ML20215C779

Draft Protective Measures Team Activities, Briefing & Related Info Re Chernobyl Accident

ML20215C779
Person / Time
Issue date:	06/12/1987
From:	NRC
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ML20215C748	List: ML20215C745 ML20215C779
References
FOIA-86-335 NUDOCS 8706180244
Download: ML20215C779 (45)

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.r> 4 7 8/ Q ~ i' () 3: 3o ? WHAT WE N g ABOUT M ACCIDENT,AT CHERNOBYL f/t_ I 1. DETECTION OF RADI0 ISOTOPES AT OLKILUOTO, FINLAND AT 1:30 PM ON SUNDAY, APRIL 27 INDICATING THE OCCURRENCE OF REACTOR ACCIDENT. 2. SOVIETS CONFIRED EXISTENE OF PEACTOR ACCIDENT AND GRAPHITE FIRE AT GERN0BYL. THEY ALSO ADMITTED THE OCCURRENCE OF SOE DEATHS AND EXTENSIVE RADIOLOGICAL EXPOSURES TO APEAS CLOSE TO THE PLANT. f 3. SOVIET PHOTOGRAPH CONFIRED SATELLITE INF0PMATION THAT BE REACTOR BUILD-ING ROOF HAD BEEN l u iN0YED. 4. LIMITED INFORMATION OF THE PEACTOR DESIGN APO SAFEIY CONSIDERATIONS IS BAT .WHICH IS AVAILABLE IN THE OPEN LITERATURE. EE OPEN LITERATURE INFORMATION 'IS NOT SUFFICIENT TO ESTIMATE THE CAUSES AND THE COURSE OF BE ACCIDENT l WITH ANY DEGREE OF CERTAINTY. W 5. RETENTION OF REFRACTORY ETALS AMONG TRANSPORTED RADIO!S0 TOPES INDICATES THAT FUEL ELTING TEPPERATURES WERE AGlEVED IN BE COURSE OF THE ACCI- .D1Et RAD 10lSOTOPE EASUREPENTS ALSO INDICATE TH OF THE CORE FISSION PRODUCT INVENTORY WAS RELEASED FROM THE PLANT. 6. RAD 10lS6 TOPE MEASUREENTS INDICATE THAT TE PLANT COULD t0T HAVE BEEN SHUT DCWN FOR A LONG PERIOD OF TIE BEFORE TE RELEASE OF FISSION PRODUCTS OCCURRED. p Fo i A-66-33F W 'L-K

m 7. SINCE GRAPHITE FIPES AE HIGHLY DIFFICULT TO INITIATE, WE CAN ITER THAT A 4 SEVERE EVEN/ OCCURRED DURING THE COURSE OF TE ACCIDENT. THIS IS CONSkSIFN WITH THE DESTRUCTION OF THE REACTOR BUILDING ROOF. ALSO,COM-ERCIAL WELLITE PHOTO INDICATED LARGE SCALE DEFLAGRATION NEAR TE REACIDR BUILD E /O\\ 8. A NLPBER OF POSSIBLE ACCIDENT SCENARIOS AE BEING CONSIDERED TO PROVIDE A j l BETTER UNDERSTANDING 0F THE EVENTS THAT OCCURED AT CHERN0BYL. THE POSSI-BLE SCB!ARIOS INCLUDE A TOTAL LOSS OF ELECTRIC POWER WHICH COULD RESULT IN B0lLING AWAY THE COOLANT AND SIEWFNT CORE DEGRADATION. THI'S SEDUENCE HAS THE POTENTIAL TO PRCDUCE C&BUSTIBLE GASES THAT CAN BURN, OR DETONATE 10 PROLVJCE THE QBSERVED CON 9P9CES. OTER SCENARIOS UNDER CONSIDERATION INCLUDE EACTIVITY TRANSUIS AND 3)0LANT PIPE BREAIG. 4 vi k o e

a. u s-u, m S THE RBMK-1000 IS A GRAPHITE-MODERATED PRESSURE-TUBE REACTOR WITH A CAPACITY.0F 1000 MWe/3200 MWt. THE REACTOR IS A DIRECT CYCLE BOILING WATER REACTOR. WATER BOILS IN SOME 1693 INDIVIDUAL PRESSURE-TUBES MADE OF A ZIRCONIUM-2.5% NI0BIUM ALLOY EMBEDDED IN STACKED GRAPHITE BLOCKS WHICH SERVE AS MODERATOR. THE REACTOR IS A TWO-LOOP DESIGN WITH 4 MAIN COOLANT PUMPS PER COOLING LOOP. THREE COOLING PUMPS IN EACH LOOP ARE REOUIRED FOR FULL POWER OPERATION, THE FOURTH PUMP IN.EACH LOOP IS A SPARE. n t TWO FUEL ELEMENTS CONTAINING 2% ENRICHED URANIUM OXIDE FUEL ARE LOADED IN EACH PRESSURE-TUBE. THE FUEL ELEMENTS ARE STACKED ONE ON TOP OF THE OTHER WITH A LATCHING MECHANISM JOINING THEM TOGETHER. EACH FUEL ELEMENT CONSISTS OF 18 FUEL PINS HELD TOGETHER WITH STEEL SPACER ELEMENTS. THE FUEL ELEMENTS HAVE ZIRCONIUM ALLOY CLADDING WITH AN OUTER DIAMETER OF 13.5 MM AND A WALL THICKNESS OF 0.9 MM. EACH FUEL ASSEMBLY IS 3.5 METERS IN LENGTH. THE 2% ENRICHED FUEL IS DESIGNED FOR A BURNUP OF 22,300 MEGAWATT DAYS / METRIC TON. THERE ARE A NUMBER OF DESIGN DIFFERENCES BETWEEN COMMERCIAL POWER PRODUCING LWRs IN THE U.S. AND THE PRESSURE TUBE REACTORS SUCH AS THE CHERNOBYL PLANT NEAR KIEV. THE MOST IMPORTANT DIFFERENCE WE BELIEVE IS THE CONTAINMENT DESIGN PHILOSOPHY. IN THE U.S. WE INCORPORATE SUBSTANTIAL MARGIN IN OUR CONTAINMENT DESIGNS TO ACCOMMODATE DESIGN BASIS ACCIDENTS. [C l h-Slo"3M W1 o

