ML20198F116

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Forwards Radiological Impact Section Input to Des.Input Delayed Due to Delay in Receipt of Meteorological Data from NOAA
ML20198F116
Person / Time
Site: Washington Public Power Supply System
Issue date: 10/16/1974
From: Harold Denton
US ATOMIC ENERGY COMMISSION (AEC)
To: Muller D
US ATOMIC ENERGY COMMISSION (AEC)
References
CON-WNP-1217 NUDOCS 8605280416
Download: ML20198F116 (27)
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4.1 Radiation Exposure to Construction Workers During the period between the startup of WPPSS No. 2 and the completion of WPPSS No. 1 and No. 4, the construction personnel working on Units 1 and 4 will be exposed to sources of radiation from the operation of WPPSS No. 2 initially and from WPPSS No. I when it goes into operation.

The applicant has estimated that 3000 and 2700 workers will be on site at the time of fuel loading of WNP-2 and WNP-1, respectively.

It is estimated that the dose rates from WNP-2 at WNP-1 and WNP-4 are 3.8 and 4.3 man-rem /yr.

The dose rate at WNP-4 resulting from operation of WNP-1 and 2 is 4.3 man-rem /yr.

Based on a fuel load date of March 1978 for WNP-2, March 1980 for WNP-1, and September 1981 for WNP-4, the total dose (integrated over the construction period) to construction personnel is estimated to be 23 man-rem.

Estimated values for other LWR's have ranged from 10 to 30 man-rem. These doses are a small fraction of the approximately 1100

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man-rem which would be received over the same period from natural background radiation (See Section 5.3.6 for a discussion of background radiation dose rates).

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WPPSS NUCLEAR PROJCCT NOI 1 AND NO, 4 10-07-74 5l2 RADIOLOLOGICAL IMPACT ON BIOTA OTHER THAN MAN S,!2.'1 EXPOSURE PATHWAYS THE PATHWAYS SY WHICH BIOTA OTHER THAN HAN HAY RECEIVE RADIATION DOSES IN THC VICINITY OF A NUCLEAR POWER STATION ARE SHOWN IN FIGURE

5.2,1.

ThO RECCNT COMPRCHENSIVE REPORTS (REF. 1,2) HAVE BEEN CONCERNED WITH RADIOACTIVITY IN THC ENVIRONHENT AND THESE PATHWAYS, THCY CAN DE READ FOR A MORE DETAILED EXPLANATION OF THE SUBJECTS THA1 WILL BE DISCUSSED DELOW, DEPENDING ON THE PATHWAY BEING CONSIDERED, TERRESTRIAL AND AQUATIC ORGANISMS HILL RECEIVE EITHER APPROXIMATELY

'THE SAME RADIATION DOSCS AS MAN OR SOMEWHAT GREATER DOSES. ALTHOUGH j

NO GUIDELINES HAVE BEEN CSTABLISHED FOR DESIRABLE LIMITS FOR RADIATION CXPOSURE TO SPECIES OTHER THAN MAN, IT IS GENERALLY AGREED j

THAT THE LIMITS CSTADLISHED FOR HUMANS ARE ALSO CONSERVATIVE FOR j

THLSE SPCCICS (RCF, 3),

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5.'2,'2 RADI0 ACTIVITY IN THE ENVIRONMENT k

THE QUANTITIES AND SPECIES OF RADIONUCLIDES EXPECTED TO BE l

DISCHARGCD ANNUALLY OY hPPSS NUCLEAR PROJECT NO. 1 AND NO. 4 IN LIQUID AND GASEOUS EFFLUENTS HAVE BEEN ESTIMATCD BY THE STAFF AND ARE 3

GIVEN IN TABLCS 3.2 AND 3.3, RESPECTIVELY, THE BASIS FOR THESE VALutS IS DISCUSSED IN SECTION 3.5, FOR THE DCTCRMINATION OF DOSES TO DIOTA OTHER THAN MAN, SPECIFIC CALCULATIONS ARE DONE PRIMARILY FOR THE LIQUID CFFLUCNTS.

THE LIQUID EFFLUENT QUANTITIES, WHEN DILUTED IN WPPSS NUCLEAR PROJECT NO. 1 AND NO. Il DISCHARGE, WOULD PRODUCE AN AVERAGC GROSS ACTIVITY CONCENTRATION, EXCLUDING THITIUM, OF 1.3X10-3 l

PICOCURICS PER HILLILITER IN THE PLANT DISCHARGE AREA.

UNDER THE l

.S AME CONDITIONS, (I.E., ALLOWING FOR THE PROMPT DILUTION FACTOR OF 10 PROVIDED BY l

THE DIFFUSER), THE TRITIUM CONCENTRATION WOULD BE 4.4 PIC0 CURIES /ML. ADDITIONAL

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DISCUSSION CONCERNING LIQUID DILUTION IS PRESENTED 'IN SECTION 5.3.

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s DOSCS TO TCRRESTRIAL ANIMALS SUCH AS RABBITS OR DEER DUC TO THE GASEOUS CFFLUCNTS ARE QUITE SIMILAR TO THOSE CALCULATED FOR MAN (SECTION 5.3).

FOR THIS REASON, BOTH THE GASCOUS EFFLUENT CONCENTRATIONS AT LOCATIONS OF INTEREST AND THE DOSE CALCULATIONS FOR GASCOUS CFFLUCNTS ARE DISCUSSED IN DETAIL IN SCCTION 5.3, 3

l S.2.'3 DOSE RATE ESTIMATES i

THE ANNUAL RADIATION DOSES 70 SOTH AQUATIC AND TERRESTRIAL BIOTA INCLUDING MAN WERE ESTIMATED ON THE ASSUMPTION OF CONSTANT CONCENTRATIONS OF RADIONUCLIDES AT A GIVEN POINT IN BOTH THE WATER l

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n AND AIR AS INDICATED IN FIGURE 5.2. t r RADIATION 00SE HAS BOTH INTERNAL AND CXTERNAL COMPONENTS. EXTERNAL COMPONENTS ORIGINATE FROM IMMERSION IN RADI0 ACTIVE AIR'AND WATCR AND FROM EXPOSURE TO RADIDACTIVE SOURCES ON SURFACES, IN DISTANT VOLUMES OF AIR AND WATER, IN EQUIPMENT, E TC.

