Text

Semiannual Radioactive Effluent Rept,Jul-Dec 1987
	ML20149M930
Person / Time
Site:	Brunswick
Issue date:	12/31/1987
From:	Dietz C; CAROLINA POWER & LIGHT CO.
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	BSEP-88-0105, BSEP-88-105, NUDOCS 8802290274
	Download: ML20149M930 (67)
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Brunswick ~ Steam. Electric' Plant

-Semiannual _ Radioactive Effluents Report July 1, 1987 to December 31, 1987~

ATTACHMENTS: PAGES:

1.; Supplemental ~Information 1/1 to'1/4 ~

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

3. ODCM and PCP Revisions 3/1 to 3/3

~

4. Enviromental Monitoring Program 4/1 to.4/3

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

6. Major Modification to Radioactive Waste 6/1-Treatment Systems

7. Meteorological Data 7/1.

8. Potential Dose Assessment 8/1 to 8/3 s-E o

8902290274 871231 PDR ADOCK 05000324 R PDR h

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ATTACHMEf4T 1 Supplemental Information July 1, to December 31, 1987 1/1

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)

(i) 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 mrem to any organ (2) Calendar Year .

(a) 30 mrem to any organ C. Liquid efflunr.tr (Technical Specification 3.11.1.2)

- (1) Calendar Quarter (a) 3 mrem to total body (b) 10 mrem to any organ (2) Calendar Year (a) 6 mrem to total body (b) 20 mrem 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.

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2. Maximum permisethle concentrations.and dose rates which determine' maximum.instanitaneous release rates.

.A. Fission and activation gases (Technical Specification 3.11.2.1.a)

'(1) 500'arem/ year to. total body-(2) 3000 mrem / year to the skin B.' Iodine-131.-iodine-133, tritium, and particulates with half-lives greater than-eight days (Technical Specification 3.11.2.1.b)

(1) 1500 mrem / 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 10CFR20, Appendix B, Table II, column 2, for radionuclides other than' noble gases.

- (1) Tritium: MPC = 3 E-03 uCi/ml and

- (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 gamma spectroscopy.

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

C. Particulates Analysis for specific radionuclides collected on filter papers by gamma spectroscopy.

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

- Used as applicable limits for Table 2A 1/3 i

6 Nuclear counting statistics are reported utilizing 1-sigma error.

Total error where reported represents a best effort to=

approximate the total of all individual and sampling-errors.

4. Batch Releases A. Liquid (1) Number of batch releases: 2.89E 02 (2) Total time period for batch releases: 3.43E 04 Minutes (3) Maximum time period for a batch release: 3.14E 02 Minutes (4) Average time period for a batch release: 1.19E 02 Minutes (5) Minimum time period for a batch release: 8.00E 00 Minutes l

(6) Average time stream flow during periods l

of release of effluent into a flowing stream : 9.29E 05 B. Gaseous (1) Number of batch releases: 0.00E 00 )

Minutes '

(2) Total time period for a batch release: 0.00E 00 Minutes j i

(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 (l' Number of releases: 0.00E 00 (2) Total activity released: 0.00E 00 Curies B. Geseous (1) Number of releases: 0.00E 00 (2) Total activity released: 0.00E 00 Curies 1/4

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' ATTACHMENT 2 ,

LEffluent and Waste Disposal Data Brunswick Steam' Electric Pl' ant July 1, 1987.to December'31, 1987 Enclosure 1 Table 1A: Gaseous Effluents - Summation of all Releases Table 1B: Gaseous Effluents - Elevated Releases Table 10: Gaseous Effluents - Ground Level Beleases Table 2A: ' Liquid-Effluents - Summation of all Releases Table 2B: Liquid Effluents Lower Limits'of Detection i

Table 3: Solid Waste and Irradiated Fuel Shipments Enclosure 2 Combustion of Waste Oil 4 ,

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2 Table 1A

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Effluent and Waste' Disposal Semiannual' Reports Year 1987 Gaseous. Effluents.- Summation'ofJall' Releases i.

