor, if EOF is activated, as needed, Notify the Senior Administrator-Security of any developments or assistance required, if EOF is not activated.
5.6 If the EOF is activated, the EOF Security Advisor shall: 5.6.1 Contact the SAS operator for information required and update on the emergency and security requirements 5.6.2 Contact the TSC Security Advisor for update on the emergency. 5.6.3 Ensure adequate MSF available for emergency (TSC, EOF, OSC, JPIC, etc.) ( 5.6.4 Provide information to the Public Affairs Coordinator at the EOF, regarding security matters, injuries, etc. 5.6.5 Maintain access control to the owner-controlled area:
- 1. Assist EOF Coordinator with entry authorizations for essential personnel and material.
- 2. Assist TSC Security Advisor with entry requirements to the owner-controlled area for essential personnel and material going to the protected area.
5.6.6 Obtain entry clearance through road-blocks for esser.tial personnel and material required at the site. 5.6.7 Provide MSF escorts, as necessary, for materials or people from off-site (e.g., airports, adverse weather conditions). O -
EP-205-1 Rev. 0.B Page 10 5.6.8 Verify security related incidents during the emrgency. 5.6.9 Provide for off-site contacts with families of injured employees, contact hospitals for follow-up information,.etc. 5.6.10 Control access into the EOF. 5.6.11 Update the Director-Security on the emergency and security requirements, as necessary. 5.7 The ACO as the site entrance shall: 5.7.1 When directed by the SAS Operator, halt access to the site to all but responding off-site emergency response groups. 5.7.2 Carry out the procedures in References g 2.2 through 2.6 as directed by the SAS T Operator or the ShiftLieutenant. 5.8 The ACO at the Security Building (primary access portal) shall: 3.8.1 When directed by the SAS Operator, halt access to the Protected Area to all but responding off-site emergency response groups. 5.8.2 Carry out the procedures in References 2.2 through 2.6 as directed by the SAS Operator or theshift Lieutenant. 5.9 The ACO at Warehouse 19 (alternate access portal) shall: 5.9.1 When directed by the SAS Operator, halt access to the Protected Area to all but responding off-site emergency response groups. 5.9.2 Carry out the procedures in References 2.2 through 2.6 as directed by the SAS Operator or the Shift Lieutenant. i I i
) EP-205-1 Rev. 0.B Page 11 5.10 The OSC Security Coordinator shall:
5.10.1 Assign Response Force Members as escorts to in-plant teams (fire brigade, R.E.T., etc.) as necessary. 5.10.2 Advise SAS on dispatch of teams and who is assigned as escorts 5.10.3 Assist in coordinating activities between Security and the OSC. 5.11 The ACO at the TSC shall: 5.11.1 Control access of authorized personnel to the TSC, when activated. An access list is provided for this purpose. 5.11.2 Issue appropriate badges to personnel on arrival. (O) 5.11.3 Have personnel sign in on log upon entry and sign out, upon departure. 5.11.4 Assist the Security Advisor, as necessary. 5.12 The ACO at the EOF shall: 5.12.1- Control access of authorized personnel to the EOF, when activated. An access list is provided for this purpose. 5.12.2 Issue appropriate badges to personnel on arrival. 5.12.3 Have personnel sign-in upon entry and sign-out upon departure. 5.12.4 Assist the Security Advisor, as necessary.
EP-205-1 Rev. 0.B Page 12 6.0 Follow-up Actions 6.1 The Security Shift Lieutenant shall: 6.1.1 After conferring with the Emergency Director, determine if the incident is security-related. If it is not security-related, establish "All Clear". 6.1.2 If the incident is determined to be security-related, direct MSF to carry out the steps of Security Force: Security Emergency during Fire, Disaster, or Radiological Emergency (EP-205-4). 6.1.3 If an evacuation is directed, report to the Emergency Director as soon as all personnel are accounted for. 6.2 The CAS Operator shall: 6.2.1 If the Security Shift Lieutenant determines that the incident is not security-related, announce "all clear" to all security personnel. 6.2.2 If the incident is determined to be security-related, carry out EP-205-4 (Security Force: Security Emergency during Fire, Disaster, or Radiological Emergency). 6.3 The SAS Operator shall: 6.3.1 If the incident is determined to be security-related, carry out EP-205-4 (Security Force: Security Emergency l during Fire, Disaster, or Radiological l Emergency). l 6.4 All MSF shall: l l 6.4.1 If it is determined that the incident is l not security related, receive the "All Clear" report from the CAS operator, and acknowledge the report. END I I
1 EP-205-2 l Rev. 0.B ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 1 i Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
SECURITY FORCE: CONTROL OF IN-PLANT ACCESS FOR EMERGENCY RESPONSE PERSONNEL 1 RECORD OF APPROVAL D CHANGES i Submitted by (^'s Supervisor of R ol5gical Emergency Date Response Prep, ss Approved by } Chairman - Liaison Committee Date { Liaison i Revision Committee No. Submitted Date Approval. Date 1
- 2 i
i 4 5 6 7 4-l 8 l l f l ($) l l
4 i i i 1 i I l EP-205-2 Rev. 0.B I 1 I i I ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
SECURITY FORCE: CONTROL OF IN-PLANT ACCESS FOR EMERGENCY RESPONSE PERSONNEL l
l 1 I p EP-205-2 h Rev. 0.B , j SECURITY FORCE: CONTROL OF IN-PLANT ACCESS FOR EMERGENCY RESPONSE PERSONNEL TABLE OF CONTENTS Page 1.0 Purpose.............................................. 1 2.0 References........................................... 1 3.0 Entry Conditions..................................... 1 4.0 General Information.................................. 1 5.0 Immediate Actions.................................... 2 j 6.0 Follow-up Actions.................................... 3 i 4 } I I l f t
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EP-205-2 Rev. 0B Page 1 1.0 Purpose To prescribe the actions to be performed by the Security Force to control in-plant access for Emergency Response personnel. 1 2.0 References 2.1 Enrico Fermi Atomic Power Plant Unit 2 Radiological Emergency Response Plan, Section B (On-Site Emergency Organization) and Section J (Protective Response). 2.2 Enrico Fermi - Unit 2 Contingency Plan Implementing Procedures. 2.3 Security Force: Response for Fire, Disaster, or Radiological Emergency (EP-205-1). 2.4 Security Force: Security Emergency during Fire, Disaster, or Radiological Emergency (EP-205-4). 3.0 Entry Conditions The Nuclear Shift Supervisor, Emergency Director, or Security Shift Lieutenant directs that the Security Force provide in-plant access for Emergency Response Teams to areas for which they normally do not have access (special access). 4.0 General Information 4.1 It is essential that the efforts of Emergency ! Response Teams in controlling an emergency not be hampered by restricted access. Prohibiting an ! Emergency Team's ability to properly function can j result in loss of life, serious injury, or excessive damage to equipment. 4.2 The steps of this procedure assume that no loss or degradation of security system hardware has occurred. If loss or degradation of security system hardware occurs, carry out EP-205-4 (Security i Force: Security Emergency during Fire, Disaster, or Radiological Emergency) to properly respond to the Security Emergency and to control in-plant access for i emergency response personnel.
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EP-205-2 Rev. 0.B Page 2 5.0 Immediate Actions 5.1 The Secondary Alarm Station (SAS) Operator shall: 5.1.1 Direct the Access Control Officer (ACO) at tLe Security Building (primary access portal) to halt access to the Protected Area to all but authorized responding personnel. 5.1.2 On-Site Emergency Response Teams which may be activated include the following:
- 1. On-Site Radiological Emergency Team.
- 2. Perscnnel Monitoring Team.
- 3. Fire Brigade.
- 4. Damage and Rescue Team.
5.1.3 Enter the names of On-Site Emergency Response personnel into the computer data base as necessary to ensure proper access for Team members. 5.1.4 Off-Site Emergency Response personnel which may be activated include the following:
- 1. Frenchtown Volunteer Fire Department.
- 2. Ambulance.
- 3. Local law enforcement agency (LLEA).
- 4. Medical support personnel.
5.1.5 Check the names of Off-Site Emergency Response personnel against the master list for that group of personnel. Enter only the names of personnel who have actually arrived on-site into the computer data base. If a person's name does not appear on the master list, he must be escorted by a Member of the Security Force (MSF). If time is critical (lives are in jeopardy or extensive equipment damage is imminent) record only the vehicle and number of personnel assigned, e.g., " Fire truck 731 with 7 personnel." 5.1.6 Provide escort officers as necessary for Off-Site Emergency Response personnel, and enter the escorts' names with the response personnel into the computer data base.
O V EP-205-2 Rev. 0.B Page 3 5.1.7 As soon as it has been completed, inform the Emergency Director that the names of Team members have been entered into the data base. Notify the Security Advisor at the TSC and EOF when activated. 5.1.8 Inform the Security Shift Lieutenant and Corporate Security (Senior Administrator-Security or his designee) of the Teams being authorized special access as soon as they have been entered into the computer data base. 5.2 The Central Alarm Station (CAS) Operator shall concur with the access request as entered into the data base by the SAS operator. 6.0 Follow-up Actions 6.1 The SAS Operator shall: /"N \ 6.1.1 Verify with the Emergency Director when the need for special access for On-Site or Off-Site Emergency Response Teams is no longer required. If the TSC is activated, verify through the Security Advisor. 6.1.2 When the need for On-Site Emergency Response Team special access is no longer required, remove the names of the members of the Team from the computer data base. 6.1.3 When the need for Off-Site Emergency Response personnel special access is no longer required, remove the name of the MSF escort with the Team from the computer data base. This action will deactivate the access for that Team. 6.1.4 Be prepared to reenter names of On-Site Emergency Response Teams into the computer data base, as directed by the Emergency Director, as it may be necessary to reactivate a Team. 6.1.5 Upon departure of Off-Site Emergency Response personnel, ootain the names, dosimeter, TLD, (~N and badge numbers of the group members if time ( ,) had not permitted this action to be performed
EP-205-2 Rev. 0.B Page 4 earlier. Collect all TLD's and dosimeters and forward them to the Health Physics Supervisor for processing. 6.1.6 Remove the names of Off-Site Emergency Response personnel from the computer data base. 6.2 The CAS Operator shall concur with changes in special access as requested by the SAS Operator. O END O
g' EP-205-3
- Rev. 0.B ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
SECURITY FORCE: CONTROL OF SITE AREA ACCESS DURING FIRE, DISASTER, OR RADIOLOGICAL EMERGENCY RECORD OF APPROVAL AND CHANGES Submitted by 4 Supervisor of Radiological gency Date Response Preparedness Approved by jk Chairman - L p ' Committee Date Liaison () Revision Committee No. Submitted Date Approval Date 1 2 3 4 5 l 6 l 7 . 8 i i i
EP-205-3 Rev. 0.B i l ENRICO FERMI ATOMIC POWER PLANT i UNIT NO. 2 , Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
SECURITY FORCE: CONTROL OF SITE AREA ACCESS DURING FIRE, DISASTER, OR RADIOLOGICAL EMERGENCY l O
_. __ _ _ = _ _ . _ 1 4 EP-205-3 Rev. 0.B SECURITY FORCE: CONTROL OF SITE AREA ACCESS DURING FIRE, DISASTER OR RADIOLOGICAL EMERGENCY TABLE OF CONTENTS Page .; 1.0 Purpose ............................................... 1 2.0 References ............................................ 1 3.0 Entry Conditions ...................................... 1 4.0 General Information ................................... 1 5.0 Immediate Actions ..................................... 2 6.0 Follow-up Actions ..................................... 7 t h i i l l 4 i i 1 i
J EP-205-3 Rev. 0.B Page 1 1.0 Purpose To prescribe the actions to be performed by the Security Force to control access to the Owner-Controlled Area or the Protected Area during fire, disaster, or radiological emergency. 2.0 References 2.1 Enrico Fermi Atomic Power Plant Unit 2 Radiological Emergency Response Plan, Section B (On-site Emergency Organization) and Section J (Protective Response). 2.2 Enrico Fermi - Unit 2 Contingency Plan Implementing Procedures. 2.3 Security Force: Response for Fire, Disaster, or Radiological Emergency (EP-205-1). 7, 3.0 Entry Conditions Any of the following occur: i
- 1. Off-site emergency response personnel are expected to arrive at the site (ambulance team, medical support personnel, the local fire department, Off-Site Radiological Emergency Team, etc.).
- 2. An event is classified as a Site Area Emergency or General Emergency (the Emergency Operations Facility (EOF) staff will be expected to arrive on-site).
- 3. Authorized government or off-site support personnel are expected to arrive on-site, in addition to those who will staff the EOF.
- 4. Unauthorized persons are expected to arrive at the site (including news media personnel).
4.0 General Information 4.1 The Security Force's responsibility in controlling access to the Owner-Controlled Area or the Protected Area during fire, disaster, and radiological emergency is to restrict access except for personnel who are part of the Emergency Response Organization O or are providing support for emergency response efforts.
EP-205-3 Rev. 0.B Page 2 4.2 Access for members of the press and of the general public is authorized, by the Security Liaison (Senior Administrator-Security, or his alternate), with concurrence of the Emergency Director, if the EOF is activated. Authorization is made by the Emergency Director if the EOF is not activated. Such access will be limited to the NOC, and to controllable, supervised groups under the cognizance of the Director of Public Information or his representative. 5.0 Immediate Actions 5.1 The Secondary Alarm Station (SAS) Operator shall: 5.1.1 As soon as possible, determine the emergency classification from the Emergency Director or Security Shift Lieutenant, or Security Advisor at the TSC, if activated. 5.1.2 When notified of RERP implementation by the Nuclear Shift Supervisor or Emergency Director, carry out EP-205-2 (Security Force: Control of In-Plant Access for Emergency Response Personnel). 5.1.3 Notify Corporate Security (the Senior Administrator-Security or his designee), if it is necessary to activate any off-duty security personnel. 5.1.4 Direct the Access Control Officer (ACO) at the owner-controlled' area entrances to halt access to the site to all but responding off-site emergency response personnel. Ensure traffic does not inhibit Emergency Response personnel from accessing the site. It may be necessary to obtain assistance from the local law enforcement agency (LLEA) or additional Security Force Personnel in controlling traffic. 5.1.5 Direct the ACO at the Security Building (primary access portal) to halt access to the Protected Area to all but responding off-site emergency response personnel and personnel authorized by the Nuclear Shift Supervisor or Emergency Director.
O EP-205-3 Rev. 0.B Page 3 l 5.1.6 Direct the ACO at Warehouse 19 (alternate access portal) to halt access to the Protected Area to all but responding off-site emergency response personnel and personnel authorized by the Nuclear Shift Supervisor or Emergency Director. 5.1.7 If off-site emergency response groups are expected to arrive (master lists will show the names of ambulance team members, medical support personnel, the local volunteer fire department personnel, Off-Site Radiological Emergency Team members, etc.):
- 1. Estimate time of arrival of off-site assistance groups. Notify the appro-priate ACO and the Security shift Lieutenant of the number of personnel expected, expected entry points, and travel routes when on-site.
(_) 2. Assign Members of the Security Force (MSF) as escorts for off-site emergency response groups. Direct the escorts to proceed to the appropriate site entrance gate, escort the group for badge issue, and then escort the group to the scene of the emergency.
- 3. When the ACO at the Owner-Controlled Area access gate reports the arrival of any Off-Site Emergency Response personnel, issue badges and enter the badge numbers into the computer data base. If time is critical (lives are in jeopardy or extensive equipment damage is imminent) record only the vehicle and number of personnel, e.g., " Fire truck 731 with 7 personnel".
- 4. Notify the Emergency Director (through TSC Security Advisor if TSC is activated) and Security Shift Lieutenant as off-site emergency response groups arrive.
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EP-205-3 Rev. 0.B Page 4
- 5. Inform Corporate Security (the Senior Administrator-Security or his designee) that special access has been authorized for Off-Site Emergency Response Teams.
5.1.8 If the event is classified by the Emergency Director as a Site Area Emergency or General Emergency (the EOF staff will be expected to arrive on-site), or if authorized government or off-site support personnel are expected to arrive on-site (in addition to those who will staff the EOF):
- 1. Request assistance from the Security Shift Lieutenant in obtaining escorts.
- 2. Assign MSF as escorts for arriving personnel. Direct the escorts to escort personrel to their destination.
5.1.9 If unauthorized persons are expected to arrive or have arrived at the site (including news media personnel):
- 1. Inform the Security Shift Lieutenant, Security Liaison (Senior Administrator-Security, or his alternate), if the EOF is activated, and the Emergency Director, through the TSC Security Advisor (if the TSC is activated).
1 l 2. Verify that the Director of Public Information has been notified. i 3. Order the ACO at the owner-controlled area entrances to direct all un-authorized persons to the Monroe Community College (Joint Public Informa-i tion Center or an alternate facility if the JPIC is not activated). The Director of Public Affairs or his representative will coordinate with the Senior Administrator-Security, or his alternate, on-site access for news media personnel and the general public. O
\_/ EP-205-3 Rev. 0.B Page 5
- 4. If a Public Affairs representative arranges for the supervised escort of otherwise unauthorized persons, obtain authorization for their entry from the Security Liaison (Senior Administrator-Security, or his alternate), if the EOF is activated. If the EOF is not activated, then obtain authorization from the Emergency Director.
- 5. If authorization for their entry is given, determine the number of personnel, assign MSF as escorts, inform the appropriate ACO's, and inform Corporate Security (Senior Administrator-Security or his designee). Direct the escorts to escort the personnel to the Near-Site News Center.
5.2 ACO's at the owner-controlled area entrances shall: 5.2.1 When directed by the SAS operator, halt access to the site to all but responding off-site emergency response groups. 5.2.2 Ensure a traffic back-up does not occur and inhibit the access to the site by necessary Emergency Response personnel. It may be necessary to obtain assistance from the LLEA or additional Security Force personnel to control traffic. 5.2.3 For responding off-site emergency response groups (ambulance team, fire department, off-site medical support group, Off-Site Radiological Emergency Team, etc.):
- 1. Inform the Security Shif t Lieutenant and SAS Operator of the number and names of responding personnel upon their arrival.
- 2. Prepare TLD's for all off-site emergency l response personnel and issue access badges.
- 3. Ensure that MSF escort the group to the i Security Building or to the scene of the s/ emergency.
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EP-205-3 Rev. 0.B Page 6 5.2.3 For EOF staff personnel, authorized govern-ment, or off-site support personnel:
- 1. Provide the SAS Operator with the number and names of personnel upon their arrival.
- 2. Ensure that MSF escort the personnel to the NOC.
5.2.4 For unauthorized persons (including news media personnel):
- 1. Inform the SAS operator.
- 2. Direct all unauthorized persons to the Monroe Community College (Joint Public Information Center or an alternate location if the JPIC is not activated).
Inform them that a Public Affairs representative will coordinate access for personnel on to the site.
- 3. Notify the SAS Operator if a group of unauthorized persons arrives in the company of an escorting Public Affairs Representative. Provide the names of personnel.to the SAS Operator. Detain them until cleared for access.
- 4. If authorization is received from the SAS ensure that MSF escort the personnel to the designated media briefing location.
5.3 The ACO at the Security Building (primary access portal) shall: l l 5.3.1 When directed by the SAS Operator, halt access to the Protected Area to all but responding emergency response groups. 5.3.2 For responding off-site emergency response groups (ambulance team, fire department, off-site medical support groups, Off-Site Radiological Emergency Team, etc.): O
/
Ot EP-205-3 Rev. 0.B Page 7
- 1. Inform the SAS Operator of the number and the names of personnel upon their arrival.
- 2. Ensure TLD's, access badges, and dosi-meters have been issued to all personnel.
If they have not, issue TLD's, access badges, and dosimeters.
- 3. Ensure that MSF escort the group to the scene of the emergency.
