Text

Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989
	ML20011F656
Person / Time
Site:	Brunswick
Issue date:	12/31/1989
From:	Harness J; CAROLINA POWER & LIGHT CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	BSEP-90-0128, BSEP-90-128, NUDOCS 9003070090
	Download: ML20011F656 (60)
	v • d • e

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E, Carolina Power & Light Company

[,

Brunswick Nuclear Project b

P. O. Box 10429 i

Southport, NC 28461-0429

- February 23, 1990 e

FILE: B09-135100 SERIAL:- BSEP/90-0128 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555 v.

BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2 DOCKET NOS. 50-325 AND $0-324 LICENSE NOS. DPR-71 AND DPR-72 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gentlemen:

Enclosed is the Semiannual Radioactive Effluent Release Report for Brunswick Steam Electric Plant covering the period from July 1, 1989, through December 31, 1989.

This report is submitted for the Brunswick Steam Electric Plant in accordance with Technical Specification 6.9.1.8.

Very truly yours, I

-1 Aww J. L. Ilarness, General Manager Brunswick Nuclear Project Til/mcg Enclosure

.cc:

Mr. S. D. Ebneter Mr. E. G. Tourigny BSEP NRC Resident Office 9003070090 901231 h

PDR ADOCK 05000324 y*

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PDC

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i 1

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m Brunswick Steam Electric Plant semiannual. Radioactive Effluent Report July 1, 1989 to December 31,1989 i

ATTACHMENTS:

PAGES:

1. Supplemental Information 1/1 to 1/5

)

2. Effluent and Waste Disposal Data 2/1 to 2/14 j

3. ODCM and PCP Revisions 3/1 j

4. Environmental Monitoring Program 4/1 to 4/3 j

q

5. Inoperable Effluent Instrumentation 5/1 to 5/4 l

6. Major Modification to Radioactive Waste 6/1 Treatment systems

7. Meteorological Data 7/1 a

8.-Annual Dose Assessment 8/1 t

?

.c W

=.

'd b

ATTACHMENT 1 Supplemental Information July 1,1989 to December 31,1989 9

1/1 w--_-________________-__-.

1 s -.

.o EFFLUENT WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information Facility:

Brunswick Steam Electric Plant Licensee Carolina Power and Light Company

1. Regulatory Limits A. Fission and activation gases (Technical Spec. 3.11.2.2)

(1) Calendar Quarter (a) 10 mrad gamma (b) 20 mrad beta (2) Calendar Year (a) 20 mrad gamma (b) 40 mrad beta B.

Iodine-131, iodine-133, tritium, and particulates with half-lives greater than eight days (Technical Spec. 3.11.2.3)

(1) Calendar Quarter (a) 15 mrom to any organ (2) Calendar Year (a) 30 mrom to any organ (3) Calendar Quarter for Burning Contaminated 011 (a) 436 uCi (4) Calendar Year for Burning Contaminated 011 (a) 872 uCi C. Liquid effluents (Technical Specification 3.11.1.2)

- (1) Calendar Quarter (a) 3 mrom to total body (b) 10 mrom to any organ (2) Calendar Year (a) 6 mrom to total body (b) 20 mrom to any organ NOTE:

Dose calculations are determined in accordance with the Off-Site Dose Calculation Manual (ODCM)

Used for percent of technical specification limit determinations in Table 1A.

- Used.for percent of technical specification limit determinations in Table 2A.

1/2 l

d

2.' Maximum permissible concentrations and dose rates which determine maximum instantaneous release rates.

A. Fission and activation games (Technical Specification 3.11.2.1.a) e (1) 500 mrom/ year to total body (2) 3000 mrom/ year to the skin i

l B.

Iodine-131, iodine-133, tritium, and particulates with half-lives greater than eight days (Technical Specification 3.11.2.1.b)

(1) 1500 mrom/ year to any organ C.

Liquid effluents (Technical Specification 3.11.1.1)

The concentration of radioactive material released in liquid effluents to unrestricted areas after dilution in the discharge canal shall be limited to the concentrations specified in 4

10CFR20, Appendix B, Table II, column 2, for radionuclides other than noble gases.

4

- (1) Tritium:

MPC = 3 E-03 uCi/ml and 1

- (2) Dissolved and entrained gases:

MPC = 2 E-04 uCi/ml

3. Measurements and Approximations of Total Radioactivity A. Fission and activation gases Analysis for specific radionuclides in representative grab samples by gauma spectroscopy.

B. Iodines Analysis for specific radionuclides collected on charcoal cartridges by gamma spectroscopy.

n C.

Particulates l

Analysis for specific radionuclides collected on filter papers l

by gamma spectroscopy.

D. Particulates for Burning Oil Analysis for specific radionuclides by grab samples of each batch of oil to be burned.

E.

Liquids Effluents Analysis for specific radionuclides of individual releases by gamma spectroscopy.

Used as applicable limits for Table 2A I

1/3

... ~

'e 9

i

=NuclOOr C0unting ctatictic3 cro rcp;rtOd utilizing 1-cigm3 Crrer.

Totti

. error where reported represents a

best effort to approximate the total of all individual and sampling errors.

i

4. Batch Releases 1

l A. Liquid (see Note 1 on page 1/5)

(1) Number of batch releases:

1.91E+02 1

(2) Total time period for batch releases:

1.88E+04 Minutes i

(3) Maximum time period for a batch release:

1.79E+02 l

Minutes (4) Average time period for a batch release 9.87E+01 Minutes j

(5) Minimum time period for a batch release:

1.00E+00 Minutes (6) Average stream flow during periods l

of release of effluent into a flowing stream 5.78E+05 GPM B. Gaseous (1) Number of batch releases 0.00E 00 Minutes (2) Total time period for a batch release 0.00E 00 Minutes (3) Maximum time period for a batch release 0.00E 00 Minutes (4) Average time period for a. batch release 0.00E 00 Minutes (5) Minimum time period for a batch release 0.00E 00 Minutes

5. Abnormal releases A. Liquid (see page 1/5 for explanation)

(1) Number of releases:

2.00E 00 (2) Total activity released:

1.71E-03 Curies B. Gaseous (1) Number of releases:

0.00E 00 (2) Total. activity released:

0.00E 00 Curies 1/4

one release was made-from the Storm Drain Collector Basin during the month of September due to heavy rainfall from hurricane Hugo.

The release lasted 881 minutes and released an estimated 1.18E+06

. gallons of water containing 8.81E-04 curies of activity to the Discharge Canal.

Close monitoring of the actual release rate was not possible due to high winds attained during the hurricane.

j l

1 One release was caused by a small leak from the Unit #1 Reactor Building closed Cooling Water (RBCCW) System via a leak' in the RBCCW/ Service Water Heat Exchanger.

The leak was due to dezinci-j fication of a tube sheet plug.

The heat exchanger was repaired and the leak was stopped.

Note 1 - The summation of batch releases in section 4.A on page 1/4 does not include the abnormal releases.

1 i

l 1/5 4

4 4

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ATTACHNENT 2

[

Effluent and Waste Disposal Data Brunswick Steam Electric Plant t

July 1, 1989 to December 31, 1989 i

Table 1A:

Gaseous Effluents - Summation of all Releases Table 13:

Gaseous Effluents - Elevated Releases Table 1C:

Gaseous Effluents - Ground Level Releases Table 2A Liquid Effluents - Summation of all Releases Table 3B:

Liquid Effluents Lower Limits of Detection i

Table 3:

Solid Waste and Irradiated Fuel Shipments Combustion of Waste Oil 2/1 i

TQb10 1A r

Effluont Ond Woot0 Dicp30G1 SamionnuG1 RCport YOQr 1989 Gaseous Effluents - Summation of all Releases I

Est.

Total Unit

,QtJ:, J.

,Q1r, _(,

Error.%

A. Fission Juri Activation Gases

1. Total release ci 5.47E+02 1.59E+02 1.15E 02

2. Average release uCi/sec 6.88E+01 2.00E+01 rate for period

3. Percent of technical specification limit 9.00E-02 3.50E-02 B. Iodines

1. Total I-131 Ci 4.58E-03 1.86E-03 7.00E 01

2. Average release uCi/E4c 5.76E-04 2.34E-04 rate for period C.

Particulates

1. Total release Ci 8.68E-03 2.55E-03 7.00E 01

2. Average release uCi/sec 1.09E-03 3.21E-04 rate for period

3. Gross alpha C1 1.39E-05 2.87E-06 D. Tritium

1. Total release Ci 6.08E+00 5.48E-01 7.00E 01

2. Average release uCi/sec 7.65E-01 6.89E-02 rate for period E.

Iodine-131. Iodine-133. Tritium JuyL Particulates

1. Total Release Ci 6.12E+00 5.62E-01

2. Average release uCi/sec 7.67E-01 7.07E-02 rate for period

3. Percent of technical specification limit 1.68E-01 7.10E-02 F. Particulates 3 dbl Burnina Contaminated Sdl,

1. Total Release ci 0.00E+00 0.00E+00

2. Average release rate for period uCi/sec 0.00E+00 0.00E+00

3. Percent of technical specification limit 0.00E+00 0.00E+00 2/2

- -.. ~.

Tchio la

.Efflu nt Cnd W20t0 Dicp 001 Semicnnu31 R p3rt YOOr 1989 Gaseous Effluents - Elevated Releases l

Continuous Release Nuclides Released Unit Ida;jl 33ut JL -

I

1. Fission Gases argon-41 Ci 2.22E+00

<LLD krypton-85m Ci 2.85E+01 2.49E-02 krypton-87 Ci 3.92E+00 3.12E-01 l

krypton-88 Ci 2.87E+01

<LLD j

xenon-133 Ci 1.17E+02 1.85E+00 xenon-135m Ci 2.60E+01 1.75E+01 xenon-135 C1 1.22E+01 8.24E+00 xenon-137 Ci 1.57E+02 6.84E+01 xenon-138 JLL 3.99E+01 3.10E+01

-l total for period C1 4.15E+02 1.27E+02 l

2.