INTERNAL EXPOSURCS ARE A RESULT OF INGESTING AND ImLE.ING' RADI0 ACTIVITY, 00SCS WILL DC DELIVERED TO AQUATIC ORGANISMS LIVING IN THE WATER CONTAINING RADIONUCLIOES DISCHARGED FROM THE POWER STATION.

THIS IS PRINCIPALLY A CONSEQUENCE OF PHYSIOLOGIC AL MECH ANISitS THAT CONCCNTRATC A NUMBER OF CLEMENTS.THAT CAN BE PRESENT IN THE AGUEOUS ENVIRONMENT.

THE CXTENT TO WHICH ELEMENTS ARE CONCENTRATED IN FISH, INVERTCBRATES, AND AQUATIC PLA.NTS UPON UPTAKE OR INGESTION HAS SEEN ESTIMATED. VALUCS OF RELATIVE BIOLOGICAL ACCUMULATION FACTORS ( RATIO OF CONCENTRATION OF NUCLIDE IN ORGANISMS TO THAT IN THE AQUEOUS ENVIRONMENT ) 0F A NUMBER OF WATER-BORNE ELEMENTS FOR SEVERAL ORGANISHS ARE PROVIDED IN TABLE S.2.1,

.00SCS TO AQUATIC PLANTS AND FISH LIVING IN THC OISCHARGE PEGION DUE TO WATER UPTAKE AND INGESTION (INTERNAL EXPOSURC) WERE CALCULATED TO BE-4,9 AND-8.0 MRAOS/ YEAR, RESPECTIVELY, FOR WPPSS NUCLEAR PROJECT NO.~ I AND NO. n OPERATION. THE DISCHARGE REGION CONCENTRATIONS WERE THOSC GIVEN ABOVE AND IT WAS ASSUMED THAT THESC URGANISMS SPENT ALL OF THE YEAR IN WATER OF MAXIMUM CONCENTRATIONS. ALL CALCULATED DOSES ARC BASED ON STANDARD MODELS (REF. n).

THE DOSES ARE QUITE CONSCRVATIVE SINCE IT IS HIGHLY UNLIKELY THAT ANY OF THE MOBILE LIFE FORMS WILL SPCND A SIGNIFICANT PORTION OF THEIR LIFE SPAN IN THE MAXIMUM ACTIVITY CONCENTRATION OF THE DISCHARGC REGION. BOTH RADIOACTIVC DECAY AND ADDITIONAL DILUTION WOULD REDUCE THE DOSE AT OTHER POINTS IN THE RIVER EXTCRNAL DOSCS TO TERRESTRIAL ANIMALS OTHER THAN MAN ARE DETERMINED ON THC BASIS OF GASCOUS CFFLUENT CONCENTRATIONS AND DIRECT RADIATION CONTRIBUTIONS AT THE LOCATIONS WHERE SUCH ANIMALS MAY ACTUALLY BE

PRESENT, TERRCSTRIAL ANIMALS IN THE ENVIRONS OF THE STATION WILL l

RECEIVE APPROXIMATELY THC SAME EXTERNAL RADIATION DOSES AS THOSE l

CALCULATED FOR MAN.

TABLE 5.'3.2 LISTS THE DOSES OUE TO THE GASEOUS i

EFFLUENTS, AN ESTIMATE CAN BE MADE FOR THE INGESTION DOSE TO A TERRESTRIAL l

ANIMAL SUCH AS A DUCK WHICH IS ASSUMED TO CONSUMC ONLY AQUATIC f

YEGETATION GROWING IN THE WATER IN THE DISCHARGE REGION. THE DUCK INGESTION 00SE WAS CALCULATED TO BE ABOUT.

22 MRADS/ YEAR, WHICH REPRESCNTS AN UPPER LIMIT ESTIMATE SINCE EQUILIBRIUM WAS ASSUMED TO EXIST BETWCCN THE AQUATIC ORGANISMS AND ALL RADIONUCLIOES IN WATER, A NONEQUILIBRIUM CONDITION FOR A RADIONUCLIDE IN AN ACTUAL EXPOSURE SITUATION WOULO RESULT IN A SMALLER BI0 ACCUMULATION AND THEREFORE IN A SMALLER DOSE FROM INTERNAL EXPOSURE,

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l THE LITERATURE RELATING TO RADIATION EFFECTS ON ORGANISFS IS '

EXTENSIVE, BUT VERY FEW STUDIES HAVE BEEN CONDUCTED ON THE EFFECTS OF CONTINUQUS lod

  • LEVEL EXPOSURE TO RADIATION FROM INGESTED RADIONUCLIDCS ON NATURAL AQUATIC OR TERRESTRIAL POPULATIONS. THE HOST RECENT AND PERTINENT STUDIES POINT GUT THAT, WHILE THE EXISTENCE OF EXTRCHELY RADIOSENSITIVE BIOTA IS POSSIBLE AND WHILE INCREASED RADIOSENSITIVITY IN ORGANISMS MAY RESULT FROM ENVIRONMENTAL INTERACTIONS, NO BIOTA HAVC YET BEEN DISCOVERED THAT SHOW A

-SENSITIVITY TO RADIATION EXPOSURES AS LOW AS THOSE ANTICIPATED IN THE AREA SURROUNDING WPPSS NUCLEAR PROJECT NO. 1 AND NO, 4 IN THE "BCIR" RCPORT (REF.5), IT IS STATED IN

SUMMARY

THAT EVIDENCE TO DATE INDICATES 1 HAT NO OTHER LIVING ORGANISMS ARE VCRY MUCH MORE RADIOSENSITIVC THAN HAN. THEREFORE, NO DETECTABLE RADIOLOGICAL IMPACT IS EXPECTED IN THE AQUATIC BIOTA OR TERRESTRIAL MAMMALS AS A RESULT OF THE QUANTITY OF RADIONUCLIDES TO BE RELEASED INTO THE COLUMBIA RIVER AND INTO THE AIR BY WPPSS NUCLEAR PROJECT NO. 1 AND NO. 4 o

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PAGE 5 TABLE 5,2.1 FRESHWATER B10 ACCUMULATION FACTORS ( R E F, 9)'

ELEMENT FISH INVERTEBRATES PLANTS

,1 (PCI/KG ORGANISM PER PCI/ LITER WATER)