5.4 Security Force Escorts shall: 5.4.1 Escort off-site emergency support personnel for badge issue, and ther. to the scene of the emergency, as directed by the SAS Operator. 5.4.2 Escort authorized government or off-site support personnel as directed by the SAS I"h Operator or the Senior Administrator-Security kls or his designee. 5.4.3 Escort normally unauthor'ized personnel, supervised by a Public Affairs Representative,
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to the designated media briefing location, as directed by the SAS Operator or the Security Liaison (Senior Administrator-Security or his designee), if the EOF is activated. 6.0 Follow-Up Actions 1 6.1 The SAS Operator shall ensure all Off-Site Emergency Response personnel leave the areas for which they were authorized access. 6.2 Upon departure of Emergency Response group personnel, obtain the names and TLD badge numbers of the group members if time had not permitted this action to be performed earlier. 6.3 The ACO at the Owner-Controlled Area access gate t shall collect TLD's and record the persons' names l upon their departure, if their names had not been recorded earlier. t l O L
EP-205-3 Rev. 0.8 Page 8 6.4 The ACO's at the Security Building (primary access portal) and Warehouse 19 (alternate access portal) shall collect TLD's and dosimeters and record the persons' names upon their departure if their names had not been recorded earlier. O i END 9
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EP-205-4s Y Rev. 0.B' ENRICO FERM5 ATOMIC POWER PLAMSj UNIT NO. 2 I . Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
SECURITY FORCE: SECURITY EMERGENCY DURING FIRE, DISASTER, OR RADIOLOGICAL EMERGENCY r. RECORD OF APPROVAL AND CHANGES s, Submitted by " Supervisor of Radiologi Akinergency ' Date Response Preparednes
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EP-205-4 Rev. 0.B i ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
SECURITY FORCE: SECURITY EMERGENCY DURING FIRE, DISASTER, OR RADIOLOGICAL EMERGENCY O 4 I I
. - - - - - , , . - - , - . . - _ - - - , - - . _ -- - . . - . - - - - - - - - - - - , - - , - - - - - - - - - - - - - - - , - - - - -- ~
a I l t l EP-205-4
) Rev. 0.B SECURITY FORCE: SECURITY EMERGENCY DURING FIRE, DISASTER, OR RADIOLOGICAL EMERGENCY I
. TABLE OF CONTENTS
- Page i
) 1.0 Purpose ............................................... 1 2.0 References ............................................ 1 ] 3.0 Entry Conditions ...................................... 1 l
j 4.0 General Information ................................... 1 5.0 Immediate Actions ..................................... 2 , 1
- 6.0 Follow-up Actions ..................................... 6 ;
i l, 5 l i i i s f i I i
EP-205-4 Rev. 0.B Page 1 1.0 Purpose To prescribe the actions to be performed by the Security Force in event of a security emergency during fire, disaster, or radiological emergency. 2.0 References 2.1 Enrico Fermi Atomic Power P'lant Unit 2 Radiological Emergency Re'sponse Plan, Section B (On-Site Emergency Organization) and Section J (Protective Response). 2.2 Enrico Fermi-Unit 2 Contingency Plan Implementing Procedures. 2.3 Security Force: Response for Fire, Disaster, or Radiological Emergency (EP-205-1). 2.4 Security Force: Control of In-Plant Access for Emergency Response Personnel (EP-205-2).
) 2.5 Use of Protective Clothing (65.000.10).
2.6 Selection and use of Respiratory Protection Equipment (65.000.20). 3.0 Entry Conditions A security emergency occurs during a fire, disaster, or radiological emergency. 4.0 General Information 4.1 A security emergency during a fire, disaster, or radiological emergency is controlled as delineated in CPIP-2 (Enrico Fermi-Unit 2 Contingency Plan Implementing Procedures), however, existing hazards i may require additional protection for Secur'ity Force personnel. 4.2 It is essential that the efforts of Emergency Response Teams in controlling the emergency not be hampered by restricted access. Loss or degradation of security system hardware could prohibit an Emergency Team's ability to properly function. This could result in loss.of life, serious injury, or excessive damage to equipment. O
EP-205-4 Rev. 0.B Page 2 5.0 Immediate Actions 5.2 The Central Alarm Station (CAS) Operator shall carry out CPIP-2 (Enrico Fermi-Unit 2 Contingency Plan Implementing Procedure) for a Security Emergency. 5.3 The Secondary Alarm Station (SAS) Operator shall carry out CPIP-2 (Enrico Fermi-Unit 2 Contingency Plan Implementing Procedure) for a Security Emergency. 5.1 The Security Shift Lieutenant shall: 5.1.1 Declare a Security Emergency when the situation becomes degraded to the point that it qualifies, in his judgment, as a Security Emergency. 5.1.2 Notify the Nuclear Shift Supervisor or the Emergency Director of the Security Emergency through the TSC Security Advisor (if the TSC is activated). 5.1.3 Establish and monitor communications with the CAS Operator, and coordinate the Members of the Security Force (MSF) response to the Security Emergency. If necessary, direct the SAS Operator to call for local law enforcement agency (LLEA) assistance. 5.1.4 Verify that the proper personnel on the noti-fication list have been contacted. Direct any notifications to be made that have not as yet been completed. 5.1.5 Ensure that any Security Response Force personnel proceeding to investigate the emergency have adequate protective clothing and respiratory equipment and take proper precautions:
- 1. In the event of a fire, direct the OSC Security Coordinator to contact the OSC Coordinator and determine, from the Fire Brigade Leader, what protective clothing or respiratory equipment is necessary and to obtain the necessary O
O EP-205-4 Rev. 0.B Page 3 equipment. If Security Response Force members must enter a fire area, direct them to report to the Fire Brigade Leader at the scene of the fire prior to entering the fire area.
- 2. In the event of personnel hazards due to an explosion, toxic chemical release, or other disaster (damaged or unsafe equip-ment, dangerous chemicals, electrical hazards, steam, leaking high pressure fluid or gas, etc.), direct the OSC Security Coordinator to contact the OSC Coordinator and determine from the Damage and Rescue Team Leader what protective clothing or respiratory equipment is necessary and have the escorts obtain the necessary equipment. If Security Response Force members must enter an area
. where,a hazard exists (as listed above),
direct them to report to the Damage and Rescue Team Leader or Scene Leader at the scene of the emergency prior to entering the area. 3.- In the event of a radiological hazard, direct the OSC Security Coordinator to contact the CSC Coordinator and determine from the On-Site Radiological Emergency Team (On-Site RET) Leader what protective clothing, respiratory equipment, or dosimetry is necessary and to have the escorts obtain the necessary equipment. If Security Response Force members must i enter an area where a radiological hazard exists, direct them to report to the On-Site RET Leader or Scene Leader at the scene of the emergency prior to entering the area. , 5.1.6 If the Security Emergency involves loss or l degradttion of security system hardware ensure
- that in-plant access for Emergency Teams is not impeded.
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EP-205-4 Rev. 0.B Page 4
- 1. If necessary, declare "open access".
- 2. If necessary, provide MSF to escort Emergency Response Teams into plant areas. The Escorts are responsible for accountability of the group they escort and for proper security of all areas entered. Escorts should have proper protective clothing, respiratory equip-ment, and dosimetry as outlined for MSF in step 5.3.4 above. They should initially report to the Emergency Team or Scene Leader at the scene of the emergency.
5.1.7 If suspects are found by the MSF, follow the appropriate apprehension guidance of Contingency Plan Implementing Procedures. 5.1.8 Direct additional MSF to continue the search and investigation to ensure additional suspects are not on the site. Search all suspected areas for evidence of sabotage, sabotage devices, or suspects. If no addi-tional suspects or sabotage are discovered, search efforts may be terminated as indicated in Contingency Plan Implementing Procedures. 5.1.9 Advise the CAS and SAS operators of progress and coordinate reports of the Security Response Force. 5.1.10 If off-site response personnel are called, meet and brief the off-site response leader on the situation. Ensure TLD's and appropriate access badges are issued to assisting personnel. 5.1.11 Direct MSF and site personnel to assist the LLEA. 5.4 The Security Response Force members shall: 5.4.1 When the Security Emergency is called, acknowledge the emergency by responding in order.of assignment code (unless otherwise directed) to the SAS, by radio, phone, or personal contact with the SAS.
EP-205-4 Rev. 0.B Page 5 5.4.2 Determine the necessary protective equipment, respiratory equipment, and dosimetry, as directed by the Security Shift Lieutenant or Security Response Force Leader (SRFL) (this will involve contacting the Fire Brigade Leader, Damage and Rescue Team Leader, or On-Site Radiological Emergency Team Leader). 5.4.3 Obtain equipment, if required, and take stations as directed by the Security shift Lieutenant or SRFL. 5.4.4 Take action as necessary to control the event.
- 1. If it is necessary to enter a fire area, report to the Fire Brigade Leader at the scene of the emergency prior to entering the area.
- 2. If it is necessary to enter a hazard area with damaged or unsafe equipment, Os dangerous chemicals, electrical hazards, steam, leaking high pressure fluid or gas, etc., report to the Damage and Rescue Team Leader or Scene Leader at the scene of the emergency prior to entering the area.
- 3. If it is necessary to enter an area with radiological hazards, report to the On-Site RET Leader or Scene Leader at the scene of the emergency prior to entering the area.
5.4.5 Apprehend suspects as directed by the Security Shift Lieutenant and isolate the affected area as directed in the Contingency Plan Implementing Procedures. 5.4.6 Investigate affected areas as directed by the Security Shift Lieutenant, the SRFL, or the CAS Operator, in that order. Report to the Security Shift Lieutenant or SRFL the results of the investigation. The CAS or SAS Operator will monitor calls and relay information to the Security Shift Lieutenant, as necessary. O V I
EP-205-4 Rev. 0.B Page 6 5.4.7 When requested by the SAS Operator, act as escorts for off-site response groups. Provide TLD's to assistance personnel when required. 5.4.8 If suspects are apprehended, escort the suspects to the Security Building or other designated location and transfer custody to Security Shift Lieutenant. 5.4.9 If security related equipment is sabotaged or damaged, report the findings to the SAS Operator. Monitor the areas as assigned until repairs or adjustments are made. 5.4.10 Provide alternate communications and back-up support for Emergency Response Teams. 5.5 Security Force Escorts shall: 5.5.1 Determine appropriate protective clothing, respiratory equipment, and dosimetry as directed by the Security Shift Lieutenant or SRFL. 5.5.2 Obtain necessary equipment, if required. 5.5.3 Report to the Emergency Team Leader or Scene Leader at the scene of the emergency. 5.5.4 Supervise entrance and exit of Emergency Team personnel. The Security Escort shall be l responsible for accountability of the group being escorted and for proper security of all areas entered. 6.0 Follow-up Actions 6.1 The Security Shift Lieutenant shall: 6.1.1 After receiving a report of damaged security equipment from the SAS operator, advise the Emergency Director and request repairs as necessary, through the TSC Security Advisor (if the TSC is activated). l 6.1.2 If possible assign MSF to perform the function j of degraded equipment. Ensure that the MSF
- assigned have adequate protective clothing, l respiratory equipment, and dosimetry.
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O EP-205-4 Rev. 0.B Page 7 6.1.3 Ensure all off-site response personnel leave the areas to which they were granted access. 6.1.4 After concurrence with the Emergency Director, declare an "All Clear." Direct the CAS Operator to announce an "All Clear". 6.1.5 Return to normal security operations. 6.2 The Members of the Security Force shall: 6.2.1 Collect the TLD's from off-site response force personnel, record names, and badge numbers and forward TLD's to the Supervisor Health Physics for processing. 6.2.2 When an "All Clear" is received, acknowledge it with the SAS operator. 6.2.3 Resume normal security operations. () 6.3 The Security Force Escorts shall report to the SAS Operator if Emergency Team personnel are unaccounted for. l l l END
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1 E EP-205-30 (~ Rev. 0.B ENRICO FERMI ATOMIC POWER PLANT . UNIT NO. 2 i Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
SECURITY FORCE: EVACUATION i , RECORD OF APPROVAL AND CHANGES Submitted by O Date i Supervisor of Radiolo ilqgE Emergency Response Preparedne ! Approved by n i Chairman - LiaV on Committee Date Liaison l- Revision Committee No. Submitted Date Approval Date I 1 l i 2 3 4 5 6 7 8 O l l
O EP-205-30 Rev. 0.B ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
SECURITY FORCE: EVACUATION O O
__ _ ._. _._ m_ . _ . __ _ ._ _ _ __ . _ 1 EP-205-30 Rev. 0.B SECURITY FORCE: EVACUATION i TABLE OF CONTENTS ' Page 1.0 Purpose ............................................... 1 2.0 References . . . ......................................... 1 3.0 Entry Conditions .......................................l 4.0 General Information ................................... 1 5.0 Immediate Actions ..................................... 2 5.1 Plant Area Evacuation . . . . ........................ 2 5.2 Protected Area Evacuation ........................ 3 5.3 Site Area Evacuation ............................. 5 Follow-up Actions ..................................... 7 I 6.0 5 I
O EP-205-30 Rev. 0.B Page 1 1.0 Purpose To prescribe the actions to be performed by the Security Force in the event an evacuation is required. 2.0 References 2.1 Enrico Fermi Atomic Power Plant Unit 2 Radiological Emergency Response Plan, Section B (On-Site Emergency Organization) and Section J (Protective Response). , 2.2 Enrico Fermi-Unit 2 Contingency Plan Implementing Procedures. 2.3 Security Force: Response for Fire, Disaster, or Radiological Emergency (EP-205-1). 2.4 Security Force: Security Emergency during Fire, Disaster, or Radiological Emergency (EP-205-4). 3.0 Entry Conditions The Security Force shall follow the guidelines of this procedure whenever an evacuation is ordered by the Nuclear Shift Supervisor or the Emergency Director. 4.0 General Information 4.1 A Plant Area Evacuation is defined as the supervised evacuation of all unnecessary personnel from a specific area of the plant to another designated, safe area inside the Protected Area. 4.2 A Protected Area Evacuation is defined as the supervised evacuation of unnecessary personnel from the Protected Area to Warehouse 19 or the Security Building. 4.3 A Site Evacuation is defined as the supervised evacuation of all unnecessary personnel from any site facility, including but not limited to, the Protected Area, the Visitors Center, the General Training and Orientation Center, and the Nuclear Operations Center to the Newport Warehouse , Monroe Power Plant, and/or Trenton Channel Power Plant. 4.4 The Security shift Lieutenant has the ultimate O responsibility for personnel accountability during an evacuation.
EP-205-30 Rev. 0.B Page 2 4.5 All personnel must be accounted for within 30 minutes of the start of an evacuation. 5.0 Immediate Actions 5.1 In the event of a PLANT AREA EVACUATION, the following steps are to be accomplished: 5.1.1 The Secondary Alarm Station (SAS) Operator shall:
- 1. Determine from the Emergency Director (through TSC Security Advisor, if the TSC is activated) which area of the plant is to be evacuated and the evacuation assembly area.
- 2. Obtain a computer printout of the access list from the affected area within 5 minutes of the start of the evacuation and inform the Emergency Director (through the TSC Security Advisor) if the TSC is activated, which personnel remain in the affected area.
- 3. Determine from the Emergency Director through the TSC Security Advisor, if the TSC is activated, which personnel are authorized to remain in the affected area.
- 4. Contact the Personnel Monitoring Team Leader within 15 minutes of the start of the evacuation and determine if all personnel in the affected area have been accounted for. The Personnel Monitoring Team Leader will either be in the Operational Support Center (OSC) or at the designated assembly area.
- 5. Notify the Security Shift Lieutenant of personnel accountability status.
9
7~ k-m EP-205-30 Rev. 0.B Page 3
- 6. All personnel must be accounted for within 30 minutes of the start of the evacuation. If all personnel who are supposed to have evacuated have not done so within 20 minutes of the start of the evacuation the SAS operator shall notify the Security Shift Lieutenant.
5.1.2 The Security Shift Lieutenant shall:
- 1. Contact the SAS Operator within 20 minutes of the start of the evacuation and ensure that all personnel have been accounted for.
- 2. If any personnel are missing report to the Emergency Director, through the TSC Security Advisor, if the TSC is activated, the names of all missing personnel.
- 3. Recommend to the Emergency Director, through the TSC Security Advisor, if the TSC is activated,the steps necessary to ensure the proper accounting of personnel not accounted for within 20 minutes of the start of the evacuation.
- 4. In the event a Security Emergency is declared during the evacuation carry out EP-205-4 (Security Force: Security Emergency during Fire, Disaster, or Radiological Emergency).
5.2 In the event of a PROTECTED AREA EVACUATION, the following steps are to be accomplished: 5.2.1 The Secondary Alarm Station (SAS) Operator shall: l
- 1. Contact the Emergency Director and verify l
the location of the evacuation assembly l area.
- 2. Obtain a computer printout of all personnel in the Protected Area
~T immediately.
{J
EP-205-30 Rev. 0.B Page 4
- 3. Determine from the Emergency Director, through the TSC Security Advisor, if the TSC is activated, which personnel are authorized to remain inside the Protected Area.
- 4. Compare the computer printout obtained in step 5.1. l(2) with the list of authorized personnel from step 5.1.l(3) and deter-mine how many personnel remain to be evacuated.
- 5. Within 15 minutes of the start of the evacuation obtain a second computer printout and determine which personnel have not yet been accounted for.
- 6. Notify the Security Shift Lieutenant of personnel accountability status.
- 7. All personnel must be accounted for within 30 minutes of the start of the evacuation. If all personnel who are lh supposed to have evacuated have not been evacuated within 20 minutes of the start of the evacuation, the SAS Operator shall notify the Security Shift Lieutenant.
5.2.2 The Access Control Officers (ACO) at the Primary Access Portal (Security Building) and Alternate Access Portal (Warehouse 19) shall:
- 1. Obtain the list of personnel authorized to remain in the Protected Area from the SAS Operator.
- 2. Within 15 minutes of the start of the evacuacion compare the list of personnel authorized to remain in the Protected Area to a list of security badges not yet returned to the Primary Access Portal (Security Building) or Alternate Access Portal (Warehouse 19). Determine if there are any missing personnel.
- 3. Report names of any missing personnel to the SAS Operator.
- 4. Report to the SAS Operator when all personnel are accounted for.
I l
EP-205-30 Rev. 0.B Page 5 5.2.3 The Security Shift Lieutenant shall:
- 1. Contact the SAS Operator within 20 minutes of the start of the evacuation and ensure all personnel have been accounted for.
- 2. If any personnel are missing report to the Emergency Director, through the TSC Security Advisor, if the TSC is activated, the names of all missing personnel.
- 3. Recommend to the Emergency Director, through the TSC Security Advisor, if the TSC is activated, the steps necessary to ensure the proper accounting of personnel not accounted for within 20 minutes of the start of the evacuation.
4. O' In the event a Security Emergency is declared during the evacuation, carry out EP-205-4 (Security Force: Security Emergency during Fire, Disaster, or Radiological Emergency). 5.3 In the event of a SITE AREA EVACUATION, the following steps are to be accomplished: NOTE: Group Leaders from the visitor's Center shall account for all personnel under their control. They shall report the names of any missing personnel to the Visitors Center staff. The Visitors Center staff shall report those names to the Security Shift Lieutenant. Director-Nuclear Training or his alternate shall be responsible for accounting for all personnel from the General Training and Orientation Center. Names of missing personnel shall be reported to the Security Shift Lieutenant. 5.3.1 The Secondary Alarm Station (SAS) Operator shall:
- 1. Contact the Emergency Director, through the TSC Security Advisor, if the TSC is
( s activated, and verify the location of the i evacuation assembly area.
EP-205-30 l Rev. 0.B Page 6 l
- 2. Obtain a computer printout of all personnel in the Protected Area innediately.
- 3. Determine from the Emergency Director, through the TSC Security Advisor, if the TSC is activated, which personnel are authorized to remain on-site.
- 4. Compare the computer printout obtained in step 5.1. l(2) with the list of personnel authorized to remain on-site from step 5.1.l(3) and determine how many personnel remain to be evacuated.
- 5. Within 15 minutes of the start of the evacuation obtain a second computer printout and determine which personnel have not yet been accounted for.
- 6. Contact the Evacuation Assembly Area and obtain a list of personnel who were reported missing from the Visitor's Center and the General Training and Orientation Center from the Personnel Monitoring Group Leader at the assembly area.
- 7. Compare the list of missing personnel from step 6 above to the list from step 2 above of personnel authorized to remain on site. Determine if any personnel are not accounted for.
- 8. Notify the Security Shift Lieutenant of personnel accountability status.
- 9. All personnel must be accounted for within 30 minutes of the start of the evacuation. If all personnel who are supposed to have evacuated have not been evacuated within 20 minutes of the start of the evacuation notify the Security Shift Lieutenant.
5.3.2 The Access Control Officers (ACO) at the owner-controlled area entrances, the Primary & Access Portal (Security Building) and the W Alternate Access Portal (Warehouse 19) shall: I
EP-205-30 Rev. 0.B Page 7
- 1. Obtain the list of personnel authorized to remain on-site from the SAS operator.
