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Annual Environ Operating Rept 1986
	ML20209H741
Person / Time
Site:	Davis Besse
Issue date:	12/31/1986
From:	Shelton D; TOLEDO EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	1-727, NUDOCS 8705040112
	Download: ML20209H741 (141)
	v • d • e

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) TABLE OF CONTENTS PAGE TABLE OF CONTENTS I LIST OF TABLES III LIST OF FIGURES IV RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT INTRODUCTION 1 CHARACTERISTICS OF RADIATION 1 SOURCES OF RADIATION 4 STUDY OF HEALTH EFFECTS 6 gS HEALTH RISKS 7 NUCLEAR REACTOR OPERATION 9 CONTAINMENT OF RADIOACTIVITY 13 REACTOR SAFETY 14 DESCRIPTION OF THE DAVIS-BESSE NUCLEAR POWER STATION SITE 15 1986 RADI0 ACTIVE LIQUID AND GASE0US EFFLUENTS

SUMMARY

24 ASSESSMENT OF RADIOLOGICAL EXPOSURE PATHWAYS 29

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() TABLE OF CONTENTS (CONTINUED)

PAGE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 39 QUALITY ASSURANCE PROGRAM 52 1986 SAMPLING PROGRAM 54 ATMOSPHERIC MONITORING 57 DIRECT RADIATION MONITORING 63 TERRESTRIAL MONITORING 69 AQUATIC MONITORING 79

SUMMARY

AND CONCLUSIONS 85 REFERENCES 86 APPENDIX A: INTERLABORATORY COMPARISON PROGRAM RESULTS A-1 APPENDIX B: DATA REPORTING CONVENTIONS B-1 APPENDIX C: PROGRAM DEVIATIONS C-1 LAND USE CENSUS 90

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TABLE TITLE PAGE 1 SAMPLING LOCATIONS 20-4 2 1986 RADI0 ACTIVE EFFLUENT RELEASES 28 3 TYPE AND FREQUENCY OF COLLECTION 42 4 SAMPLE CODES USED IN TABLE 3 43 5 SAMPLING

SUMMARY

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6 ENVIRONMENTAL RADIOLOGICAL 45 MONITORING PROGRAM

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7 1986 AVERAGE GROSS BETA 62 4

CONCENTRATIONS

() 8 EXAMPLE OF LAND USE CENSUS TABLE 93

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N' LIST OF FIGURES FIGURE TITLE PAGE 1 DAVIS-BESSE NUCLEAR POWER STATION 12 UNIT NO. I j 2 SAMPLING LOCATIONS ON THE SITE 18 PERIPHERY OF THE DAVIS-BESSE NUCLEAR POWER STATION 3 SAMPLING LOCATIONS (EXCEPTING 19 THOSE ON THE SITE PERIPHERY),

DAVIS-BESSE NUCLEAR POWER STATION 4 ENVIRONMENTAL EXPOSURE PATHWAYS OF 30 MAN DUE TO RELEASES OF RADI0 ACTIVE MATERIALS TO THE ATMOSPHERE AND LAKE 7

( ,) 5 MAXIMUM INDIVIDUAL DOSE DUE TO 33 RELEASE OF NOBLE GAS -

WHOLE BODY DOSE 6 MAXIMUM INDIVIDUAL DOSE DUE TO 34 RELEASE OF NOBLE GASES -

SKIN DOSES 7 MAXIMUM INDIVIDUAL GASEOUS DOSE 35 DUE TO RELEASE OF H-3, C-14, RADIOI0 DINES AND PARTICULATES -

WHOLE BODY DOSES 8 MAXIMUM INDIVIDUAL GASEOUS DOSE 36 DUE TO RELEASE OF H-3, C-14, RADIOI0 DINE AND PARTICULATES -

SIGNIFICANT ORGAN

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LIST OF FIGURES (CONTINUED)

FIGURE TITLE PAGE 9 MAXIMUM INDIVIDUAL GASEOUS DOSE 37

- LIQUID - WHOLE BODY DOSES; CRITICAL RECEPT 0R: 0.6 MILES NW 0F DISCHARGE 10 MAXIMUM INDIVIDUAL DOSE - LIQUID - 38 SIGNIFICANT ORGAN DOSE 11 AIRBORNE PARTICULATES - MONTHLY 61 AVERAGES OF GROSS BETA ANALYSES 12 AMBIENT GAMMA RADIATION (TLD) - 66 MONTHLY AVERAGES

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. QUARTERLY AVERAGES I 14 AMBIENT GAMMA RADIATION (TLD) - 68 QUARTERLY AVERAGES Il 15 MAP SHOWING THE 16 CARDINAL 92 COMPASS POINTS

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RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l

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SUMMARY

THE OPERATION OF A NUCLEAR POWER PLANT MAY RESULT IN THE RELEASE OF SMALL AMOUNTS OF RADIOACTIVITY TO THE SURROUNDING ENVIRONMENT. A RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) HAS BEEN ESTABLISHED TO MONITOR THE RADIATION AND RADIOACTIVITY RELEASED TO THE ENVIRONMENT AROUND THE DAVIS-BESSE NUCLEAR POWER STATION. THIS PROGRAM INCLUDES THE SAMPLING, ANALYSIS, AND EVALUATION OF THE EFFECTS OF THESE RELEASES TO THE ENVIRONMENT, AS WELL AS THE EVALUATION OF THE RADIATION DOSES TO INDIVIDUALS.

APPROXIMATELY 5 YEARS OF INTENSIVE STUDIES WERE CONDUCTED BEFORE DAVIS-BESSE BECAME OPERATIONAL. THESE STUDIES PROVIDE A VAST WEALTH OF DATA ON PREOPERATIONAL LEVELS OF RADI0 ACTIVITY AND ARE USED FOR COMPARISON WITH OUR PRESENT RESULTS.

EACH YEAR AN ENVIRONMENTAL OPERATING REPORT IS PREPARED BY DAVIS-BESSE AND SUBMITTED TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION'(NRC). THE ANNUAL ENVIRONMENTAL O OPERATING REPORT CONTAINS THE RESULTS OF ALL RADIOLOGICAL AND NON-RADIOLOGICAL ENVIRONMENTAL MONITORING PERFORMED DURING THE PAST YEAR. THIS IS THE NINTH FULL YEAR OF STUDY SINCE DAVIS-BESSE BECAME OPERATIONAL.

IN PREVIOUS YEARS, THE REPORTS SUBMITTED TO THE NRC WERE VERY TECHNICAL AND DIFFICULT FOR THE AVERAGE PERSON TO UNDERSTAND. THIS YEAR WE HAVE TRIED TO IMPROVE THE REPORT SO IT WILL BE EASILY UNDERSTANDABLE TO THE GENERAL PUBLIC, BUT STILL MEET THE NRC REQUIREMENTS.

IN 1986, OVER 2000 RADIOLOGICAL SAMPLES WERE COLLECTED AND OVER 2600 ANALYSES FOR RADIOACTIVITY WERE PERFORMED.

RADIONUCLIDE CONCENTRATIONS MEASURED AT INDICATOR LOCATIONS WERE COMPARED WITH LEVELS MEASURED AT CONTROL LOCATIONS AND THOSE MEASURED IN PREOPERATIONAL STUDIES. THESE COMPARISONS 11DICATE BACKGROUND LEVEL RADI0 ACTIVITY IN ALL SAMPLES COLLECTED.

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THERE WAS AN EFFECT ON ENVIRONMENTAL RADI0 ACTIVITY RESULTING FROM THE ACCIDENT AT THE CHERNOBYL NUCLEAR REACTOR,s THE SAMPLING MEDLA AFFECTED WERE AIR AND MILK. LOW LEVELS OF I-131, RU-103, RU-106, CS-134, AND CS-137 WERE DETECTED IN THE AIR AND l-131 WAS DETECTED IN MILK SAMPLES COLLECTED DURING MAY, JUNE, AND JULY.

THE 1986 OPERATION OF DAVIS-BESSE HAD NO SIGNIFICANT OR MEASURABLE EFFECT ON THE QUALITY OF THE ENVIRONMENT. ALL RADI0 ACTIVITY RELEASED IN THE STATION'S EFFLUENTS WAS WELL BELOW THE APPLICABLE FEDEPAL AND STATE ^ REGULATORY LIMITS.

THE ESTIMATED RADIATION DOSE TO THE GENERAL PUBLIC DUE TO THE OPERATION OF DAVIS-BESSE WAS ALSO WELL BELOW ALL APPLI-CABLE REGULATORY LIMITS. ,

THE RESULTS OF THE RAD!OLOG[DAL ENVIRONMENTAL MONITORING PROGRAM DEMONS 1NATE THE ADEQUACY OF THE CONTROL OF RADI0AC-TIVE EFFLUENTS AT DAVIS-BESSE. THESE RESULTS ALSO SHOW THAT _. l DAVIS-BESSE COMPLIES WITH ALL APPLICABLE FEDERAL AND STATE REGULATIONS.

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C RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT INTRODUCTION C0AL, OIL, NATURAL GAS AND HYDROPOWER HAVE BEEN USED TO RUN

, THE NATION'S ELECTRIC GENERATING PLANTS; HOWEVER, EACH HAS ITS PRICE TO PAY. COAL FIRED POWER PLANTS EXTRACT A GREAT PRICE FROM THE ENVIRONMENT THROUGH THE EFFECTS OF MINING, 1 ACID RAIN, AND AIRBORNE DISCHARGES. 0IL AND NATURAL GAS ARE I IN LIMITED SUPPLY AND ARE THEREFORE COSTLY. HYDROPOWER IS I LIMITED DUE TO THE IMPACT OF DAMMING OUR WATERWAYS AND WE ONLY HAVE A FEW SUITABLE SITES LEFT IN OUR COUNTRY. I NUCLEAR ENERGY NOW PROVIDES AN ALTERNATE SOURCE OF ENERGY.

BESIDES BEING A READILY AVAILABLE SOURCE OF ENERGY, NUCLEAR POWER PLANTS HAVE A VERY SMALL IMPACT ON THE ENVIRONMENT.

IN FACT, THE AREA AROUND THE DAVIS-BESSE NUCLEAR POWER STATION IS SO ENVIRONMENTALLY SAFE THAT THE HUNDREDS OF ACRES SURROUNDING THE PLANT ARE A WILDLIFE PRESERVE.

IN ORDER FOR YOU TO MORE FULLY UNDERSTAND THIS UNIQUE SOURCE OF ENERGY, BACKGROUND INFORMATION ON BASIC RADIATION CHARAC-

TERISTICS, RISK ASSESSMENT, REACTOR OPERATIONS, EFFLUENT

\- CONTROL, AND ENVIRONMENTAL MONITORING IS PROVIDED.

CHARACTERISTICS OF RADIATION ALL MATTER IS MADE OF ATOMS, WHICH ARE THE SMALLEST PARTS OF AN ELEMENT THAT STILL HAVE ALL THE CHEMICAL PROPERTIES OF THAT ELEMENT. ATOMS ARE SO SMALL THAT 36 BILLION OF THEM COULD BE PLACED ON THE HEAD OF A PIN. AT THE CENTER OF AN l

ATOM IS A NUCLEUS. THE NUCLEUS CONSISTS OF l NEUTRONS, WITH NO CHARGE AND PROTONS, WITH A POSITIVE CHARGE. ELECTRONS MOVE IN AN ORBIT AROUND THE NUCLEUS AND ARE NEGATIVELY CHARGED. NORMALLY, THE PARTS OF AN ATOM ARE IN A BALANCED OR STABLE STATE. ATOMS WHOSE NUCLEI CONTAIN AN EXCESS OF ENERGY ARE CALLED RADIOACTIVE ATOMS OR RADIO-NUCLIDES. RADIONUCLIDES CAN BE NATURALLY OCCURRING, SUCH AS CRANIUM-238, THORIUM-232 AND POTASSIUM-40, OR MAN-MADE, SUCH l AS 10 DINE-131, CESIUM-137, AND COBALT-60.

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RADI0 ACTIVITY IS THE RESULT OF EITHER ELECTRICALLY CHARGED l PARTICULATES (ALPHA AND BETA PARTICLES) OR ELECTROMAGNETIC ENERGY (GAMMA AND X-RAYS). ALPHA PARTICLES ARE POSITIVELY CHARGED AND CAN BE EASILY STOPPED BY A SHEET OF PAPER OR A FEW CENTIMETERS OF AIR. BETA PARTICLES, A STREAM OF HIGH SPEED ELECTRONS, ARE MORE PENETRATING THAN ALPHA PARTICLES.

THEY CAN USUALLY PENETRATE THIN METAL SHEETS, BUT THEY CANNOT PASS THROUGH A MILLIMETER OF LEAD OR A FEW CENTIME-TERS OF FLESH.

GAMMA AND X-RAYS ARE FORMS OF ELECTROMAGNETIC RADIATION WHICH ARE ENERGY WAVES RESULTING FROM INTERACTIONS WITH THE ELECTRIC OR MAGNETIC FIELD OF THE ATOM'S NUCLEUS. LIGHT IS A COMMON FORM 0F ELECTROMAGNETIC RADIATION. THE PRIMARY DIFFERENCE BETWEEN LIGHT AND GAMMA /X-RAYS IS THE FACT THAT GAMMA AND X-RAYS ARE 10NIZING RADIATION. GAMMA AND X-RAYS CAN BE STOPPED BY SHIELDING SUCH AS LEAD OR CONCRETE.

RADIOACTIVE ATOMS ATTEMPT TO REACH A STABLE (NON-RADIO ACTIVE) STATE BY LOSING ENERGY THROUGH A PROCESS KNOWN AS RADIOACTIVE DECAY. RADIOACTIVE DECAY RELEASES ENERGY FROM THE ATOM THROUGH THE EXPULSION OF PARTICLES AND ELECTROMAG-NETIC RADIATION. PARTICULATE RADIATION MAY BE ELECTRICALLY l CHARGED SUCH AS ALPHA OR BETA PARTICLES, OR BE ELECTRICALLY NEUTRAL, SUCH AS NEUTRONS.

[i AL F-L I FE THE AMOUNT OF TIME REQUIRED FOR RADIOACTIVE DECAY IS UNIQUE TO EACH RADIONUCLIDE AND IS MEASURED BY HALF-LIVES. A RADIOACTIVE HALF-LIFE IS THE AMOUNT OF TIME REQUIRED FOR A RADI0 ACTIVE SUBSTANCE TO LOSE HALF 0F ITS ACTIVITY THROUGH THE. PROCESS OF RADI0 ACTIVE' DECAY. COBALT-60 HAS A HALF-LIFE OF ABOUT 5 YEARS, S0 AFTER 5 YEARS 50% OF ITS ACTIVITY IS GONE AND AFTER 10 YEARS 75% HAS DECAYED AWAY. HALF-LIVES VARY FROM MILLIONTHS OF A SECOND TO MILLIONS OF YEARS.

RADI0 ACTIVE ATOMS MAY DECAY DIRECTLY TO A STABLE STATE OR MAi UNDERGO A SERIES OF DECAY STAGES, DAUGHTER PRODUCTS, WHICH EVENTUALLY LEAD TO A STABLE ATOM. RADIUM-226, FOR EXAMPLE, HAS 10 SUCCESSIVE DAUGHTER PRODUCTS WHICH LEAD TO LEAD-226 AS A FINAL STABLE FORM.

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O MEASUREMENTS THE AMOUNT OF ACTIVITY OF A RADIONUCLIDE IS MEASURED BY A BASIC UNIT CALLED A CURIE, NAMED AFTER MARIE AND PIERRE CURIE WHO DISCOVERED RADIUM IN 1898. A CURIE (CI) IS THAT AMOUNT OF A RADI0 ACTIVE MATERIAL THAT DISINTEGRATES (DECAYS)

AT A RATE OF 37 BILLION ATOMS PER SECOND. IN THE EVALUATION OF ENVIRONMENTAL RADI0 ACTIVITY, A CURIE IS AN EXTREMELY LARGE AMOUNT, SO SMALLER UNITS OF THE CURIE ARE USED. TWO COMMON UNITS ARE THE MICR0 CURIE (UCI), ONE MILLIONTH OF A CURIE AND THE PIC0 CURIE (PCI), ONE TRILLIONTH OF A CURIE.

A CURIE IS A MEASUREMENT OF RADIOACTIVITY AND NOT QUANTITY.

THE AMOUNT OF SOME COMMON ELEMENTS NECESSARY TO PRODUCE ONE CURIE OF RADI0 ACTIVITY ARE LISTED BELOW.

. ISOTOPE AMOUNT OF MATERIAL RADIUM-226 1 GRAM 4

() 10 DINE-131 URANIUM-238 8 MILLIONTHS OF A GRAM 3.3 TONS NOTE: 1 POUND = 454 GRAMS DOSE TOTAL BODY (WHOLE BODY) RADIATION INVOLVES THE EXPOSURE OF i

ALL ORGANS. MOST BACKGROUND EXPOSURES ARE OF THIS FORM.

RADI0 ACTIVE ELEMENTS CAN ENTER THE BODY THROUGH INHALATION OR INGESTION. WHEN THEY D0, THEY ARE NOT DISTRIBUTED EVENLY. FOR EXAMPLE, RADIOI0 DINE SELECTIVELY CONCENTRATES IN THE THYROID GLAND, WHILE RADIOCESIUM COLLECTS IN MUSCLE AND LIVER TISSUE AND RADIOSTRONTIUM IN MINERALIZED BONE.

THE TOTAL DOSE TO ORGANS BY A GIVEN RADIONUCLIDE ALSO DEPENDS ON THE QUANTITY AND THE AMOUNT OF TIME THAT THE RADIONUCLIDE REMAINS IN THE BODY. SOME RADIONUCLIDES REMAIN IN THE BODY FOR VERY SHORT TIMES DUE TO THEIR RAPID RADI0AC-TIVE DECAY AS WELL AS THEIR NORMAL ELIMINATION FROM THE

() BODY. OTHERS MAY REMAIN FOR YEARS.

PERSONNEL EXPOSURE IS NORMALLY MEASURED BY A UNIT OF RADIA-TION CALLED A REM (ROENTGEN EQUIVALENT MAN). A REM IS THE UNIT OF DOSE OF ANY TYPE OF IONIZING RADIATION THAT PRODUCES EQUIVALENT BIOLOGICAL EFFECTS AS A UNIT OF ABSORBED DOSE OF ORDINARY X-RAYS. S0 1 REM OF ALPHA RADIATION PRODUCES EQUIVALENT BIOLOGICAL EFFECTS AS 1 REM OF X-RAYS. 0FTEN A SMALLER UNIT OF THE REM, A MILLIREM (MREM) IS USED. 1000 MILLIREMS ARE EQUIVALENT TO 1 REM. GENERALLY, THE TERM PERSON-REM OR MAN-REM IS USED TO REPORT THE TOTAL DOSE TO A POPULATION. IF A POPULATION OF 10,000 PEOPLE EACH RECEIVED 1 REM, THE TOTAL DOSE TO THE POPULATION WOULD BE REPORTED AS 10,000 PERSON-REMS.

SOURCES OF RADIATION RADIATION IS NOT A NEW CREATION OF THE NUCLEAR POWER INDUS-TRY. IT IS A NATURAL PART OF THE EARTH. MANKIND HAS ALWAYS LIVED WITH RADIATION AND ALWAYS WILL. EVERY SECOND OF OUR LIVES, OVER 7,000 ATOMS UNDERG0' RADIOACTIVE DECAY IN THE BODY OF THE AVERAGE ADULT. RADI0 ACTIVITY EXISTS IN THE SOIL, WATER, AIR AND OUTER SPACE. ALL THESE COMMON SOURCES OF RADIATION CONTRIBUTE TO NATURAL BACKGROUND RADIATION.

SOME OF THE COMMON SOURCES OF BACKGROUND RADIATION AND THEIR ASSOCIATED DOSES ARE GIVEN BELOW.

SOURCE D0sE (MILLIREM /YR.)

NATURAL: COSMIC RAYS 45 INTERNAL 25 GROUND SOURCES 60 MAN MADE MEDICAL / DENTAL X-RAYS 72 WEAPONS FALLOUT 4 RADI0 PHARMACEUTICALS 2 OCCUPATIONAL 0.8 NUCLEAR POWER 0.003 0

l () THE AVERAGE PERSON IN THE UNITED STATES RECEIVES ABOUT 220 MREM (0.22 REM) PER YEAR FROM THE NATURAL BACKGROUND SOURCES 0F RADIATION. LOCAL FACTORS SUCH AS GEOLOGY, ALTITUDE AND WEATHER CONDITIONS CAN PRODUCE FLUCTUATIONS IN BACKGROUND RADIATION LEVELS. IN COLORADO, FOR EXAMPLE, PEOPLE RECEIVE AN ADDITIONAL 80 MREM EACH YEAR FROM COSMIC RADIATION DUE TO THEIR HIGH ALTITUDE AND RADIOACTIVITY NATURALLY OCCURRING IN THE S0IL.

RECENTLY, CONCERN HAS BEEN EXPRESSED OVER ANOTHER SOURCE OF NATURAL BACKGROUND RADIATION - RADON, RADON IS AN INVISIBLE GAS WHICH IS NATURALLY RADI0 ACTIVE. IT IS PRODUCED BY THE DECAY OF URANIUM AND RADIUM, WHICH ARE FOUND AS TRACE ELEMENTS IN THE EARTH'S CRUST. THE NATIONAL COUNCIL ON RADIATION PROTECTION AND MEASUREMENTS (NCRP) ESTIMATES THAT THE AVERAGE INDIVIDUAL RECEIVES ABOUT 3000 MREM A YEAR TO THE LUNGS FROM NATURAL RADON. RADON IS NOT A SIGNIFICANT THREAT TO HEALTH IN AN OPEN AIR ENVIRONMENT, BECAUSE IT DISPERSES READILY. .HOWEVER, WHEN IT ACCUMULATES IN A TIGHTLY SEALED AREA AND CANNOT DISPERSE, IT MAY CAUSE LUNG CANCER. MANY HOUSES ARE BEING BUILT THAT ARE TIGHTLY SEALED AND THIS CAN ALLOW AN ACCUMULATION OF RADON. BUILDING

() MATERIALS SUCH AS CINDER BLOCK AND CONCRETE ARE RADON SOURCES. RADON CAN ALSO BE DISSOLVED IN WELL WATER AND CONTRIBUTE TO AIRBORNE RADON IN HOUSES WHEN RELEASED THROUGH SHOWERS OR WASHING. RADON MAY BE RESPONSIBLE FOR AS MANY AS 20,000 CASES OF LUNG CANCER A YEAR IN THE UNITED STATES.

OTHER NATURAL SOURCES OF RADIATION INCLUDE DRINKING WATER WHICH CONTAINS TRACES OF URANIUM AND RADIUM, AND MILK WHICH CONTAINS RADIOACTIVE POTASSIUM.

ABOUT 300 COSMIC RAYS FROM OUTER SPACE PASS THROUGH EACH PERSON EVERY SECOND. THE INTERACTION OF COSMIC RAYS WITH ATOMS IN THE EARTH'S ATMOSPHERE PRODUCES RADIONUCLIDES SUCH AS BERYLLIUM-7 (BE-7), BERYLLIUM-10 (BE-10), CARBON-14 (C-14), TRITIUM (H-3), AND SODIUM-22 (NA-22). SOME OF THESE

! RADIONUCLIDES BECOME DEPOSITED ON LAND AND WATER SURFACES l El!LE THE REMAINDER STAY SUSPENDED IN THE ATMOSPHERE.

PEOPLE ARE ALSO EXPOSED TO RADIATION FROM MAN-MADE SOURCES

OF RADIATION. THE LARGEST OF THESE SOURCES IS EXPOSURE FROM MEDICAL X-RAYS, FLUOROSCOPIC EXAMINATIONS, AND RADI0 PHARMA-CEUTICALS (RADI0 ACTIVE DRUGS). THESE SOURCES RESULT IN AN

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AVERAGE DOSE OF 72 MREM A YEAR. SMALL DOSES ARE CAUSED BY CONSUMER PRODUCTS SUCH AS TELEVISIONS, SMOKE ALARMS, AND FERTILIZER. VERY SMALL DOSES RESULT FROM THE PRODUCTION OF NUCLEAR POWER.

STUDY OF HEALTH EFFECTS THE EFFECTS OF IONIZING RADIATION ON HUMAN HEALTH HAVE BEEN UNDER STUDY FOR MORE THAN EIGHTY YEARS. SCIENTISTS HAVE GAINED MUCH VALUABLE KNOWLEDGE THROUGH THE STUDY OF LABORA-TORY ANIMALS THAT WERE EXPOSED TO RADIATION UNDER EXTREMELY CONTROLLED CONDITIONS. HOWEVER, IT HAS PROVEN DIFFICULT TO RELATE THE BIOLOGICAL EFFECTS OF IRRADIATED LABORATORY ANIMALS TO THE POTENTIAL HEALTH EFFECTS OF HUMANS. HENCE, MUCH STUDY HAS BEEN DONE WITH HUMAN POPULATIONS THAT WERE IRRADIATED UNDER VARIOUS CIRCUMSTANCES. THESE GROUPS INCLUDE THE SURVIV0RS OF THE ATOM BOMB; PERSONS UNDERGOING MEDICAL RADIATION TREATMENT; RADIUM DIAL PAINTERS, WHO INGESTED LARGE AMOUNTS OF RADI0 ACTIVITY BY " TIPPING" THE PAINT BRUSHES WITH THEIR LIPSJ URANIUM MINERS, WHO INHALED LARGE AMOUNTS OF RADIOACTIVE DUST WHILE MINING PITCHBLENDJ AND EARLY RADIOLOGISTS, WHO ACCUMULATED LARGE DOSES OF RADIATION WHILE UNAWARE OF THE POTENTIAL HAZARDS. l THE STUDIES PERFORMED ON THESE GROUPS HAVE HELPED INCREASE OUR KNOWLEDGE ON THE HEALTH EFFECTS OF LARGE DOSES OF RADIATION. TO BE ON THE CONSERVATIVE SIDE, GENERALLY WE ASSUME THAT HEALTH EFFECTS OCCUR PROPORTIONALLY TO THOSE OBSERVED FOLLOWING A LARGE DOSE OF RADIATION.

RADIATION SCIENTISTS AGREE THAT THIS ASSUMPTION OVERESTI-MATES THE RISKS ASSOCIATED WITH LOW LEVEL RADIATION EXPO-SURE.

~ THE EFFECTS PREDICTED IN THIS MANNER HAVE NOT BEEN ACTUALLY OBSERVED IN INDIVIDUALS EXPOSED TO LOW LEVEL RADIATION.

RELATING THE EFFECTS OBSERVED DUE TO HIGH LEVEL EXPOSURE TO THE POTENTIAL EFFECTS WHICH MAY BE CAUSED BY LOW LEVEL FXPOSURE IS DIFFICULT TO SAY THE LEAST. ONE COULD WELL STATE, "N0 ONE KNOWS THE RISKS OF SMOKING A FEW CIGARETTES,"

BUT THE RISKS OF SMOKING A LARGE NUMBER OF CIGARETTES ARE WELL KNOWN. IF 10,000 PEOPLE SM0KE AN AVERAGE OF FOUR CIGARETTES A DAY, ABOUT 100 DEATHS WILL RESULTJ DATA ARE NOT O

AVAILABLE FOR LOWER SMOKING RATES, FOR RADIATION, DOSES OF 100 REM TO EACH OF 10,000 PEOPLE WOULD BE REQUIRED TO CAUSE AN EQUAL NUMBER OF DEATHS. THE EFFECTS OF RADIATION ON HUMANS AT DOSES OF 100 REM ARE WELL KNOWN. THE MAJOR CONTROVERSY OVER RADIATION RISKS TODAY IS HOW TO EXTEND THE RISK ESTIMATES TO EVEN LOWER LEVELS. AS WE GET TO LOWER LEVELS, IT BECOMES MORE AND MORE DIFFICULT TO DETECT THE EFFECTS, AND THIS BECOMES A PROBLEM. WOULD IT BE POSSIBLE TO DETECT THE EFFECT OF DOING ONE SITUP OR PUSHUP A DAY?

FINDING OUT THE EFFECT ON THE DEATH RATE OF ONE REM OF EXPOSURE IS ABOUT THE SAME AS TRYING TO FIND OUT THE EFFECT OF SM0 KING ONE CIGARETTE A MONTH. THE POINT IS THAT THE EFFECT OF ONE REM IS EXTREMELY SMALL. THERE ARE PHYSICAL LIMITS TO HOW FAR WE CAN GO TO ASCERTAIN PRECISELY THE SIZE OF THE RISK, BUT WE D0 KNOW IT IS SMALL.

HEALTH RISKS SINCE THE ACTUAL EFFECTS OF LOW LEVEL RADIATION ARE DIFFI-CULT TO ASCERTAIN, SCIENTISTS OFTEN REFER TO THE RISK INVOLVED IN AN ACTION. THE PROBLEM IS ONE OF EVALUATING ALTERNATIVES - 0F COMPARING RISKS AND WEIGHING THEM AGAINST

() BENEFITS. RISKS ARE A PART OF EVERYDAY LIFE. THE PROBLEM LIES IN DETERMINING HOW GREAT ARE THE RISKS AND WHAT SHOULD WE TRULY BE AFRAID OF. FOR THIS, IT IS IMPORTANT TO ACQUIRE A SENSE OF PERSPECTIVE.

WE ACCEPT THE INEVITABILITY OF AUTOMOBILE ACCIDENTS.

CHANCES ARE THAT SEVERAL OF THE PEOPLE READING THIS REPORT WILL BE SERIOUSLY INJURED THIS YEAR FROM AUTOMOBILES. BY BUILDING SAFER CARS OR WEARING SEAT BELTS, THE RISK COULD BE REDUCED. BUT EVEN A PARKED CAR IS NOT RISK FREE. YOU COULD CHOOSE NOT TO DRIVE, YET PEDESTRIANS AND BICYCLISTS ARE ALSO INJURED BY CARS. REDUCING THE RISK OF INJURY FROM AUTOM0-BILES TO ZERO REQUIRES MOVING TO A PLACE WHERE THERE ARE NONE.

WHILE ACCEPTING THE MANY DAILY RISKS OF LIVING, MANY SEEM TO BE GETTING THE IDEA THAT THEIR DEMANDS FOR ENERGY SHOULD BE MET ON ESSENTIALLY A RISK-FREE BASIS. SINCE THIS IS IMPOS-SIBLE, ATTENTION SHOULD BE FOCUSED ON TAKING REASONABLE STEPS TO SAFEGUARD THE PUBLIC, ON DEVELOPING REALISTIC ASSESSMENT OF THE RISKS, AND ON PLACING THEM IN PERSPECTIVE.

ONE OF THE MOST WIDELY DISTORTED RISKS IS RADIATION.