,.3 s J ANOTHER BASIC DIFFERENCE IS THAT THE CHERNOBYL UNITS ARE GRAPHITE I MODERATED, WATER COOLED HIGH PRESSURE TUBE REACTORS. THE PRESSURE TUBE CONCEPT EMPLOYS A LARGE NUMBER (ABOUT 1660) 0F SEPARAYE WATER FLOW PATHS THROUGH A GRAPHITE MATRIX (EACH WITH INDIVIDUAL FUEL . ASSEMBLIES) TO PRODUCE STEAM FOR THE TURBINE. WE HAVE YERY LITTLE DETAIL ABOUT THE SAFETY DESIGN OF THE CHERNOBYL TYPE UNITS. BASED ON INFORMATION AVAILABLE FROM THE TRADE JOURNALS SCME OF THE CHERNOBYL PLANT DO UTILIZE EMERGENCY WORKING < SYSTEMS f INCLUDING SUPPRESSION POOL TYPE SYSTEMS., IT IS NOT CLEAR THAT THE '4 LEVELS OF REDUNDANCY AND D'!VERSITY IN SAFETY SYSTEMS FOR THE CHERNOBYL PLANTS ARE COMPARABLE TO THOSE EMPLOYED IN LWRs IN THIS COUNTRY. e [. 2-

s m l d(.' T_HE DESIGN OF COMMERCIAL U.S. LIGHT WATER REACTORS IS BASED, ON THREE LEVELS OF SAFETY, COMMONLY CALLED THE DEFENSE-IN-DEPiH I APPROACH. THESE THREE LEVELS OF SAFETY ARE: A. RELIABLE PLANT OPERATION AND PREVENTION OF ACCIDENTS DURING _ NORMAL OPERATING CONDITIONS THROUGH CAREFUL OPERATOR TRAINING AN'D THE !NTRINSIC FEATURES OF THE DESIGN, SUCH AS QUALITY ASSURANCE, REDUNDANCY, DIVERSITY, INDEPENDENCE, MAINTAINA-BILITY, TESTABILITY, INSPECTABILITY, AND FAIL-SAFE i CHARACTERISTICS. B. PROTECTION AGAINST ACCIDENTS THAT MIGHT OCCUR IN SPITE OF THE CARE TAKEN IN DESIGN. CONSTRUCTION, AND OPERATION OF THE PLANT. THIS LEVEL OF SAFETY IS PROVIDED BY REDUNDANCY OF CRITICAL COMPONENTS AS WELL AS BY PROTECTION DEVICES AND SYSTEMS DESIGNED TO ENSURE THAT SUCH EVENTS WILL BE ARRESTED WITHOUT ADVERSE EFFECTS ON PUBLIC HEALTH AND SAFETY. CONSERVATIVE DESIGN PRACTICES, INCLUDING THE PROVISION OF REDUNDANT DETECTION AND ACTUATING EQUIPMENT, ARE INCORPORATED IN THE PROTECTION SYSTEMS TO ENSURE BOTH THE EFFECTIVENESS AND RELIABILITY OF THE PLANT RESPONSE. C. PROVIDING ACCEPTABLE PLANT RESPONSE TO EXTREMELY UNLIKELY A CIDENTS. ALTHOUGH OCCURRENCE OF THESE FAULTS IS OF LOW PROBABILITY, APPROPRIATE ENGINEERED SAFETY FEATURES ARE INCORPORATED INTO THE DESIGN TC SAFELY ACCOMMODATE SUCH ,j I

1 ) 1 m ) EVENTS. AS DISCUSSED ABOVE, THE SAFETY DESIGN PHILOSOPHY OF THE PLANT MUST PROVIDE FOR PREVENTION OR MITIGATION OF THE FULL RANGE OF EVENTS, FROM RELATIVELY TRIVI'AL EVENTS l T0. LOW PROBABILITY ACCIDENTS. IN U.S. COMMERCIAL LIGHT WATER REACTORS, THERE ARE THREE BARRIERS TO PREVENT. FISSION PRODUCT RELEASE: FUEL CLADDING, PRIMARY SYSTEM. BOUNDARY, AND CONTAINMENT. i U.S. CONTAINMENTS. VARY IN DESIGN, BUT ALL HAVE SOME INHERENT i CAPABILITY TO ACCOMMODATE AND/0~R REDUCE THE CONSEQUENCES ~OF A SPECTRUM 0F CORE DAMAGE ACCIDENTS. (I.E., REDUCE FISSION PRODUCT RELEASE). l BECAUSE U.S. COMMERCIAL LIGHT WATER REACTORS DO NOT'CONTAIN GRAPHITE, THEY CANNOT FAIL IN THE'SAME MANNER AS THE CHERNOBYL REACTOR. HENCE, THEY WOULD NOT BE CHALLENGED BY THE CONSE0VENCES f 0F A GRAPHITE FIRE. WHILE HYDROGEN CAN BE GENERATED DURING CORE i DAMAGE ACCIDENTS IN U.S. REACTORS, HYDROGEN CONTROL FEATURES HAVE BEEN INSTALLED-FOR THE CONTAINMENTS MOST SUSCEPTIBLE TO FAILURE I

FROM HYDROGEN BURNING.