Iodines i

iodine-131 Ci 3.81E-03 1.52E-03 iodine-132 C1 1.25E-02 1.57E-03 iodine-133 C1 1.81E-02 7.25E-03 iodine-134 Ci 2.56E-03

<LLD iodine-135 Sj, 2.20E-02 7.74E-03

(

total for. period Ci 5.90E-02 1.81E-02 3.

Particulates chromium-51 Ci 5.27E-04 7.83E-05 I

manganese-54 C1 1.64E-05 1.24E-04 cobalt-58 Ci 6.42E-06 6.09E-06 cobalt-60 Ci 2.99E-05 1.59E-04 strontium-89 Ci 3.85E-04 1.11E-04 strontium-90 Ci 2.17E-06 1.31E-06 cesium-134 C1 1.51E-05 6.82E-07 cesium-137 Ci 2.45E-05 4.78E-05 barium-140 Ci 8.04E-04 1.06E-04 lanthanum-140

.gi.

5.82E-04_ 7.52E-05 total for period C1 2.39E-03 7.09E-03

4. Tritium hydrogen-3 Ci 2.56E+00 8.77E-02 2/3

x Toblo-1C LBffluent_and Waste Disposal Semiannual Report-

-Year 1989-Gaseous Effluents - Ground Level Releases:

Continuous Release-Nuclides Released Unit

,Qtr1

,Q 1 r_ 1

1. Fission AluMUL

_ xenon-133 C1 1.59E+01

<LLD

- xenon-135m C1 1.35E+01~ 1.47E+01 yenon-135 JLL 1.03E+02 1.69E+01-total for-period!

Ci 1.32E+02 3.16E+01-

2. Iodines iodine-131 Ci 7.74E-04 3.35E-04 iodine-132 Ci 4.17E-03' 1.32E-03 iodine-133 Ci 5.'83E-03.

2.24E-03 iodine-135 jll 7.43E-03 2.30E-03 total for period Ci 1.82E-02 6.20E-03

3. Particulates chromium-51 Ci 5.58E-03 5.38E-05

' maganese-54' Ci-1.80E-04 9.01E-04 cobalt-58 Ci 1.09E-04 7.60E-05 cobalt-60 Ci 3.87E-04 7.12E-04 iron-59 Ci 1.50E-05 6.51E strontium-89 Ci 6.06E 2.85E niobium-95 Ci

<LLD 3.08E-06 cesium-137--

Ci

<LLD 2.53E-05 barium-140 Ci 6.19E-06

<LLD lanthanum-140 Ci 5.27E-06

<LLD

. cerium-141 JLL 1.52E-06

<LLD total for period Ci

.6.29E-03 1.84E-03

4. Tritium-'

. hydrogen-3 Ci 3.52E+00 4.60E-01 2/4 L

g

.I

-l Tchlo 2A

~., ;

.. Effluent ~and Waste Disposal Semiannual Report Year 1989 Liquid Effluents - Summation of.all Releases

.?

Unit

.atI.2.

_Gttr i

.Is1.T91 t

JL Error Tm

'A.. Fission'.93L Activation hef,

Products seh ao

1. Total-release (excluding Ci 7.58E 1.12E-01 3.50E 01 j

+

tritium, gases, & alpha)

2. Avg.' diluted conc.

uCi/ml 3.63E-09 5.51E-09

(

3.

Percent limit-7.30E-02 3.33E-01 t

i B. Tritium

~

1. Total' release Ci 7.64E+00 2.84E+00 4.00E 00

2. Avg. diluted conc.

.uci/ml 3.66E-07 1.40E-07

3. Percent limit 1.22E-02 4.67E-03 I

?

Dissolved JgyL Entrained Gases l

C.

1. Total release Ci 3.22E-02 9.74E-02 3.50E 01.

2. Avg. diluted conc.

uCi/ml 1.54E-09 4.80E-09 l

3. Percent limit 7.70E 2.40E-03 g

i i

+

D.-Gross aloha radioactivity 1., Total release ci

< LLD'

< LLD 4.00E 01 i

E. Volume JUL waste liters 9.51E+06 8.57E+06-1.25E 01 1

JUL dilution water p

F. Total (used durina released ldut averace dil. cone.)

liters 2.09E+10 2.03E+10 1.30E 01 G. Volume JdL coolina water liters 4.69E+11 2.23E+11-discharaed from clant u

L 1;

1 L

2/5 L.

i

TABLE 2B-o,~ :F.ffluent and: Waste-Disposal Semiannual Report Year. 1989 Liquid Effluents

. Batch Mode Nuclides Rele& Sed Unit

.Q t l ;L

,Qtr.L 1._ Fission Jy31 activation Droducts sodium-24 Ci 6.93E-04

<LLD-chromium-51.

Ci 2.74E-02 6.42E-03

' manganese-54 C1 1.09E-02 3.27E-02 iron-55 Ci 1.33E-03 1.89E-03 manganese-56 C1 3.15E-05

<LLD-cobalt-58 Ci 3.28E-03 9.40E-03 iron-59 Ci 8.95E-04 9.98E-04 cobalt-60 Ci 1.66E-02 4.62E-02 arsenic-76 Ci 4.84E-05 1.52E-04 strontium-89 Ci 3.33E-05 5.39E-05 strontium-90 Ci

-1.63E-05

<LLD yttrium-91m Ci 1.63E-04 5.33E-04 yttrium-92 Ci 1.57E-03 8.37E-03 strontium-92 Ci 1.78E-05 4.30E-05 niobium-95 Ci

<LLD 2.54E-05 niobium-97 Ci

<LLD 8.63E-04 technetium-99m Ci 1.13E-03 1.34E-04 technetium-104 Ci 8.32E -9.19E-05 ruthenium-105 Ci:

<LLD 3.77E-04 silver-110m Ci 2.89E-05 1.52E-05 iodine-131 C1 1.02E-03 3.14E-05 iodine-132 Ci

<LLD 2.75E-05 iodine-133 Ci 6.02E-04 2.93E-04 cesium-134 C1 4.57E-03 1.14E-03

iodine-134 Ci 4.04E-05

<LLD iodind-135 Ci 9.30E-05 9.53E-05 cesium-136 Ci 4.74E-05

<LLD cesium-137 C1 4.63E-03 1.44E-03

. lanthanum-140-Ci 1.65E-04 2.70E-04 cerium-141 Ci

<LLD 8.47E-06 lanthanum-142 Ci 1.41E-05 1.10E-04 cerium-144 Ci 1.79E-04

<LLD tunasten-187 jdk 2.98E-04'

<LLD total.for period C1 7.58E-02 1.12E-01

2. Gases xenon-133 Ci 6.61E-03 1.59E-02 xenon-133m Ci 3.41E-05 1.39E-04 xenon-135m Ci 4.79E-04 4.83E-04 xenon-135 Jil 2.51E-02 8.09E-02 total for period C1 3.22E-02 9.74E-02 2/6

x L

E Lower Limits of Detection

~.

July through December 1989 uCi/ml

1. Liauid Releases

2. Gaseous Releases Na-24 1.25E-08 Ar-41 1.08E-08 Mn-56 6.57E-08 Xe-133 1.40E-08 Sr-90 2.31E-09 Kr-88 2.40E-08 Nb*95 1.28E-08.

Nb 2.38E-06 Ru-105 3.11E-08 3.

Iodines JyML Particulates I-134 2.86E-08 Co-141 1.89E-08 W-187 6.76E-08 Co-141 5.36E-14 Co-144 8.37E-08 Nb 5.00E-14 I-132 2.56E-08 La-140 1.30E-13 Cs-136 2.43E-08 Ba-140 2.51E-13 T /2 Too short 1

Alpha 3.39E-08 I-134 Cs-137 7.192-14 NOTES 1:

The<above values represent typical "a priori" LLDs for isotopes where values of "<LLD" are indicated in Tables 1A, 1B, 1C, 2A, and 2B.

2:

WhereLactivity for any nuclide is reported as " Less than LLD",

that nuclide is considered not present and the LLD activity listed is not considered in'aummary data.

2/7

.m L_

__.__._.____________________.m

Tablo 3A Efflurnt cnd-W sto Dicp 031 S miennual R: port Yotr 1989 Solid Waste and Irradiated Fuel Shipments 1

Waste Class A, Igly,throuah December

1. Total' volume shicoed (cubic meters) 1.91~E2 Total curie quantity (estimated) 2.28 E2 2.

Tvos ji Waste Units Six-month Est. Total

-Period Error.4

a. Spent resins, filter sludges meters 3 4.01 El Curies 2.24 E2 1.00E1

b. Dry active waste, compacted meters 3 1.29 E2 noncompacted Curies 3.93 E0 1.00E1

c. Irradiated components meters 3 0.00 EO-Curies 0.00 EO N/A

d. Others (oil) meters 3 2.17 El i

Curies 6.47 E-3 1.00E1

3. Estimate 3dL maior radionuclide comoosition a.

Cr-51 4.52 EO%

Mn-54 9.74-E0%

Fe-55 5.37 El%

Co-58 2.28 EO%

Co-60 1.59 El%

Cs-134 6.34 EO%

Cs-137 6.45 EO%

b.

Mn-54 2.37 EO%

Fe-55 8.43 El%

l-Co-60 1.09 El%

Cs-137 1.28.E0%

c.

N/A N/A d.