C 4550 9100 4550 NA 100 200 500 P

100000 20000 500000 SC 2

1000 10000 CR 200 2000 4000 MN 400 90000 10000

'FE 100 3200 1000

.C0 50 200 200 NI 100 100 50 ZN 2000 10000 20000 RB 2000 1000 1000 SR 30 100 500 Y

25 1000 5000

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40 RU 10 300 2000 l

RH 10' 300 200 AG 2

770

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10 1500 TE 400 150 100 1

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40 CS 2000 100 500 BA 4

200 500 LA

'25 1000 5000 CE 1

1000 4000 PR 25 1000 5000 ND 25 1000 5000 PM 25 1000 5000 SM 25 1000 5000

'EU 25 1000 5000 GD 25 1000 5000 W

1200 10 1200 NP 10 400

-300 PU 4

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AM 25 1000 5000 CM 25 1000 5000 1

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PAGE 6 i

.Sf3 RADIOLOGICAL IMPACT ON MAN S.3.'1 EXPOSURt PATH' WAYS ROUTINE POWER GENERATION BY WPPSS NUCLEAR PROJECT NO. 1 AND NO. 4 WILL RCSULT IN THE RELEASE OF SMALL QUANTITIES OF FISSION AND ACTIVATION PRODUCTS TO THE ENVIRONMENT.

THIS CVALUATION WILL PROVIDE DOSE ESTIMATES WHICH CAN SERVE AS A BASIS FOR A DETERMINATION THAT RELEASES TO UNRESTRICTED AREAS ARE AS LOW AS PRACTICABLE IN ACCORDANCE WITH 10 CFR 50 AND WITHIN THE LIMITS SPECIFIED IN 10 CFR -20 THE ACC STAFF HAS ESTIMATED THE PROBABLE NUCLIDE RELEASES FROM WPPSS NUCLEAR PROJECT NO. 1 AND NO. 4 BASED UPON EXPERIENCE WITH

. COMPARABLE OPERATING REACTORS AND AN EVALUATION OF. THE RADWASTE

.SYSTCM.

THCSC RELEASES HAVE BEEN DISCUSSED IN SECTION 3.5 ESTIMATIONS WERC MADE OF RADIATION DOSES TO MAN AT AND BEYOND THE SITE BOUNDARY VIA THE MOST SIGNIFICANT PATHWAYS AMONG THOSE DIAGRAMHCD IN FIG. 5.3.1 THE CALCULATIONS ARE BASED ON CONSERVATIVE ASSUHPTIONS REGARDING THE DILUTIONS OF EFFLUENT GASES AND RADIONUCLIDES IN THC LIQUID DISCHARGE, AND THE USE BY MAN OF THE PLANT SURROUNDINGS.

IN GENERAL, RADIATION 003CS CALCULATED BY THE

. STAFF ARC INTENDED TO APPLY TO AN AVERAGE ADULT. SPECIFIC PERSONS WILL RECCIVE HIGHER OR LOWER DOSCSt DEPENDING UPON THEIR AGE, LIVING HABITS, FOOD PREFERENCES, OR RECREATIONAL ACTIVITICS.

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BASCD UPON EXPERIENCE AT COMPARABLE OPERATING NUCLEAR POWER REACTORS, AN ESTIMATE HAS BEEN MADE OF THE OCCUPATIONAL RADIATION EXPOSURES CXPCCTED TO RESULT FROM PLANT UPERATION.

5.3.2 LIQUID EFFLUENTS EXPECTED NUCLIDE RELEASES IN THE LIQUID EFFLUENT HAVE BEEN CALCULATED FOR WPPSS NUCLEAR PROJECT NO. 1 AND NO. 4 AND ARE LISTED IN TABLE 3.2.

POTEh7IAL RADIATION DOSES FROM WPPSS NUCLEAR PROJECT NO. 2 (FORMERLY HANFORD No. 2) WERE ESTIMATED USING THE RELEASES PRESENTED IN TABLE III-2 0F THE HANFORD NO. 2 FES.Q4)

IN THE IMMEDIATE VICINITY OF THE WPPSS NUCLEAR PROJECT NO. 1 AND NO. 4 DISCHARGE, THE GROSS ACTIVITY CONCENTRATION, EXCLUSIVE OF TRITIUM, IS ESTIMATED TO BE 1.3X10-3 PIC0 CURIES /ML. UNDER THE SAME CONDITIONS, THE TRITIUM CONCENTRATION WOULD BE 4.4 PIC0 CURIES /ML, AS STATED IN SECTION 5.2.2.

DURING NORMAL REACTOR OPERATIONS, A FRACTION OF THE NOBLE GASES PRODUCED WILL BE RELEASED IN THE LIQUID EFFLUENT AND SUBSEQUENTLY DISCHARGED INTO THE COLUMBIA RIVER. THE AEC DIRECTORATE OF REGULATORY OPERATIONS HAS ANALYZED OPERATING REACTOR RADIOACTIVE LIQUID EFFLUENT FOR NOBLE GAS CONTENT AND UNDER CONDITIONS

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'0F HIGHEST ANNUAL AVERAGE NOBLE CAS CONCENTRATIONS IN THE DISCHARGE WATER, NO SIGNIFICANT DOSES WOULD BE DELIVERED TO HUMAN BEINGS.

CONSUMPTION OF WATER REPRESENTS A POTENTIALLY SIGNIFICANT EXPOSURE PATHWAY TO THE POPULATION. THE NEAREST POTABLE WATER INTAKE THAT COULD BE AFFECTED BY THE PLANT LIQUID EFFLUENTS IS AT RICHLAND WHICH IS LOCATED 10 MILES SOUTH OF THE SITE.

INDIVIDUAL DOSES VIA THIS PATHWAY ARE EVALUATED USING STANDARD DOSE MODELS (REF. 4) AND AN ASSUMED DAILY CONSUMPTION OF 1.2 LITERS. DILUTION WAS CALCULATED USING THE MODELS DISCUSSED IN SECTION 2.5.

OTHER PATHWAYS OF RELATIVE IMPORTANCE INVOLVE RECREATIONAL USE OF RIVER IN THE VICINITY OF THE DISCHARGE ZONE.

INDIVIDUAL DOSES FROM CONSUMING FISH CAUGHT IN THE IMMEDIATE DISCHARGE AREA WERE EVALUATED USING THE BIOLOGICAL ACCUMULATION FACTORS LISTED IN TABLE 5.2.1 AND STANDARD MODELS (REF. 4).