Est.

Total Unit: 'Otr_3 ;Otr 4' ' Error.%

' A. Fission and' activation.

gases

, 1.. Total release Ci =7.91E 03 4.35E 03 1215E 02-

>: 2. Average release uCi/sec 9.95E 02 5.47E 02 rate for period o

3. Percent of technical

-specification limit % 3.60E-01. 1.99E-01" B. Iodines

1. Total I-131 Ci 3.'42E-02 5.14E-03 7.002 01

2. Average release uC1/sec 4.31E-03 6.47E-04 rate for period C. Particulates

1. Total release C1 8.39E-02 2.12E-02 7.00E 01

2. Average release uCi/sec 1.06E-02 2.67E-03 rate for period

3. Gross alpha Ci 7.23E-06 7.99E-06 D. Tritium

1. Total release C1 1.95E 00 2.53E 00 7.00E 01 I 2. Average release uCi/sec 2.45E-01 3.18E-01 rate for period l

E. Iodine-131, lodine-133 Tritium

. and Particulates

1. Total Release C1 3.00E 00 2.59E 00

2. Average release uCi/sec 3.78E-01 3.25E-01 rate for period

3. Percent of technical specification limit % 1.71E 00 2.13E-01 I

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, e Table 1B

-Effluent'and Waste Disposal ~Semiannuel Report Year 1987 ,

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. Gaseous-Effluents - Elevated Releases Continuous Release ,

Nuclides-Released Unit Otr 3- Otr 41 >

1. Fission Gases

' argon-41 Ci 1.40E 01 2.60Ef01 krypton-85m' ' C1' l'.42E 01 '5.51E 01

. krypton-87 C1 1.09E 01 '1.36E 01-

-krypton-88 HCi 1.06E 01 7.79E 01.

xenon-133 Ci- 4.14E 01 8.22E 01 !

xenon-135m Ci- 2.16E 01 1.96E 01 xenon-135 C1 1.39E 01 9.08E 00 ,

xenon-137 HCi 1.82E 02 1.11E 02 xenon-138 Ci 6.40E 01 4.50E'01 total for period C1 3.73E 02 4.39E-02 2 .~ Iodines iodine-131 Ci 2.13E 1.87E-03 iodine-132 Ci 4.85E-03 3.08E-03 lodine-133 Ci li13E-02 7.32E-03 iodine-135 C1 -3.54E-03 3.37E-03 total for period C1 2.18E-02 1.56E-02 3.-Particulates chromium-51 Ci < LLD 1.82E-03 i manganese-54 Ci 7.89E-06 7.30E-05 cobalt-58 C1 < LLD 1.70E . cobalt-60 C1 3.34E-05. 2.69E-05 strontium-89 Ci 7.05E 3.53E-03 strontium-90 C1 2.76E-06 1.27E-05

-ruthenium-103 C1 1.69E-06 < LLD cesium-237 Ci 5.08E-05 3.69E-06 barium /lanthAnup-L40 Ci 7.98E-03 1.82E-03 total for. period C1 3.78E-03 7~30E-03

4. Tritium

~hycao.cs-3 C1 4.44E-01 7.98E-01 i

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Table 1C Effluent and Waste Disposal Semiannual Report Year 1987 Gaseous Effluents - Ground Level Releases Continuous Release Nuc.lides Released Unit Otr 3 Otr 4

1. Fission Gases krypton-87 Ci < LLD 7.06E-02 krypton-88 Ci < LLD 1.46E-01 xenon-133 Ci 8.19E 02 2.41E 03 xenon-135 Ci 6.72E 03 11 10E 03 total for period Ci 7.54E 03 3.91E 03

