ML20211Q806

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Forwards Daily Status Rept for NRC Chernobyl Incident Tracking Team for 860505.Status Briefing on Chernobyl Nuclear Accident Encl
ML20211Q806
Person / Time
Issue date: 05/05/1986
From: Speis T
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20211Q749 List:
References
FOIA-86-517 NUDOCS 8612220106
Download: ML20211Q806 (51)
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{{#Wiki_filter:\\[ 9 MAY 5, 1986 e. TDDRANDlKFUK: visisusuriun FROM: THEMIS SPEIS, DIRECTOR CHERNOBYL INCIDENT TRACKING TEAM

SUBJECT:

CHERNOBYL INCIDENT TRACKING TEAM DAILY STATUS PEPORT - MAY 5, 1986 ENCLOSED IS THE DAILY STATUS REPORT OF MAY 5, 1986 FOR THE NRC'S INCIDENT TRACKING TEAM, ORIGINAL SIGNED BY BRIAN SHERON FOR: THEMIS SPEIS, DIRECTOR CHERNOBYL INCIDENT TRACKING TEAM ENCLOSURE: AS STATED V~o s &- 86-5 /7 e en$$ $.-efh*"g'g", E A m

b I '4.. INCIDENT TRACKING TEAM - DAILY STATUS REPORT - MAY 5,1986 ITEMS OF INTEREST JAPANESE REPORTED RAINWATER ACTIVITY OF 10,000 PIC0 CURIES / LITER WITH A f%XIMlfi 0F 13,000 PIC0 CURIES / LITER. FDA ACTION GUIDELINES ARE THAT INGESTION PATHWAYS SHOULD BE INTERRUPTED WHEN ACTIVITY IN MILK REACHES 15,000 PIC0 CURIES PER LITER. CALCULATIONS WHICH EXAMINED PRELIMINARY DATA ON THE RATIOS OF IODINE 131 TO IODINE 133 INDICATE THAT THE CHERNOBYL REACTOR WAS SHUT DOWN ON FRIDAY, APRIL 25. REFINED CALCULATIONS BY PACIFIC NORTHWEST LABORATORIES (PNL) 0F STATION BLACKOUT INDICATE THAT IF UNIT 3 LOST ALL AC POWER OR FEEDWATER AFTER NINE DAYS OF BEING SHUT DOWN, BOILOFF AND HEATUP TO THE POINT OF CORE DAMAGE WOULD TAKE APPROXIMATELY TWO TO FOUR DAYS, GIVEN THE UNCERTAINTIES IN DESIGN DATA. DATA FROM NORWAY RECEIVED WIS MORNING SHOWS AIR CONCENTRATIONS OF RADIO-ACTIVITY OVER OSLO DECREASING FROM INITIAL VALUES CN 4/28/86 UNTIL ABOUT N00N, 5/4/86; THEN SUDDENLY INCREASING. WHILE THE REASON IS UNCLEAR, IT COULD BE THE EFFECT OF A RETURNING PLUME. RADI0 ACTIVITY IS NOW OFF 0F COAST OF NORTHWEST U.S. NRC IS REQUESTING ALL UTILITIES WITH NUCLEAR REACTORS ON WEST COAST TO ASSIST NRC BY MEASURING RADIOACTIVITY IN RAINWATER SAMPLES AND REPORTING RESULTS TO NRC'S OPERATIONS CENTER. i l l p i 8 -sc -670 n. 1

N Y' STATUS BRIEFING ON THE CHERNOBYL NUCl. EAR ACCIDBff PRESENTED TO THE ADVISORY C0mlTTEE ON REACTOR SAFEGUARDS VAY 8 ~ ~ _ 111EMIS SPEIS, DIRECTOR BRIAN SHERON, DEPUTY DIFECTOR DIVISION OF SAFEIY REVIEW AfD OW.RSIGHT OFFICE OF NUCLEAR REACTOR REGULATION AND INCIDENT TRACKIPE TEAM FRANK CONGEL JACK KUDRICK F o I h - f (o - E h 33 3