- 2. Within 15 minutes of the start of the evacuation, compare the list of authorized personnel with the list of security badges not yet returned to the entrance gates, the Primary Access Portal (Security Building) or the Alternate Access Portal (Warehouse 19). Determine if there are any missing personnel.
- 3. Report the names of all missing personnel to the SAS Operator.
- 4. Report to the SAS Operator when all personnel are accounted for.
5.3.3 The Security Shift Lieutenant shall:
- 1. Contact the SAS Operator within 20 minutes of the start of the evacuation and ensure all personnel have been accounted for.
- 2. Report the names of any missing personnel obtained from the SAS Operator in step 5.3.1 to the Emergency Director, through the TSC Security Advisor, if the TSC is activated.
- 3. Recommend to the Emergency Director, through the TSC Security Advisor, if the TSC is activated. the steps necessary to ensure the proper accounting of personnel not accounted for within 20 minutes of the start of the evacuation.
- 4. In the event of a Security Emergency is declared during the evacuation, carry out EP-205-4 (Security Force: Security Emergency during Fire, Disaster, or Radiological Emergency).
O
EP-205-30 Rev. 0.B Page 8 6.0 Follow-up Actions 6.1 The SAS Operator shall, as time permits, determine the actual location of all personnel authorized to remain in the affected areas. 6.2 The Security Shift Lieutenant shall: 6.2.1 Determine from the Emergency Director, through the TSC Security Advisor, if the TSC is activated, if off-site assistance will be required. 6.2.2 If off-site assistance is required direct that EP-205-1 (Security Force: Response for Fire, Disaster, or Radiological Emergency) be carried out. 6.2.3 Determine from the Emergency Director, through the TSC Security Advisor, if the TSC is
- activated, when the requirement for the evacuation is terminated.
6.3 When directed by the Security shift Lieutenant, Members of the Security Force shall return to normal security operations. END O
=
^
EP-210-1 Rev. 0.B ENRICO, FERMI ATOMIC POWER PLANT l UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
OFF-SITE RADIOLOGICAL EMERGENCY TEAM: ACTIVATION RECORD OF APPROVAL ND CHANGES 3 Submitted by ed Supervisor of Rao olo@ical Emergency Date Response Prepar ess Approved by -s Chairman -TgJhison Committee Date , Liaison Committee O Revision No. Submitted Date Approval Date i 1 l 2 l 3 4 5 6 7 8 N
4 i r i l l I i i EP-210-1 , Rev. 0.B i l 1 I 8 l' \ 4 J ; l i l t i I I i ! I l ENRICO FERMI ATOMIC POWER PLANT l UNIT NO. 2 i e i I Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
OFF-SITE RADIOLOGICAL EMERGENCY TEAM: ACTIVATION l@ l i
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l i 1 l i EP-210-1 ! Rev. 0.B OFF-SITE RADIOLOGICAL EMERGENCY TEAM: ACTIVATION i TABLE OF CONTENTS _Page 1.0 Purpose.............................................. 1 i 2.0 References........................................... 1 l
; 3.0 Entry Conditions..................................... 1 4.0 General Information.................................. 1 l 5.0 Immediate Actions.................................... 2 6.0 Follow-up Actions.................................... 4 ,
Attachment i List of Emergency Equipment and Documents.......... Attachment 1 I i 'l I t 4 4 I 3 9..
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(^'i EP-210-1 V Rev. 0.B Page 1 1.0 Purpose To prescribe the procedure for activation of the Off-Site Radiological Emergency Team (Off-Site RET). 2.0 References 2.1 Enrico Fermi Atomic Power Plant Unit 2 Radiological Emergency Response Plan, Section B (On-Site Emergency Organization), Section H (Emergency Facilities), and Section I (Accident Assessment). 2.2 Off-Site Radiological Emergency Team: Functions (EP-210-2). , 2.3 Health Physics Records (61.000.50). 2.4 Off-Site Radiological Emergency Team Instruction Guide. Entry Conditions l i (3 sg 3.0 The Off-Site RET shall be activated as directed by the Emergency Director in the event of: l
- 1. Radioactive liquid release to the environment.
- 2. Gaseous radioactive release to the environment.
- 3. Site Area Emergency.
- 4. General Emergency. ,
4.0 General Information 4.1 A Wayne Division dispatcher will be the Off-Site RET Coordinator and will be located in the Emergency Operations Facility (EOF). He will dispatch the field survey teams to sample points designated by the Radiation Protection Coordinator and record sample results as the teams report back. This data will be given to the Radiation Protection Coordinator for analysis. 1 O
EP-210-1 h Rev. 0.B Page 2 4.2 In the Newport Warehouse, additional personnel have been assigned as follows: 4.2.1 RET Supervisor - a senior Wayne Division supervisor who will oversee and coordinate the assembly and formation of the RET field survey teams. 4.2.2 RET Equipment Coordinator - assigned to maintain accountability of equipment and assist the RET Supervisor. 4.3 For a Site Area Emergency the Off-Site RET shall consist of a minimum of four (4) personnel. 4.4 For a General Emergency the Off-Site RET shall consist of a minimum of eight (8) personnel. 4.5 Additional personnel from the Wayne Division Personnel Pool are available for the assignment of up to twenty (20) 2-man, Off-Site Teams. 4.6 The Off-Site RET's responsibilities consist of the following: 4.6.1 Obtaining off-site air samples and performing a basic analysis for radionuclide content. 4.6.2 Obtaining off-site water samples. 4.6.3 Conducting off-site radiation surveys. 4.6.4 Obtaining off-site environmental samples (grass, soil, etc.). 5.0 Immediate Actions 5.1 When activated the Off-Site RET members shall report to the Newport Warehouse or other location designated by the Emergency Director, or the EOF Coordinator if the EOF is activated. O
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ks- EP-210-1 Rev. 0.B Page 3 5.2 Upon arrival at the Newport Warehouse the RET Supervisor shall: 5.2.1 Contact the EOF Administrator and determine the identity of Off-Site RET personnel reporting to Newport Warehouse. ! 5.2.2 Divide available personnel into 2-man teams as l they arrive at the Newport Warehouse. 5.2.3 Contact the RET Coordinator and inform him when teams are assembled and ready for initial assignments. 5.3 Upon arrival at the Newport Warehouse the RET i Equipment Coordinator shall: 5.3.1 Distribute off-site radiological kits to each , team. 1 Direct each team to inventory'each kit and (' - s 5.3.2 perform operational checks on all radiological test equipment prior to departing for the field. 5.3.3 Replace any inoperative or missing equipment with equipment contained in unused kits. Missing or inoperative equipment shall be noted and reported to the General'.5upervisor-Health Physics. 5.4 The RET Coordinator shall: 5.4.1 Determine the required survey areas and sample media from the Radiation Protection Coordinator. 5.4.2 Contact the RET Supervisor at the Newport ' Warehouse and give initial assignments to the Off-Site RET's. (Subsequent assignments will be given via radio). 5.4.3 Instruct team members concerning the following:
- 1. Making periodic reports of air sample and s survey results to the RET Coordinator.
1 l-
EP-210-1 Rev. 0.B Page 4
- 2. Making immediate reports if radiation levels are in excess of the control value ;
assigned by the Radiation Protection ' Coordinator.
- 3. Maintaining records of all surveys.
5.5 RET Members shall: 5.5.1 Report to the RET Supervisor at the Newport Warehouse when directed by the EOF Administrator or the Emergency Director. 5.5.2 Obtain an off-site radiological kit from the RET Equipment Coordinator. 5.5.3 Inventory the kit and perform all required operational checks of the test equipment. 5.5.4 Report any missing or inoperative equipment to the RET Equipment Coordinator. Obtain replacement equipment from the Equipment Coordinator. 5.5.5 At the direction of the RET Supervisor proceed to the field and perform surveys and collect samples required by the RET Coordinator. 5.5.6 Report survey results to the RET Coordinator. Any samples taken shall be given to the couriers to be delivered to the Emergency Laboratory for analysis. 5.5.7 After the completion of required surveys contact the RET Coordinator via radio and obtain new sample and survey instructions. 6.0 Follow-up Actions 6.1 If additional support is necessary the RET Coordinator shall determine the approximate number of personnel necessary, and with the concurrence of the Radiation Protection Coordinator, obtain additional support personnel from the Wayne Division Personnel Pool. O
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g . . ,, , s 6.2.1"?, Maintain communications wfth all Off-Site. RET ' groups. #) ' , , Q, ij / ,-.
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- 6. L,2 Keep the Radiation Prote3:tich' C60F'dinator l informed of thEr emergency l especially '"
with I J regard to the following: d' ' -
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- 1. Areas with significant radiation r levels.
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- 2. Areas with excessive ' airborne, radio-activi ty.1. 2vels . ,
6.2.3 Ensure all samples are dok;ivered tcg the [., , Emergency Laboratory Sampl'e Coordinator. '
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3 6.2.4 During Recovery Program 'd'irect of f-Dite / , # // sampling and survey programs as df.rectdd j !dy# , the Recovery Manager. # v 1 / .} - . i /, r j ( - s
,,he RET Supervisor shall:
6.3 T , c. ,
'6,.3.1 Supervise any addi,tional personnel, kucated '
- by the RET Coordinator who report to,the Newport' Warehouse. - 6 gg ,
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, s p . 9. 2 Monitor all radio communications with the ,,
,2 ., f, figld teams and respond to the, EOF as ,
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6.4.l Survey eqs.1pment for contamination and reques t ' Health Physics assistqnce in dec.ontdtination i' / as required. j 'j i
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EP-210-1 h Rev. 0.B Page 6 6.4.2 Direct an inventory of all equipment used during the emergency.
- 1. All equipment shall be checked for proper operability, serviced or repaired as necessary (batteries replaced, filters replaced, etc.) and restowed in the equipment storage room.
- 2. Any missing or damaged equipment shall be recovered, or replaced and reported to the General Supervisor - Health Physics.
6.4.3 Maintain records of sign-on and sign-off times, mileage, or other expenses of RET personnel at the Newport Warehouse. O l O
I , [' EP-210-1
\ - Rev. 0.B LIST OF EMERGENCY EQUIPMENT AND DOCUMENTS Check that the following equipment is available and functional:
QUANTITY ITEM QUANTITY AVAILABLE
- 1. Set of Procedures for Obtaining 1 Environmental Samples
- 2. Radeco H809C battery powered air sampler 1 using iodine selective cartridges
- 3. Extra air sampler heads 2
- a. Particulate filters 100
- b. Silver zeolite cartridges 8
- 4. Scott Single Lens Scottoramic Facepiece 4 (801450-40) with a Scott High Efficiency Particulate Filter Cartridge (604401-50)
- 5. Eberline RM14 (frisker) or Ludlum 177 1 s (frisker) and pancake probe
- 6. Dose rate meter (RO-2) 1
- 7. TLDs fcr personnel 4 .
- 8. TLDs for environment 20
- 9. 0-200 or 0-500 mRoentgen self-reading 4 dosimeter
- 10. Dosimeter charger and batteries 1
- 11. Envelopes and bags (ea.) for samples 100
- 12. Labels for samples 200
- 13. Boxes of smears 4
- 14. Ludlum 12S micro R meter 1
- 15. Survey forms 100 N Attachment 1 Os Page 1 of 2
l EP-210-1 Rev. 0.B QUANTITY ITEM QUANTITY AVAILABLE
- 16. Log book 1
- 17. Paper clothing sets 6
- 18. High Band portable radio 1
- 19. Bottle of KI tablets 2 O
END Attachment 1 Page 2 of 2
EP-210-2
- O Rev. 0.B ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type
- EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
OFF-SITE RADIOLOGICAL EMERGENCY TEAM: FUNCTIONS RECORD OF APPROVAL AND CHANGES Submitted by eb Date Supervisor of Radiolo id@7 Emergency ! Response Preparedne Approved by O Chairman - Liarson Committee Date l Liaison Revision Committee No. Submitted Date Approval Date l 1 2 3 4 5 l 6 i l 7 8 iO
! t i l EP-210-2 l Rev. 0.B i t i I ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
OFF-SITE RADIOLOGICAL EMERGENCY TEAM: FUNCTIONS l l i i f I i i-----_.._________ __ _ _ _
EP-210-2 Rev. 0.B OFF-SITE RADIOLOGICAL EMERGENCY TEAM: FUNCTIONS TABLE OF CONTENTS Page i 1.0 Purpose............................................... 1 l i 2.0 References............................................ 1 3.0 Entry Conditions...................................... 1 4.0 General Information................................... 1 5.0 Immediate Actions..................................... 2 5.2 Radioactive Liquid Release....................... 2 5.3 Gaseous Radioactive Release...................... 3 6.0 Follow-up Actions..................................... 4 Enclosures Possible Environmental Samples...................... Enclosure 1
P ' EP-210-2 Rev. 0.B Page 1 1.0 Purpose To prescribe the procedures for the Off-Site Radiological Emergency Team (Off-Site RET). 2.0 References 2.1 Enrico Fermi Atomic Power Plant Unit 2 Radiological Emergency Response Plan, Section B (On-Site Emergency Organization), Section H (Emergency Facilities), and Section I (Accident Assessment). 2.2 Off-Site Radiological Emergency Team: Activation (EP-210-1) . 2.3 Airborne Radioactivity Survey Techniques (63.000.30). 2.4 Health Physics Records (61.000.50). 2.5 Radiation Survey Techniques (63.000.10). 2.6 Off-Site Radiological Emergency Team Instruction () 3.0 Guide. Entry Conditions The off-Site RET shall be activated as directed by the Emergency Director in the event of:
- 1. Radioactive liquid release to the environment.
- 2. Gaseous radioactive release to the environment.
- 3. Site Area Emergency.
- 4. General Emergency.
4.0 General Information l 4.1 When required by the Emergency Director, the EOF l Administrator is responsible for activating the required off-site personnel for formation of the Off-Site RET. This will include the RET Supervisor, the RET Equipment Coordinator, and Off-Site RET members. All of these personnel report to the Newport Warehouse. The RET Coordinator shall be informed and shall report to the EOF. O
EP-210-2 Rev. 0.B Page 2 4.2 The RET Supervisor will oversee and coordinate the assembly and formation of the RET field survey teams. Specific responsibilities are delineated in EP-210-1 (Off-Site RET: Activation). 4.3 The RET Equipment Coordinator is assigned to maintain accountability of all equipment and assist the RET Supervisor. His specific responsibilities are delineated in EP-210-1 (Off-Site RET: Activation). 5.0 Immediate Actions 5.1 The Off-Site RET shall be activated in accordance with EP-210-1 (Off-Site RET: Activation). 5.2 In the event of a RADIOACTIVE LIQUID RELEASE to the environment the RET Coordinator shall: 5.2.1 Contact the Radiation Protection Coordinator and obtain the following information:
- 1. Areas to be surveyed.
h
- 2. Samples to be taken.
5.2.2 Contact the RET Supervisor and direct members to obtain the following water samples if the release has entered, or potentially entered the waters of Lake Erie.
- 1. Fermi I potable water intake.
- 2. Control - Trenton Power Plant intake.
- 3. City of Monroe water intake.
- 4. Control - Detroit water intake at Fighting Island.
- 5. Any other water samples as directed by the Radiation Protection Coordinator.
5.2.3 Instruct Team members on the following:
- 1. All surveys and samples to be taken.
O
i f) (i EP-210-2 Rev. 0.B Page 3
- 2. Making periodic reports of survey results to the RET Coordinator.
- 3. Making immediate reports if radiation levels are in excess of the control value
! determined by the Radiation Protection Coordinator.
- 4. Maintaining records of all samples taken.
5.2.4 Report the results of off-site surveys to the Radiation Protection Coordinator. 5.2.5 Direct all samples taken be collected and delivered to the Radiation Protection Coordinator in the EOF. 5.3 In the event of a RADIOACTIVE GASEOUS RELEASE to the environment the RET Coordinator shall: l 5.3.1 Contact the Radiation Protection Coordinator I obtain the following information: l '
/ l. Samples to be taken.
- 2. Areas to be surveyed.
5.3.2 Contact the RET Supervisor and direct members to conduct initial surveys and obtain initial samples as directed by the Radiation l Protection Coordinator (subsequent assignments will be given by radio). 5.3.3 Instruct Team members on the following:
- 1. All surveys and samples to be taken including samplos at the following water intakes:
- a. Fermi I potable water intake
- b. Control - Trenton Power Plant intake
- c. City of Monroe water intake
- d. Control - Detroit water intake at Fighting Island O
1 l EP-210-2 h Rev. 0.B Page 4
- e. Any other water samples as directed by the Radiation Protection Coordinator.
- 2. Collecting designated supplemental environmental TLD's from various locations and replacing them with new TLD's.
- 3. Making periodic reports of air sample and survey results to the RET Coordinator.
- 4. Making immediate reports if radiation levels are in excess of the control value assigned by the Radiation Protection Coordinator.
- 5. Maintaining records of all samples.
5.3.4 Report the results of off-site surveys to the Radiation Protection Coordinator. 5.3.5 Direct all samples taken be .llected and delivered to the Radiation Protection Coordinator in the EOF. 6.0 Follow-up Actions The RET Coordinator shall: 6.1 Ensure all surveys and samples required by the Radiation Protection Coordinator have been completed. 6.2 Ensure all supplemental environmental TLD's removed for analysis have been replaced with new TLD's. 6.3 Ensure all Follow-up Actions of EP-210-1 (Off-Site RET: Activation) have been completed. O
EP-210-2 Rev. 0.B POSSIBLE ENVIRONMENTAL SAMPLES The following table may be used in determining environmental media and quantities to be sampled: Quantity / Volume Medium Sampled Each Sample Analysis Preferred Sample Location Air-Particulates 20 ft3 Beta, gamma Downwind from site
- Air-Iodine 20 ft3 Beta, gamma Downwind from site
- Air-Noble Gas 20 ft3 Beta, gamma Downwind from site
- Water-Lake, 1 liter Beta, Gamma 10 downstream from site Stream, River (Note 1) Isotopic 2 upstream from site for control Water-Tap 1 liter Gamma 2 for control 15 mi from Isotopic site (Note 2) 4 downwind from site Soil (including 1 kg Gamma 2 for control 15 mi.
shoreline Isotopic from site Os sediment) (Note 3) 6 downwind from site vegetation 1 kg Gamma 2 for control 15 mi. Isotopic from site (Note 3) 6 downwind from site Milk 2 liters I-131, 2 for conttol 15 mi. Cs-137, from site ** Sr-90 (Note 4) 5-10 downwind from site **
- Within Plume Exposure Pathway
**If owner cooperation available Enclosure 1 Page 1 of 2
EP-210-2 I Rev. 0.B Note 1: Upstream samples should be a minimum of 5 mi. upstream of plant outfall. Note 2: Control samples should come from least prevalent wind direction from township (municipal) water supply. Note 3: Control samples should come from least prevalent wind direction at nearest TLD site for sample account-ability. Downwind samples should be taken at/near TLD locations for sample accountability. Note 4: Milk samples should be raw, untreated milk from dairies in least prevalent wind direction for control purposes. NOT ALL SAMPLES ON THIS TABLE NEED TO BE COLLECTED DURING EMERGENCY CONDITIONS, HOWEVER, A REPRESENTATIVE SAMPLE SHOULD BE TAKEN ON THOSE LISTED AS TIME PERMITS. O END Enclosure 1 Page 2 of 2
EP-290 O Rev. 0.B ENRICO, FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
EMERGENCY NOTIFICATIONS RECORD OF APPROVAL AND CHANGES Submitted by M Supervisor of Radiologi g Emergency Date Response Preparedne Approved by Chairman - Liay 6n Committee Date Liaison Committee O Revision No. Submitted Date Approval Date 1 2 3 4 5 6 7 8 4
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EP-290 O Rev. 0.B ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
EMERGENCY NOTIFICATIONS O
~
O
/' EP-290 Rev. 0.B EMERGENCY NOTIFICATIONS TABLE OF CONTENTS Page 1.0 Entry Conditions..................................... 1 1 2.0 General Information.................................. 1 3.0 Procedure............................................ 1 Attachments Initial Notification Message Form.................. Attachment 1 Nuclear Regulatory Commission (NRC) Initial Notification Form................................ Attachment 2 Off-Site Emergency Support Organizations Activation....................................... Attachment 3 Standby Notification Message Form.................. Attachment 4 l Operations Support Center Activation............... Attachment 5 l Technical Support Center Activation................ Attachment 6 Emergency Operations Facility Activation........... Attachment 7 1
i l
[' EP-290 l Rev. 0.B l Page 1 1.0 Entry Conditions An emergency has been classified in accordance with EP-101 (Classification of Emergencies). 2.0 General Information 2.1 The actual notifications should normally be delegated to the Control Room, Technical Support Center (TSC), or Emergency Operations Facility (EOF) Communicator. 2.2 Emergency notifications to state and local author-ities should te made as soon as possible, but must be made within the following prescribed time limits:
- 1. Unusual Event: 1 hour
- 2. Alert: 30 minutes
- 3. Site Area Emergency: 15 minutes I
( 4. General Emergency: 15 minutes
}
2.3 The Emergency Director must be kept informed as to the status of notifications. If any difficulties are , encountered in completing any required notifications the Emergency Director must be notified immediately. 3.0 Procedure 3.1 Upon classification of an emergency perform the following: 3.1.1 Complete the Notification Form (Attachment 1). 3.1.2 Notify the Fermi 2 On-Call Plant Supervisor. Relay the information on the Notification Form. The Fermi 2 On-Call Plant Supervisor is responsible for notifying any additional Detroit Edison officials including the on-call Media Relations Representative. 3.1.3 Notify the following required Government Emergency Response Organizations:
- 1. Michigan State Police
- 2. Monroe County Sheriff
EP-290 Rev. 0.B Page 2
- 3. Sandwich West Police Station - Canada (notify at the Alert level or higher and notify only once) 3.1.4 Nuclear Regulatory Commission (NRC) notification.