BECAUSE YOU CANNOT SEE, FEEL, TASTE, HEAR, OR SMELL RADIA-TION, IT HAS AN AURA 0F MYSTERY. BUT THIS SAME MYSTERY APPEARS TO BE ABSENT FROM OTHER POTENTIALLY HAZARDOUS THINGS FOR WHICH WE HAVE A LACK OF SENSORY PERCEPTION, SUCH AS RADIO WAVES, CARBON MON 0XIDE, AND SMALL CONCENTRATIONS OF NUMERCUS CANCER-CAUSING SUBSTANCES. THESE DO NOT GENERATE THE SAME DEGREE OF FEAR AS RADIATION, TO BETTER EXPLAIN THE EFFECT OF RADIATION ON PEOPLE, WE CAN COMPARE THE RISK OF RADIATION EXPOSURE WITH THE RISKS ASSOCIATED WITH OTHER LIFE EXPERIENCES. WHEN WE LOOK AT THE RISK OF DEATH ASSOCIATED WITH VARIOUS ACTIVITIES, WE USUALLY LOOK AT THE "0NE-IN-A-MILLION" RISK. IN OTHER WORDS, THERE IS ONE CHANCE IN A MILLION THAT EACH OF THE FOLLOWING ACTIVITIES WILL PRODUCE DEATH:

e SMOKING 1.5 CIGARETTES e DRINKING i LITER Of WINE e EATING 40 TABLESP0CNS OF PEANUT BUTTER e EATING 100 CHARCJAL-BROILED STEAKS e TRAVELING 300 MILES IN A CAR e TRAVELING 1000 MILES IN A JET PLANE o HAVING 1 CHEST X-RAi e RADIATION FROM LIVING OUTDOORS, 24 HOURS A DAY, EVERY DAY, FOR 5 YEARS AT THE SITE BOUNDARY OF A NUCLEAR POWER PLANT.

WHEN COMPARED TO THE RISKS OF EVERYDAY LIFE, THE RISKS ASSOCIATED WITH LOW LEVEL RADIATION EXPOSURE ARE SMALL.

THE AMERICAN CANCER SOCIETY ESTIMATES THAT ABOUT 30 PERCENT OF ALL AMERICANS WILL DEVELOP CANCER AT SOME TIME IN THEIR LIVES FROM ALL POSSIBLE CAUSES. S0, IN A GROUP OF 10,000 PEOPLE IT IS EXPECTED THAT 3,000 0F THEM WILL DEVELOP CANCER. IF EACH PERSON WERE TO RECEIVE ONE ADDITIONAL REM OF RADIATION, THEN IT IS EXPECTED THAT 3 MORE MAY DEVELOP CANCER. THIS INCREASES THE RISKS FROM 30 PERCENT TO 30.03%.

HENCE, THE RISKS OF RADIATION EXPOSURE ARE SMALL WHEN COMPARED TO THE HAZARDS OF NORMAL EVERYDAY LIFE.

THESE COMPARISONS SHOULD GIVE SOME IDEA 0F THE RISK INVOLVED IN THINGS WITH WHICH YOU ARE FAMILIAR. THEY GIVE A BASIS FOR JUDGING WHAT SM0 KING, EATING, OR DRIVING A CAR COULD MEAN TO YOUR HEALTH AND SAFETY. THIS IS THE KIND OF PER-SPECTIVE TO WHICH PEOPLE CAN RELATE. EVERYONE KNOWS THAT LIFE IS RISKY. IF YOU HAVE THE BASIS FOR JUDGEMENT, YOU CAN DECIDE WHAT TO DO OR NOT D0.

NUCLEAR REACTOR OPERATION NUCLEAR POWER PLANTS ARE BUILT TO PROVIDE ELECTRICITY FOR PEOPLE. ELECTRICITY IS PRODUCED BY PLANTS USING FOSSIL FUEL, URANIUM, OR FALLING WATER. A FOSSIL-FUELED POWER PLANT BURNS C0AL, OIL OR NATURAL GAS IN A BOILER TO PRODUCE HEAT ENERGY. NUCLEAR POWER PLANTS USE URANIUM FUEL AND THE HEAT PRODUCED FROM THE FISSION PROCESS IS USED TO MAKE HEAT ENERGY. IN BOTH CASES, THE HEAT BOILS WATER TO PRODUCE STEAM WHICH DRIVES A TURBINE WHICH TURNS A GENERATOR AND PRODUCES ELECTRICITY.

NUCLEAR ENERGY IS PRODUCED BY A PROCESS CALLED FISSION.

FISSION OCCURS WHEN A HEAVY ATOM, SUCH AS URANIUM, IS SPLIT INTO LIGHTER FRAGMENTS. THIS SPLITTING CAUSES HEAT AND SEVERAL SMALL UNITS OF ENERGY CALLED NEUTRONS TO BE RE-LEASED. THE RELEASED NEUTRONS STRIKE OTHER URANIUM ATOMS, CAUSING THEM TO SPLIT (FISSION) AND SO RELEASE MORE HEAT AND NEUTRONS. THIS IS CALLED A CHAIN REACTION BECAUSE IT CONTINUES UNTIL STOPPED BY INSERTION OF THE REACTOR CONTROL RODS.

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O NATURAL URANIUM CONTAINS LESS THAT ONE PERCENT OF THE ISOTOPE U-235 WHEN IT IS MINED. THE REMAINDER OF THE NATURAL URANIUM IS THE IS0 TOPE U-238. U-235 IS MORE READILY i FISSIONED THAN THE OTHER, S0 THE AMOUNT OF U-235 MUST BE l INCREASED TO TWO OR THREE PERCENT FOR USE IN A COMMERCIAL l NUCLEAR REACTOR. THIS IS DONE BY A PROCESS CALLED ENRICH-MENT. BY COMPARISON, WEAPONS GRADE URANIUM IS ENRICHED TO OVER 90%. !

AFTER ENRICHMENT, THE URANIUM FUEL IS CHEMICALLY CHANGED TO URANIUM DIOXIDE, A DRY BLACK POWDER. THIS POWDER IS COM- I PRESSED AND SHAPED INTO SMALL CERAMIC PELLETS. EACH PELLET l IS ABOUT 3/4 INCHES LONG AND 3/8 INCHES IN DIAMETER. THE PELLETS ARE PLACED INTO 12 FOOT LONG METAL TUBES MADE OF ZIRCONIUM ALLOY, FUEL RODS. ABOUT FIVE POUNDS OF PELLETS ARE USED TO CILL EACH ROD. A TOTAL OF 208 FUEL RODS MAKE A SINGLE FUEL ASSEMBLY. THE DAVIS-BESSE REACTOR CORE CONTAINS 177 FUEL AS' EMBLIES.

CONTROL RODS ARE AN ESSENTIAL PART OF THE REACTOR CORE.

CONTROL RODS ".ONTAIN CADMIUM, INDIUM, AND SILVER METALS THAT ABSORB NEUTRO,4S AND CONTROL THE AMOUNT OF NEUTRONS PRODUCED IN THE REACTOR. A CHAIN REACTION CANNOT OCCUR WHEN THE RODS ARE INSERTED INTO THE CORE; THE CONTROL RODS ACT AS BRAKES TO SLOW DOWN OR STOP THE CHAIN REACTION. WHEN THE RODS ARE WITHDRAWN, FISSION OCCURS AND HEAT IS ONCE MORE GENERATED.

THE DAVIS-BESSE STATION USES A PRESSURIZED WATER REACTOR (PWR), SEE FIGURE 1. THE WATER IN THE REACTOR COOLING ._

SYSTEM ENTERS THE REACTOR AT 558 DEGREES FAHRENHEIT UNDER A PRESSURE OF 2,200 POUNDS-PER-SQUARE INCH (PSI). THIS PRESSURE PREVENTS THE WATER IN THE REACTOR FR M BOILING AND TURNING INTO STEAM.

THE REACTOR COOLING WATER ~ CIRCULATES CONTINUOUSLY IN A CLOSED PRIMARY LOOP THROUGH THE REACTOR AND STEAM GENERATORS (GREEN ON FIGURE 1). THE WATER HEATS TO 606 DEGREES FAHREN-HEIT AS IT PASSES THROUGH THE CORE. THE PIPES CARRYING THIS HOT WATER PASS THROUGH THE STEAM GENERATOR WHICH COOLS THE WATER DOWN TO 558 DEGREES FAHRENHEIT AGAIN. THE REACTOR HEAT IS TRANSFERRED TO A SECONDARY LOOP IN THE STEAM GENERA-TORS (BLUE ON FIGURE 1). THE REACTOR COOLING WATER (PRIMARY COOLANT) IS PREVENTED FROM COMING IN DIRECT CONTACT WITH THE WATER IN THE SECONDARY LOOP BY TUBES IN THE STEAM GENERA-O t

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TORS. THE WATER IN.THE SECONDARY LOOP B0!(S TO STEAM IN THE STEAM GENERATOR AND THE STEAM (RED ON FIGURE 1) FLOWS TO THE TURBINE GENERATOR WHERE ITS ENERGY IS CONVERTED TO ELECTRICITY.

FROM THE POINT THAT THE STEAM LEAVES THE REACTOR BUILDING, THE NUCLEAR PLANT CLOSELY RESEMBLES ANY OTHER STEAM POWERED

GENERATING PLANT. STEAM FROM THE' STEAM GENERATOR DRIVES THE

. TURBINE-GENERATOR AND IS THEN CONDENSED. IT IS COOLED TO A

} LIQUID FORM BY TRANSFERRING ITS HEAT.T0 A THIRD CLOSED LOOP SYSTEM CALLED THE CIRCULATING WATER SYSTEM (YELLOW ON FIGURE

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1). WATER IN THIS SYSTEM CARRIES HEAT FROM THE CONDENSER TO THE COOLING TOWER WHERE HEAT IS LOST TO THE ATMOSPHERE.

i THIS WATER IS COMPLETELY SEPARATED FROM ANY WATER WHICH IS i POTENTIALLY RADIOACTIVE. THE WATER IS RECIRCULATED BACK TO THE CONDENSER TO COOL MORE STEAM.

t COOLING TOWERS ARE PROBABLY THE MOST DISTINCTIVE FEATURES AT

! NUCLEAR POWER PLANTS AND ARE USED TO REMOVE EXCESS HEAT FROM

! THE PLANT SO THE AMOUNT OF WARM WATER DISCHARGED TO LAKE

! ERIE IS MINIMIZED. SUCH TOWERS ARE ALSO FOUND AT SOME NEW C0AL-FIRED PLANTS.

!O 1 THE COOLING TOWER STRUCTURE IS ACTUALLY A CHIMNEY DESIGNED TO CREATE A NATURAL DRAFT, JUST LIKE THE CHIMNEY IN A l . FIREPLACE. IT IS OPEN AT THE BOTTOM TO LET AIR IN. AB0VE l

THIS ARE SHEETS OF FILL MATERIAL, ARRANGED S0 THAT AIR CAN FLOW PAST. WARMED WATER IS SHOWERED DOWN ONTO THE FILL AND

IS COOLED TO ABOUT 60 DEGREES FAHRENHEIT BY THE DRAFT.0F AIR PASSING UP THROUGH THE CHIMNEY. THIS COOLED WATER FALLS l INTO A POOL AT THE BOTTOM OF THE TOWER AND IS RETURNED TO i i THE CONDENSER TO BE USED AGAIN.

{ THIS WATER DOES NOT MIX WITH THE REACTOR WATER AND IS l THEREFORE NON-RADIOACTIVE. BOTH THE PRIMARY AND SECONDARY i COOLING SYSTEMS ARE CONTAINED WITHIN SEPARATE CLOSED PIPING

! SYSTEMS. THE VAPOR DISCHARGED FROM THE COOLING TOWER INTO THE ATMOSPHERE IS JUST PLAIN WATER.

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\> CONTAINMENT OF RADIOACTIVITY ESSENTIALLY ALL THE RADI0 ACTIVITY OF AN OPERATING NUCLEAR POWER PLANT IS CONTAINED BY A SYSTEM OF ISOLATION BARRIERS.

THEY PREVENT THE ESCAPE OF RADI0 ACTIVITY TO THE ENVIRONMENT.

THE FIRST BARRIER IS PROVIDED BY THE CERAMIC FUEL PELLETS.

THEY CONTAIN THE FUEL AND MOST OF THE FISSION PRODUCTS PRODUCED. ONLY THOSE FISSION PRODUCTS THAT ARE VOLATILE AND GASEOUS AT NORMAL OPERATING TEMPERATURE ARE ABLE TO MIGRATE OUT.

THE PELLETS ARE CONTAINED IN THE SECOND BARRIER, THE FUEL RODS. THEY ALSO PREVENT THE ESCAPE OF RADI0 ACTIVITY. THERE IS A SMALL GAP BETWEEN THE FUEL AND THE METAL CONTAINER IN WHICH NOBLE GASES AND OTHER VOLATILE NUCLIDES CAN COLLECT.

THE THIRD BARRIER IS THE PRIMARY COOLANT. MANY OF THE FISSION PRODUCTS, INCLUDING RAD 1010 DINES AND STRONT!UMS, ARE WATER SOLUBLE AND ARE RETAINED IN THE PRIMARY COOLANT.

THESE NUCLIDES CAN BE REMOVED BY THE PURIFICATION SYSTEM (DEMINERALIZERS) 0F THE REACTOR. THE NOBLE GASES, SUCH AS RADIOACTIVE KRYPTONS AND XENONS, DO NOT READILY DISSOLVE BUT I)

\-' EVOLVE INTO A GAS OR VAPOR PHASE ABOVE THE COOLANT, ESPE-CIALLY WHEN THE COOLANT IS DEPRESSURIZED.

THE STEEL REACTOR PRESSURE VESSEL, WITH WALLS THAT ARE 81 INCHES THICK, AND THE STEEL P! PING OF THE PRIMARY COOLANT SYSTEM PROVIDE A FOURTH BARRIER, AND CONTAIN ALL RADIO-NUCLIDES IN THE PRIMARY COOLANT.

THE CONTAINMENT BUILDING PROVIDES THE FINAL BARRIER. THIS IS THE DOME SHAPED BUILDING SEEN IN THE THE MIDDLE OF THE PLANT SITE. THE CONTAINMENT BUILDING HAS THICK, STEEL LINED, REINFORCED CONCRETE WALLS (21 FEET THICK) TO ENCLOSE THE PRIMARY COOLANT SYSTEM AND PROVIDES ADDITIONAL DEFENSE AGAINST ANY UNCONTROLLED RELEASE OF RADIOACTIVITY TO THE ENVIRONMENT.

ALL THESE BARRIERS COMBINE TO PROTECT THE PUBLIC AND THE ENVIRONMENT FROM AN UNCONTROLLED DISCHARGE OF RADI0 ACTIVITY AND HIGH LEVELS OF RADIATION.

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PEACTOR SAFETY h NUCLEAR POWER PLANTS ARE INHERENTLY SAFE, NOT ONLY BY THE LAWS OF PHYSICS, BUT BY DESIGN. hUCLEAR POWER PLANTS CANNOT EXPLODE LIKE A BOMB BECAUSE THE CONCENTRATION OF FISSIONABLE MATERIAL IS FAR LESS THAN IS NECESSARY FOR SUCH A NUCLEAR EXPLOS!ON, JUST AS THE BATTERY OF A FLASHLIGHT PROVIDES EN0 UGH ENERGY TO PRODUCE LIGHT, BUT THE AMOUNT OF ENERGY IS FAR BELOW THE AMOUNT NEEDED TO ELECTROCUTE A PERSON. MANY SAFETY FEATURES WITH SEVERAL BACKUP SYSTEMS ARE PROVIDED TO ASSURE THAT ANY POSSIBLE ACCIDENT WOULD BE PREVENT D FROM CAUSING A SERIOUS HEALTH OR SAFETY THREAT TO THE PUBLIC.

THE DAVIS-BESSE REACTOR, LIKE ALL U.S. NUCLEAR UNITS, HAS MANY OVERLAPPING SAFETY FEATURES, CALLED REDUNDANT DEVICES.

IF ONE SYSTEM SHOULD FAIL, THERE WOULD STILL BE BACK-UP SYSTEMS TO ASSURE THE SAFETY OF THE PLANT.

DURING NORMAL OPERATION, THE REACTOR CONTROL SYSTEM REGU-LATES THE POWER OUTPUT BY ADJUSTING THE POSITION OF THE CONTROL RODS WHICH ABSORB NEUTRONS. IN THE EVENT OF AN UNUSUAL OCCURRENCE, THE REACTOR IS AUTOMATICALLY SHUT DOWN BY A SEPARATE REACTOR PROTECTION SYSTEM THAT CAUSES l'.L THE CONTROL RODS TO BE QUICKLY INSERTED INTO THE REACTOR ORE, lll STOPPING ALL CHAIN REACTIONS. THE CONTROL ROOM IS LOCATED AWAY FROM THE REACTOR AND WOULD BE SAFE TO OCCUPY DURING MOST ACCIDENTS CONCE!VABLE.

TO GUARD AGAINST THE POSSIBILITY OF A LOSS OF REACTOR COOLING WATER, THE REACTOR SYSTEM IS EQUIPPED WITH AN EMERGENCY CORE COOLING SYSTEM DESIGNED TO PUMP RESERVE WATER INTO THE REACTOR AUTOMATICALLY IF THE REACTOR COOLANT PRESSURE DROPS BELOW A PREDETERMINED LEVEL.

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iJ m DESCRIPTION OF THE DAVIS-BESSE NUCLEAR POWER STATION SITE THE DAVIS-BESSE SITE IS LOCATED IN CARROLL TOWNSHIP OF OTTAWA COUNTY, OHto. IT IS ON THE SOUTHWESTERN SHORE OF LAKE ERIE JUST NORTH OF THE MOUTH OF THE TOUSSAINT RIVER.

THE SITE LIES NORTH AND EAST OF OHIO STATE ROUTE 2, APPROXI-MATELY 10 MILES NW OF PORT CLINTON, 7 MILES N OF OAK HARBOR, AND 25 MILES E OF TOLEDO, OHIO.

THISSECTIONOFOHIO'ISFLATANDMARSHY,$;THMAXIMUM ELEVATIONS OF ONLY A FEW FEET AB0VE LAKE LEVEL. THE AREA WAS ORIGINALLY SWAMP FOREST AND MARSHLAND, RICH IN WILDLIFE BUT USELESS FOR SETTLING AND FARMING. DURING THE NINETEENTH CENTURY, THE LAND WAS CLEARED AND DRAINED, AND HAS BEEN FARMED SUCCESSFULLY SINCE. TODAY,' THE TERRAIN CONSISTS OF FARMLAND WITH MARSHES EXTENDING IN SOME PLACES FOR UP TO 2 MILES INLAND FROM THE SANDUSKY LAKE SHORE RIDGE.

MORE THAN HALF THE DAVIS-BESSE SITE AREA IS MARSHLAND; THE FARMLAND PORTION OF THE SITE IS MARGINAL. THE MARSHES ARE PART OF A VALUABLE ECOLOGICAL RESOURCE, PROVIDING A BREEDING

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GROUND FOR A VARIETY OF WILDLIFE AND A REFUGE FOR MIGRATORY BIRDS. MAJOR SPECIES OF BIRDS USING THIS PORTION OF THE LAKE ERIE MARSHES INCLUDE MALLARDS, BLACK DUCKS, WIGEON, SNOWY EGRETS, GREAT BLUE HERONS, BLUE-WINGED TEAL AND CANADA GEESE. IN FACT, THERE ARE THOUSANDS OF GEESE LIVING RIGHT ON THE SITE. WORKERS AND VISITORS HAVE TO WADE THROUGH THEM TO MOVE AROUND THE SITE. BALD EAGLES, OSPREYS, SWANS, GREAT HORNED OWLS, AND A LARGE NUMBER OF HAWKS ARE OFTEN SEEN IN THE AREA.

THE SITE INCLUDES A TRACT KNOWN AS NAVARRE MARSH, WHICH WAS ACQUIRED FROM THE U.S. BUREAU OF SPORT FISHERIES AND WILD-LIFE, DEPARTMENT OF THE INTERIOR. IN 1971, TOLEDO EDISON PURCHASED THE 188 ACRE TOUSSAINT RIVER MARSH. THE TOUSSAINT river MARSH IS CONTIGUOUS WITH THE 610-ACRE NAVARRE MARSH UNIT OF THE OTTAWA NATIONAL WILDLIFE REFUGE.

MOST OF THE REMAINING MARSH HAS BEEN MAINTAINED BY PRIVATE HUNTING CLUBS, THE U.S. FISH AND WILDLIFE SERVICE, AND THE OHIO DEPARTMENT OF NATURAL RESOURCES, DIVISION OF WILDLIFE.

THERE ARE SOME RESIDENCES ALONG THE LAKESHORE USED MAINLY AS SUMMER HOUSES. HOWEVER, THE MAJOR RES0RT AREA 0F THE COUNTY g-'S IS FARTHER EAST, AROUND PORT CLINTON, SANDUSKY, AND THE V GROUP OF ISLANDS KNOWN AS PUT-IN-BAY.

THE IMMEDIATE AREA NEAR DAVIS-BESSE IS SPARSELY POPULATED; OTTAWA COUNTY HAD A POPULATION OF ONLY 40,076 IN A 1980 CENSUS. THE NEAREST INCORPORATED COMMUNITIES ARE:

PORT CLINTON - 10 MILES SE, POPULATION 7,223 0AK HARBOR - 7 MILES S, POPULATION 2,678 ROCKY RIDGE - 7 MILES WSW, POPULATION 457 THESE POPULATIONS ARE AGAIN FROM THE MOST RECENT, 1980, CENSUS. TOLEDO IS THE NEAREST MAJOR CITY,.ABOUT 25 MILES W 0F DAVIS-BESSE, AND HAS A POPULATION OF ABOUT 354,650.

THE NON-MARSH AREAS AROUND THE DAVIS-BESSE SITE ARE USED 1 PRIMARILY FOR FARMING. THE MAJOR CR0PS INCLUDE SOYBEANS, WHEAT, 0ATS, HAY, FRUIT AND VEGETABLES. LIVESTOCK RAISING AND DAIRY FARMS ARE NOT MAJOR ACTIVITIES.

THE MAIN INDUSTRIES WITHIN 5 MILES OF THE SITE ARE LOCATED IN ERIE INDUSTRIAL PARK, ABOUT 4 MILES SE OF THE SITE. THEY INCLUDE COMPANIES SUCH AS UNIR0YAL AND USCO DISTRIBUTION SERVICES.

THE STATE OF OHIO, DEPARTMENT OF NATURAL RESOURCES OPERATES MANY WILDLIFE AND RECREATIONAL AREAS WITHIN 10 MILES OF THE lll SITE. THESE INCLUDE MAGEE MARSH, TURTLE CREEK, CRANE CREEK STATE PARK, AND THE OTTAWA NATIONAL WILDLIFE REFUGE. MAGEE MARSH AND TURTLE CREEK LIE BETWEEN 3 AND 6 MILES NW OF THE SITE. MAGEE MARSH IS A WILDLIFE PRESERVE WITH THE PUBLIC BEING ADMITTED FOR FISHING, NATURE STUDY, AND CONTROLLED HUNTING IN SEASON. TURTLE CREEK, A WOODED AREA AT THE SOUTHERN END OF MAGEE MARSH, OFFERS BOATING AND FISHING.

CRANE CREEK STATE PARK IS ADJACENT TO MAGEE MARSH AND IS A POPULAR PICNICKING, SWIMMING, AND FISHING AREA. THE OTTAWA NATIONAL WILDLIFE REFUGE LIES 4 TO 9 MILES WNW OF THE SITE, IMMEDIATELY WEST OF MAGEE MARSH. DARBY MARSH AND THE UNUSED PORTIONS OF NAVARRE MARSH AT THE SITE ARE MANAGED AS UNITS OF THIS NATIONAL REFUGE.

THE RADIOLOGICAL CHARACTERISTICS OF THE AREA SURROUNDING DAVIS-BESSE ARE NOT UNUSUAL. NATURAL AND MAN-MADE BACK-GROUND RADIATION LEVELS IN THE AREA ARE TYPICAL FOR MIDWEST-ERN STATES. RADIOLOGICAL MONITORING STATIONS HAVE BEEN ACTIVE IN THE AREA SINCE 1960, SO THAT A CONSIDERABLE BACKGROUND OF DATA IS AVAILABLE. THESE STATIONS HAVE O

MONITORED NOT ONLY LAKE ERIE, BUT ALSO SURFACE, GROUND, AND

TAP WATER IN THE AREA, AS WELL AS MILK,. DIETARY AND ATMOSPHERIC CONCENTRATIONS. THROUGH COMPARISON WITH THIS EXTENSIVE BACKGROUND DATA, THE CHANGE IN RADIATION LEVELS DUE TO THE OPERATION OF DAVIS-BESSE HAS BEEN SHOWN TO BE MINIMAL, FIGURES 2 AND 3 SHOW DAVIS-BESSE NUCLEAR POWER STATION AND THE SAMPLING LOCATIONS OF THE RADIOLOGICAL ENVIRONMENTAL 4 MONITORING PROGRAM IN THE VICINITY. DESCRIPTIONS OF THE SAMPLING LOCATIONS MAY BE FOUND'0N TABLE 1. THERE ARE TWO TYPES OF SAMPLING LOCATIONS, INDICATOR AND CONTROL. INDICA-TOR LOCATIONS ARE THOSE WHICH ARE EXPECTED TO SHOW THE EFFECTS (IF ANY) 0F THE PLANT OPERATION. GENERALLY, THEY ARE WITHIN FIVE (5) MILES OF THE PLANT AND LOCATED WHERE THE HIGHEST EXPOSURES ARE PREDICTED TO OCCUR. CONTROL LOCATIONS ARE SELECTED SO AS NOT TO BE INFLUENCED BY ANY PLANT OPERA-TION. TYPICALLY, THEY ARE LOCATED AT FIVE (5) MILES OR MORE FROM THE PLANT.

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O' TABLE 1 SAMPLING LOCATIONS, DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 TYPE OF CODE LOCATION' LOCATION DESCRIPTION T-1 I SITE BOUNDARY, 0.6 MILES NE OF STATION, NEAR INTAKE CANAL.

T-2 i SITE BOUNDARY, 0.9 MILES E OF STATION.

T-3 i SITE BOUNDARY, 1.4 MILES SE OF STATION, NEAR TOUSSAINT RIVER AND STORM DRAIN.

T-4 i SITE BOUNDARY, 0.8 MILES S OF STATION, NEAR LOCUST POINT AND TOUSSAINT RIVER.

T-5 I MAIN ENTRANCE TO SITE, 0.5 MILES W OF STATION.

(3 k- > T-7 I SAND BEACH, 0.9 MILES NNW OF STATION.

T-8 I EARL MOORE FARM, 2.7 MILES WSW OF STATION.

T-9 C OAK HARBOR, 6.8 MILES SW OF STATION.

T-11 C PORT CLINTON, 9.5 MILES SE OF STATION.

T-12 C TOLEDO WATER IREATMENT STATION, AIRBORNE PARTICULATE AND IODINE COLLECTED 23.5 MILES WNW OF STAT!0H AND WATER SAMPLES TAKEN FROM INTAKE CRIB 11.25 MILES NW OF STATION.

T-17 I IRv FICK'S WELL ONSITE, 0.7 MILES SW OF STATION.

T-20 1 GAETH FARM, 5.5 MILES WSW OF STATION.

I = INDICATOR LOCATIONSJ C = CONTROL LOCATIONS O

TABLE 1 h SAMPLING LOCATIONS, DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO 1 (CONTINUED)

TYPE OF CODE LOCATION

LOCATION DESCRIPTION T-23 C PUT-IN-BAY LIGHTHOUSE, 14.3 MILES ENE OF STATION, T-24 C SANDUSKY, 24,9 MILES SE OF STATION, T-25 I MILLER FARM, 3.7 MILES S OF STATION.

T-27 C MAGEE MARSH, 5.3 MILES WNW OF STATION.

T-28 I UNIT 1 TREATED AND UNTREATED WATER SUPPLY, ONSITE.

T-29 I LAKE ERIE, INTAKE AREA, 1.5 MILES NE OF STATION. g T-30 i LAKE ERIE, DISCHARGE AREA, 0.9 MILES ENE OF STATION.

T-31 i ONSITE.

T-32 I LAND. WITHIN 5 MILES RADIUS OF STATION.

T-33 i LAKE ERIE, WITHIN 5 MILES RADIUS OF SITE.

T-34 C LAND, GREATER THAN 10 MILES RADIUS OF SITE.

T-35 C LAKE ERIE, GREATER THAN 10 MILES RADIUS OF SITE.

T-36 I THE PRIVATE GARDEN OR FARM HAVING THE HIGHEST X/0.**

I = INDICATOR LOCATIONSI C = CONTROL LOCATIONS

- X/0 = RELATIVE ATMOSPHERIC DISPERSION (L KEllH00D OF WINDS CARRYING RADI0 ACTIVITY TO AN AREA) 9 1

() TABLE 1 SAMPLING LOCATIONS, DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 (CONTINUED)

TYPE OF CODE LOCATION

LOCATION DESCRIPTION T-37 C THE FARM 10 TO 20 MILES FROM THE SITE IN THE LEAST PREVALENT WIND DIRECTION.

T-38 i SITE BOUNDARY, 0.6 ENE OF STATION NEAR LAKE.

T-39 I SITE BOUNDARY, 1.2 MILES ESE OF STATION NEAR DITCH TO TOUSSAINT.

T-40 1 SITE BOUNDARY, 0.7 MILES SE OF STATION NEAR DITCH TO TOUSSAINT.

T-41 1 SITE BOUNDARY 0.6 MILES SSE OF STATION NEAR O DITCH TO TOUSSAINT.

T-42 I SITE BOUNDARY, 0.8 MILES SSW OF STATION BY ECC.

T-43 i SITE BOUNDARY, 0.5 MILES SW OF STATION ALONG ROUTE 2 FENCE.

T-44 i SITE BOUNDARY, 0.5 MILES W OF STATION BY RAILROAD TRACKS.

T-45 i SITE BOUNDARY, 0.5 MILES WNW OF STATION ON ACCESS ROAD BEHIND COOLING TOWER.

T-46 I SITE BOUNDARY, 0.5 MILES NW OF STATION ALONG ACCESS ROAD.

T-47 i SITE BOUNDARY, 0.5 MILES N OF STATION ALONG ACCESS ROAD BY GATE.

I

INDICATOR LOCATIONSI C = CONTROL LOCATIONS TABLE 1 SAMPLING LOCATIONS, DAVIS-BESSE NUCLEAR POWER l STATION, UNIT NO. 1 (CONTINUED) l TYPE OF CODE LOCATION

LOCATION DESCRIPTION l

T-48 i SITE BOUNDARY, 0.5 MILES NNE OF STATION BY !

LAKE.

T-49 I SITE BOUNDARY, 0.5 MILES NE OF STATION ALONG ACCESS ROAD BY LAKE.

l T-50 I ERIE INDUSTRIAL PARK, 4.5 MILES ESE OF l STATION BY WATER TOWER.

T-51 1 DAUP FARM, 600 TETTAU ROAD, PORT CLINTON, OHIO, 4.5 MILtiS SSE OF THE STATION.

T-52 T-53 1

I MILLER FARn, 3.7 MIL ES S OF SITE ON WEST CAMP .'ERRY WESTERN ROAD.

NIXON FARM, 4.5 MILES SSE OF SITE ON WEST hl '

CAMP PERRY WESTERN ROAD.

T-54 I M. BE!ER FARM, 4.8 MILES WSW 0F SITE ON GENZMAN ROAD.

T-55 i KING FARM, 5 MILES WEST OF SITE ON ROUTE 2.