Co-60 3.03 El Fe-55 6.56 El Cs-137 1.87 EO H-3 0.94 EO 2/8

,.J y

Tablo 3A;(cont.)

Effluent and Waste Disposal Semiannual Report Year 1989 Solid Waste and Irradiated Fuel-Shipments

4..GIgER. reference-table, y,,ggig, stream, form, and, container tvos.

Stream 19IE.

Container Jiygg, h,gf_shioments a.

Rosin-Dewatered &

. Type A/ Type B-8/0 Solidified *

.b.

Dry active Compacted /non-22 waste compacted waste c.

Irradiated N/A N/A components d.

Other STP 2

solidification agent or absorbent (e.g., coment, urea formaldehyde)

NONE

5. Shioment Discosition

a. Solid Waste Number.21.Shioments

,]igda,,gf, Transportation Destination 30 Sole Use CNSI/Barnwell SC 2

Sole Use

-US Ecology /

Hanford

b. Irradiated Components Number,g1,Shiomants

,liggg..gf. Transoortation Destination-0 N/A N/A 2/9

TQblo 3B Effluont Qnd WQOto Diopo0Ql SGmiQnnuQ1 R0 port' YoQr 1989 Solid = Waste and Irradiated Fuel Shipments Waste Class JL J300Lthrouah December

1. Total volume shioned (cubic' meters) 1.35-El Total Curie quantity (estimated) 1.05 E3

2. Jyjut jtt Waste -

Units Six-month Jet. Total Period Error.(

a. Spent resins, filter sludges meters 3 1.35 El 1.00E1 Curies 1.05 E3 s

' b. Dry active waste,- compacted, metere3 0

N/A and noncompacted Curies 0

c. Irradiated components meters 3 0

N/A curies o

d. Others (describe) meters 3 0

N/A Curies-0

3. Estimate 3dl maior radionuclide composition a.

Cr-51 1.22 El%

Mn-54 6.86 E04 Fe-55 5.90 El%

Co-58 1.66 EO%

Co-60 1.52 El%

Ni-63 1.23 E0%

Cs-134 1.84 EO%

Cs-137 1.83 EO%

b.

N/A N/A c.

N/A N/A d.

N/A N/A

4. Cross reference table. Waste stream. IgIEL.gni container _ty.pt stream J.EXEL container h h g shioments

a. Resin Dewatered &

Type A/ Type B 2/1 Solidified

b. Dry active Compacted /non-N/A N/A compacted waste

c. Irradiated N/A components

d. Other N/A

Solidification agent or absorbent (e.g., cement, urea formaldehyde)

N/A 2/10

Tchlo.3B (cant.)

,'.. Effluent.and Waste Disposal Semiannual Report Year 1989 Solid Waste and Irradiated Fuel Shipments 5.Shiomant Disposition

a. Solid Waste Number.2L Shioments Mode si Transoortation Destination 3

sole use CNSI/Barnwell SC

b. Irradiated Fuel Number..ql Shioments Mode,gi Transportation Destination 0

N/A N/A i

i I

2/11

7 i

Tablo 3C

.c

' ' Effluent and Waste Disposal Semiannual Report Year 1989 Solid Waste and Irradiated Fuel Shipments-Waste Class fl-July throuch December

1. Total volume Jhioned (cubic meters) 3.55 EO Total curie quantity (estimated) 4.68 E2

2. Type JEL Waste Unit Six-month Est. Total Period Error,%

a. Spent resins, filter sludges meters 3 N/A curies

b. Dry active waste, compacted meters 3 N/A and noncompacted c.' Irradiated components meters 3 3.55 E0 1.00El Curies.

4.68 E2

~

d. Others (describe) meters 3 N/A Curies 3.

Estimate jpi maior radionuclide comoosition a.

N/A I

b.

N/A L

c.

Fe l'.43 El%

l Co-60 2.99 El%

Ni-63 1.34 E0%

Sb-125 5.43 El%

d.

N/A 4.

Cross reference table, waste stream, form JgEL container type Stream Form Container Tvos IBb_ Jtt shioments 1

L

a. Resin Dewatered &

N/A N/A H

Solidified *

b. Dry active Compacted /non-N/A N/A waste compacted

.i

c. Irradiated Type B 2

components

d. Others N/A N/A

Solidification agent or absorbent (e.g., cement, urea formaldehyde)

N/A 2/12

._o.-

Tablo 3c'(cont.)

Effluent and Waste Disposal Semiannual Report Year 1989 Solid Waste and Irradiated Fuel Shipments 5..Shioment Discosition

a. Solid Waste-Number g Shioments Jipig.pf, Transportation Destination 2

solo use CNSI/Barnwell SC b.-Irradiated Fuel (non-burial)

Number,gi Sbioments jiggg._qi, Transoortation Destination 5-solo use/ Rail CP&L/SHNPP 2/13

e.,.

ENCLOSURE,,

,c 4

Combustion of Waste Oil July through December Year 1989-

.There was no incineration of' contaminated waste oil during this~ reporting period.

t

).

2/14 1

ATTACHMENT 3 Off-Site Dose Calculation Manual (ODCM) and-Process Control Program (PCP) Revisions July 1, 1989 to December 31, 1989 Brunswick Steam Electric Plant There were no revisions made to the Process Control-Program during this reporting period.

Revision 09 was issued to the Off-site Dose calculation Manual (ODCM) to incorporate the dose limits and calculational methods associated with the Technical Specification change to allow the

- incineration of contaminatad waste oil.

Revision 09 is attached, l

1 I

I.

l 1:

l-l l-1 i

i.

3/1 l

=

~. 97 1

1..:

'(

BRUNSWICK STEAM ELECTRIC PLANT OFF-SITE DOSE CAI.CULATION MAhTAL (ODCM) t REVISION 9 DOCKET NOS. 50-324-50-325 CAROLINA POWER & LIGHT COMPANY i

9, l,,

I LIST OF EFFECTIVE PAGES-ODCM Page (s)

Revision 1-111 9

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s LIST OF EFFECTIVE-PAGES (Continued)

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C C-8 o

C-9 8

C C-13 o

C-14 8

C-15 o

C-16 8

(

C C-18 o

D D-2 1

E-1 4

'E E-3 g

F F-3 0

G t H H-5 9

ODCM (BSEP) 11 Rev. 9 o

t.-

s' '-

E TABLE OF CONTENTS

[

Section-Title Page-Li s t o f E f f e c t iv u Pa ge s.....................................

1 Table of Contents............................................

iii s

List of Tables............................................

iv

' List of Figures.............................................

ix 5

1.0 INTRODUCTION

11 2.0 LIOUID EFFLUENTS............................................

2-1 2.1

' Complianc e with 10CFR20 (Liquids)....................

2-1 (Alarm / Trip Setpoint Determination)

.2.2 Compliance with 10CFR50 (Liquids)....................

2-11 3.0 GASEOUS EFFLUENTS...........................................

3-1 3.1 Monitor Alarm Setpoint Determination.................

3-1 3.2 Compliance with 10CFR20 (Gas eous)....................

3-15 3.3

-Compliance with 10CFR50 (Gaseous)....................

3-34 4.0 R ADIOLOGI CAL ENVIRONMENTAL..................................

4-1 MONITORING PROGRAM

' (

5.0 INTERLABORATORY COMPARISON PR0 GRAM..........................

5-1 6.0 TOTAL DOSE (40CFR190 CONFORMANCE)...........................

6-1 APPENDIX A - Meteorological Dispersion Factor...............

A-1 Computations APPENDIX B - Calculation of B and V Values................

B-1 1

i for the Elevated Plume APPENDIX C - Dose Parame ters f or Radiciodines,..............

C-1 Particulates, and Tritium APPENDIX D - Lower Limit of De tec tion (LLD).................

D-1 APPENDIX E - Radioactive Liquid and Gas eous.................

E-1 Effluent Monitoring Instrumentation Numbers APPENDIX F - Liquid and Gaseous Effluent System............

F-1 Diagrams APPENDIX G - ODCM Software Package..........................

G-1 APPENDIX H - Methodology and Calculations for Burning.......

H-1 Waste Oil ODCM (BSEP) 111 Rev. 9

p"s.

Y

}_

L mrem / year per uC1/see per m a for food and ground plane

=

pathways i

The release rate of radionuclide i in gaseous effluents from Q

a free-standing stack, uC1/sec i

The release rate of radionuclide i in gaseous effluents'from

'Q

=

V

.all' vents releases, uCL/sec W

The highest calculated annual average dispetaion parameter for

=

v estimating the dose to an individual at the controlling location due to all vent releases W = sec/m8 for the inhalation pathway-y 2

W = meters for the food and ground plane pathways y

W The highest calculated annual average dispersion parameter for

=

estimating the dose to an individual at the controlling location due to stack releases 8

W,= sec/m for the inhalation pathway

~8 W,= meters for the food and ground plane pathways Radioiodines, particulates, and tritium may be released from the stac).,

Reactor Buildings, and Turbine Buildings at BSEP.

Radioiodines, particulates, and tritium may also be released from decontamination operations in the Hot Shop, burning waste oil in the incinerator, and incineration of scintillation vials in accordance with 10CFR20.306.

Effluents from the Hot Shop roof vent and incinerator are combined with the Turbine Building's vent releases.

