ML20209G434

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Radioactive Effluent & Waste Disposal Rept Including Radiological Impact on Humans,Jan-June 1986
ML20209G434
Person / Time
Site: Pilgrim
Issue date: 06/30/1986
From: Bowman C, Sowdon T
BOSTON EDISON CO.
To:
Shared Package
ML20209G361 List:
References
NUDOCS 8609120471
Download: ML20209G434 (45)
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Text

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Pilgrim Nuclear Power Station Radioactive Effluent and Waste Disposal Report including Radiological Impact on Humans January 1 through June 30,1986 l

Environmental and Radiological Health and Safety Group Date: September 1,1986 BOSTON BEDISON ENERGY FOR TOMORROW \

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PILGRIM NUCLEAR POWER STATION RADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT INCLUDING RADIOLOGICAL IMPACT ON HUMANS JANL'ARY l THROUGH JULY 30, 1986 i

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Prepared by: [ #__ .

C. E./ Bowman Sen16r Radiological Engineer Approved by: M T.' L. Sow W Radiological Section Head Date of Submittal: September 1, 1986

. TABLE OF CONTENTS Section Page

1. Introduction and Summary 1
2. Effluent, Waste Disposal and Wind Data 1
3. Off-Site Doses Resulting From Radioactive Liquid Effluents 41
4. Off-Site Ooses Resulting From Radioactive Gaseous Effluents 46
5. Off-Site Ooses From Direct Radiation 67 LIST OF TABLES Table Paje Supplemental Information 2 IA Gaseous Effluents - Summation of All Peleases 3 l.

IB Gaseous Effluents - Elevated Release 4 IC Gaseous Effluents - Ground Level Release 5 2A Liquid Effluents - Summation of All Releases 6 2B Liquid Effluents 7 3 Solid Waste and Irradiated fuel Shipments a 4A 1 Distribution of Wind Olrections and Speeds - 33 ft. Level 9

- of 160 ft. Tower 4A-2 Distribution of Wind Directions and Speeds - 160 ft. Level 25 of 160 ft. Tower

1. . 3.2-1 January 1 - June 1986 Liquid Release Maximum Individual Doses 42

. from all Pathways for Adults (MREM) 3.2 2 January - June 19R6 Liquirl Ralpatot Marinum individual Dose 41

' rom all Pathways for Teenagers (MREM) 3.2-3 January - June 1986 Liquid Releases Maximum Individual Doses 44 from all Pathways for Children (MREM) 3.3-1 Population Ooses Resulting from the January - June 1986 45 Liquid Effluents i

LIST OF TABLES (cont.)

, Table Page 4.1-1 Undepleted Relative Concentrations per Unit Emission for 47 Reactor Building Vent for January - March 1986 4.1-2 Depleted Releative Concentrations per Unit Emission for 48 Reactor Building Vent for January - March 1986 4.1-3 Relative Deposition Concentrations per Unit Emission for 49 Reactor Building Vent for January - March 1986 4.1-4 Undeoleted Relative Concentrations per Unit Emission for Main Stack for January - March 1986 50 4.1-5 Depleted Relative Concentrations per Unit Emission for Main Stack for January - March 1986 51 1

' 4.1-6 Relative Deposition Concentrations per Unit Emission for 52 Main Stack for January - March 1986 h 4.1-7 Undepleted Relative Concentrations per Unit Emission for 53 Reactor. Building Vent for April - June 1986 4.1-8 Depleted Relative Concentrations per Unit Emission for 54 Reactor Building Vent for April - June 1986 l~ 4.1-9 Relative Deposition Concentrations per Unit Emission for 55 h ,,

Reactor Butiding Vent for April - June 1986 j 4.1-10 Undepleted Relative Concentrations per Unit Emission for 56

Main Stack for April - June 1986

, 4.1-11 Depleted Relative Concentrations per Unit Emission for 57 Main Stack for April - June 1986 4.1-12 Relative Deposition Concentrations per Unit Emission for 58 Main Stack for April - June 1986

[

Maximum Individual Locations and Pathways 59 f.2-1 ,

4.2-2 January - June 1986 Gaseous Release Maximum Individual Doses from all Pathways for Adults (MREM) 60 4.2-3 January - June 1986 Gaseous Release Maximum Individual Doses from all Pathways for Teenagers (MREM) 61 4.2-4 January - June 1986 Gaseous Release Maximum Individual Doses from all Pathways for Children (MREM) 62 4.2-5 January - June 1986 Gaseous Release Maximum Individual Dose from all Pathways for Infants (MREM) 63 11

. Table Page 4.2-6 January - June 1986 Gaseous Release Maximum Individual Doses 0.7 Miles W 4.3-1 Population Distribution 65 4.3-2 Population Doses Via Major Pathways Resulting from Gaseous Effluents during January - June 1986 66 Fy wb L .