I = INDICATOR LOCATIONS; C = CONTROL LOCATIONS O

() 1986 RADI0 ACTIVE LIQUID AND GASE0US EFFLUENTS

SUMMARY

SOURCES THROUGH THE NORMAL OPERATIONS OF A NUCLEAR POWER PLANT, MOST OF THE FISSION PRODUCTS ARE RETAINED BY THE BARRIERS OF THE FUEL AND FUEL CLADDING. HOWEVER, THESE BARRIERS ARE NOT DESIGNED TO PREVENT SMALL AMOUNTS OF RADI0 ACTIVE FISSION PRODUCTS FROM MIGRATING INTO THE PRIMARY COOLANT (GREEN ON FIGURE 1). ADDITIONALLY, TRACE AMOUNTS OF THE COMPONENT AND STRUCTURE SURFACES, WHICH HAVE BEEN ACTIVATED, ALSO GET INTO THE PRIMARY COOLANT WATER. MANY OF THESE PARTICLES ARE REMOVED THROUGH DEMINERALIZERS IN A PURIFICATION SYSTEM FOR THE PRIMARY COOLANT.

SMALL RELEASES OF RADI0 ACTIVE LIQUIDS MAY OCCUR FROM VALVES, PIPING OR EQUIPMENT ASSOCIATED WITH THE PRIMARY COOLANT SYSTEM. THESE LIQUIDS ARE COLLECTED THROUGH A SERIES OF FLOOR AND EQUIPMENT DRAINS AND SUMPS, ALL LIQUIDS OF THIS NATURE ARE PURIFIED AND CAREFULLY MONITORED PRIOR TO RELEASE.

THE NOBLE GAS FISSION PRODUCTS, WHICH ARE NOT VERY SOLUBLE

() IN THE PRIMARY COOLANT AND CANNOT BE REMOVED BY DEMIN2RAL-IZERS, ARE GIVEN OFF AS A GAS WHEN THE PRIMARY COOLANT IS DEPRESSURIZED. THESE GASSES ARE THEN COLLECTED BY A SYSTEM DESIGNED FOR GAS COLLECTION AND STORAGE. PROCESSING AND MONITORING THE WASTE TREATMENT SYSTEMS AT DAVIS-BESSE ARE DESIGNED TO COLLECT AND PROCESS THE LIQUID AND GASEOUS WASTES WHICH CONTAIN RADI0 ACTIVE MATERIAL. THE PLANT'S RADI0 ACTIVE WASTE SYSTEMS PROVIDE FOR THE STORAGE, CLEAN UP, AND RECYCLING OF LIQUID AND GASEOUS WASTES. FOR EXAMPLE, THE WASTE GAS DECAY TANKS ARE HOLDING TANKS WHICH ALLOW RADIOACTIVITY IN GAS TO DECAY PRIOR TO RELEASE TO THE STATION VENT. WASTES ARE SAMPLED AT THE END OF THE TREATMENT SYSTEM AND ARE RECIRCU-LATED FOR ADDITIONAL PROCESSING IF REQUIRED. IN-PLANT MONITORING SYSTEMS ARE USED TO ENSURE ANY RADI0AC-TIVE MATERIAL RELEASED IS BELOW THE APPROPRIATE REGULATORY LIMIT. INSTRUMENTS MONITOR AND RECORD THE RADIATION LEVELS OF ALL RELEASES. LIQu!D RADI0 ACTIVE-WASTE EFFLUENT LINE MONITORS PROVIDE ALARMS AND AUTOMATIC STOPPING OF RELEASES PRIOR TO " LEASING LIQUIDS WHICH EXCEED THE REGULATORY LIMITS. dELEASES FROM THE WASTE GAS DECAY TANK AND CONTAIN-MENT PURGES ARE MONITORED BY THE STATION VENT MONITOR AND ARE ALSO CONTROLLED INDIVIDUALLY TO PROVIDE ADDITIONAL ASSURANCE THAT RELEASES ARE NOT EXCEEDING THE LIMITS. FOR BOTH LIQUID AND GASEOUS RELEASES, IF THE RADIATION LEVELS INCREASE AB0VE A SET LEVEL, ALARMS AND CONTROL VALVES WILL AUTOMATICALLY ACTIVATE. ALSO, AS A PRECAUTION AGAINST UNEXPECTED ACCUMULATION OF RADI0 ACTIVITY IN THE ENVIRONMENT, AN EXTENSIVE PROGRAM FOR MONITORING THE PLANT ENVIRONS HAS BEEN ESTABLISHED. THE ENVIRONMENTAL MONITORING OF EFFLUENTS INCLUDES: e OPERATION OF GAS AND LIQUID PROCESSING SYSTEMS. e INSTALLATION AND OPERATION OF IN-PLANT RADIATION MONITORING SYSTEM. e ESTABLISHMENT OF AN IN-PLANT AND OFF-SITE ENVIRON MENTAL SAMPLING AND ANALYSIS PROGRAM. e ESTABLISHMENT OF A QUALITY ASSURANCE PROGRAM, O INCLUDING PROCEDURAL CONTROLS. e CALCULATION OF DOSES TO THE PUBLIC. LIMITS THE U.S. NUCLEAR REGULATORY COMMISSION (NRC) REQUIRES NUCLEAR POWER PLANTS TO BE DESIGNED, CONSTRUCTED AND OPERAT-ED TO KEEP THE LEVELS OF RADI0 ACTIVE MATERIAL IN EFFLUENT RELEASES TO UNRESTRICTED AREAS AS LOW AS REASONABLY ACHIEV-ABLE OR ALARA. TO ASSURE THESE CRITERIA ARE MET, EACH LICENSE AUTHORIZING NUCLEAR REACTOR OPERATION INCLUDES TECHNICAL SPECIFICATIONS GOVERNING THE RELEASE OF RADI0AC-TIVE EFFLUENTS (10 CFR 50, APPENDIX I). THE TECHNICAL SPECIFICATIONS SPECIFY THE LIMITS FOR THE RELEASE OF RADIO-ACTIVE EFFLUENTS, AS WELL AS THE LIMITS FOR DOSES TO THE GENERAL PUBLIC FROM THE RELEASE OF RADI0 ACTIVE LIQUID AND GASEOUS EFFLUENTS. THESE LIMITS ARE SET WELL BELOW THE NRC GUIDELINES, S0 KEEPING RELEASES WITHIN THESE OPERATING GUIDELINES IS A DEMONSTRATION THAT RADI0 ACTIVE EFFLUENTS ARE BEING MAINTAINED AS LOW AS IS REASONABLY ACHIEVABLE. ggi t (} THE DOSE TO A MEMBER OF THE GENERAL PUBLIC FROM RADI0 ACTIVE MATERIAL IN LIQUID EFFLUENTS RELEASED TO UNRESTRICTED AREAS IS LIMITED TO: e LESS THAN OR EQUAL TO 3 MREMS PER YEAR TO THE TOTAL BODY.

                                                                                    - AND -

e LESS THAN OR EQUAL TO 10 MREMS PER YEAR TO ANY ORGAN. i THE AIR DOSE DUE TO RELEASE OF NOBLE GASES IN GASEOUS EFFLUENTS IS RESTRICTED TO: e LESS THAN OR EQUAL TO 10 MRADS PER YEAR FOR GAMMA 1 RADIATION. i

                                                                                    - AND -       ,

e LESS THAN OR EQUAL TO 20 MRADS PER YEAR FOR BETA RADIATION. THE DOSE TO A MEMBER OF THE GENERAL PUBLIC FROM 10 DINE-131, ([]) TRITIUM, AND ALL PARTICULATE RADIONUCLIDES WITH A HALF-LIFE GREATER THAN 8 DAYS IN GASEOUS EFFLUENTS IS LIMITED TO: e LESS THAN OR EQUAL TO 15 MREM PER YEAR TO ANY ORGAN. THESE ALARA GUIDELINES ARE A FRACTION OF THE DOSE LIMITS ESTABLISHED BY THE ENVIRONMENTAL PROTECTION AGENCY (EPA). ! IN ITS ENVIRONMENTAL DOSE STANDARD OF 40 CFR 190, THE EPA ESTABLISHED DOSE LIMITS IN THE VICINITY OF A NUCLEAR POWER PLANT. THESE DOSE LIMITS ARE: , e LESS THAN OR EQUAL TO 25 MREMS PER YEAR TO THE TOTAL BODY e LESS THAN OR EQUAL TO 75 MREMS PER YEAR TO THE 4 THYROID AND l e LESS THAN OR EQUAL TO 25 MREMS PER YEAR TO ANY OTHER ORGAN. O 1

e, . l ~;- ' RESULTS THE RESULTS OF THE LIQUID AND GASEOUS EFFLUENT MONITORING PROGRAM ARE REPORTED SEMIANNUALLY TO THE NRC. TABLE 2 PRESENTS A COMPARISON OF THE DOSES FROM THE 1986 RADI0 ACTIVE EFFLUENT RELEASES AND THE REGULATORY LIMITS. RADIOACTIVE LIQUID AND GASEOUS RELEASES AT DAVIS-BESSE HAVE NEVER EXCEEDED ANY FEDERAL REGULATORY OR TECHNICAL SPECIFI-CATION LIMITS. THE RESULTS OF THE LIQUID AND GASEOUS DISCHARGES AT DAVIS-BESSE FOR 1986 ARE LISTED ON TABLE 2.

          .THESE RESULTS SHOW THAT RADIOACTIVE EFFLUENTS RELEASED FROM
         ' DAVIS-BESSE ARE MAINTAINED AT LEVELS FAR BELOW THE REGULATORY LIMITS FOR DOSES TO THE GENERAL PUBLIC AND EVEN A    '

LOWER FRACTION OF THE EPA DOSE LIMITS. e O 1 m TABLE 2 1986 RADI0 ACTIVE EFFLUENT RELEASES LIQUID EFFLUENTS 1986 NRC PERCENT OF EPA PERCENT OF TYPE DOSE LIMIT NRC LIMIT LIMIT EPA LIMIT (MREM /YR) (MREM /YR) (MREM /YR) TOTAL BODY 0.066 3 2.2% 25 0.26% ANY ORGAN 0.098 10 O.98% 25 0.39% GASEOUS EFFLUENTS 1986 NRC PERCENT OF EPA PERCENT OF TYPE DOSE LIMIT NRC LIMIT LIMIT EPA LIMIT (MREM /YR) (MREM /YR) (MREM /YR) O NOBLE GAS 0.00000007 .10 0.0000007% 25 0.0000003% (GAMMA) NOBLE GAS 0.00000012 20 0.0000006% 25 0.0000005% (BETA) I-131, 0.006 15 0.0f4% 75 0.008% TRITIUM AND (ANY ORGAN) (THYROID) PARTICULATE RADIONUCLIDES

    -WITH HALF-LIVES
    -GREATER THAN 8 DAYS, O

r'

l ASSESSMENT OF RADIOLOGICAL EXPOSURE PATHWAYS h RADIOLOGICAL EXPOSURE PATHWAYS ARE THE METHODS BY WHICH PEOPLE MAY BECOME EXPOSED TO RADIONUCLIDES RELEASED FROM NUCLEAR FACILITIES. THE MAJOR PATHWAYS OF CONCERN ARE THOSE WHICH COULD CAUSE AN APPRECIABLE RADIATION DOSE. THE MAJOR PATHWAYS ARE DETERMINED BASED UPON THE TYPE AND AMOUNT OF RADI0 ACTIVITY RELEASED, THE ENVIRONMENTAL TRANSPORT MECHA-NISM, AND OUR USE OF THE ENVIRONMENT. THE TYPE AND AMOUNT OF RADIOACTIVITY RELEASED IS CAREFULLY MEASURED AT DAVIS-BESSE. THESE MEASUREMENTS INCLUDE ANALYSIS OF THE PHYSICAL AND CHEMICAL NATURE OF THE RADIONUCLIDES AND ARE USED TO DETERMINE HOW THE RADIONUCLIDES WILL INTERACT WITH THE ENVIRONMENT. THE ENVIRONMENTAL TRANSPORT MECHANISM INCLUDES CONSIDERATION OF PHYSICAL FACTORS, SUCH AS THE HYDROLOGICAL (WATER) AND METEOROLOGICAL (WEATHER) CHARACTERISTICS OF THE AREA. THIS PROVIDES INFORMATION ON THE WATER FLOW, WIND SPEED AND WIND DIRECTION AT THE TIME OF THE RELEASE WHICH IS USED TO EVALUATE HOW THE RADIONUCLIDES WILL BE DISTRIBUTED IN THE AREA. THE MOST IMPORTANT FACTOR IN EVALUATING THE EXPOSURE PATHWAYS IS THE USE OF THE ENVIRONMENT, MANY FACTORS ARE CONSIDERED SUCH AS DIETARY INTAKE OF RESIDENTS IN THE AREA, RECREATIONAL USE OF THE AREA, AND THE LOCATION lh OF HOMES. THE ENVIRONMENTAL PATHWAYS CONSIDERED ARE SHOWN IN FIGURE 4. THE RADI0 ACTIVE GASEOUS EFFLUENT EXPOSURE PATHWAYS INCLUDE PLUME EXPOSURE, INHALATION, MILK CONSUMPTION, MEAT CONSUMP-TION, AND DEPOSITION CN THE SOIL, CROPS, ANIMALS AND ANIMAL FEED. THE RADIOACTIVE LIQUID EFFLUENT EXPOSURE PATHWAYS INCLUDE DRINKING WATER, FISH CONSUMPTION AND DIRECT EXPOSURE FROM THE LAKE. ENVIRONMENTAL SAMPLES ARE COLLECTED AND ANALYZED IN ORDER TO ASSESS THE IMPACT OF THE OPERATION OF DAVIS-BESSE ON THE ENVIRONMENT AND TO ASSESS THE DISPERSION AND ACCUMULATION OF RADIONUCLIDES FROM GASEOUS AND LIQUID EFFLUENT RELEASES. THE RESULTS OF ANALYSES OF SAMPLES COLLECTED IN 1986 SHOW THAT THE OPERATION OF DAVIS-BESSE HAD NO SIGNIFICANT OR MEASURABLE EFFECT ON THE QUALITY OF THE ENVIRONMENT AND THAT ALL RADIOACTIVITY RELEASED IN THE STATION'S EFFLUENTS WAS WELL BELOW THE REGULATORY LIMITS. 9 FIGURE 4 (m Diluted By Atmosphere Airborne Releases N Plume . Animals Exposure . . . . (Milk, Meat) 3; g..3

                                  .                                                                  Y:         I I
                      '                  Consumed By Man
                                                                $                                           !Uj j{ ~,

l'j b qj _ h Liquid Releases 5 a Consumed gI Diluted By Lake By Animals a ( g { _:ap y _s y g % y E_ "_1 9. Bilk

                                                                            $           Consumed i1                                  . M                        By Man Vegetation pe,                          Ma                                                                              FISH

(-] [' E / rom Soj'i . g A# 'N . Drinking r j' ,' .

    ~
            ~ .:;,. - ;-cW!         @                                 Shoreline Exposure ,

p. e \v LAKE

W -

                      .. T y            a.                                    \
                                      -t QQt.. .    .
                           ~.

Environmental Exposure Pathways Of Man Due To Releases Of Radioactive Material To The Atmosphere And Lake. O v

p) (__ TO CONFIRM THE RESULTS OF THE ENVIRONMENTAL SAMPLING PRO-GRAM, CALCULATIONS ARE ALSO PERFORMED TO ESTIMATE THE RADIATION EXPOSURE OF THE GENERAL PUBLIC. DcSE CALCULATIONS ARE BASED ON A VERY CONSERVATIVE (OVER ESTIMATED) MODEL. THE INTERNATIONAL COUNCIL ON RADIATION PROTECTION AND MEASUREMENTS (ICRP) HAS DEVELOPED GUIDELINES FOR THE CALCU-LATION OF RADIATION DOSES. THESE GUIDELINES MAKE USE OF A

     " STANDARD MAN" AND MAXIMUM USE FACTORS FOR THE ENVIRONMENT.

THE USE OF THESE GUIDELINES RESULTS IN A VERY CONSERVATIVE ESTIMATE (OVER ESTIMATION) 0F THE ENVIRONMENTAL DOSE TO PEOPLE. THE TYPE AND AMOUNT OF RADI0 ACTIVITY RELEASED FROM DAVIS-BESSE IS CALCULATED USING MEASUREMENTS FROM INSTALLED PLANT EFFLUENT MONITORS AND EFFLUENT SAMPLE ANALYSES. THESE CALCULATIONS AND MEASUREMENTS ARE USED WITH METEOROLOGICAL DATA TO DETERMINE THE DISTRIBUTION OF THE RADIONUCLIDES AND TO CALCULATE THE DOSE TO THE GENERAL PUBLIC. BASED UPON CALCULATIONS P$RFORMED FOR 1986, THE LIQUID AND GASEOUS EFFLUENTS RELEASED FROM DAVIS-BESSE RESULTED IN A POPULATION DOSE OF 0.44 PERSON-REM, TOTAL BODY. THE SAME POPULATION WOULD RECEIVE ABOUT 488,000 PERSON-REMS EVERY [\

 '   YEAR DUE TO NORMAL BACKGROUND AND MEDICAL RADIATION.

DOSE LIMIT GUIDELINES WERE ESTABLISHED BY THE NRC FOR RELEASES OF RADI0 ACTIVE EFFLUENTS FROM NUCLEAR POWER PLANTS. THESE GUIDELINES ARE PRESENTED IN THE CODE OF FEDERAL REGULATIONS, SECTION 10, PART 50, APPENDIX I. THESE GUIDE-LINES ARE BASED ON THE PHILOSOPHY OF "AS LOW AS IS REASON-ABLY ACHIEVABLE" - ALARA. MAINTAINING RELEASES WITHIN THESE OPERATING GUIDELINES DEMONSTRATES THAT RADI0 ACTIVE EFFLUENTS ARE BEING MAINTAINED "AS LOW AS IS REASONABLY ACHIEVABLE." l AS MENTIONED IN THE PREVIOUS SECTION, THESE NRC ALARA GUIDELINES ARE ONLY A SMALL FRACTION OF THE DOSE LIMITS ESTABLISHED BY THE EPA. FIGURES 5 - 10 PRESENT A COMPARISON OF THE NRC GUIDELINES

     /.1D THE RESULTS OF MONITORING AT DAVIS-BESSE SINCE 1978.

ALL SIX GRAPHS SHOW THAT DAVIS-BESSE HAS MAINTAINED DOSES FAR BELOW THE APPLICABLE REGULATORY LIMITS SINCE IT BEGAN

, OPERATION. l 0

THE WORST CASES OCCURRED IN 1981 FOR DOSES DUE TO BOTH h GASEOUS AND LIQUID EFFLUENTS (FIGURES 8 AND 9). THE PEAK EXPOSURES IN 1981 WERE DUE TO MECHANICAL DAMAGE THAT Hl:;ULIED IN A PRIMARY TO SECONDARY LEAK IN THE MULTISTEAM SEPARATOR AND CAUSED AN INCREASE IN RADI0 ACTIVITY IN EFFLUENTS. BUT EVEN THEN, RELEASES WERE STILL MAINTAINED WELL BELOW THE NRC GUIDELINES AND THE EPA LIMITS WITH YEARLY DOSES LESS THAN 50% OF THE REGULATORY GUIDELINES. THE LEVELS OF RADI0 ACTIVITY RELEASED TO THE ENVIRONMENT IN LIQUID AND GASE0US EFFLUENTS IS VERY LOW. THE LEVELS ARE S0 LOW THAT IF A PERSON LIVED IN THE AREA 0F MAXIMUM CONCEN-TRATION, BREATHED THE EFFLUENTS, CONSUMED FOOD AND MILK FROM THIS MAXIMUM EXPOSURE AREA, DRANK WATER FROM THE LAKE, STOOD ON THE SHORELINE INFLUENCED BY THE PLANT DISCHARGE AND ATE FISH THAT LIVE IN THE PLANT DISCHARGE, A TOTAL DOSE OF ABOUT 0.072 MREM FOR THE WHOLE YEAR TO THE TOTAL BODY WOULD BE RECEIVED. THAT SAME PERSON WOULD RECEIVE ABOUT 220 MREM A YEAR FROM NATURAL BACKGROUND AND MEDICAL RADIATION. DAVIS-BESSE HAS NEVER EXCEEDED ANY OF THE REGULATORY GUIDE-LINES FOR RADIOACTIVE EFFLUENT RELEASES. AS FIGURES 5 - 10 SHOW THE YEARLY DOSE TO THE PUBLIC, DUE TO THE OPERATION OF DAVIS-BESSE, WAS MANY TIMES LOWER THAN THE APPLICABLE REGULATORY GUIDELINES. 9 FIGURE 5 Maximum Individual Eose O From Relenes of Noble Gass-Whole Body 110 HRC 00 DEUNE 100 Il C 0 U U U U U U U 90-80 - l 70 - E i i 60 - 3 0 o c 40-9 l 30 - 20 - 10 - DAVIS--DESSE 0- - l : : i

      -10              i     i            i      i        i        i     i      i 1977   1978 1979       1980      1981     1982     1983  1984   1985  1986 O                                                 Year

FIGmtE 6 - MaximuniIndividualEose , O n . o 0,,,, 110 NilC @DEIN 1004 0 0 0 0 0 0 0 0 0 90-80-

    !   70 -

5 i V 60-3 0 50 - c 40 - 1 0 l ? l 30 - 20 - 10 - DA & ESSE , , 0-

       -10         i      i     i       i       i        i    i    i 1977  1978   1979  1980    1981    1982     1983 1984 1985    1986 .

Year

FIGURE 7 Mi*"* I"di'id"'I G88* "* D 8' O H3, CIA ledu ami Pellaisle - Body 110 NRC EDOEE 100 0 0 0 0 0 0 0 0 0 l 90 - 80 - l 70 - 5 i i 60-3 0 0 c 40-e E l 30-20 - l 10 - , DAE BESSE 0 : i : !

           -10         i    i        i        i       i        i    i    i 1977 1978 1979     1980     1981    1982     1983 1984 1985 1986 O                                           Year l

1

FIGURE 8 - Maximum Individual Gaseous) Ewe O H3, C14,Isen ad Patmisis - Ogm l 110 t EC E DEIN 100 " C U U U U U U U U 90 - 80 - l 70 - 5 i 1 60-3 0 0 c 40 - e l 30 - 20 - 10 -

   #                                          '       I N,

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   -10            i    i         i      i       i      i        i      i 1977   1978 1979      1980   1981   1982     1983     1984 1985    1986 Year

FIGURE 9

 ,                            Maximum Individual liquid Ewe Whole Body Dose osial heepino.s mhi w-we 110                                                                                              .:

100;! O c c c c c c c 3 90-i 80 - l 70-s V 60-i 0 E-g C 40-e l 30- . I 20] 10 - DAYtS-BESSE 0' :

              -10           i                    ,       ,       ,       ,
                                                                                        ,         i 1977   1978                  1979    1980    1981    1982   1983  1984       1985       1986 O                                                              Year

FIGURE 10 O M'*"* I"di'id"'Hi'i"* Crfilcol Recephr:0.6 miles NW - Organ . 110 MIC E DEN 1004l C 0 0 0 0 0 :: 0 0 90 - 80 -

     !   70 -
    !i   60-3 0

0 j 40 - 2 l 30-20 - t 10 - DAEMSSE . p 0: --

        -10           i    i          i        i             i             i          i                       i 1977    1978 1979       1980     1981      1982              1983    1984                    1985     1986 O                                           Year

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                                                                                                                                                                                                                               - c MONITORING PROGRAM O

() RADIOLOGICAL ENVIRONMENTAL MONITORINS PROGRAM THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) AT ' DAVIS-BESSE WAS ESTABLISHED TO COMPLY WITH NRC REGULATIONS. THE NRC REQUIRES DAVIS-BESSE TO MONITOR THE PLANT ENVIRONS FOR RADI0 ACTIVITY WHICH MAY BE RELEASED AS A RESULT OF NORMAL OPERATIONS AND POSTULATED ACCIDENTS. THE OBJECTIVES OF DAVIS-BESSE'S RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ARE: e TO ASSESS PUBLIC EXPOSURE DUE TO THE OPERATION OF THE PLANT e TO EVALUATE THE AFFECT, IF ANY, OF THE PLANT ON IMPORTANT EXPOSURE PATHWAYS e TO IDENTIFY PHYSICAL AND BIOLOGICAL SITES OF RADI0AC-TIVE BUILDUP, IF ANY, IN'THE ENVIRONMENT AND RESULT-ING CHANGES IN BACKGROUND RADIATION LEVELS e TO VERIFY THE ADEQUACY OF IN-PLANT CONTROLS OF () RADIOACTIVE MATERIALS. BECAUSE OF THE MANY POTENTIAL PATHWAYS OF RADIATION EXPOSURE FROM BOTH NATURAL AND MAN-MADE SOURCES, THE LEVELS OF RADI0 ACTIVITY IN AN AREA (AND HOW THEY VARY) MUST BE DOCUMENTED. TO MEET THIS OBJECTIVE, AN EXTENSIVE PREOPERATIONAL RADIO-LOGICAL ENVIRONMENTAL MONITORING PROGRAM WAS INITIATED AT THE DAVIS-BESSE SITE IN 1972. THIS PROGRAM INCLUDED COLLEC-TION AND ANALYSES OF AIRBORNE PARTICULATES, AIRBORNE IODINE, GAMMA RADIATION, MILK, GROUND WATER, MEAT AND WILDLIFE, l FRUITS AND VEGETABLES, ANIMAL AND WILDLIFE FEED, S0ll, SURFACE WATER, FISH, AND BOTTOM SEDIMENTS. FOR APPROXIMATE-LY 5 YEARS BEFORE THE INITIAL OPERATION OF DAVIS-BESSE, MONITORING WAS CONDUCTED TO ACCUMULATE DATA ON THE BACK-GROUND RADIATION AND RADIOACTIVITY LEVELS AT THE DAVIS-BESSE SITE. SOME EXAMPLES OF BACKGROUND RADI0 ACTIVITY LEVELS ARE LISTED ON THE NEXT PAGE. O O l l

I BACKGROUND RADI0 ACTIVITY LEVELS O TYPE OF SAMPLE LEVEL OF ACTIVITY AIRBORNE PARTICULATE 0.1 PCI/M3 SURFACE WATER 4x10-9UCI GROSS BETA /ML DRINKING WATER 3x10-9UCI GROSS BETA /ML AMBIENT RADIATION 8-22 MR/QTR. FISH 2x10-6UCI GROSS BETA / GRAM-WET THE DATA COLLECTED PRIOR TO THE OPERATION OF DAVIS-BESSE PROVIDES AN EXTENSIVE BACKGROUND OF INFORMATION WHICH CAN BE USED TO EVALUATE ANY INCREASES IN THE RADIATION AND RADI0AC-T!VITY LEVELS IN THE ENVIRONMENT WHICH MAY OCCUR WHILE THE PLANT IS OPERATING. FUEL ELEMENTS WERE LOADED IN THE PLANT ON 23 THROUGH 27 O APRIL, 1977 AND INITIAL CRITICALITY WAS ACHIEVED ON AUGUST 12, 1977. APPROXIMATELY 91 YEARS OF OPERATIONAL MONITORING WAS COMPLETED BY THE END OF DECEMBER, 1986. THE OPERATIONAL RADIOLOGICAL MONITORING RROGRAM IS SIMILAR TO THE PREOPERATIONAL PROGRAM. SAMPLING INCLUDES THE COLLECTION AND ANALYSES OF AIRBORNE PARTICULATES, AIRBORNE IODINE, DIRECT RADIATION, TREATED AND UNTREATED SURFACE WATER, GROUND (WELL) WATER, FISH, GREEN LEAFY VEGETABLES, MILK, SOIL SAMPLES, LAKE BOTTOM SEDIMENTS, MEAT AND WILD-LIFE, AND ANIMAL AND WILDLIFE FEED. THE SELECTION OF SAMPLING LOCATIONS WAS BASED UPON METEORO-LOGICAL DATA, INDICATING THE PREVAILING WIND DIRECTION IN THE AREA, HYDROLOGICAL DATA, AND THE LOCATIONS OF THE MAIN INTAKES OF WATER FROM LAKE ERIE WHICH ARE USED BY THE NEARBY POPULATION, THE SELECTION OF SAMPLING LOCATIONS WAS ALSO BASED ON THE ANALYSIS OF PATHWAYS IN THE ENVIRONMENT. SINCE THE SITE IS LOCATED IN AN AGRICULTURAL REGION, MILK AND FOOD CROPS FROM THE AREA ARE ALSO SAMPLED. SAMPLING INCLUDES O l INDICATOR AND CONTROL LOCATIONS. INDICATOR LOCATIONS ARE

!                                THOSE WHICH ARE EXPECTED TO SHOW THE EFFECTS OF THE PLANT j                                 OPERATION.                                     GENERALLY, THEY ARE WITHIN 5 MILES OF THE PLANT AND ARE LOCATED WHERE THE HIGHEST EXPOSURES ARE PREDICTED TO

OCCUR. CONTROL LOCATIONS ARE SELECTED SO AS NOT TO BE INFLUENCED BY ANY PLANT OPERATION. TYPICALLY, THEY ARE LOCATED AT 5 MILES OR MORE FROM THE PLANT. A COMPARISON OF THE RESULTS OF CONTROL AND INDICATOR SAMPLES ALLOWS FOR THE
EVALUATION.0F THE SAMPLES WHILE TAKING INTO ACCOUNT NORMALLY OCCURRING BACKGROUND LEVELS AND FLUCTUATIONS DUE TO EVENTS 4 SUCH AS COSMIC RADIATION AND NUCLEAR FALLOUT FROM WEAPONS i TESTING. FIGURES 2 AND 3 SHOW THE SAMPLING LOCATIONS.

j- TABLE 1 LISTS AND DESCRIBES ALL SAMPLE LOCATIONS. THE SAMPLING FREQUENCY FOR THE VARIOUS MEDIA WAS CHOSEN i BASED UPON THE RADIONUCLIDES, THEIR HALF-LIVES, AND THEIR ) BEHAVIOR IN THE BIOLOGICAL AND PHYSICAL SYSTEM. 10 DINE-131, 2 FOR EXAMPLE, HAS A SHORT HALF-LIFE (8 DAYS). BECAUSE OF t THIS SHORT HALF-LIFE, THE SAMPLING FREQUENCY OF MILK IS i INCREASED FROM MONTHLY TO TWICE A MONTH DURING THE SUMMER I GRAZING MONTHS. HOWEVER, SINCE IODINE -131 IS ALSO SAMPLED 1 IN THE AIR ON A WEEKLY SCHEDULE AT 11 LOCATIONS AROUND THE i SITE, IF THERE WAS A SIGNIFICANT RELEASE OF IODINE FROM THE ! STATION OR ANY OTHER NUCLEAR STATION OR FROM AN ATMOSPHERIC WEAPONS TEST, 10 DINE-131 WOULD BE DETECTED. ! TABLE 3 PROVIDES A LIST OF SAMPLING LOCATIONS, TYPE OF LOCATION, TYPE OF SAMPLE, AND COLLECTION FREQUENCY. TABLE l 4 EXPLAINS THE CODES USED IN TABLE 3. ALL SAMPLES ARE ANALYZED BY AN INDEPENDENT LABORATORY, ! TELEDYNE ISOTOPES MIDWEST. THE ANALYTICAL RESULTS ARE l REPORTED AND REVIEWED ON A ROUTINE BASIS TO DETERMINE IF ANY ! UNUSUAL TRENDS ARE DEVELOPING. TABLES 5 AND 6 PROVIDE A

SUMMARY

OF RADIONUCLIDE CONCENTRATIONS IN ENVIRONMENTAL SAMPLES AT DAVIS-BESSE FOR 1986. i i l0 l . l !

   . - _ . _ , . _ . - , . _ , _ , . _ _ . _ _ _ . - . . ~ . . . _ . _ . - - -                      _ _ . . _ . . _ _ . _ , . . . . . _ . - . _ _ .