J >; n e 1. DESCRIPTION OF NRC INVOLVEE NT 2. DESCRIPTION OF THE SITE 3A. DESCRIPTION OF THE PLANT 3B, DESCRIPTION OF PRIMARY SYSTEM ENCLOSURE 4. WHAT WE KNOW ABOUT THE ACCIDENT A. STATUS OF PLANT AS OF 5/6/86 B. EVENT C. RADIOLOGICAL 5, WHAT ARE FUTURE PLANS O Foi Pr-86 -5 'Y 33

y-- r i y 1, DESCRIPTION OF NRC PROGRAM 0 PRESIDENT ESTABLISHED INTERAGENCY TASK FORCE - EPA ADMINISTRATOR LEE T1&AS IS CHAIRMAN OF TASK FORCE - EPA IS LEAD AGENCY 0 HAROLD DENTON IS NRC KMBER ON INTERAGENCY TASK FORCE O ED0 ESTABLISHED NRC INCIDENT TRACKING TEAM IN NRC THEMIS SPEIS IS DIRECTOR, BRIAN SPERON IS DEPUTY DIRECTOR /ALTEPNATE ORGANIZATION OF TEAM IS SET-UP ALONG LINES OF INCIDENT RESPONSE CENTER ORGANIZATION, - PROTECTIVE EASURES TEAM ABOUT - REACTOR SAFETY TEAM 20 - STATUS OFFICER / LIAISON TEAMS PEOPLE TEAM OPERATIONS ARE AT THE INCIDENT RESPONSE CENTER IN ftBB, BETHESDA, TEAM ON DUW ALL DAY, 0 WENT INTO EFFECT MAY 1, 1986

-r;,V NRC CHERNOBYL TRACKING TEAM DIRECTOR: DR. THEMIS SPEls DEPUT( DIRECTOR: DR. BRIAN SHERON STATUS OFFICER, DEPUTY AND ASSISTANT: K. PERKINS, R. PRIEBE, J. HIMES ET SECRETARY: J. RAINES, K. B0HRER, S. J0teSON REACTOR SAFET( DIRECTOR: B. SHERON/E, JORDAN CCORDINATOR: J. HICKMAN/D. M RKSBERRY C. ALLEN C. KELBER B. CARTER J. MILLER B. HARDIN M. TOKAR D. SCALETTI W. SWENSON P. WILLIAMS C. THCPAS J. KUDRICK F. MIRAGLIA

0. LYNCH PROTECTIVE WASURES: F. CONGEL COORDINATOR:

C. SAKENAS/T. McKENNA J. FAIROBENT W. MEINKE E. BRANAGAN R. HOGAN S. ACHARYA R. KORNASIEWICZ J. SWIFT F. STURZ LIAISON: COORDINATOR: B. WEISS /E, WEINSTEIN IP: R. SENSENEY, H. FAULKNER, J. SHEA, A. GORE, M. MAHY CIA: W. SWENSEN PAO: J. FOUCHARD CA0: S. KENT FEDS: B. WElsS/E, WEINSTEIN ~ STATES: D. NUSSBAUMER NRC REGIONS: R. CAPRA AE0D: F. HEBDON WSS: L. ROUSE /J. LONG ADP SUPPORT SYSTEMS COORDINATOR: J. CARTER J. JULIUS C0t1JNICAT10NS C00PDINATOR: M. HAWKINS ADMINISTPATION SUPPORT COORDINATOR: K. JACKSON /S. SIMONDS A. STEVENS M. KING M. DEBOSE E. ANTONIOU E. PEYTON