SINCE THE TMI-2 ACCIDENT IN 1979, MUCH WORK HAS BEEN PERFORMED TO ASSESS THE CAPABILITIES OF U.S. COMMERCIAL LIGHT WATER REACTORS TO PREVCNT AND/OR MITIGATE THE CONSEQUENCES OF CORE DAMAGING j ACCIDENTS SUCH AS LARGE RELEASES OF RADI0 ACTIVE FISSION PRODUCTS. l \\ -2 4

Q-4 WHILE THESE CONTAINMENTS ARE'NOT SPECIFICALLY DESIGNED FOR CORE i l DAMAGE ACCIDENTS, THEY HAVE BEEN SHOWN T0 BE AOLE TO ACCOMMODATE A SPECTRUM OF CORE DAMAGE ACCIDENTS AND THUS REDUCE THE RELEASE-f tOF FISSION PRODUCTS. ALSO, SINCE'THE TMI-2 ACCIDENT, THE NRC HAS R,EQUIRED U.S. COMMERCIAL. PLANTS TO INCLUDE ADDITIONAL DESIGN FEATURES AND OTHER OPERATIONAL ENHANCEMENTS TO BETTER ENSURE THAT FISSION PRODUCTS WOULD BE RETAINED IN THE EVENT OF A CORE DAMAGING ACCIDENT. THESE INCLUDE: HYDR 0 GEN CONTROL SYSTEMS TO PREVENT DAMAGE IN PLANTS WITH CONTAINMENTS THAT CANNOT ACCOMMODATE A HYDROGEN BURN OR EXPLOSION IN THE EVENT OF GENERATION OF LARGE AMOUNTS OF HYDROGEN DURING CORE DAMAGING ~ ACCIDENTS. IMPROYED EMERGENCY OPERATING PROCEDURES AND TRAINING FOR PLANT OPERATIONS. i 1 FINALLY, IN THE EVENT THAT FISSIDN-PRODUCTS WERE RELEASED FROM CONTAINMENT DURING A SEVERE CORE DAMAGE ACCIDENT, THE NRC HAS REQUIRED THAT EACH NUCLEAR PLANT HAVE A GREATLY ENHANCED RESPONSE CAPABILITY. BOTH OFFSITE AND ONEITE EMERGENCY PLANS ARE REQUIRED. LICENSEES ARE REQUIRED TO DRILL THEIR EMERGENCY PLAN PERIODICALLY. STATE 'AND LOCAL AUTHORITIES ARE TRAINED TO RESPOND TO NUCLEAR PLANT EMERGENCIES AS WELL. A FEDERAL RESPONSE PLAN HAS BEEN DEVELOPED AND EXERCISED TO ASSURE COORDINATED RESPONSE IF REQUIRED OF THE FEDERAL AGENCIES. W I g /t. THE NRC HAS ESTABLISHED AN INCIDENT TRACKING TEAM. THE OBJECTIVE-MOFTHISTEAMISTOSUPPORTTHEEPAINTERGOVEMNMENTALTASKFORCE AND TO. ASSESS THE IMPACT OF THE CHERNOBYL EVEi?T ON U_.S. REACTORS. THE INCIDENT TRACKING TEAM IS REVIEWING ALL INFORMATION AYAILABLE ' TO THE'NP.C IN ORDER TO BETTER ASCERTAIN THE NATURE OF THE ACCIDENT. WE WILL CONTINUE,TO REVIEW ALL DATA AS IT BECOMES AVAILABLE. t I O t 4

~ gg [' s. m k DURING THE COURSE OF THE INCIDENT TRACKING TEAM REVIEW AND EVALUATION, THE TEAM WILL BE CONSTANTLY ASSESSING THE INFDRMATION WE HAVE RECEIVED OR DEVELOPED TO DETERMINE IF CHANGES TO THE. NRC'S. REQUIREMENTS SHOULD BE CONSIDERED. AGENCY PROCEDURES FOR 'I INITIATING SUCH CHANGES ARE WELL ESTABLISHED AND DOCUMENTED. i i i l G i l

f{b s 4 00ESTION. WHAT 00 WE KNOW ABOUT THE.0FFSITE RADIOLOGICAL DOSES RECEIVED? RESPONSE. RADI0 ACTIVITY HAS BEEN DETECTED IN MANY COUNTRIES, INCLUDING SWEDEN AND FINLAND. USING THE MEASUREMENTS IN SWEDEN AND FINLAND IT IS POSSIBLE TO ESTIMATE DOSES TO INDZYIDUALS IN THE VICINITY OF THE CHERNOBYL SITE BY EXTRAPOL& LION TECHNIOffFS. ALTHOUGH THERE ARE LARGE UNCERTAINTIES IN THESE EXTRAPOLATIONS, IT IS POSSIBLE TO GENERALLY CHARACTERIZE THE RELATIVE SEVERITY DF THE ACCIDENT. THE RADIATION DOSES TO INDIVIDUALS WITHIN 2-3 MILES OF THE PLANT ARE VARIABLE DEPENDING PRIMARILY ON THE WEATHER CONDITIONS AT THE SITE AND THE TEMPERATURE OF THE R,ELEASE PLUME. HOWEVER, EVEN i USING BENIGN ASSUMPTIONS, THE WHOLE BODY DOSE TO INDIVIDUALS OVER 24 HOURS COULD BE FROM ABOUT 20 REM UP TO HUNDREDS OF REM. k THE CORRESPONDING THYROID DOSES WOULD RANGE _FROM ABOUT,20_0 REM _ UP TO THOUSANDS OF REM. THESE DOSES ARE SUFFICIENT TO PRODUCE SEVERE PHYSICAL TRAUMA INCLUDING DEATH.