SWIMMING, BOATING, AND RECREATIONAL USE OF THE SHORELINE IN THE DISCHARGE REGION WERE ALSO INCLUDED IN THE EVALUATION.

TABLE 5.3.1 SUMMARIZES THE POTENTIAL INDIVIDUAL DOSES FROM THE LIQUID EFFLUENTS.

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PAGE 9 TABLE 5.3.1 ANNUAL INDIVIDUAL DOSES FROM LIQUID EFFLUENTS LOCATION PATHWAY DOSE (MREM /YR)

TOTAL BODY GI TRACT THYROID BONE COOLANT FISH 1.5 0.057 0.042 1.0 DISCHARGE INGESTION (2.4)*

(0.11)

(0.29)

(1.7)

REGION RECREATIONAL USE OF 0.079 SHORELINE (0.13)

(500 HRS /YR)

SWIMMING 1.5x104 (100 HRS /YR)

(6.1x10 4)

BOATING 7.3x10-5 (100 HRS /YR)

(1.8x10-4) i hICHLAND WATER 3.9x10 4 1.9x104 4.3x104 1.9x105 INGESTION (4.1x10 4)

(2.2x10 4) (1.1x10 3) (4.5x10 5) i n'

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  • THE DOSE IN THE UPPER POSITION IN EACH ROW IS DUE TO WPPSS 1 AND 4 OPERATION.

THE DOSE IN THE LOWER POSITION (IN PARENTHESES) IS DUE TO WPPSS -1, 2, AND 4 OPERATION.

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J 5.3.3 CASEOUS EFFLUENTS RADI0 ACTIVE EFFLUENTS RELEASED TO THE ATMOSPHERE FROM THE PLANT WILL RESULT IN THE MOST SIGNIFICANT RADIATION DOSES TO THE PUBLIC. AEC STAFF ESTIMATES OF THE PROBABLE GASEOUS AND PARTICULATE RELEASES LISTED IN TABLE 3.3 WERE USED TO EVALUATE POTENTIAL DOSES. POTENTIAL RADIATION DOSES FROM WPPSS NUCLEAR PROJECT No. 2 (FORMERLY HANFORD NO. 2) WERE ESTIMATED USING THE RELEASES PRESENTED IN TABLE III-3 0F THE HANFORD NO. 2 FES(14)- ALL DOSE CALCULATIONS WERE PERFORMED USING ANNUAL AVERAGE SITE METEOROLOGICAL CONDITIONS AND ASSUMING THAT RELEASES OCCUR AT A CONSTANT RATE. RADI0 ACTIVE GASES ARE RELEASED NEAR GROUND LEVEL FROM THE PLANT.

THUS, DOSES RESULT FROM IMMERSION IN THE DISPERSED RADIOACTIVE GASES (REF. 6, 7).

THE PRIMARY FOOD PATHWAY TO MAN INVOLVES THE INGESTION BY DAIRY COWS OF RADI0 IODINE DEPOSITED ONTO GRAZING AREAS. CONSUMPTION OF MILK FROM THESE COWS CAN RESULT IN EXPOSURE TO THE HUMAN THYROID. DOSES TO A CHILD'S

- i, THYROID WHICH WOULD RESULT FROM CONSUMING ONE LITER OF MILX DAILY FROM A COW GRAZING 9 MONTHS ANNUALLY WERE CALCULATED FOR THE NEAREST FARM USING i

RECOGNIZED MODELS (REF. 6).

D ANOTHER FOOD PATHWAY TO MAN OF SECOND/.RY IMPORTANCE INVOLVES THE CONSUMPTION OF LEAFY VEGETABLES SUBJECT TO DEPOSITION OF THE RADIONUCLIDES RELEASED TO J

THE ATMOSPHERE. THE THYROID DOSE RESULTING FROM THE CONSUMPTION OF LEAFY VEGETABLES PRODUCED AT THE NEAREST FARM OR RESIDENCE DURING THE GROWING PERIOD WAS EVALUATED.

ALL DOSES DUE TO GASEOUS EFFLUENTS ARE SUMMARIZED IN TABLE 5.3.2.

5.3.4 COMPARISON OF CALCULATED DOSE WITH PROPOSED APPENDIX I DESIGN OBJECTIVES TABLE 5.3.3 SHOWS THE COMPARISON OF CALCULATED DOSES FROM PLANT OPERATION WITH PROPOSED APPENDIX I DESIGN OBJECTIVES. THE CRITICAL PATHWAY FOR THIS PLANT IS THE AIR-GRASS-MILK-INFANT THYROID PATHWAY, CALCULATED AT A LOCATION 4.3 MILES SE OF THE PLANT.

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I PAGE 11 TABLE 5.3.2 ANNUAL INDIVIDUAL DOSES DUE TO GASEOUS EFFLUENTS 3

LOCATION X/Q (SEC/M )

DOSE (MREM /YR)

TOTAL BODY SKIN THYROID' 0.061(1.2)*

0.28(2.5) 0.049(0.21)**

SITE BOUNDARY 1.8x106 (2.4 MI ESE)

NEAREST FARM 6.9x107 0.019(0.35) 0.10(0.80) 2.9(9.1)***

(4.3 MI SE)

NEAREST RESIDENCE 1.2x106 0.038(0.72) 0.18(1.6) 0.32(1.1)****

(3.3 MI ESE)

  • The first dose in each column is due to WPPSS 1 and 4 operation.

The second dose (ir, parentheses) is due to WPPSS 1, 2, and 4 operation.

    • Adult thyroid dose from inhalation of radioiodines
      • Infant thyroid dose from ingestion of milk and inhalation of radioiodines
        • Adult thyroid dose from inhalation of radiciodines and ingestion of green leafy vegetables.

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TABLE 5.3.3 COMPARISON OF CALCULATED DOSES FROM WPPSS 1, 2, AND 4 OPERATION WITH APPENDIX I DESIGN OBJECTIVE DOSES

  • CRITERION PROPOSED APPENDIX I

_ CALCULATED DOSES DESIGN OBJECTIVE A.

LIQUID EFFLUENTS DUE TO TOTAL BODY OR ANY ORGAN FROM ALL 5 mrem /yr 2.5 mrem /yr PATHWAYS B.

GASEOUS EFFLUENTS GAMMA DOSE IN AIR 10 mrad /yr 1.2 mrad /yr i

BETA DOSE IN AIR 20 mrad /yr 2.6 mrad /yr DOSE TO TOTAL BODY OF AN INDIVIDUAL 5 mrem /yr 0.72 mrem /yr i

DOSE TO SKIN OF AN INDIVIDUAL 15 mrem /yr 1.6 mrem /yr C.