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1. INTRODUCTION AND

SUMMARY

This report is issued for the period January - June 1986 in

  • accordance with NRC Regulatory Guide 1.21, " Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light Water Cooled Nuclear Power Plants" (Rev 1). The information supplied includes doses from liquid releases, doses from gaseous releases and direct gamma radiation doses.
3. EFFLUENT, WASTE O!SPOSAL AND HIND DATA Radioactive liquid and gaseous releases, wind speed data together with measurement errors and solid waste disposal information are i

given in Tables IA, IB, IC, 2A, 28, 3, 4A-1, 4A-2, and supplemental information section in the standard Regulatory Guide 1.21 format.

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EFFl.UENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental informatson JANUARY - JUNE 1986 Feethey hignm Nuclear Posee Station Ucenwe DPR 35 ,

1. Regulatoc> Unuts a Fmk'n and astnation rases Qs + Qv $1

.757E 0.10/E b lodinei 2ci/Qtr s

Perio ulates half Ines >* d.n l 13 (Q3 x 1.8E4 + Qy x 1.8E5) f I d laquid elliuents 10Ci/Qtr 2 Maumum Permanble Concenication Pioside the MR i uwd in delernuning allowable release talen vi sonsenitalnins a f mum and asfivalnin pses 10 CFR 20 b loJines Appendia D s Partsulates. half hses >= das s Table II i d. i equid eliluena s it . 3. x 10-s pc6/mi, all test.10 CF R 20, Appends: B. Table 11 2

3 Average Energs Proude lhe averaye encep> IU of the radionushde inntme in selease* on thsion and a,tivatkin pset it apph,able l' . u,,

4 Measurements and 4pproumaisons of Total Radioactmt)

Ptimde she inctlnidt used to nicasur or appmuniste she total radioastivity in elflucnin and ihe methods uwJ in deternune radionu.hJe somposition a l utnm and Jolivainin pset c,, y b lojines g,, n g, s Parti.utales L .

d bquideltluenin ^"F'

$ Balch Releam Pioude air sollowing information eelating so bahh releases o' tadina tive maittials in hquid and pawous efiluents a Uqwd i Number of baish relea** 143 2 1o:41inne perniJ tin baith releaset 368.7 lir.

. 1 Maumum time pein=1 for a bauh tel'** - 8.42 lir.

4 Aseraye inne period for bal6h teleaws 2, $7 ggy,

3. Minimum inme gnod fin a baish telcaw -

6 Astrate tiream flow dunnp periods of releaw ver $ gEih a flowmp stream 2.34E5 gpm ope b Gaseous (Not Appheable)

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6 Abnormal Releases

' b. N/A 2

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TABLE 1 A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES JANUARY - JUNE 1986 Quarter Quarter Est. Total Unit Error, %

' A. Fission and activation gases

1. Total release Ci *1.23r2 8.86r-1 M l
2. Average release rate for period pCi/sec *l.59El 1.13E-1

{ 3. Percent of Technical Specification limit  % *7.24E-3 1.13E-4 B. Iodines .

L 1. Total iodine.131 Ci 47.24E-3 46.50E-4 30 l

2. Average release rate for period uCi/see <9.19E-4 48.26E-5
3. Percent of Technical Specification limit  % < 3. 62 E- 1 <3.25E-2 C. Particulates A
1. Particulates with half lives > 8 days Ci <2.31E-3
  • 41.1SE-3 30 l
2. Average release rate for period pCl/sec <2.94E-4 * <l.46E-4
3. Percent of Technical Specification limit  % 5.43E-2 42.76E-2
4. Gross alpha radioactivity Ci
  • 5.00E-7

[ Cl *2.00E0 *2.00E0 42 I. 1. Total release l

2. Average release rate for period pCi/sec *2.54E-1 *2.54E-1 I 3. Percent of Technical Specification limit  % - -

l4 g .