Y e'9 M 4 8

o Y 2. DESCRIPTION OF THE CHERf0BYL SITE THE CHERNOBYL REACTOR SITE IS A 4 UNIT SITE LOCATED ON THE PRIPYAT RIVER APPROXIPATELY 10 MILES NORTliWEST nF CHERT 0BYL CHERNOBYL IS A SMALL TOWN LOCATED APPROXIMATELY 60 MILES NORTH OF KIEV POPULATIONS - KIEV - 21 MILLION l - PRIPYAT + 3 OTHER NEARBY TOWNS - 49,000 WillilN 18 MILE RADillS (EVACUATION ZONE) - 150,000 TO 180,000 - WITHIN A 100 MILE RADIUS - 7 MILLION TERRAIN APPEARS TO ROLLING HILLS ALL FOUR UNITS ARE RBPK-1000 CLASS PLANTS, UNIT 1 OPERATIONAL AROUND 1977, UNIT 4 OPERATIONAL IN 1983, IM) K)RE RBW-1000 CLASS UNITS CURRENTLY UNDER CONSTRUCTION AT SITE,

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. l1 3. DESCRIPTION OF THE PLANT O e B

i f CHEoNOBYL PLANT CHARACTERISTICS THE CHERNOBYL UNITS (RUSSIAN NA T RB,7 -1000) ARE DIRECT CYCLE B0ILING-WATER PRESSURE-TUBE REACTORS EACH UNIT IS RATED AT ABOUT 3200 M THE REACTOR FUEL IS CONTAINED IN A LARGE NUMBER ( 1660) 0F INDIVIDUAL ZIRCALOY PRESSURE TUBES IFBEDDED IN A MATRIX OF GRAPHITEBLOCKS, EACH PRESSURE TIEE CONTAINS 18 ZlRCALOY CLAD q FUEL PINS ENRICHED TO ABOUT 1.8% U-235. THE PRESSURE TUEES ARE 8,8 CM (3,5 INCH) IN DIATTER. THEREACTORISAB0dr12M( 40 FT) IN DIATTER AND 8M ( 26FT) HIGH INCLUDING SIDE AND TOP GRAPHITE REFLECTORS THE GRAPHITE MATRIX IS ENCLOSED WITHIN AN INERTED ATPOSHPERE

3 e SI,v. OPERATING PUMPS (8 PUMPS TOTAL, TW PUPS ARE ON STANDBY) CIRCULATE COOLING WATER TO THE INLET OF EACH INDIVIDUAL PPESSURE TUBE (FUEL ASSEMBLY) THROUGH INDIVIDUAL LINES FOR EACH ASSEMBLY STEAM IS PRODUCED WITHIN THE ASSEMBLY AND IS EXTRACTED FROM THE TOP OF EACH PRESSURE TUBE AND COLLECTED IN A HEADER C050N TO ONE OF FOUR STEAM DRUMS CONTROL IS ACCOMPLISHED WITH 211 BORON CARBIDE CONTROL RODS THE CONTROL ROD CHANNELS ARE COOLED SEPARATELY ON LINE REFUELING (ESSENTIALLY CONTINUOUS) EPERGENCY COOLING SYSTEMS ARE DESIGNED FOR MAIN COOLANT PIPE BREAK

5 4 ECCS SYSTEMS INCLUDE PASSIVE INJECTION TANKS LOW PRESSURE PUMPED INJECTION (ON DIESELS) HIGH PRESSURE PUPPED INJECTION (0N DIESELS)

s CHERNOBYL PLANT PARATTERS f GPAPHITE MODERATED BWR (RBMK 1000) ON-LINE REFUELING REACTOR POWER 3140INr CYLINDRICAL CORE 12M DIA TTER (GRAPHITE mDERATED) 7M HEIGHT RADIAL GPAPHITE REFLECTOR IM THICK TOP AND BOTTOM REFLECTORS .5MTHICK CORE CONTAINS:

  • URANIUM FUEL ELE?ENTS 27, ENRICHED 002
  • N DERATOR t
  • COOLANT
  • CONTROL RODS

x o. CHEFNCBYL PLANT PAP #ETERS (CONTINUEI))

  • RADIAL AND VERTICAL NEUTRON FLUX SENSORS
  • TD PERATURE SENSORS PDDERATOR:
  • 2488 VERTICAL COLLPNS OF GRAPHITE
  • 25cM x 25cM BLOCKS FUEL ASS &BLIES:

1700 CELLS

  • ENCLOSED IN ZP PRESSURE TUBES 8,8cM DIA,
  • 18 FUEL EL9ENTS PER ASSENLY EACH 1,35cM DIA,
  • ARGON-HEllUM INERTED e

n CHERNOBYL PLANT PAPATTERS_ (CONTINUED) ECCS:

  • DESIGNEI) FOR MAIN COOLANT PIPE BPEAK
  • PASSIVE INJECTION TANKS
  • LOW PRESSURE PUMPED INJECTION (ON DIESELS)
  • HIGH PRESSURE PlW ED INJECTION (0N DIESELS) l i

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'250 mm'8: Failed Fue1 0 / Detectors ( Gm ^> r Subass oblies Graphite Downcomers Core l l l 7, \\ Main i 5 Group Dispensing j Ikaders A )Feedwater Pressure I ( ) '] / Header ~~ Tubes U v C ^> e XS Water Pipelines (1600-1700) (t J t Schematic of an RDMK-1000 Generating Unit _ = _. , s RBMX Fuel Assembly A.A o 1600-1700 pressure tubes o 1 fuel assembly per pressure ~ tube, 250 m pitch / g3

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t o 2 subassemblies per pressure / tube, 3.5 m long 1 i O o 20 m gap between subassemblies ' ..}. o 18 Zirconium clad UO2 fuel 3 I BB rods per subassembly f ~' ^ ^ ' ' o 1.8 - 2.0% enriched uranium in fuel rods <It == ' = o Self-powered detectors mounted in central thimbles of 130 5 ~ fuel assemblies 4 o Argon-helium gas mix in gap between clad and pellet l CC o Coolant fed into channel from the bottom jii)I' h RBMX Control Rods [ o 211 control rods, 700 m pitch, g } j.[. 9 45' to the fuel lattice r h h o Cooling for control rods separate from water pipelines i -~ o Control rods on top and bottom [UR of core o Made of a boron carbide sleeve inside an aluminum alloy tube eactor Core 1 Hanger

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2 Pin o Height - 7 m 3 Transition piece l 4 Stem o Radius - 12.2 m S Fuel element f 6 Suppor1:ng rod o Moderater consists of 250 X 250 m l = l 7 Steeve blocks 8 0 " *

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Reflector 1 m thick on sides. 9 Nuts l L 0.5 m thick on ends o Thermocouples at joints of blocks at 3 heights to measure temperature of graphite Q 3B, DESCRIPTION OF PRIMARY SYSTEM ENCLOSURE RBMK-1000 ENCLOSURE PHILS0PHY DEDUCED FROM LITERATURE o ENCLOSE REACTOR AND PAJOR PIPING WITHIN TWO DRY WELLS o PROVIDES A WETWELL BENEATH THE DRWELL STRUCTURES o ENCLOSE REPAINING PRIPARY SYSTEM WITH A CflFINEENT STRUCTURE o ETAL LINED RECTANGULAR VOLUES CURRENT CONCLUSIONS: o WE DO NOT HAVE ENOUGH INFORPATION TO DRAW ANY DEFINITE CONCLUSIONS REGARDING THE CAPABILITIES OF THE PRIMARY SYSTEM ENCLOSURE o IT APPEARS THAT THE SWlET PHILOSOPHY OF CONTAINENT/ CONFINEENT MAY BE SIGNIFICANTLY DIFFERENT FROM U.S./ EUROPE \\ S NM ~ OE IT TS RY T OS L G P U N N Y A I O GR V P I NA I S IM R P S) NI O ES IR T R R( AP C OM PL M A JO PO EF E AO UO RO R MR SP / / s a .~ '/s TN ) E T M F E / 6 G 3 N 2 A ( RRA m TN 2 A 7 L P i l ) 0 ( ) TF 7 ) T L 2 F E 6 V 1 8 E ( 9 L ( m DN 6 m UO 9 0 R 4 3 G N O ~ I S T S IR E SA R s . T. ) PD P t l I P 0 L S 20 U 0 - U P .S0 S. P. A 8 V 7 / 2 p;+I R !l O N j,#'h.9@du T G M - 4', 4, e.g C I A S R5 .s I j' E E .e. u4-R D i WN, l l1~