RADI0 IODINE AND PARTICULATES DOSE TO ANY ORGAN FROM ALL PATHWAYS 15 mrem /yr 9.1 mrem /yr i

  • As presented in Concluding Statement of Position of the Regulatory Staff, Docket No. RM-50-2, February 20, 1974, pp. 25-30, U.S. Atomic Energy

' Commission.

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n, PAGE 13 5.3.5 DIRECT RADIATION 5.3.5.1 RADIATION FROM THE FACILITY THE PLANT DESIGN INCLUDES SPECIFIC SHIELDING OF THE REACTOR, HOLD-UP TANKS, FILTERS, DEMINERALIZERS AND OTHER AREAS WHERE RADIOACTIVE MATERIALS MAY FLOW OR BE STORED, PRIMARILY. FOR THE PROTECTION OF PLANT PERSONNEL. DIRECT RADIATION FROM THESE SOURCES IS THEREFORE NOT EXPECTED TO BE SIGNIFICANT AT THE SITE BOUNDARY.

CONFIRMING MEASUREMENTS WILL BE MADE AS PART OF THE APPLICANT'S ENVIRONMENTAL MONITORING PROGRAM AFTER PLANT START-UP. LOW LEVEL RADIOACTIVITY STORAGE CONTAINERS OUTSIDE THE PLANT ARE ESTIMATED TO CONTRIBUTE LESS THAN.01 MREM /YR AT THE SITE BOUNDARY.

THE PRINCIPAL SOURCES OF HUMAN EXPOSURE TO DIRECT RADIATION THAT WOULD RESULT FROM THE OPERATION OF THE WPPSS No. 2 STATION ARE THE HIGH PRESSURE TURBINES-0F THE BOILING WATER REACTOR. AS A CONSEQUENCE OF NUCLEAR REACTIONS OCCURING IN THE PRIMARY HEAT EXCHANGE LOOP OF THESE SYSTEMS (PARTICULARLY, THE 0-16 (N, P)

N-16 REACTION), ENERGETIC GAMMA RAYS ARE PRODUCED.

IN THEIR PASSAGE THROUGH THE CONTAINMENT AND THE ATMOSPHERE, THE FLUX IS ATTENTUATED AND THE GAMMA ENERGY IS DEGRADED.

ESTIMATES OF DIRECT RADIATION DOSE MAY BE OBTAINED USING VALUES MEASURED AT o ANOTHER SITE (REF. 13).

THE CLOSEST DISTANCE TO THE SHORELINE FROM THE PLANT

,f TURBINE IS ABOUT 18,000 FEET EAST. AT AN OPERATIONAL LEVEL OF 0.8 FOR THE PLANT, THE DIRECT RADIATION DOSE DELIVERED TO A PERSON BOATING AT THIS LOCATION FOR 500 HOURS PER YEAR IS ESTIMATED TO BE 4x10-5 MREM PER YEAR. ALL OTHER OFFSITE DIRECT RADIATION DOSES DUE TO OPERATION OF THE WPPSS NO. 2 STATION WILL BE LESS THAN THE ABOVE QUOTED VALUE UNDER THE SAME CONDITIONS.

a 5.3.5.2 TRANSPORTATION OF RADIOACTIVE MATERIAL THE TRANSPORTATION OF COLD FUEL TO A REACTOR, OF IRRADIATED FUEL FROM THE REACTOR TO A FUEL REPROCESSING PLANT, AND OF SOLID RADIOACTIVE WASTES FROM THE f.

REACTOR TO BURIAL GROUNDS IS WITHIN THE SCOPE OF THE AEC REPORT ENTITLED,

" ENVIRONMENTAL SURVEY OF TRANSPORTATION OF RADIOACTIVE MATERIALS TO AND FROM i

NUCLEAR POWER PLANTS". THE ENVIRONMENTAL EFFECTS OF SUCH TRANSPORTATION ARE SUMMARIZED IN TABLE 5.3.4 5.3.5.3 OCCUPATIONAL RADIATION EXPOSURE BASED ON A REVIEW OF THE APPLICANT'S SAFETY ANALYSIS REPORT, THE STAFF HAS DETERMINED THAT INDIVIDUAL OCCUPATIONAL DOSES CAN BE MAINTAINED WITHIN THE LIMITS OF 10 CFR 20.

RADIATION DOSE LIMITS OF 10 CFR 20 ARE BASED ON A THOROUGH CONSIDERATION OF THE BIOLOGICAL RISK OF EXPOSUEE TO IONIZING RADIATION.

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TABLE 5.3.4 ENVIRO !MEtlTAL IMPACT OF TRA!!SPORTATIOi 0F FUEL AtiD WASTEI TO Af;D FROM Ot:E LIGHT-WATER-COOLED f!UCLEAR PONER REACTOR a

. Nomal Conditions of Transport "l

Environmental Imoact Heat'; weight, and traffic density

- Negligible

[

Estimated Range of Doses Humber of to Exposed

- Cumulative Dose to

(

Exposed Persons Individuals 2 Exposed Population i

Population Exposed (per reactor year)

(per reactor year)3

?

Transportation l

workers 200 0.01 to 300 millirem 4 man-rem l

General public e.

Onicokers 1,100 0.003 to 1."3 millf rem )

3 man-rem Along Rcute 600,000 0.000i to U.00 mii nrem; 1 Data supporting this table are given in the Commission's " Environmental Survey of Transportation of Radioactive Materials To and From Huclear Power Plants," WASH-1238, December 197,2.

2The Federal Radiation Council has recommended that the radiation doses frca all sources of radiation other than natural background and medical exposures should be limited to 5,000 millirem per year for individuals as a result of occupational exposure and should be limited to 500 millirem per year for individuals in the general population.

The dose to individuals due to average natural background radiation is about 130 millirem per year.

3 Man-rem is an expression for the summation of whole body doses to individuals in a group.

Thus, if each member of a population group of 1,000 people were to receive a dose of 0.001 rem (1 millirem), or if 2 people were. to receive a dose of 0.5 rem (500 millirem) each, the total man-rem in each case would be 1 man-rem.