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AEstimates 0

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TABLE 1B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT ( 1986 I GASEOUS EFFLUENTS - ELEVATED RELEASE JANUARY - JimE 1986 1

(

CONTINUOUS MODE BATCH MODE . t l Nuclides Released l Unit l Quarter } l Ouwter 2 l Ouwter l Quarter

  • Estimates
1. Fission gases krypton 85 Ci
  • 8.00E-3 **

krypton 85m Ci 1.62El **

krypton 87 Ci - **

krypton 88 Cl 9.88E0 **

xenon 133 Ci 8.74El **

xenon 135 Ci 7.30E-1 **

xenon 135m Ci - **

xenon 138 Ci - **

xenon 131m - Ci _ *,

xenon 137 Ci **

xenon 133m Ci - **

Total for period Cl

  • 1.14E2 **

,, 2. Iodines ** Plant Shutdown 2nd Quarter 1986 lodine 131 Ci 43.28E-3 42.23E-4 lodine 133 Ci 47.85E-3 <S.36E-4 lodine 135 Ci 4 5. 65 E-3 41.31E-3

[ <l.68E-z <2.09E-3 I Total for period Ci 7 3. Particulates

'< strontium 89 Ci 9.41E-5 *al.00E-4 strontium 90 Ci 1.92E-6

g cesium 137 Ci <1.92E-5 41.97E-5 barium lanthanum 140 Cl 43.24E-4 e5.9tE-5 chromium 51 Cl - -

manganew 54 Ci 3.5tE-6 45.24E-6 cobalt 58 Cl - <4.I6E-6 tron 59 Ci cobalt 60 Cl 49. 91 E-5 45.60E-5 sine 65 C1 - -

zirconium nlobium 95 Ci - -

cerium 141 Ci - -

cerium 144 Ci . .

ruthenium 103 Ci . _

ruthenium 106 Ci - -

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  • Estimates 6

e TABLE 1C .

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT h986)

GASEOUS EFFLUENTS . GROUND LEVEL RELEASE JANUARY - JUNE 1986 CONTINUOUS MODE BATCH MODE Nuclides Released Unit Overter Overter Overter Overter

1. Finalon saws krypton 85 Ci . .

, krypton 85m Cl 7.97E-1 -

j krypton 87 Ci 2.48E0 -

krypton 88 Ci 2.64E0 -

xenon.133 Cl 1.46 EO -

xenon.135 Ci 3.92E0 8.86E-1 xenon.135m ' Cl . .

xenon.138 Ci .

Total for period Cl 1.13El 8.86E-1 2.lodines

., todine 131 Ci 4 3.96E-3 4 4.27E-4 todine 133 Cl 42.55E-2 4,8.89E-4 lodine 135 Ci 44.60E-2 4 5.58E-3 Total for period Cl 47.55E-2 46.90E-3 i

3. Particulates strontium.89 Cl 1.96E-4 2.00E-4*

strontium.00 Cl 1.08E-6 1.00E-6*

f. reslum.134 Ci . .

cesium.137 Cl < 6. 59E-5 4 6.64E-5 barium. lanthanum.140 Ci <1.27E-3 4 5.55E-4 manganese.54 Ci <l.23E-5 c1.18E-5 l cobalt.58 Cl - < l . 4 71'.-5 tron.59 Cl 4 3.78E-6 cobalt.60 Cl < l . 86E-4 4 5.38E-5 ame.65 Cl - -

airconium.ntobium.95 Cl . .

cerium 141 Cl 4.00E-5 -

ruthenium.103 C1 - -

ruthenium 106 Cl . .

