ML20097A374

From kanterella
Jump to navigation Jump to search
Radioactive Effluent & Waste Disposal Rept Including Radiological Impact on Humans for Jan-June 1984
ML20097A374
Person / Time
Site: Pilgrim
Issue date: 06/30/1984
From: Lunn B, Sowdon T
BOSTON EDISON CO.
To:
Shared Package
ML20097A344 List:
References
NUDOCS 8409130255
Download: ML20097A374 (15)
v • d • e


Text

F' j

. I j

^

PILGRIM NUCLEAR POWER STATION RADIOACTIVE EFFLUENT AND WASTE-DISPOSAL REPORT INCLUDING RADIOLOGICAL IMPACT ON HUMANS JANUARY I THROUGH JUNE 30,;1984 Prepared by: 82-b [Mw Brian P. Lunn Health Physics Engineer Approved by:82# A XM dr_b ~ ~

T. L. So(don Environmental & Radiological Health & Safety Group Leader Date of Submittal: September 1, 1984 8409130255 840831 1 PDR ADOCK 05000293 R PDR

~ - . .

-, 1 . - -, -

~TABi.E 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 9
4. Off-Site Doses Resulting From Radioactive Gaseous Effluents 10
5. Off-Site Doses From Direct Radiation 12 LIST OF TABLES Table Page Supplemental Information 2 1A Gaseous Effluents - Summation of All Releases 3 ,

1B Gaseous Effluents - Elevated Release 4 1C Gaseous Effluents - Ground Level Release 5 2A Liquid Effluents - Sumation of All Releases 6 2B Liquid Effluents 7 3 Solid Waste and Irradiated Fuel Shipments 8 4.3-1 Population Distribution 11 Note: Tables 4A-1, 4A-?., 3.2-1, 3.2-2, 3.2-3, 3.3-1, 4.1-1 through 4.1-12, 4.2-1 through 4.2-6, and 4.3-2 will be provided at a .

later date. I i

77~

v m

1. INTRODUCTION'AND

SUMMARY

This report is issued for the period Janaury - June 1984 in accordance with NRC Regulatory-Guide-1.21, "Heasuring, 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 it quid releases, doses from gaseous releases;and direct gamma radiation doses.

2. EFFLUENT, WASTE DISPOSAL AND WIND DATA Radioactive liquid and gaseous releases, wind speed data together with measurement errors and solid waste disposal information are 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.

l I

, ;e

  • EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information January - June, 1984 Facility Pilgrini Nuclear Power Station Ucensee DPR.35
1. - Itegulatory Units
a. Fissnin and activation gaws: QS + .Ik pI 0.25/ E 0.10( T b- todmes: 2Ci/ Quarter c.

Particutaies. hair.hves >8 days: 13(1.8E4Qs+1.8E5Qq ) s I

d. laquid efiluents:

10C1/ Quarter 2 Masimum Permissible Concentration Piovide the MK's used in detertraning allowable sclease rates or concentratoms.

a. Fission and activation paws: _10 CFh 20
h. lodmes: Appendix B
c. Part sculates, half.hves >M days: Table 11
d. Liquid efthent 11 3 = 1 X 10-5 pCl/ml; all rest,10 CFR 20, Apperidia B. Table II
3. Average Energy Proside the average energy IU of the radionuchde mniure in scleasesof fission and acuvation gases. il apphcabhE..t.w, N/A
4. Measurements and Approsimations of Total Radioactivity Provide the methods used to measure or appmumate the total radioactiuty in et0uents and the nwihods used to determme radamuchde composition..
a. Fission and activ:nion gases. g,
b. lodmes:

Istopic

c. Particulates:

Analysis

d. Liquid e(Guents:
5. Batch Releases Pmvide lle lollowmg informatson relatmp to hatch releases of radniactive matenals in liquid and gaseous ef0uents.
a. Uquid
1. Number of hatch relcaws: 324 2- Totalim* l*"od 'o' ha'ch reled*5: 1425.55 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br />
3. Maumum time period for a batch releaw: - 76.-50 hours
4. Average time perk >d for batch releases:

5.