- 1. Complete the message form of Attachment 2.
- 2. Contact the NRC Regional Office and the NRC Operations Center in Bethesda, Maryland. Read the completed message form ( Attachment 2) .
3.1.5 Notify American Nuclear Insurers (ANI) at the Alert level or higher (notify only once). This notification will be made from the TSC, once the TSC is activated. 3.2 Follow-up reports to the Fermi 2 On-Call Plant Supervisor, Government Emergency Response Organizations, and the NRC. 3.2.1 Complete the Notification Form of Attachment 1 and ensure message number, date, and time are updated. 3.2.2 Call the following and read the completed Notification Form (Attachment 1):
- 1. Fermi 2 On-Call Plant Supervisor.
- 2. Government Emergency Response Organizations listed in 3.1.3.
- 3. NRC Region III Office.
- 4. NRC Operations Center in Bethesda.
NOTE: An off-duty Nuclear Supervising opera-tor will be assigned to make any necessary follow-up reports to the NRC. 3.3 Fire or Medical assistance required: 3.3.1 Complete the applicable section of the message form of Attachment 3.
EPA-290 ( '-) s- Rev. 0.B Page 3 3.3.2 Call the applicable telephone number and read I the completed message form. 3.3.3 Notify the Secondary Alarm Station (SAS) Operator and relay the following information to him:
- 1. Support organization reporting on-site.
- 2. Number of personnel reporting on-site.
- 3. Number of vehicles reporting on-site. ,
l
- 4. Owner-controlled area access gate to be '
used.
- 5. Scene of the emergency.
- 3.4 To place personnel on standby
l l 3.4.1 Complete the message form of Attachment 4. l l O
\s / 3.4.2 Call the first person listed on the Communication Chain for the facility to be placed on standby (see steps 3.5.2, 3.6.2 or l 3.7.2 below).
I 3.4.3 Read the completed message form (Attachment 4). Ensure each person fully understands this is a standby notification. 3.5 Operational Support Center (OSC) activation: 3.5.1 Complete the message form of Attachment 5. 1 3.5.2 Notify the OSC Coordinator. 3.6 Technical Support Center (TSC) activation: 3.6.1 Complete the message form of Attachment 6. 3.6.2 Notify the TSC Administration and Support Coordinator. 3.7 Emergency Operations Facility (EOF) activation: 3.7.1 Complete the message form of Attachment 7. l l
EP-290 Rev. 0.B Page 4 3.7.2 Notify the EOF Administrator. 3.8 Phone numbers for all the agencies, facilities, support personnel, and off-site support organizations can be found in the Detroit Edison RERP Notification Directory. O O
~ . - - . .-.
l l EP-290 j Rev. 0.B NOTIFICATION FORM t
"This is the Enrico Fermi Atomic Power Plant - Unit 2. The following is notification of an emergency. This is/is not a drill.
Date Emergency Message No. Time
- 1. FROM
- Enrico Fermi 2 CR TSC EOF )
- Title i Telephone No.
TIME VERIFICATION: NAME/ TITLE /TEL.NO.
- 2. TO: Michigan Monroe Co.
NRC Media Relations
- Canada
*American Nuclear Insurers
*(ONE NOTIFICATION ONLY - INITIATE AT THE ALERT LEVEL OR HIGHER)
- 3. CLASS OF EMERGENCY Time Declared Unusual Event Site Area Emergency Alert General Emergency
- 4. DESCRIPTION OF EVENT l 5. PROGNOSIS STABLE ESCALATING DE-ESCALATING TERMINATING Attachment 1 Page 1 of 3
EP-290 Rev. 0.B
- 6. EDISON EMERGENCY RESPONSE ACTIONS UNDERWAY OFFSITE ASSISTANCE PREVIO'JSLY REQUESTED: YES NO FIRE AMBULANCE POLICE _ HOSPITAL OTHER SITE EVACUATION: YES NO LIMITED ONSITE RETS DISPATCHED: YES NO OFFSITE RETS DISPATCHED: YES NO _
- 7. RADIOLOGICAL RELEASE DATA POTENTIAL FOR RELEASE: YES NO ACTUAL RELEASE: YES NO TIME OF RELEASE AIRBORNE WATERBORNE SURFACE SPILL DURATION OF RELEASE (ESTIMATED)
- 8. METEOROLOGICAL DATA WIND SPEED, MPH M/SEC WIND DIRECTION,, FROM TO TEMPERATURE ,F 10m 60m WT F/50M STABILITY CLASS (CIRCLE) A B C D E F G PRECIPITATION SECTORS AFFECTED FORECAST (3 HR) l l
l l l l Attachment 1 l Page 2 of 3 I
! EP-290 Rev. 0.B
- 9. PROJECTED RADIOLOGICAL DATA POTENTIAL ACTUAL
, MONITOR DRYWELL (CAHRRM) SGTS READING RAD /HR )Ci/cc TIME OF READING TIME REACTOR SCRAM TIME CALC (8 HR INC.) FROM: TO: FROM: TO: TIME RELEASE NOT APPJ,ICABLE i DURATION RELEASE NOT APPLICABLE ] NOBLE GASES Ci(ACT) Ci(ACT l IODINES Ci Ci DOSE WHOLE BODY THYROID WHOLE BODY THYROID DOSE DOSE DOSE DOSE DOSE DOSE DOSE DOSE RATE RATE RATE RATE REM MR/HR REM MR/HR REM MR/HR REM MR/HR EAB (0.57 MI, 915 M) 2 MILES 5 MILES 10 MILES PAG RADIUS FOR 1 REM (1000 MR) MILES MILES
- 10. PROTECTIVE ACTION RECOMMENDATIONS t
SECTOR (S) MILES NONE SHELTERING PRECAUTIONARY EVACUATION EVACUATION CONTAMINATON CONTROL FOOD WATER MILK OTHER i
- 11. REMARKS CC: Other:
p Attachment 1 gj Page 3 of 3
EP-290
\_, Rev. 0.B
\
l NUCLEAR REGULATORY COMMISSION (NRC) INITIAL NOTIFICATION FORM This is Enrico Fermi Atomic Power Plant - Unit 2. The following is a notification of an emergency. Record the following information:
- 1. "This is ,
(Name) (Title) of Enrico Fermi 2."
- 2. "An emergency condition has occurred at Fermi 2.
! This is/ is not a drill."
- 3. "The emergency condition has been classified / reclassified
; (circle one) as:
AN UNUSUAL EVENT AN ALERT A SITE AREA EMERGENCY A GENERAL EMERGENCY at AM PM / / . month day ! 4. " Details of the emergency are as follows: What Happened: l Cause: Consequence: l l l Attachment 2 O Page 1 of 5 l
EP-290 Rev. 0.B Actions Taken: Current Status: Action Planned:
- 3. " Additional details are as follows:
- a. The plant is currently in/ not in a stable condition.
- b. All systems functioned as designed.
The following system and/or equipment failed to function properly
- c. The event:
Does NOT involve the release of radioactive materials from the plant or involve the public." Involves the POTENTIAL for the release of radioactive materials, but NO radioactive materials have been released." Attachment 2 Page 2 of 5
EP-290 O Rev. 0.B Does involve the release of some radioactive material from the plant, but at a level below that considered a public hazard. Source: Cause: Quantity: ." (relative to tech, spec.) Does involve the release of radioactive materials from the plant. Source: Cause: Quantity: ."
- d. Recommended protective actions for the public are as follows:
) Sheltering in zones .
Evacuation of zones . Other Attachment 2 Page 3 of 5
i ( EP-290 Rev. 0.B
- e. "The event:
involved a reactor trip. Cause: _ involved a power runback. Cause: involved operation under a LCO. Cause: involved initiation of ECCS. Cause: ."
- 6. "There was/were injured person (s)."
number
, "There was/were contaminated person (s) ."
number
" Injured person (s) were/ were not decontaminated prior to being taken to the hospital."
- 7. "There is a coolant leak. The leak was detected by The leak is isolable / not isolable.
When the leak was detected, the system was purged / not purged. Leak rate is increasing, decreasing, i'solated." Attachment 2 Page 4 of 5 I l
EP-290 O Rev. 0.B
- 8. "A security computer failure occurred.
A security problem was detected / not detected. Compensating measures have/ have not been taken."
- 9. "The following notifications have been made:
Detroit Edison Management Michigan State Police Monroe County Sheriff Canadian Government."
- 10. "The on-call Media Relations Representative has/
has not been informed. I i A press release P 'en made. A press ' release io planned. No press release has been made nor is planned."
- 11. "May I please have your name for our records."
(Name) (Title) P
\i i
Attachment 2 O Page 5 of 5 I
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/ EP-290 ) ;
1 t ./ Rev. 0.B ,
- g. O ,
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f ~, , OFF-SITE EMERGENCY SUPPORT ORGAhEZATIONS ACTIVATION '/
. , og .. ;
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gga ~~ '- 1 s 1.0 Frenchtown Voladteer Fire Department /f
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' 5
- 1. "This is- -'
(state /name and-title) ' calling f rom the Enrico Fermi Atomic Pcwer Plant - Unit /7. There is a fir 9 at the site. Your assistance isrequ.ested immediately." ,
- 2. "Use the: access gate.'; ' - -
,'e 3.- "The following precautions shall be.t'aken i.. ' y reporting to the scene .
N 1 F l
- 4. Determine the following information from the Firo ,
Department and relay this information to the SAS < Operator.
- 1. Number of vehicles expected to arrive l
- 2. Number of personnel expected to arrive 1
l l l 1 Attachment 3 O Page 1 of 3
EP-290 Rev. 0.B AMBULANCE 2.0 EMTS Ambulance Service
- 1. "This is (state name and title) calling from the Enrico Fermi Atomic Power Plant - Unit 2. There are injured personnel at the site and your assistance is required immediately."
- 2. " Number of injured personnel is ."
- 3. " Injuries to personnel are ."
- 4. " Number of potentially contaminated personnel is
- 5. "Use the access gate."
- 6. "The following precautions shall be taken:
- 7. Determine the following information from the Ambulance Service and relay this information to the SAS Operator.
- 1. Number of vehicles expected to arrive
- 2. Number of personnel expected to arrive Attachment 3 Page 2 of 3
EP-290
- Rev. 0.B HOSPITAL 3.0 Seaway Hospital
- 1. "This is (state name and title) calling from Enrico Fermi Atomic Power Plant -
Unit 2. There are injured personnel at the site and the EMTS Ambulance Service has been contacted to transport the victims to you."
- 2. " Number of injured personnel is ."
- 3. " Injuries to personnel are ."
- 4. " Number of potentially contaminated personnel is
- 5. " Number of personnel suffering from excessive radiation exposure is ."
- 6. (If there are potentially contaminated personnel state the following:)
"You are requested to implement your Radiological Emergency Plan."
{ i I Attachment 3 l l ( g-)N Page 3 of 3 t I
EP-290 , O- Rev. 0.B l l STANDBY MESSAGE FORM i 1.0 Standby notification.
"This is (state name and title) calling from Enrico Fermi 2. There is a(n)
(state classification of emergency) which requires that the (state the f acility) be placed on standby. You must remain available and be prepared to report to your assigned
- position. If it becomes necessary to activate I
the (state the facility), you will be notified. You are required to carry out your initial notifications of the (state the facility) Communication Chain and ensure personnel notified are aware this is a standby notification." G Attachment 4 O Page 1 of 1
T 1 4 ( i
- EP-290 l Rev. 0.B j OPERATIONAL SUPPORT CENTER (OSC) ACTIVATION l
1.0 Notification of the On-Call OSC Coordinator. l l
"This is (state name and I
titie) calling from Enrico Fermi 2. There is been l a(n) (state classification of ! emergency) which requires the OSC to be activated. l Activate the OSC." i O i l O Attachment 5 Page 1 of 1 l l
_ _ . _ _ _ _ _ _ _ _ . _ _ . _ - - _ _ . ._ _ _ _ _ .- --__. _ _ _ _ - - - - _ _ ___m _ _ _ _.--. -_._ . _ 1 i O EP-290 Rev. 0.B 4 { TECHNICAL SUPPORT CENTER STAFF (TSC) ACTIVATION i ! 1.0 Initiate the Technical Support Center Communication Chain.
"This is (state name and i
title) calling from the Enrico Fermi 2. There is a(n) ; l (state classification of i emergency) which requires the TSC to be activated. J You are required to carry out your initial notiff. cations of L the TSC Communication Chain." i i o-l 1 l r i i l 4 Attachment 6 j' .l O Page 1 of 1 l 4 g,.e -. 4---- ,-- - - - ,,-r--.-,-, , , , - - - - - ,v,, - . , ,-.n-,---. ,- -. . - - - . . - - - . . , . - . , . - - - , , , , - - . , - - - , . ~ ~ , - - - - , , - - - -
e i l EP-290 Rev. 0.B EMERGENCY OPERATIONS FACILITY (EOF) ACTIVATION
; 1.0 Initiate the Emergency Operations Facility Communication Chain.
"This is (state name and title) calling from Enrico Fermi 2. There is a(n)
(state classification of emergency) which requires you to activate the EOF. l l You are required to carry out your initial notifications of the EOF Communication Chain." 2
- O i
i I i I J
- END l
Attachment 7 O Page 1 of 1
' ' EP-301-1 Rev. 0.B ENRICO FERMI ATOM;C POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
TECHNICAL SUPPORT CENTER: ACTIVATION RECORD OF APPROVAL AND CHA Submitted by rV Supervisor of Radiologica Etadtgency Date Response Preparedness Approved by G Chairman - Liaison Yommittee Date Liaison Revision Committee No. Submitted Date Approval Date 1 2 3 4 5 6 7 8 O
O EP-301-1 Rev. 0.B ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
TECHNICAL SUPPORT CENTER: ACTIVATION O O 4
! p EP-30'.-l Rev. 0.B l
TECHNICAL SUPPORT CENTER: ACTIVATION TABLE OF CONTENTS Page 1.0 Purpose............................................... 1 2.0 Reference............................................. 1 3.0 Entry Conditions...................................... 1 4.0 General Information................................... 2 5.0 Procedure............................................. 2 Attachments List of Emergency Equipment and Documents......... Attachment 1 Technical Support Center Layout Diagram............ Attachment 2
- i f
i l t l
EP-301-1 O Rev. 0.B Page 1 1.0 Purpose To prescribe procedures for activation of the Tacnnical Support Center (TSC), and to delineate the initial respon-sibilities of the Emergency Director (Superintendent-Nuclear Production or his alternate) and the Administration e and Support Coordinator. 2.0 References 2.1 Enrico Fermi Atomic Power Plant Unit 2 Radiological Emergency Response Plan, Section B (Onsite Emergency Organization), Section F (Emergency Communications), Section H (Emergency Facilities and Equipment), Section I (Accident Assessment), and Section M (Reentry and Recovery Planning and Post-Accident Operations Planning). 2.2 Functional Criteria for Emergency Response Facilities (NUREG 0696), Section 2 (Technical Support Center). 2.3 Classification of Emergencies (EP-101) . 2.4 Unusual Event (EP-102) 2.5 Alert (EP-103) 2.6 Site Area Emergency (EP-104) 2.7 General Emergency (EP-105 ) 2.8 On-Site Radiological Emergency Team (EP-201 series) 2.9 Emergency Notifications (EP-290) 2.10 Selection and Use of Respiratory Protection Equipment (65.000.20). 2.11 Radiation, Contamination, and Airborne Guides and Limits (61.000.05). 3.0 Entry Conditions The TSC is activated for the following classes of emergencies:
- 1. Alert.
O
1 EP-301-1 Rev. 0.B ! Page 2
- 2. Site Area Emergency.
- 3. General Emergency.
4.0 General Information The TSC is equipped to enable the TSC staff to assess plant status nd make recommendations to the Emergency Director concern.as olant operations, corrective actions, and protective .ctions.
5.0 Procedure
5.1 Upon activation of the TSC, the first individuals to arrive at the TSC shall: 5.1.1 Energize the following equipment, if not already energized:
- 1. Lighting system.
- 2. HVAC system.
- 3. Area radiation monitor.
- 4. Air sampler.
- 5. Data acquisition system.
5.1.2 Check the area radiation level and airborne contamination levels.
- 1. If airborne contamination levels exceed the limits of Health Physics Procedure 61.000.05 (Radiation, Contamination, and Airborne Guides and Limits), don respiratory equipment in accordance with Health Physics Procedure 65.000.20 (Selection and Use of Respiratory Protection Equipment).
- 2. If either level exceec s the designated limits:
- a. Contact the Emercancy Director and inform him of the condition of the TSC. The Emergency Director will determine which TSC functions should be moved to the Control Room.
EP-301-1 O Rev. 0.B Page 3 Personnel not assigned to the Control Room will proceed to the OSC, EOF, or other area, as directed by the Emergency Director.
- b. Hang signs directing personnel to proceed to the Control Room, OSC, EOF, or other area directed by the Emergency Director. Pre-printed signs are available with the emergency equipment.
- c. Proceed to the Control Room, OSC, the EOF or other area directed by the Emergency Director.
5.2 Upon his arrival, the Superintendent-Nuclear Production (or alternately, the Assistant Superintendent or Operations Engineer) shall: 5.2.1 Contact the Emergency Director either by phone or proceeding to the Control Room. () 5.2.2 Review the current status of the emergency, including:
- 1. Background information leading up to the emergency.
- 2. Indications and suspected cause of the emergency, including existing hazards to personnel, damage to plant systems, instrumentation, and other equipment; and radiation levels or releases.
- 3. Classification of the emergency.
- 4. Corrective actions taken.
- 5. Status of execution of the steps in EP-101 (Classification of Emergencies) and other Emergency Plan Implementing Procedures, especially activation of Emergency Teams and performing required notifications.
- 6. Present plant lineups, and plant evolutions or operations in progress.
O
EP-301-1 Rev. 0.B Page 4
- 7. Evolutions or operations which have been directed or are planned, but not yet carried out.
5.2.3 Relieve the Emergency Director of his - responsibilities, and ensure that emergency organization personnel are aware that the Superintendent-Nuclear Production (or alternate) is now the Emergency Director. Notification will be through the plant announcing system or telephones as applicable. (After being relieved as Emergency Director, the Nuclear Shift Supervisor or Assistant Shift Supervisor shall retain his responsibilities and authority in the Control Room). 5.2.4 Activate the TSC staff, or ensure that they have already been activated (see EP-290, Emergency Notifications). If another TSC staff member is available, delegate this task to him. The following personnel are normally assigned to the TSC staff:
- 1. Technical Engineer.
- 2. Nuclear Safety Advisor.
- 3. Radiation Protection Advisor - General Supervisor-Health Physics.
- 4. Radiochemistry Advisor - General Supervisor-Chemistry.
- 5. Security Liaison - Security Shift Lieutenant (or his alternate, the Nuclear Security Chief).