TABLE 3 h TYPE AND FREQUENCY OF COLLECTION Sampling Location Type Weekly Monthly Quarterly Semi-Annually Annually 1 I AP Al TLD TLD SO 2 I AP Al TLD TLD 50 3 I AP Al SWU TLD TLD S0 4 I AP Al TLD TLD 50 5 i TLD TLD 7 I AP Al TLD TLD WW SO 8 I AP Al TLD H a TLD VE D AF C 50 9 C AP Al TLD TLD 50 11 C AP Al SWU SWT TLD TLD 50 12 C AP Al SWU SWT TLD TLD 50 17 i WW 20 i H* 23 C AP Al TLD a TLD 50 24 C TLD H TLD D 25 I VE 27 C AP Al TLD TLD WW BS SO 28 I SWU SWT 29 i BS 30 i BS 31 I WL SHW 32 i ME i d 33 F WF ST b C 34 C NE VE AF 35 C d F 36 I GLVc 37 C GLV 33-55 1 TLD TLD 50 l SWu ' Semi-monthly during the grazing season, May through October. C Two varieties from each location. d Cattlef eed collected during the 1st quarter, grass collected during 3rd quarter. Two species from each location. 1 O l l l

TABLE 4 SAMPLE CODES USED IN TABLE 3 CODE DESCRIPTION AP AIRBORNE PARTICULATE AI AIRBORNE IODINE TLD(M) THERM 0 LUMINESCENT DOSIMETER - MONTHLY TLD(0) THERM 0 LUMINESCENT DOSIMETER - QUARTERLY M MILK WW WELL WATER (GROUND WATER) ME DOMESTIC MEAT VE FRUITS AND VEGETABLES GLV GREEN LEAFY VEGETABLES AF ANIMAL FEED (SILAGE, GRAIN, GRASS) SMW SMARTWEED SWT SURFACE WATER - TREATED SWU SURFACE WATER - UNTREATED F FISH BS BOTTOM SEDIMENTS SO SOIL WL WILDLIFE (MUSKRAT OR RACCOON) ST SNAPPING TURTLE WF WATER F0WL (GOOSE) O

TABLE 5 h SAMPLING

SUMMARY

, 1986 Collection Number Nunber of Nunter of Sample Type and of Samples Samples Type Frequency, Locations Collected Missed Remarks Air Environment Airborne particulates C/W 11 560b 12 See text. Page 56 Airborne todine C/W 11 560b 12 See text. Page 56 TLDs C/M 31 369 3 See text, Page 56 C/Q 31 121 3 See text, Page 56 Tcrrestrial Environment Hilk (May-Oct) G/SM 3 36 0 (Nov-Anr) G/M 3 18 0 Groundwater G/Q 3 12 0 Edible Meat

a. Domestic meat G/SA 2 4 0

b. Wildlife (two species) G/SA 1 2 0

c. Waterfowl G/A 1 1 0

d. Snapping Turtle G/A 1 1 0 G/SA 3 25 0 Fruits and vegetables (two varieties from each location) 2 8 0 Green leafy vegetables (during G/M harvest season)

Animal and wildlife feed

a. Cattlefeed G/A 2 2 0 Collected 1st Q

b. Crass or corn G/A 2 2 0 Collected 3rd Q G/A 1 1 0

c. Smartweed G/A 11 11 0 soil aquatic Envtronment Treated surface water G/WM 3 156b o Untreated surface water G/WM 2 96b 8 See text Page 56 COMP /WM 2 104b o COMP /M 1 12 0 Fish (two species) G/SA 2 8 0 Bottom sediments G/SA 3 6 0

Type of collection is coded as follows: C/ = continuous; G/ = grab; C0t1P/ = composite. Frequency is coded as foIIOws /'nal
weekly coinposited it:0nthly; /W = weekly; /SM = semi-monthly; /M = monthly; /Q = quarterly,

   /SA = seini-annually; /A = annually.

Samples are ;ent to lahoratory weekly. O 4 e$* b I a o o o e o o o o o a o o o lm' . 1 - e A em = t +o NN e=e o

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TABLE 6 cne iro..mentsi Rad ioio2:<.i noniioring P,os,4a 5.i,4,,, Wame of facility Davis.Besse hac lear Po.er Station Ducket No. 50-346 Location of Facility Otta-a Onio Reporting Period January - Decemoer 1966

                                             .               (County, State)

Indicator Location with etignest Sams.le Type and Locations Control Tys,e Ar.noal mean Locations humber of nean (F)C emanner of (tw. s t s ) Analysesa kangeC nean (F) nean (f) ana-cout one L LLDb Locationd Range Wange mesulgse Air borne 1-131 560 0.0F e lodine 0.44 (16/304) T-2. 56te boundary 0.69 (3/51) 0.40 (11/256) 0 I (pcilm 3) (0.12-1.00) 0.9 mi E (0.29-1.00) (0.12-1.20) 2 1: 0 (ros.ti.ly) Gansna 156 1.0 (aA h ! cass) 13.1 (84/84) T-8. Earl Moore Fara 20.3 (12/12) 14.6 (72/72) 0 (7.8-23.9) 2.7 mi WSW (16.s-23.9) (9. 0-19. 4 ) ILD (Quarter ly) Gaarua 52 1.0 (ak/91 days) 13.6 (28/28) 1-8. Earl Moore Fara 1u.5 (4/4) 14.8 (24/24) 0 a * (9.0-22.1) 2.7 mi W5W (16.0-22.1) (9.2-18.4)

 $    ILD (Monthly)

(mR/91 dJss) Gamma 14l 1.0 15.8(141/141) T-44. 5tte ioundary 21.8 (12/12) stone 0 a (Ir.ner Rin.g (8.2-25.7) 0.5 at v (18.4-25.0)

$s te Bouncary)

ItD (Quarterly) Gaarne 45 1.0 (mk/91 days) 13.3 (45/45) T-45. Site boundary 18.2 (4/4) mone . 0 (Inner king (7.5 19.7) 0.5 at usew (16.1-19.7) Site Boundary) ILD (nonthly) Gaarne 72 1.0 (mR/91 days) 16.1 (72/72) T-50, trie Industrial 18.3 (12/12) kone 0 (Outer Ring, app, (11.8-20.3) Park. 4.5 mi Est of (17.0-20.3) Station by water 5 mi distant) Tower ILD (Quarterly) Gaasna 24 1.0 (mR/91 days) 16.4 (24/24) 1-54. M. Beter farm 18.8 (4/4) alone D (Outer king, (!!.8-21.5) 4.3 at v51 (14.0 21.4) approntmately 5 mi distant) e - -- - - 9 9

                                                                                                                                                  /'N V                                                                               )

TABLE 6 ca.ironment.i a.oioiosicai =nstorin, crosr s. l ry. Name of Fx tlity Davis-Besse Nuclear Power Station Docket 130. 50-34e Location of Facility Ott awa, Unto Reporting Persoo January - Decemoer 1986 (Co nty, State) . Indic ator Location with Highest Control Sample Type and Locatsons annual Mean locatsons m of li pe hooer of me (F)c Mean (t ) j (tan t s ) An a l yses

LLIA nean (t) leon-coattne RangeC Location 8 mange Waage isesults#
Milk (pC1/1 1-1J1 54 0. 5 2.5 (7/36) T-20, Gaeth Farn 3.4 (4/18) 3.3 (4/18) 0 (0.6-8.5) 5.5 mi ww (0.6-8.5) (1.6-5.4) l 9 - U9 54 2. 0 (LLD - - (LLD 0

                         $r-90         54   0. 5        1.7 (36/36)         T-20, Gaetn Fare          1.8 (18/18)               1.7 (18/18)  .       4 (1.0-2.8)            5.5 an uses              ( 1. 2-2. es)             (1.1-2.6) i G5            54 L-N K-40           100           1330 (36/36)        T-20 Gaeta Fara           1350 (18/18)                                   0 I

1250 (18/18) (1100-1640) 5.5 an uses ( t ito-Inwo) (1060-14bol Cs-137 10 (LLp - - (LLO O i i Ha- 140 10 (LLO - - <LLp 8 (g/I) Ca 54 0.5 T-24. Tof t's Dairy 0.94 (36/36) 0.9e (18/18) 0.% (18/18) 0 (0.18-1.11) 24.9 at SE (0. t50-1.17) (0.410 1.21) K 54 0.04 1.51 (36/36) T-20 Gaeta fare 1.54 (18/18) 1.42 (18/lb) 0 (stable) (l.25-1.86) 5.5 at w$is (1.21-1.81) (1.22-1.65) (pCi/g) Sr-90/Ca 54 0.5 1.80 ( 36/36) T-20 Gaeta Fars 1.93 (18/18) 1.82 (18/18) 0 ( 0. 87-2. tml) 5.5 mi ww (1.01-2.80) (1.15-21.4) (pt s/9) Cs-137/K 54 8.3 (LLD - - (LLO O 1

TABLE 6 cn.iroa-cat.: n.aicio9 c i esuiitorin9 ero9r. s-.r1 (continoeai ! n.me of f ac il it y 04.es-ucsse nuc lear Power Station Doctet sea. 5)-146 Locat son of f ac I ty Ot t ama, Ole 30 deporting Persod Januar y - Decemoer 1986 (Cousety. State) Ina sc a tor Location eten Higinest Control 54 006 Type and Locations annual Mean Type Nuncer of Locations huser at Mean (F)C #4ean (t ) Mean (F) soon-routine (Units) Analysesa LL tJb Wange Locationd Wange Menge Aesults'

      . ell water          08 (55) 12                   0. 6                0.7 (1/8)             T-17. Erv fict's well (pt. i/ s )                                                                                                               0.7 (1/4)                        <t Lu        O 0.7 e6 $w                                    -

Gd (D5) 12 1.0' 2.6 (8/8) T-27. Magee Marsa J.7 (1/4) 3.7 (1/4) 0 (1.1-3.7) 5. 3 a s inew - - Gd ( TR ) 12 1. 0 ' 2.6 (d/8) T-27. M49ee Marsa 3.5 (1/4) 3.7(1/4) 0 l (1.7-3.7) 5. 3 m i Wend - - H-3 12 330 <t L D - - (LLO O l

                           $r-89        8               1.2                    (L L O                        -                                -

LLO O Sr-90 8 0.8 <t L O - - (LLO O GS 8 C5-137 10.0 (LLD - GLD I 0 g fainte Meat G5 8 00 I '#9 ** ' K-40 0.1 3.22 (6/6) T-31. (hst te 3.90 (2/2) 1.90 (2/2) 0 (1.95-4.64) 0.6 as sic (3.17-4.64) (1.77-2.02)

                                                                                                                                                                                           -)
                                                                                                                                                                                           -(

Cs-131 0.079 (LLD - -

                                                                                                                                                                  <tL O         O i                      tr-c9      25              0.017                    (LLO                         -

F M ts an -

                                                                                                                                                                  <t L O        O vegeta M es (PC1/g wet) -i
                          $r-9J       25              0.005                 0.008 (3/11)          T-25. Miller fare  ~            0.008 (1/9)                     (LLO          O (0.006-0.010)              3. 7 a s 5                 (0.Es6-0.010)

G5 25 K-40 0.50 2.76 (16/17) T-8. Moore Fars 2.79 (7/8) 2.71 (8/8) 0 (1.00-5.33) 2. 7 mi v5W (1.00-5.33) (1.00-6.33) h3-95 0.03) (LLO - -

                                                                                                                                                                  <LLO          O Ir-95                     0.054                    (LLO                         -                                -
                                                                                                                                                                  <LLO          O Ru-106                    0.25                     <LLO                         -                                -

(LLO O Cs-137 0.028 (LLD - -

                                                                                                                                                                  <LL O         O Ce-141                   0.068                     (LLD                         -                                 -

(LLO O Ce-144 0.76 <LLO - -

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TABLE 6 rn. ror~ntai R.dioiosicai mn e tori,., Prc<a. Su ar, (cont inuco) home of Facility Oswis-Besse n. clear Ga er Statloa Docket ko. 50-346 Location of Factitty Otta.s. onto Reporting Persoo January - Decemoer 19:16 (County. State) Indicator Location unch Hignest Control Sample Type and Locaticns Annual Mean Locations her of Type heter of Mean (F)C Mean (F) Mean (F) son-routine (unst.) 4.elyses* LLIA RangeC Locatione Range Range mesults' sogg au-103 0. 0 36 <L LD - GLD 0 (pC1/g dry) Ro-106 0.69 CLD - - qLD

  '    ( cant 'd)                                                                                                                       0 Cs-137          0.057       0.52 (4/6)         1-23. Put-In-tsay,        1.01 (1/l)          0.51 (5/5)        0 (0.29-0.Ls)          23.5 as w5w                  -

(0.15-1.01) Ce-141 1.12 GLD - - CLD 0 Ce-144 0.66 ALD - - (LLD 0 $ Treated Surface Gs (55) 36 0. 9 (LLD - - GLD 0 e (pct /1) CB (05) 36 1.0 2.1 (12/12) T-ll, Port Clinton 2.5 (12/12) 2.3 (24/24) O (1.2-2.6) 9.5 at SE (1.5-3.5) (1.3-3.5) C8 (TR) 36 1.0 2.1 (12/12) T-11, Port Citnton 2.5 (12/12) 2.3 (24/24) 0 (1.2-2.6) 9.5 at SE (1.5-3.5) (1.3-3.5) H-3 12 330 '

                                                    . GLD                    -                         -

GLD 0 Sr-89 8 i.2 ALD - - (LLD 0 Sr-90 8 1.1 4LD - - (LLD 0 G5 8 Cs-137 10.0 cLLD - -

                                                                                                                         <LL D          0 Untreated Surface   G8 (55) 46       0.7         1.0 (2/22)          1-11 Port Clinton        1.4 (2/12)           1.4 (2/24)       0 water                                           (1.0-1.1)            9.5 at SE               (0.9-1.8)            (0.9-1.8)

GB (05) 46 1.0 2.8 (22/22) T-12. Toledo WP5 3.0 (11/11) 2.8 (24/24) 0 (2.1-3.6) 11.25 at WNW (1.8-3.2) (1.8-4.5) GB (TR) 46 1.0 2.9 (22/22) T-11. Port Clinton 3.1 (12/12) 2.8 (24/24) 0 (2.1-4.5) 9.5 mi SE (1.9-5.4) (1.8-5.4) H-3 36 330 <LLD - - (LLD 0 Sr-89 8 2. 7 GLD - - (LLD 0 0 0 0

lABLE 6 Environ =ntai n.muwic.i mnitoring eros,am su O r, (continued) O Name of Fac ti s t y Davis.* esse Nuclear Power Station Docket No. 50-346 Location of F4:llity Ottawa, Onio Reporting Period January - Decencer 1986 (County State) Indicator Location uitn Hignest Control Sample Type and Locat ions Annual piean Type hus.cer of Locations nummer of Mean (F)C Mean (t) pican (F) hon-routone (Units) Analyses

LLDD RangeC Locationd Range Ran9e Results*

ur. treated Surf ace Sr-90 8 1.2 (LLD - - (LLD ' O , water (pti/l) , G5 8 C5-137 10 (LLD (LLD i 0 fish G3 8 0.1 3.04 (4/4) T-35. Lake Erie 3.92 (4/4) 3.92 (4/4) 0 (DCi/g wet) (2.91-3.34) 15 at NE (2.11-7.52) (2.11-7.52) G5 8 K-40 0.1 2.85 (4/4) T-35. Late Erie 3.07 (4/4) 0 ui 2.64 (4/4) l (2.61-2.94) 15 mi NE (2.94-3.19) (1.90-3.48)

             ,                                         Cs-137          0.037            (LLD                    -                       -                   <L LD           0 botton Sediments                   G8            6   1.0        24.1 (4/4)            T-29. Lake Erie (pCitg dry)                                                                                                  27.7 (2/2)            18.8 (2/2)         0 (18.5-36.6)           Intake.1.5 mi mE          (18.8-36.6)           (18.3-19.4)              .
                                                     $r-89         6   0.024            <LLD                  -                          -                   RLD            0 l                                                   Sr-90         6   0.015       0.030 (2/4)          T-29. Lake Erle.           0.042 (2/2)           0.017 (1/2)        0 j                                                                                  0.018-0.042            Intake                          -                     -

1.5 m1 .c GS 6 K-40 0.1 15.9 (4'4)/ T-29. Lake Erte 19.6 (2/2) 11/3 (2/2) 0 (9.3-20.1) Int ake (18.8-20.1) (11.3-11.3) , 1.5 at NE

                                                  ,    C5-131          0.049            <LLD                    -                        -                   (LLD           0

G8 = gross bet a. C5 = gansna scan. 55 = suspended solids. 05 = dissolved solids. TN
total residue.

                    , Lt0 = nos.inal lower Itait of detection based on 4.66 sigma counting error for sackground sample, d

a up detectde Masuments onh. hattun of hteCtabk measurements at sMif W Maths is inOCaW in pamthses. N). s osations are specified ny station code (Iable 4.1) and distance (miles) and direction relative to reactor site.

                    ,, Non-routine results arelhose editCh eaCeed ten times the Centrol station value.
                    ' Four results; o.O.u. su.007. (0.009 and (0.017) nave been eacluded in the determination of the LLD for gross beta in airborne particulates.
                    ' The elevated LLDsresulted from lou voliane.

Quarterly compositesof all samples from indicator locations and all samples from control locations were gauna scanned together. Taus.tw

                    ,* s.ut ion .itse the hignest annual mean cannot be identified.

Tuenty s t o resu lt s ( <0.10. <0.13. (0.20. <0.10. <0.20 <0.10. <0.08. (0.12. <0.08. <0.16. <0.08. <0.08. (0.10. (0.10. <0.09 <0.35. <p.ots.

                        <u. lu, <u.0w. <u.10. (0.19. <0.08 <0.08 <0.09. <0.16 and <0 12 nave seen escluded in the determination of the LLD of airoorne HMI sse-lJ1.
                     , lhe elevated LtDs resulted from apparent pisap malfunction, low wo esne, or a delay in counting.

S e s result s '(<4.0. <4.8. <4.6. <4.5 <5.4. <5.2) have been escluded in the determination of the LLD for dissolved 501845 and total residue in = ell ester. ine elevated LLDs resulted from hign solids content.

QUALITY ASSURANCE PROGRAM QUALITY ASSURANCE (QA) CONSISTS OF ALL THE PLANNED AND SYSTEMATIC ACTIONS THAT ARE NECESSARY TO PROVIDE ADEQUATE CONFIDENCE IN THE RESULTS OF AN ACTIVITY, IN THIS CASE, OUR ENVIRONMENTAL MONITORING PROGRAM. IN OTHER WORDS, QA IS A PROGRAM WHICH PROVIDES A WAY TO CHECK THE ADEQUACY AND VALIDITY OF OUR MONITORING PROGRAM THROUGH WRITTEN POLICIES, PROCEDURES, AND RECORDS. THE QA PROGRAM AT DAVIS-BESSE IS CONDUCTED IN ACCORDANCE WITH THE GUIDELINES SPECIFIED IN NRC REGULATORY GUIDE 4.15, " QUALITY ASSURANCE FOR RADIOLOGICAL MONITORING PROGRAMS" AND AS REQUIRED BY OUR TECHNICAL SPECIFICATIONS. THE PROGRAM IS DESIGNED TO IDENTIFY POSSIBLE DEFICIENCIES S0 CORRECTIVE ACTIONS MAY BE IMMEDIATELY TAKEN. , DAVIS-BESSE'S QUALITY ASSURANCE PROGRAM ALSO PROVIDES CONFIDENCE IN THE RESULTS OF THE MONITORING PROGRAM THROUGH: e REGULAR AUDITS OF THE MONITOR-ING PROGRAM e PERFORMING AUDITS OF ANALYTICAL CONTRACTOR h LABORATORIES e REQUIRING ANALYTICAL CONTRACTOR LABORATORIES TO PARTICIPATE IN THE UNITED STATES ENVIRONMENTAL PROTECTION AGENCY (US EPA) CROSS-CHECK PROGRAM e REQUIRING ANALYTICAL CONTRACTOR LABORATORIES TO SPLIT SAMPLES FOR SEPARATE ANALYSIS e SPLITTING SAMPLES AND HAVING THE SAMPLES ANALYZED BY INDEPENDENT LABORATORIES, AND THEN COMPARING THE RESULTS FOR AGREEMENT e REQUIRING ANALYTICAL CONTRACTOR LABORATORIES TO PERFORM IN-HOUSE SPIKED SAMPLE ANALYSIS QA AUDITS AND INSPECTIONS OF THE DAVIS-BESSE ENVIRONMENTAL MONITORING PROGRAM ARE PERFORMED BY THE US NRC, US EPA, OHIO EPA AND INDEPENDENT GROUPS, AS WELL AS DAVIS-BESSE'S 0A DEPARTMENT, O di F O IN ADDITION TO THE DAVIS-BESSE ENVIRONMENTAL MONITORING PROGRAM, THE NRC AND THE OHIO EPA ALSO PERFORM INDEPENDENT MONITORING OF THE DAVIS-BESSE ENVIRONMENT. THE RESULTS OF THESE PROGRAMS ARE COMPARED TO THE RESULTS OBTAINED BY DAVIS-BESSE. THE ANALYTICAL LABORATORY USED BY DAVIS-BESSE HAS ITS OWN 4 INTERNAL QUALITY CONTROL PROGRAM FOR THEIR TLD PROGRAM. THEY HAVE ALSO PARTICIPATED IN 5 INTERNATIONAL INTRA-COMPARISONS OF ENVIRONMENTAL DOSIMETERS. O . l l i l lO 1 i

y l 1986 SAMPLING PROGRAM THE SAMPLING PROGRAM WAS CONDUCTED IN ACCORDANCE WITH THE j DAVIS-BESSE TECHNICAL SPECIFICATIONS. 'THE PROGRAM INCLUDED ' COLLECTION (BOTH ON-SITE AND OFF-SITE) AND RADI0 ACTIVE ANALYSES OF AIRBORNE PARTICULATES, AIRBORNE IODINE, DIRECT RADIATION, GROUND (WELL) WATER, MILK, EDIBLE MEAT, FRUIT, ., ANIMAL FEED, S0IL, GREEN LEAFY VEGETABLES, TREATED AND UNTREATED SURFACE WATER, FISH AND LAKE BOTTOM SEDIMENTS. l ALL SAMPLES ARE SENT TO TELEDYNE ISOTOPES MIDWEST LABORATO- ! RIES, UNDER THE MAN 4GEMENT OF L. G. HUEBNER, FOR ANALYSES. o RESULTS OF SAMPLE ANALYSES DURING THE PERIOD JANUARY - DECEMBER 1986 ARE SUMMARIZED IN TABLE 6. T RADIONUCLIDE CONCENTRATIONS MEASURED AT INDICATOR LOCATIONS WERE COMPARED WITH LEVELS MEASURED AT CONTROL LOCATIONS AND IN PREOPERATIONAL STUDIES. SAMPLE RESULTS ARE ALSO COMPARED TO THE LOWER LIMIT OF DETECTION (LLD) 0F THE ANALYSIS BEING PERFORMED. THE LLD IS THE SMALLEST CONCENTRATION OF RADIO-ACTIVITY IN A SAMPLE THAT- NILL BE DETECTED WITH 95% PROBA-BILITY (SEE APPENDIX B). THE COMPARISONS INDICATE BACKGROUND-LEVEL RADI0 ACTIVITIES IN ALL SAMPLES COLLECTED. NO STATION EFFECT ON THE ENVIRONMENT WAS. INDICATED IN ANY OF THE SAMPLING MEDIA COLLECTED AND ANALYZED. THERE WAS AN EFFECT ON THE ENVIRONMENTAL RADI0 ACTIVITY RESULTING FROM AN~ ACCIDENT AT THE CHERNOBYL NUCLEAR REACTOR (USSR) ON APRIL 26, 1986. THE SAMPLING MEDIA AFFECTED WERE AIR AND MILK. IN THE MIDWESTERN STATES OF THE U.S.A., THE RADIOACTIVITY RELEASED DURING THE CHERNOBYL ACCIDENT WAS DETECTED ABOUT TWO WEEKS AFTER THE ACCIDENT. RADIONUCLIDES DETECTED WERE RU-103, RU-106, 1-131, CS-134 AND CS-137 IN AIR, MILK, PRECIPITATION AND VEGETATION. THE HIGHEST LEVEL OF I-131 IN MILK FROM THE MIDWEST ANALYZED WAS 82.2 PCI/L IN MILK COLLECTED MAY 23, 1986 IN ILLINOIS, bY.MID-JUNE, LEVELS OF l-131 (AND GROSS BETA IN THE AIR PARTICULATES) IN THE MIDWEST FELL BELOW THE DETECTION LIMIT (1-131) OR RETURNED TO THE PRE-CHERNOBYL LEVEL ' GROSS BETA). THE LEVEL OF CESIUM ISOTOPES DECREASED BUT WAS STILL DETECT-ABLE SPORADICALLY IN GRASS AND MILK. O

,                 ?"                                                                                          .

1% -

O' rp AT DAVIS-BESSE, THE EFFECTS OF CHERNOBYL WERE NOTED IN AIR PARTICULATES, AIRBORNE IODINE, AND MILK. , e AIR PARTICULATES GROSS BETA IN AIR PARTICULATES COLLECTED BETWEEN MAY

                                         - 12, 1986 AND JUNE 9, 1986 HAD ELEVATED LEVELS RANGING 3

UP TO 0.212 PCI/M FOR ALL LOCATIONS. IN COMPARISON, . GROSS BETA ACTIVITY AVERAGED 0.023 PCI/M 3 DURING 1986, EXCLUDING THE-PERIOD BETWEEN MAY 12, 1986 AND JUNE 9, 1986. m . T -DURING THE SECOND QUARTER OF 1986, FOUR GAMMA-EMITTING On ISOTOPES (RU-103, RU-106, CS-134, AND CS-137) WERE h i DETECTED AND AVERAGED 0.012, 0.010, 0.009, AND 0.017 0 ~ PCI/M3, RESPECTIVELY, THESE ISOTOPES WERE BELOW THEIR i RESPECTIVE LOWER LIMITS OF DETECTION (LLD) LEVELS , DURING THE FIRST, THIRD AND FOURTH QUARTERS. e AIRBORNE IODINE 10 DINE-131 WAS DETECTED IN 27 CHARCOAL SAMPLES COLLECT-l() i ED DURING THE SAME PERIOD AND RANGED FROM 0.12 TO 1.20 PCI/M 3, AVERAGING 0.44 PCI/M 3 FOR ALL MEASUREMENTS. IT WAS BELOW THE DETECTION LIMIT DURING THE REST OF THE YEAR. e MILK ELEVEN MILK SAMPLES COLLECTED BETWEEN MAY 12, 1986 AND JULY 7, 1986 HAD l-131 RANGING FROM 0.6 TO 8.5 PCI/L l AND AVERAGING 2.8 PCI/L. DURING THE REST OF THE YEAR, , 1-131 CONCENTRATIONS WERE BELOW THE LLD LEVEL OF 0.5 l PCI/L. i ALL THESE EFFECTS ARE ATTRIBUTED TO THE CHERN0BYL ACCIDENT,

l SINCE DAVIS-BESSE WAS NOT OPERATING DURING THIS PERIOD AND MANY OF THE ISOTOPES DETECTED ONLY OCCUR WITH MELTING OF

FUEL.

t l THE LEVELS OF RADI0 ACTIVITY DETECTED AROUND DAVIS-BESSE DUE l , , . TO CHERNOBYL WERE SMALL. THE ESTIMATED EQUIVALENT WHOLE !. BODY DOSE DUE TO THESE ELEVATED LEVELS WAS APPROXIMATELY l_: ' l

/'

0.001 MREM. THIS IS ONLY A FRACTION OF THE LIMITS SET BY THE NRC AND EPA FOR EXPOSURE TO THE GENERAL PUBLIC (SEE PAGE 26). r , . - , , _ _ -.,%, .~,,~m__--- ,, -,m,m__ , , _ - , - . - , _ , , , - , me,.

THE PERFORMANCE OF THE PROGRAM IS DISCUSSED IN TABLE 5. THE PROGRAM WAS PERFORMED AS DESCRIBED IN THE FOLLOWING SECTIONS WITH THE FOLLOWING EXCEPTIONS: e THERE WERE NO GROSS BETA IN AIR PARTICULATES NOR AIRBORNE 10 DINE-131 DATA FROM LOCATIONS T-1, T-2, T-3, T-4, T-7, T-8, T-9, T-11, AND T-27 FOR THE WEEK ENDING JUNE 2, 1986 DUE TO A WORK STOPPAGE BY THE IBEW (INTERNATIONAL BROTHERHOOD OF ELECTRICAL WORK-ERS), LOCAL 245. THE NRC WAS CONTACTED AND AGREED THAT SAMPLES NORMALLY COLLECTED ON JUNE 2 CCOULD BE COLLECTED THE FOLLOWING WEEK ON JUNE 9. e THERE WERE NO GROSS BETA IN AIR PARTICULATES NOR AIRBORNE 10 DINE-131 DATA FROM LOCATION T-1 FOR THE COLLECTION WEEKS ENDING SEPTEMBER 8, 1986 AND SEPTEM-BER 15, 1986 BECAUSE AN AIR PUMP BROKE DOWN. e THERE WERE NO GROSS BETA NOR AIRBORNE 10 DINE-131 DATA FROM LOCATION T-9 FOR THE COLLECTION WEEK ENDING SEPTEMBER 2, 1986 BECAUSE SAMPLES WERE LOST IN-TRANSIT TO THE PLANT. e THERE WERE NO TLD DATA FOR LOCATION T-39 FOR THE MONTHS OF MAY AND JULY AND FOR THE SECOND AND THIRD QUARTERS, 1986 BECAUSE TLDS WERE LOST DUE TO VANDALISM. e THERE WERE NO TLD DATA FOR LOCATION I-49 FOR THE MONTH OF OCTOBER AND FOR THE FOURTH QUARTER OF 1986 BECAUSE TLDS WERE LOST DUE TO VANDALISM. e UNTREATED SURFACE WATER FROM LAKE ERIE AT SITE BOUNDARY LOCATION T-3 WAS NOT COLLECTED DURING THE MONTHS OF JANUARY AND FEBRUARY OF 1986 BECAUSE THF LAKE WAS FROZEN. DUE TO THE NUMBER OF SAMPLING STATIONS AND THE WEEKLY SAMPLING SCHEDULE OF MANY OF THESE LOCATIONS, THIS LOSS OF DATA IS NOT SIGNIFICANT. THE DISCUSSION OF THE RESULTS HAS BEEN DIVIDED INTO THREE BROAD CATEGORIES; THE ATMOSPHERIC, TERRESTRIAL, AND AQUATIC ENVIRONMENTS. WITHIN EACH CATEGORY, THE VARIOUS SAMPLES COLLECTED ARE DISCUSSED. 4 i (]) ATMOSPHERIC MONITORING THE ATMOSPHERE IS ONE OF THE PRIMARY EXPOSURE PATHWAYS TO PEOPLE THROUGH BREATHING OR INGESTING RADIONUCLIDES RELEASED TO THE ATMOSPHERE. DAVIS-BESSE MEASURES AIRBORNE RADIOAC-TIVITY CONTINUOUSLY AT ELEVEN LOCATIONS AROUND THE STATION. THE SAMPLING LOCATIONS ARE SHOWN IN FIGURES 2 AND 3. TABLE 1 DESCRIBES THE LOCATIONS, LISTING FOR EACH ITS DIRECTION i AND DISTANCE FROM THE STATION AND INDICATING WHICH ARE INDICATOR AND WHICH ARE CONTROL LOCATIONS. THERE ARE FOUR INDICATOR STATIONS AT THE SITE BOUNDARY AND TWO ON PRIVATE PROPERTY, SAND BEACH AND A LOCAL FARM. THERE ARE FIVE CONTROL LOCATIONS IN NEARBY COMMUNITIES - 0AK HARBOR, PORT CLINTON, TOLEDO, PUT-IN-BAY, AND MAGEE MARSH. THE CONTROL LOCATIONS PROVIDE A MEASURE OF THE BACKGROUND RADI0 ACTIVITY FOR COMPARIS0N WITH THE INDICATOR STATION RESULTS. AIR SAMPLES ARE COLLECTED WEEKLY AND ANALYZED FOR GROSS BETA, RADIOI0 DINE, STRONTIUM-89 AND 90, AND GAMMA-EMITTING , RADIONUCLIDES. NO CONTRIBUTION TO THE GENERAL LEVEL OF AIRBORNE RADI0ACTIV-ITY'COULD BE IDENTIFIED AS A RESULT OF THE OPERATION OF DAVIS-BESSE DURING 1986. THE RADIOACTIVITY DETECTED IS CONSISTENT WITH THE LEVELS NORMALLY FOUND IN THE ENVIRONMENT DUE TO BACKGROUND RADI0 ACTIVITY AND FALLOUT FROM NUCLEAR

WEAPONS TESTING AND CHERNOBYL.