4.40 h w s Mmimum linw penod for a hatch relcaw: - 10 minutes

6. Average stream now dunng periods of relcaw of effluent into a flow mg stream-5. 27E4GPM
b. Gawous (Not Applicable)
6. Abnormal Relesws a.None
b. None 2

TABLE 1 A EFFLUENT AND WASTE DISPOSAL SEMlANNUAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES JANUARY - JUNE 1984 Quarter Quarter Est. Total Unit 1 2 Error, %

A. Fission and activation gases

1. Total release Ci *
  • l
2. Average release rate for period gCi/sec
3. Percent of Technical Specification limit  %

B. Iodines

1. Totallodine-131 Ci < 4. 74E-R
  • 75 l
2. Average release rate for period uCi/sec < 9.14 E-6
3. Percent of Technical Specification limit  % < 2. 37E-3 C. Particulates
1. Particulates with half-lives > 8 days Ci <1.1RE-3 1.37F-3 30 l
2. Average release rate for period pCi/see < 2. 28E-4 5.29E-4
3. Percent of Technical Specification limit  % <0.05 <0.05
4. Gross alpha radioactivity Ci 7.15 E-7 <1.19E-6 D. Tritium
1. Total release Ci 1.28E0 1.89E-1 40 l
2. Average release rate for period pCi/sec 1.63E-1 2.40E-2
3. Percent of Technical Specification limit  % - -
  • Plant shutdown on 12/10/83 - no releases 3

J :.  ;

1 TABLE 1B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT ( 1984 I GASEOUS EFFLUENTS - ELEVATED RELEASE

, JANUARY - JUNE 1984 CONTINUOUS MODE BATCH MODE l Nuclides Released l Unit l Quarter -1l Quarter-2 l Ouarter - l Quarter l

1. Fission gases krypton-85 _ Ci krypton 85m Ci krypton 87 Ci *
  • xenon-135m Ci *
  • Total for period Ci * *
2. Iodines iodine 131 Ci < 6.19E-6
  • Total for period Ci < 6.19E-6 *
3. Particulates strontium 89 Ci <1.52E-4
  • Ci 3.04E-6 barium lanthanum-140 Ci < 9.60E-6
  • chromium 51 Ci -

manganese 54 Ci 1.24E-6

tron 7iD Ci cobalt 60

  • Ci 8.13E-6 zinc-65 Ci -

cerium 141 Ci -

  • cerium 144 Ci -

ruthenium 103 Ci -

ruthenium 106 Ci -

  • 4

7--

SB*

TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1984)

GASEOUS EFFLUENTS GROUND LEVEL RELEASE JANUARY - JUNE 1984 CONTINUOUS MODE BATCH MODE

- Nuclides Released Unit Quarter g Quarter Quarter Quarter.1

1. Fission gases krypton 85 Ci *
  • Cl *
  • krypton-88 Ci Ci
  • Ci *
  • xenon-135 xenon 135m Ci Ci
  • Total for period Ci
2. Iodines iodine-131 Ci *

<4.12E-5 iodine-133 Ci iodine-135 Ci Total for period Ci < 4.12E-5

3. Particulates strontium-89 Ci < 1.28E-6 < 6.90E-7 strontium 90 Ci <1,94E-7 1.23E-6 cesium 134 Ci 1.24E-5 1.02E-5 cesium 137 Ci 1.46E-4 1.17E-4 barium lanthanum 140 Ci < 5.07E-3 -

manganese 54 Ci 2.11E-4 1.73E-4 cobalt-58 Ci 2.84E-5 9.39E-6 fron 59 Ci -

cobalt-G0 Ci 5.54E-4 8.29E-4 zine-65 Ci - 2.26E-4 zirconium niot. .m95 Ci cerium 141 Ci . -

ruthenium 103 Ci - -

ruthenium 106 Ci -

  • Plant Shutdown on 12/10/83 - no releases 5
  • *- . JANUARY - JUNE 1984-TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Q984 ) ~

LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Quarter Quarter Est. Total Unit p Error, %

}

A. Fission and activation products

1. Total release (not including tritium, Ci noble gases, or alpha) 1.61E0' 7.01E-2 30
2. Average diluted concentration pCi/ml during period 1.05E-7 4.01E-8
3. Percent of applicable limit  % 16.10 0.70 B. Tritium
1. Total release Ci l'00E1

. 4.57E-1 30

2. Average diluted concentration pCi/ml during period 6.54E-7 2.61E-7
3. Percent of applicable limit 4 6.54 2.61 C. Dissolved and entrained gases
1. Total release Ci (a) (a) l
2. Average diluted concentration pCi/ml

- ~

during period

3. Percent of applicable limit  %

D. Gross alpha radioactivity l 1. Total release l Ci l < 3.60E-4 l < 7. 54E-5 l 40 l E. Volume of waste released (prior liters 7.26E6- 9.99E5 20 to dilution)

F. Volume of dilution water used liters 20 1.53E10 1.75E9 during period (a) No measurable releases.

6

4 e ..- ,

TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1984)