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, o, PAGE 15 MAINTAINING RADIATION DOSES OF PLANT PERSONNEL WIDlIN THESE EIMITS ENSURES THAT THE RISK ASSOCIATED WITH RADIATION EXPCSURE IS NO GREATER THAN THOSE RISKS NORMALLY ACCEPTED BY WORKERS IN OTHER PRESENT DAY INDUSTIGES (REF.10). USING INFORMATION COMPILED BY THE COMMISSION (REF.11) 0F PAST EXPERIENCE FROM OPERATING NUCLEAR REACTOR PLANTS, IT IS ESTIMATED THAT THE AVERAGE COLLECTIVE DOSE TO ALL ON-SITE PERSONNEL AT LARGE OPERATING NUCLEAR PLANTS WILL BE APPROXIMATELY 450 MAN-REM PER YEAR PER UNIT. THE TOTAL DOSE FOR THIS PLANT WILL BE INFLUENCED BY SEVERAL FACTORS FOR WHICH DEFINITIVE NUMERICAL VALUES ARS NOT.AVAILABLE.

THESE FACTORS ARE EXPECTED TO LEAD TO DOSES TO ON-SITE PERSONNEL LOWER THAN ESTIMATED ABOVE.

IMPROVEMENTS TO THE RADIOACTIVE WASTE EFFLUENT TREATMEITf SYSTEM TO MAINTAIN OFF-SITE POPULATION DOSES AS LOW AS PRACTICABLE MAY CAUSE AN INCREASE TO ON-SITE PERSONNEL DOSES, IF ALL OTHER FACTORS REMAIN UNCHANGED.

. HOWEVER, THE APPLICANT'S IMFLEMENTATION OF REGULATORY GUIDE 8.8 AND ODIER GUIDANCE PkOVIDED THROUGH THE STAFF RADIATION PROTECTION REVIEW PROCESS IS EXPECTED ~TO RESULT IN AN OVERALL REDUCTION OF TOTAL DOSES FROM THOSE CURRENTLY EXPERIENCED.

BECAUSE OF THE UNCERTAINTY IN THE FACTORS MODIFYING THE ABOVE EST1MAfE, A VALUE OF 900 MAN-REM WILL BE USED FOR THE OCCUPATIONAL RADIATION EXPOSURE FOR THE 2 UNIT STATION.

l A

5.3.1

SUMMARY

OF ANNUAL RADIATION DOSES b(ECOMBINEDDOSE(MAN-RDI)DUCTOGASEOUSEFFLUENTSTOALLINDIVIDUALSIIVING WITHIN A FIFTY MILE RADIUS OF THE PLANTS WAS CALCULATED USING THE PROJECTED 1980 POPULATION DATA FURNISHED BY THE APPLICANT (REF. 8). VALUES FOR THE MAN-REM DOSE AT VARIOUS DISTANCES FROM THE PLANTS ARE SUMMARIZED IN TABLE 5.3 5 PRESENTLY, ACCORDING TO THE APPLICANT, ABOUT 55,000 PEOPLE (RICHIAND AND'PASCO)

DERIVE THEIR DRINK!NG WATER FROM THE RIVER WIDIIN 50 MILES DOWNSTREAM OF THE PLANT. THE TOTAL EXPOSURE TO THIS POPUIATION WAS EVALUATED USING THE DRINKING WATER DOSE PRESENTED IN TABLE 5.3.1 AND APPLYING APPROPRIATE DILUTION FACTORS.

THE MAN-REM CONTRIBUTION FROM ODIER WATER INTAKES ON THE COLUMBIA. RIVER IS EXPECTED TO BE NEGLIGIBLE.

THE CUMULATIVE DOSE RESULTING FROM THE CONSUMPTION OF FISH HARVESTED FROM THE CEBUMBIA RIVER WAS ALSO ESTIMATED.

ACCORDING TO THE APPLICANT, IT IS ESTIMATED THAT 14,000 KG/YR (EDIBLE WEIGHT) 0F SPORTFISH IS HARVESTED WITHIN 50 MILES OF THE PLANT.

POPULATION DOSES FROM RECREATIONAL USE OF THE RIVER SHORELINE, AS WELL AS USE OF THE RIVER FOR SWD' MING AND BOATING, WERE ESTIMATED USING TOTAg USAGE ESTIMATES 0

SUPPLIED BY THE APPLICANT FOR THESE ACTIVITIES, VIZ., 2.24x10,1.32x10, AND 6.6x105 MAN-HOURS /YR, RESPECTIVELY. A DULITION FACTOR OT 6740 WAS APPLIED IN THIS INSTANCE ALSO.

THE POPULATION DOSE FROM ALL SOURCES INCLUDING NATURAL BACKGROUND, CLOUD IMMERSION, DRINKING WATER INCESTION, CONSUMPTION OF FISH, RECREATION, TRANSPORTATION, AND OCCUPATIONAL EXPOSURES IS SUMMARIZED IN TABLE 5.3.6.

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FACE 16 TABLE 5.3.5 CUMULAT1VE POPULATION, ANNUAL CUMULATIVE DOSE, AND AVERAGE AhKUAL TOTAL BOPY DOSE DUE TO GASEOUS EFF,6UENTS IN SELECTED ANNULI ABOUT THE PLANT CDfULATIVE CUMULATIV2 ANNUAL AVERAGE RADIUS POPUT.ATION CUMULATIVE DOSE ANNUAL DOSE (MILES)

(HAN-REM)

(MILLIREM) 1 0

0.0 0.0 (0.0) 2 0

0.0 0.0 (0.0) 3 0

0.0 0.0 (0.0) 4 38 0.0003 (0.0053)*

0.0079 (0.14) 5 138 0.001 (0,017) 0.0012 (0.12) 10 2868 0.006 (0,11) 0.0021 (0.038) 20 74,198 0.045 (0.78) 0.0006 (0,011)

-30 107,088 0.053 (0.92) 0.0005 (0.0086) 40 139,248 0.0$6 (0.97) 0.0004 (0.0070) j 50 197,018 0.061 (1.0) 0.0003.(0.0051)

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  • Dose in parentheses is due to WPPSS 1, 2 and 4 operation, while the other dose-is due to WPPSS 1 and 4 only.