COLLECTION AND ANALYSIS AIR SAMPLING PUMPS ARE USED TO DRAW CONTINUOUS SAMPLES. AIR IS DRAWN AT A FIXED RATE THROUGH PARTICULATE MEMBRANE FILTERS AND CHARC0AL CARTRIDGES AT A RATE OF ABOUT ONE CUBIC FOOT PER MINUTE. THE TOTAL VOLUME IS CALCULATED BASED ON FLOW RATE AND RUNNING TIME. AIR SAMPLING PUMPS ARE CHECKED AND TESTED ON A WEEKLY BASIS AND ARE CALIBRATED AT LEAST EVERY SIX MONTHS. AIR PARTICULATE FILTERS ARE COLLECTED WEEKLY BY ENVIRONMEN-TAL COMPLIANCE PERSONNEL AT ELEVEN LOCATIONS (T-1, T-2, T-3, , T-4, T-7, T-8, T-9, T-11, T-12,-T-23, AND T-27). THE FILTERS ARE HANDLED VERY CAREFULLY SO AS NOT TO DISTURB ANY DEPOSITED PARTICLES. THEY ARE PLACED INTO INDIVIDUAL GLASSINE PROTECTIVE ENVELOPES AND SENT TO THE LABORATORY FOR i RADIOMETRIC ANALYSES. iO 1 i

   -   ,- .-..,      --.- --.- ----- -- ,     - - - - , - - - - -      - - - , - . , . . - , , . , - - - - - , - - - - , -       --n.- -------r,--, , n ,

AIRBORNE PARTICULATE FILTERS ARE ANALYZED WEEKLY FOR GROSS h BETA RADIOACTIVITY. ANY FILTERS SHOWING HIGH BETA ACTIVITY LEVELS (GREATER THAN 10 TIMES THE YEARLY AVERAGE OF CONTROL SAMPLES) WERE ANALYZED BY GAMMA SPECTROSCOPY TO IDENTIFY AND MEASURE GAMMA-EMITTING NUCLIDES. ONCE A QUARTER, ALL FILTERS FROM THE INDICATOR STATIONS (T-1, T-2, T-3, T-4, T-7, AND T-8) WERE COMPOSITED (PUT TOGETHER) AND ALL THE FILTERS FROM THE CONTROL STATIONS (T-9, T-11, T-12, T-23, AND T-27) WERE COMPOSITED. THESE COMPOSITE SAMPLES WERE ANALYZED FOR STRONTIUM -89 AND 90 AND ALSO GAMMA SCANNED USING A GE (LI) DETECTOR. THIS DETECTOR IDENTIFIES AND MEASURES GAMMA EMITTERS. CHARCOAL CARTRIDGES WERE INSTALLED DOWNSTREAM OF THE PARTIC-ULATE FILTERS TO COLLECT AIRBORNE RAD 1010 DINE. CHARC0AL CARTRIDGES WERE COLLECTED AND SENT TO THE LABORATORY WEEKLY. 10 DINE-131 WAS MEASURED USING GAMMA SPECTRAL ANALYSIS OF THE CHARC0AL CARTRIDGES. RESULTS THE AIRBORNE PARTICULATE AND RADIOIODINE ANALYSES RESULTS FOR 1986 WERE WITHIN NORMAL BACKGROUND LEVELS AND NO IN-CREASES WERE NOTED AS A RESULT OF THE OPERATION OF DAVIS-BESSE. AN EFFECT ON AIRBORNE ACTIVITY WAS NOTED IN MAY AND JUNE AS A RESULT OF THE ACCIDENT AT THE CHERNOBYL NUCLEAR REACTOR ON APRIL 26, 1986. THE RESULTS ARE DISCUSSED BELOW. RESULTS OF THE GROSS BETA AIRBORNE RARTICULATE. ANALYSES YIELDED ANNUAL MEANS WHICH WERE NEARLY IDENTICAL AT THE FIVE CONTRglLOCATIONSANDTHESIXINDICATORLOCATIONS(0.033 PCI/M , AND 0.032 PCI/M ,3 RESPECTIVELY). EVIDENCE FOR THIS MAY BE SEEN IN THE SIMILARITY OF THE TRENDS IN THE AVERAGE MONTHLY GROSS BETA CONCENTRATIONS SHOWN IN FIGURE 11. THE 3 HIGHEST ANNUAL MEAN (0.037 PCI/M ) WAS MEASURED AT THE CONTROL LOCATION (T-12). THE ACTIVITY WAS HIGHER THAN IN 1985 (0.024 AND 0.022 PCI/M ,3 RESPECTIVELY). THE INCREASE IS FROM THE CHERNOBYL ACCIDENT. THE RADI0 ACTIVE DEBRIS FROM CHERNOBYL WAS FIRST DETECTED IN SAMPLES COLLECTED ON MAY 12, 1986, AND CONTINUED THROUGH THE COLLECTION PERIOD ENDING ON JUNE 9, 1986. ANALYSES OF AIR PARTICULATES COLLECTED ON JUNE 16, 1986 SHOWED THAT GROSS BETA ACTIVITY RETURNED TO THE PRE-CHERNOBYL LEVEL. O O GROSS BETA ACTIVITY DURING THIS PERIOD RANGED UP TO 0.212 PCI/M3 AND AVERAGED 0.134 PCI/M , IN COMPARISON, GROSS BETA ACTIVITY AVERAGED 0.023 PCI/M ,3 DURING THE YEAR, EXCEPT FOR

;      THE PERIOD BETWEEN MAY 12, 1986 AND JUNE 9, 1986, (AGAIN DUE TO CHERNOBYL).

A SPRING PEAK IN BETA CONCENTRATION HAD BEEN OBSERVED ALMOST ANNUALLY FOR MANY YEARS. THE PEAK HAD BEEN ATTRIBUTED TO FALLOUT OF NUCLIDES FROM THE STRATOSPHERE, IT WAS PRO-NOUNCED IN 1981, OCCURRED TO A LESSER DEGREE IN 1982, AND , DID NOT OCCUR IN 1983, 1984, OR 1985. IN 1986, THE SPRING , PEAK COULD NOT BE IDENTIFIED BECAUSE IT WAS OVERSHADOWED BY THE RELEASES OF RADI0 ACTIVITY FROM CHERNOBYL. GROSS BETA ANNUAL AVERAGES FOR EACH LOCATION ARE PRESENTED IN TABLE-7. STRONTIUM-89 AND STRONTIUM-90 CONCENTRATIONS WERE BELOW ! THEIR RESPECTIVE LOWER LIMITS OF DETECTION (LLD) 0F 0.005

AND 0.001 PCI/M3 IN ALL SAMPLES, GAMMA SPECTROSCOPIC ANALYSIS OF QUARTERLY COMPOSITES OF AIR i PARTICULATE FILTERS YIELDED SIMILAR RESULTS FOR INDICATOR AND CONTROL LOCATIONS. BERYLLIUM-7, WHICH IS PRODUCED O CONTINUOUSLY IN THE UPPER ATMOSPHERE BY COSMIC RADI'ATION, WAS DETECTED IN ALL SAMPLES. ALL OTHER GAMMA-EMITTING ISOTOPES WERE BELOW THEIR RESPECTIVE LLDS DURING THE FIRST, THIRD, AND FOURTH QUARTERS. DORING THE SECOND' QUARTER OF 1986, FOUR GAMMA-EMMITTING

ISOTOPES (RU-103, RU-106, CS-134, AND CS-137) WERE IDfNTI-I FIED AND AVERAGED 0.012, 0.010, 0.009 AND 0.017 PCI/W ,

l RESPECTIVELY. THE RATIO 0F CS-134 TO CS-137 IN AIR PARTICU-

;      LATES WAS ABOUT 1:2, THE SAME AS IN THE MIX OF GASES RE-LEASED AT THE TIME OF THE ACCIDENT AT CHERNOBYL.

WEEKLY LEVELS OF AIRBORNE 10 DINE-131 WERE BELOW THE LOWER ! LIMIT OF DETECTION (LLD) 0F 0.07 PCI/M 3 IN 507 0F THE 560 l SAMPLES ANALYZED. THE LLD OF 0.07 PCI/M3 COULD NOT BE REACHED IN 26 SAMPLES BECAUSE OF LOW VOLUME RESULTING FROM A I PUMP MALFUNCTION (ELEVATED AIRBORNE IODINE RESULTS ARE PRESENTED IN APPENDIX C). 10 DINE-131 LEVELS IN 27 SAMPLES COLLECTED BETWEEN MAY 12, i 1986 AND JUNE 9, 1986 RANGED UP TO 1.20 PCI/M3 AND AVERAGED i 0.44 PCI/M AT INDICATOR LOCATIONS AND 0.40 PCI/M3 AT

CONTROL LOCATIONS.

l

i l THE PRESENCE OF AIRBORNE I-131 IN THE ENVIRONMENT IN MAY AND JUNE IS FROM THE CHERNOBYL ACCIDENT, O l 0

FIGURE 11 Monthly ^verages O = = m .n. - - 0.15 0.14 - 0.13 - 0.12 - 0.11 - (CHERNOBYL) 0.1-0.09 J n . E 0 08 - l \ 6 0.07 - a 0.06 - 0.05 - , 0.04 -

g1 , ACAT106 ' Q & " O.01-0 i i i i i i i i , i l JAN FB liar APR liAY JUN Jul. AUG SEP OCT NOV DEC lionth

+ l !^ O TA8te 7 , 1986 AVERAGE GROSS BETA CONCENTRATIONS 3 LOCATION ANNUAL AVERAGE (PCI/M ) i T-l'(I) 0.034 i T-2 (I) 0.035 ; I T-3 (I) 0.031

;                     T-4 (I)                                                                                      0.029 T-7 (I)                                                                                      0.032 1

T-8 (I) 0.032 i

!                     T-9 (C)                                                    .                                 0.033 i

i T-11 (C) 0.031 i T-12 (C) 0.037 l. T-23 (C) 0.031 I T-27 (C) 0.034 ! (I) - INDICATOR LOCATION i (C) - CONTROL LOCATION NOTE: AS YOU CAN SEE THE ANNUAL AVERAGES FOR EACH LOCATION j ARE S0 CLOSE THAT THE DIFFERENCES ARE NOT SIGNIFICANT. i i i i { i iO l

',,,._,,_-..----_,,,-          __     . . -_~,. ,, ,., - , , - ,,, ,_, _ ., _ ,_                          _     ,         _ _ ,      . _ - _ _ - - , -

DIRECT RADIATION MONITORING llhI POPULATIONS MAY BE EXPOSED TO EXTERNAL RADIATION FROM SEVERAL SOURCES, INCLUDING AIRBORNE EFFLUENTS AND DEPOSITION OF RADIONUCLIDES ON SOIL OR VEGETATION. DAVIS-BESSE NUCLEAR POWER STATION OPERATES A TOTAL OF 31 RADIATION MONITORING STATIONS. THERE ARE 25 INDICATOR SITES WITHIN 5 MILES AND 6 CONTROL SITES MORE THAN 5 MILES FROM THE PLANT, NATURALLY OCCURRING SOURCES, INCLUDING RADIATION OF COSMIC ORIGIN AND NATURAL RADI0 ACTIVE MATERIALS IN THE AIR AND GROUND, AS WELL AS FALLOUT FROM WEAPONS TESTING AND CHERNOBYL, RESULTED IN A CERTAIN AMOUNT OF RADIATION BEING RECORDED AT ALL MONITORING LOCATIONS. THE AMOUNT OF BACK-GROUND RADIATION IS DETERMINED FROM THE TLDS LOCATED AT THE - CONTROL SITES. RESULTS OF THE RADIATION MONITORING PROGRAM AT DAVIS-BESSE SHOWED THAT THE DOSE RATES PRESENT DURING 1986 WERE SIMILAR TO BACKGROUND LEVELS OF PREVIOUS YEARS. COLLECTION AND ANALYSIS RADIATION LEVELS AT AND AROUND DAVIS-BESSE ARE CONSTANTLY MONITORED BY A NETWORK OF THERM 0 LUMINESCENT DOS! METERS lll (TLDS). THE TLD PACKETS USED AT DAVIS-BESSE CONTAIN THREE CALCIUM FLOURIDE MANGANESE (CAF2: MN) BULBS. THREE BULBS ARE USED TO ENSURE THE PRECISION OF THE MEASUREMENTS. THERM 0 LUMINESCENCE IS A PROCESS IN WHICH IONIZING RADIATION INTERACTS WITH THE SENSITIVE MATERIAL IN THE TLD (THE PH0SPHOR) AND SOME OF THE ENERGY IS STORED IN " TRAPS" IN THE TLD MATERIAL. THE TLD TRAPS ARE SO STABLE THAT THEY DO NOT DECAY APPRECIABLY OVER MONTHS OR EVEN YEARS. THIS PROVIDES AN EXCELLENT METHOD TO MEASURE DOSES RECEIVED OVER LONG PERIODS OF TIME. THE AMOUNT OF ENERGY THAT WAS STORED IN THE TLD AS A RESULT OF INTERACTION WITH RADIATION IS REMOVED AND MEASURED BY A CONTROLLED HEATING PROCESS IN A CALIBRATED READING SYSTEM. AS THE TLD IS HEATED, THE PHOSPHOR RELEASES THE STORED ENERGY AS LIGHT. THE AMOUNT OF LIGHT RELEASED IS DIRECTLY PROP 0RTIONAL TO THE AMOUNT OF RADIATION TO WHICH THE TLD WAS EXPOSED. THE READING PROCESS REZEROS THE TLD AND PREPARES IT FOR RE-USE. 9

                              -..                 -          . _ = _    .  .      .-    . _ _ .    -  -_ .  - ._,

i O TWO SETS OF TLD PACKETS ARE PLACED AT EACH LOCATION. ONE SET IS COLLECTED AND. REPLACED MONTHLY. THE.SECOND SET'IS COLLECTED AND REPLACED QUARTERLY. THE TLDS ARE SENT TO THE LABORATORY TO BE READ. DAVIS-BESSE HAS TLDS LOCATED AT THIRTY-ONE (31) LOCATIONS. i THERE ARE SIX CONTROL STATIONS (T-9, T-11, T-12, T-23, T-24, AND T-27) LOCATED IN SUCH A MANNER AS NOT TO BE INFLUENCED BY DAVIS-BESSE. THERE ARE THIRTEEN (13) REGULAR INDICATOR STATIONS (T 5, T-7, T-8, AND T 55) AND. TWELVE

SPECIAL INDICATOR STATIONS (T 49). THE REGULAR l INDICATOR STATIONS INCLUDE LOCATIONS ON-SITE AND UP TO 5

!                                   MILES AWAY FROM DAVIS-BESSE. THE SPECIAL INDICATOR LOCA-TIONS ARE AT THE SITE BOUNDARY AND FORM A RING AROUND THE

STATION. .

j THE NRC ALSO PERFORMS DIRECT RADIATION MONITORING AT MANY l LOCATIONS AT AND AROUND DAVIS-BESSE. THE NRC TLD DIRECT i- RADIATION MONITORING NETWORK FOR DAVIS-BESSE NUCLEAR POWER L STATION WAS ESTABLISHED IN THE SPRING OF 1980. THE NRC HAS i TWENTY-TWO (22) TLD STATIONS DISTRIBUTED IN TWO RINGS CENTERED AROUND THE DAVIS-BESSE RADIOLOGICAL RELEASE STACK.

                                    '"" '"""" "'""  '              c^'"" " ""'" ^ '" -"' "^"'"' ^" '""

i O OUTER RING IS LOCATED WITHIN A FIVE-MILE RADIUS OF THE SITE. WITHIN EACH RING, A TLD STATION IS LOCATED IN EACH STANDARD l WINDR0SE SECTOR UNLESS THE SECTOR CONSISTS ENTIRELY OF OPEN i WATER:0R UNOCCUPIED, INACCESSIBLE LAND. THE NRC DOSIMETER ! FOR EACH STATION IS PLACED IN A MOISTURE-RESISTANT POLYESTER j POUCH INSIDE A POLYPROPYLENE MESH CYLINDRICAL CONTAINER. i THE CONTAINERS ARE ATTACHED TO A RELATIVELY PERMANENT STRUCTURE, SUCH AS A UTILITY POLE. ONCE PLACED IN THE i FIELD, THE NRC TLDS ARE NOT RECOVERED UNTIL THE NEXT QUAR-l TERLY SHIPMENT IS RECEIVED. I RESULTS i' RESULTS OF THE RADIATION MONITORING PROGRAM AT DAVIS-BESSE ( SHOWED THAT THE DOSE RATES PRESENT DURING 1986 WERE SIMILAR TO BACKGROUND LEVELS OF PREVIOUS YEARS. e ! THE MONTHLY AND QUARTERLY TLDS FOR THE CONTROL, REGULAR } ^ INDICATOR AND SPECIAL INDICATOR LOCATIONS SHOWED ALMOST IDENTICAL READINGS WITH NO SIGNIFICANT VARIANCE. THE RESULTS OF THESE TLDS ARE SHOWN ON THE NEXT PAGE. O i l L - . - - - . . - . . - . , . - - - - - . _ . . - . . _ _

AVERAGE TLD EXPOSURE LOCATION MONTHLY QUARTERLY (MREM /91 DAYS) (MREM /91 DAYS) CONTROL 14.6 2.6 14.8 2.6 REGULAR INDICATOR 14.5 3.5 14.8 2.6 SPECIAL INDICATOR 15.7 4.4 13.3 2.9 THE ANNUAL AVERAGE DOSE EQUIVALENT FOR ALL LOCATIONS MEA-SURED BY MONTHLY AND QUARTERLY TLDS WAS SIMILAR TO PREVIOUS YEARS. THEY WERE: e 1980 - 14.5 MREM /91 DAYS e 1981 - 14.8 MREM /91 DAYS e 1982 - 14.5 MREM /91 DAYS e 1983 - 13.2 MREM /91 DAYS e 1984 - 13.2 MREM /91 DAYS e 1985 - 14.4 MREM /91 DAYS ll e 1986 - 14.8 MREM /91 DAYS THESE VALUES ARE LOWER THAN THE ESTIMATED AVERAGE NATURAL BACKGROUND RADIATION FOR MIDDLE AMERICA, 19.5 MREM /91 DAYS BASED ON DATA FROM THE REPORT " NATURAL BACKGROUND RADIATION IN THE UNITED STATES," (NATIONAL COUNCIL ON RADIATION PROTECTION AND MEASUREMENTS, 1975). FIGURES 12 - 14 PRESENT A CoMPARIS0N OF RESULTS FROM CONTROL AND INDICATOR STATIONS. THESE GRAPHS SHOW THAT THE MONTHLY AND QUARTERLY AVERAGES FOR ALL LOCATIONS ARE ALMOST IDENTICAL, FOR EACH NRC LOCATION, THE RESULTS WERE COMPARED TO THOSE OF PREVIOUS YEARS AND TO THOSE OF DAVIS-BESSE. THE RESULTS WERE VERY SIMILAR. IN 1985, THE NRC TLDS AVERAGED 16.9 2.9 MREM /91 DAYS AND IN 1986 THEY AVERAGED 16.8 2.4 MREM /91 DAYS. FIGURE 12 Mhl7 ^"8 O Ambiud Gamma Relaise(D) ' 10 9-8- 7- [ 6-O 1 0 Mi g h I

                                                                                                    \lj               1 E Esut4L                                                  "

J i , 3-2- 1-0 ii iiiiiiiiiiiiiii i i i i i N M EY Jul. SEP NOV N N EY JUI. SEP NOV l O - , a

 - - - - ,.,,,,--,,,---,.--.,----,,,,---,---,-,,---.-,,------,,,-,-------c-    -        --             -        -
                                                                                                                                        .+n-,          - - - - , - - - - - - - - - - - -

FIGURE 13 Quarterly Averages O ,

                              --x                               .

19 - 18 - 17 - M$J: - E WCAT0lt 14 .i 13 - [ 12 - l 11-O i E

         'l~.

E 8-7- 6-5- 4-3- 2-1- 0 i i i i i i 1&1 1&2 IW3 1@4 151 1&2 153 1&4 0 -

FIGURE 14 Quarterly Averages O mmmu ' a 19-18 - 1 17-CoE1p_: 15 - 4- i SPECALICCATOR v 13- [ 12 - l 11-

      ;    10 -
      )     9-E     8-7-

6-5- , 4-3- l 2-( t-0 i i i i i i 161 162 t@3 164 1%1 1&2 153 1%4

(~'s (J TERRESTRIAL MONITORING FOOD, MILK, GROUND WATER AND SOIL PLAY A VITAL ROLE IN THE LIFE OF MAN. THEY ALL DIRECTLY AFFECT WHAT MAN CONSUMES AND PROVIDE AN IMPORTANT METHOD TO MEASURE MAN'S RADIATION DOSE DUE TO INGESTION, RADIONUCLIDES CAN BECOME INCORPORATED INTO MAN'S FOOD CHAIN BY BEING DEPOSITED ON PLANTS AND SOIL FROM ATMOSPHERIC RELEASES AND ALSO FROM IRRIGATION OF CROPS USING LAKE WATER THAT RECEIVES LIQUID EFFLUENTS (SEE FIGURE 4). RADIONUCLIDES ARE PRESENT IN THE ENVIRONMENT DUE TO NATURAL BACKGROUND RADI0 ACTIVITY AND FROM NUCLEAR FALLOUT AND ARE EXPECTED TO BE PRESENT TO SOME EXTENT IN ALL SAMPLES COL-LECTED. THE CONTRIBUTION OF RADIONUCLIDES FROM THE OPERA-T!ON OF DAVIS-BESSE WAS ASSESSED BY COMPARING THE RESULTS OF SAMPLES COLLECTED AT THE INDICATOR STATIONS WITH CONTROL SAMPLES AND ALSO WITH HISTORICAL LEVELS FOR BACKGROUND. A LAND USE CENSUS WAS CONDUCTED TO DETERMINE THE LOCATIONS OF THE NEAREST MILK ANIMALS AND GARDENS, GREATER THAN 500 (~'\ SQUARE FEET PRODUCING BROAD LEAF VEGETATION, IN EACH OF THE

 \                                  16 CARDINAL COMPASS POINT SECTORS OUT TO A DISTANCE OF FIVE MILES. THE RESULTS OF THIS CENSUS ARE PRESENTED IN THE LAND USE CENSUS SECTION.

ALL SAMPLES COLLECTED IN 1986 SHOWED THAT THE OPERATION OF DAVIS-BESSE DID NOT CONTRIBUTE TO THE RADI0 ACTIVITY LEVELS IN THE ENVIRONMENT. DAVIS-BESSE MONITORS THE TERRESTRIAL ENVIRONMENT BY COLLECT-ING AND ANALYZING SAMPLES OF GROUND WATER, MILK, EDIBLE MEAT, FRUITS AND VEGETABLES, ANIMAL AND WILDLIFE FEED, S0IL AND GREEN LEAFY VEGETABLES, GROUND (WELL) WATER GROUND (WELL) WATER IS NOT LIKELY TO BE AFFECTED BY THE OPERATION OF DAVIS-BESSE. IT IS NOT USUALLY AFFECTED UNLESS THERE ARE LIQUID DISCHARGES TO THE GROUND AND DAVIS-BESSE DOES NOT DO THIS. HOWEVER, SAMPLES ARE COLLECTED QUARTERLY AT THREE LOCATIONS. O

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h (LLD) FOR ALL ANALYSES PERFORMED. THIS SHOWS THAT THE OPERATION OF DAVIS-BESSE HAD NO EFFECT ON RADIONUCLIDE CONCENTRATIONS IN GROUND (WELL) WATER. GROSS BETA CONCENTRATIONS IN SUSPENDED SOLIDS WERE BELOW THE LLD OF 0.6 PCI/L IN ALL SAMPLES BUT ONE. THE DETECTED CONCENTRATION WAS BARELY AB0VE THE LLD LEVEL (0.7 PCI/L). GROSS BETA CONCENTRATIONS IN DISSOLVED SOLIDS AVERAGED 2.6 PCI/L AT THE INDICATOR LOCATIONS AND 3.7 PCI/L AT THE CONTROL LOCATION. THE LOCATI'ON WITH THE HIGHEST ANNUAL AVERAGE WAS THE CONTROL LOCATION T-27 AND WAS 3.7 PCI/L. THE CONTROL SAMPLES MEASURE THE BACKGROUND (NORMAL) LEVEL OR RADI0 ACTIVITY. FOR THE WELL WATER SAMPLES THE CONTROL SAMPLE.WAS HIGHER THAN THE INDICATOR. THIS MEANS THAT ONLY BACKGROUND ACTIVITY IS BEING DETECTED AND THAT NO RADI0AC-TIVITY FROM DAVIS-BESSE IS PRESENT. THE RANGE OF GROSS BETA CONCENTRATIONS WERE SIMILAR TO THOSE OBSERVED IN 1978 THROUGH 1985. TRITIUM CONCENTRATION WAS BELOW THE LOWER LIMIT DETECTION IN ALL SAMPLES. O b ( ]) STRONTIUM-89 AND STRONTIUM-90 CONCENTRATIONS WERE BELOW THEIR RESPECTIVE LLDS OF 1.2 PCI/L AND 0.8 PCI/L IN ALL

SAMPLES.

ALL SAMPLES WERE BELOW THE LLD OF 10.0 PCI/L FOR CESIUM-137 CONCENTRATION. E MILK IS IMPORTANT IN ASSESSING THE POTENTIAL DOSE CONSUMED BY MAN. MILK IS ONE OF THE FEW FOOD PRODUCTS THAT IS i CONSUMED SHORTLY AFTER IT IS PRODUCED AND IS CONSUMED BY PEOPLE OF ALL AGES, INCLUDING INFANTS. THE MILK PATHWAY. CONSISTS OF THE DEPOSITION OF RADIONUCLIDES FROM ATMOSPHERIC RELEASES ONTO PLANTS CONSUMED BY' COWS. THE C0WS PRODUCE MILK WHICH IS CONSUMED BY MAN (SEE FIGURE 4). THE ISOTOPES OF CONCERN ARE PRIMARILY 10 DINE-131 AND STRONTIUM-89 AND -90 WHICH TEND TO CONCENTRATE IN MILK. ] COLLECTION AND ANALYSIS

/T SAMPLES OF UNTREATED COW MILK WERE COLLECTED MONTHLY FROM k- / NOVEMBER THROUGH APRIL AND SEMI-MONTHLY FROM MAY THROUGH
OCTOBER (GRAZING SEASON) FROM TWO LOCATIONS (T-8 AND T-20)

BY ENVIRONMENTAL COMPLIANCE PERSONNEL. SAMPLES WERE ALSO COLLECTED FROM A CONTROL LOCATION (T-24) IN SANDUSKY, AT THE SAME FREQUENCY, AS A MEASUREMENT OF BACKGROUND RADI0 ACTIVITY LEVELS. THE SAMPLES WERE COLLECTED IN CLEAN, UNUSED PLASTIC i CONTAINERS. TWO GALLONS WERE COLLECTED FROM EACH LOCATION AND WERE SHIPPED IMMEDIATELY, ON ICE, TO THE LABORATORY. } TO COMPLY WITH THE ENVIRONMENTAL TECHNICAL SPECIFICATIONS ! FOR DAVIS-BESSE NUCLEAR POWER STATION, ANALYSIS FOR IODINE

                                  -131 WAS CONDUCTED WITHIN 8 DAYS OF CAMPLING.                                                                     IODINE -131 WAS SEPARATED CHEMICALLY AND WAS BETA COUNTED TO OBTAIN A l                                 MINIMUM SENSITIVITY OF 0.5 PCI/L AND O'..RALL ERROR (1 SIGMA CONFIDENCE LEVEL) 0F                              25% WHEN 10 DINE-131 ACTIVITY EXCEEDS

+ 0.5 PCI/L. THE SAMPLES WERE ALSO ANALYZED FOR STRONTIUM -89 AND 90, CALCIUM, STABLE POTASSIUM AND A GAMMA SPECTRAL ANALYSIS PERFORMED. i _ - _ _ . . . _ _ , . _ ~ . . , _ _ _ . _ - _ , _ , , . . . - , . _ . -

                                                                                      , _ _ _ .       __ _ ,m. _ _- ., - - - . . . . _ _ , ,               _ . _ , -     _ . , _ . . _ , _ . _ , ,

RESULTS lh A TOTAL OF 54 MILK SAMPLES WERE COLLECTED AND ANALYZED IN 1986. THE RESULTS OBTAINED WERE SIMILAR TO THOSE OF PREVI-OUS YEARS WITH THE EXCEPTION OF SAMPLES COLLECTED IN MAY, JUNE, AND JULY. THESE SAMPLES SHOWED INCREASED LEVELS DUE TO FALLOUT FROM THE CHERN0BYL ACCIDENT. A TOTAL OF 54 ANALYSES FOR 10 DINE-131 IN MILK WERE PERFORMED DURING THE REPORTING PERIOD. FORTY-THREE SAMPLES HAD l-131 CONCENTRATIONS BELOW THE LLD LEVEL OF 0.5 PCI/L. ELEVEN SAMPLES, COLLECTED BETWEEN MAY 12, 1986 AND JULY 7, 1986, CONTAINED I-131 IN VARIOUS CONCENTRATIONS. THE LEVEL RANGED FROM 0.6 TO 8.5 PCI/L AND AVERAGED 2.8 PCI/L. VARIABILITY IN CONCENTRATION OF l-131 IN MILK DEPENDED ON THE METHOD OF FEEDING THE COWS (WHETHER THEY GRAZED OUTDOORS OR WERE FED ON STORED FEED). THE PRESENCE OF l-131 IN MILK COLLECTED DURING THIS PERIOD IS FROM THE CHERNOBYL ACCIDENT. STRONTIUM-90 ACTIVITY WAS DETECTED IN ALL SAMPLES COLLECTED AND RANGED FROM 1.0 TO 2.8 PCI/L. THE ANNUAL AVERAGE VALUE FOR STRONTIUM-90 WAS IDENTICAL AT BOTH INDICATOR AND CONTROL LOCATIONS (1.7 PCI/L). THEREFORE THERE WAS NO EFFECT FROM DAVIS-BESSE. THE LOCATION WITH THE HIGHEST AVERAGE (1.8 PCI/L) WAS INDICATOR LOCATION T-20, WHICH IS STILL EXTREMELY LOW. THE AVERAGE VALUES WERE SIMILAR TO THOSE MEASURED IN 1977 THROUGH 1985. STRONTIUM-89 WAS BELOW THE LLD LEVEL OF 2.0 PCI/L IN ALL SAMPLES. THE CONCENTRATIONS OF BARIUM-140 AND CESIUM-137 WERE BELOW 10 PCI/L IN ALL SAMPLES COLLECTED. RESULTS FOR POTASSIUM-40, A NATURALLY OCCURING RADIONUCLIDE, WERE SIMILAR AT CONTROL AND INDICATOR LOCATIONS (1250 AND 1330 PCI/L, RESPECTIVELY). INDICATOR LOCATION T-20 HAD THE HIGHEST AVERAGE (1350 PCI/L). THE LEVELS WERE ALMOST IDENTICAL TO THOSE OBSERVED IN 1985. O I SINCE THE CHEMISTRIES OF CALCIUM AND STRONTIUM, AND POTASSI-UM AND CESIUM ARE SIMILAR, ORGANISMS TEND TO DEPOSIT CESIUM

        -137 IN MUSCLE TISSUE AND STRONTIUM-89 AND -90 IN BONES. IN ORDER TO DETECT POTENTIAL ENVIRONMENTAL ACCUMULATION OF THESE RADIONUCLIDES, THE RATIOS OF STRONTIUM-90 ACTIVITY TO THE WEIGHT OF CALCIUM AND OF THE CESIUM-137 ACTIVITY TO THE WEIGHT OF STABLE POTASSIUM WERE MONITORED IN MILK. THE MEASURED CONCENTRATIONS OF CALCIUM AND STABLE POTASSIUM WERE IN AGREEMENT WITH PREVIOUSLY DETERMINED VALUES OF 1.16 0.08 G/L AND 1.50 0.21 G/L, RESPECTIVELY. NO STATISTICALLY SIGNIFICANT VARIATIONS IN THE RATIOS WERE OBSERVED.