~ ~ .p i e ~. 'l i. " AS IEICATED BY PAST STUDIES OF POTENTIAL SEEE REACTOR ACCIDENT CONSEQUENCES, AClfTE FATALITIES FROM RADIATION WOULD E EXFtutu CNLY RF1 ATIVELY EAR THE o [ EACTOR, ALL WELL WITHIN RUSSIA. OF COURSE, THERE MAY HAVE BEEN OTHER CASUAL AT _TE PLANT, DUE TO FIES OR OfEMICAL EXPLOSIONS. THE NLPBER OF ACtfTE FATALITIES FM RADIATION WOULD BE HIGHLY DEPEEENT ON TE POPULATION DISTRIBUTION IN THE VICINITY OF TE SITE NO IRP! THE EASURES TAkEN TO PRO 1ECT THE RUSSIAN PUBLIC AfD TWS MAY RANGE FfD1 A FEW D0 ZEN PEDPLE UP TO A FEW THOUSAND PEDPLE. IT IS i EASONABLE TO EXPECT THAY EASURES WOULD HAVE BEEN TAKEN TO KEEP TE NLFEER TOWARD TE LOWER Ef0 0F THIS RANGE. FOR INSTANCE, IT I,S KNOWN THAT TE USSR HAS A CIVIL DEFENSE SYSTEM WICH PROVIDES SELTERS FOR THE _ POPULATION WHICH MIGHT BE USEFUL IN THIS EVENT._ ON TE BASIS OF THE IFORMATION E HAVE RECEIVED TO DATE, WE HAVE SEEN NO Il0lCATION THAT ANYDE OUTSIDE OF TE USSR HAS BEEN EXPOSED TO DOSES THAT WOULD CALEE AClfTE EFFECTS THAT CAN BE DETECTED BY SCIENTIFIC EANS, AND CERTAINLY.NO EFF CIS THAT WOULD BE NOTICEABLE BY THE EXPOSED PERSONS. THE LONG-TERM tretus MAY BE INTERPETED PRIMARILY. ON TE BASIS OF INF0PMTION LEARED FROM THE PEDPLE EXPOSED AT HIROSHIMA AND NAGASAKI, AND '0THER GROUPS OF l PEDPLE WHO HAVE BEEN EXPOSED TO LARGE DOSES OF RADIATION. FOR THE SMALL DOSES I EXPERIENCED IN WESTERN EUROPE, USING THE EXTRAPOLA1ED INFORVATION PROVIDED BY ( TE NATIONAL ACADEMY OF SCIENCES BEIR COMITTEE AND SIMILAR SCIENTIFIC

==- ORGANIZATIONS, IT IS POSSIBLE TO ESTIMATE THAT TE L0fG-TERM EFFECTS WILL RANGE FIDi ZERO TO A FEW HlNDRED FATALITIES FROM CANCERS OCCURRING SOE DECADES IN TE FlfiURE. SIMILARLY, GEETIC tretus (WICH WOULD OCCUR PRIMARILY IN THE NEXT 5 TO 10 GENERATIONS) WOULD BE ESTIMATED IN THE RANGE FROM ZER0 TO A THOUSAf0 OR TWO. OTHER HEALTH EFFECTS SUCH AS NON-FATAL CANCERS MIGHT BE EXPECTED TO OCQJR IN C0FPARABLE NLFBERS.

2-WITHIN THE USSR MERE HIGHER DOSES ARE OC0JRRING, IT IS LIKELY THAT THE LONG-TE EFFECTS WILL JNCLUDE OTER HEALTH PROBLEMS SUCH AS titt.us ON TH IN SMALL-HEADED CHILDREN WITH REDUCED ETAL CAPABILITIES, INCREASEDJNCIDENCE OF LEUKEMIAS AW INCREASED INCIDENCE OF THYROID DISFUNCTION 1%Y ALSO BE OBS WITHIN A FEW YEARS. O f I b

i BRIEFING PAPER ON EMERGENCY. PLANNING FOR COMMERCIAL NUCLEAR POWER PLANTS IN THE UNITED STATES REGULATIONS 0F THE NUCLEAR REGULATORY COMMISSION AND THE FEDERAL' EMERGENCY MANAGEMENT AGENCY REQUIRE EMERGENCY PREPAREDNESS PROGRAMS AROUND NUCLEAR PLANTS. THE PRINCIPAL FEATURES OF THESE EMERGENCY. PREPAREDNESS PROGRAMS ARE: i (1) DETAILED PLANS' EXIST FOR PROTECTIVE MEASURES FOR THE l PUBLIC FOR A PLUME EXPOSURE EMERGENCY PLANNING ZONE (EPZ) 0F ABOUT 10 MILES IN RADI_US AND AN INGESTION PATHWAY EPZ OF 50 MILES ~IN RADIUS. WITHIN THE PLUME EXPOSURE EPZ, SHELTERING AND EVACUATION ARE PLANNED FOR. WITHIN ABOUT 50 MILES, THE CONTROL OF MILK PRODUCTS AND OTHER FOOD STOCKS IS PLANNED FOR. '(2) GRADED EMERGENCY ACTION LEVELS ARE SPECIFIED. THERE ARE FOUR DIFFERENT LEVELS RANGING FROM NOTIFICATION OF AN UNUSUAL EVENT UP TO A GENERAL EMERGENCY. FOR ALL OF THESE LEVELS, STATE AND LOCAL GOVERNMENTS ARE NOTIFIED BY THE UTILITY WITHIN 15 MINUTES. FOR THE MOST SEVERE OF THESE LEVELS THE PUBLIC ALSO MUST BE NOTIFIED AND KEPT UPDATED DURING THE COURSE OF ANY ACCIDENT. (3) STATE AND LOCAL GOVERNMENT AUTHORITIES CAN NOTIFY THE PUBLICWITHkN15MINUTESAFTERNOTIFICATIONBYTHELICENSEE. fo l A -8(=-M5 W2