LIQUID EFFLUENTS JANUARY'- JUNE 1984 CONTINUOUS MODE BATCH MODE Nuclides Released Unit - Quarter Quarter Quarter 1 Ouarter 2 strontium 89 Ci < 3.08E-4 < 4.50E-5 strontium 90 Ci 1.83E-3 < 9. 63 E-5 cesium-134 Ci 2.80E-3 1.80E cesium-137 Ci 7.89E-2 7.02E-3 iodine 131 Ci 8.20E -

cobalt 58 Ci p_7ar-p 7.07E-4 cobalt 60 Ci 8.41E-1 4.19E-2 iron-59 Ci 5.57E-3 -

zine 65 Ci 1.61E-3 3.77E-4 manganese 54 Ci 8.33E-2 3.13E-3 chromium 51 Ci 2.62E-5 1.61E-5 zirconimum niobium 95 Ci molybdenum 99- . .

technetium 99m Ci barium lanthanum 140 Ci 1.29E-6 -

cerium 141 Ci 2.23E-3 -

iodine-133 Ci - -

cerium 144 Ci 2.08E-3 -

silver 110m Ci

~

iron 55 Ci 4.55E-1 1.24E-2 l unidentified l Ci l l l 1.09E 4.22E-3 Total for period (above) Ci 1.61E0 7.01E-2 xenon 133 Ci - -

xenon 135 Ci - -

7

4 .- ,

TABLE 3 EFFLUENT AND WASTE DISPOSAL' SEMI-ANNUAL REPORT (1984)

SOLIO WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY - JUNE 1984 A. SOLIO WASTE SHIPPED OFF SITE FOR BURIAL OR DISPOSAL. (not irradiated fuel)

1. TYPE OF WASTE UNIT 6 MONTH EST. TOTAL PERIOD ERROR %'
a. Spent resins, filter sludges. m' 82.12 evaporator bottoms, etc. Cl- 311.39830 N/A
b. Dry compressible waste, m' 1241.55 contaminated equipment, etc. C1 29.16550 N/A
c. Irradiated components, m' control rods, etc. Cl N/A N/A
d. Other (Describe) m'

-miscellaneous low-level waste Cl N/A N/A

2. ESTIMATE OF MAJOR NUCLIOE COMPOSITION.

(by type of waste)  % E(Curies)

a. Spent Resin, Filter Sludges, Co-60 44.505 138.58645 Evaporator Bottoms, etc. Co-58 2.116 8.4579 H-3 0.046 0.14254 Cs-137 32.869 102.35222 Cs-134 2.549 7.93936 C-14 0.026 0.08098 Fe-59 0.196 0.60939 I-131 0.004 0.01180 I-129 0.010 0.03110 La-140 0.064 0.20060 Nb-95 0.010 0.03181 Zr-95 0.007 0.02066 Sr-90 7.441 23.17074 Ni-63 1.403 4.37051 Tc-99m 0.010 0.03110 Mo-99 - -

Zn-65 1.698 5.28686 Mn-54 3.874 12.06298 Cr-51 2.148 6.68872 Np-239 0.004 0.01180 Pu-241 0.372 1.15971 Ru-103 0.008 0.02609 Cm-242 0.017 0.05187 Sb-124 0.023 0.07307 TOTAL 100.000 311.39830 8A

J ,

TABLE <3 (continu;d) 1 ..

% E(Curies)

b. Dry Compressible Waste Co-60 43.719 12.73023 Contaminated Equipment Co-58 7.620 2.21876 Cs-137 7.882 2.29517 Cs-134 0.499 0.14529 Fe-59 1.315 0.38298 I-131 0.021 0.00626 Ba-140 0.506 0.14720 Sr-90 0.167 0.04859 Tc-99m 0.012 0.00357 Zn-65 4.564 1.32893 Mn-54 5.032 1.46510 Nb-95 0.058 0.01692 Zr-95 0.027 0.00788 Cr-51 25.950 7.55626 Ce-141 0.149 0.04338 Ru-103 0.036 0.01061 51-63 0.744 0.21663 Pu-241 0.374 0.=10874 Cm-242 0.010 0.00286 I-129 0.)l0 0.00296
  • C-14 0.018- ~~

0.00532

  • H-3 1.068 0.35797 Cs-136 .009 0.00275 Sb-124 .128 0.03724 Aq-110 .082 0.02390 TOTAL 100.000 *29 16550
c. N/A
d. N/A
3. SOLID WASTE DISPOSITION Number of Shipments Mode of Transportation Destination 52 Tractor - Trailer Barnwell, S.C.
4. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None N/A N/a

  • C-14 and H-3 activities were not considered as part of the total percent for the first several shipments of 1984, but were listed separately on shipping documents. These separate totals have been added to the Curie column for this report.

8B

g , - - - - -

-)

,e

3. lOFF-SITE DOSES RESULTING FROM RADIOACTIVE-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 #1'.

' Population dataLare 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 Population Doses The population doses are shown in Table 3.3-1.

4 l

i P

9 L_.

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

- presented in the Appendix I analysis for Unit #1 1. The gaseous releases for both reactor building vent and the main stack, for the period January - June 1984, 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/Q 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 ef fluents f rom 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 220 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 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.3 The 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 been included; those pathways not included account for a total of less than 5% of the overall population doses.