2. Iodines iodine-131 C1 3.21E-02 3.27E-03 iodine-132 C1 1.26E 00 3.43E-02 iodine-133 Ci 9.22E-01 2.77E-02 iodine-134 Ci 5.81E-02 1.22E-02 lodine-135 C1 1.89E 00 3.74E-02 total for period Ci 4.16E 00 1.15E-01

3. Particulates chromium-51 Ci 7.23E-02 1.15E-02 manganese-54 C1 2.03E-03 5.77E-04 cobalt-58 C1 1.24E-03 3.21E-04 cobalt-60 Cf. 1.83E-03 5.35E-04 Iron-59 Ci 4.42E-04 3.24E-05 strontium-69 C1 1.54E-04 3.18E-04 strontium-90 Ci 2 . '. 0 E- 0 6 4.32E-06 cesium-137 Ci 2.61E-05 1.85E-05

, barium-lanthanum-140 C1 2.11E-03 6.46E-04 cerium-141 Ci < LLD 4.48E-07 total for period Ci 8.01E-02 1.39E-02

4. Tritium hydrogen-3 C1 1.511 00 1.73E 00 2/4 t

Table 2A Effluent and Waste Disp > sal Semiannual Report' Year 1987 Liquid Effluente - Summation of all Releases Unit Otr 3 Otr 4 Est Tot.

% Error

'A. Fission and activation products

1. Total release (excluding C1 2.63E-01 2.15E-01 3.50E 01 tritium, gases, & alpha)

2. Avg. diluted conc. uCi/ml 4.21E-09 3.69E-09

3. Percent limit % 2.34E-01 1.39E-01 ,

B. Tritium

1. Total-release C1 2.77E 00 7.07E 00 4.00E 00

2. Avg. diluted conc. uC1/mi 4.44E-08 1.21E-07 ,

3. Percent limit % 1.48E-03 4.05E-03 C. Dissolved and Entrained gases

1. Total release C1 3.30E-02 5.53E-02 3.50E 01

2. Avg. diluted conc, uCi/mi 5.29E-10 9.50E-10

3. Percent limit . % 2.645-04 4.75E-04 D. Gross alpha radioactivity

1. Total release 9.41E-04 1.15E-04 4.00E 01 E. Volume of waste liters 1.02E 07 1.18E 07 1.25E 01 F. Total of dil, water liters 6.24E 10 5.82E 10 1.53E 01 (used during released for average dil. conc.)

G. Volun.c of cooling water liters 5.09E 11 4.47E 11 discharged from plant 2/5

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TABLE 2B Effluent and Waste Disposal Semiannual Report Year- 1987 Liquid Effluents - Batch Mode Nuclides Released Unit Qtr 3 Otr 4

1. Fission and act. products sodium-24 Ci 7.67E-03 3.52E-03 chromium-51 C1 2.88E-02 4.73E-02 manganese-54 Ci 7.77E-02 5.52E-02 iron-55 C1 1.03E-02 3.81E-03 cobalt-58 C1 1.09E-02 2.08E-03 iron-59 Ci 4.37E-04 < LLD cobalt-60 Ci 9.09E-02 4.23E-02 zinc-69m Ci < LLD 3.91E-06 arsenic-76 C1 1.43E-03 2.31E-03 strontium-89 C1 1.32E-04 4.50E-03 strontium-90 Ci < LLD 6.99E-05 strontium-92 Ci < LLD 5.08E-06 technetium-99m Ci < LLD 4.03E-05 technetium-101 Ci 2.33E-04 < LLD ruthenium-105 Ci 1.05E-05 < LLD antimony-125 Ci 5.92E-05 < LLD iodine-131 Ci 6,59E-03 8.09E-03 iodine-133 Ci 9.86E-03 1.38E-02 iodine-135 Ci 9.53E-05 3.11E-04 cesium-134 Ci 1.81E-03 3.33E-03 cesium-136 Ci 3.33E-05 2.71E-05 cesium-137 C1 1.58E-02 2.76E-02 barium / lanthanum-140 Ci 5.26E-05 7.72E-04 cerium-144 Ci < LLD 1.01E-04 tungsten-187 Ci