- 6. Administration and Support Coordinator.
1
- 7. Environmental Assessment Team.
- 8. Communicators.
l l The following additional personnel are activated for a Site Area Emergency or a General Emergency.
EP-301-1 O Rev. 0.B Page 5
- 9. Support for the Nuclear Safety Advisor -
Thermal lydraulic, Mechanical, Electrical, and Instrumentation and Control Engineers and General Electric Representative, Architect / Engineers, or Consultants.
- 10. Clerks.
- 11. Typists.
- 12. Couriers.
- 13. Quality Assurance Advisor.
5.2.5 Personnel assigned to the TSC must report to their required positions within 30 minutes if they were on-site when notified or within 90 minutes if they were off-site when notified. 5.2.6 Direct the Administration and Support Coordinator to establish the TSC in accordance O with Step 5.3 of this procedure. Brief the Administration and Support Coordinator concerning the emergency outlined in Step 5.2.2. If any of the information concerning the emergency is unclear, direct the Administration and Support Coordinator to determine the required information. Ensure that priorities for providing support are clear. 5.2.7 Continue the actions initiated by the Nuclear Shift Supervisor. The Emergency Director must focus on overall control of the emergency response and must not be distracted from this primary responsibility. 5.3 The Administration and Support Coordinator shall: 5.3.1 Verify that other TSC staff members have been notified (see step 5.2.5 above). 5.3.2 Supervise the establishment of the TSC. The TSC should be fully functional within 30 minutes of the start of activation. O
i EP-301-1 Rev. 0.B Page 6 NOTE: The subsequent steps of this procedure assume that the TSC functions have not been moved to an alternate location. If the TSC is not habitable, documents and personnel should be moved to the Control Room as directed by the Emergency Director. Since conges-tion and confusion in the Control Room is unacceptable, some TSC functions may have to be transferred to an alternate location (for example, the Operational Support Center (OSC) or the Emergency Operations Facility (EOF). 5.3.3 Check out and maintain the following communications circuits: Type
- 1. NRC Operations (ENS) Hotline
- 2. NRC-HPN Dedicated
- 3. Control Room Direct Ring
- 4. EOF Direct Ring
- 5. Michigan State Police Direct Ring
- 6. Monroe County Sheriff Direct Ring
- 7. OSC Direct Ring
- 8. Security Building Dedicated
- 9. NRC-Designated use Dedicated (two lines)
- 10. 45 lines General Business
- 11. 2 lines Conferencing
- 12. Facsimile General Business
- 13. Public address -
- 14. Plant Intercom (HYCOM) -
- 15. Operations Radio
- 16. Security Radio 5.3.4 Check that the emergency equipment listed in Attachment 1 is functional, and that the materials, equipment, and documents are available.
O
() EP-301-1 Rev. 0.B Page 7 5.3.5 As soon as sufficient emergency personnel are availa'ie, r direct that a contamination control , station and security checkpoint be established at the entrance to the TSC. l NOTE: No additional checkpoint should be established which could impede traffic between the Control Room and 3 the TSC. i 5.3.6 Ensure that the number of people allowed in the TSC is held to about 25 to limit congestion and confusion (approximately 20 i persons from Edison and 5 from the NRC). O I
- O
EP-301-1 Rev. 0.B LIST OF EMERGENCY EOUIPMENT AND DOCUMENTS TECHNICAL SUPPORT CENTER Check that the following equipment is available and functional: OUANTITY ITEM QUANTITY AVAILABLE
- 1. Eberline RMl4 (Frisker) or Ludlum 177 (Frisker) 2
- 2. Air sampler 1
- a. Extra heads 3 1
- b. HD-28 silver zeolite cartridges 20
- c. Filters 20
- 3. Dose rate meter (RO-2) 1
- 4. Dosimeter charger and battery 1 25
( ) 5. Self-reading Dosimeters, 500 mR
- 6. Self-reading Dosimeters, 100 mR 25
- 7. Portable area radiation monitor 1 l
- 8. Full sets of protective clothing
- a. Coveralls 30 pr.
I b. Cloth hoods 30
- c. Plastic shoe covers 30 pr.
- d. Rubber shoe covers 30 pr.
- e. Cotton glove liners 30 pr.
- f. Rubber gloves 30 pr.
- g. Surgeons' caps 30
- 9. Respirators 25 Attachment 1 Page 1 of 3
EP-301-1 Rev. 0.B QUANTITY ITEM QUANTITY AVAILABLE
- 10. Potassium Iodide (bottles) 10
- 11. Telecopy/ Facsimile 1
- 12. Copy machine 1
- 13. Typewriter 2
- 14. Supply cabinet 1
- 15. Various Administrative supplies
- 17. File cabinets 2
- 18. Status boards for:
- a. Plant parameters 1
- b. Environmental samples 1
- c. Meteorological data 1
- 19. TI Silent 700 terminal 2
- 20. Apple II Computer 1
- 21. Aperture card reader and printer 1
- 22. Radiation monitoring equipment -
direct, airborne, I-131. 3
- 23. Pre-printed signs designating alternate TSC locations 2 Check that the following documents are available:
ITEM OUANTITY AVAILABLE
- 1. Final Safety Anal /sis Report (FSAR) 1 set YES NO
- 2. Technical Specifications 1 set YES NO Attachment 1 Page 2 of 3 9
EP-301-1 Rev. 0.B ITEM QUANTITY AVAILABLE
- 3. Piping and Instrumentation Diagram 1 set YES NO (P& ids)
- 4. Structural Drawings 1 set YES NO
- 5. Plant Procedures 1 set each YES NO
; 6. Operating Records 1 set YES NO
- 7. OSRO records and reports 1 set YES NO
- 8. Emergency Plan 1 copy YES NO
- 9. State and County F2ergency 1 copy each YES NO Response Plans
- 10. Off-site population dose data 1 set YES NO
- 11. Radiation exposure histories 1 set YES NO I
( ) 12. Environmental radiological monitoring records 1 set YES NO
- 13. Security Contingency Plan (classified) 1 copy YES NO
- 14. Physical Security Plan (classified) l copy YES NO
- 15. Security Standard Operating Procedures 1 set YES NO
- 16. Emergency Plan Implementing Procedures 2 sets YES NO i
- Attachment 1 Page 3 of 3
1
- i I %,
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EP-301-2 () Rev. 0.B ENRICO FERMI ATOMIC POh'ER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
TECHNICAL SUPPORT CENTER: SUPPORT FUNCTIONS
, RECORD OF APPROVAL AND CHANGES Submitted by rO Supervisor of Radiological- eksincy Date Response Preparedness Approved by O Chairman - Liaison CdKmittee Date Liaison Revision Committee
(} No. Submitted Date Approval Date 1 2 3 4 5 6 7 8 O
4 I i i i 1 i EP-301-2 Rev. 0.B l i i I ! f i i l ' i i l ENRICO FERMI ATOMIC POWER PLANT - UNIT NO. 2
- \
! Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE r i
Title:
TECHNICAL SUPPORT CENTER: SUPPORT FUNCTIONS I h l l l
---,,... _ .__-_ _ _ _ , _ _ = _ , _ _ . . _ _ _ _ _ _ _ _ _ _ . - -
EP-301-2 Rev. 0.B TECHNICAL SUPPORT CENTER: SUPPORT FUNCTIONS TABLE OF CONTENTS Page 1.0 Purpose.............................................. 1 2.0 References........................................... 1 3.0 Entry Conditions..................................... 2 4.0 General Information.................................. 2 5.0 Procedure............................................ 3
I EP-301-2 Rev. 0.B Page 1 , 1.0 Purpose To delineate the responsibilities and actions of the staff in the Technical Support Center (TSC). 2.0 References 2.1 Enrico Fermi Atomic Power Plant Unit 2 Radiological
- Emergency Response Plan, Section B (On-site Emergency Organization), Section F (Emergency Communications),
Section H (Emergency Facilities and Equipment) , Section I (Accident Assessment), Section J (Protective Response), Section K (Radiological Exposure Control), and Section M (Reentry and Recovery Planning and Post-Accident Operations Planning). 2.2 Functional Criteria for Emergency Response Facilities (NUREG 0696) Section 2 (Technical Support Center). 2.3 Technical Support Center - Activation (EP-301-1). 2.4 Classification of Emergencies (EP-101). 2.5 Unusual Event (EP-102). 2.6 Alert (EP-103). 2.7 Site Area Emergency (EP-104). I 2.8 General Emergency (EP-105). 2.9 Manual Dose Assessment Calculation Procedure (EP-303-3). 2.10 Selection and Use of Respiratory Protection Equipment (65.000.20). 2.11 Radiation, Contamination, and Airborne Guides and l Limits (61.000.05). I O
}
EP-301-2 Rev. 0.B Page 2 3.0 Entry Conditions The TSC is activated for the following classes of emergencies:
- 1. Alert.
- 2. Site Area Emergency.
- 3. General Emergency.
4.0 General Information 4.1 The TSC is equipped to enable the TSC staff to assess plant status and make recommendations to the Emergency Director concerning plant operations, corrective actions, and protective actions. 4.2 TSC Data Systems 4.2.1 TSC data systems are available for the following:
- 1. Reviewing the accident sequence.
- 2. Determining appropriate mitigating actions.
- 3. Evaluating the extent of damage to plant systems.
- 4. Determining plant status during recovery.
4.2.2 TSC data available for evaluation shall consist of the following:
- 1. Meteorological conditions.
- 2. Radiological release information.
- 3. Plant parameters significant for evaluating the emergency situation.
4.2.3 The TSC staff is responsible for monitoring the data available in step 4.2.2 and providing recommendations to the Emergency Director concerning plant operations, corrective actions, and protective actions. O
f
) EP-301-2 Rev. 0.B Page 3 5.0 Procedure 5.1 As TSC staff personnel arrive they are assigned tasks to perform in order to provide the Emergency Director with the information and support he requires in order to evaluate and mitigate the emergency.
- 1. Plant status and dynamics prior to and during the accident.
- 2. Performance of accident' mitigation functions.
- 3. Current status and trend of the accident.
- 4. Damage to the plant systems and equipment.
- 5. Status of emergency operations (including personnel activity in the plant) .
- 6. Magnitude of any radiological release to the j environment.
- 7. Prevailing meteorological status.
- 8. Projected levels of radioactivity resulting from an airborne or waterborne release.
- 9. Potential impact of radiological, hazards on public health and safety.
5.2 The Administration and Support Coordinator shall supervise the establishment of the TSC. He shall assign personnel to complete the steps necessary to activate the TSC in accordance with EP-301-1 (TSC: Activation). He shall also be responsible for the following: 5.2.1 Coordinating logistic support for emergency personnel. 5.2.2 Advising the Emergency Director and Nuclear Operations Staff on matters relating to logistic support (personnel and equipment) . 5.2.3 Establishing and maintaining a long term record file for the emergency. This record . file shall be maintained as a legal record of O the emergency including, as a minimum, times of notifications of Federal, State and local l
1 l EP-301-2 Rev. 0.B Page 4 agencies, all notification forms, all chrono-logical logs of the emergency maintained by the individuals assigned to the TSC, and an overall chronological log of all events occurring during the emergency. 5.2.4 Providing work schedules for Nuclear Operations emergency response personnel. 5.2.5 Supervising the status board updaters, clerks, communicators, and secretaries in the performance of their duties. 5.3 The following personnel are assigned to the TSC and are responsible for carrying out their specific duties. 5.3.1 Emergency Director
- 1. Coordinating and directing the combined activities of Detroit Edison personnel in the Control Room, Technical Support Center, Operational Support Center, and elsewhere on owner-controlled property.
- 2. Classifying the emergency.
- 3. Notifying off-site plant, corporate, and government personnel. (Upon activation of the EOF, the EOF Coordinator is the liaison to all off-site agencies.
- 4. Issuing instructions to emergency response teams and ensuring that the
, appropriate procedures are being followed, i 5. Directing dose projection and assessment and recommending off-site protective action measures. (Upon activation of the EOF, the EOF Coordinator is responsible for this function.)
- 6. Ensuring continuity of on-site resources.
- 7. If necessary, authorizing plant emergency workers to receive radiation doses in excess of normal 10CFR20 limits.
EP-301-2 Rev. 0.B Page 5 Emergency exposure limits are described in Health Physics Procedure 69.000.15 (Emergency Exposure Limits). 5.3.2 Technical Engineer
- 1. Providing recommendations to the l
Emergency Director concerning plant technical matters.
- 2. Providing technical support.
- 3. Providing work assignments for Technical and Engineering Groups.
5.3.3 Nuclear Safety Advisor
- 1. Advising the Emergency Director on engineering matters.
- 2. Providing work assignments for Nuclear Engineering support groups.
5.3.4 Radiation Protection Advisor l
- 1. Performing dose projections with assistance from the Dose Assessment Team.
l i
- 2. Dispatching Radiological Emergency Teams on-site.
l 3. Evaluating on-site radiological surveys.
- 4. Maintaining personnel exposure records.
- 5. Ensuring that radiation protection equipment, such as dosimetric devices, respiratory protection gear, and protective clothing is issued and controlled.
- 6. Advising the Emergency Director concerning radiological protective actions.
- 7. Directing decontamination activities.
S 8. Providing work assignments for radiation
) protection personnel.
EP-301-2 Rev. 0.B Page 6 5.3.5 Environmental Assessment Team
- 1. Assessing meteorological conditions
- 2. Evaluating results of off-site environmental surveys
- 3. Performing both on-site and off-site dose assessment and projections 5.3.6 Radiochemistry Advisor
- 1. Directing in-plant sampling activities.
- 2. Directing Radiochemistry Laboratory activities.
- 3. Advising the Emergency Director on radwaste processing, storage, and disposal.
5.3.7 Security Liaison Officer
- 1. Ensuring that site security is maintained and appropriate contingency measures are implemented.
- 2. Ensuring that security and traffic control measures are in effect for on-site, including traffic direction during an evacuation.
- 3. Establishing and maintaining a security checkpoint at the entrance to the TSC.
5.3.8 Quality Assurance Advisor
- 1. Maintaining records concerning the emergency.
- 2. Assisting in preparation of specific emergency procedures as required.
- 3. Ensuring all quality assurance procedures applicable to the emergency are followed.
O
i () EP-301-2 Rev. 0.B Page 7 l 5.3.9 Thermal Hydraulics, Mechanical, Electrical and Instrument and Control Engineers are responsible for advising the Nuclear Safety Advisor on technical plant matters. 5.3.10 The Communicator
- 1. Making any required notifications and communications as directed.
- 2. Notifying additional support personnel as directed.
5.3.11 Additional personnel are assigned to perform the following functions:
- 1. Maintaining the status boards current.
- 2. Providing administrative support such as typing, copying, and sending and filing 1
messages. 5.4 If the emergency situation is such that the EOF must / be activated, some functions carried out initially by the TSC staff shall be transferred to EOF Personnel. 5.4.1 Any off-site protective actions which have been planned or are in progress must be reported to the EOF Coordinator. 5.4.2 For off-site radiological monitoring and dose assessment the Radiation Protection Advisor shall:
- 1. Contact the Radiation Protection Coordinator in the EOF.
- 2. Report the status of off-site activities especially with regard to the following:
- a. Radiological release information.
- b. Meteorological data.
- c. Surveys which have been performed.
- d. Samples which have been takes.
- e. If Off-Site Radiological Emergency Team members have been activated.
EP-301-2 Rev. 0.B Page 8
- 3. Relay any additional data which the Radiation Protection Coordinator may require in order to assume off-site monitoring responsibilities.
5.4.3 Any public affairs information which has been released or is to be released shall be reported to the Public Information Coordinator in the EOF. 5.5 Relocation of the TSC 5.5.1 If the airborne radioactivity levels in the TSC exceed the limits of Health Physics Procedure 61.000.05 (Radiation, Contamination, and Airborne Guides and Limits) at any time during the emergency:
- 1. All personnel shall don respiratory equipment in accordance with Health Physics Procedure 65.000.20 (Selection and Use of Respiratory Protection Equipment).
- 2. The Emergency Director shall transfer the TSC functions to alternate locations:
- a. Some TSC support functions may be transferred to the Control Room.
- b. Most TSC functions will be transferred to the Emergency Operations Facility (EOF).
5.5.2 If area radiation levels exceed the designated limits, TSC support functions will be similarly transferred at the direction of the Emergency Director. END
.= - .. .
1 4 EP-302-1 Rev. 0.B ( i ENRICO FERMI ATOMir POh'ER PLANT UNIT.NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
OPERATIONAL SUPPORT CENTER: ACTIVATION RECORD OF APPROVAL A CHANGES Submitted by- (' )-
- j. Supervisor of Radio gical-Emergency Date Response Preparedn i Approved by fs Chairman - Liahp6n Committee Date l' Liaison Revision Committee No. Submitted Date Approval Date
( 1 i ~ 2 3 4 5 6 7 8 O
9 l I EP-302-1 Rev. 0.B I l I< 4 ENRICO FERMI ATOMIC POWER PLANT i UNIT NO. 2 i Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
OPERATIONAL SUPPORT CENTER: ACTIVATION i i ,I I r I 1 j i l
EP-302-1 Rev. 0.B OPERATIONAL SUPPORT CENTER: ACTIVATION l TABLE OF CONTENTS Page 1.0 Purpose............................................... 1 2.0 References............................................ 1 3.0 Entry Conditions...................................... 1 4.0 General Information................................... 1 5.0 Immediate Action...................................... 1 6.0 Follow-up Actions..................................... 3 Attachments List of Emergency Equipment and Documents.......... Attachment 1 Layout of the Operational Support Center........... Attachment 2 l t i I l 1
EP-302-1 O- Rev. 0.B Page 1 1.0 Purpose To prescribe the procedures for activation and functioning of the Operational Support Center (OSC). 2.0 References 2.1 Enrico Fermi Atomic Power Plant Unit 2 Radiological Emergency Response Plan, Section B (Oncite Emergency Organization), Section F (Emergency Communications), and Section H (Emergency Facilities and Equipment). 2.2 Functional Criteria for Emergency Response Facilities (NUREG-0696), Section 3 (Operational Support Center). 2.3 Alert (EP-103). 2.4 Site Area Emergency (EP-104). 2.5 General Emergency (EP-105). 3.0 Entry Conditions () The OSC may be activated for any of the following classes of emergencies:
- 1. Unusual Event.
- 2. Alert.
- 3. Site Area Emergency.
- 4. General Emergency.
4.0 General Information The OSC is the designated location where non-licensed operations support personnel routinely report when not actively engaged in emergency assignments. The alternate OSC is the Machine Shop. 5.0 Immediate Actions 5.1 The following personnel shall normally report to, and be dispatched from the OSC:
- 1. Fire Brigade.
- 2. Damage and Rescue Team.
O
EP-302-1 Rev. 0.B Page 2
- 3. On-Site Radiological Emergency Team.
I
- 4. Personnel Monitoring Team.
- 5. Instrument Technicians.
- 6. Engineers (not specifically assigned other functions in the Control Room or in an Emergency Center).
- 7. General maintenance personnel.
- 8. Off-shift personnel called in to support emergency efforts.
- 9. On-shift personnel not assigned during emergencies.
5.2 The Maintenance Engineer (or his alternate the General Foreman or Senior Engineer) shall assume the role of OSC Coordinator and shall perform the following: 5.2.1 On arrival, report to the Emergency Director that the OSC is being activated. 5.2.2 Assign an individual to inventory the equipment listed in Attachment 1. 5.2.3 Ensure phone lines are checked out and maintained between the OSC and the following: Type
- 1. Control Room Direct Ring
- 2. TSC Direct Ring
- 3. 4 lines General Business 5.2.4 When the phone lines are checked, report to the Emergency Director that the OSC has been activated.
l 5.2.5 Coordinate with Emergency Team seaders the following:
- 1. Augmenting Emergency Teams using unassigned or off-shift personnel assembled in the OSC.
O
EP-302-1 Rev. 0.B Page 3
- 2. Activating off-shift personnel during
~
back shifts.
- 3. Assist in providing replac3 ment emergency equipment and necessary parts and support for emergency damage repair.
5.2.6 Supervise the assignment of required personnel to emergency tasks as directed by the Emer-
' gency Director or Nuclear Shift Supervisor.