I O i l l I O

1 EDIBLE MEAT llh EDIBLE MEAT, BOTH DOMESTIC AND WILD, PROVIDES A SOURCE FOR THE ASSESSMENT OF THE INDIRECT CONSUMPTION PATHWAY OF RADIONUCLIDES BY PEOPLE. RADIONUCLIDES MAY BE DEPOSITED FROM THE ATMOSPHERE ON FOODS CONSUMED BY ANIMALS WHICH ARE THEN CONSUMED BY HUMANS. SAMPLES WERE TAKEN SEMI-ANNUALLY AT 4 LOCATIONS AND INCLUDED MUSKRAT AND CHICKEN. A GOOSE AND A SNAPPING TURTLE WERE ALSO COLLECTED. COLLECTION AND ANALYSIS SEM! ANNUALLY, DOMESTIC MEAT SAMPLES (CHICKENS) WERE COLLECT-ED FROM ONE INDICATOR LOCATION (T-32) AND ONE CONTROL LOCATION (T-34) AND ONE REPRESENTATIVE SPECIES OF WILDLIFE (MUSKRAT) WAS COLLECTED ON-SITE (T-31). IN ADDITION, ONE CANADA GOOSE AND ONE SNAPPING TURTLE WERE COLLECTED ON-SITE (T-31). SAMPLES WERE SHIPPED TO THE CONTRACTOR LABORATORY, WHERE A GAMMA SPECTRAL ANALYSIS WAS PERFORMED ON THE EDIBLE PORTION OF THE MEAT. RESULTS IN THE EDIBLE MEAT SAMPLES (CHICKENS, MUSKRAT, CANADA GOOSE, AND SNAPPING TURTLE) THE MEAN POTASSIUM-40 CONCENTRATION WAS 3.22 PCI/G WET WEIGHT FOR THE INDICATOR LOCATIONS AND 1.90 PCI/G WET WEIGHT FOR THE CONTROL LOCATION. CESIUM-137 CONCENTRATION WAS BELOW THE LLD OF 0.029 PCI/G WET WEIGHT IN ALL SAMPLES. 9 FRUITS AND VEGETABLES (}}) FRUITS AND VEGETABLES MAY BE DIRECTLY OR INDIRECTLY AFFECTED BY RADIONUCLIDE DEPOSITION. RADIONUCLIDES FROM ATMOSPHERIC RELEASES CAN BE DEPOSITED ON THE OUTSIDE OF THE FRUITS AND VEGETABLES. ALSO, RADIONUCLIDES FROM THE SOIL CAN BE TAKEN UP BY THE PLANT'S ROOTS AND BECOME INCORPORATED INTO THE FLESH OF THE FRUIT OR VEGETABLE. FRUITS AND VEGETABLES WERE COLLECTED AT 2 INDICATOR LOCA-TIONS WITHIN 5 MILES OF THE PLANT AND AT 1 CONTROL LOCATION GREATER THAN 10 MILES FROM THE PLANT. COLLECTION AND ANALYSIS SEMIANNUALLY, AT LEAST TWO VARIETIES OF FRUITS AND VEGETA-BLES WERE COLLECTED FROM EACH OF TWO INDICATOR LOCATIONS (T-8 AND T-25) AND FROM ONE CONTROL LOCATION (T-34). A SAMPLE CONSISTS OF 5 - 10 POUNDS OF FRUIT OR VEGETABLE, DEPENDING ON THE WATER CONTENT. FOR EXAMPLE, MORE TOMATOES ARE NEEDED FOR ANALYSIS THAN CARROTS OR BEANS. THE SAMPLES WERE COLLECTED AND SEALED IN PLASTIC BAGS TO

       \ _,/ PREVENT LOSS OF MOISTURE, PACKED IN A COOLER ON ICE AND SHIPPED IMMEDIATELY TO PREVENT SPOILAGE. THE EDIBLE PORTION WAS ANALYZED FOR STRONTIUM-89 AND 90 AND RECEIVED A GAMMA

, SPECTRAL ANALYSIS. RESULTS ANALYSES PERFORMED ON ALL FRUIT AND VEGETABLE SAMPLES SHOWED LEVELS THAT WERE EITHER BELOW LOWER DETECTABLE LIMITS (LLD) OR SIMILAR TO RESULTS OBTAINED IN PREVIOUS YEARS. THE RESULTS SHOW THAT DAVIS-BESSE HAD NO EFFECT ON THE LEVELS OF RADI0 ACTIVITY PRESENT IN FRUITS AND VEGETABLES. STRONTIUM-89 WAS BELOW THE LLD OF 0.017 PCI/G WET WEIGHT IN ALL ' SAMPLES. STRONTIUM-90 WAS DETECTED IN THREE OF TWENTY-FIVE SAMPLES AND RANGED FROM 0.006 TO 0.010 PCI/G WET WEIGHT, WHICH IS STILL VERY LOW AND COMPARABLE TO PREVIOUS YEARS. O

THE ONLY GAMMA-EMITTING ISOTOPE DETECTED WAS NATURALLY-OCCURRING POTASSIUM-40. THE AVERAGE CONCENTRATIONS WERE 2.76 PCI/G WET WEIGHT FOR THE INDICATOR LOCATIONS AND 2.71 PCI/G WET WEIGHT FOR THE CONTROL LOCATIONS. THE CONCENTRATIONS DETECTED WERE IDENTICAL OR SIMILAR TO THOSE DETECTED IN 1977 THROUGH 1985. ALL OTHER GAMMA-EMITTING ISOTOPES WERE BELOW THEIR LLDS. ANIMAL AND WILDLIFE FEED ANIMAL AND WILDLIFE FEED, LIKE FRUITS AND VEGETABLES, CAN RECEIVE EITHER DIRECT EXTERNAL DEPOSITION OF RADIONUCLIDES OR INTERNAL DEPOSITION BY ROOT UPTAKE FROM THE SOIL. THIS FEED IS CONSUMED BY ANIMALS WHICH COULD BE CONSUMED BY HUMANS, SAMPLES WERE COLLECTED AT 2 INDICATOR LOCATIONS AND 1 CONTROL LOCATION. ANIMAL FEED WAS COLLECTED SEMI-ANNUALLY AND WILDLIFE FEED WAS COLLECTED ANNUALLY. l COLLECTION AND ANALYSIS ANIMAL FEED WAS COLLECTED TWICE DURING THE YEAR FROM ONE INDICATOR LOCATION (T-8) AND ONE CONTROL LOCATION (T-34). g CATTLEFEED WAS COLLECTED DURING THE FIRST QUARTER AND GRASS WAS COLLECTED DURING THE THIRD QUARTER. ALSO A SAMPLE OF SMARTWEED WAS COLLECTED FROM LOCATION T-31 (0N-SITE). FOUR TO SIX POUNDS OF SAMPLE WERE COLLECTED IN PLASTIC BAGS AND SHIPPED TO THE LABORATORY FOR A GAMMA SPECTRAL ANALYSIS. RESULTS IN GRASS, SMARTWEED, AND SILAGE THE ONLY GAMMA-EMITTING ISOTOPE DETECTED WAS POTASSIUM-40. P0 TASS!UM-40 IS A NATURALLY OCCURRING RADIONUCLIDE. THE ANNUAL AVERAGE K-40 CONCENTRATION FOR THE CONTROL LOCATION T-34 WAS 5.29 PCI/G WET WEIGHT COMPARED TO THE AVERAGE VALUE OF 9.89 PCI/G WET WEIGHT FOR INDICATOR LOCATIONS. ALL OTHER GAMMA-EMITTING ISOTOPES WERE BELOW THEIR LLDS. 9

A (s-) SQ1L ANALYSIS OF THE SOIL PROVIDES A MEA'SURr. DENT OF RADIONUCLIDE DEPOSITION FROM THE ATMOSPHERE. S01' ANALYSIS ALSO AIDS IN EVALUATING TRENDS OF LONG-TERM ACCUhULATION IN THE ENVIRONMENT. NATURALLY OCCURRING RADIONUCLIDES (URAN!UM, THORIUM) AS WELL AS FALLOUT RADIONUCLIDES (COBALT, STRON-TIUM) ARE EXPECTED TO BE PRESENT IN THESE SAMPLES. SOIL SAMPLES WERE COLLECTED ANNUALLY AT 6 INDIC ATOR LOCA-T!ONS WITHIN 3 MILES OF THE SITE'AND AT 5 CONTROL STATIONS MORE THAN 5 MILES AWAY. COLLECTION AND ANALYSIS SOIL SAMPLES WERE COLLECTED FROM ALL ELEVEN AIR SAMPLING LOCATIONS; SIX INDICATOR LOCATIONS (T-1, T-2, T-3, T-4, T-7 AND T-8) AND FIVE CONTROL LOCATIONS (T-9, T-11, T-12, T-23, AND T-27). ENVIRONMENTAL COMPLIANCE PERSONNEL CAREFULLY CHECKED EACH AREA AND CHOOSE A PROPER SAMPLING SITE, UNDIS-TURBED AND WITH LITTLE VEGETATION. APPROXIMATELY 5 POUNDS OF SOIL WAS TAKEN FROM THE TOP TWO INCHES OF SOIL AT THE SITE. THE SOIL WAS SEALED IN A PLASTIC BAG AND SHIPPED TO O' - THE CONTRACTOR LABORATORY. GAMMA SPECTRAL ANALYSES WERE PERFORMED ON ALL SAMPLES. RESULTS Soll SAMPLES WERE COLLECTED.!N JUNE 1986 AND ANALYZED FOR GAMMA-EMITTING ISOTOPES. THE PREDOMINANT ACTIVITY WAS DUE TO POTASSIUM-40 WHICH HAD AN AVERAGE VALUE OF 11.8 PCI/G DRY WEIGHT AT THE INDICATOR LOCATIONS AND 16.2 PCI/G DRY WEIGHT AT THE CONTROL LOCATIONS. SINCE THE CONTROL LOCATIONS SHOWED HIGHER LEVELS OF POTASSIUM-40 THAN THE INDICATOR STATIONS, THIS MEANS THAT ALL LOCATIONS ARE MEASURING ONLY NORMALLY PRESENT BACKGROUND RADIOACTIVITY. CES!UM-137 CONCENTRATION WAS ABOVE THE LLD OF 0.57 PCl/G IN NINE OF THE ELEVEN SAMPLES. THE AVERAGE CONCENTRATION AT THE INDICATOR LOCATIONS WAS 0.52 PCl/G DRY WEIGHT AND 0.51 PCI/G DRY WEIGHT AT THE CONTROL LOCATIONS. THE HIGHEST CES!UM-137 CONCENTRATION, 1.01 PCl/G, WAS DETECTED AT THE CONTROL LOCATION T-23, 23.5 MILES WNW OF THE STATION. THE LEVEL OF CONCENTRATION AND THE DISTRIBUTION PATTERN WERE SIMILAR TO THOSE OBSERVED IN 1978 THROUGH 1985. THE LACK OF SIGNIF-ICANT CHANGE OVER THE YEARS IS EVIDENCE OF THE NEGLIGIBLE () IMPACT OF DAVIS-BESSE ON THE ENVIRONMENT IN TERMS OF RADIOACTIVITY. GREEN LEAFY VEGETABLES llh GREEN LEAFY VEGETABLES WERE COLLECTED MONTHLY AT 3 LOCATIONS DURING THE GROWING AND HARVEST SEASON. THESE VEGETABLES WERE ANALYZED BECAUSE THEY ARE A DIRECT PATHWAY TO MAN SHOULD THERE BE ANY RADIONUCLIDES PRESENT. COLLECTION AND ANALYSIS MONTHLY, DURING THE HARVEST SEASON (JULY, AUGUST, SEPTEM-BER), GREEN LEAFY VEGETABLES WERE COLLECTED FROM ONE INDICA-TOR LOCATION (T-36) AND ONE CONTROL LOCATION (T-37). 10-15 POUNDS WERE COLLECTED, DEPENDING ON THE WATER CONTENT OF THE SAMPLE. THE SAMPLES WERE SEALED IN PLASTIC BAGS TO PREVENT LOSS OF MOISTURE AND SHIPPED ON ICE TO THE LABORATORY. THE SAMPLES WERE ANALYZED FOR IODINE -131 AND OTHER GAMMA EMITTING ISOTOPES. RESULTS GREEN LEAFY VEGETABLES (CABBAGE). COLLECTED DURING HARVEST SEASON WERE ANALYZED FOR 10 DINE-131. ALL RESULTS WERE BELOW THE LLD OF 0.028 PCI/G WET WEIGHT. ALL GAMMA-EMITTING ISOTOPES EXCEPT P0 TASS!UM-40, WHICH IS NATURALLY OCCURRING, WERE BELOW THEIR RESPECTIVE LLDS. POTASSIUM-40 CONCENTRA-TION AVERAGED 3.86 PCl/G WET WEIGHT AND 1,73 PCI/G WET WEIGHT FOR INDICATOR AND CONTROL LOCATIONS, RESPECTIVELY. THESE LEVELS ARE ALMOST IDENTICAL TO THOSE SEEN IN PREVIOUS YEARS. IN 1985, POTASSIUM-40 CONCENTRATION AVERAGED 3.85 PCl/G WET WEIGHT AND 2.07 PCI/G WET WEIGHT FOR INDICATOR AND CONTROL LOCATIONS RESPECTIVELY. O () AQUATIC MONITORING LAKE ERIE'IS A WIDELY USED SOURCE FOR DRINKING WATER, FISHING AND RECREATIONAL ACTIVITIES. HENCE, IT IS CLOSELY MONITORED BY DAVIS-BESSE FOR RADIONUCLIDES. THE MAIN EXPOSURE PATHWAY TO MAN FROM WATERBORNE RADIONUCLIDES IS THROUGH THE CONSUMPTION OF DRINKING WATER, FISH, AQUATIC WILDLIFE, AND IRRIGATED CROPS. HENCE, SAMPLES OF TREATED (DRINKING) WATER AND UNTREATED WATER WERE COLLECTED, ALSO, SEDIMENTS FROM THE LAKE BOTTOM WERE COLLECTED TO PROVIDE AN INDICATION OF THE ACCUMULATION OF RADIONUCLIDES WHICH MAY AFFECT PEOPLE THROUGH AQUATIC SPECIES, RESUSPENSION INTO DRINKING WATER SUPPLIES AND EXTERNAL RADIATION EXPOSURE TO PEOPLE IN THE WATER (SWIMMERS, BOATERS). DAVIS-BESSE COLLECTED TREATED AND UNTREATED SURFACE WATER, FISH, AND LAKE BOTTOM SEDIMENT SAMPLES. THE RESULTS OF ANALYSES OF THESE SAMPLES SHOW THAT THE OPERATION OF DAVIS-BESSE HAD NO DETECTABLE EFFECTS ON THE AQUATIC ENVIRONMENT. TREATED SURFACE WATER TREATED SURFACE (DRINKING) WATER SAMPLES WERE COLLECTED AND O ANALYZED TO DETERMINE THE EFFECT OF DAVIS-BESSE ON THE WATER BEING CONSUMED. COLLECTION AND ANALYSIS TREATED SURFACE WATER USED FOR DRINKING WAS COLLECTED AT THREE LOCATIONS ON LAKE ERIE (T-11, T-12, AND T-28). ONE LOCATION IS ON-SITE (T-28, UNIT 1 TRE?TED WATER SUPPLY) AND THE OTHER TWO ARE PUBLIC WATER SUPPLIERS (PORT CLINTON AND TOLEDO FILTRATION PLANTS). ONE QUART OF WATER WAS COLLECTED WEEKLY FROM EACH LOCATION IN A CLEAN, UNUSED PLASTIC CONTAINER. THE WATER SAMPLES WERE THEN SENT TO THE ANALYTICAL LABORATO-RY AND WERE COMPOSITED MONTHLY.AND ANALYZED FOR GROSS BETA IN DISSOLVED AND SUSPENDED FRACTIONS. THE SAMPLES FROM EACH LOCATION WERE COMBINED QUARTERLY AND A TRITIUM ANALYSIS WAS PERFORMED, ALSO, GAMMA SPECTRAL AND STRONTIUM-89 AND 90 ANALYSES WERE PERFORMED ON QUARTERLY COMPOSITES OF THE INDICATOR SAMPLES (T-28) AND THE TWO COMBINED CONTROL SAMPLES (T-11 AND T-12). GAMMA SPECTRAL ANALYSES WOULD BE PERFORMED ON INDIVIDUAL SAMPLES IF GROSS BETA CONCENTRATION IN ANY SINGLE SAMPLE WAS GREATER THEN 10 PCI/L. NO SAMPLES () REACHED THIS LEVEL. l l RESULTS A TOTAL OF 156 TREATED WATER SAMPLES WERE COLLECTED AND ANALYZED IN 1986. IN TREATED WATER SAMPLES, THE GROSS BETA ACTIVITY IN SUSPENDED SOLIDS WAS BELOW THE LLD OF 0.7 PCI/L IN ALL SAMPLES. THE AVERAGE GROSS BETA CONCENTRATION IN DISSOLVED SOLIDS WAS NEARLY IDENTICAL AT INDICATOR AND CONTROL LOCATIONS (2.1 AND 2.3 PCI/L, RESPECTIVELY). THE VALUES ARE SIMILAR TO THOSE MEASURED IN 1975 THROUGH 1985. A COMPARISON OF THE RESULTS FOR THE CONTROL AND INDICATOR STATIONS SHOWS ALMOST IDENTICAL RESULTS. TRITIUM ACTIVITY WAS BELOW THE LOWER LIMIT OF DETECTION IN ALL SAMPLES. STRONTIUM-89 AND STRONTIUM-90 CONCENTRATIONS WERE BELOW THE LLD LEVELS OF 1.2 PCI/L AND 1.1 PCI/L, RESPECTIVELY, IN ALL SAMPLES. CESIUM-137 LEVEL WAS BELOW THE LLD OF 10 PCI/L IN ALL SAMPLES. SIMILAR RESULTS WERE OBTAINED IN 1979 THROUGH 1985. O O t I i'M (m,) UNTREATED SURFACE WATER THE DIRECTION OF MOVEMENT OF WATER IN LAKE ERIE IN THE VICINITY OF THE PLANT IS NOT CONSTANT - THERE IS NO UPSTREAM OR DOWNSTREAM DIRECTION. WATER SAMPLES WERE TAKEN IN THE AREAS OF THE PLANT INTAKE AND DISCHARGE AND AT THE DESIGNAT-ED WATER INTAKE USED BY THE SURROUNDING POPULATIONS FOR DRINKING AND OTHER PURPOSES. THESE SAMPLES WOULD PROVIDE THE FIRST INDICATION OF RADI0 ACTIVE EFFLUENT LEAKAGE INTO THE ENVIRONMENT FROM ANY STATION DISCHARGE. COLLECTION AND ANALYSIS UNTREATED (RAW) SURFACE WATER WAS COLLECTED FROM TWO LOCA-TIONS ON-SITE AND FROM THREE PUBLIC WATER SUPPLIERS IN ORDER TO DETECT ANY INCREASES ABOVE BACKGROUND. WEEKLY, ONE QUART SAMPLES OF UNTREATED WATER FROM LAKE ERIE WERE COLLECTED FROM ONE INDICATOR LOCATION (T-3) AND ONE CONTROL LOCATION (T-11). WEEKLY COMPOS'ITE SAMPLES WERE COLLECTED FROM A SECOND CONTROL LOCATION (T-12) AND A SECOND INDICATOR LOCATION (T-50). SAMPLES AT LOCATIONS T-11, T-12, AND T-50 WERE COLLECTED FROM UNTREATED WATER TAPS AT PORT CLINTON, (~N TOLEDO, AND ERIE INDUSTRIAL PARK FILTRATION PLANTS. IN ADDITION, MONTHLY COMPOSITE SAMPLES WERE COLLECTED FROM ONE IN-PLANT WATER SUPPLY (T-28, UNIT 1 UNTREATED WATER SUPPLY, ON-SITE). SAMPLES WERE COLLECTED IN NEW, CLEAN PLASTIC CONTAINERS AND SHIPPED TO THE LABORATORY FOR ANALYSIS. THE SAMPLES FROM EACH LOCATION WERE COMPOSITED MONTHLY AND ANALYZED FOR GROSS BETA ACTIVITY IN DISSOLVED AND SUSPENDED 3 FRACTIONS. QUARTERLY COMPOSITES FROM COMBINED INDICATOR AND COMBINED CONTROL LOCATIONS WERE GAMMA SCANNED AND ANALYZED FOR STRONTIUM-89 AND -90. TRITIUM ANALYSIS WAS PERFORMED ON QUARTERLY COMPOSITES FROM EACH LOCATION. GAMMA SPECTRAL ANALYSES WOULD BE PERFORMED ON INDIVIDUAL SAMPLES IF GROSS BETA CONCENTRATION IN ANY SINGLE SAMPLE WAS GREATER THAN 10 PCI/L. HOWEVER, SAMPLES DID NOT REACH THIS LEVEL. t 4 - . _ , - _ . ._ . . . _ . . _ . _ _ . ~ _ . . , , . - . _ . . - . - . . .

RESULTS lh IN UNTREATED WATER SAMPLES, THE AVERAGE GROSS BETA CONCEN-TRATION IN SUSPENDED SOLIDS AVERAGED 1.0 PCI/L AT INDICATOR LOCATIONS AND 1.4 PCI/L AT CONTROL LOCATIONS. IN DISSOLVED SOLIDS THE AVERAGE CONCENTRATION WAS IDENTICAL AT BOTH INDICATOR AND CONTROL LOCATIONS (2.8 PCI/L). FOR TOTAL RESIDUE, THE AVERAGE CONCENTRATIONS WERE 2.9 PCI/L AT INDICATOR LOCATIONS AND 2.8 PCI/L AT CONTROL LOCATIONS. NONE OF THESE RESULTS SHOW STATISTICALLY SIGN 171 CANT DIFFER-ENCES BETWEEN INDICATOR AND CONTROL LOCATIONS. THE TRITIUM CONCENTRATION WAS BELOW THE LOWER LIMIT OF DETECTION IN ALL SAMPLES. STRONTIUM-89 CONCENTRATION WAS BELOW THE LLD OF 2.7 PCI/L IN ALL SAMPLES. STRONTIUM-90 CONCENTRATION WAS BELOW THE LLD OF 1.7 PCI/L IN ALL SAMPLES. CESIUM-137 CONCENTRATION WAS BELOW THE LLD OF 10.0 PCI/L FOR ALL LOCATIONS. THESE RESULTS SHOW NO EFFECT ON AREA WATER FROM DAVIS-BESSE. FISH FISH PROVIDE AN INDICATION OF THE RADIONUCLIDES CONSUMED BY HUMANS AS WELL AS THE AMOUNT OF RADIOACTIVITY IN THE ECOSYSTEM. COLLECTION AND ANALYSIS FISH SAMPLES WERE COLLECTED SEMIANNUALLY IN LAKE ERIE IN THE VICINITY OF THE SITE AND FROM A LOCATION GREATER THAN 10 MILES FROM THE SITE. THE SAMPLING METHOD FOR FISH DEPENDS ON THE SPECIES OF FISH TO BE COLLECTED, LOCATION, AND TIME OF THE YEAR. SHORE SEINES, NETS, FISH TRAPS OR HOOK AND LINE ARE USED TO OBTAIN FISH SAMPLES. COMMERCIAL FISHERMEN OR SPORT FISHERMEN WERE UTILIZED TO OBTAIN SAMPLES. THE SAMPLES ARE COLLECTED IN SUCH A MANNER TO ENSURE THE FISH'WERE FRESH AND THE REQUIRED l INFORMATION (SUCH AS SPECIES, DATE AND LOCATION OF COLLEC-l TIOM! WERE PROVIDED. til _ _ _____________ s

1 2

.O         TWO SPECIES OF FISH (WHITE BASS AND WALLEYE) WERE COLLECTED SEMIANNUALLY FROM EACH OF TWO LOCATIONS IN LAKE ERIE; ONE INDICATOR LOCATION IN THE VICINITY OF THE DISCHARGE (T-33)

AND ONE CONTROL LOCATION GREATER THAN 10 MILES FROM THE PLANT (T-35). 5 - 10 POUNDS OF EACH SPECIES WERE COLLECTED AT EACH LOCATION AND SEALED IN PLASTIC BAGS AND LABELED. THE FISH WAS SHIPPED IMMEDIATELY, ON ICE, TO THE LABORATORY. ! THE FLESH WAS SEPARATED FROM THE BONES AND ANALYZED FOR GROSS BETA AND GAMMA EMITTING ISOTOPES. RESULTS THE MEAN GROSS BETA CONCENTRATION IN FISH MUSCLE WAS SIMILAR FOR INDICATOR AND CONTROL LOCATIONS (3.04 AND 3.92 PCI/G WET WEIGHT, RESPECTIVELY). SINCE THE CONTROL (BACKGROUND) LOCATIONS SHOW HIGHER LEVELS THAN THE INDICATOR LOCATIONS, ONLY BACKGROUND ACTIVITY IS BEING DETECTED. x THE PREDOMINANT GAMMA-EMITTING ISOTOPE DETECTED WAS NATURALLY- ! OCCURRING POTASSIUM-40. THE AVERAGE POTASSIUM-40 CONCEN-TRATION WAS 2.85 PCI/G WET WEIGHT FOR THE INDICATOR LOCATION AND 2.64 PCI/G WET WEIGHT FOR THE CONTROL LOCATION. CESIUM-137 CONCENTRATION WAS BELOW THE LLD LEVEL OF 0.037 PCI/G WET WEIGHT IN ALL SAMPLES. THE LEVELS OF CONCENTRA-

TION WERE SIMILAR TO THOSE OBSERVED IN 1978 THROUGH 1985.

BOTTOM SEDIMENTS BOTTOM SEDIMENT SAMPLES WERE TAKEN TO DETERMINE THE BUILDUP l OF RADIONUCLIDES WHICH MIGHT RESULT FROM SOLIDS PRECIPITAT-ING IN THE LAKE (BUILDUP OF RADI0 ACTIVITY ON THE LAKE BOTTOM). COLLECTION AND ANALYSIS BOTTOM SEDIMENT SAMPLES WERE COLLECTED SEMIANNUALLY AT THREE i.0 CATIONS IN LAKE ERIE: AT TWO INDICATOR LOCATIONS, INTAKE (T-29) AND DISCHARGE (T-30), AND AT ONE CONTROL LOCATION ABOUT 5.3 MILES WNW FROM THE PLANT (T-27). THEY WERE COLLECTED USING A SHOVEL, AN EMORY DREDGE OR SIMILAR DEVIC-4 ES. SAMPLES WERE TAKEN FROM THE LAKE BOTTOM UNTIL AT LEAST 4 POUNDS HAD BEEN COLLECTED AT EACH LOCATION.

THE SAMPLES WERE ANALYZED FOR GROSS BETA ACTIVITY, STRONTIUM

 -89 AND 90 AND GAMMA SCANNED TO IDENTIFY AND QUANTIFY GAMMA EMITTING RADIONUCLIDES.

RESULTS THE AVERAGE GROSS BETA CONCENTRATION IN BOTTOM SEDIMENTS WAS 24.1 PCI/G DRY WEIGHT FOR INDICATOR LOCATIONS AND 18.8 PCI/G DRY WEIGHT FOR THE CONTROL LOCATION. THE LOCATION WITH THE HIGHEST AVERAGE WAS INDICATOR LOCATION T-29 (27.7 PCI/G DRY WEIGHT). INDICATOR LOCATION T-29 HAD THE HIGHEST AVERAGE POTASSIUM-40 CONCENTRATION (19.6 PCI/G DRY WEIGHT) WHICH WAS THE MAJOR CONTRIBUTOR TO THE GROSS BETA ACTIVITY AT ALL LOCATIONS. STRONTIUM-90 WAS DETECTED IN THREE SAMPLES AND AVERAGED 0.030 PCI/G DRY WEIGHT AND 0.017 PCI/G DRY WEIGHT AT INDICA-TOR AND CONTROL LOCATIONS. THE CONCENTRATION OF STRONTIUM-89 WAS BELOW THE LLD LEVEL OF 0.024 PCI/G DRY WEIGHT IN ALL SAMPLES. CESIUM-137 WAS NOT DETECTED IN ANY OF THE SIX SAMPLES ABOVE THE LLD LEVEL OF 0.049 PCI/G DRY WEIGHT. SIMILAR LEVELS, DISTRIBUTION AND COMPOSITION OF DETECTED RADIONUCLIDES WERE lll DETECTED IN 1978 THROUGH 1985. ANALYSIS OF BOTTOM SEDIMENT SAMPLES COLLECTED IN 1986 PRODUCED RESULTS COMPARABLE TO THOSE OBTAINED IN PREVIOUS YEARS. t l () CONCLUSION OVER 2600 ANALYSES WERE PERFORMED ON ENVIRONMENTAL SAMPLES IN 1986. THE RESULTS OF THESE ANALYSES SHOW ONLY BACKGROUND-LEVEL RADI0 ACTIVITY IN ALL SAMPLES COLLECTED. THERE WAS SOME EFFECT ON ENVIRONMENTAL RADI0 ACTIVITY RESULT-ING FROM THE NUCLEAR ACCIDENT AT CHERNOBYL ON APRIL 26,

 ,    1986. LOW LEVELS OF l-131, RU-103, RU-106, CS-134 AND CS-137 WERE DETECTED IN THE AIR AND l-131 WAS DETECTED IN MILK SAMPLES COLLECTED DURING MAY, JUNE AND JULY, 1986.