LLD 1.49E-04 total for period C1 2.63E-01 2.15E-01

2. Gases xenon-133 Ci 9.87E-03 1.48E-02 xenon-133m Ci 3.34E-05 < LLD xenon-135 C1 2.20E-02 4.02E-02 xenon-135m Ci 5.96E-05 3.20E-04 total for period Ci 3.20E-02 5.53E-02 I

2/e

Lower Limits of Detection uCi/ml

1. Liquid Releases 2. Gaseous Releases Fe-59 3.71 E-8 Kr-87 1.90 E-8 Zn-69m 7.51 E-9 Kr-88 2.22 E-8 Sr-90 2.27 E-9 Sr-92 1.59 E-8 3. Iodines and Particulates Tc-99m 7.87 E-9 Tc-101 6.96 E-8 Cr-51 2.54 E-13 Ru-105 4.27 E-8 Co-58 2.40 E-14 Sb-125 4.46 E-9 Ru-103 3.03 E-14 Xe-133m 1.04 E-7 Ce-141 3.54 E-14 Ce-144 4.76 E-8 W-187 3.37 E-8 NOTES 1: -The above values represent typical "a priori" LLDs for isotopes where values of "<LLD" are indicated in Tables 1A, 18, 1C, 2A, and 2B.

2: Where activity for any nuclide is reported as " Less than LLD", that nuclide is considered not present and the LLD activity listed is not considered in summary data.

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Table 3A Effluent and Waste Disposal Semiannual Report. Year 1987 Sc Id Waste and Irradiated fuel. Shipments Waste Class A July through December

1. Total volume shipped (cubic meters) 2.98 E2 Total Curie quantity (estimated) 7.65 E2

2. Type of Waste Units Six-month Est. Total Period Error,%

a. Spent resins, filter sludges meters

1.39 E2 Curies 7.56 E2 1.00E1

b. Dry active waste, compacted, meters 1.44 E2 noncompacted Curies 3.68 E0 1.00E1

c. Irradiated components meters" 3.63 EO Curies 4.74 E0 1.00E1

d. Others (oil) meters

1.13 El Curies 1.72 E-1 1.00E1

3. Estimate of major radionuclide composition

a. Mn-54 1.46 El%

Fe-55 4.77 El%

Co-60 3.08 El%

Hi-63 2.11 EO%

Cs-137 2.80 EO%

b. Mn-54 9.59 E0T.

Fe-55 6.83 El%

Co-60 1.99 El%

Ni-63 1,03 E0%

c. Mn-54 1.80 EO%

Fe-55 5.44 El%

Co-60 4.02 El%

- Ni-63 3.55 E0%

d. Fe-55 8.84 E0%

Co-60 5.21 E0%

Sr-89 6.94 El%

Sr-90 4.81 E0%

Cs-134 5.33 EO%

Cs-137 3.57 E07.

Pu-241 2.63 E0n 2/8

2 Table 3A (cont.)

Effluent and Waste Disposal Semiannual Report Year 1987 Solid Waste and Irradiated Fuel Shipments

4. Cross reference table. Waste stream, form, and containet- type.

Stream Form Container type No. of shipments

a. Resin Dewatered & Type A/ Type B 25/00 Solidified *

b. Dry active Compacted /non- LSA/STP 18 waste compacted waste

c. Irradiated Type B 1 components

d. Other LSA/STP 1

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

5. Shipment Disposition

a. Solid Waste Number of Shipments Mode of Transportation Destination 25 Sole Use Chem-Nuclear Barnwell. SC 1 Sole Use U.S. Ecology Richland. WA 16 Sole Use S.E.G.