2 l 2 r 3 (4)- EACH NUCLEAR POWER PLANT HAS AN ON-SITE TECHNICAL SUPPORT CENTER TO AID IN THE MANAGEMENT OF A NUCLEAR POWER PLANT DURING AN - ACCIDENT'AND A NEAR-SITE EMERGENCY OPERATIONS FACILITY FOR C00RDI-NATION WITH STATE AND LOCAL GOVERNMENTS. (5) PUBLIC EDUCATION PROGRAMS-EXIST ON THE NATURE OF THE HAZARD AND APPROPRIATE ACTIONS DURING EMERGENCIES. EMERGENCY PREPAREDNESS INFORMATION IS DISTRIBUTEC ANNUALLY TO THE PUBLIC i WITHIN ABOUT 10 MILES OF EACH NUCLEAR'POWCR PLANT. (6) PERIODIC EXERCISES ARE CONDUCTED TO TEST UTILITY, STATE, LOCAL AND FEDERAL EMERGENCY PLANS. THE NUCLEAR REGULATORY COMMISSION AND THE FEDERAL EMERGENCY MANAGEMENT AGENCY EVALUATE THE EMERGENCY PREPAREDNESS CAPA-BILITIES OF THE UTILITIES AND THE STATE AND LOCAL GOVERNMENTS TO ENSURE A STATE OF READINESS TO RESPOND BY REVIEWING THE EMERGENCY-PLANS, PERFORMING IMPLEMENTATION INSPECTIONS AND OBSERVING AND EVALUATING EXERCISES. l b

~ PRIMARY CONTAINMENT .i IN COMMERCIAL U.S. REACTORS, PROTECTION FROM RELEASE OF FISSION PRODUCTS =DURING ACCIDENTS IS PROVIDED BY A CONTAINMENT BUILDING SURROUNDING THE PRIMARY COOLANT SYSTEM. A CONTAINMENT BUILDING IS SO NAMED BECAUSE IT IS DESIGNED TO CONTAIN, OR PREVENT THE RELEASE OF FISSION PRODUCTS DURING ACCIDENTS. A CONTAINMENT STRUCTURE'HAS A PRESSURE RETENTION CAPABILITY. FOR EXAMPLE, LARGE DRY CONTAINMENTS IN THE U.S. CAN WITHSTAND UP TO 2,TO 3 TIMES (I.E., ABOUT 120-140 PSI) 0F THEIR DESIGN PRESSURE (I.E., 40-50 PSI) WITHOUT FAILURE. THESE CONTAINMENTS USUALLY INCORPORATE OTHER FEATURES, SUCH AS SPRAY SYSTEMS FOR PRESSURE SUPPRESSION AND HYDROGEN RECOMBINERS FOR HYDROGEN CONTROL. SOME CONTAINMENTS IN BWRs ARE INERTED TO PREVENT HYDROGEN COMBUSTION. CONTAINMENTS ALSO HAVE REQUIREMENTS ON ALLOWABLE LEAKAGE RATES. ANOTHER TYPE OF BUILDING THAT CAN SURROUND A REACTOR IS CALLED A CONFINEMENT BUILDING. CAPABILITIES OF CONFINEMENT RUILDINGS CAN VARY. HOWEVER, A CONFINEMENT BUILDING TYPICALLY DOES NOT PAVE THE SAME DEGREE OF PRESSURE RETENTION CAPABILITY OR LEAK RATE CONTROL AS A CONTAINMENT BUILDING. IT MAY REDUCE RADI0 ACTIVE RELEASES FROM SEVERE ACCIDENTS BY THE PHYSICAL, BARRIER IT POSES TO THE RILEASE PATH, AND ANY INHERENT PRESSURE RETENTION CAPABILITY IT MAY HAVE. ~

4 7 THERE ARE EVENTS WHERE THE RELEASE RATES TO THE CONFINEMENT BUILDING ARE LOW ENOUGH~TO BE WITHIN THE CAPABILITY OF THIS STRUCTURE. MOST CONFINEMENT STRUCTURES ARE DESIGNED T'O WITHSTAND A TORNADO EVENT. THIS TRANSLATES TO A PRESSURE CAPABILITY OF 1 TO 3 PSIG. WITHIN THIS PRESSURE WINDOW, THE STRUCTURE WILL FUNCTION ~AS A CONTROLLED FILTERED LEAKAGE BARRIER. THE U.S. NRC DOES NOT HAVE ANY INFORMATION REGARDING THE CAPABILITY OF THE CONFINEMENT BUILDINGS SURROUNDING REACTORS OWNED $ND OPERATED BY THE U.S. DOE. ALL U.S. LIGHT WATER REACTOR NUCLEAR POWER PLANTS HAVE A PRIMARY CONTAINMENT. SURROUNDING THE REACTOR VESSEL. THE MAIN PURPOSE OF THE CONTAINMENT IS THE RETENTION OF FISSION PRODUCTS IN THE EVENT OF A MAJOR DESIGN BASIS ACCIDENT. TYPICALLY, THIS MEANS THAT THE STRUCTURE IS DESIGNED TO WITHSTAND THE PRESSURIZATION DUE TO A COMPLETE P,UPTURE OF THE LARGEST PIPE IN THE SYSTEM. THIS ACCIDENT ESTABLISHES, AS A RESULT THE DESIGN PRESSURE AND TEMPERATURE CONDITIONS OF THE CONTAINMENT. THE CAPABILITY OF THE CONTAINMENT TO SURVIVE AN ACCIDENT, HOWEVER, IS GREATER THAN THAT WHICH IT WAS DESIGNED FOR. AS PREVIOUSLY STATED, THE VARIOUS CONTAINMENT DESIGNS WITHIN THE U.S. ARE BELIEVED TO BE CAPABLE OF WITHSTANDING PRESSURES 2 TO 3 TIMES THE DESIGN PRESSURE BASED ON OUR CONTINUING EVALUATIONS IN THE AREA 0F SEVERE ACCIDENTS (I.E., CORE MELT). I l m