THE RESULTS OF RADIOLOGICAL ENVIRONMENTAL MONITORING AT DAVIS-BESSE IN 1986 SHOW THAT THE OPERATION OF DAVIS-BESSE HAD NO ADVERSE EFFECT ON THE QUALITY OF THE ENVIRONMENT. O .I O 1

() REFERENCES ANSI N545-1975, " PERFORMANCE, TESTING AND PROCEDURAL SPECIFICATIONS FOR THERM 0 LUMINESCENCE DOSIMETRY," AMERICAN NATIONAL STANDARDS INSTITUTE, INC., 1430 BROADWAY, NEW YORK, NEW YORK 10018 "CHERNOBYL' SEQUENCE OF EVENTS," INFO REPRINT, ATOMIC INDUS TRIAL FORUM, INC., BETHESDA, MARYLAND, AUGUST 21, 1986. DETROIT EDISON, "PREOPERATIONAL ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM AT FERMI-2, ANNUAL REPORT," NUS CORPORATION, PITTSBURG, PENNSYLVANIA, 1983. DOE EP-0023 "A GUIDE FOR ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE AT U.S. DEPARTMENT OF ENERGY INSTALLA-TIONS," DEPARTMENT OF ENERGY, WASHINGTON, D.C., 1981. KIRK, T. J. AND G. N. MIDKIFF, HEALTH PHYSICS FUNDAMENTALS, GENERAL PHYSICS CORPORATION, 1980. LINNEMANN, R. E., " RUSSIAN MEDICAL RESPONSE TO CHERNOBYL," O' CURIE-0SITY, VOLUME 3, NUMBER 3, DECEMBER, 1986. MILLER JR. F., COLLEGE PHYSICS, HARCOURT, BRACE, AND WORLD, NEW YORK, NEW YORK, 1959.

    " NUMERICAL GUIDES FOR DESIGN OBJECTIVES AND LIMITING CONDITIONS FOR OPERATION TO MEET THE CRITERION 'AS LOW AS IS REASONABLY ACHIEVABLE' FOR RADI0 ACTIVE MATERIAL IN LIGHT-WATER COOLED NUCLEAR POWER REACTOR EFFLUENTS,"

CODE OF FEDERAL REGULATIONS, TITLE 10 ENERGY, PART 50

          " DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES," APPENDIX I, 1986.

REGULATORY GUIDE 4.1, " PROGRAMS FOR MONITORING RADI0 ACTIVITY IN THE ENVIRONS OF NUCLEAR POWER PLANTS," US NRC, APRIL, 1975. REGULATORY GUIDE 4.13, " PERFORMANCE, TESTING, AND PROCEDURAL SPECIFICATIONS FOR THERM 0 LUMINESCENCE DOSIMETRY: ENVIRONMENTAL APPLICATIONS," US NRC, JULY, 1977. i

REGULATORY GUIDE 4,15, " QUALITY ASSURANCE FOR RADIOLOGICAL MONITORING PROGRAMS (NORMAL OPERATIONS) - EFFLUENT STREAMS AND THE ENVIRONMENT," US NRC, FEBRUARY, 1979. REGULATORY GUIDE 0475, " RADIOLOGICAL ENVIRONMENTAL MONITOR ING BY NRC LICENSES FOR ROUTINE OPERATIONS OF NUCLEAR FACILITIES," US NRC, SEPTEMBER, 1978. REGULATORY GUIDE 0837, "NRC TLD DIRECT RADIATION MONITORING NETWORK," VOLUME 5, NUMBER 4, US NRC, DECEMBER 1985. "S0VIET NUCLEAR ACCIDENT: U.S. SCRUTINIZES FALLOUT, OTHER EFFECTS," CHEMICAL AND ENSINEERING NEWS, VOLUME 64, NUMBER 19, MAY, 1986. " STANDARDS FOR PROTECTION AGAINST RADIATION," CODE OF FEDERAL REGULATIONS, TITLE 10, ENERGY, PART 20, 1986. TELEDYNE ISOTOPES MIDWEST LABORATORY, "0PERATIONAL RADIOLOGICAL MONITORING FOR THE DAVIS-BESSE NUCLEAR POWER STATION UNIT NO, 1, OAK HARBOR, OH," ANNUAL REPORT, PARTS I AND II, 1983, ggg

         , "0PERATIONAL RADIOLOGICAL MONITORING FOR THE DAVIS-BESSE NUCLEAR POWER STATION UNIT NO, 1, OAK HARBOR, OH," ANNUAL REPORT, PARTS I AND II, 1984.
         , "0PERATIONAL RADIOLOGICAL MONITORING FOR THE DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1, OAK HARBOR, OH," ANNUAL REPORT, PARTS I AND II, 1985,
        -, "CPERATIONAL RADIOLOGICAL MONITORING FOR THE DAVIS-BESSE NUCLEAR POWER STATION UNIT NO, 1, 0AK HARBOR, OH," ANNUAL REPORT, PARTS I AND II, 1986.

TOLEDO EDISON COMPANY, " DAVIS-BESSE: NUCLEAR ENERGY FOR NORTHERN OHIO."

         , " DAVIS-BESSE NUCLEAR POWER STATION UNIT No. 1, RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS," VOLUME 1, APPENDIX A TO LICENSE NO. NPF-3, AMENDMENT 95, O

l n V TOLEDO EDISON COMPANY, " ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM," ST 5099.03, REVISION 13, 1986.

                          " FINAL ENVIRONMENTAL STATEMENT - RELATED TO THE CONSTRUCTION OF DAVIS-BESSE NUCLEAR POWER STATION,"

DOCKET #50-346, 1973.

                          " PERFORMANCE SPECIFICATIONS FOR RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM," S-720, REVISION 1, 1986.
                          " SEMIANNUAL RADIOACTIVE LIQUID AND GASEOUS RELEASE REPORT," JANUAR't 1 - JUNE 30,1986.
                       ,  " SEMIANNUAL RADI0 ACTIVE LIQUID AND GASEOUS RELEASE REPORT," JULY l - DECEMBER 31, 1986.
                          " UPDATED SAFETY ANALYSIS FOR THE OFF-SITE RADIOLOGICAL MONITORING PROGRAM, USAR 11.6, REVISION 4, 1985, ps WILSON,         R., "CHERNOBYL: ASSESSING THE ACCIDENT,"

ISSUES IN SCIENCE AND TECHNOLOGY, FALL, 1986. r APPROXIMATELY 5 YEARS OF RADIOLOGICAL MONITORING WERE COMPLETED PRIOR TO THE OPERATION OF DAVIS-BESSE. FOR EACH YEAR AN ANNUAL ENVIRONMENTAL REPORT WAS PREPARED AND SUBMIT-TED TO THE NRC. THESE REPORTS CONTAIN A VAST WEALTH OF DATA ON THE NORMAL LEVELS OF RADI0 ACTIVITY IN THE AREA AND HAVE BEEN USED FOR COMPARISON PURPOSES IN THIS REPORT. THIS RE, PORT PRESENTS THE NINTH' FULL YEAR OF OPERATIONAL DATA FOR ENVIRONMENTAL RADIOLOGICAL MONITORING AT DAVIS-BESSE., REPORTS OF PAST YEARS WERE USED FOR DATA COMPARISON. THESE REPORTS INCLUDE: o PREOPERATIONAL ENVIRONMENTAL MONITORING PROGRAMS UP THROUGH 1977, e ANNUAL ENVIRONMENTAL OPERATING REPORTS FOR 1977 THROUGH 1985. l l i i

O (THIS PAGE INTENTIONALLY LEFT BLANK) O l l Ol i

O i APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS 4 O d I i t O A-1

  ,      --o----- - , , , -    ,r--,----------w.---,,.,v,w,-..w.v--,.c                       ._     -------------.---...e---------w,--.---e.e---

O Appendix A Interlaboratory Comparison Program Results Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of its quality control program in December 1971. These programs are operated by agencies which supply environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems.

Participant laboratories measure the concentrations of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits._ Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used. The results in Table A-1 were obtained through participation in the environ-mental sample crosscheck program for milk, water, air filters, and food samples during the period May 1984 through November 1986. This program has been conducted by the U. S. Environmental Protection Agency Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring - and

Support Laboratory, Las Vegas, Nevada.

l The results in Table A-2 were obtained for thermoluminescent dosimeters (TLD's) during the period 1976, 1977, 1979, 1980, and 1981 through parti-cipation in the Second, Third, Fourth, and Fif th International Intercomparison - of Environmental Dosimeters under the sponsorships listed in Table A-2. Table A-3 lists results of the analyses on in-house spiked samples. l Table A-4 lists results of the analyses on in-house " blank" samples. I i i O j . A-2

    ,-,,,-,-,,,,--e-e.,-,-    -w,-----,,-       --,-----w------,-,,c----,,--,-..--,-w

Table A-1. U.S. Environmental Protection Agency's crosscheck program, com-parison of EPA and Teledyne Isotopes Midwest Laboratory results for milk, water, air filters, and food samples, 1984 through 1986.a Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis ibc fla, n=3d STW-358 Water May 1984 Gross alpha 3.010.6 318.7 Gross beta 6.7tl.2 618.7 STM-366 Milk June 1984 Sr-89 2113.1 2518.7 Sr-90 1312.0 1712.6 I-131 4615.3 43t10.4 Cs-137 3814.0 3518.7 K-40 15771172 14961130 STW-368 Water July 1984 Gross alpha 5.1tl.1 618.7 Gross beta 11.912.4 1318.7 STW-369 Water August 1984 I-131 34.315.0 34.0110.4 STW-370 Water August 1984 H-3 30031253 28171617 STF-371 Food July 1984 Sr-89 22.015.3 25.018.7 Sr-90 14.713.1 20.012.6 I-131 <172 39.0110.4 Cs-137 24.015.3 25.018.7 K-40 25031132 26051226.0 l STAF-372 Air August 1984 Gross alpha 15.311.2 1718.7 Filter Gross beta 56.010.0 5118.7 Sr-90 14.311.2 1812.4 Cs-137 21.012.0 1518.7 l STW-375 Water Sept. 1984 Ra-226 5.110.4 4.911.27 Ra-228 2.210.1 2.310.60 STW-377 Water Sept . 1984 Gross alpha 3.311.2 5.018.7 Gross beta 12.712.3 16.018.7 1 STW-379 Water Oct. 1984 H-3 28601312 28101356 STW-380 Water Oct. 1984 Cr-51 <36 4018.7 Co-60 20.311.2 2018.7 l Zn-65 150t8.1 14718.7 Ru-106 <30 4718.7 Cs-134 31.317.0 3118.7 Cs-137 26.711.2 2418.7 A-3

t Table A-1. (continued)

Concentration in >C1/lb Lab Sample- Date TIML Result EPA tesult Code Type Collected Analysis ibc tio,n=3d STM-382 Milk Oct. 1984 Sr-89 15.7t4.2 22*8.7 Sr-90 12.7*1.2 16*2.6 I-131 41.713.1 42*10.4 Cs-137 31.3*6.1 3218.7 K-40 1447*66 1517*131 STW-384 Water Oct. 1984 Gross alpha 9.7*1.2 14*8.7 (Blind) Sample A Ra-226 3.310.2 3.0t0.8 Ra-228 3.4tl.6 2.1*0.5 Uranium nae 5t10.4 Sample 8 Gross beta 48.315.0 64f8.7 Sr-89 10.714.6 11i8.7 Sr-90 7.311.2 12t2.6 Co-60 16.311.2 14*8.7 Cs-134 <2 2t8.7 Cs-137 16.7tl.2 14*8.7 Air Nov. 1984 Gross alpha 18.711.2 15t8.7 O STAF-387 Filter Gross beta 59.0*5.3 52*8.7

,                                                       Sr-90          18.311.2       21i2.6 10.311.2 4

Cs-137 10*8.7-STW-388 Water Dec. 1984 I-131 28.0i2.0 36i10.4 STW-389 Water Dec. 1984 -H-3 3583i110 31821624 STW-391 Water Dec. 1984 Ra-226 8.411.7 8.6*2.2 Ra-228 3.110.2 4.1*1.1 STW-392 Water Jan. 1985 Sr-89 <3.0 3.018.7 Sr-90 27.315.2 30.0*2.6 l STW-393 Water Jan. 1985 Gross alpha 3.3*1.2 518.7 l Gross beta 17.3t3.0 1518.7 STS-395 Food Jan. 1985 Gross alpha 4.712.3 6.018.7 Gross beta 11.311.2 15.0i8.7 Sr-89 25.316.4 34.018.7 Sr-90 27.018.8 26.0t2.6 I-131 38.012.0 35.0 10.4 Cs-137 32.712.4 29.018.7 l K-40 1410*212 1382i208 i O A-4 l l l . . _ _ . - ._ _. _ _.. _ _ _ _ -

I Table A-1. (continued) Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis 12ac *b. n=3d STW-397 Water Feb. 1985 Cr-51 <29 4818.7 Co-60 21.3i3.0 2018.7 Zn-65 53.7i5.0 5518.7 Ru-106 <23 25i8.7 Cs-134 32.311.2 35i8.7 Cs-137 25.3*3.0 2518.7 STW-398 Water Feb. 1985 H-3 3869t319 3796i634 STM-400 Milk March 1985 I-131 7.3*2.4 9.011.6 STW-402 Water March 1985 Ra-226 4.610.6 5.0il.3 Ra-228 <0.8 9.012.3 Reanalysis Ra-228 9.0i0.4 STW-404 Water March 1985 Gross alpha 4.712.3 618.7 Gross beta 11.311.2 1518.7 STAF-405 Air March 1985 Gross alpha 9.311.0 10.018.7 O Filter Gross beta 42.011.1 36.018.7 Sr-90 13.3*1.0 15.0*2.6 Cs-137 6.311.0 6. 0i8. 7 STW-407 Water April 1985 I-131 8.010.0 7.5tl.3 STW-408 Water April 1985 H-3 33991150 35591630 STW-409 Water April 1985 (Blind) Gross alpha 29.711.8 32.018.7 Sample A Ra-226 4.410.2 4.111.0 Ra-228 nae 6.2il.6 Uranium nae 7.0110.4 Sample 8 Gross beta 74.3111.8 72.018.7 Sr-89 12.3t7.6 10.018.7 Sr-90 14.7 2.4 15.0i2.6 Co-60 14.712.4 15.018.7 Cs-134 12.012.0 15.018.7 Cs-137 14.0t2.0 12.018.7 O A-5

Table A-1. (continued) Concentration in 2Ci/lb Lab Sample Date TIML Result EPA .tesult Code Type Collected Analysis *2aC ilo, n=3d STW-413 Water May 1985 Sr-89 36.0t12.4 39.0 8.7 Sr-90 14.3*4.2 15.0t2.6 STW-414 Water May 1985 Gross alpha 8.3*4.1 12.0*8.7 Gross beta 8.7*1.2 11.0*8.7 j STW-416 Water June 1985 Cr-51 44.716.0 44.018.7 Co-60 14.3tl.2 14.0i8.7 - Zn-65 50.317.0 47.Qt8.7 Ru-106 55.315.8 62.0 8.7 Cs-134 32.7*1.2 35.0i8.7 Cs-137 22.7*2.4 20.0 8.7 STW-418 Water June 1985 H-3 2446*132 2416 609 STM-421 Milk June 1985 Sr-89 10.3*4.6 11.0*8.7 Sr-90 9.0i2.0 11.0t2.6 I-131 11.7tl.2 11.0*10.4

 ; O                                       Cs-137 K-40 12.7tl.2 1512162 11.0i8.7 1525i132 STW-423    Water       July 1985      Gross alpha  5.0i0.0          11.0t8.7 Gross beta   5.0i2.0            8.0*8.7 STW-425    Water       August 1985    1-131       25.7*3.0          33.0*10.4 STW-426    Water       August 1985    H-3         4363*83           4480*776 i

STAF-427 Air August 1985 Gross alpha 11.310.6 13.0i8.7 Filter Gross beta 46.011.0 44.0i8.7 Sr-90 17.710.6 18.0t2.6 Cs-137 10.310.6 8.0i8.7 l STW-429 Water Sept . 1985 Sr-89 15.7f0.6 20.018.7 Sr-90 7.010.0 7.012.6 STW-430 Water Sept . 1985 Ra-226 8.210.3 8.9*2.3

Ra-228 4.110.3 4.6*1.2 l STW-431 Water Sept . 1985 Gross alpha 4.710.6 8.018.7 Gross beta 4.7tl.2 8.0*8.7 iO I

l A-6 l

Table A-1. (continued) h Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis 12aC ilo, n=3d STW-433 Water Oct. 1985 Cr-51 <13 21.018.7 Co-60 19.30.6 20.018.7 Zn-65 19.710.6 19.018.7 Ru-106 <19 20.018.7 Cs-134 17.011.0 20.018.7 Cs-137 19.311.2 20.018.7 STW-435 Water Oct. 1985 H-3 1957150 19741598 - l STW-436 Water Oct. 1985 437 (Blind) Sample A Gross . alpha 53.0*1.0 52.0122.6

                                   -Ra-226         5.9i0.1       6.3tl.6 Ra-228          8.210.1     10.li2.6 Uranium          NA8         8.0110.4 Sample 8                Gross beta Sr-89 85.7f2.5 21.311.5 75.018. 7 27.018.7    h' Sr-90         10.310.6       9.012.6 Co-60          18.311.2     18.0i8.7 Cs-134         16.311.2     18.018.7 Cs-137         19.0*1.0     18.018.7 STM-439     Milk       Oct. 1985    Sr-89          50.310.6     48.018.7 Sr-90          23.310.6     26.0i2.6 I-131         45.713.2     42.0110.4 Cs-137         60.710.6     56.0i8.7 K-40           1547129      1540t134 STW-441     Water       Nov. 1985   Gross alpha     5.310.6     10.018.7 Gross beta     11.711.2     13.0i8.7 STW-443     Water      Dec. 1985     I-131         46.712.1     45.0110.4 STW-444     Water      Dec. 198S    Ra-226          6.510.1       7.111.9 Ra-228          6.1*0.1       7.311.9 STW-445     Water      Jan. 1986    Sr-89          29.712.5     31.018.7 Sr-90          13.710.6     15.012.6 STW-446     Water      Jan. 1986    Gross alpha     3.010.0      3.018.7 Gross beta      5.310.6       7.018.7 A-7

O Table A-1. (continued) Concentration in pC1/lb Lab Sample Date TIML Result EPA tesult

Code Type Collected Analysis 22aC lo, n=3d

.               STW-447                                  Food                                  Jan. 1986      Sr-89                                24.3t2.5                                    25.018.7 Sr-90                                17.3t0.6                                     10.0t2.6 I-131                              22.7*2.3                                     20.0t10.4 Cs-137                               16.3t0.6                                     15.0t8.7 K-40                                927*46                                         950t249 STW-448                                  Water                                 Feb. 1986      Cr-51                               45.0t3.6                                     38.0t8.7 Co-60                                19.7tl.5                                     18.0 8.7 Zn-65                               44.0t3.5                                     40.0t8.7 Ru-106                                      <9. 0                                  0.0t8.7 Cs-134                              28.3t2.3                                     30.018.7 4                                                                                                              Cs-137                              23.7t0.6                                     22.0*8.7

STW-449 Water Feb. 1986 H-3 5176t48 5227t910 i STW-450 Water Feb. 1986' U total 8.0t0.0 9.0t10.4
STW-451 Milk Feb. 1986 I-131 7.0t0.0 9.0t10.4
STW-452 Water March 1986 Ra-226 3.8t0.1 4.1tl.1 Ra-228 11.020.5 12.4*3.2 STW-453 Water March 1986 Gross alpha 6.7t0.6 15.0t8.7 Gross beta 7.3*0.6 8.0t8. 7 STW-454 Water April 1986 I-131 7.0t0.0 9.0t10.4 I

STW-455 Water April 1986

456 (Blind)

Sample A Gross alpha 15.0tl.0 17.0t8.7 Ra-226 3.1*0.1 2.9t0.8 Ra-228 1. 5*0. 2 2. 0t0. 5 Uranium 4.7*0.6 5.0t10.4 Sample B Gross beta 28.7tl.2 35.0t8.7 Sr-89 5.7*0.6 7.0t8. 7 , Sr-90 7.0t0.0 7.0t2. 6 l Co-60 10.721.5 10.028.7 ! Cs-134 4.0tl. 7 5.0t8.7

Cs-137 5.3t0.6 5. 01 8. 7 lO l

1 A-8 l

Table A-1. (continued) Concentration in pCf/lb O Date TIML Result EPA Result Lab Sample ilo, n=3d Code Type Collected Analysis i?ac April 1986 Gross alpha 13.710.6 15.018.7 STAF-457 Air 47.018.7 Filter Gross beta 46.310.6 Sr-90 14.710.6 18.012.6 Cs-137 10.710.6 10.0i8.7 April 1986 Tritium 4313170 44231327 STU-458 Urine Water May 1986 Sr-89 4.310.6 5.0i8.7 STW-459 5.012.6 Sr-90 5.010.0 Water May 1986 Gross alpha 5.310.6 8.018.7 STW-460 Gross beta 11.3tl.2 15.018.7 Water June 1986 Cr-51 <9.0 0.018.7 STW-461 Co-60 66.0i1.0 66.018.7 Zn-65 87.311.5 86.018.7 Ru-106 39.712.5 50.018.7 Cs-134 49.312.5 49.0i8.7 Cs-137 10.311.5 10.018.7 Water June 1986 Tritium 3427*25 31251626 STW-462 Milk June 1986 Sr-89 <1.0 0.0i8.7 STM-464 Sr-90 15.310.6 16.0i2.6 I-131 48.3*2.3 41.0110.4 Cs-137 43.7tl.5 31.0i8.7 K-40 15671114 1600i139 Water July 1986 Gross alpha 4.710.6 6.018.7 STW-465 Gross beta 18.7tl.2 18.0i8.7 Water August 1986 1-131 30.310.6 45.0110.4 STW-467 STW-468 Water August 1986 Pu-239 11.310.6 10.lil.8 Water August 1986 Uranium 4.010.0 4.0110.4 STW-469 STAF-470 Air September 1986 Gross alpha 19.311.5 22.018.7 471 Filter Gross beta 64.012.6 66.018.7 472 Sr-90 22.0t1.0 22.012.6 Cs-137 2$.711.5 22.018.7 Water September 1986 Ra-226 6.010.1 6.111.6 STW-473 Ra-228 8.711.1 9.112.4 A-9

Table A-1. (continued) Concentration in aCi/lb Lab Sample Date TIML Result EPA lesult Code Type Collected Analysis *2ac ilo, n=3d STW-474 Water September 1986 Gross alpha 16.3i3.2 15.0*8.7 Gross beta 9.0tl.0 8.018.7 STW-475 Water October 1986 Cr-51 63.3i5.5 59.018.7 Co-60 31.012.0 31.018.7 Zn-65 87.315.9 85.018.7 Ru-106 74.717.4 74. 018.7 Cs-134 25.710.6 28.018.7 Cs-137 46.311.5 44.018.7 STW-476 Water October 1986 H-3 5918f60 5973i1035 STM-479 Milk November 1986 Sr-89 7.711.2 9.018.7 Sr-90 1.0t0.0 0.0*2.6 I-131 52.313.1 49.0t10.4 Cs-137 45.7i3.1 39.0i8.7 K-40 14891104 15651135 STU-480 Urine November 1986 H-3 5540t26 5257i912 STW-481 Water November 1986 Gross alpha 12.014.0 20.0*8.7 Gross beta 20.013.5 20.0i8.7 a Results obtained by Teledyne Isotopes Midwest Laboratory as a participant in the environmental sample crosscheck program operated by the Intercom-parison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S. Environmental Protection Agency, b (EPA), Las Vegas, Nevada. t All results are in pCi/1, except for elemental potassium (K) data, which are ! in mg/1; air filter samples, which are in pCi/ filter; and food, which is in pCi/kg. c Unless otherwise indicated, the TIML results are given as the mean 12 standard deviations for three determinations. d USEPA results are presented as the known values i control limits of b for n = 3. e NA = Not analyzed. f Analyzed but not reported to the EPA. l 9 Results af ter calculations corrected (error in calculations when reported to j EPA). A-10 l l

Table A-2. Crosscheck program results, thermoluminescent dosimeters (TLDs). mR Teledyne Average 120 d Lab TLD Result Known (all Code Type Measurement 12aa valuec participants) 2nd International Intercomparisonb 115-2 CaF2:Mn Field 17.0il.9 17.1 16.417.7 Bulb Lab 20.814.1 21.3 18.817.6 3rd International Intercomparisone 115-3 CaF2:Mn Field 30.713.2 34.914.8 31.513.0 ? Bulb = Lab 89.616.4 91.7114.6 86.2124.0 4th International Intercomparisonf 115-4 CaF2:Mn Field 14.111.1 14.111.4 16.019.0 Bulb Lab (Low) 9.311.3 12.212.4 12.017.6 Lab (High) 40.411.4 45.819.2 43.9113.2 Sth International Intercomparison9 115-5A CaFg:Mn Field 31.411.8 30.016.0 30.2114.6 Bulb Lab at 77.415.8 75.217.6 75.8 40.4 beginning Lab at 96.615.8 88.418.8 90.7131.2 the end

O O O Table A-2. (Continued) i mR Teledyne Lab TLD Result Avera9e i 2a d Code Type Measurement

2b a Known Valuec (all participants) i 115-5B LiF-100 Field 30.314.8 30.016.0 Chips 30.2114.6 Lab at 81.117.4 75.217.6 beginning 75.8140.4 Lab at 85.4111.7 88.418.8 the end 90.7131.2

{ 7th International Intercomparisonh

     ?                                                          -

G 115-7A LiF-100 Field 75.412.6 Chips 75.816.0 75.1129.8 Lab (Co-60) 80.Di3.5 79.914.0 77.9127.6 Lab (Cs-137) 66.612.5 75.013.8 73.0122.2 115-78 CaF2:Mn Field 71.512.6 75.816.0 75.1129.8 Bulbs Lab (Co-60) 84.816.4 79.914.0 77.9127.6 Lab (Cs-137) 78.811.6 75.013.8 73.0t22.2 115-7C CaSO4 :Dy Field 76.812.7 75.816.0 . Cards 75.1129.8 Lab (Co-60) 82.513.7 79.914.0 77.9127.6 Lab (Cs-137 79.013.2 75.013.8 73.0122.2 i -

Table A-2. (Continued) l mR Teledyne Average i a d Lab TLD Result Known (all Code Type Measurement iba valuec participants) l 8th International Intercomparisoni 115-8A LiF-100 Field Site 1 29.511.4 29.711.5 28.9112.4 Chips Field Site 2 11.310.8 10.410.5 10.119.06 Lab (Cs-137) 13.710.9 17.210.9 16.216.8 115-8B CaF2:Mn Field Site 1 32.311.2 29.711.5 28.9112.4 Bulbs Field Site 2 9.011.0 10.410.5 10.119.0 i y Lab (Cs-137) 15.8i0.9 17.210.9 16.216.8 115-8C CaSO4 :0y Field Site 1 32.310.7 29.711.5 28.9112.4 Cards Field Site 2 10.610.6 10.410.5 10.119.0 Lab (Cs-137 18.110.8 17.210.9 16.216.8 a Lab result given is the mean 12 standard deviations of three determinations. b Second International Intercomparison of Environmental Dosimeters conducted in April of 1976 by the Health and Safety Laboratory (GASL), New York, New York, and the School of Public Health of the University of Texas, Houston, Texas. c Value determined by sponsor of the intercomparison using continuously operated pressurized ion chanber. d Mean 12 standard deviations of results obtained by all laboratories participating in the program. e Third International Intercomparison of Environmental Dosimeters conducted in summer of 1977 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas, Houston, Texas. f Fourth International Intercomparison of Environmental Dosimeters conducted in summer of 1979 by the School of Public Health of the University of Texas, Houston, Texas. 9 Fif th International Intercomparison of Environmental Dosimeter conducted in fall of 1980 at Idaho Falls, Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas and Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy. h Seventh International Intercomparison of Environmental Dosimeters conducted in the spring and summer of 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, the U.S. Nuclear Regulatory

              . Commission, and the U.S. Environmental Protection Agency.

I Fighth International Intercomparison of Environmental Dosimeters conducted in the fall and winter of

                      -1986 at New York, New York, and sponsored by t        .S. Department of Energy.

Table A-3. In-house spiked samples. Concentration in pC1/1 Lab Sample Date TIML Result Known Expected Code Type Collected Analysis n=3 Activity Precision 1s,n=3a QC-MI-6 Milk Feb. 1986 Sr-89 6.0tl.9 6.4*3.0 8.7 Sr-90 14.2il.7 12.9i2.0 5.2 1-131 34.2i3.8 35.2*3.5 10.4 Cs-134 32.0il.8 27.315.0 8.7 2 Cs-137 35.8t2.1 35.015.0 8.7 i QC-W-14 Water Mar. 1986 Sr-89 1.6i0.4 1.6i1.0 7.1 Sr-90 2.4t0.2 2.4*2.0 4.2 QC-W-15 Water Apr. 1986 I-131 44.9*2.4 41.5*7.0 10.6 Co-60 10.6*1.7 12.li5.0 7- l.b Cs-l'34 30.2*2.4 25.8t8.0 7.lb Cs-137 21.9tl.9 19 915.0 7.lb QC-MI-7 Milk Apr. 1986' I-131 39.7*3.3 41.5*7.0 10.4 Cs-134 28.7*2.8 25.8 8.0 8.7 Cs-137 21.212.8 19.9*5.0 8.7 SPW-1 Water May 1986 Gross alpha 15.8*1.8 18.0*5.0 SC - QC-W-16 Water June 1986 Gross alpha 16.210.7 16.9*2.5 8.7

;                                                                                                                                Gross beta         38.4*3.5-       30.215.0           8.7 QC-MI-9                              Milk                   June 1986                                                   Sr-89       <1.0                     0.0     7.lb

! Sr-90 12.611.8 13.313.0 4.2b

I-131 38.917.0 34.8t7.0 10.4

. Cs-134 33.0*3.4 36.115.0- 8.7 Cs-137 38.5*2.8 39.0*5.0 8.7 ( SPW-2 Water June 1986 Gross alpha 16.8tl.8 18.Qt5.0 Sc SPW Water June 1986 Gross alpha 17.710.8 18.0*5.0 Sc QC-W-18 Water Sep. 1986 Cs-134 34.7f5.6 31.3*5.0 8.7 ' Cs-137 51.1*7.0 43.318.0 8.7 I QC-W-19 Water Sep. 1986 Sr-89 13.614.1 15.613.5 7.lb Sr-90 6.411.6 6.212.0 4.20 O l A-14

    ,+,,,-.-*-,w-      - . - - - - - , , - - , - . , -          --...--.---.-._,,-...w-,,,,,,,,,,,,.w.,,,,c,,,,n,--,.,,__w.----m.v--,.--                                ,,..---,--m           .-,ww-     .-

Table A-3. In-housespikedsamples(continued) Concentration in pC1/1 Lab Sample Date TIML Result Known Expected Code Type Collected Analysis n=3 Activity Precision 1s, n=3a QC-W-21 Water Oct. 1986 Co-60 19.2i2.2 18.513.0 8.7 Cs-134 31.715.2 25.618.0 8.7 Cs-137 23.811.0 21.615.0 8.7 QC-MI-11 Milk Oct 1986 Sr-89 12.311.8 14.313.0 8.7 QC-W-20 Water Nov. 1986 H-3 3855t180 3960i350 520b QC-W-22 Water Dec. 1986 Gross alpha 9.811.4 11.214.0 8.7 Gross beta 21.712.0 23.815.0 8.7 QC-W-23 Water Jan. 1987 I-131 29.8i2.5 27.913.0 10.4 QC-MI-12 Milk Jan. 1987 I-131 36.511.3 32.615.0 10.4 Cs-137 32.614.2 27.418.0 8.7 a D n=3 unless noted otherwise. n=2. c n=1. O A-15

Table A-4. In-house " blank" samples. ' Concentration in pC1/1 Acceptance Lab Sample Date Results Criteria Code Type Collected Analysis (4.660) (4.660) BL-1 0.I. Water Nov. 1985 Gross alpha <0.1 <1

Gross beta <0.4 <4 ,

l BL-2 0.I. Water Nov. 1985 Cs-137 (gamma) <1. 9 <10 i i BL-3 0.I. Water Nov. 1985 Sr-89 <0.5 <5 { Sr-90 <0.6 <1 BL-5 0.I. Water Nov.1985 Ra-226 <0.4 <1 Ra-228 <0.4 <1 l SPW-2265 D.I. Water Apr. 1985 Gross alpha <0.6 <1 Gross beta <2.2 <4

Sr-89 <0.2 <5

,O Sr-90 I-131

                                                                                                                <0.4
                                                                                                                <0.2
                                                                                                                               <1
                                                                                                                               <1 Cs-137 (gamma)      <7.4          <10 1

BL-6 D.I. Water Apr. 1986 Gross alpha <0.4- <1 6 j BL-7 D.I. Water Apr. 1986 Gross alpha <0.4 <1 BL-8 0.I. Water June 1986 Gross alpha <0.4 <1 4

BL-9 0.I. Water June 1986 Gross alpha <0.3 <1 a

I i 4 IO 4

!                                                                                      A-16 i

M-ds- d.-. -mmJ A u=--*h- *-.-.e a. h-- ---M.- a ~.-- -4_-a. #- -

   ...m_      ___a. _ mA   ..m.-.h--M.a-             A--.a.a N

l l l I l APPENDIX B DATA REPORTING CONVENTIONS l 1 i i I 4 i L 1 J i 1 1 l i i i l 1 l i l 4 B-1

Data Reporting Conventions 1.0. All activities are decay corrected to collection time.