Oak Ridge,Tenn 2 Sole U'fe GusuRex Oak Ridge,Tenn

b. Irradiated Components Number of Shipments Mode of Transportation Destination 1 Sole Use Crwm-Nuclear Barnwell, Sc 2/9

h Table 3B Effluent and Waste Disposal Semiannual Report Year 1987 Solid Wasts and Irradiated Fuel Shipments Waste Class B July through December

1. Total volume shipped, (cubic meters) 0.00 E0 Total Ci quantity (estimated)

2. Type of Waste Units Six-month Est. Total Period Error,7.

a. Spent resins, filter sludges meters * ~N/A N/A Curies

b. Dry active waste, compacted, meters

N/A N/A and noncompacted Curies

c. Irradiated components meters

N/A N/A Curies

d. Others (describe) meters

N/A N/A curies

3. Estimate of major radionuclide composition

a. N/A N/A

b. N/A N/A

c. N/A N/A

d. N/A N/A

4. Cross reference table, waste stream, form and container type t' ream Form Container type No. of shipments

a. Resin Dewatered & N/A N/A 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 2/20

Table 3B (cont.)

Effluent and Waste Disposal Semiannual Report Year 1987 Solid Waste and-Irradiated Fuel Shipments

5. Shipment Disposition

a. Solid Waste Number of Shipments Mode of Transportation Destination-N/A N/A N/A-

~b. Irradiated Fuel Number of Shipments Mode of Transportation Destination N/A N/A N/A 2/11

Table 3C-

. Effluent and' Waste Disposal Semiannual Report Year. 1987 Solid Waste and Irradiated Fuel. Shipments Waste Class'C -July throughLDecember

1. Total volume shipped, (cubic meters) 3.53 EO Total Ci quantity (estimated) 3.97 E4

2. Type of Waste Unit Six-month Est.~ Total Period Error,?.-

a. Spent resins, filter sludges meters

N/A Curies

b. Dry active waste, compacted meters

N/A and noncompacted

c. Irradiated components meters

3.53 EO Curies 3.97 E4 1.00 El

d. Others (describe) meters

N/A Curies

3. Estimate of major radionuclide composition

a. N/A

b. N/A

c. Mn-54 1.82 EOT.

Fe-55 5.31 E lf.

Co-60 4.12 Elf.

Ni-6J 3.79 E07,

d. N/A 4 ~ oss reference table, waste stream, form and container type Stream Form Container Type No. of shipments

a. Resin Dewatered & Type A/ Type B N/A Solidified *

b. Dry active Compacted /non- N/A N/A '

waste compacted

c. Irradiated Type B 4 components

d. Others N/A N/A

Solidification agent or absorbent (e.g., cement, urea formaldehyde) N/A 2/12

Table 3C (cont.)

Effluent and Waste Disposal Semiannual Report Year 1987-Solid Waste and Irradiated Fuel Shipments

5. Shipment Disposition

a. Solid Waste Number of Shipments Mode of Transportation Destination N/A N/A N/A

b. Irradiated Components Number of Shipments Mode of Transportation Destination 4 Sole Use Chem Nuclear Barnwell, SC 2/13

ENCLOSURE 2 Combustion of Waste Oil During the third quarter 6.14E 03 gallons of waste oil with 1.28E 00 uCi of waste oil were disposed by incineration. During the fourth quarter, 9.94E 02 gallons with 1.24E 00 uCi of oil were disposed of by incineration.

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ATTACHMENT 3 Off-Site Dose Calculation Manual (ODCM) and Process Control Program (PCP) Revisions July 1, to December 31, 1987 Brunswick Steam Electric Plant : Revisions to the Off-Site Dose Calculation Manual (ODCM) : Revisions to the Process Control Program (PCP) 3/1

ENCLOSURE 1 Revision 7 of the Off-Site Dose Calculation Manual (ODCM)

-Section 3.2.2, page 3-21-and section 3.3.2, page 3-40 were revised .to include technical specification reference for clarification.

. Table 3.3-2, page 3-30 was revised to include the most recent:

Land Use Census.