sh TABLE 1 SUMMARIZES THE TYPES OF CONTAINMENTS DEPICTED IN FIGURES I THROUGH 6 WHICH ARE USED IN U.S. NUCLEAR POWER PLANTS. THE TABLE ALSO PROVIDES THE DESIGN PRESSURE AND NET FREE VOLUME FOR A TYPICAL l PLANT IN EACH CATEGORY. IN ADDITION TO THE PRIMARY CONTAINMENTS, MOST, IF NOT ALL, PLANTS HAVE A SECONDARY CONTAINMENT SURROUNDING THE PRIMAR.Y STRUCTURE. THIS BUILDING IS NOT CONSIDERED AS A PRESSURE BOUNDARY AND DOES NOT NECESSARILY HAVE A PRESSURE RETENTION CAPABILITY, BUT CAN BE - CONSIDERED A CONFINEMENT STRUCTURE, AS PREVIOUSLY DISCUSSED. OTHER FEATURES OF U.S. REACTORS THAT PROVIDE ADDITIONAL REDUCTION IN RADIOACTIVITY RELEASE INCLUDE THE SUPPRESSION POOL IN BWR PLANTS, ICE BEDS IN ICE CONDENSER PLANTS, AND THE AUXILIARY BUILDING FOR ALL, PLANTS. THE CONTAINMENT CHALLENGE FROM HIDROGEN COMBUSTION IS DEALT WITH BY REQUIRING: (1) ALL PLANTS WITH MARK I OR MARK II CONTAINMENTS TO BE INERTED SO THEY WILL INHIBIT HYDROGEN DETONATION. 9 (2) PLANTS WITH MARK III CONTAINMENTS AND ICE CONDENSER PLANTS TO HAVE AN IGNITER SYSTEM TO BURN THE HYDROGEN PRIOR TO REACHING AN EXPLOSIVE CONCENTRATION. 3-

(3) PLANTS WITH LARGE ORY AND SUBATMOSPHERIC CONTAINMENTS, BECAUSE OF THEIR LARGE VOLUME AND LARGE ULTIMATE. CAPABIL'ITY, BE EQUIPPED WITH H RECOMBINERS_TO 2 MAINTAIN THE HYDROGEN CONCENTRATION IN THE CONTAINMENT BELOW THE LOWER FLAMMABILITY LIMITS OR TO SURVIVE A-HYDROGEN BURN WITHOUT RUPTURE. 9 6 ' / I a l l 1 l -A l

r TABLE 1-l. MAJOR TYPES OF CDNTAINMENTS FOR U.S. HEACTORS !./ / / I s s / t r g esf a 4 le t J r 4 slJ /,/,e / / e / / /s ?/ s s s s . Dry containment (PWR) 50 15 2 6 8 81' Ice suppression (PWR) 2 8 10 Mark 1 (BWR) 2 22 24 Mark II (swu 9 9 Mark lli (BWR) g g 4 TABLE l-2. TYPICAL CONTAIM4ENT PARAMETERS Primary Containment Containment Representative Free volume Design Pressure Ty pe Plant (106 f t3) (psig) 1 Herk l Peoch Bottom-0.28 56 2. perk 11 Limerick 0.40 55 3. Mark 111 Grand Gulf 1.7 15 4 Ice condenser Seavoyah 1.2 11 5 Dry containment a. Prestressed THI-l 2.0 55 concrete b. Reinforced Cosenene Peek 2.5 50 concreto c. Steel St. Lucie 2.5 40 cylinder d. Steel Yellow Creek 3.6 45 sphere e'.' pheric Su betmos-Surry 1.8 45 Qlfo W 2-

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v. .\\ THE CONTAINMENT IS A PRESSURE SUPPRESSION TYPE CONSISTING OF 4 MAJOR COMPARTMENTS. THE DRYWELL IS DIVIDED INTO 2 SEPARATE VOLUMES. l ONE CONTAINING THE REACTOR VAULT WHILE THE SECOND COMPARTMENT CONTAINS THE ASSOCIATED PUMPS AND PIPING. THE REMAINING TWO VOLUMES ARE TWO SEPARATE SUPPRESSION POOLS; ONE ON TOP OF THE OTHER. WATER DEPTH OF EACH POOL IS 4'. t l l e 1

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g g.. l E (/[I 1 1 i } What do we know about the offsite radiological doses received? _f s 6 8 h n.l ~ .\\ (~lg, L Nhat are the potential near-term end long-tem effects on the world V populations in terms of latent and acute fatalities as well as genetic i i 5 ' defects 'for. future generations? h. y a rY f,hg .j How does.NRC Emergency Planning treat an acciderit such as this one? v z I p' 4 h

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1. 4-Foi A-B(a,-335 VJ 3 A.