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REACTOR VAULT-

~ PRESSURE BOUNDARY P N ANNULUS 2 ) REACTOR O (H,'+N) 2 k ? / / / / / /,, / l r' [ PRESSURE RELIEF VALVE l (3PSISETPOINT) INLET PIPING

  • REACTOR VAULT ONLY, NOT PRIMARY SYSTEM.

l 1 a SUPPRESSION POOL o W O SUPPRESSION POOLS (ONE ON TOP 0F THE OTHER) o DESIGN PRESSURE: UNKNOWN o VENT PIPE DIAETER: 280 m (11 IN) 400 m (16 IN) o VENT SUBERGENCE: 3 FT l 0 OVERHEAD SPRAYS e 4 SUPPRESSION POOL ARP.ANGEMENT REACTOR VAULT MAJOR PIPING l [ ROOM / t I a 4- -] ~" ~ W-WETWELL m n A A s s-7t- -; AIR J.* : .1, J.....*.. SPACE m 7 n a g nKa K a n a , c, _.. .\\. \\. _ g...,,, u,.. < SUPPRESSION VENT PIPES ~ ~ POOL (S) OVERFLOW TUBE _ SPRINKLERS l 1 l -.,n- -nm.-- n m e r-a v v aov .. = '. .y t.: t.w l .e g t *e ' i..,as. ~ s t t =v ,.I. f.,,4 t 4

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s s x ii c., t.., v 1 m i s A etQt Q f iI; N-7p mg" : y c. j,, ' 1 N < i '(D ~, 7" s ,, l n,. \\,J l I e .r w s. xvm. i 1-x \\ \\ \\ t }:= vp "4 4 m { : a i t Y D .g t g g a ADDITIONAL CONSIDERATIONS I o LEAKTIGHT VOL(fES PERIODICALLY LEAK TESTED o SRV's R0lffED TO POOL o POOL (S) USED AS ECCS RECIRCULATION SOURCE o NON-INERTED V0LifES l 1 e ~. 4 'O e WAT E M ABOUT THE ACCIDENT O e e 4,A, STATUS OF PLANT AS OF 5/6/86 - UNIT 4 REACTOR BUILDING IS DESTROYED - SOE RADICACTIVITY REPORTED TO BE STILL LEAKING FROM PLANT - SITE EVACUATED OUT TO 18 MILES (150,000 - 180,00CT?) - LIVESTOCK SLAUGHTERED WITHIN 12 MILE RADIUS - CONTROL ROOMS OF INTACT 3 UNITS ARE REPORTED TO BE MANNED - THREE INTACT UNITS ARE BEING COOLED - SOE CLEANUP ACTIVITIES REPORTED TO BE UNDERWAY - EVACUEES TAKEN TO VILLAGES APPROXIMATELY 60 MILES SOUTH OF CHERNOBYL AND WEST OF KIEV l l l l 1- ~ . c* .~:..z. g::,< y f. u ..:. ss':. ~ T,gi~ -l.K:. :y:...% n* e? ?'.~.s a; w.<-p.-.yi., r ;.pc.., p.. Q..g. g . s ;~%:.:

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.m g _ 14m..g p:.... u. 14.B. EVENT SCENARIO (PRELIMINARY) AS REPORTED BY SOVIET GOVERNTNT INITIAL CHEMICAL EXPLOSION OCCURRED AS PLANT WAS G0ING INTO PLANNED SHUE0WN TIE OF EXPLOSION WAS 1:23, APRIL 26,1986 BASED ON RADIONUCLIDE EASUREENTS, STAFF HAS CALCULATED TIE OF PLANT SHUTDOWN AT ABOUT MIDNIGHT, APRIL 25, 1986 THIS IS CONSISTENT WITH SOVIET REPORTS WE DO NOT YET HAVE ANY AUBORITATIVE DESCRIPTION OF THE CHERNOBYL ACCIDENT BASED ON INFORMATION AVAILABLE TO DATE, WE CAN CONSTRUCT THE FOLLOWING: AT 1:23 AM, APRIL 26, 1986 AN EXPLOSION OCCURRED AT THE CHERNOBYL NUCLEAR PLANT, UNIT 4 EXPLOSION IS SAID TO HAVE OCCURRED IN THE BUILDING WHICH HOUSES THE REACTOR (SOVIETS CALL THIS THE MACHINE HALL) AS A RESULT OF EXPLOSION, THE ROOF 0F THE REACTOR BUILDING CAUGHTFIRE FIRE DAMAGE CAUSED A BREACH OF REACTOR CONTAltfENT INITIAL RADI0 ACTIVE RELEASE SUBSEQUENT INITIATION OF GRAPHITE FIRE e o THERE ARE MANY POSSIBLE SCENARIOS FOR CHERNOBYL THAT CAN LEAD TO THE DAPAGED CORE. o WE STILL DO NOT KNOW ABOUT THE ACTUAL SEQUENCE OF EVENTS WERE. SO E POSSIBILITIES ARE: - EXPLOSION / FIRE IN TURBINE OR REACTOR BUILDING ULTIMATELY CAUSES LOSS OF CONTROL (COOLING) TO CORE. LEADS TO CORE UNC0VERY AND ELTDOWN - EXPLOSION / FIRE IN TURBINE OR REACTOR BUILDING CAUSES FAILURE OF REACTOR BUILDING AND DAMAGES REACTOR OTHER POSSIBILITIES: - FUEL HANDLING ACCIDENT - FLOW BLOCKAGE - REACTIVITY TRANSIENT ..-..-y O' a-ROUGH DESCRIPTION OF A HEATUP SCENARIO - PRIMARY COOLANT WATER B0llS OFF - WITH PEACTOR SHUT DOWN, NO HEAT GENERATION IN GRAPHITE - FUEL AND GRAPHITE COOL AND APPROACH QUASI-THERPAL EQUlllBRIUM -FUELUNCOVERSOVERSEVEPALHOURSANDHEATSUP - FUEL CLADDING OXIDATION AND FAILURE - FUEL ASS &BLY CASING FAILURE NEAR TOP OF CORE - HIGH PRESSURE-HIGH TE W ERATURE STEAM AND OTHER GASES PRESSURIZE THE GRAPHITE CAVITY - FAILUPE OF GRAPHITE CAVITY ALLOWS AIR INGPESS TO CORE REGION l - GRAPHITE FIRE STARTED AND A CHEMICAL (GAS) EXPLOSION IS POSSIBLE - GRAPHITE CONTINUES TO BURN OVER A LONG TIE l (,D IT IS K)ST LIIEl.Y THAT THE SOVIETS DO NOT YET KNOW WITH CERTAIN1Y THE ACTUAL SEQUENCE OF EVENTS, THIS IS SIMILAR TO OUR IKREDGE OF THE SEQUENCE OF EVENTS AT TMI-2 WITHIN THE FIRST EEK OR S0 AFTER THE ACCIDENT, o I S ,e--, SUBJECTS I SOU RC ES O r DATA SU V VA R.Y O F ENVIRO N M E NTA DA~A U ETEORO _OGY l SOURCE TERM i EXTRA 3OLATION FACTORS DOSES H EALTH I U 3LICATIONS O l w e i i i e l 4 SOURCES OF ENVIRONMENTAL DATA l 1 l ELEVATED LEVELS OF RADIOACTMTY DETECTED IN MORE THAN 1O COUNTRIES 1 SWEDEN AND FINLAND PROVIDED ACTMTY MEASUREMENTS AS A FUNCTION OF TIME BEGINNING SHORTLY AFTER THE ACCIDENT