  • Estimaton

t TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1986)

LIOUlD EFFLUENTS SUMMATION OF ALL RELEASES ,

JANUARY - JUNE 1986 Quarter Quarter Est. Total Unit g 2 Error. %

A. Fission and activation products

1. Total release (not including tritium. Ci noble gases. or alpha) 4 7.39E-2 4 4.75E-2* 30
2. Average diluted concentration pct /ml during period 41.07E-8 4 5.54E-9*
3. Percent of applicable limit  % 4 7.39E-1 4 4.75E-t*

l-. B. Tritium

1. Total release Ci 5.90E0 6.00E0* 30
2. Average diluted concentration pCi/mi i

. 8.60E-7 7.00E-7*

, during period

3. Percent of applicable limit 4 8.60 7.00*

! C. Dissolved and entrained gases

1. Total release Cl 1.30E-3 7.56E-3 40
2. Average diluted concentration pCl/ml

(" .89E40 8.82E-10 I.. during period

3. Percent of applicable limit  % - -

D. Gross alphe radioactivity e 1.4/E-4 l l 1. Total release l Cl l 2.41E-4*{ 40 l E. Volume of waste released (prior liters g

i to dilution)

, F. Volume of dilution water used liters 6.86E9 8.57E9 20 i during perim!

  • Estimatoa  !

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e TABLE 2B .

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1986)

LIQUID EFFLUENTS JANUARY - JUNE 1986 CONTINUOUS MODE BATCH MODE Nuchdes Released Umt Quarter 1 Quarter 2 Ouarter Quarter strontium 89 Ci <2.02E-4 < 2. 00E-4*

strontium 90 Ci 46.86E-5 <7.00E-5*

cesium 134 Ci 4.26E-4 9.4ar-6 cesium 137 Ci 9.44E-3 1.57E-3 _

iodine 131 Ci 8.49E-4 7.81E-5 t

cobalt 58 -

Ci 8.13E-5 5.68E-4 j

t cobalt 60 Cl 7.86E-3 6.78E-3 tron 59 Ci - 3.06E-4 strontium- 83 - Cl t_97p y -

manganese 54 Ci 7.64E-5 1.23E-3

. chromium 51 Ci - 1.06E-3 zirconimum niobium 95 Ci 2.56E-6 -

iodine-135 4.58E-4 -

Ci barium lanthanum.140 Ci 1,19g-$ -

cerium 141 Ci 1.72E-6 1.43E-5 lodine 133 Ci 2.50E-3 7.89E-5 certum 144 Ci - -

silver 110m Ci - 2.67E-4 ___

tron 55 Ci 42.80E-2 -

l unidentified Ci 2.39E-2 3.41E-2 Total for period (above) Ci 47.39E-2 4.63E-2*

xenon 133 Cl 1.73E-4 1.71E-3 menon 135 Ci 1.13E-3 5.85E-3

  • Estimaten 7

TABLE 3 EFFLUENT AND HASTE DISPOSAL SEMI-ANNUAL REPORT (1985)

SOLID HASTE AND IRRADIATED FUEL SHIPMENTS JANUARY - JUNE 1986 A. SOLID HASTE SHIPPED OFF SITE FOR BURIAL OR DISPOSAL. (not irradiated fuel)

1. TYPE OF HASTE UNIT 6 MONTH EST. 10TAL PERIOD ERROR %
a. Spent resins, filter sludges, m' 157.054 evaporator bottoms, etc. Cl 383.914 N/A
b. Dry compressible waste, m' 286.426 contaminated equipment, etc. C1 1.121 N/A
c. Irradiated components, m' O.000 control rods, etc. C) 0.000 N/A
d. Other (Describe) m' O.000 i

miscellaneous low-level waste Cl 0.000 N/A

2. ESTIMATE OF MAJOR NUCLIOE COMPOSITION.

(by type of waste)  % C1 y a. Spent Resin, Filter Sludges, Co-60 50.53 1.94E+2 m Evaporator Bottoms, etc. Co-58 11.22 4.31E+1 Cs-137 14.69 5.64E+1

.g Cs-134 1.64 6.28E+0 Fe-59 1.57 6.02E+0

[' 1-131 0.09 3.42E-1 La-140 0.22 8.59E-1

}, Ba-140 0.10 3.81E 1 4 Sr-90 0.07 2.65E-1

. Tc-99m 0.01 2.86E-2 Zn-65 1.19 4.56E+0 Mn-54 11.07 4.25E+1 Ni-63 0.71 2.73E+0 Zr-95 .025 .13152 Cr-51 6. f3 2.43E.1 Ce-141 0._04 1.53E-1 xe-131m 0.28 1.09E+0

' A3-133 0.66 9.56E-3 Pu-241 0.16 6.06E-1 Cm-242 0.00 3.75E-3 C-14 0.0) 2.61E 1 Transuranics 0.01 2.52E-2 Total 100% 383.914 ,

8A

. Table 3 (Continued)

2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION.