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f PAGE 17 TABLE 5.3.6

SUMMARY

OF ANNUAL TOTAL BODY DOSES TO 111E POPULATION WITHIN 50 MILES CATEGORY POPULATION DOSE (MAN-REM /YR)

NATURAL ENVIR0h W AL RADI0 ACTIVITY 20,900 NUCLEAR PLANT OPERATION PIANT WORK FORCE 900 (1350)*

GENERAL FUBLIC GASEOUS CLOUD 0.061 (1.0)

DRINKINC WATER 0.022 (0.023) i FISH INGESTION

'O.002 (0.003)

RECREATION (FISHING, SWLWING, BOATING) 0.005 (0.006) o CONSUMPTION OF IRRIGATED CROPS 0.003 (0.005) l TRANSPORTATION OF NUCLEAR FUEL AND RADI0 ACTIVE WASTES 6 (9)

  • Dose in parenth Nes is due to WPPS$ 1, 2 and 4 operation, while the other dose b

is due to WPPSS 1 and 4 only.

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b 5,3,6 EVALUATION OF RADIOLOGICAL IMDACT THE AVERAGE ANNUAL DOSE FROM GASEQUS EFFLUENTS TO PERSONS'LIVING IN UNRESTRICTED AREAS WITHIN 50 MILES OF THE PLANT IS LESS THAN 0.01 MREM /YR AS SHOWN IN TABLE 5.3.5.

MAXIHUM INDIVIDUAL DOSES DUE TO LIQUID AND GASEOUS EFFLUENT RELEASES ARE LESS THAN 5 MREM /YR AS SEEN IN TABLES 5.3.1 AND 5.'3,2.

THESE VALUES ARE ONLY A FEW PERCENT OF THE NATURAL BACKGROUND EXPOSURE OF.100 REM /YR (REF. 12), ARE DEL 0n THE NORMAL VARIATION IN BACKGROUND DOSES AND REPRESENT NO MEASURABLE RADIOLOGICAL IMPACT.

3 USING CONSERVATIVE ASSUMPTIONS, THE TOTAL MAN-REM IN UNRESTRICTED AREAS FROM ALL EFFLUENT PATHWAYS, RECEIVED BY'THE ESTIMATED 1980 POPULATION OF 197,000 PERSONS WHO WILL LIVE WITHIN A FIFTY MILE RADIUS OF WPPSS NUCLEAR PROJECT NO. 1 AND NO. 4, WOULD BE ABOUT 6.1 MAN = REM PER YEAR.

BY COMPARISON, AN ANNUAL TOTAL OF ABOUT 20,900 MANaREM IS DELIVERED TO THE SAME POPULATION AS A RESULT OF THE AVERAGE NATURAL BACKGROUND DOSE RATE OF ABOUT.106 REM PER YEAR IN THE VICINITY OF WPPSS NUCLEAR PROJECT NO, 1 AND NO 4

?

THE 900 MAN-RtM ESTIMATED AS OCCUPATIONAL ON-SITE EXPOSURE IS A SMALL PERCENTAGE OF THE ANNUAL TOTAL OF ABOUT 20,900 MAN-REN i

DELIVERED TO THE 1980 POPULATION LIVING WITHIN A 50 MILE RADIUS OF HPPSS NUCLEAR PROJECT NO. 1 AND NO. 4.

1 EFFLUENTS FROM PLANT OPERATION WILL THEN BE AN CXTREMELY MINOR CONTRIBUTOR TO THE RADIATION DOSE THAT PERSONS LIVING IN THE AREA NORMALLY RECEIVE FROM NATURAL BACKGROUND RADIATION.

THE ESTIMATED RADIATION DOSES TO INDIVIDUALS AND TO THE POPULATION FROM NORMAL OPERATION OF THE STATION SUPPORT THE CONCLUSION IN SECTION 3.4 THAT THE RELEASES OF RADI0 ACTIVE MATERIALS IN LIQUID AND GASEOUS EFFLUENTS ARE AS LOW AS PRACTICABLE.

b

O PAGE 19 REFERENCES

1. "RADI0 ACTIVITY IN THE MARINF. ENVIRONMENT", PANEL ON R.I.M.E, OF THE COMMITICE ON OCCANOGRAPHY, NAS-NRC, 1971 2.' GARNER,R. J.3" TRANSFER OF RADI0 CTIVE MATERIALS FROM THE A

TERRESTRIAL ENVIRONMENT TO ANIMALS AND MAN", CRC CRITICAL REVIEWS IN ENVIRONMENTAL CONTROL, 2. 337-385(1971)

3. AUERBACH, S, J.t" ECOLOGICAL CONSIDERATIONS IN SITING NUCLEAR POWER PLANTS. THE LONG TERM BIOTA EFFECTS PROBLEMS", NUCLEAR SAFETY,.

12, 25(1971)

4. " RECOMMENDATIONS OF THE INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION",ICRP PUBLICATION 2, PERGAMON PRESS,1959 2

~5.* "THE EFFECTS ON POPULATIONS OF EXPOSURE TO LOW LEVELS OF IONIZING RADIATION", REPORT OF THE ADVISORY COMMITTEE ON BIOLOGICAL EFFCCTS OF j

IONIZING RADIATIONS, NAS=NRC, 1972 6.

ATTACHMENT TO CONCLUDING STATEMENT OF POSITION OF THE REGULATORY i

RULEMAKING HEARING ON:

NUMERICAL GUIDES FOR DESIGN OBJECTIVES AND LIMITING CONDITIONS FOR OPERATION TO MEET THE CRITERION "AS LOW AS PRACTICAB ACTIVE MATERIAL IN LIGHT WATER COOLED NUCLEAR POWER REACTORS, DOCKET N 3

FEBRUARY 20, 1974.

T. D.

H.' SLAOC, ED.p" METEOROLOGY AND' ATOMIC ENERGY, 1968", TID-24190

8. APPLICANTIS ENVIRONMENTAL. REPORT, SECTION 2.2 9

THOMPSON, S.

E.,

C.

A.' BURTON, D. J.

QUINN, AND Y. C. NG)

.nCONCENTRATION FACTORS OF CHEMICAL ELEMENTS IN EDIBLE AQUATIC ORGANISMS", UCRL = 50504 REV.' 1 (1972)

I 10.-" IMPLICATIONS OF COMMISSION RECOMMENDATIONS THAT 00SES BE KEPT AS LOW AS READILY ACHIEVASLE", ICRP PUBLICATION 22(1973)

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11. MURPHY, T.'D.7

" A COMPIL ATION OF GCCUPATIONAL RADI ATION EXPOSURE l

FROM LIGHT WATER C00 LEO NUCLEAR POWER PLANTSI 1969=1973",

U.S.A.E,C.,

WASH-1311 (MAY, 197/l) l l

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PAGE 20

12. OAKLEY, DONALD T., " NATURAL RADIATION EXPOSURE IN THE UNITED STATES",

ORP/SID 72-1, OFFICE OF RAD. PROG., U.S.E.P.A., JUNE,1972.