  • O l

l + i i l 1 ENVIRONMENTAL DATA: 26-28 APRIL 1986 SWEDEN ~ 1-131 IN AIR: 100 1OOOO pCi/m3 1 Cs-137 IN AIR: 1 1000 pCi/m3 ) Cs-134 IN AIR: 1 1000 pCi/m3 -l l-131 IN MILK: <700 40000 pCi/l l DIRECT RADIATION: 20 250 micro R/hr FINLAND j 1-131 IN M!LK: 100 1000 pCi/l l'e DIRECT RADIATION: 10 .100 micro R/hr l j i v s 'w. e F O G T G N N N N EU IR R RP D U E EU N D H FO A T N F C e N F R R D - T I O B O E T

E R I

I S O A N S DO t i P T A I l U R RE USS F R AE QTN F A V VS SA E D P E OA NE R I Y T EGT TI T P G I T D AI URI F U F R QOF O S O N MO PW A J MS MN 0 A N S r t0 S T 0 M 0A A 0 T E 1 R 5T E 5 SIA S R 5 0R 0 A 1 O O P NRF 1 1 T R oat O P F S AT T U TmVFR N R A E ADE A SO Y N LF R NP NA OS O M N NO B O A R OC RT T I I TN T 3 E T EH I A C H C E I T ECIDG C D R E N TE R U RASE I I R O S FNH E C T A DL O I I S DRO S E R UCH I H LE L D D S T PD N N DI P ABE N A N O A W S C R A T AI RN I O G NL D 5 N D AA N 2 M OEA E E E D4U O ENWI L SI T OEIT E A RR N O E P OS T PSI SMLU I OP RNV O F P I Rr EEF DEEO DRI i T RO NPCS NFAD y E I I M W W ll ) l i l ll c O s e '- ~ SOURCE TERM ~ ~ G 4 ) SOURCE TERM ESTIMATED BY EXTRAPOLATION OF l ESTIMATED DOSE FROM CONCENTRATION l MEASUREMENTS IN FINLAND AND SWEDEN BACK TO CHERNOBYL SITE ir es' l-ENERGETIC ATMOSPHERIC RELEASE SIMILAR TO WASH-1400 PWR1 AND PWR'2 IN MAGNITUDE l WITHOUT ACTINIDES (EXCEPT Np-239) UNCERTAINTIES DO NOT PRECLyDE RELEASES OF PWR3 MAGNITUDES i t-y RELEASE SCENARIO FOR CHERNOBYL IS PROBABLY DIFFERENT FROM WASH-1400 SCENARIOS ik. AVAILABLE DATA INDICATE PROLON,GED RELEASE N 6 l l EXTRAPOLATION FACTORS I (BACK TO CHERNOBYL SITE) i i ACCOUNT FOR: DISPERSAL IN AIR ' ~ RADIOACTIVE DECAY r CLOUD DEPLETION i l j VALUES FOR: ) EXPOSURE TO NOBLE GASES (1 E+5) INHALATION OF IODINES (1 E l 6) l t \\ . ESTIMATED DOSES DOSE,* REM., LOCATION, WHOLE BODY, THYROID ;.: 1 l STOCKHOLM O.002 0.01 (750 MI) HELSINKI O.005 NO DATA (700 MI) CHERNOBYL >100 4000 (1 MI) CHERNOBYL >1 40 (20 MI)

  • BASED ON 1 -DAY EXP_O_SURE_lN U.SSR; 2-DAYS FOR SWEDEN AND FINLAND

\\ ~ ~ J ~ e HEALTH IMPLICATIONS SHORT-TERM: SEVERE PHYSICAL TRAUMA. INCLUDING DEATH WITHIN 1 3 MILES LONG-TERM: FATAL AND NON-FATAL CANCERS (POTENTIALLY WORLD-WIDE) GENETlc EFFECTS f -~. 33 --}}

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