(by type of waste) (continued)

% Ci

b. Dry Compressible Waste Co-60 61.54 6.77E-1 Contaminated Equipment Co-58 0.99 1.08E-2 Cs-137 21.20 2.33E-1 Cs-134 1.44 1.58E-2 Sr-90 0.32 3.49E-3 Tc-99 0.00 2.99E-5 Mn-54 3.14 3.46E-2 Cr-51 1.53 1.68E-2 Pu-241 0.98 1.07E-2 Cm-242 0.00 7.00E-6 C-14 3.01 3.03E-2 I-129 0.00 2.16E-2 H-3 4.98 5.47E-2 N1-63 0.86 9.49E-3 g Transuranics 0.03 2.79E-4 TOTAL 100 % 1.121
c. Irradiated Components Control Rods, etc.

N/A

d. Other (Solidified C1) f Miscellaneous Low Level Waste N/A
3. SOLIO HASTE DISPOSITION Number of Shipments Mode of Transcortation Destination 37 Tractor - Trailer Barnwell, S.C.
4. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination 8

None N/A N/A 88

TABLE 4A-1 DISTRIBUTION OF HIND DIRECTIONS AND SPEEDS FOR THE 33 FT. LEVEL OF THE 160 FT. TOWER (Data will be provided at a later date) i L .

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TABLE 4A-2 DISTRIBUTION OF WIND DIRECTIONS AND SPEEDS FOR THE 160 FT. LEVEL OF THE 160 FT T0HER (Data will be provided at a later date) f

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3. OFFSITE DOSES RESULTING FR0" RADI0 ACTIVE LIQUID EFFLUENTS 3.1 General Dose Assessment The methods and parameters used to calculate the off-site doses are presented in the Appendix I analysis for Unit #'.

Population data are based upon the 1980 census data'; effluent .

releases are given elsewhere in this report.

Numerical constants used in the analyses have been updated to conform to Revision 1 of Regulatory Guide 1.109 dated October 1977.

3.2 Maximum Individual Doses The maximum individual doses and pathways considered are shown in Tables 3.2-1 through 3.2-3.

3.3 Populatien Doses i The population doses are shown in Table 3.3-1.

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1 See References #1 pg. 68 3 See Reference #3 pg. 68 41

Table 3.2-1 4

January - June 1986 Liquid Release Maximum Individual Doses From All Pathways for Adults (MREM) i Pathway Bone Liver Thy gid Kidney Lung GI-LLI Skin Total Body <

l Salt Water fish i

Salt Water Shell Fish l Discharge Canal

! Shoreline To be provided later.

Ocean Shoreline Deposits

! Swimming 1 .

l Boating i

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Table 3.2-2

! January - June 1986 Liquid Release Maximum Individual Doses from All Pathways for Teenagers (MREM)

Pathway Bone Liver Thyroid Kidney Lung GI-tLI Skin Total Body Salt Water fish Salt Water Shell Fish Discharge Canal Shoreline To be provided later.

Ocean Shoreline Deposits Swinuning 4

Boating Iotal 43

. p w og g p r -- .3 - - ,.

Table 3.2-3 i January - June 1986 Liquid Release Maximum Individual

{ Doses from_All Pathways for Children (MREM) i Pathway Bone Liver Thyroid Kidney M GI-LLI Skin Total Body Salt Water

Fish Salt Water Shell Fish Discharge Canal Shoreline To be provided later.

Ocean Shoreline Deposits Swimming Boating Total i

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, Table 3.3-1 Population Doses Resulting From The January - June 1986 Liquid Effluents Pathway Thyroid Total Body (MAN-REM)

Salt Water I Fish Salt Water Shell Fish Salt Water To be provided later.

Plants i Ocean Shoreline Deposits l Swimming E Total i

NOTE: These are the major pathways for liquid effluents.