5.3 In the event the OSC becomes uninhabitable, the OSC Supervisor shall, at the direction of the Emergency Director, relocate OSC personnel to the Machine Shop or other location and establish this as the new assembly and staging area. When the alternate OSC is established, report to the Emergency Director that the alternate OSC is established. 6.0 Follow-Up Actions The OSC Supervisor shall: () 6.1 Keep the Emergency Director informed as to the manning status of the OSC. 6.2 Keep the Emergency Director informed as to the status of Jobs being performed by Emergency Team members and other personnel assigned to the OSC. 6.3 Make recommendations to the Emergency Director concerning additional support personnel required. 6.4 Continue to support the Emergency Team Leaders by l providing additional personnel and equipment, as l necessary. i 1
EP-302-1 CJ Rev. 0.B LIST OF EMERGENCY EQUIPMENT AND DOCUMENTS OPERATIONAL SUPPORT CENTER QUANTITY ITEM OUANTITY AVAILABLE
- 1. Fire protection clothing:
- a. Yellow turnout coats 12
- b. Boots 12 pr.
- c. Fire-fighter gloves 12 pr.
- d. Fire hats 12
- e. Fire-resistant pants with suspenders 12 pr.
- 2. Portable lights (with extra sets-of batteries)
- a. Flashlights (5 cell) 5
- b. Six volt lantern 1
- 3. Portable extinguishers:
l l a. CO2 3 i /3 b. Chemical (404 ansul) 1 l D
- 4. Scott Air Paks
- a. Without speak-easy 8
- b. With speak-easy 6
- 5. Scott Air Bottles 32
- 6. Hand Truck l i
- 7. Trauma II First Aid Kit 1 __
- 8. Sets of Air Splints 2
- 9. Life Lines (50 f t) 4
- 10. Mask Cleaning solution with Bucket i
- 11. MSA Air Bottles 4 Attachment 1
, Page 1 of 5
EP-302-1 Rev. 0.B LIST OF EMERGENCY EOUIPMENT IN FIRE PROTECTION EOUIPMENT LOCKER
'JANTITY ITEM QUANTITY AVAILABLE
- 1. Fire axe 1
- 2. Wrecking bar 1
- 3. Canvas tarps 2
- 4. Bolt cutters 1
- 5. MSA Air Packs 5
- 6. MSA Air Bottles 6
- 7. Sets of Rain Gear 3
- 8. Small Valve Wrenches 2
- 9. Medium Valve Wrenches 2
- 10. Air Jack l
- 11. Assorted Pliers, Screwdrivers and Fuse Pullers
- 12. Administrative Supplies Attachment 1 Fage 2 of 5 O
EP-302-1 Rev. 0.B LIST OF EMERGENCY EOUIPMENT IN FIRST AID AND STRETCHER LOCKERS QUANTITY ITEM QUANTITY AVAILABLE
- 1. Trauma II First Aid Kit 1
- 2. Bottles of O2 2
- 3. 02 Regulators 2
- 4. Blankets 4
- 5. Plastic Stokes Stretcher 2
- 6. Fire Extinguisher
- a. CO 2 3
- b. Chemical (404 ansul) 9 O
O Attachment 1 Page 3 of 5
EP-302-1 Rev. 0.B LIST OF EMERGENCY EOUIPMENT IN HEALTH PHYSICS LOCKERS QUANTITY ITEM OUANTITY AVAILABLE
- 1. Eberline RMl4 (Frisker) or Ludlum 177 Frisker) 6
- 2. Eberline RO-2 (Dose rate meter) 6
- 3. Portal area radiation monitor 1
- 4. Protective clothing:
- a. Coveralls 30 pr.
- b. Cloth hoods 30
- c. Plastic shoe covers 30 pr.
- d. Rubber shoe covers 30 pr.
- e. Cotton glove liners 30 pr.
- f. Rubber gloves 30 pr.
- g. Surgeons' caps 30
- 5. Partial sets of protective clothing
- a. Pairs of gloves with cloth liners 50
- b. Pairs of shoe covers 100
- 6. High Range Dosimeters 20
- 7. Air samples and filters / cartridges 5
- a. Extra filter heads 15
- b. Particulate filters 200
- c. Silver zeolite cartridges 50 l
- 8. Dosimeter charger with extra batteries 2
- 9. Plastic bags 60
- 10. Survey maps 200 l
t 11. Boxes of smears 40 I 1 Attachment 1 Page 4 of 5 O
O EP-302-1 Rev. 0.B QUANTITY ITJM QUANTITY AVAILABLE
- 12. Radiological barrier materials
- a. Rope (150 ft. rolls) 10
- b. Caution signs and assorted inserts 20
- c. Step off pads 10
- 13. MSA SCBA with 10 extra bottles 5
- 14. Rolls of 2 in. masking tape 50
- 15. Full face respirators with extra filters 10
- 16. Flashlights
- a. Extra batteries 10
- 17. Potassium Iodide (bottles) 5
- 18. 50 foot extension cords 2
()19. Administrative supplies 1
- 20. Emergency Plan Implementing Procedures 1 (1 set) o Attachment 1 Page 5 of 5
O O O i CONIROL ROOM i MM l
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EP-303-1 rN, Rev. 0.B (_,- ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
EMERGENCY OPERATIONS FACILITY: ACTIVATION
, RECORD OF APPROVAL AND CHANGES Submitted by eb itgE Emergency Date Supervisor of Radiol Response Preparedn Approved by i()
Chairman - Lisison Committee Date Liaison Revision Committee No. Submitted Date Approval Date (' ) 2 3 l 4 _ _ 5 6 7 8
,m U
I EP-303-1 Rev. 0.B l l 4 l ENRICO FERMI ATOMIC POWER PLANT l UNIT NO. 2 i Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE l
Title:
EMERGENCY OPERATIONS FACILITY: ACTIVATION l l l i
-.__,,em_~~.___,--.www_,,m._. .m_.....,,-w- w-wv -- .,we c, e ww-r--wwr----w-=- -- -----v
i l EP-303-1 Rev. 0.B EMERGENCY OPERATIONS FACILITY: ACTIVATION TABLE OF CONTENTS Page 1.0 Purpose............................................... 1 2.0 References............................................ 1 3.0 Entry Conditions...................................... 1 4.0 General Information................................... 1 5.0 Procedure............................................. 2 Attachments List of Emergency Equipment and Documents.......... Attachment 1 Layout of the Emergency Operations Facility........ Attachment 2 N
\
' EP-303-1 Rev. 0.B Page 1 1.0 Purpose To prescribe the steps for activation of the Emergency Operations Facility (EOF), and to delineate the responsi-bilities and actions of the EOF Coordinator. 2.0 References 2.1 Enrico Fermi Atomic Power Plant Unit 2 Radiological Emergency Response Plan, Section B (Onsite Emergency Organization), Section F (Emergency Communications), and Section H (Emergency Facilities and Equipment). 2.2 Functional Criteria for Emergency Response Facilities (NUREG-0696), Section 4 (Emergency Operations Facility) 2.3 Site Area Emergency (EP-104) 2.4 General Emergency (EP-105) () 2.5 Emergency Notifications (EP-290) 2.6 Emergency Operations Facility - Support Functions (EP-303-2) 2.7 Selection and Use of Respiratory Protection Equipment (65.000.20). 2.8 Radiation, Contamination, and Airborne Guides and Limits (61.000.05). 3.0 Entry Conditions The EOF is activated for the following classes of emergencies:
- 1. Site Area Emergency.
- 2. General Emergency.
4.0 General Information The EOF serves the following functions:
- 1. Command post for the coordination of the emergency
-~ response actions by off-site organizations.
N./ DJ
EP-303-1 Rev. 0.B Page 2
- 2. Coordination of off-site radiological and environmental assessments.
- 3. Determining and recommending protective actions for the public.
- 4. Coordination of information provided to the Joint Public Infccmation Team for public dissemination.
- 5. Providing support to the Emergency Director on nuclear operations.
- 6. Management of recovery operations.
5.0 Procedure 5.1 Upon activation of the EOF, the first individuals to arrive shall: 5.1.1 Energize the following equipment if not already energized:
- 1. Lighting system.
- 2. HVAC system.
- 3. Area radiation monitor.
- 4. Air sampler.
- 5. Data acquisition system.
5.1.2 Check the area radiation level and the airborne contamination level.
- 1. If the airborne radioactivity level exceeds the limit of Health Physics Procedure 61.000.05 (Radiation, Contamination and Airborne Guides and Limits), don respiratory equipment in accordance with Health Physics Procedure 65.000.20 (Selection and Use of Respiratory Protection Equipment) .
O
EP-303-1 l f)) s_ Rev. 0.B Page 3
- 2. If either level exceeds the established limits:
- a. Contact the Emergency Director and inform him of the condition of the EOF. The Emergency Director shall direct that EOF functions be moved to another area.
- b. Hang signs directing personnel to proceed to the alternate area directed by the Emergency Director,
- c. Proceed to the alternate location as specified by the Emergency Director.
5.2 Upon his arrival at the EOF the Manager, Wayne Division (or his alternate, the Director-Customer and Marketing Services, Wayne Division) shall assume the role of Emergency Operations Facility Coordinator (EOF Coordinator) and shall perform the following: () NOTE: In determining technical information, the EOF coordinator may direct an appropriately qualified member of the EOF staff to obtain the information and provide him with a summary. 5.2.1 Contact the Emergency Director (in the Control Room or Technical Support Center). 5.2.2 Review the current status of the emergency including:
- l. Background information leading up to the emergency.
- 2. Indications and suspected cause of the emergency, including existing hazards to personnel, damage to plant systems, instrumentation, and other equipment; and radiation levels or releases.
- 3. Corrective actions taken.
- 4. Status of execution of Emergency Plan Implementing Procedures, especially s activation of Emergency Teams and
,) performing required notifications.
EP-303-1 Rev. 0.B Page 4
- 5. Present plant lineups, and plant evolu-tions or operations in progress.
- 6. Evolutions or operations which have been directed or are planned, but not yet carried out.
- 7. Status of activating the off-Site Radiological Emergency Team and the status of off-site samples and surveys.
- 8. Status of dose assessments performed and protective actions taken on-site or recommended to the public.
- 9. Status of any press releases or other public information which has been released.
5.2.3 Activate the EOF staff, or ensure that they have already been activated (see EP-290, Emergency Notifications). Personnel assigned to the EOF, when notified of an emergency, must report to their positions within 30 minutes if they are on-site when notified, or within 90 minutes if off-site when notified. The following personnel are normally assigned to the EOF staff:
- 1. Emergency Officer - Vice President -
i Nuclear Operations.
- 2. Security Liaison - the Senior Administrator - Security (or his alternate the Security Nuclear Coordinator).
- 3. Nuclear Operations Advisor (off-shift Nuclear Shift C"?ervisors).
! 4. Radiation Protection Coordinator - Senior l Health Physicist (or his alternate the Radiation / Chemistry Engineer). l 5. Public Information Coordinator - I Director-Public Information (or his alternate the Senior Journalist). i l
EP-303-1 Rev. 0.B Page 5
- 6. EOF Administrator - Director -
Administration (or his alternate the Supervisor-Planning).
- 7. Radiological Emergency Team Coordinator -
Wayne Division Dispatcher.
- 8. Radiation Protection Communicator.
- 9. Environmental Assessment Team - Dose Assessors and Meteorologist.
- 10. Emergency Laboratory Technicians.
- 11. Communicators.
- 12. Clerical support.
- 13. Couriers.
- 14. Status board updaters.
) 15. Consultants and EOF Technical Liaison for the Nuclear Operations Advisor.
5.2.4 Direct the EOF Administrator to carry out step 5.3 of this procedure to continue establishing the EOF. 5.2.5 Supervise the establishment of the EOF. NOTE: The subsequent steps of this proce-dure assume that the EOF functions have not been moved to an alternate location. If the EOF is not habitable, documents and personnel should be moved to the alternate location as directed by the EOF Coordinator after conferring with the Emergency Director. 5.3 The EOF Administrator shall: 5.3.1 Check out and maintain the following communi-cation circuits: O U
EP-303-1 Rev. 0.B Page 6 Type
- 1. NRC Operations (ENS) Hotline
- 2. NRC-HPN Dedicated
- 3. TSC Direct Ring
- 4. Michigan State Police Direct Ring
- 5. Monroe Country Sheriff Direct Ring
- 6. NRC Designated use General Business (2 lines)
- 7. General Offices Direct Ring
- 8. Joint Public Information Center (JPIC) Direct Ring
- 9. 37 lines General Business
- 10. 2 lines Conferencing
- 11. Off-Site RET Members Radio
- 12. Security Radio
- 13. Facsimile machine General Business
- 14. Public Address -
- 15. Plant intercom (HYCOM) -
5.3.2 Assign an individual to check that the emergency equipment listed in Attachment 1 is functional and that the materials and documents are available. 5.3.3 Ensure that the number of people allowed in the EOF is held to 40 persons to limit congestion and confusion (9 persons from the NRC, 1 person from FEMA and 29 persons from Edison and local and state agencies). 5.4 Upon establishment of the EOF, the EOF Coordinator shall: 5.4.1 Maintain close contact with the Emergency Director in order to keep apprised of the plant status and of actions being carried out by the Emergency Director. 5.4.2 Be alert to potential off-site consequences of the emergency. 5.4.3 Supervise the functioning of the EOF staff. O
~. . _ -
l j
; EP-303-1 Rev. 0.B Page 7 l
5.4.4 Coordinate activities for off-site samples and surveys with the Radiation Protection Coordinator. 5.4.5 Keep the Emergency Officer informed of the activities of the EOF Staff, particularly with regard to off-site dose projections and recommended protective actions. 5.4.6 Recommend protective measures to off-site response organizations based on the results off-site dose projections. 5.4.7 Keep the Emergency Director apprised of actions taken off-site and of consequences off-site. i O l O
O EP-303-1 Re . 0.B LIST OF EMERGENCY EQUIPMENT AND DOCUMENTS EMERGENCY OPERATIONS FACILITY Check that the following equipment is available and functional: QUANTITY ITEM QUANTITY AVAILAuLE
- 1. Eberline RM14 (Frisker) or Ludlum 177 (Frisker) 2
- 2. Iodine air sampler insensitive to noble gas 1
- a. Extra heads 3
- b. Filters 100
- c. Silver zeolite cartridges 50
, 3. Dose rate meters (RO-2) 2
- 4. Dosimeter charger and battery 2
- 5. Dosimeters 15 -
- 6. Smear envelopes 100
- 7. Sample bags 50
- 8. Boxes of smears 6
- 9. Survey forms 100
- 10. TLDs 15
- 11. Respirators 10
- 12. Telecopy/ facsimile 1
- 13. Copy machine 1
- 14. Typewriter 1
- 15. Supply cabinet 1 Attachment 1 O<
Page 1 of 3 A
l EP-303-1 Rev. 0.B QUANTITY ITEM QUANTITY AVAILABLE
- 16. Various Administrative supplies
- 17. File cabinets 2
- 18. Apple II Computer 2
- 19. TI Silent 700 terminal 1
- 20. Pre-printed signs designating alternate 2 EOF locations Check that the following documents are available:
QUANTITY ITEM QUANTITY AVAILABLE
- 1. Final Safety Analysis Report (FSAR) 1 set YES NO
- 2. Technical Specifications 1 set YES NO
- 3. Piping and Instrumentation Diagrams 1 set YES NO (P&I D's)
- 4. Structural Drawings 1 set YES NO
- 5. Plant Procedures 1 set each YES NO
- 6. Operating Records 1 set YES NO
- 7. Evacuation Plans 1 set YES NO
- 8. Emergency Plan 1 copy YES NO
- 9. State and County Emergency 1 copy each YES JK)
Response Plans
- 10. Offsite population dose data 1 set YES NO
- 11. Radiation exposure histories 1 set YES NO
- 12. Environmental radiological monitoring 1 set YES NO records Attachment 1 Page 2 of 3
. -.- - . _ ._. .. .__ - -- -- . _ . = ._ . . .
QUANTITY ITEM QUANTITY AVAILABLE
- 13. Security contingency Plan (Classified) l each YES NO
- 14. Security Operations Procedures 1 set YES NO i
j 15. Physical Security Plan (classified) l each YES NO t i 16. Emergency Plan Implementing Procedures 2 sets YES NO i .i i f l I I O i i I Attachment 1 O Page 3 of 3 f
..._____.,....-,_._.--._.-_.,...m.. ._,m.
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CONFEREM
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l ,- ( 5' _ 00 LUUUU000UUO(,
\ \F-ff 1) NUCLEAR OPERATIONS ADVISOR 6) SECRETARY f;
-} 2) RADIATION PROTECTION COORDINATOR 7) COMMUNICATOR 11) PUBLIC AFFIARS LIAISON o
"~
$ 3) CONSULTANTS 8) SECURITY LIAISON
- 4) ENVIRONMENTAL ASSESSMENT TEAM (E.A.T) 9) STATE LIAISON. 12) EOF ADMINISTRATOR (METEOROLOGIST)
- 5) ENVIRONMENTAL ASSESSMENT TEAM (E. A.T) 10) EOF COORDINATOR 13) EMERGENCY OFFICER (DOSE)
EP-303 ,
Rev. 0.B ENRICO FERMI ATOM 1C POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
EMERGENCY OPERATIONS FACILITY: SUPPORT FUNCTIONS RECORD OF APPROVAL AND CitANGES Submitted by e Supervisor of Radio o4idal- Emergency Date Response Prepared s Approved by n l, Chairman - L1 94 son Committee Date t Liaison , Revision
~
Committee No. Submitted Date Approval Date 1 i 2 , i
- 3 1
4 i i 5 6 t 7 - 8 l l !O '
e t l I l EP-303-2
- j. Rev. 0.B i
f i 1 ! ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 e i Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE i l
Title:
EMERGENCY OPERATIONS FACILITY: SUPPORT FUNCTIONS l l .i f 1 O e
f i 4 CP-303-2 i ! s Rev. 0.B 1 EMERGENCY OPERATIONS FACILITY: SUPPORT FUNCTIONS 1
, TABLE OF CONTENTS j Page l 1.0 Purpose............................................... 1 i
2.0 References............................................ 1
- 3.0 Entry Conditions...................................... 1 i
- 4.0 General Information................................... 1 l 5.0 Procedure............................................. 2 1
l I s _. y,___,,.,- - - . . _ _ _ - - , - ._.m, ,-
- - - - - - - + , - . , - . _ . . - _ . - . . _ . . . _ - , , , - - - , _ _._. _ -.m ,
EP-303-2 Rev. 0.B Page 1 1.0 Purpose To delineate the responsibilities and actions of the ! Emergency Operations Facili,ty (EOF) Staff. I 2.0 References I 2.1 Enrico Fermi Atomic Power Plant Unit 2 Radiological Emergency Response Plan, Section B (Onsite Emergency Organization), Section F (Emergency Communications),* Section H (Emergency Facilities and Equipment), Section I (Emergency Facilities and Equipment) , Section J (Protective Response), Section K (Radiological Exposure Control), and Section M (Reentry and Recovery Planning and Post-Accident Operations Planning).
. 2.2 Functional Criteria for Emergency Response Facilities (NUREG-0696), Section 4 (Emergency Operations Facility).
() 2.3 Site Area Emergency (EP-104). 2.4 General Emergency (EP-105). ! 2.5 Emergency Notifications (EP-290). 2.6 Emergency Operations Facility - Activation , (EP-303-1). 2.7
- Manual Dose .Tssessment Calculation Procedure i (EP-303-3).
3.0 Entry Conditions ,w The EOF is activated for the following classes of i emergencies:
- 1. Site Area Emergency.
- 2. General Emergency.
! 4.0 General Information The EOF serves the following functions:
- 1. Command post for the coordination of the emergency
() 1 response actions by off-site organizations.
1 EP-303-2 Rev. 0.B Page 2
- 2. Coordination of off-site r,adiological and environmental assessments.
- 3. Determining and recommending protective actions for the public.
- 4. Coordination of information provided to the Joint Public Information Team for public dissemination.
- 5. Providing support to the Emergency Director on nuclear operations.
- 6. Management of recovery operations.
5.0 Procedure 5.1 The responsibilities of personnel assigned to the EOF are described in the following. 5.1.1 Emergency Officer The Emergency Officer is in overall charge of the emergency. Reporting to him are the Emergency Director, EOF Coordinator, and the JPIC Administrator. His responsibilities include:
- 1. Ensuring that the full resources of Detroit Edison Company are made available as required to secure the plant systems and to minimize the effects of the incident on plant personnel and the public. This includes availability of other utilities and vendor resources.