To show compliance with 10CFR20, (see Appendix H for waste oil) Expression 3.2-9 is modified to incorporate the various release points for BSEP:

>(

ODCH (BSEP) 3-22 Rev. 9

m g

m

..'~

i

. 8 sec/m for the inhalation pathway and tritium

=

meters 2 t

for the food and ground plane pathway t

'w The dispersion parameter for estimating the dose to an

=

y individual at the controlling location for short

-term vent releases (equal to or less than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year) -

=

sec/m8 L

p for the inhalation pathway and tritium meters ~2

=

for the food and ground plane pathway 3.17 x 10~0

=

The inverse of the number of seconds in a yaar R

The dose factor for each identified radionuclide 1

=

g the organ of interest, mrem /yr per uti/see per m a or I

mrem /yr per uCi/m 3 Radioiodines, particulates, and tritium may be released f b

i Reactor Buildings,-and Turbine Buildings at BSEP rom the stack, and tritium may also be released from decontamination oper tiRadicio Shop, burning waste oil in the-incinerator, and' incinea ons in the Hot t

vials.-

ration of scintillation-Effluents from the Hot Shop ' roof vent and incinerator are

'f.

with the Turbine Building's vent releases.

combined Burning waste oil in the incinerator is limited to 0.1% of 10CFR50 Appendix ~I (see A

[

methodology and calculations).

ppendix H for At BSEP all releases are considered long-term in duration.

Therefore, incorporating the various release points int

+

Expression 3.3-13 results in the following expression t o

10CFR50 for a particular organ:

o show compliance with

-8 3.17 x 10 I R W

1

,Q1 rb (91

9

)*Ntb (9

+W 1

1

+9

)

1 s

rbl rb2 tbl tb2 s 15.0 mrem per quarter or 30 mrem per year (3.3-14)

ODCM (BSEP)

(-

3-42 Rev. 9

+

e t

h4

.=.

4 4

4 g

1.

r, APPENDIX H METHODOLOGY AND CALCULATIONS FOR BURNING WASTE OIL To permit burning of slightly contaminated waste oil in the clean trash.

N incinerator, an insignificant fraction (0.1%) of the following regulations _must be met:

10CFR20; 10CFR50, Appendix I; and 40CFR190.

The fellowing sections contain the methodology and the calculations to determine the concentration and the cumulative total activity to bei used in procedures to demonstrate compliance with the above regulations.

I.

Compliance with 10CFR20 for I-131, I-133 Particulates, and Tritium..

The inhalation dose rate associated with burning waste oil is 1 insignificant by definition.

Regulatory Guide 1.109 states, "A pathway is considered significant if a conservative evaluation yields an additional. dose increment equal to or more than 10 percent of the total from all pathways. considered." Since the release rate by incineratlon-of.

waste oil is s 10% of the plant's total release rate, the dose rate via waste oil is insignificant.

10CFR20 Limit 1500 mrem /yr (Inhalation to a child's most critical

=

organ) t

. Insignificant 150 mrem /yr (10% of limit)

=

.I 0.1% of 10CFR20 = 1.5 mrem /yr, this more than c.eets the above criteria and is a consistent fraction as listed in Technical Specification 3.ll.2.3'C.

Since the limit is going to be limited to 0.1% of 10CFR20,' the maximum release rate (uci/sec) can be~ calculated by the following equation:

1.5 mrem /yr Q

(R ) (X/Q)'

=

g I

s Where =

R Dose factor for the most restrictive organ to a child i

=

g g

-(lung)-foringalationusingCo-60(7.06E6 mrem /yr/uCi/m )

(X/Q) = Annual average relative concentration for release from the Turbine Building, 7.5E-6 sec/m3 Since the incinerator operates > 500 hrs /yr and the stack height is considered to be ground level, the meteorology used for dilution will be the-same as the Turbine Buildings (ground level continuous). From Appendix A Table A-1 the most restrictive sector is SSE (7.5E-6 sec/m ).

3 L

ODCH (BSEP)

H-1 Rev. 9

{ '*

APPENDIX H (Cont'd)

For the source term mix, 100% of the activity is Most of the activity in the slightly contaminatedassumed to be Cobalt-60.

Cesium-137.. No iodines will be permitted in theactivat um-134 and incineration.

Cobalt-60 is the most waste oil for inhalation pathway to a child's lung (Table 3 3 18) restrictive radionuclid Therefore, Q

l.5 mrem /yr

=

(7.06E6 mrem /yr/uci/m')

g (7.5E-6 sec/m3)_.

Qg 2.83E-2 uC1/sec

=

The maximum oil flow rate for burning oil in th gal / min.

The maximum flow rate in ec/sec is calculated as f (6 gal / min) (min /60 sec) (3785 cc/ gal) = 378 5 ows:

cc./sec

'The main fuel oil tank for the incinerator shall n t 20% by volume of slightly contaminated oil o

contain more than conservatism, the flow rate will equal 6 gallons / m m n.

For additional or burning oil.

determined by the following equation:The maximum concen to be burned can be i

Max. Conc. (uC1/cc) =

.Et f

Where:

f = waste oil flow rate 378.5 cc/sec Max. Conc. (uCi/cc) =

'~2.83E-2 uC1/sec 378.5 cc/sec 7.48E-5 uC1/cc

=

The. maximum concentration of waste oil to be inci 7.48E-5 uCi/cc which is 0.1% of 10CFR20 limit nerated is limited to By limiting the concentration to an insignificby procedu s.

oil prior to burning, intent of. Technical Specification 3.11 2 1 ant release rate meets the-i II.

_ Compliance with 10CFR50, Appendix I for I-131, I-133, Pa Tritium Technical Specification 3.11.2.3.C limits the bur i incinerator to 0.1% of two times 10CFR50, Appendin ng of waste oil in the For conservatism, burning of waste oil $ hall be li ix I (two-unit site).

Appendix I.

i m ted to 10CFR50,

{

'ODCM-(BSEP)

H-2 Rev. 9

_ - - - ~ " ' ' ' ' '

_ _ _, _ - - - - - - " ' - ~ ~

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

--e ;

s.

(.

APPENDIX H (Cont'd)

Therefore:-

.001 x 7.5 mrems = 0.0075 mrem to any organ during any calendar.

quarter

.001 x 15 mrems = 0.0150 mrem to any organ during any calendar year The cumulative dose for the above yearly limit is' determined by the following equation:

0.015 (mrem) s 3.17E-8. [(R

+ R

+- Rg) (D/Qtb )(9

)*

g g

g 1

G H

V B

oil (Rg ) (X/Qtb i

(O I

oil The above equation can be further reduced as follows:.

0.015 mrem s (3.17E-8)[(Q

) [(R

+ R

+ R ) (D/Q g

g y

g tb oil G

M V

.B (Rg ) (X/Qtb)I

(,.

i g

The activity in the slightly contaminated waste oil is long lived fission. corrosion, and activation products.

There is no Iodine-131 or i

Iodine-133 in the oil.

Using the most conservative radionuclides i

(Cesium-134. Cesium-137, and. Cobalt-60), a quarterly and yearly activity-can be calculated for all organs and all age groups for the summation.of

.all pathway doses.. The maximum activity to be released for a calendar quarter and calendar. year can be determined as follows:

Q 0.015 r

1,gg

= (3.17E-8) [(R

+ R

+

R

+ Rg )(D/Qg) + (Rg )(X/Qtb))

g g

g G

H V

B I

j Where:

3.17E-8 = The inverse of the number of seconds in a year i

Rg Dose factor for an organ for radionuclide i for the

=

i g

ground plane exposure pathway, mrem /yr per uCi/sec per l

m 2, Table 3.3-1 ODCM (BSEP)

H-3 Rev. 9

n

=

.(.

APPENDIX H (Cont'd)'

RI Dose factor for 'an organ for radionuclide i for the cow

=

g milk pathway, mrem /yr per uC1/sec per m"8, Tables 3.3-8, 3.3-9, 3.3-10, and 3.3-11~, there is no goat milk' production within 5 miles of site R

i Dose factor. for an organ for radionuclide i for the-

=

vegetable pathway, mrem /yr per pCi/sec per m'2, Tables 3.3-2, 3.3-3 and 3.3-4 l

R i

Dose factor for an organ for radionuclide i for the meat

=

B Pathway, mrem /yr per uCi/sec per m'8, Tables 3.3-5, 3.3-6, and 3.3-7 R

i Dose factor for an organ for radionuclide i for the

=

inhalation pathway, mrem /yr per uC1/m, Tables 3.3-16, 3

3.3-17, 3.3-18, and 3.3-19 D/Qtb Annual average deposition for release from the

=

Turbine Buildings, NE sector = 1.9E-8 m 8 most restrictive, from Appendix A, Table A-3 X/Qtb = Annual average relative' concentration for releases Y

f rom the Turbine Buildings, SSE sector 7.5E-6 sec/m,

3 most restrictive, from Appendix A.-Table A-1 4:

9

g' The most restrictive age group and organ is Child Bene.- The maximum release

_ in any calendar year is 436 pCi.

The maximum release in any calendar quarter i-is 436 x 1/2 = 218 uCi.

All slightly contaminated waste oil that is to be= burned in the incinerator shall be controlled by procedures demonstrating that the quarterly limit (218 l:

~

uC1) and yearly limit. (436 pCi) are not exceeded. Doubling these LCi limits j.

shall'be used for calculating percent of technical specification limit in the semiannual-report. At the end of each calendar year a dose assessment will be made using the NRC approved computer code GASPAR.

i i~

i 1

1.

ODCM (BSEP)

H-4 Rev. 9

F'g.