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4. OFF-SITE DOSES RESULTING FROM RADI0 ACTIVE GASEOUS EFFLUENTS 4.1 General Dose Assessment The methods and parameters used to calculate the off-site doses are .

presented in the Appendix I analysis for Unit #1'. The gaseous releases for both reactor building vent and the main stack, for the period January - June 1986, are elsewhere in this report.

Meteorological information for calculating dispersion of these releases are shown in Tables 4.1-1 through 4.1-12. For each quarter year, values of X/Q, X/Q depleted and D/0 are tabulated for twenty-three radial distances at sixteen compass directions using the AEOLUS program which was provided to Boston Edison by Yankee Atomic Electric Company.

AEOLUS is a computer code for evaluating atmospheric dispersion of routine radioactive effluents from commercial nuclear power stations,

[ and for computing statistical distributions of radiation doses which

( would result from postulated accidental releases of assumed intensity. The code is based, in part, on Regulatory Guide 1.111 developed by the U.S. Nuclear Regulatory Commission as guidance toward Implementation of Appendix I to 10 CFR Part 50 and the "as low as reasonably achievable" objectives. Table 4.1-1 through 4.1-12 are based on data taken at the 160 ft. elevation for the main stack and the 33-foot elevation for the reactor building vent.

4.2 Maximum Individual Doses The maximum individual dose locations and pathways assumed are presented in Table 4.2-1. The resultant maximum individual adult, teenage, child and infant doses are reported in Tables 4.2-2 through f 4.2-5. In the summary Table 4.2-6, doses for skin and total body; individual organ doses are due to iodine and air particulates only.

4.3 Population Doses The assumed population distribution is shown in Table 4.3-1 and is

^ based upon 1980 Census Data for the permanent population.' The 3

population doses by pathway are presented in Table 4.3-2.

In accordance with Regulatory Guide 1.21, only pathways yielding significant contribution to the total dose have baen included; those pathways not included account for a total of less than 57. of the overall population doses.

t 1 See References #1 pg. 68 3 See Reference #3 pg. 68 46

.. TABLE 4.1-1

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UNDEPLETED RELATIVE CONCENTRAT10NS PER UNIT EMISSION FOR REACTOR BUILDING VENT FOR January - March 1986 f (Data to be provided at a later date) i I

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TABLE 4.1-2

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. DEPLETED RELATAIVE CONCENTRATION PER UNIT

.. EMISSION FOR REACTOR BUILDING VENT FOR JANUARY - MARCH 1986 4

8 (Data to be provided at a later date) e L ..

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. . - - - ...-. - .-. = - .

i TABLE 4.1-3 l l

e RELATIVE DEPOSITION CONCENTRATIONS PER UNIT EMISSION FOR REACTOR BUILDING VENT FOR JANUARY - MARCH 1986  :

1 l

(Data to be provided at a later date)

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TABLE 4.1-4

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. UNDEPLETED RELATIVE CONCENTRATION PER UNIT EMISSION FOR MAIN STACK FOR JANUARY - MARCH 1986 (Data to be provided at a later date) i i

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TABLE 4.1-5 DEPLETED RELATEVE CONCENTRATIONS PER UNIT EMISSION FOR MAIN STACK FOR JANUARY - MARCH 1986 o

(Data to be provided at a later date) l I

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

. TABLE 4.1-6 '

4

)

RELATIVE DEPOSITION CONCENTRATIONS PER UNIT

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EMISSION FOR MAIN STACK FOR JANUARY - MARCH 1986 1

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TABLE 4.1-7 UNDEPLETED RELATIVE CONCENTRATIONS PER UNIT

~

EMISSION FOR REACTOR BUILDING VENT FOR APRIL - JUNE 1986 7

(Data to be provided at a later date)

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TABLE 4.1-8 DEPLETED RELATIVE CONCENTRATIONS PER UNIT

, EMISSION FOR REACTOR BUILDING VENT APRIL - JUNE 1986 f (Data to be provided at a later date) l 1

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TABLE 4.1-9 RELATIVE DEPOSITION CONCENTRATIONS PER UNIT EMISSION FOR REACTOR BUILDING VENT FOR APRIL - JUNE 1986 O

(Data to be provided at a later date) 4 m

w 1

r.