- 2. Ensuring information released to the public is accurate and directed through proper channels.
- 3. Communications with Corporate Headquarters.
- 4. Establishing the long term emergency and recovery organizations.
O
EP-303-2 O' Rev. 0.B Page 3 5.1.2 Emergency Operations Facility (EOF) Coordinator
- 1. Coordinating and directing activities in EOF.
- 2. Notification of Government Emergency response agencies.
- 3. Recommending protective actions to Government Emergency response agencies.
5.1.3 Radiation Protection Coordinator
- 1. Coordinating and directing off-site dose assessment activities.
- 2. Determining survey areas for Radiological Emergency Teams.
- 3. Determining environmental sample media.
4. Evaluating results of off-site environmental surveys l
- 5. Advising the EOF Coordinator on protective actions to be taken.
- 6. Directing activities in the analysis laboratory.
- 7. Ensuring proper Health Physics records of the emergency are maintained.
- 8. Coordinating radiation protection for personnel in the EOF.
5.1.4 The Radiation Protection Communicator makes any required notifications and communications as directed by the Radiation Protection Coordinator. 5.1.5 Environmental Assessment Team
- 1. Assessing meteorological conditions.
- 2. Performing dose assessment and projections.
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- EP-303-2 Rev. 0.B Page 4 5.1.6 Security Liaison
- 1. Coordinating access and egress of off-site personnel on owner-controlled areas.
- 2. Acting as security liaison for security personnel at the Michigan State Police Emergency Operations Center, the Joint Public Information Center, and the TSC.
- 3. Acting as liaison between security operations and the EOF Coordinator.
- 4. Establishing and maintaining a security checkpoint at the entrance to the EOF.
5.1.7 Radiological Emergency Team (R.E.T.) Coordinator
- 1. Coordinating efforts of the Off-Site Radiological Emergency Teams.
. 2. Assigning survey areas.
- 3. Reporting the results of off-site surveys to the Radiation Protection Coordinator.
5.1.8 Nuclear Operations Advisor
- 1. Providing updated information on the operational status of the plant.
- 2. Advising the EOF Coordinator on the status of plant operations.
5.1.9 Putlic Information Coordinator
- 1. Coordinating public information with the Joint Public Information Team.
- 2. Liaison between the Emergency Officer and the Joint Public Information Team.
- 3. Liaison between EOF and near-site news media center.
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EP-303-2 Rev. 0.B Page 5 5.1.10 EOF Administrator
- 1. Supervising the establishment of the EOF.
- 2. Providing logistic support.
- 3. Providing documentation control and support.
- 4. Establishing and maintaining a long term record file for the emergency. This record file shall be maintained as a legal record of the emergency including, as a minimum, times of notifications of Federal, State and local agencies, all notification forms, all chronological '
logs of the emergency maintained by the individuals assigned to the EOF, and an overall chronological log of all events occurring during the emergency.
) 5. Supervising the communicators, clerks, status board updaters, and secretaries assigned to the EOF.
5.1.11 The Communicator
- 1. Making any required notifications and i communications as directed.
- 2. Notifying additional support personnel as directed.
5.1.12 Laboratory Technicians
- 1. Analyzing samples collected by the Off-Site RET members.
- 2. Reporting the results of the sample analysis to the Radiation Protection Coordinator.
O
EP-303-2 h Rev. 0.B Page 6 5.1.13 Additional support personnel, including clerks, secretaries, and status board updaters.
- 1. Providing administrative support, including copying, message typing and filing.
- 2. Ensuring all status board information is kept current.
5.2 All personnel shall keep a chronological log of all activities performed by them during the emergency and any other significant events. Tiiese logs shall be forwarded to the EOF administrator for inclusion into the long. term records. O END f e O
O EP-303-3 Rev. 0.B ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 Type: EMERGENCY PLAN IMPLEMENTING PROCEDURE
Title:
MANUAL DOSE ASSESSMENT CALCULATIONAL PROCEDURE O ' l e l l 0
EP-303-3 Rev. 0.B (v) MANUAL DOSE ASSESSMENT CALCULATIONAL PROCEDURE Table of Contents Page 1.0 Purpose............................................ 1 2.0 References......................................... 1 30 Entry Conditions................................... 1 4.0 General Information................................ 1 4.1 Introduction.................................. 1 4.2 Monitor Assumptions........................... 2 i 43 Isotopic Compositon of the Source............. 3 4.4 Primary Containment Leakage Rate.............. 4 4.5 Standby Gas Treatment System Filter Efficiency.4 4.6 Release Height................................ 4 4.7 Meteorological Conditions..................... 4 f)s s, 4.8 Fermi 2 Site Boundary Distances............... 5 5.0 Procedure for Projected Dose Assessment............ 6 5.1 Projected Whole Body Gamma Dose Based on Drywell Monitor Reading, Xe-133. (Equivalent)........................ Attachment 1 52 Projected Thyroid Inhalation Dose Based i on Drywell Monitor Reading - I-131 (Equivalent)........................ Attachment 2 53 Projected Whole Body Gamma Dose Based on Standby Gas Treatment System Monitor Reading - Xe-133 (Equivalent)....... Attachment 3 5.4 Projected Thyroid Inhalation Dose Based on Standby Gas Treatment System Monitor Reading - I-131 (Equivalent)........ Attachment 4 55 Emergency Classification Calculation - Worst Case Conditions............... Attachment 5
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EP-303-3 Rev. 0.B Page 1 1.0 Purpose _ To calculate doses received off-site prior to or following release of radioactive material. 2.0 References 2.1 " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents", Environmental Protection Agency, Office of Radiation Programs, Environmental Analysis Division, EPA-520/1-75-001, September, 1975 2.2 " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants", NUREG-0654, FEMA-REP-1, Revision 1, 1980 23 " Assumptions Used for Evaluating the Potential Radiological Consequences of a loss of Coolant Accident for Boiling Water Reactors", Reg. Guide 1 3 2.4 " Meteorological Programs in Support of Nuclear Power Plants", Reg. Guide 1.23, Rev. 1, September, 1981 2.5 " Meteorology & Atomic Energy", 1968 r k 30 Entry Conditions This procedure is used when there is a potential for a radioactive release to occur or a radioactive release has occurred. It is limited to the use of readings from the high activity range drywell monitor or the standby gas treatment system (SGTS) stack effluent monitor. 4.0 General Information 4.1 Introduction The manual method for Fermi 2 off-site dose and dose rate assessment involves the accident classification methods of NUREG-0654 as well as the EPA Protective Action Guidelines. The method addresses accidents occurring in the primary containment. NUREG-0654 site area emergencies and general emergencies are predicted. Total dose predictions offsite are com-pared to the Protective Action Guidelines. The manual method uses conservative assumptions similar to those of Regulatory Guide 13 The acci-dent scenario starts with releases of noble gases and iodines to the primary containment at reactor shutdown. The amounts of airborne activity are esti-(~s mated from monitor readings. The airborne activities leak to the reactor building at the design basis leak rate where they are exhausted immediately through an iodine filter to the environment at
EP-30?-3 Rev. 0.B Page 2 / ground level. The activities are then transpcrted instantaneously downwind to the dose point. Dose equations used are those for a semi-infinite cloud whose concentration is that for the center of a Gaussian plume. The dispersion parameters are those for the current Pasquill Stability Class at that distance downwind. 4.2 Monitor Assumptions The monitor locations chosen are an in-containment and a standby gas treatment system (SGTS) monitor. These monitors provide the idealized readings of rad (air)/hr and uCi/cc of Xe-133 equivalent respec-tively. The in-containment monitor is located on the outer wall of the drywell at the 605 ft eleva-tion. It views a portion of a cylindrical annulus cloud of gamma emitters and is not affected by beta radiation. The SGTS monitor is located in the standby gas treatment effluent stream after the iodine filter. It provides the effective Xe-133 activity concentration, based on energy emitted, at that point. All calculated monitor readings use the following assumptions.
- 1. For the purpose of determining the actual amount of noble gas released to the primary contain-ment, 100% of the core inventory of noble gases are instantaneously released to the entire pri-mary containment at reactor shutdown with per-feet mixing.
- 2. For the purpose of determining the actual amount of iodines airborne in the primary containment, 100% of the core inventory of noble gases plus 25% of the core inventory of iodines are instan-taneously released to the entire primary con-tainment at reactor shutdown with perfect mixing.
3 Nuclides with half-lives less than 3 minutes are omitted.
- 4. The design basis primary containment leak rate is used.
5 No mixing (holdup) in the reactor building is used. O
EP-303-3 g Rev. 0.B
/ Page 3 43 Isotopic Composition of the Source For noble gases with no delay time between shut-down and the accident, one would expect the nuclide mix to be the same as in the core inven-tory at shutdown. The maximum noble gas acti-vity would then be 100% of the core inventory.
To be conservative, this activity is assumed to be immediately airborne. The ratio of the actual to the calculated monitor readings would be a measure of the fraction of the 100% core activity that was actually released. The exclu-sion of iodine activity from the monitor readings would result in a conservative estimate of that fraction since the actual monitor reading could be higher due to iodines. For iodine, the amount of release relative to the noble gas release is unknown. Furthermore, the amounts airborne and available for leakage are unknown. Regulatory Guide 1 3 is used to obtain a conservative estimate of the relative O amounts of iodine released. This Regulatory Guide states that 100% of the noble gases and 25% of the iodines in the core inventory are airborne and available for leakage to the environment. It is assumed that, for the pur-pose of determining thyroid inhalation doses, the amounts of iodine released are always in this proportion; that is, the amount of iodine airborne in the primary containment will always be 25% of the iodine core inventory times the fraction of the Regulatory Guide 1 3 mixture that is actually airborne. This fraction is the ratio of the actual monitor reading to the calculated reading including both 100% noble gases and 25% iodines. For example, if the ratio of the monitor readings is 1/2, it is assumed that'12-1/2% of the iodines are airborne. In this example, the fraction of the 100% core inven-tory of noble gases that is airborne would be 1/2, but this fraction would not be conservative because the actual amounts of iodine present are unknown. The iodine contribution to the calculated monitor reading is excluded when the fraction of noble gases airborne is determined. O
EP-303-3 Rev. 0.B 4.4 Primary Containment Leakage Rate The primary containment leakage rate is not only unknown but also is probably a complicated function of time. To be conservative, we select the design basis leak rate given in the FSAR. This value of 0.5%/ day is assumed to be constant for the duration of the accident. 4.5 Standby Gas Treatment System (SGTS) Filter Efficiency The FSAR states that the SGTS filter efficiency for iodine is 99%. This is a conservative value. The actual value may be higher. Since the actual value is unknown, the conservative value is used which will result in an overestimation of the thyrofd , inhalation dose consequences. I 4.6 Release Height The Fermi 2 SGTS vent is not at sufficient height to-take credit for elevated release. Although some height effects are present, a ground level release is selected. Although a methodology for partial elevated releases could be formulated (Reg. Guide 1.111), finite cloud considerations would have to be used for whole body dose determinations. In addi-tion, terrain effects would have to be considered. These complications were rejected in favor of the more simple conservative ground release. 4.7 Meteorological Conditions Dose rates and doses are inversely proportional to wind speed. To project such quantities over time, the wind speed must be known. It is assumed that the wind speed at the time of the projection is constant over the time period of the projection. Dose projections over large time periods should be avoided because of changes in wind speed and direc-tion. Of course, instantaneous dose rates downwind are independent of wind direction but integrated doses apply only to directions in which the wind was blowing. 4.7.1 Meteorological Stability Class The Pasquill stability class (Reg. Guide 1.23) ; required to fix the amount of dispersion in the Gaussian plume model. The stability class is assumed to be constant over the time period of the projection. The stability classes are defined as follows: \
EP-303-3 Rev. 0.B (~) Page 5 V Temperature Lapse Rate (oC/50m) Stability Class less than -0 95 A Extremely Unstable
-0 95 to -0.85 B Moderately Unstable
-0.85 to -0 75 C Slightly Unstable
-0.75 to -0.25 D Neutral
-0.25 to 75 E Slightly Stable 0 75 to 2.00 F Moderately Stable greater than 2.00 G Extremely Stable
, 4.7 2 Atmospheric Dispersion The relative concentration (X/Q') at a downwind dose point that is found from the semi-infinite cloud model. (Meteorology and Atomic Energy - 1968 and Reg. Guide 1 3.) The relative concentration at the center of a Gaussian plume at that downwind distance is assumed to exist in all space.
4.8 Site Boundary Distances Site boundary distances (meters) for each direction are presented below. () - Exclusion Radius Site Boundary LPZ i N 915 1249 4827 NNE 915 1646 4827 NE offshore offshore offshore l ENE offshore offchore offshore I E offshore offshore offshore i ESE offshore offshore offshore SE offshore offshore offshore SSE offshore offshore offshore S 915 1417 offshore
, SSW 915 1542 offshore SW 915 1920 offshore I
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EP-303-3 Rev. 0.B Page 6 Exclusion Site Radius Boundary LPZ WSU 915 1798 4827 W 915 1390 4827 WNW 915 1082 4827 NW 915 915 4827 NNW 915 990 4827 5.0 Procedure for Projected Dose Assessment The data, tables, worksheets, and curves in the following attachments are used to classify the magnitude of potential and actual airborne releases and assess the offsite consequences. The Red, Yellow, and White emergency designa-tions are based on dose ranges in Table 5.2 of the " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents", Environmental Protection Agency, Office of Radiation Programs, Environmental Analysis Division, EPA-520/1-75-001, September, 1975 Their definition is: White Emergency Whole Body .05 to 1 rem Thyroid 3 to 5 rem Yellow Emergency Whole Body 1 to 5 rem Thyroid 5 to 25 rem Red Emergency Whole Body 5 rem and above Thyroid 25 rem and above Attachments 5.1 through 5 5 are used to assess the offsite consequences of potential or actual radioactive releases: 5.1 PROJECTED WHOLE BODY GAMMA DOSE BASED ON DRYWELL MONITOR READING - Xe-133 (EQUIVALENT) O
i ' EP-303-3' Rev. 0.B Page 7 I 52 PROJECTED THYROID INHALATION DOSE BASED ON DRYWELL MONITOR READING, I-131 (EQUIVALENT) 1 53 PROJECTED WHOLE BODY GAMMA DOSE BASED ON STANDBY GAS TREATMENT SYSTEM MONITOR READING, Xe-133 (EQUIVALENT) 5.4 PROJECTED THYROID INHALATION DOSE BASED ON STANDBY GAS TREATMENT SYSTEM MONITOR j READING, I-131 (EQUIVALENT) I 5.5 EMERGENCY CLASSIFICATION CALCULATION - WORST CASE CONDITIONS 1 O i i r l lO 4
J O EP-303-3
. Rev. 0.B i
ATTACHMENT 5.1 , s PROJECTED WHOLE BODY GAMMA DOSE BASED ON DRYWELL MONITOR READING Xe-133 (EQUIVALENT) O t O l
- _ , . _ _ - _ . - , . , , - - . __ ,,.___a , , , _ , _.__,_,,_._...,_,mm__-, , _ , , .. _,,_ __ _ _ _ _ _ y,_.,ym.y ,- .e--_- ,,w,-m-w-- ,--_.w, e, -. - .- .,- - ,
DATE TIME ATTACHMENT 5.1 WORKSHEET 5.1.1 DRYWELL MONITOR READING PROJECTED ACTIVITY RELEASE Xe-133 (EQUIVALENT) Time of shutdown of reactor Time after shutdown of release to primary containment Time of Drywell Monitor Reading 8-hour period selected (Column 1, Table 5.1.1) for activity release O Q/R, C1.hr/ Rem, from Table 5.1.1 for Xe-133 equivalent Drywell Monitor reading, R/hr x 1000, mrem /hr C1, released (activity) = (Q/R)x(Monitor Reading)x 10-3
= .'* x x10-3 =
0 EP-303-3 Rev. 0.B Attachment 1 Page 1 of 16
Table 5.1.1 Xe-133 EQUIVALENT Q/R FOR RELEASE AT 0. HOURS AFTER SHUTDOWN OF REACTOR Time Period Drywell Monitor After Release Q/R, Ci-br/ Rem, for 100% Nobles to Primary Plus 0.0% Iodines at Indicated Time Containment, After Release to Primary Containment Hrs. 10 min 20 min 30 min 40 min 50 min 1 hour 2 hrs 4 hrs 6 hrs 8 hrs 16 hrs 24 hrs 0-8 4.44 5.44 6.16 6.75 7.27 7.73 10.0 14.8 20.4 26.6 52.7 74.7 8-16 1.10 1 35 1.52 1.67 1.80 1 91 2.48 3 66 5.04 6.58 13 0 18.5 16-24 540 .662 749 .822 .885 941 1.22 1.80 2.48 3 24 6.42 9.09 24-32 360 .442 500 548 590 .628 .814 1.20 1.65 2.16 4.28 6.06 32-40 .276 339 384 .421 .453 .482 .625 921 1.27 1.66 3.28 4.65 40-48 .230 .282 319 350 376 .400 519 765 1.05 1 38 2.73 3 86 48-56 .201 .246 .279 306 329 350 .454 .669 922 1.20 2 39 3 38 56-64 .182 .223 .252 .277 .298 317 .411 .606 .835 1.09 2.16 3 06 64-72 .168 .206 .233 .256 .276 .293 380 560 772 1.101 2.00 2.83 72-80 .158 .193 .219 .240 .258 .275 356 525 723 944 1.87 2.65 80-88 .149 .183 .207 .227 .244 .259 336 .496 .683 .892 1.77 2.50 88-96 .141 .173 .196 .215 .231 .246 319 .470 .648 .846 1.68 2 38 96-104 .134 .165 .186 .204 .220 .234 304 .448 .617 .805 1.60- 2.26 104-112 .128 .157 .178 .195 .210 .223 .289 .427 588 768 1.52 2.15 112-120 .122 .150 .169 .186 .200 .213 .276 .407 561 732 1.45 2.05 120-128 .117 .143 .162 .177 .191 .203 .263 388 535 .698 1 38 1.96 128-136 .111 .136 .154 .169 .182 .194 .252 371 511 .667 1 32 1.87 136-144 .106 .130 .148 .162 .174 .185 .240 354 .488 .637 1.26 1 79 144-152 .102 .124 .141 .155 .166 .177 .229 338 .466 .609 1.21 1.71 152-160 .0970 .119 .135 .148 .159 .169 .219 323 .445 581 1.15 1.63 160-168 .0927 .114 .129 .141 152 .162 .210 309 .425 556 1.10 1.56 168-176 .0886 .109 .123 .135 .145 .154 .200 .295 .406 531 1.05 1.49 176-184 .0846 .104 .117 .129 .139 7.147 .191 .282 388 507 1.00 1.42 184-192 .0809 .0991 .112 .123 .132 .141 .183 .269 371 .484 960 1 36 8NEQ Rc?L o
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DATE TIME () WORKSHEET 5.1.2 DRYWELL MONITOR READING EMERGENCY CLASSIFICATION CALCULATION - Xe-133 1 Pasquill Stability Category
- Distance, Miles **
Type of Dose (Xe-133 Whole Body Gamma) Multiplying Factor from Table 5.1.2 Curies Released (Worksheet 5 1.1) O Normalized Curies Released = Multiplying Factor X Curies Released Wind Speed, mph Plot - wind speed, Normalized Curies Released on Figure 5.1.1 Emergency Classification Graph i
- Categories A through G i
** Exclusion Area Boundary = 0 57 miles (915 m, NW, Sector Q) l All other site boundaries must be taken from Section 4.8 1
g-wg EP-303-3 ( ,/ Rev. 0.B l 4 Attachment 1 Page 3 of 16
Table 5.1.2 PAG EMERGENCY CLASSIFICATION MULTIPLYING FACTORS FOR Xe-133 ACTIVITY (Ci) RELEASED Pasquill Stability Distance from Release Point Class 915 meters 1 Mile 2 Miles 3 Miles 4 Miles 5 Miles A 2.46-6 5.62-7 3 01-7 2.09-7 1.61-7 1 32-7 B 1.22-5 4.02-6 1.02-6 4.54-7 2.55-7 1.75-7 C 2.74-5 1.02-5 2.96-6 1.42-6 8.45-7 5.64-7 L 6.74-5 2.98-5 1.07-5 5.87-6 3.84-6 2.77-6 E 1.19-4 5.70-5 2.21-5 1.28-5 8.66-6 6.42-6 F 2.02-4 1.10-4 4.76-5 2.87-5 2.00-5 1.52-5 G 3 02-4 2.01-4 1.03-4 6.55-5 4.69-5 3 61-5 Pasquill Stability Distance from Release Point Class 6 Miles 7 Miles 8 Miles 9 Miles 10 Miles A 1.12-7 9 72-8 8.61-8 7.74-8 7.04-8 B 1.48-7 1.29-7 1.15-7 1.03-7 9 36-8 C 4.05-7 3 07-7 2.41-7 1.94-7 1.61-7 D 2.12-6 1.69-6 1 39-6 1.17-6 1.01-6 E 5.04-6 4.11-6 3.44-6 2 95-6 2.57-6 F 1.21-5 9 99-6 8.47-6 7 33-6 6.44-6 G 2.91-5 2.42-5 2.06-5 1.79-5 1.58-5 8$$$ 2;?L .eo5 oSb1 "S O O O
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DATE TIME O ' V WORKSHEET 5.1 3 DRYWELL MONITOR READING DOSE CALCULATION - Xe-133 Distance 1 Distance 2 Distance 3 Distance 4 Pasquill Stability Category Distance, Miles Type of Dose (Xe-133 Whole Body Gamma) Value from Table 5 1 3 (a) .