a... y 3 c [ QUESTION; What do we know about the offsite radiological doses k received? i L.4 { f f I RESPONSE. e r k Radioactivity has.been detected in many countries, including Sweden and Finland. Usin'g the measurements in Sweden and Finland it is possible to {- estimate doses to individuals'in the vicinity of the Chernobyl site by P extrapolation techniques. Although there are large uncertainties in these' - extrapolations, it is possible to generally characterize the relative f g severity of the accident. The radiation doses to individuals within 2-3 e miles of the plant are variable depending primarily on the weather conditions at the site and the temperature of the release plume. However, even using [ benign as'sumptions, th'e whole body dose to individuals over 24 hours could be from about 20 rem up to hundreds of rem. The corresponding thyroid doses would range from about 200 rem up to thousands of rem. These doses are h [, sufficient to produce severe physical trauma including death. i v V.. g I i .=- .t. = est I g~en R-8 (.-335 W3 i

s Document Name: BRANAGAN - PMT Requestor's 10: OC- ,p ' I'- Author's Name: Branagan Document Coments: L ee '. l - e i, .l- >= 64 8 i n 's s e, a m 4 .e f' 9. i t 1. l 4 1 e f. g, v[ e 2 j.. i f '. ~

i ws us., s o, MAY 9 '86 ':37 CCNAA SCIENCE DIV. PAGE.01 g. (D-OSO9 -d Y l 3 s l COORDINATION COUNCIL FOR NORTH AMERICAN AFFAIRS OmCE IN U.s.A. / Sc!ENCE DIVISION 4 sos CONNECTICUT AVENUE, N.W., SUWs 13. WA.HINGTON D.C. 30008 RaranaNes No. CAESA*D t w N. ASS.ee.seN egg e... FAX:(202)362-3187 ' TELEFAX C0VER SHEET DATE: M*Y S, 1988 i T0: Mr. Bob Senseney, Office of. Int'l Programs l c/o Operation Center 951-0550 FAX # 492-sis 7 or 492-8110 VARIFICATION # 492-8893 I i' FROM; CCNAA, Science Div. 244-0822' '~

• • • • • • • • • • • eo...**ee*************.........

THIS TRANSMISSION CONSISTS OF 3 PAGESs EXCLUDING TH!'S ~ l l COVER SHEET. i ) F o I h - 8 (* ~~5 W -i W& 1

MAY 9.'86 _8:38 CCNAA SCIENCE DIV. PAGE.02 ese es 17 27 nTOMIC ENEF.GY COUNCIL R.O.C. e ****

• Re2

'I i 1 J Atomic Energy Council, the Republic of_ Chi _na_ For releases; Friday, May 9, 1986 SOVIET NUCLEAR ACCIDENT REPORT Contacts Chao Chin Tung Tel: (02)392-8567 Telex: 26554 Sir.catom Fax: (02)341-5377 After the Chernobyl accident, Taiwan Radiation Monitoring Center and the Institute of Nuclear Energy Research hava enhanced the survey activities of radioactive fallouts l in Taiwan area. Until May 7, 1986, the gross beta activities, detected both by cum. paper and air particulate, Y".II*"ygphgn,,,g,ygg,og,rggsj{p,b}gg,g,pgy,hgg, afternoon of May 7, 1986, measured 20-39 pCi/l of I-131. Comparing with the ales:t level of 3,000 pCi/1, the detected value was rather low, which poses no threat to the public health. t J B yo I A - 8 6->~55 W 4-

MAY 9 '66 6:38 CCNAA SCIENCE DIV. PAGE 03 s U si* 17 r22 M TOMI C ENERGY C*"NCI L. R. 0. 4.. Cross Beta activity of f allout on Taiwan, R.O.C. (cum papst) 2 untetuci/km. day ... Location I-Lan Lungtan Taipet Hsinchu Taichung Kaohsiung .--_r_.y .Ian., t g l 4 4. as { as.a7 l sa.es i fi s. s e l ss es l

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+a. e as.s l l _.-I. _. p _. _. 1. e s. e s l. _. _.._ _. I '[W hG l A-@"'M Alert level: 34,000 uC1/km. day Issued on May 9,1986 by. the Atomic Energy Council, R.O.C. l l

l l MAY 9 '86 0139. CCNAA SCIENCE DIV. PAGE.04 L 05, g3 17 27 ATOMIC ENERAY COUNCIL R.U.t.:. = * *

• noa t-Gross Beta activity of fallout on Taiwan, R.O.C.

(air particulate) unit: 10~13uci/mi Location I_Lan Taipei Taichung Kaohsiung Hengchun p__._...y_.._..j..g..._._....,....._......, Jan.,'86 I O.82i O.S41 0.G1 1 0,661 0.4SI p.. __ _ . p +._ _. - -... p _._ _... _. p .....g reb.,'86 1 0-. 4 6 1 0 431 0 651 0 G31 0 24 I g. _. .p._ _.. _. .p __ .p . p - _.... .I Mar..,'86 i O.591 0.491 0 641 0 7 7 1-G.15I p.... _..g._ .p._ _. .p -._....._.p.. _....... 4 Apr.,'86 1, 0 431 0 441 0.431 0.621 0 49i g ._. p _..p ._ - __.p _. _ _ _. . p -- - _.....i 04/21/86 1 0.261 0.691 0.26I O.G21 0. ? il l' i.... _ 2. _.i -. _. _. _..i 04/23/86 1 0 4WI e.I < e.aq i o.oe i o.,, i p .p._ _..p..._ _ __ __. p - _ + _ .i 04/25/86 1 0 6 C l. 0 34 1 0 431 0.71 1 0..I 3 I g..... ._ __.p - _. ,p - __ . p .p _. _.... . 4 04/28/86 i 0 95.1 0 951 0.601 0.621 0 6e1 p._ _ -._.p _ .. _ +._._ _. _ .p _ 4.._._. .. i 04/30/86 1 0 431 0 391 0.57i O.621 0.391 l p ._.. - __.p _. .p _._ _ .p .p .i 1 05/01/86 1 0.B21 0 521 0 631 0 52I O.21 1 p -._ .p .p . p _..p _. ..i 1 0 531 0 431 0.B01 0 521 0.2ei .p __... _. _.p _.._ _ __ _.. p. _ '_... _.. p _. _. . p._ ....._. i 05/02/86 l 0.521 0.60l 0 60'l 0 261 05/03/86 I