~

]

b '. ;

a

d' e

f APPENDIX H.(Cont'd) i Summary of Co-60, Cs-137, and Cs-134~

UCi Release Yearly Limit by Age Group and Organ T' Body CI-Tract Bone Liver Kidney Thyroid Lung Skin Co l Adult 1,132 965 1,158 1,147 1,158 1,158 1.044 988 0

~ Teen 1,120 977 1,158 1,142 1,158 1,158 999 988 l

Child _

1,091 1,037 1,158 1,134 1,158 1,158 1,025-988

~F Infant 1,153 1,151 1,158 1,155 1,158 1,158 1,070 988 s

Cs-137 Adult 1,179 2,349' 1,112 928 1,564 2,418 2,053 2,075

-Teen 1,278 2,333-826 678 1,292 2,418 1,812 2,075 Child 1,474 2,349 436*

453 1,001 2,418 1,603 2,075 Infant 1,910 2,390 575 509 1,205 2,418 1,714 2,075 Cs-134-

' Adult 1,063 3,471 1,623 1,125 1,857 3,652 2,766

~3,129 Teen 1,163 3,452 1,233 649 1,478 3,652 2,337 3,129

~

Child 1,441 3,517 672 442 1,120 3,652 2,017 3,129

-Infant' 2,258 3,594 851 513' 1,417 3,652

'2,217 3.129

Most restrictive quantity in pCi resulting in 0.1% of 10CFR50 App. I limit.

l111. Compliance with 40CFR190 The annual (calendar year)-dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ except the thyroid, which shall be limited to-less than or equal to 75 mrem.

Incinerating waste oil is limited to 0.015 mrem to the most critical organ (including whole body) using all pathways. 40CFR190 is automatically complied with since 0.015 mrem is s 0.1% of 25 mrem.

ODCM (BSEP)

H-5 Rev. 9 4

lNb

~ >

ATTACHMENT ~4':

F Environmental Monitoring Program July'1, ~ 1989 to' December 31, 1989 1 Milk and Vegetable Sample Locations 1

s Land Use Census

.Yi 4/1

. 4

~

s

- -. c.

t..;

' t. !:

ENCICSU'RE l-Milk and-Vegetable sample Locations July --December, 1989-'

No milk sample locations were availabl's during this time period.

Vegetable sample locations remained-: unchanged.

U 4

1 4/2 i

=.:

o

'a

-ENCLOSURE 2 Land Use census July - December, 1989-The results of the'1989 Land Use Census were reported in the January - June,'1989 Semiannual Report.

i I

^

4 o-I

. )

i I

'i 4/3

y '.?

o; q.

u,'.

S-l-ATTACHMENT-5=

b Inoperable Effluent Instrumentation July 1, 1989 to December 31, 1989 li g

Enclosure ~1 Radioactive Liquid Effluent Monitoring Instrumentation. 1 Radioactive Gaseous Effluent' Monitoring.

. Enclosure 3:

Liquid Hold-Up Tank i-t a

t f

.___ - - - - - _ -=_-- -- - _ 0

._ e.

' l0, '

ENCLOSURE 1 July 1,-1989 to December 31,-1989.

Radioactive' Liquid Effluent Monitoring Instrumentation The liquid radwasta effluent flow measurement device (2-G16-FIT--

N057) was inoperable for greater than 30 days during this period.

The' instrument was not returned to service within a 30 day period due to. the inability to calibrate the. instrument within its

' design accuracy.

(

i 5/2

i ENCLOSURE 2 l

July 1, 1989 to December 31, 1989 l

Radioactive Gaseous Effluent Monitoring Instrumentation j

i No radioactive gaseous affluent nonitoring instrumentation was f

f-inoperable for greater than 30 days during this reporting period.

i

}

i

[

i I

i.

b i

i h

s I

l[

-r o

l i

e b

e 5/3 t

= ~ ~

v e

-g

- o.

[

ENC 108URE 3 i

+

i r

Liquid Hold-Up Tank

[

t July 1, 1989 to December 31, 1989 No liquid hold-up tank exceeded the 10 Ci limit during this reporting period.

1 i

s

[

i I

s.

6 o

e e

e r

t c

L l.

i r

T

'b i

I i

E l

I l

5/4 1

g 1

e ATTACHNENT 6 Major Modifications to the Radioactive waste Treatment System July 1, 1989 to December 31, 1989 As per footnote 7 to Technical specification 6.15, a discussion of any major modifications to the radioactive waste treatment systems will be submitted with the Final Safety Analysis Report update.

6/1

ATTACHMENT 7

+

Meteorological Data j

July 1, 1989 to December 31,1989 i

)

=As per Technical specification 6.9.1.10.a footnote 6, the annual summary of noteorological data collected over the calendar year

.will be submitted to a file and will be available for NRC review upon request.

l b

t i

[

2 v

t

+

k 7/1

ATTACHNENT 4

'+ -

Annual Dose Assessment January 1, 1989 to December 31, 1989 a

i f

l i

8/1

Annual Dooo Accoooment Brunswick Steam Electric Plant January to December, 1989

Attached is the annual dose assessment for the year 1989.

Enclosure in Annual Liquid Dose Assessment Annual Gaseous Dose Assessment 8/1 i mz

l 1

I Incitylr0 1 1

Annual Liquid Dose Assessment i

Pace 8/2-1 IADTAP II cover Sheet 8/2-2 Site Specific Data l

8/2-3 Source Term 8/2-4 As Low As Reasonably Achievable Maximum Individual Dose 8/2-5 Summary - Total Integrated and Recreation Population Dose i

1 I

i D

t l.

8/2

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4.25E-03 4.20E-03 l - 1.86E-02'-l.

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2.71E-05 1.36E-03-~l^

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2.66E-09.

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9.61E-04.I 9.87E-10 I

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39V 91M I 7.32E-04 I

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7.51E-09^ l 1.03E-05 l

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1.01E-02 l

4.89E-08' l 4.89E-08 l

4.84E l -4.84E-06 l

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1.32E-04 l

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1.24E-05 1

42MO 99 1.06E-04 I

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l. 8.69E-10 -l 8.46E-06 l ~8.20E-06 l

437C 99M 4.94E I.1.28E-07 l 't.28E-07 i _ 2.60E l 2.60E I 44R4 105 l

..6.89E-04 l

8.79E-09. I 8.79E-09 -l

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47AG 11CM l 1.13E-04 I

3.51E-07 l

3.39E-07 1

3.11E-03 l

3.OOE-03 l

52TE 1794 l 6.56E-05 l

1.66E-09 I.2.12E-09' i 2.52E-05 1

3.23E-05 l

52TE 132-l 1.88E-04 1

1.59E-09 l

1.61E-09 I,-8.43E-06 I

8.56E-06 l

531 131 I

7.89E l 2.22E-07.. l'.2.46E-G5 l

2.81E-05 l~ 3.12E-03 l

531-132 l

7.86E-05 i '3.60E-09 1

3.60E-09' l 4.59E-05 1

4.59E-05 l

' \\

531 133 1

5.15E-03 l

6.11E-OS-l: 6.36E 1,-1.19E-05 I.1.24E-05 I

N 531 134 l

4.04E-05 l

1.74E-09 l

1.14E-09

'l 4.31E-05 l

4.31E-05 I

8 53I 135 1

1.62E-03 l

5.79E-08 : I 5.79E-08

.l 3.57E-05 I' 3.57E-05 I

55CS 134 l

7.98E-02 I

5.86E-04 l

4.69E-04 -l

.7.35E-03

.I 5.88E-03 1

55CS 136 l

8.05E-04 l

2.62E-07 i: 1.37E-07 l

3.2SE-04 l

1.70E-04 I

55CS 137 I

7.68E-02 I

7.45E-04' I 6.78E-04 l

9.70E-03 i '8.83E-03 l

55CS 138 I

4.50E-05 t.85E-09 l

1.85E-09 I

4.10E-OS l' 4.10E-05. I 57LA 142 l

1.24E-04 5.76E-09 I

5.76E-09' l 4.64E-05. I 4.64E-05 I

SBCE 141

1. 8.47E-06 1.10E-10 l

1.10E-10 1.30E-05 l

1.30E-05 l

58CE 144 l

2.39E-04 1.45E l 1.44E-05~

6.06E-OS I

6.04E-05 1

72HF 181 l

1.85E-05 l

3.34E-09 I '3.30E-09 1.81E-04 l

1.OSE-OS 1.78E-04 1

74W 187 l

2.18E-03 l

2.282-08 1

2.28E-08 l

1.05E-05 I

3 93NP 239 l

1.55E-03 l

6.06E-09 l ^ 6.06E-09 l

3.91E-06 I

3.91E*06 i

TO7AL 5.82EcO3 5.57E-03

^-

T 1VW*q yMw3

$We**'

'7yg 1*I4N(f

-9. u' F* M d g

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CS IOW CS REASONABLV ACHIEVABLE-.O' O'

O.

i-A DULT

'D.0 S'E S (MREM PER VEAR INTAKE)

DOSE PATHWAV-SMIN BOME LIVER.

-TOTAL'BOOV THVROID MIDNEY Lt#1G GI-LLi FISH 3.95E-04

.9.62E-04 5.98E-04 1.07E-04 2.72E-04 9.93E-05' 1.91E-03 INVERT 2.07E 4.51E-04 3.67E-04 1.33E-04

.8.86E-05 6.87E-05 2.53E : SHORELINE 6.OOE-03 5.11E-03 5.11E 5.11E-03' 5.11E-03 5.11E-03

'5.11E -5.11E-03 SWIMMING 4.44E-06 4.44E-06; 4.44E-06 4.44E-06 4.44E-06 4.44E-06' 4.44E-06'~

BOATING 2.22E-06 2.22E-06 2.22E-06 2.22E-06 2.22E-06 2.22E-06.