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r., l T. EP-30S-3 , l Rev. 0.B Attachment 1
,Page-6 of 16 l
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O Table 5.1 3 DOSE CALCULATION Xe-133; Whole Body Gamma Dose, Rem mph Ci Pasquill Stability Distance from Release Point Class 915 meters 1 Mile 2 Miles 3 Miles 4 Miles 5 Miles
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DATE () WORKSHEET 5.1.4 i DRYWELL MONITOR READING FOR AREA AFFECTED CALCULATION- Xe-133 Curies Released (Worksheet 5.1.1) Wind Speed, mph Atmospheric Dispersion Factor, m-2 i = 1 963 X Wind Speed, mph Curies Released = White
= 39 2 x Wind Speed, mph Curies Released : Yellow
= 196 3 x Wind Speed, mph
' Curies Released : Red Pasquill Stability Category From Figure 5.1 3 Atmospheric Dispersion Factor vs. Distance Graph Obtain: White Distance miles .
Yellow Distance s miles Red Distance miles
) '/ EP-303-3 Rev. 0.B Attachment 1 Page 9 of 16
DATS WORKSH'EET 5.1.5 DRYWELL MONITOR READING CALCULATION OF DOSE AT DISTANCES BETWEEN 0.57 AND 50 MILES - Xe-133 Distance 1 Distance 2 Disthnce 3 Distance 4 Distance, miles 4 Pasquill Stability Category Obtain: Atmospheric Dispersion Factor, m-2 Figure 5.1 3 nd Speed, mph Curies Released (Worksheet 5.1.1)
's Dose = .02548 x Curies Released x Atmospheric Dispersion Factor Wind Speed
= :
1 ( i O EP-303-3 Rev. 0.B Attachment 1 Page 10 of 16
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DATE s TIME WORKSHEET 5.1.6 GENERAL EMERGENCY DETERMINATION FOR DRYWELL MONITOR - Xe-133 Pasquill Stability Category Type of Dose Rate (Xe-133 Whole Body Gamma) * - Time of Monitor Reading (Worksheet 5.1.1) Value of Monitor Reading from (a) rad /hr General Emergency Table 5.1.4 m/sec Wind Speed (b) mph Monitor Reading for General Emergency: 447 0 x (a) x (b) = (c) mrad /hr Actual Monitor Reading (Worksheet 5 1.1) (d) mead /hr Emergency Condition Emergency If (d) 2 (c) enter General If (d) 4 (c) enter no l l I l i 1. O EP-303-3 Rev. 0.B Attachment 1 Page 13 of 16
24 - DRWELI. MONI TOR RE AOINGS-CENER AL EMERGENCY FOR RELEASE AT .000 HR AFTER SHUTDOw'8 wHOLE BODY CAMMA OOSE RATE EMERGENCY (EA8 DOSE RATE .CE. 1.0 RAD /HR) TIME OFTER DRWELL MONITOR DOSE RATE (100% N06LES PLUS .00% IOOINES). OFLEASE. RAD / HOUR PER METER /SECOND. FOR PASQUILL STA8ILITY CLASS 600R$ A B C D E F G , 167 6.63*06 f.34*06 5.97*05 2.43405 1.37*05 8.19404 5.41404
.333 5.4t*06 1.90*06 4.87*05 f.98*05 1.12*05 6.62604 4.4t*04
.500 4.78*06 9.69*05 4.30*05 9.75*05 9.87*04 5.85+04 3.90*04 i.
.667 4.35*06 8.83605 3.92405 1.59605 9.00604 5.33604 3.55*04
.833 4.05*06 8.21*05 3.64*05 1.48*05 8.36*04 4.95404 3.30604 i 3.81*06 7.72'05 3.43*05 1.39*05 7.86*04 4.66*04 3.10*04
- 1.000 t.250 3.53*06 7.14*05 3.97*05 9.29*05 7.27*04 4.38*04 2.87*04 !*
t.500 3.30*06 6.68*05 2.97405 f.21*05 6.8t*04 4.03*04 2.69*04 6.29*05 2.79605 1.14405 6.41*04 3.80804 2.53*04 ! t.750 3.1t*O6 2.000 2.94*06 5.95*05 2.64+05 1.07*05 6.06*O4 3.59*04 2.39804 53 l 2.250 2.78*06 5.64*05 2.50*05 1.02405 5.74*04 3.40*04 2.27404 m - 2.38*05' 9.67*04 5.45*04 3.23*04 2.15404 CT 2.500 2.64*06 5.36*05 5 2.750 2.5t*06 5.09*05 2.26*05 9.19*04 5.19*04 3.07*04 2.05*04 $' 3.000 2.3980G 4.85*05 2.15*05 8.76*04 4.94404 2.93*04 1.95*04 3.250 2.28*06 4.63*05 2.05*O5 8.35*04 4.79404 2.79404 f.86*04 Ln
- 3.500 2.98*06 4.42*05 1.96*05 7.97+04 4.50*04 2.66*04 9.78*04 3.750 2.08*06 4.22*05 1.87*05 7.62+04 4.30'04 2.55*04 f.70*04 f*
4.000 1.99806 4.04*05 f.79*05 7.29*04 4.lf*04 2.44*04 1.62804 g, . 4.250 f.9t*06 3.87*05 f.72*05 6.98*04 3.94404 2.33*04 1.56*04 4.500 1.83*06 3.71*05 f.65*05 6.69*04 3.77+04 2.24*04 1.49+04 4.750 9.75*06 3.56*05 f.58*05 6.42404 3.62604 2.14*04 f.43*04 5.000 9.69*O6 3.4t*05 f.52*05 6.16*04 3.48*04 2.06*04 f.37*04 5.333 9.60'06 3.24*05 1.44*05 5.85*04 3.30*04 1.95*04 9.30604 , 5.657 1.52806 3.08*05 9.37*05 5.56*04 3.13*04 9.86404 1.24*04 6.000 f.45*06 2.93*05 0.30*05 5.29*04 2.98*04 1.77*04 f.18*04 6.500 9.35*06 2.73605 1.29405 4.92604 2.78*04 1.65*04 1.10*04 7.000 8.26*O6 2.55*05 1.13*05 4.60*04 2.60404 9.54*04 1.03*04 8.000 1.ft*06 2.24*05 9.96*04 4.05*04 2.28*04 1.35+O4 9.OJ'03 , 16.000 5.58*05 1.13*05 5.02404 2.04*04 1.45*04 6.83603 4.55*03 24.000 3.94*05 7.99*04 3.55804 1.44*04 8.14*03 4.82'03 3.22*03 O ss > :o m m rt C N 4 rt < l om. La O C) s, D' H g .O GJ g C C3 LJ
$ 0 0
DATE TIME O WORKSHEET 5.1.7 SITE AREA EMERGENCY DETERMINATION FOR DRYWELL MONITOR - Xe-133 Type of Dose Rate (Xe-133 Whole Body Gamma) Time of Monitor Reading (Worksheet 5.1.1) Value of Monitor Reading from Site Area Emergency Table 5.1.5 x 1000 (a) mead /hr Actual Monitor Reading () (Worksheet 5.1.1) (b) mrad /hr Emergency Condition If (b) 2 (a) enter Site Area If (b) < (a) enter no Emergency I EP-303-3 Rev. 0.B Attachment 1
,, Page 15 of 16
l l 1V81'3 S
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*t94 C6+0C
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. O EP-303-3 Rev. 0.B ATTACHMENT 5.2 PROJECTED THYROID INHALATION DOSE I BASED ON DRYWELL MONITOR READING I-131 (EQUIVALENT) i O .
1 l l l l l O
DATE i ()
- ATTACHMENT 5.2 WORKSHEET 5.2.1 DRYWELL MONITOR READING I
PROJECTED ACTIVITY RELEASE I-131 (EQUIVALENT) Time of shutdown of reactor Time after shutdown of release
- to primary containment Time of Drywell Monitor Reading 8-hour period selected (Column 1, Table 5.2.1)
() { f for activity release , Q/R, C1'hr/ Rem, from Table 5.2.1 for I-131 l equivalent Drywell Monitor reading, R/hr x 1000, mrem /hr i l C1, released (activity) = (Q/R)x(Monitor Reading)x 10-3 ! = x x10-3 = 0 EP-303-3 Rev. 0.B Attachment 2 Page 1 of 16
Table 5.2.1 I-131 EQUIVALENT Q/R FOR RELEASE AT 0 HOURS AFTER SHUTDOWN OF REACTOR Time Period Drywell Monitor After Release Q/R, Ci hr/ Rem, for 100% Nobles to Primary Plus 25% Iodines at Indicated Time Containment, After Release to Primary Containment Hrs. 10 min 20 min 30 min 40 min 50 min 1 hour 2 hrs 4 hrs 6 hrs 8 hrs 16 hrs 24 hrs 0-8 2.52-4 2.92-4 3 23-4 3.49-4 3 74-4 3 98-4 5.27-4 7.85-4 1.06-3 1 34-3 2.46-3 3 50-3 8-16 2.16-4 2.50-4 2 76-4 2 99-4 3 21-4 3.41-4 4.51-4 6.73-4 9.05-4 1.14-3 2.11-3 3 00-3 16-24 1 94-4 2.24-4 2.48-4 2.68-4 2.87-4 3 05-4 4.04-4 6.03-4 8.11-4 1.03-3 1.89-3 2.69-3 24-32 1.77-4 2.05-4 2.27-4 2.46-4 2.63-4 2.80-4 3 70-4 5.52-4 7.42-4 9.40-4 1.73-3 2.46-3 32-40 1.64-4 1 90-4 2.10-4 2.28-4 2.44-4 2.59-4 3 43-4 5.12-4 6.88-4 8.71-4 1.61-3 2.28-3 40-48 1.54-4 1.78-4 1 97-4 2.13-4 2.28-4 2.43-4 3 21-4 4.79-4 6.45-4 8.16-4 1.50-3 2.14-3 48-56 1.45-4 1.68-4 1.86-4 2.01-4 2.15-4 2.29-4 3 03-4 4.52-4 6.08-4 7.70-4 1.42-3 2.02-3 56-64 1 38-4 1.59-4 1.76-4 1.91-4 2.04-4 2.17-4 2.88-4 4.29-4 5 77-4 7 30-4 1 34-3 1 91-3 64-72 1 31-4 1.52-4 1.68-4 1.82-4 1.95-4 2.07-4 2 74-4 4.09-4 5.50-4 6.95-4 1.28-3 1.82-3 72-80 1.25-4 1.45-4 1.60-4 1.74-4 1.86-4 1 98-4 2.62-4 3 91-4 5.25-4 6.65-4 1.23-3 1 74-3 80-88 1.20-4 1 39-4 1.54-4 1.67-4 1.79-4 1.90-4 2.51-4 3.75-4 5.04-4 6 38-4 1.18-3 1.67-3 88-96 1.16-4 1 34-4 1.48-4 1.60-4 1.72-4 1.82-4 2.42-4 3.60-4 4.84-4 6.13-4 1.13-3 1.61-3 96-104 1.11-4 1.29-4 1.43-4 1.54-4 1.65-4 1.76-4 2 33-4 3 47-4 4.67-4 5 91-4 1.09-3 1.55-3 104-112 1.07-4 1.24-4 1 37-4 1.49-4 1.59-4 1.69-4 2.24-4 3 35-4 4.50-4 5.70-4 1.05-3 1.49-3 112-120 1.04-4 1.20-4 1 33-4 1.44-4 1.54-4 1.64-4 2.17-4 3.23-4 4 35-4 5.50-4 1.01-3 1.44-3 120-128 1.00-4 1.16-4 1.28-4 1 39-4 1.49-4 1.58-4 2.09-4 3 12-4 4.20-4 5 32-4 9.80-4 1 39-3 128-136 9 70-5 1.12-4 1.24-4 1 34-4 1.44-4 1.53-4 2.03-4 3 02-4 4.06-4 5.14-4 9.48-4 1 35-3 136-144 9 39-5 1.09-4 1.20-4 1 30-4 1 39-4 1.48-4 1 96-4 2.92-4 3 93-4 4.98-4 9.18-4 1 30-3 144-152 9 09-5 1.05-4 1.16-4 1.26-4 1 35-4 1.43-4 1.90-4 2.83-4 3.81-4 4.82-4 8.68-4 1.26-3 152-160 8.81-5 1.02-4 1.13-4 1.22-4 1 31-4 1 39-4 1.84-4 2.74-4 3.69-4 4.67-4 8.61-4 1.22-3 160-168 8.53-5 9.89-5 1.094 1.18-4 1.27-4 1 35-4 1 78-4 2.66-4 3 58-4 4.53-4 8.34-4 1.17-3 168-176 8.27-5 9.58-5 1.06-4 1.15-4 1.23-4 1 30-4 1.73-4 2.58-4 3 47-4 4 39-4 8.08-4 1.15-3 176-184 8.02-5 9.29-5 1.03-4 1.11-4 1.19-4 1.26-4 1.67-4 2.50-4 3 36-4 4.25-4 7.84-4 1.11-3 184-192 7 77-5 9 01-5 9 95-5 1.08-4 1.15-4 1.23-4 1.62-4 2.42-4 3 26-4 4.12-4 7.60-4 1.08-3 ENEY 20?1
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DATE WORKSHEET 5.2.2 DRYWELL MONITOR READING EMERGENCY CLASSIFICATION CALCULATION - I-131 (EQUIVALENT) Pasquill Stability Category
- Distance, Miles **
Type of Dose (I-131 Thyroid Inhalation Dose) Multiplying Factor from Ttble 5.2.2 Curies Released (Worksheet 5.2.1) f^) V Normalized Curies Released = Multiplying Factor X Curies Released Wind Speed, mph Plot - wind speed, Normalized Curies Released on Figure 5.2.1 Emergency Classification Graph Categories A through G Exclusion Area Boundary = 0.57 miles (915m, NW, Section Q) all other site boundaries must be taken from Section 4.8 i l EP-303-3 Rev. 0.B Attachment 2 Page 3 of 16
Table 5.2.2 PAG EMERGENCY CLASSIFICATION MULTIPLYING FACTORS FOR I-131 ACTIVITY (C1) RELEASED Pasquill Stability Distance from Release Point Class 915 meters 1 Mile 2 Miles 3 Miles 4 Miles 5 Miles A 1.86-2 4.26-3 2.28-3 1.58-3 1.22-3 9 96-4 B 9 20-2 3 05-2 7.70-3 3 43-3 1 93-3 1 32-3 C 2.07-1 7 74-2 2.24-2 1.08-2 6 39-3 4.27-3 D 5.10-1 2.26-1 8.10-2 4.45-2 2 91-2 2.10-2 E 9 03-1 4 31-1 1.68-1 9 66-2 6.55-2 4.86-2 F 1.52+0 8 33-1 3 61-1 2.17-1 1 52-1 1.15-1 G 2.29+0 1.52+0 7.77-1 4.95-1 3 55-1 2 73-1 Pasquill Stability Distance from Release Point Class 6 Miles 7 Miles 8 Miles 9 Miles 10 Miles A 8.45-4 7 35-4 6.52-4 5.86-4 5 33-4 B 1.12-3 9.78-4 8.67-4 7 79-4 7 09-4 C 3 07-3 2 32-3 1.82-3 1.47-3 1.22-3 D 1.60-2 1.28-2 1.05-2 8.88-3 7.62-3 E 3.81-2 3 11-2 2.61-2 2.23-2 1.94-2 F 9 15-2 7.56-2 6.41-2 5.55-2 4.87-2 G 2.20-1 1.83-1 1.56-1 1 35-1 1.19-1 % 0 ." a aso8 f '* zm O O O
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DATE i TIME 4 WORKSHEET 5.2 3 DRYWELL MONITOR READING i DOSE CALCULATION - I-131 4 Distance 1 Distance 2 Distance 3 Distance 4 i, Pasquill Stability Category Distance, Miles
- Type of Dose
! (I-131 Thyroid Inhalation) i
. Value from Table 5.2 3 (a) I ries Released (Worksheet 5.2.1) Wind Speed,' mph i Curies Released (b) Wind Speed, mph Dose, Rem = (a) x (b) I O EP-303-3 l' Rev. 0.B Attachment 2 Page 6 of 16
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Table 5.2 3 DOSE CALCULATION I-131 Thyroid Inhalation Dose, Rem
- mph Ci Pasquill _
Stability Distance from Release Point Class 915 meters 1 Mile 2 Miles 3 Miles 4 Miles 5 Miles A 5.59-3 1.28-3 6.83-4 4.74-4 3.66-4 2 99-4 B 2.76-2 9 14-3 2 31-3 1.03-3 5.80-4 3 97-4 C 6.21-2 2 32-2 6.71-3 3 23-3 1 92-3 1.28-3 D 1.53-1 6.77-2 2.43-2 1 33-2 8.73-3 6.29-3 E 2.71-1 1.29-1 5.03-2 2 90-2 1.97-2 1.46-2 F 4.57-1 2.50-1 1.08-1 6.52-2 4.55-2 3 44-2 G 6.86-1 4.56-1 2 33-1 1.49-1 1.07-1 8.19-2 Class 6 Miles 7 Miles 8 Miles 9 Miles 10 Miles A 2.54-4 2.21-4 1 95-4 1.76-4 1.60-4 B 3 37-4 2 93-4 2.60-4 2.34-4 2.13-4 C 9.20-4 6.96-4 5.46-4 4.41-4 3 64-4 D 4.81-3 3.84-3 3 16-3 2.66-3 2.28-3 E 1.14-2 9 32-3 7.82-3 6.69-3 5.83-3 F 2.75-2 2.27-2 1.92-2 1.66-2 1.46-2 G 6.60-2 5.49-2 4.68-2 4.06-2 3 58-2 NNNY 10?a aeoS f '* D e e
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DATE WORKSHEET 5.2.4 DRYWELL MONITOR READING FOR AREA AFFECTED CALCULATION- I-131 Curies Released (Worksheet 5.2.1) Wind Speed, mph Atmospheric Dispersion Factor, m-2
= 2 59 x 10-4 x Wind Speed, mph Curies Released = White
= 4 32 x 10-3 x Wind Speed, mph Curies Released = Yellow
= 2.16 x 10-2 x Wind Speed, mph Curies Released = Red Pasquill Stability Category From Figure 5 2 3 Atmospheric Dispersion Factor vs. Distance Graph Obtain: White Distance miles Yellow Distance miles Red Distance miles i /
i EP-303-3 , Rev. 0.B Attachment 2 Page 9 of 16
DATE TIME () WORKSHEET 5.2.5 DRYWELL MONITOR READING CALCULATION OF DOSE AT DISTANCES BETWEEN .57 AND 50. MILES - I-131 Distance 1 Distance 2 Distance 3 Distance 4 Distance, miles Pasquill Stability Category Obtain: Atmospheric Dispersion Factor, m-2 Figure 5 2 3
- nd Speed, mph Curies Released (Worksheet 5.2.1)
Dose, Rem = 1157. x Curies Released x Atmospheric Dispersion Factor Wind Speed \ - l 1 l f EP-303-3 Rev. 0.B Attachment 2 Page 10 of 16
Figure 5.2.3 Sheet 1 of 2 Atmospheric Dispersion Factor Times Wind Speed for Indicated
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