2.0. Single Measurements Each single measurement is reported as follows: xis where x = value of the measurement; s = 2a counting uncertainty (corresponding to the 955 confidence level). In cases where the activity is found to be below the lower limit of detection L it is reported as

                                         <L 4              where L = is the lower limit of detection based on 4.66a uncertainty for a background sagle.

O 3.0. Duplicate Analyses 3.1. Individual results: x1 i s1 x2 i s2 Reported result: xis where x = (1/2) (x1 + x2) s= s 2,3 3.2. Individual results: <L1

                                                            <L2 Reported result:                       <L where L = lower of L1 and L2

~ 3.3. Individual results: xis

                                                            <L Reported result:                       x i s if x > L;
                                                            <L otherwise B-2

O 4.0. Cog utation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are coq uted from all of the individual measurements over the period averaged; for exagle, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation (s) of a set of n nuders x1, x2 Xn are defined as follows: x=1n Ix 3, I (x-x)2 n-1 4.2 Values below the highest lower limit of detection are not included in the average. 4.3 If all of the values in the averaging group are less than the highest LLD, the highest LLD is reported. 4.4 If all but one of the values are less than the highest LLD, the & W single value x and asscciated two sigma error is reported. 4.5. In rounding off, the following rules are followed: 4.5.1. If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an exagle,11.443 is rounded off to 11.44.- 4.5.2 If the figure following those to be retained is greater than 5, the figure is dropped, and the last retained figure is raised by 1. As an exagle,11.446 is rounded off to 11.45. 4.5.3. If the figure following those to be retained is 5, and if there are no figures other than zeros beyond the five, the figure 5 is dropped, and the last-place figure retained is increased by one if it is an odd nuder or it is kept unchanged if an even number. As an exagle,11.435 is rounded off to 11.44, while 11.425 is rounded off to 11.42. O B-3

6 O , O< i APPENDIX C PROGRAM DEVIATIONS O l C-1

                 //   .

s TABLE C-1 AIRBORNE 10 DINE, ELEVATED RESULTS, 1986 '

{}

DATE l-131 .' COLLECTED LOCATION PCI/M 3 COMMENTS ,

                                                                                            *   ~

02/03/86 T-23 0.10 DUE TO LOW VOLUME OF 78 M3. 02/10/86 T-23 0.13 DUE TO LOW VOLUME OF 68 M3 , . 3

02/17/86 T-23 0.20 DUE TO LOW VOLUME OF 71 M .

02/18/86 T-7 0.10 DUE TO LOW VOLUME OF 151 M 3 02/24/86 T-2 0.20 DUE TO LOW VOLUME OF 130 M3 ,

3
03/03/86 T-2 0.10 DUE TO LOW VOLUME OF 146 M 03/10/86 T-2 0.08 DUE TO LOW VOLUME OF 152 M3 ,
1 03/24/86 T-23 0.12 DUE TO LOW VOLUME OF 108 M3 ,
l 04/14/86' T-12 0.08 DUE TO LOW VOLUME OF 154 M3 ,
g T-2 >

0.2910.05 elevA1ED ACTiviTv DUE 10 FALL 0uT O05/12/86 05/12/86 T-4 0.12 0.03 FROM THE CHERNOBYL NUCLEAR PLANT 05/12/86 i '-7 0.28 0.04 (USSR) ACCIDENT ON APRIL 26, 1986. 05/12/86 128 0.59 0.08 05/12/86 T-9 0.30 0.04' 05/12/86 T-11 0.23!0.03 '

       .05/12/86            T-23          0.25 0.05             '

G5/12/86 T-27 0.12 0.03 05/19/86 T-1 0.70 0.11 ELEVATED ACTIVITY DUE TO FALLOUT 05/19/86 T-2 1.00 0.31 FROM THE CHERNOBYL NUCLEAR PLANT 05/19/86 T-3 0.15 0.04 (USSR) ACCIDENT ON APRIL 26, 1986. 05/19/86 T-4 0.46 0.06 05/19/86 T-7 0.14 0.04 05/19/86 T-8 0.13 0.04 05/19/86 T-9+ 0.37 0.05 05/19/86 T-11 1.20 0.28 . 0.17 0.04 ^ 05/19/86 T-12 05/19/86 T-27 0.38 0.06

     ,. . LOW VOLUMES ARE DUE TO PUF.f' MALFUNCTIONS.

(O J s i C-2 , i I

                                                                    --              _                  i

TABLE C-1 AIRBORNE 10 DINE, ELEVATED RESULTS, 1986 (CONTINUED) DATE l-131 O COLLECTED LOCATION PCI/M3 COMMENTS 05/27/86 T-1 0.31 0.04 ELEVATED ACTIVITY DUE TO FALLOUT 05/27/86 T-2 0.79 0.18 FROM THE CHERN0BYL NUCLEAR PLANT 05/27/86 T-3 0.22 0.04 (USSR) ACCIDENT ON APRIL 26, 1986. 05/27/86 T-4 0.60 0.09 05/27/86 T-7 0.54 0.12 05/27/86 T-8 0.68 0.16 05/27/86 T-9 0.84 0.21 05/27/86 T-11 0.23t0.04 05/27/86 T-27 0.34 0.13 05/27/86 T-23 0.16 DUE TO LOW VOLUME OF 102 M3. 06/07/86 T-1 0.08 DUE TO DELAY IN COUNTING. 06/07/86 T-2 0.08 06/09/86 T-9 0.10 DUE TO DELAY IN COUNTING. 06/09/86 T-27 0.10 06/23/86 T-9 0.09 3 DUE TO LOW VOLUME OF 230 M . g DUE TO LOW VOLUME OF 53 M3. 07/28/86 T-4 0.35 DUE TO LOW VOLUME OF 122 M3 . 08/11/86 T-27 0.08 08/25/86 T-1 0.10 DUE TO LOW VOLUME OF 118 M3 ,

3
08/25/86 T-2 0.09 DUE TO LOW VOLUME OF 121 M .

08/25/86 T-3 0.10 DUE TO LOW VOLUME OF 117 M . 09/02/86 T-1 0.19 DUE TO LOW VOLUME OF 25 M3. 11/10/86 T-9 0.08 DUE TO LOW VOLUME OF 197 M . 12/15/86 T-3 0.08 DUE TO LOW VOLUME OF 151 M3 ,

3
12/15/86 T-9 0.09 DUE TO LOW VOLUME OF 135 M .

DUE TO LOW VOLUME OF 124 M3. 12/22/86 T-9 0.16 DUE TO LOW VOLUME OF 171 M3. 12/22/86 T-12 0.12 LOW VOLUMES ARE DUE TO PUMP MALFUNCTIONS. COUNTING DELAYS ARE DUE TO LABORATORY ERROR. C-3

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4

                   -LAND USE CENSUS IN ORDER TO MONITOR THE POSSIBLE RADI0 ACTIVE MATERIAL IN OUR

SURROUNDING ENVIRONMENT, WE MUST IDENTIFY THE VARIOUS PATHWAYS BY WHICH RADIOACTIVE MATERIAL MAY REACH THE POPULA-TION. THESE PATHWAYS INCLUDE:-

! e INHALATION PATHWAY - BREATHING RADI0 ACTIVE MATERIAL BEING CARRIED IN THE AIR e GROUND EXPOSURE PATHWAY - THE EXPOSURE OF PEOPLE TO l RADIATION DEPOSITED ON THE GROUND e VEGETATION PATHWAY - THE EATING OF PLANTS, FRUIT, ETC f WHICH HAVE A BUILD-UP OF DEPOSITED RADIONUCLIDES OR WHICH HAVE ABSORBED RADI0 ACTIVE MATERIALS THROUGH THE SOIL. , e MILK PATHWAY - THE PROCESS WHEREBY RADIONUCLIDES COULD BE DEPOSITED ON FORAGE, EATEN BY A COW OR GOAT, l THEN PROCESSED INTO THEIR MILK WHICH IS CONSUMED BY PEOPLE e PLUME EXPOSURE PATHWAY - THE EXPOSURE TO PEOPLE

DIRECTLY FROM A PLUME OR " CLOUD" 0F RADI0 ACTIVE MATERIAL e MEAT PATHWAYS - LOCAL FISH, GEESE, DEER,-AND FARM

< ANIMALS WHICH COULD HAVE EATEN RADI0 ACTIVE MATERIAL DEPOSITED IN THE WATER OR ON THEIR FORAGE AND WHICH IN TURN MAY BE CONSUMED BY PEOPLE i' l AFTER THESE PATHWAYS ARE IDENTIFIED, THEY ARE INVESTIGATED IN RELATIONSHIP TO DAVIS-BESSE AND THE SURROUNDING COMMUNI-TIES. TO DO THIS, WE PERFORM AN ANNUAL LAND USE CENSUS, A i STUDY OF THE POPULATION WITHIN FIVE MILES OF DAVIS-BESSE. THIS ENTAILS DRIVING ALONG ALL THE ROADWAYS WITHIN A FIVE MILE RADIUS OF DAVIS-BESSE, MAPPING THE NEAREST RESIDENT, THE NEAREST GARDEN (LARGER THAN 500 SQUARE FEET) AND THE

i. NEAREST MILK COWS OR G0ATS. AS A DOUBLE CHECK, THE OTTAWA l

COUNTY AGRICULTURAL COOPERATIVE EXTENSION AGENCY PROVIDES

;                   CONFIRMATION OF ANY DAIRY ANIMALS.

LO = _ _ - -

ONCE ALL THE NEAREST PATHWAYS ARE LOCATED ON A MAP WHICH HAS BEEN DIVIDED INTO 16 EQUAL SECTORS CORRESPONDING TO THE CARDINAL COMPASS POINTS (SEE FIGURE 15), WE CAN THEN DETERMINE THE CLOSEST INDIVIDUAL PATHWAY FOR EACH SECTOR. THE DISTANCE OF EACH PATHWAY FROM DAVIS-BESSE IS THEN DETERMINED (IN METERS) AND THE INFORMATION PUT INTO TABULAR FORM. FOR AN EXAMPLE, SEE TABLE 8. SECTION 9 ON TABLE 8 SHOWS THREE COLUMNS. FOR EXAMPLE, THE FIRST COLUMN LISTS THE CLOSEST RESIDENCE IN THAT SECTOR WHICH IS AT 1130 METERS. THIS LOCATION WOULD HAVE A POTEN-TIAL INHALATION PATHWAY AS WELL AS POSSIBLE GROUND AND PLUME EXPOSURE PATHWAYS. THEREFORE, A "1" IS ENTERED IN THAT COLUMN FOR EACH PATHWAY PR'ESENT. THE SECOND COLUMN LISTS THE NEXT CLOSEST RE.SIDENCE WITH A DIFFERENT PATHWAY PRESENT. COLUMNS ARE ADDED UNTIL ALL PATHWAYS ARE IDENTIFIED. EACH OF THE 16 SECTORS ARE COMPLETED IN THIS WAY. THE INFORMATION GATHERED IN THE ANNUAL LAND USE CENSUS IS USEFUL IN SEVERAL WAYS INCLUDING CALCULATIONS OF POTENTIAL OFF-SITE DOSES TO THE PUBLIC DUE TO THE RELEASE OF RADIOAC-TIVE LIQUID AND GASEOUS EFFLUENTS AS DISCUSSED IN THE 1986 RADI0 ACTIVE LIQUID AND GASEOUS EFFLUENTS

SUMMARY

. ADDITION-ALLY, THE LAND USE CENSUS DATA PROVIDES DAVIS-BESSE VALUABLE lh INFORMATION FOR DETERMINING THE BEST LOCATIONS FOR OUR MONITORING STATIONS (SEE RADIOLOGICAL ENVIRONMENTAL MONITOR-ING PROGRAM). THE RESULTS OF THE 1986 LAND USE CENSUS ARE PRESENTED IN THE FOLLOWING REPORT. AS DISCUSSED IN THE REPORT, SOME OF THE PATHWAYS HAVE CHANGED IN THE LAST YEAR DUE TO CHANGES IN GARDENS AND MILK ANIMAL LOCATIONS. THE CLOSEST PATHWAY IS LOCATED AT 900 METERS IN THE NNE SECTOR AND CONTAINS A VEGETATION PATHWAY. THIS LOCATION HAS NOT CHANGED SINCE 1983. =- l

i l

  'C                                                                                       FIGURE 15 MAP SHOWING THE 16 CARDINAL COMPASS POINTS N
                                                                                                                             /

NNW NNE NW NE WNW - ENE W E WSW ESE SW SE

 /                                                                           SSW                                         SSE x

l l I

--t v

TABLE 8 h EXAMPLE OF LAND USE CENSUS TABLE RECEPTOR DISTANCE FROM SITE (METERS) SECTOR 7 (SE) INHALATION CONTAMINATED GROUND VEGETATION C0w MILK GOAT MILK PLUME EXPOSURE SECTOR 8 (SSE) 2030 2920 INHALATION 1 1 CONTAMINATED GROUND 1 1 VEGETATION 1 C0w MILK GOAT MILK PLUME EXPOSURE 1 1 SECTOR 9 (S) 1130 1430 5860 INHALATION 1 1 1 CONTAMINATED GROUND 1 1 1 VEGETATION 1 1 C0w MILK 1 GOAT MILK 1 PLUME EXPOSURE 1 1 1

O 1986 LAND-USE CENSUS TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION i i O O

m. _ _ _ - -

l ( ]) 1986 LAND-USE CENSUS l 1 APPENDIX I, TO 10 CFR 50, SECTION IV B, STATES IN PART THAT l THE LICENSEE SHALL ESTABLISH AN APPROPRIATE SURVEILLANCE AND L MONITORING. PROGRAM FOR EVALUATING DOSES TO INDIVIDUALS FROM i PRINCIPAL PATHWAYS OF EXPOSURE. THE DAVIS-BESSE TECHNICAL j - SPECIFICATIONS, APPENDIX A, SECTION 3.12.2, STATES "A LAND l USE CENSUS SHALL BE CONDUCTED AND SHALL IDENTIFY WITHIN A DISTANCE OF 8 KM (5 MILES) THE LOCATION, IN EACH OF-THE 16 METEOROLOGICAL SECTORS, OF THE NEAREST MILK ANIMAL, THE NEAREST RESIDENCE'AND THE NEAREST GARDEN OF GREATER THAN 50

2

M 2 (500 'FT ) PRODUCING BROAD LEAF VEGETATION."

THE 1986 LAND-USE CENSUS WAS CONDUCTED ON MAY- 14, 19, 20 AND

21, 1986. ALL OF THE PATHWAY LOCATIONS WERE DETERMINED: WITHIN A FIVE-MILE RADIUS OF THE STATION VENT. RADIOLOGICAL l . EXPOSURE PATHWAYS ARE THE METHODS BY WHICH PEOPLE MAY BECOME EXPOSED TO RADIONUCLIDES RELEASED FROM NUCLEAR FACILITIES.; PATHWAYS RECORDED IN THE LAND-USE CENSUS WERE RESIDENCES,

. VEGETABLE GARDENS AND MILK ANIMALS. THE OTTAWA COUNTY

COOPERATIVE EXTENSION AGENCY CONFIRMED THE PRESENCE OF MILK C.0WS AND MILK G0ATS REPORTED WITHIN THIS FIVE-MILE RADIUS.

[} ' i THE FOLLOWING CHANGES WERE RECORDED IN THE 1986 CENSUS: l !- N SECTOR - A VEGETABLE PATHWAY AT 890 METERS WAS DELETED. i NNE SECTOR - THE VEGETABLE PATHWAY AT 900 METERS WHICH WAS PREVIOUSLY PRESENT WAS NOT OBSERVED AT THE-1 TIME OF THE CENSUS. SINCE NO MAJOR CHANGE HAD l OCCURRED IN THE AREA AND THE CENSUS WAS TAKEN i IN EARLY SPRING, IT WAS ASSUMED THAT THE ,- GARDEN WOULD BE PLANTED AT A'LATER DATE AND WAS INCLUDED IN THE CENSUS. ESE SECTOR - A DAIRY GOAT PATHWAY WAS DELETED AT 21,240 METERS (13.2 MILES).

SSE SECTOR - THE VEGETABLE PATHWAY AT 2,680 METERS WAS CHANGED TO 2,920 METERS.

                                -    A BEEF CATTLE PATHWAY WAS DELETED AT 4,000 METERS.                                                                                  (
                                -    A DAIRY G0AT PATHWAY WAS DELETED AT 23,500 l                                     METERS.

'O 9 95 - 4

                                    .s--m-w,,,---                                            wem,-,,.-e----->m,-we-,-ww,---

S SECTOR - A DAIRY GOAT PATHWAY WAS ADDED AT 5,860 h METERS. A BEEF CATTLE PATHWAY WAS DELETED AT 4,420 METERS. SSW SECTOR - THE VEGETABLE PATHWAY AT 1,260 METERS WAS CHANGED TO 1,000 METERS. A BEEF CATTLE PATHWAY WAS DELETED AT 3,780 METERS. SW SECTOR - THE VEGETABLE PATHWAY AT 1,050 METERS WAS CHANGED TO 1,360 METERS. A BEEF CATTLE PATHWAY WAS DELETED AT 4,740 METERS. A DAIRY G0AT PATHWAY WAS DELETED AT 11,910 METERS. WSW SECTOR - A BEEF CATTLE PATHWAY WAS DELETED AT 8,100 METERS. A DAIRY GOAT PATHWAY WAS DELETED AT 14,480 METERS. W SECTOR - A BEEF CATTLE PATHWAY WAS DELETED AT 1,700 METERS. WNW SECTOR - THE VEGETABLE PATHWAY AT 2,880 METERS WAS CHANGED TO 2,280 METERS. A NEW RESIDENCE AT 1,520 METERS WAS ADDED. NW SECTOR - THE RESIDENCE AND VEGETABLE PATHWAY AT 1,160 METERS WAS DELETED.

          -   A RESIDENCE AT 2,000 METERS WAS ADDED.

A RESIDENCE AND VEGETABLE PATHWAY WAS ADDED AT 2,290 METERS. NNW SECTOR - A RESIDENCE AT 1,250 METERS, WHICH WAS OVER-LOOKED IN THE 1985 CENSUS, WAS ADDED. PATHWAYS ARE ADDED OR DELETED AS GARDEN LOCATIONS CHANGE, AS NEW HOUSES ARE BUILT OR AS PEOPLE BEGIN OR STOP RAISING DAIRY ANIMALS. 9 O aeSULTS THE RESULTS OF THE 1986 LAND-USE CENSUS ARE PRESENTED IN SHORT FORM IN TABLE 1. THE DETAILED PATHWAY LIST IN TABLE 2 IS USED TO UPDATE THE DATA BASE OF THE DAVIS-BESSE COMPUTER DISPERSION MODEL USED IN THE EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT. TABLE 7 IS THE UPDATED TABLE FOR APPEN-DIX B 0F THE OFFSITE DOSE CALCULATIONS MANUAL (0DCM). THE ODCM DESCRIBES THE METHODOLOGY AND PARAMETERS USED IN CALCULATING OFFSITE DOSES DUE TO RADI0 ACTIVE LIQUID AND GASEOUS EFFLUENTS AND IN CALCULATING LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION ALARM / TRIP SETPOINTS. THE CRITICAL RECEPT 0R OF THE 1986 CENSUS HAS NOT CHANGED FROM THE 1983, 1984, AND 1985 REPORTS. THE VEGETATION PATHWAY AT 900 METERS IN THE NNE SECTOR WITH X/Q VALUE OF 1.19E-6 AND D/Q VALUE OF 1.39E-8 IS STILL THE MOST CRITICAL RECEPTOR. X/Q IS THE RELATIVE ATMOSPHERIC DISPERSION AND IS USED TO DETERMINE HOW EFFLUENTS WILL BE CARRIED THROUGHOUT THE AREA. D/0 IS THE RELATIVE DEPOSITION PER UNI.T AREA AND IS USED TO PREDICT HOW MUCH RADI0 ACTIVITY MAY BECOME DEPOS-ITED IN AN AREA. O ee- = =- e--- TABLE 1 $ PATHWAY IDENTIFICATION SECTOR DISTANCE (METERS) PATHWAY N 870 RESIDENCE NNE 870 RESIDENCE 900 RESIDENCE, VEGETABLE GARDEN

NE 900 RESIDENCE ENE** -- --

E** -- -- _ ESE** -- -- SE** -- -- SSE 2030 2920 RESIDENCE RESIDENCE, VEGETABLE GARDEN g S 1130 RESIDENCE 1430 RESIDENCE, VEGETABLE GARDEN 5860 RESIDENCE, VEGETABLE GARDEN, DAIRY G0AT SSW 1000 RESIDENCE, VEGETABLE GARDEN SW 990 RESIDENCE 1360 RESIDENCE, VEGETABLE GARDEN WSW 1640 RESIDENCE, VEGETABLE GARDEN 4250 RESIDENCE, VEGETABLE GARDEN, DAIRY COWS W 980 RESIDENCE, VEGETABLE GARDEN

THE VEGETABLE GARDEN WAS NOT OBSERVED AT THE TIME OF THE CENSUS, HOWEVER IT WAS ASSUMED THAT IT WOULD BE PLANTED AT A LATER DATE AND WAS THEREFORE INCLUDED IN THE CENSUS.

        ** SECTORS OVER LAKE ERIE AND MARSH AREAS.
                                                                            - h -

I O 148te 1 (CONTINUED) PATHWAY IDENTIFICATION SECTOR DISTANCE (METERS) PATHWAY WNW 1520 RESIDENCE , 2280 RESIDENCE, VEGETABLE GARDEN NW 2000 RESIDENCE 2290 RESIDENCE, VEGETABLE GARDEN

NNW 1250 RESIDENCE -

RESIDENCE, VEGETABLE GARDEN 1330 O 1 t' h 'l lQ s

                                                                                                  ,__            _ _ _ . _                                       . _ . , = _ _ _
  , _ ~ . - - - - . . . , _ . _ , , _ _ , , _ _ . _ _ _ . . _ . _ . . . _ _ , _ , . . - . . . .                                  _ . _ - . - . . . . _ . - . _ . _ . . ~ . . , . _ _ . . _ . . - _ _ _ . -

TABLE 2 h PATHWAY DISTANCE FROM SITE (METERS) SECTOR 1 (N) 870 INHALATION 1 CONTAMINATED GROUND 1 VEGETATION COW MILK G0AT MILK PLUME EXPOSURE 1 SECTOR 2(NNE) 870 900* INHALATION 1 1 CONTAMINATED GROUND 1 1 VEGETATION 1

COW MILK GOAT MILK PLUME EXPOSURE 1 1 lg SECTOR 3 (NE) 900 INHALATION 1 CONTAMINATED GROUND 1 VEGETATION COW MILK GOAT MILK PLUME EXPOSURE 1

THE VEGETABLE GARDEN WAS NOT OBSERVED AT THE TIME OF THE CENSUS, IT WAS ASSUMED THAT THE GARDEN WOULD BE PLANTED AT A LATER TIME AND WAS THEREFORE INCLUDED IN THE CENSUS AS A CONSERVATIVE MEASURE.

              = _ _ . _        _

h

                            - 100 -                               l 1

i (]) TABLE 2 (CONTINUED) j PATHWAY DISTANCE FROM SITE (METERS) i SECTOR 4 (ENE)** --

,                     INHALATION CONTAMINATED GROUND VEGETATION C0w MILK GOAT MILK i                     PLUME EXPOSURE l

! SECTOR 5 (E)** -- l INHALATION i CONTAMINATED GROUND i VEGETATION i C0w MILK i n GOAT MILK lU i PLUME EXPOSURE SECTOR 6 (ESE)** -- INHALATION j CONTAMINATED GROUND ! VEGETATION ! C0w MILK GOAT MILK PLUME EXPOSURE l 1 ! SECTORS OVER LAKE ERIE AND MARSH AREAS i i l i I 'O

                                                              - 101 -

E- _ ___ _ __ _ _ -- - . . _ _ - _.

TABLE 2 (CONTINUED) PATHWAY DISTANCE FROM SITE (METERS) SECTOR 7 (SE)** -- INHALATION CONTAMINATED GROUND VEGETATION C0w MILK G0AT MILK PLUME EXPOSURE SECTOR 8 (SSE) 2030 2920 INHALATION 1 1 CONTAMINATED GROUND 1 1 VEGETATION 1 Cow MILK GOAT MILK PLUME EXPOSURE 1 1 SECTOR 9 (S) 1130 1430 5860 INHALATION 1 1 1 CONTAMINATED GROUND 1 1 1 VEGETATION 1 1 C0w MILK GOAT MILK 1 PLUME EXPOSURE 1 1 1 SECTORS OVER LAKE ERIE AND MARSH AREAS I O l

                           - 102 -                  .

[( ) TABLE 2 (CONTINUED) PATHWAY DISTANCE FROM SITE (METERS) , i i SECTOR 10 (SSW) 1000 i' INHALATION 1 ! CONTAMINATED GROUND 1 i VEGETATION 1 l C0w MILK

i. GOAT MILK l PLUME EXPOSURE 1

. i i 1 SECTOR 11 (SW) 990 1360 I' INHALATION 1 1

CONTAMINATED GROUND 1 1 i VEGETATION 1: COW MILK
. Q GOAT MILK PLUME EXPOSURE 1 1 i SECTOR 12 (WSW) 1640 4250 i INHALATION 1 1 i CONTAMINATED GROUND 1 1: VEGETATION 1 1 Cow MILK 1

! GOAT MILK : l PLUME EXPOSURE 1 1 i i t? O . l

                                                                                  - 103 -

l ~ i

g TABLE 2 W (CONTINUED) PATHWAY DISTANCE FROM SITE (METERS) S_ECTOR 13 (W) 980 INHALATION 1 CONTAMINATED GROUND 1 VEGETATION 1 C0w MILK GOAT MILK PLUME EXPOSURE 1 SECTOR 14 (WNW)_ 1520 2280 INHALATION 1 1 CONTAMINATED GROUND 1 1 VEGETATION 1 C0w MILK GOAT MILK PLUME EXPOSURE 1 1 SECTOR 15 (NW) 2000 2290 INHALATION 1 1 CONTAMINATED GROUND 1 1 VEGETATION 1 C0w MILK G0AT MILK PLUME EXPOSURE 1 1 0

                             - 104 -

Q TABLE 2 (CONTINUED) PATHWAY DISTANCE FROM SITE (METERS) SECTOR 16 (NNW) 1250 1330 INHALATION 1 1 CONTAMINATED GROUND l- 1 VEGETATION 1 COW flILK GOAT MILK PLUME EXPOSURE 1 1 O i 1 0

                                  - 10s -

OFF-SITE DOSE CALCULATIONS MANUAL TABLE 7, APPENDIX B 4h CONTROLLING PATHWAY LOCATION PATHWAYS AND ATMOSPHERIC DISPERSION PARAMETERS DISTANCE SECTOR (METERS) PATHWAYS AGE GROUP X/0! D/0 N 870 INHALATION CHILD 9.34E-7 8.55E-9 NNE 900 VEGETATION CHILD 1.19E-6 1.39E-8 NE 900 INHALATION CHILD 1.26E-6 1.58E-8 ENE -- Eo -- ESE -- SE -- SSE 2,920 VEGETATION CHILD 6.75E-8 7.82E-10 S 5,860 GOAT / MILK INFANT 2.89E-8 1.66E-10 SSW 1,000 VEGETATION CHILD 1.92E-7 4.18E-9 SW 1,360 VEGETATION CHILD 2.05E-7 3.85E-9 WSW 4,250 COW / MILK INFANT 5.74E-8 5.36E-10 W 980 VEGETATION CHILD 6.21E-7 9.58E-9 WNW 2,280 VEGETATION CHILD 9.70E-8 1.03E-9 m NW 2,290 VEGETATION CHILD 7.02E-8 5.84E-10 W NNW 1,330 VEGETATION CHILD 2.51E-7 1.57E-9 THE VEGETABLE GARDEN WAS NOT OBSERVED AT THE TIME OF THE CENSUS, IT WAS ASSUMED THE GARDEN WOULD BE PLANTED AT A LATER DATE AND WAS THEREFORE INCLUDED IN THE CENSUS AS A CONSERVATIVE MEASURE. SINCE THESE SECTORS ARE LOCATED OVER MARSH AREAS AND OVER LAKE ERIE, NO INGESTION PATHWAYS ARE PRESENT. 9

                                   - 106 -
                                                                                ]

TOLEDO

                                                               %mmEDISON Docket No. 50-346                                                 DONALD C. SHELTON Vr.a Preedent-Nudear (419]249 2399 License No. NPF-3 Serial No. 1-727 April 30, 1987 United States Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Gentlemen:

Under separate cover, we are transmitting two (2) copies of the 1986 Annual Environmental Operating Report for the Davis-Besse Nuclear Power Station, Unit No. 1. This report is submitted in accordance with Section 6.9.1.10 of the Davis-Besse Operating License Appendix A, Technical Specifications. Very tru ours, DCS:JSL:p1f Attachment ec: DB-1 NRC Resident Inspector A. B. Davis, Regional Administrator (2 copies) A. W. DeAgazio, NRC/NRR Davis-Besse Project Manager 1 l l v i/ 6 \ v THE TOLEDO EOISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO OHIO 43G52 \

\}}

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