2.22E TOTAL 6.00E-03 5.72E-03 6.53E-03 6.00E-03 5.36E-03 5.48E-03 5.29E-03

'9.56E USAGE (MG/VR.HR/YR)

DILUTION TIME (HR)

SHOREw1DTH FACTOR =0.5 FISH 29.2 30.0 24.00

' ~ '

INVERT

.7.3 30.0 24.00 SHORELINE 500.0 30.0 0.00 SWIMMING 100.0 30.0 0.00 BOATING 100.0 30.0-0.00 T EEN D0$ES-(MREM PER VEAR INTAKE)

DOSE PATHwAV SMIN BONE LIVER TOTAL BOOV THYROID KIDMEY LUNG GI-LLI FISH 5.41E-04 1.28E-03 5.46E-04 1.32E-04 3.59E-04 1.53E 1.71E-03 INVERT 2.75E-04 6.01E-04 4.53E-04 1.64E-04 1.13E-04 1.07E-04 2.32E-03 SHORELINE 6.00E-03 5.11E-03 5.11E-03 d.llE-U3 5.11E-03 5.11E-03 5.11E-03

-5.11E-03 SWIMMING 4.44E-06 4.44E-06 4.44E-06 4.44E-06 4.44E-06 4.44E-06 4.44E-06 em BOATING 2.22E-06 2.22E-06 2.22E-06 2.22E-06 2.22E-06 2.22E-06 2.2 7-06 N

TOTAL 6.OOE-03 5.94E-03 7.OOE-03 6.12E-03

.5.42E 5.59E-03 5.38E-03 9.*ti-03 g

p

-I USAGE (EG/YR.HR/VR)

DILUTION TIME (HR)

SHOREw!DTH FACTOR =0.5

FISH 29.2 30.0 24.00 INVERT 7.3 30.0 24.00 SHORELINE 500.0 30.0 0.00 SWIMMING 100.0 30.0 0.00 BOATING 100.0 30.0 0.00 CHILD D0$ES (MREM PER YEAR INTAME)

DOSE PATHWAY SKIN

-BONE LIVER TOTAL BODY THvROID KIDNEY LUNG GI*LLI ~

FISH 1.55E-03 2.51E-03 8.46E-04 3.19E-04 6.75E-04 2.83E-04 1.35E-03E INVERT 7.72E-04 1.17E-03 1.04E-03 3.97E-04 2.09E-04 2.02E-04 1.87E-03 SHORELINE 6.00E-03 5.11E 5.11E-03 5.11E-03 5.11E-03 5.11E-03 5.11E-03 5.11E SWIMMING 4.44E-06 4.44E-06 4.44E-06 4.44E-06 4.44E-06 4.44E-06 4.44E-06" BOATING 2.22E-06 2.22E-06 2.22E-06 2.22E-06 2.22E-06 2.22E-06 2.22E-06 W TOTAL 6.00E-03 7.44E-03 8.81E-03 7.01E-03 5.84E-03 6.00E-03 5.60E 8.34E-03 USAGE (MG/YR.HR/YR)

. DILUTION TIME (HR)

SHOREWIDTH FACTOR =0.5 FISH 29.2 30.0 24.00

. INVERT 7.3 30.0 24.00 SHORELINE 500.0 30.0 0.00 SWIMMING 100.0 30.0 0.00 BOATING 100.0 30.0

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Annual Gaseous Dose Assessment JJUUL 8/3-1 GASPAR Cover Sheet 8/3-2 to 3ource term for the three release modes and the site 8/3-4 aggregate i

8/3-5' Total 50 mile Integrated Population Dose by pathways and organs 8/3-6 Hypothetical maximun individual organ dose due to Iodines, Particulates, and Tritium for a cow milk pathway.at 4.75 miles Northeast.

8/3-7 Maximum site boundary dose by age group and organs-for all pathways, t

8/3-8 Estimated individual organ dose using the 1989 Land-Use census for the worst sector and existing pathways.

8/3-9 Maximum site boundary dose due to Iodines, Particu-lates, and Tritium for existing pathways, i

?

9 6

V 4

Y 8/3 w

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....eeeeee aee. eeee......eeeeeeeeeeeeeeeee. eesee.e

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GGGGGGGG AA 55555555 PPPPPPPP AA ARRRRRRR G

G AA S

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AA RR R

G A A 5555555 PP P

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A RR RR GGGGGGG A A S555555 PP A

A RR RR e

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e EVALUATION OF ATMOSPHERIC RELEASES e

e COMPUTED 02/13/90 e

e e

BRUNSWICK UNITS GASEOUS RELEASES 1989 e

e e

C0 e

e N

W F.F. ECMERNAN. D.G.

LASH REVISED 8/19/77 I

e H

e e

e RADIOLOGICAL ASSESSasENT BRANCH e

U.S. NUCLEAR REGULATORY COesu1 SSION e

WASHINGTON.D.C. 20S55 e

e 4

eeeestetee...se eSette.eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee teeeeeeeeeeeeeeeeeeeeeeeee n -

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x:

^

\\q' CP&L SENI-ANNUAL RADIOLDGICC.L EFFiUENT REPORTING RUM DAT2 C2/13/90.

GASRPT g'

. INPUT SOURCE TERMS RUN TIME: 07:06:26

+

THIS 1989 SOURCE TERM (GROUND LEVEL) BSEP UMITS 1 AND 2 1 H-3 2.700E+00 25 mM-54 7.800E-07 38 SR-89 6.790E-06 38 SR-90 1.300E-07 53 1 -131 4.660E-04 53 I -132 2.130E-03 53 I -133-2.490E-03 53 I -135 7.570E-03 54 XE-133 1.940E+0?

54 XE-135 4.430E+01 54 XE-135 M 4.860E+00 56 BA-140 1.690E-06 57 LA-140 1.570E-06 58 CE-141 f.510E-07 58 CE-144 1.130E-06 Op

\\w I

w

_,~. _,.

. ~

- - - - - ~

., - - ~,,. _..

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'-J J 1

CP&L SEMI-ANMUAL CADIOLOGICCL EFFLUEZT REPORTING-RUN DATE:.%2/13/D0 GASRPT' INPUT SOURCE TERNS-RUM TIME: C7:06:26 1989' SOURCE TERM (MIXED MODE) _SSEP UNIT 1 A ND ' 2 1-H-- '3 2.420E+00 24 CR-51

' 2.280E-02 25 MN-54

. 1.940E-03 26 FE 9.640E-06 27 CD-57 2.990E-06 27 CO-58 5.620E-04' 27 CO-60 2.660E-03 38 SR-89 2.270E-05 38 SR-90 '

1.190E-06 41 NS-95 8.450E 44 RU-103 6.270E-06 53 I -131 1.680E-03 53 I -132 9.040E-03 53 I -133 1.330E-02 53 1 -134 1.060E-03 53 I -135 1.550E-02 54 XE-133 5.450E=31 54 NE-135 1.680E+02 54 XE-135 N 3.100E+01 55 CS-134 9.110E-06 55 CS-137 2.990E-05 56 BA-140 5.220E-05 57 LA-140 3.870E-05 CD 58 CE-141 1.520E-06

'N

-58 CE-144 2.050E-05 s

LJ 72'HF-181 1.100E-05 I

to 4

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CP&L SEMI-ANNUAL CA010 LOGIC.0L' EFFLUENT REPORTING RUN DATE: C2/13/90 GASRPT INPUT SOURCE TERMS RUN TIME: 07:06:26

~ 4, e

1989 SOURCE TERM (ELEVATED MOOE) BSEP UNITS 1&2 I H-3

~4.082E+00 18 AR-41 5.181E+00 24 CR-51 1.539E-03 25 MN-54 1.695E-04 27 CO-58 2.663E-05

[

27 CD-60 2.561E-04 j

36 MR-85 m 6.785E*01 36 RR-87 7.663E+00 36 MR-88 5.549E+01 38 SR-89 9.360E-04 38 SR 5.670E-06 53 I -131 1.299E-02 53 I -132 2.633E-02 53 I -133 6.187E-02 53 I -134 2.865E-03 53 I -135 6.395E-02 54 XE-133 2.701E+02 54 XE-135 4.779E+01 54 XE-135 M 7.430E+DI 54 XE-137 3.788E+02 54 XE-138 1.292E+02 55 CS-134 3.322E-05 55 CS-337 1.065E-04 op 56 BA-140 1.275E-03

'%g 57 LA-140 9.827E-04 LJ-AGGREGATE SOURCE TERM i

45 1

H-3 9.2020E+00 18 AR-41 5.1810E+00 24 CR-St 2.4339E-02 25 MN-54 2.1103E-03 26 FE-59 9.6400E-05 27 CD-57 2.9900E-06 27 CO-58 5.8863E-04 27 CO-60 2.916tE-03 36 MR-85 M 6.7850E+01 36 KR-87 7.6630E+00 36 KR-88 5.5490E+01 38 SR-89 9.6549E-04 30 SR-90 6.9900E-06 5

41 N8-95 8.4500E-06 44 RU-103 6.2700E-06 53 I -131 1.5136E-02 53 I -132 3.7500E-02 53 I -133 7.7660E-02 53 I -834 3.9250E-03 53 I ~135 8.7020E-02 54 XE-133 3.4400E+02 54 XE-135 2.6009E+02 54 XE-135 m 1.1016E+02 54 XE-137 3.7880E+02 54 XE-138 1.2920E+02 55 CS-134 4.2330E-05 55 CS-137 1.3640E-04 56 BA-140 1.3289E-03 57 LA-140 1.0230E-03' 58 CE-141 1.6710E-06 58 CE-144 2.1630E-05 72 HF-181 1.1000E-05

..,.a

~

-9 3

.t CPOL SEMI-ANNUAL CADIDLOGICAL EFFLUECT REPORTING RUM DAT3: (2/13/90 5-GASRPT CLAR3 ANNUAL !%TEGRATE) POPULcTION DOSE SUBMBinRY (MANREM)

RUN TIME: 08:54:07 D~

1989 SOURCE TERM (ELEVATED MODE) SSEP UNITS 1&2 THIS 1989 SOURCE TERM (GROUND LEVEL) SSEP UNITS 1 AND 2 1989 SOURCE TERM (MIXED MODE) 8SEP UNIT 1 AND 2 TOTAL BODY GI-TRACT BONE LIVER MIDNEY THYROID LUNG SKIN

- TOTAL **

3.397E-02 3.421E-02 3.324E-02 3.402E-02 3.405E-02 6.244E-02 3.528E-02 7.592E-02 PLUME 2.403E-02 2.403E-02 2.403E-02 2.403E-02 2.403E-02 2.403E-02 2.458E-02 6.463E-02 70.73%

70.23%

72.28%

70.62%

70.56%

38.48%

69.67%

85.12%

GROUND PLAME 8.559E-03' 8.559E-03 8.559E-03 8.559E-03 8.559E-03 8.559E-03 8.559E-C3 1.007E-02 25.19%

25.02%

25.75%

25.16%

25.14%

13.71%

24.29%

13.26%

f INHALATION 9.632E-04 ~ '1.023E-03 8.485E-05 1.014E-03 1.061E-03 1.43tE-02 1.831E-03 9.255E-04 2.84%

2.99%

0.26%

2.98%

3.12%

22.95%

5.19%

1.22%

VEGETATION 3.865E-04 5.443E-04 5.590E-04 3.858E-04 3.674E-04 1.437E-02.