10

__...._..,-,.y_ _ _ _ - . , _ , - _ , - - . - , . _ . ,_,m. __ . _ ~ , . ~

9 '. e 4 .

=rt T N N 9 A e tr9 ar*

O O N O O O- O O O O 6 e e e e 4 e ~ e e e es

' O ned as =# ad e, and N e .ma #

@' ' art art S $ 4 9 P **

W ** ** C3 .

49 O. M. .

O. art .=N=

. . d. . . . - e O O O

O.. O O. a*

art O - M T a= M a= d e E*

  • N T

N s==

N c N W urt urt # @ ef9 O O't M C O O O O O O + e

+ + + e o +

Oe w. end =s .e

.# end ens ins .ad and q - - -

A . ned g e. . es c'9 ==

W

, O. O. 3 a=. d. M.

w

=*

. N. O. .

O. O O

M.

M.

a=

et.

ett O af9 a'= - Pm M W a= a= a= W ** O MN M

4 e

M M M w g e P9 C

A O

e eO O

are O

g O O O -O O' e

O e

& e e e + e e *

  • e

.no e had end sad had nas .ad and .mo and end and M e e @ N e N N T af9 ert P' o.

O. d.

=rt M c.

N am

.w Q.

p O.

q

d. . O.

N e.

N g

g. g.

w.

m N.

m e.

erg g en.

a=

NM N

C e

9 9 W M M 9 ~ W W N M w O O O O O O O O O O O e e e e e e o

  • e *

=s e d d ims =a and =d

.ao one ame O e @ d e9 4 4 M N d s= c0 O O. N. d. #. N. . a=. e. d. .

c4 N

M.

As . .

am a= a= .= se N c9 O O === -

gr9 O

== e C O O ef9 am N

se M E' wt M N N r 8'9 3; O O O O M e M O

==*

t.

er e e e O O O O'9 e

.e o e e o me w # as and .ms

==D' y e. e a= N and . end M

end ens ed9 et Ba E @ P.

ar9 g

.===  % W9. . t'l. dr9 O. d. #. . . M.

r # N P. g gne

== ar9 == O. O O. O O. O. O. == &

e em O= en M,-- A+ O w mee .= N O' E ==

w

=*

  • a bg N 4 ==. N P9 N O ==

M (f - N O O O 44 sd O O O O e e O. e e e o e as c w tad =# ied and.

e p g 8

and.

e has

- N - O O

.= n 31 um e.

or9

O. t's. . . . . . . ==.

.%g e ef9. O. N. .

M N e

w ** e ==

e 0 C C O O O. O a S eN N O w

N an.

f89 a= s= O P9 O O O O O e e o e o and and tad sta and c9 O O O =rt er9 N, . O.

ar9. a= M. O. . . . . . .

O. N M == Q O O O O O O O O.

MN art O d c4 e

ari a= N N N == N N As O O O O O O O O e o e e e + e o and and taif end end and and d

tad tr9 uS O O P9 O.rt un9. e.

3 M. N. M.

O O

O

. e=. M.

=rt NM N N - N e o O O O O N

O e

am O

== as asm O

O O O O e e

+ e + + med ned med und and .es d O O O O O **

ef9. O.

s*

  • er9

. . . . . . . . . a=.

N O O O O O O O O O. *=

a= w M C M 8== st

.=

T N em N

a* == N a= O O O O O O e e

+ e e e ens ame e'=

O

. . . ==. .

A, m.. . . . . .

O O O O. art a-v O O

O ar9 a= a= c. O. O

> 2 l

8

- d ha6 %ad A

ens 3 3

2 5 E g E tad had tad had d brI t/9 @ t/l 4 I

5. < OFF-SITE DIRECT RADIATION Doses due to direct radiation as measured by thermoluminiscent dosimeter for the period January - June 1984 were as follows:

Dose Rate (uR/hr)

Near Plant (0 -0.16 Miles from the Plant) 15.5 Exclusion Area (0.25-0.68 Miles from the Plant) 5.4 Distant Neighborhood (0.7-6.5 Miles from the Plant) 6.8 Background (8-21 Miles from the Plant) 6.6 The measured values for the first two quarters indicate a small but 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.

6 1

l 4

l 12 4

, . -~.--____m

r y

. j REFERENCES

s

/

1. "P* syrim Station Unit 1 Appendix I Evaluation" Submitted in Accordance wi".h 10 CFR 50 Appendix 1, April 1977.
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 HM Associates, July 31, 1981, ppg. 2-3 and 2-7.

1 13 k

Retrieved from "https://kanterella.com/w/index.php?title=ML20097A374&oldid=2782771"