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.p - - _. -... + _. - -.p .p - __ -. -. p._ .........g 1 0 531 0.601 05/04/86 i O.561 0.81 1 3 p .p .p _ _. ._._.p ._.p .{ 05/05/86-1 'O. 5 2 1 0.44 1 0.591 0.651 0'.44 l .p._...__+_._..p-_..__._.+.___9.._._..i ~ 05/06/86 1 0,. 5 2 1 0 631 0 821 0.621 0 351 .p.. .p .p .p . i. _._..... i 05/07/86 1 0.521 0 621 0 601 0.7Fi 0 64 I .p._. _ .p -.p __._..._ .p.. - _. _ _..l. _.- _.....; 1 0 1 0 77l I .p.._ .p p ._ G 4 I 1 05/08/86 - __.p .p- _.._ ... _.i I i l I/, I Ave, of I Apr., 1985 i O.S61 0 55l 0.59L 0. S'S I ~ 0 60I I 1, I l l I I s .p .p ._._.p _ __._ .p -._ _.._ . p Ave. of I I I I I I May,.1985 1 0.394 0 431* O 491 0.59i O.31 1 I 1 I I I I .p - - _. _.p .p ._ p _._ _ _ - + _. ..- _. i Range of I O.231 0. 151 0 151 0.23I O.23i Apr., 1985 : 1 ( l l l l 3 l l t I 0.851 1 46t 1 1 1 1 1.551 0.G7 i .p .... p._ __ _. _..g .p . p Range of 'l 0.OI l 0 OI I O.01 1 0. 191 0 10i 1 I I I M3y, 1985 I I I I I I i l. 1.061 1 16l 1 601 1 33I 0.62I a. .a._.._. __.4. A_. 4.- ._s Alert levels 2,500 x 10~1IuC1/mi Issued on May 9, 1986 by the Atomic Enerov Council, R.O.C.

MAY 13 '86 10:05 CCNAA SCIENCE DIV. PAGE 01 "s

• )

z / t COORDINATION COUNCIL FOR NORTH AMERICAN AFFAIRS omCE IN U.S.A. / SCIENCE Divist0N anos cone;Icticuf AvsNUS.N.W., SW478133 I WASHINGTON D.C. 30006 "='a"*- a"." ',f.*!?..'.!7.*!.'.".7. FAXi(202)362-3187 TEIEFAX COVER Sf1EET DATE: k/3k4 4 To: SidM04 A/Ad GCl-n[re FAX # /M,.2-2/8,') sy" t/f2 -I//d VARIFICATION # 415-M/S l FROM: AAAUh4 [thwe biv. THIS TRANSMIS$10N, CONSIST 5 0F 1 PAGES, EXCLUDING THIS COVER' SHEET. ~ .g 4 f p i a -s r.-w>s w5 o

,c ms 4.s oc ausco sunss a c i g m,, e pav .~ ..,....PAGE 02 a Gross anta acca.va.ty vA taA4vu v.. (air particulate) unita 10-13uci/m1l Location 2-Lan Taipei Taichung Xaohsiung Hongchun ... p...... - - y - - - ~,,g _ =, ,g.... e.g.m " l 'Jen.-19s6 l 'O. S 2 1 0.54l O.01 1 0. 8 8. I e... 0.'. 4. 5 l i., 1 Feb. 1sas, p. _ _... _.p .p _._.._ _ +..... 7.p,._ ,._. 4 3 e, 4 8.1 0.481 0.65l 0. B 3.I l .p.........._ +. + + _..,,..g. j,',ld., 3 '4 I j......_... ,6 _ - .{ - 1 Mar. 198 i O.591 0.491 0 84I 0 77l,e.4.Gl p..6 ..p......,.....p._ .p _ _. _ +._ _ .p.. L .g . I-Apr.1980 l 04.)1 0.44I 0 431 0. f5 2 1 0 431 + + ..._.p ._._.. p .g. lOt/28I O 95I O 9 'S I O.8s1 0.8 p...

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-1 t1AY-13 '86 10:06 CCNAA SCIENCE DIV. PAGE.03 .. ~ , S5 ( 13 17 s 24 RT. Gross Beta Activity of Fallour en Taiwan, ROC (cum. Paper) y 7 _ y - y _.s.u..C.1/k._m _. day 3 Unit y k f .. l location i I-Lan i Taipei i }isinchu l l l .I I i Taichugg..I .Kaohsiung I j g. ..... -. +...:... _.4. _. .p._ .p. .p <. g, 6.:. 1 ! Jan. 1986 1 4 #;. 5 6.I 3 2. 8 6 l 2.0 6 4 I l 6 4' S T T2.* I 2 1 g. _... j..... _ +, - - _ _.p 4. _.. p _.._ ' _ _.I ) l38.23130 16121. 7 0 l'-3 2 '.' 6'9 I' 3 0's e 9 i ._._.. +..... - -_ .p .p... _ _ + '.E 4 l Feb. 1986' ' l Mar. 1986 l38 1g139 91iS5.95122.3.~7'la9 711 ._..4.. .__f 4. .p- .p._- M'.p _.(

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