2.820E-04 2.772E-04 1.14%

1.59%

1.68%

1.13%

1.08%

23.01%

0.80%

0.37%

CDw MILM 8.913E*06 7.856E-06 3.14tE-06 1.086E-05 1.161E-05 8.742E-04 6.726E-06 6.543E-06 0.03%

0.02%

0.03%

1.40%

0.02%

0.0t%

MEAT & POULTRY 2.756E-05 5.263E-05 5.07tE-06 2.656E-05 2.397E-05 3.OB8E-04 2.218E-05 2.188E-05 0.08%

0.15%

0.02%

0.08%

0.07%

0.49%

0.06%

0.03%

co\\w t

t.p 1

g -:

s n

=

j CP&L SENI-AMMUAL CA020LOGICCL EFFLUERT REPORTING RUN OATE: C2/13/90 GASRPT RAOIOTION DOSES CT SELECTE3 LOCATIONS RUM TINE: 06:54:C7

?-

1989 SOURCE TERM (ELEVATED MODE) SSEP UNITS 1&2 THIS 1989 SOURCE TERW (GROUND LEVEL) SSEP UNITS 1 AND 2

=

1989 SOURCE TERM (MIXED MOOE) SSEP UNIT I AND 2 SPECIAL LOCATION METERS DIR PL GR IN V CM GM M a41 cow MILK 7644.0 ME O 1 1

1 1 O O ANNUAL 8 ETA AIR DOSE = 1.936E-03 MILLRAOS ANNUAL GAMMA AIR DOSE = 2.045E-03 MILLRADS TOTAL SODY GI-TRACT SONE LIVER KIDNEY THYROID LUNG SKIN ADULT 8.513E-04 9.453E-04 8.777E-04 8.63tE-04 8.626E-04 1.248E-02.

8.146E-04 9.084E-04 GROUND PLANE 7.OO2E-04 7.OO2E-04 7.OO2E-04 7.CO2E-04 7.OO2E-04 7.OO2E-04 7.OO2E-04 8.235E-04 INHALATION

'2.594E-05 2.822E-05 2.265E-06 2.744E-05 2.883E-05 3.863E-04 5.12SE-05 2.487E-05 VEGETATION 8.442E-05 1.819E-04 1.365E-04 7.968E-05 6.682E 2.709E-03 4.66tE-05 4.48kE-uS cow MILK 4.083E-05 3.503E-05 3.873E-05 5.578E-05 6.680E-05 8.686E-03 1.656E-OS 1.StSE-OS TEENAGER 8.814E-04 9.649E-04 9.650E-04 9.189E-04 9.18tE-04 1.723E-02

-8.41tE-04' 9.196E-04 GROUND PLANE 7.OO2E-04 7.OO2E-04 7.OO2E-04 7.OO2E-04 7.OO2E-04 7.OC2E-04 7.OO2E-04 8.235E-04 INHALATION 2.641E-05 2.853E-05 2.994E-06 2.854E-05 3.045E-05 4.955E-04 6.395E- 05 2.503E-05 VEGETATION 9.855E-05 1.909E-04 1.923E-04 9.869E-05 7.575E-05 2.267E-03 5.444E-05 5.139E-05 COW MILK 5.629E-05 4.517E-05 6.954E-05 9.154E-05 1.117E-04 1.377E-02 2.259E-05 f.974E-05 CHILD 9.719E-04 9.456E-04 1.286E-03 1.034E-03 1.025E-03 3.215E-02 8.737E-04 9.564E-04 ce NN, GROUND PLANE 7.OO2E-04 7.OO2E-04 7.OO2E-04 7.OO2E-04 7.OO2E-04 7.OO2E-04 7.OO2E-04 8.235E-04 La INHALATION 2.369E-05 2.39tE-05 3.796E-06 2.551E-C5 2.716E-05 5.978E-04 5.391E-05 2.213E-05 t

VEGETATION 1.578E-04 1.712E-04 4.151E-04 1.528E-04 1.134E-04 3.473E-03 8.414E-05 7.960E-05 Ch COW MILK 9.026E-05 5.031E-05 1.667E-04 1.553E-04 1.840E-04 2.738E-02 3.553E-05 3.118E-05 INFANT 8.654E-04 7.792E-04 1.021E-03 1.047E-03 1.028E-03 6.775E-02 7.894E-04 8.835E-04 GROUND PLANE 7.OO2E-04 7.OO2E-04 7.OO2E-04 7.OO2E-04 7.OO2E-04 7.OO2E-04 7.OO2E-C4 8.235E-04 INHALATION 1.378E-05 1.342E-05 2.633E-06 1.573E-05 1.599E-05 5.388E-04 3.418E-05.

1.273E-05 COW MILK 1.514E-04 6.558E-05 3.18CE-04 3.309E-04 3.114E-04 6.65tE-02

5. Site-05 4.731E-05

m y

CP&L

. SEMI-ANNUAL CADIOLOGICCL EFFLUEOT REPORTING' RUN OATE: C2/f3/90 GASRPT RADIATION DOSES AT SELECTED LOCATIONS RUN TIME: 07:06:26 THIS 1989 SOURCE TERM (GROUND LEVEL) SSEP UNITS 1 AND 2 1989 SOURCE TERM (MIMEO MODE) SSEP UNIT 1 AND 2 1989 SOURCE TERM (ELEVATED MCDE) SSEP UNITS 1&2 SPECIAL LOCATION METERS DIR PL GR IN V CM GM M s 3 SITE BOUNDARY 1127.0

-NE 1 1 1 1 1 1 1

ANNUAL BETA AIR DOSE = 2.403E-02 WILLRAOS ANNUAL GAMMA AIR DOSE = 1.799E-02 MILLRADS TOTAL SODY GI-TRACT BONE LIVER KIDNEY THVROID LUNG

$ MIN ADULT 2.559E-02 2.687E-02 2.545E-02 2.6 TOE-02 2.614E-02 3.668E-Of 2.431E-02 4.588E-02 PLUME I.182E-02 1.182E-02 1.182E-02 1.182E-02 1.182E-02 2.182E 1.206E-02 3.203E-02 GROUND PLANE 1.OO6E-02 1.OO6E-02 1.OO6E-02 1.OO6E-02 1.OO6E-02 1.OO6E-02 1 OO6E-02 1.183E-02 INHALATION 4.184E-04 4.263E-04 1.284E-05 4.290E-04 4.398E-04 2.730E-03 4.722E-04 4.115E-04 VEGETATION 1.310E-03 2.714E-03

1. 9 2SE-03 1.241E-03 1.072E-03 4.209E-02 7.660E-04 7.427E-04 COM MILM 6.295E-04 5.456E-04 5.663E-04 8.556E-04 1.044E-03 1.347E-Os 2.697E-04 2.507E-04 GOAT MILM 1.175E-03 7.433E-04 1.013E-03 1.532E-03 1.564E-03 1.618E-OI 5.676E-04 5.t4E-04 MEAT & POULTRY 1.748E-04 5.572E-04 5.200E-05 1.619E-04 1.317E-04 3.635E-03 1.102E-04 f.067E-04 TEENAGER 2.634E-02 2.717E-02 2.747E-02 2.78tE-02 2.791E-02 5.33tE-01 2.473E-02 4.618E-02 PLUME 1.182E-02 1.182E-02 1.1P2E-02 1.182E-02 1.182E-02 1.182E-02 1.206E-02 3.203E-02 GROUND PLANE I.OO6E-02 1.OO6E-02 3.OO6E-02 1.OO6E-02 1.OO6E-02 f.OO6E-02 1.OO6E-02 1.183E-02 INHALATION 4.232E-04 4.313E-04 1.715E-05 4.381E-04 4.527E-04 3.449E-03 5.043E-04 4.14fE-04 cm VEGETATION 1.528E-03 2.858E-03 2.699E-03 1.52tE-03 1.211E-C3 3.523E-02 8.917E-04 8.504E-04

% COM MILK 8.736E-04 7.049E-04 1.016E-03 1.396E-03 f.739E-03 2.135E-Of 3.652E-04 3.266E-04 La GOAT WILM 1.517E-03 9.798E-04 1.813E-03 2.465E-03 2.538E-03 2.564E-Of 7.804E-04 6.662E-04 MEA) & POULTRY 1.129E-04 3.078E-04 4.190E-05 1.074E-04 8.391E-05 2.619E-03 6.680E-05 6.368E-05 u