Section 3.2.2.1, page 3-42 was revised to correct a typographical error.

Section 4.0, page 4-1 was revised to correct a figure reference.

Table 4.0-1,pages 4-3 and 4-4 were revised to include an additional airborne sample-point (#205) and broadleaf vegetation sample point (#803) to the program.

Figure 4.0-1a, page4-5 and Figure 4.0-ic, page 4-7 were revised to indicate the locations of the airborne and broadleaf vegetation sample points added to the program.

AI-61. Attachment 1 has been included to provide ~ documentation of PNSC review.

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ENCLOSURE 2 Revisions to the Process Control Program (PCP)

There were no revisions to the PCP during this time period.

3/3

ATTACHMENT 1 REQUEST FOR OFF SITE DOSE CALCULATION MANUAL CHANGE Originator: 1e.ns NL k. be m Date: 9- \b- 67 Pages and sections revised: R-at ; 3 2.2 3 3 -3ch To.ble 3 2.-2

3-4 o; 2.'6.2.l J*

2-42. 3.3. A l

4-1 4.o:' 4 -3 464 t 4 -4. c. :

A-5j A-T Reason for change: Anu ud w cansa ushde j h k en4 *

c. W L n e 3 m o h m ore _ r t,a J.Oo:4.' 1Ce I-sb A comp 1,*cu w a%k %(nlemt sg.c.'A G Safety Analysis Complete j k [

(RCI-03.1 Attachment 1): e/ M A . I T Allh Date: 8"l8-87 6 ,.) -

h 1st Party Nuclear Safety Reviewer mendhNot Recomended Date: f/'/ /9 7

[,* / / /6 %. - ' decomendehNot Recomended Date: O S'/F 7 l 2nd . Party Nuclear Safety Reviewer ;

w ommen Ne,c Recomended Date: 7 f '[ i F4C fupervisor ~t My[M (Recom ~

fot Recomended Date: 9 8/-92 jESC Project Specialist g APPROVALS:

O : -

comende Not Recomended Date: 9y Manager - E&RC d~M /

/.Not Recomended Date: I o f 7 / P')

PNSC Chai~rman C DM ['p M ot f Approved Date: (e)y*[S'-) t General Manager

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RECElVED OCT 3 1981 BNP, D00. CONTROL i i BSEP/Vol. I/AI-61 3 Rev. 2

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s BRUNSWICK STEAM ELECTRIC PLANT 0FF-SITE DOSE CALCULATION MANUAL '

(ODCM) ,

b REVISION 7 t

a DOCKET NOS. 50-324 50-325 Y

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l CAROLINA POWER & LIGHT COMPANY ,

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LIST OF EFFECTIVE PAGES ODCM Page(s) Revision 1-11 7-iii-ix 6 1 0 2 2-2 0 2 2-6 1 2-7 0 2 2-10 1 2 2-12 0 2 2-16 1 3 3-12 4 3-13 1 3-14 4 3-15 5 3 3-18 4 3-19 6 3-20 1 3-21 7 3 3-23 1 3-24 4 3-25 1 3-26 4 3-27 6 3-28 4 3-29 1 3-30 7 3-31 4 3 3-36 1 3 3-38 4 3-39 6 3-40 7 3-41 1 3-42 7 3 3-45 1 3 3-48 4 3 3-68 1 4-1 7 4-2 5 4 4-5 7 4-6 3 4-7 7 5-1 0 6 6-2 0 6-3 4 A-1 0 A-2 4 A A-4 0 A A-7 4 ODCM (BSEP) i Rev 7

h LIST OF EFFECTIVE PAGES (Continued)

ODCM Pase(s) Revision A A-9 0 A A-13 4 A A-15 0 A A-19 4-A A-21 0 A-22 4 .