F L ,

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TABLE 4.1_10 UNDEPLETED RELATAIVE CONCENTRATIONS PER UNIT

, EMISSION FOR MAIN STACK FOR APRIL - JUNE 1986

) (Data to be orovided at a later date) 1 L .

F

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1

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1 0

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TABLE 4.1-11

- l DEPLETED RELATIVE CONCENTRATIONS PER UNIT

~

EMISSION FOR MAIN STACK FOR APRIL - JUNE 1986 )

e 4

(Data to be provided at a later date) h t

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TABLE 4.1-12 RELATIVE DEPOSITION CONCENTRATIONS PER UNIT EMISSION FOR MAIN STACK FOR APRIL - JUNE 1986 (Data to be provided at a later date) i i

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Table 4.2-1 -  !

. Maximua Individual Locations and Pathrays'

'Janu'ary - June 1986 P_athway 0.7 Miles 0.6 Miles 2.2 Miles H ESE H Noble Gas Immersion Yes Yes Yes Inhalation Yes Yes Yes l

i l

Garden Yes Yes Yes Meat No No No ,

i Cows Milk No No Yes I

I Goats MIIk No No No i

1. Yy indicates that the pathway is analyzed.

No indicates that it is not considered.

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Table 4.2-2 January - June 1986 Gaseous Release Maximum Individual Doses from All Pathways for Adults (MREM) 1 Location Bone Liver Thyroid Kidney Lung GI-LLI Skin Total Body i ,

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1 ,

  • 0.7 Miles N

i 0.6 Miles ESE To be provided later.

i 2.2 Miles W

i 3

  • MaxTmum dose location 1

i- 60 i

1

. ~ -

w q y== m - -- -

Table 4.2-3 January - June 1986 Gaseous Release Maximum Individual Doses from All Pathways for Teenagers (MREM)

Locati_on Bone Liver Thyroid Kidney L_ung GI-LLI Skin Total Body

  • 0.7 Miles W

0.6 Miles ESE To be provided later.

2.2 Miles H

~' ~

' Maximum' dose location 61

. - - q p - -- -

Table 4.2-4 January - June 1986 Gaseous Release Maximum Individual Doses from All Pathways for Children (MREM) location Bone Liver Thyroid Kidney Lung GI-LLI Skin Total Body

  • 0.7 Hiles H

0.6 Hiles ESE To be provided later.

2.2 Miles H

~~

  • Hanimum dese location ~~ '~ .

62

- ~

m W y== m --

E ,

Table 4.2-5 January - June 1986 Gaseous Release Maximum Individual Doses _From All Pathways for Infants (MREM)

Location Bone Liver Thyroid Kidney Lung GI-LLI Skin Total Body

  • 0.7 Miles W

0.6 Miles ESE To be provided later.

l i

2.2 Miles N

~ - - ~ ~ ~ ~ ~ " " ~ ~

  • Ma x 15udi ~doie~ loca t ion '

63

y d_o B

l

. a t

T o

n i

k S

l a I o u L d L i -

v _ I i G d _

n I

- m u

i m

x g a n M u

- L e

s 6 a

- e l

2 e) 4 Rm e . 4 e sR y r 6 l um e e b o(. n t a

- a e d

-; T ss i l ae K

. G s_ d o e 6D d 8 i g 9 1

v o

r e p n d u i i_ e J o b m y T

h r

y T

o r

a u

n A J a

r e

- i L

v

=

e n

o B

p u r o

r e

g t G_ t a d n l n I a e u e t f g d e h n A A T C I

. l

~ ~ , , , o ~

. 3 . . .

. . . G. e. 3 .

l 2 W9 *N = 5, 9= W 5 I M 99 o.

~ - ., -- -

. ~

O w

~

5 e

@ e 9

~. 3 .

. G. e. G. G. ~.

.. Ie I - .~ - ~ $

J.

- ee A A J a a a 4 a 4 4 4 i A a; i e

.O - @ . * @ . - - - .O 0 e

.. e.~ I.

~ .- I.. +. -. -..~..

.e

.Y

. ~.

.. . A.

g; - - e -

~

s 3 t. 3 3 3 $. $. $. 3 3 G. $.