CHILD 2.853E-01 2.721E-02 3.455E-02 3.127E-02 3.122E-02 1.Of8E+00 2.582E-02 4.719E-02 PLUME 1.182E-#2 1.182E-02 1.182E-02 1.182E-02 1.182E-02 1.182E-02 1.206E-02 3.203E-02 GROUND PLANE 1.OO6E-02 1.OO6E-02 1.OO6E-02 1.OO6E-02 1.OO6E-02 1.OO6E-02 1.OO6E-02 1.183E-02 INHALATION

3. 767 E-M4 3.761E-04 2.202E-05 3.892E-04 4.Ot9E-04 4.096E-03 4.402E-04 3.662E-04 VEGETATION 2.446E-03 2.635E-03 5.798E-03 2.350E-03 1.813E-03 5.400E-02 1.379E-03 1.317E-03 cow MILK 1.413E-03 8.016E-04 2.436E-03 2.366E-03 2.863E-03 4.246E-Of 5.747E-04 5.159E-04 GOAT MILK 2.263E-03 1.306E-03 4.329E-03 4.150E-03 4.157E-03 5.099E-01 1.226E-03 1.053E-03 NEAT & POULTRY 1.475E-04 2.022E-04 7.515E-05 1.318E-04 1.025E-04 3.934E-03 8.050E-05 7.692E-05 INF2NT 2.809E-02 2.500E-02 3.454E-02 3.554E-02 3.389E-02 2.295E+00 2.518E-02 4.645E-02 PLUME 1.182E-02 1.182E-02 1.182E-02 1.182E-02 1.182E-02 1.182E-02 1.206E-02 3.203E-02 GROUND PLAME 1.OO6E-02 1.OO6E-02 1.OO6E-02 1.OO6E-02 1.OO6E-02 1.OO6E-02 f.OO6E-02 1.183E-02 INHALATION 2.178E-04 2.147E-04 1.578E-OS 2.312E-04 2.336E-04 3.607E-03 2.6tSE-04 2.106E-04 COW MILK 2.375E-03 1.056E-03 4.673E-03 5.038E-03 4.843E-03 1.031E+00 8.882E-04 7.828E-04 GOAT MILK 3.614E-03 1.849E-03 7.969E-03 8.388E-03 6.926E-03 1.238E+00 1.908E-03

?.597E-03

.I r

CP&L SEMI-AMMUAL RADIOLOGICAL EFFLUENT REPORTING RUN DATE: C 2/ tiV90 GASRPT LADIOTION DOSES GT SELECTE) LOCOTIONS RUN TIME: 08:54:07

'm

~

1989 SOURCE TERM (ELEVATED MODn) BSEP UNITS 1&2 THIS 1989 SOURCE TERM (GROUND LEVEL", SSEP UNITS 1 ANO 2 1989 SOURCE TERM (MIXED MODE) BSEP UNIT I AND 2 SPECIAL LOCATION METERS DIR PL GR IN V CM GM M

24 RESIOENCE 1609.0 SM 1

1 1 1 O O O ANNUAL BETA AIR DOSE = 8.974E-03 MILLRADS ANNUAL GAMMA AIR DOSE = 6.591E-03 MILLRADS TOTAL 800Y GI-TRACT BONE LIVER MIDNEY THYROID LUNG SRIN ADULT 6.894E-03 7.168E-03 6.842E-03 6.880E-03 6.849E-03 1.832E-02 6.863E-03 1.466E-02 PLUME 4.336E-03 4.33SE-03 4.336E-03 4.336E-03 4.336E-03 4.336E-03 4.426E-03 f.189E-02 GROUND PLANE 1.987E-03 1.987E-03 1.987E-03 1.987E-03 1.987E-03 1.987E-03 1.987E-03 2.337E-03 INHALATION 1.565E-04 1.590E-04 4.774E-06 1.604E-04 1.644E-04 1.023E-03 f.664E-04 1.539E-04 VEGETATION 4.134E-04 6.849E-04 5.131E-04 3.957E-04 3.609E-04 1.097E-02 2.837E-04 2.778E-04 TEENAGER 6.959E-03 7.217E-03 7.052E-03 6.963E-03 6.90fE-03 1.683E-02 6.916E-03 1.470E-02 PLUME 4.336E-03 4.336E-C3 4.336E-03 4.336E-03 4.336E-03 4.336E-03 4.426E-03 1.189E-02 GROUNO PLANE 1.987E-03 1.987E-03 1.987E-03 1.987E-03 1.987E-03 1.987E-03 1.987E-03 2.337E-03 INHALATION 1.583E-04 1.609E-04 6.378E-06 1.637E-04 1.692E-04 f.292E-03 1.737E-04 1.549E-04 VEGETATION 4.769E-04 7.327E-04 7.214E-04 4.754E-04 4.085E-04 9.211E-03 3.285E-04 3.18tE-04 CHILD 7.217E-03 7.23tE-03 7.888E-03 7.20SE-03 7.09tE-03 2.197E-02 7.074E-03 1.486E-02 co

'N PLUME 4.336E-03 4.336E-03 4.336E-03 4.336E-03 4.336E-03 4.336E-03 4.426E-03 1.189E-02 s

GROUND PLANE 1.987E-03 1.987E-03 1.987E-03 1.987E-03 1.987E-03 1.987E-03 1.987E-03 2.337E-03 I

INHALATION 1.408E-04 1.405E-04 8.188E-06 1.454E-04 f.502E-04 1.533E-03 1.526E-04

1. 3 70E-04 OD VEGETATION 7.527E-04 7.669E-04 1.556E-03 7.356E-04 6.371E-04 1.412E-02 5.082E-04 4.927E-04 INFAN7 6.40SE-03 6.404E-03 6.330E-03 6.480E-03 6.411E-03 7.673E-03 6.503E-03 1.43tE-02 PLUME c 336E-03 4.336E-03 4.336E-03 4.336E-03 4.336E-03 4.336E-03 4.426E-03 1.189E-02 GROUND PLANE 1.987E-03 f.987E-03 1.987E-03 1.987E-03 1.987E-03 1.987E-03 1.987E-03 2.337E-03 INHALATION 8.143E-05 8.023E-05 5.883E-06 8.636E-OS 8.732E-OS 3.349E-03 9.017E-05 7.877E-05

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

{-

CPIL SEMI-ANNUAL C A010 LOGICAL EFFLUENT REPORTING RUN DATE: C2/13/90 l

t GASRPT RADIATION DOSES CT SELECTE3 LOCATIONS RUN TIME: 08:54:07

'VU

3 1989 SOURCE TERM (ELEVATED MODE) BSEP UNITS 1&2 THIS 1989 SOURCE TERM (GROUND LEVEL) BSEP UNITS 1 AND 2 1989 SOURCE TERM (MIXED MODE) BSEP UNIT 1 AND 2 SPECIAL LOCATION METERS DIR PL GR IN V CM GM M s 3 SITE 800NOARY 1127.0 NE O 1 1 1 0 0 0 ANNUAL BETA AIR DOSE = 2.403E-02 MILLRA05 ANNUAL GAMMA AIR DOSE = 1.799E-02 MILLRAOS TOTAL 800Y GI-TRACT SONE LIVER KIDNEY THVROID LONG SKIN ADULT 1.179E-02 1.320E-02 1.200E-02 1.173E-02 1.157E-02 5.488E-02 1.130E-02 1.299E-02 GROUND PLANE 1.006E-02 1.006E-02 1.006E-02 1.006E-02' 1.006E-02 1.006E-02 1.006E-02 1.183E-02 INHALATION 4.184E-04 4.263E-04 1.284E-05 4.290E-04 4.398E-04 2.730E-03 4.722E-04 4.115E-04 WEGETATION 1.310E-03 2.714E-03 1.9 25E-03 1.241E-03 1.072E-03 4.209E-02 7.660E-04 7.427E-04 TEENAGER 1.201E-02 1.33SE-02 1.278E-02 1.202E-02 1.173E-02 4.874E-02 1.1A6E-02 1.310E-02 GROUND PLANE 1.006E-02 1.006E-02 1.006E-02 1.006E-02 1.006E-02 1.006E-02 1.006E-02 1.183E-02 INHALATION 4.232E-04 4.313E-04 1.715E-05 4.381E-04 4.527E-04 3.449E-03 5.043E-04 4.14tE-04 WEGETATION 1.528E-03 2.858E-03 2.699E-03 1.521E-03 1.211E-03 3.523E-02 8.917E-04 8.504E-04 CHILD 1.288E-02 1.307E-02 1.588E-02 1.280E-02 1.228E-02 6.816E-02 1.188E-02 1.352E-02 GROUND PLANE 1.006E-02 1.006E-02 1.006E-02 1.006E-02 1.006E-02 1.006E-02 1.006E-02 1.183E-02 O'

INHALATION 3.767E-04 3.76tE-04 2.202E-05 3.892E-04 4.018E-04 4.096E-03 4.402E-04 3.662E-04 N'

VEGETATION 2.446E-03 2.635E-03 5.798E-03 2.350E-03 1.8132-03 5.400E-02 1.379E-03 1.317E-03 t.

INFANT 1.028E-02 1.028E-02 1.008E-02 1.029E-02 1.030E-02 1.367E-02 1.032E-02 1.204E-02 GROUND PLANE 1.006E-02 1.006E-02 1.006E-02 1.006E-02 1.006E-02 1.006E-02 1.006E-02 1.183E-02 IMHALATION 2.178E-04 2.147E-04 1.578E-05 2.312E-04 2.336E-04 3.607E-03 2.GISE-04 2.106E-04

~.

Y

BSEP-90-0128, Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989

Text

1.0 INTRODUCTION

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BSEP-90-0128, Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989

Text

1.0 INTRODUCTION

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