A A-28 O B B-33 0 C C-18 0 '

D D-2 1 E-1 4 i E-2 3 i E-3 4 F F-3 0 G-1 1 f

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LIST OF FIGURES No. _

Title g 4.0-ta BSEP Sample Point Locations................................ 4-5 4.0-lb BSEP Sample Point Locations................................ 4-6 4.0-1c BSEP Sample Point Locations................................ 4-7 F-1 Liquid Radwaste Effluent System............................ F-2 F-2 Gaseous Radwaste Effluent System........................... F-3 ODCM (BSEP) ix Rev 7

The.Vg factor is computed with conversion from air dose to tissue depth dose, thus; I

jk A gg u, EI g e -u Td vg = 1.1 K/r EEE (3.2-7) d jkl "j

where:

U T

=

The tissue energy absorption coefficient for photons of energy Eg , em /gm T

d

=

The tissue density thickness taken to represent the total body dose (5 ga/cm2 )

1.1 =

The ratio of the tissue to air absorption coefficients over the energy range of photons of interest, mres/arad 3.2.2 I-131. I-133, Particulates, and Tritium

The dose rate in unrestricted areas resulting from the release of radio-iodines and particulates with half-lives greater than 8 days is limited to 1500 mrem / year to any organ. Based upon NUREG 0133, the following is used to show compliance with 10CFR20.

Ig P g(W,h g + Wy gh) s MOO mrem /yr (3.2-0 s v where:

P g

=

Dose parameter for radioiodines and particulates with half-lives greater than 8 days based upon the critical organ and the most restrictive age group 3

= mrem / year per uCi/m for inhalation pathways and for tritium

For ODCM calculations performed to comply with T/S 4.11.2.1.2 and 4.11.2.3, the I-133 values used are determined by actual analysia. {

ODCM (BSEP) 3-21 Rev. 7

TABLE 3.2-2 DISTANCE TO CONTROLLING LOCATIONS AS MEASURED PROM THE BRUNSWICK PLANT CENTER (Mi) i Site Milk Milk Meat Nearest Nearest Sector: Boundary Cow Goat Animal Resident Garden NNE 0.7 - -

1.3 1.2 1.2 NE 0.7 4.75* - - - -

ENE 0.7 - - - - -

E 0.7 - - - - -

l ESE 0.7 - - -

1.6 1.6 l ,

SE 0.7 - - -

0.9 -

l I

SSE 0.7 - - -

2.3 - l

S 0.8 - - -

1.5 1.7 l SSW 0.8 - - -

1.4 1.4 l SW 0.7 - - -

1.0 1.0 WSW 0.7 - -

2.0 1.1 1.0 W 0.7 - - -

0.8 0.9 WNW 0.6 - - -

0.9 0.9 NW 0.6 - - -

0.9 -

NNW 0.6 - - -

0.9 1.0 l N 0.7 - - - - -

A "hypothetical" cow milk pathway is located at this point in accordance l with 5.3.1 of NUREG 0133.

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i ODCM (BSF 3-30 Rev. 7 i l

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fr For tre calendar year:

Dy s 20 mrad (3.3-11)

DS s 40 mrad (3.3-12) where:

Dy = The air dose from gamma radiation, mrad D8 = The air dose from beta radiation, arad The quarterly limits given above represent one-half the annual design objective of Section II.B.1 of Appendix I of 10CFR50. If any of the limits of ;

Expressions 3.3-9 through 3.3-12 are exceeded, a special report pursuant to Section IV.A of Appendix I of 10CFR50 must be filed with the NRC.