W 5 W 5 M

. .. I. E. -W. . ~. .. f. 5.

. . . . I. . . ~. .

, es - - - - - - - - - - - * - - - -

.f . .,

C e. ~

-i Il 4 c,

E:. :. . .

~.-. . 3 .

  • a a m x=

-~.~.yy=x3

_s

~

        • 9 g

ii:

3 -

L -

. s: .

xnmy3

. g - - -

.n, ~. ~ .

s. .n, ~ - .

P.

i. e

- ~ .

I. N. I. *,

P

.~. .. .~. ~.. .~. .. .

~.

em I. N. ,* N. ,* *

  • n .,. .N.

--~~-~

~

0 V

- e.

. ~. .

T ** I. I. I. -

- - - ~ .

7

- ~

P.

~ m c.

.se .en . . e.e

e. . 3 I R. S.

g - -. -

l an .a A 3s = $R l.IW .

N N 6

Table 4.3-2 Population Doses Via Major Pathways Resulting From Gaseous Effluents During January - June 1986 Pathway Thyroid Total Body 9 (MAN-REM) (MAN-REM)

{ Noble Gas Immersion (gamma)

I' i

l To be provided later.

Ground Plane Deposition B

Inhalation sid l

66

,- 5. OFF-SITE DIRECT RADIATION Doses due to direct radiation as measured by thermoluminiscent ,

dosimeter for the period January - June 1986 were as follows:

' Dose Rate (uR/hr)

Near Plant (0.-0.16 Miles from the Plant) Data to be provided at a Exclusion Area (0.25-0.68 Miles from the Plant) later date.

Distant Neighborhood (0.7-6.5 Miles from the Plant)

Background (8-21 Miles from the Plant)

E .

l The measured values for the last two quarters indicate a small but L measurable dose contribution due to direct radiation at Near Plant Locations (within 0.16 miles) but no statistically significant contribution beyond about 0.25 miles.

{

u.

" r J

67

~

REFERENCES

1. " Pilgrim Station Unit 1 Appendix Evaluation" Submitted in Accordance with 10 CFR 50 Appendix I, April 1977.

f

(

2. Pilgrim Station Environmental Report, Amendment 4, April 1975, pg.

2-329/330.

3. "An Update of Population Distribution Around the Pilgrim Site,"

prepared for Boston Edison by HMM Associates, July 31, 1981, ppg. 2-3 o., and 2-7.

I.,

t i *.

Le lI I

68 f

l l

Regulatory Affairs and Programs

,,v Correspondence Control Sheet

,. Outgoing E Letter 2.86.124 Distribution:

J. E. Howard J. D. Keyes H. F. Brannan A. L. Oxsen Licensing File w/a PNPS Doc. Control w/a H. S. Stowe Yankee Atomic w/a NUS Corporation w/a t % 9/e n 'cht 7: = a H. Wendland (ANI) w/a Peter Walsh J. M. Fulton w/a A. Shatas w/a R. Tis w/a (3 copies)

T. L. Sowdon w/a C. Gustin w/a (6 copies)

C. E. Bowman w/a (5 copies)

NRC Inspector (PNPS) w/a(2 copies)

External Distribution w/a John A. Zwolinski (NRC) (6 copies)

Commonwealth of Massachusetts Department of Labor and Industries Mr. Robert Maletta Mass. Division of Water Pollution Control Robert Hallisey Mass Department of Public Health (2 copies) occuum Mr. Robert Lawton ELEASED Mass. Division of Marine Fisheries 1 I SEP 051986 I t Mr. David McCurdy FOR USE Yankee Atomic- o 03 2 Mr. Edward Cumming Yankee Atomic

Subject:

Radioactive Effluent and Waste Disposal Report for the Period January I through June 30, 1986

. Issued: 8/28/86 Summary: This report is required by Tech. Spec. 6.9.C.1 (Reg. Guide 1.21)

Keywords: REG GUIDE 1.21 EFFLUENT RA&P

Contact:

M. T. Lenhart Classification: C Assignments / Commitments Proeide updated report including Met. Tower Data and Calculations for submittal to the NRC.

Responsibility: T. Sowdon Plan Due RA&P: NA Date Due RA&P: 9/30/86 Date Due NRC: ASAP

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