13. LOWDER, W. M., P. E. RAFT, AND C. V. GOGOLAK, "EEVIRONMENTAL GAMMA

. j RADIATION FROM NITROGEN-16 DECAY IN THE TURBINES OF A LRAGE BOILING WATER

{

REACTOR", HASL' TM 72-1, FEB.,- 1972

14. DIRECTORATE OF LICENSING, U.S. ATOMIC ENERGY COMMISSION, " FINAL ENVIRONMENTAL STATEMENT RELATED TO THE PROPOSED HANF0ED NUMBER TWO NUCLEAR POWER PLANT," DOCKET No. 50-397, DECEMBER 1972.

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i 6.1 Radiological Monitoring 6.1.1 Preoperational Program 1

The applicant has proposed an offiste preoperational radiological i

monitoring program to provide for measurement of background radiation 1

levels and radioactivity in the plant environs. The preoperational

' l program which provides a necessary basis for the operational radio-l logical monitoring program, will also permit the applicant to train personnel, evaluate procedures, equipment and techniques, as indicated in Regulatory Guide 4.1.

A description of the applicant's proposed program is summarized in Table 6.1.1.

Figure 6.1.1 shows the proposed sampling locations.

The applicant has provided a commitment to monitor the radioiodine pathways discussed in Section 5.3.4.

More detailed information on the applicant's radiological monitoring program is presented in section 6.1 of the applicant's Environmental Report. The applicant proposes to initiate the program two years prior to operation of the facility.

The Staff concludes that the preoperacional monitoring program proposed by the Applicant is adequate to provide baseline data which will assist 1

in verifying radioactivity concentrations and related public exposures after plant operation, and is therefore acceptable.

6.1.2 Operational Program j

The operational offsite radiological monitoring program is conducted to measure radiation levels and radioactivity in the plant environs.

L It. assists and provides backup support to the detailed effluent monitoring (as recommended by Regulatory Guide 1.21) which is needed I

to evaluate individual and population exposures and verify projected or anticipated radioactivity concentrations.

l The applicant plans assentially to continue the proposed preoperational program during the operating period. However, refinements may be made i

in the program to reflect changes in land use or preoperational l

monitoring experience.

t An evaluation of the applicant's proposed operational monitoring program will be performed during the operating license review, and the details of the required monitoring program will be incorporated into the Environmental Technical Specifications for the operating license.

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-2 6.1.3 Related Environmental Measurement and Monitoring Programs As indicated in a recent review by Corley(l), the Hanford Project environs has been the subject of intensive radiological environmental surveillance since 1945. These surveillance act.ivities have included the collection of samples of air, water, foodstuffs, and certain indicator media at numerous locations for gross and specific radio-nuclide analyses.

Since 1959, particular emph' asis has been placed on sampling and analysis of media in critical exposure pathways, permitting the routine preparation of composite environmental dose estimates (l).

Individual adult whole body and bone doses calculated from environmental

~

measurements around the Hanford Plant have generally decreased since 1963(2) from 0.06 and 1.3 mrem /yr, respectively (12 and 89 precent od dose standard (3))

to less than on.e percent of standard (<0.005 and <0.015 rem /yr, respectively) since 1971(4),

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8.

SAMPLING SUmfARY Sonste Treo Stettone sameltar tretueacy Analysts 4.

Sachareved

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Contievava Recording %

'(Backgrcund Ca m e b) TLD Seelmeters 13 Meathly - Annually j(Readout and Record 1(at Noted Frequency 3.

Air Y

a) Particolates 37

%g (Crees Alpha f

(Cross sera

, b) ledtse b

g, gI e

(Camma 5ces t

(taele fedtee 3.

River Water 5

Heathly (Suspeeded Cross Alpha

/

(Iaciudes Richland Water

(

Cross Seta Flaat Istake)

-(Dissolved Cross Alpha

(

Crose Beta (Camma Scan & Tritiue 4

Crois dwater and 6

sentaeaually (Crose Alpha Rataveter (as available)

(Cross seta 3

Heathly (Camme Scan & Tritium 3.

Vegetation & Livestock e) Estural vegetatten 10 3 samples Annually (Cross seta

.e (During Crowing Seasee) g~

(90$r b) Feed and Feed crepe 10 (During Crewing Seasee)

'(1311 (137 e C

s) heed Animale 5

(Duries Crowteg Seasse)

,Camme Scao

(

4.

set!

13 At Laast Annually (Cress Alpha (Crees Sete (90 r e

(137Ce (Camme Scan 7.

Sediment 3

Quarterly (Crees Alpha (Crose seta (90sr (Comme Scao 8.

Milk 4

Heathly

'(1311 i

(90 r (137 e C

(Elaneetal Caletim 9.

Aquat te ri..te al.ta ls..,.

3 Sealannually

'(Crose h ta (40s

6) %iet si 5

sessans. atty g,og, j

(Cenom Scan

13. 4:11411ta a) Ratbits or Substitute 3

Ann. ally Thyre.lJ - 111g Fenwr Ys C*ama Sea s, b) Watertewt 3

Annuallr g es*Ie - 12. &f n, p

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References I

i 1

Corley, J. P.

(Battelle-Northwest) ; "The Banford Environmental Surveillance Program", Proceedings of the Second AEC Environ-j mental Protection Conference (WASH-1332) ; Albuquerque, NM, April 16-19, 1974 (Issued July 1974).

2.

Essig, T. H., and S. K. Bhagat.

" Age Dependent Radiation Dose i

EsHmates for Residents of the Hanford Environs, 1945-1968",

BNWL-SA-3079. Battelle-Northwes t, Richland, WA; June 15, 1970.

3.

" Standards for Radiation Protection," AEC Manual, Chapter 0524, with Appendix.

U.S. Atomic Energy Commission, Washington, D.C.,

1963 (Revised October 1973).

4.

Nees, W. L. and J. P. Corley.

" Environmental Surveillance At Hanford for CY-1973", BNWL-1811. Battelle-Northwest, Richland, WA; April 1974.

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