3.3.2 I-131, I-133, Particulates, and Tritium

i 3.3.2.1 Cumulation of DosesSection II.C of Appendix I of 10CFR50 limits the release of radiciodines and radioactive material in particulate form from each reactor such that estimated '

dose or dose commitment to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 arem to any organ. Based upon 7

NUREG 0133, the dose to an organ of an individual from radioiodines and !

particulater, with half-lives greater than 8 days in gaseous effluents released to unrestricted areas, can be determined by the following expression l During any calendar quarter of year:

i I

3.17 x 10 -8 I gRg (W, Qg +w,qt +Wy Qg &vy qt) s s v v s 7.5 area per quarter or 15 mrem per calendar year (3.3-13)

For ODCM calculations performed to comply with T/S 4.11.2.1.2 and 4.11.2.3, the I-133 values used are determined by actual analysis, i 4

r ODCM (BSEP) 3-40 Rev. 7 I i

~

I

= sec/m for the inhalation pathway and tritium ,

meters" for the food and ground plane pathway vy

The dispersion parameter for estimating the dose to an ,

individual at the controlling location for short : era vent releases (equal to or less than 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months / year)

= sec/m3 for the inhalation pathway and tritium

-2

= meters for the food and ground plane pathway 3.17 x'10~0 = The inverse of the number of seconds in a year .

Rg =

The dose factor for each identified radionuclide i of I the organ of 1.'terest, arem/yr per uC1/sec per m' or area /yr per uCi/m#

Radioiodines and particulates may be released from the stack, Reactor Buildings, and Turbine Buildings at BSEP. Radioiodines and particulates may f

also be released from decontamination operations in the Hot Shop. Effluents l from the Hot Shop roof vent are combined with the Turbine Building's vent ,

releases. At BSEP all releasas are considered long-term in duration.

Therefore, incorporating the various release points into Expression 3.3-13 results in the following expression to show compliance with 10CFR50 for a particu?ar organt 3.17 x .t0 -8 I R g

~

W,Qg +W rb (91 +9 1 )+ tb (91 +N i )

. s rbt rb2 tb1 tb2 s15.0arem(perquarter}or30mres(peryear) (3.3-14)

ODCM (BSEP) 3-42 Rev. 7

4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Table 4.0-1 contaihs the semple point description, sampling and collection frequency analysis, and analysis frequency for various exposure pathways in the vicinity of the BSEP for the radiological monitoring program. Figures 4.0-1a, 4.0-1b, and 4.0-le show the l

locations of the various points.

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o TABLE 4.0-1 (Cont'd) 9m v Esposure Path =ay Sample Sample Point Description Approminate Sampling and Analysis and/or Sample ID No. Distance, and Direction Collection Frequency Frequency Analysis (a)

DIRECT RADIAfl0N 33 4.0 alles E O O C m Dose (Cont'd) 34 5.5 miles ENE O O Camma Dose al 10.0 elles WNW (C) 0 0 Camma Dose-36 9.3 miles NE O O Comme Dese 37 5.5 elles NW 0 0 Camma Dose .

38 11.0 miles W 0 C, Camma Dose 39 5.3 miles SW 0 0 Camma Dese 40 6.9 miles WSW 0 0 Camma Dose AlkDORNE Radiolodine and 200 1.0 miles SW Vistors Center Continuous sampler W Radiolodine Particulate 201 0.6 alles NE PMAC operation eith sample Canister 202 1.0 miles 5 Substation - Const. Ild, collected meekly or as I- m analysis 203 2.3 miles SSW Southport substation required by dust load- Particulate sampler e 204 23 miles NME Sutton Plant - Contro1(c) lag, whichever is more -

Gross tota resto-

& 205 0.6 alles SSE 5 poll Pond frequent. activity analysis following filter l change in).

O em isotopie analysis of j

composite by i location. l WATERBONNE

a. Surface 400 0.7 elles NE Intake Canal - Control (c) Composite Sample (d) Monthly Camuna isotopic-CoIIectlan - M 0 Monthly Tritium 401 4.9 miles SSW Discharge Canal at 5till Pond

b. Sediment 500 4.9 alles SSW Discharge - Beach Sealannual Semiannual Comme isotopic u

O tan 8_E 4.0-1 (Cont'd)

S

=

hEsposurePathmey Sample Sample Point Descr!p:fon, Appromimete Samp3Ing and Analysta v and/or Sample ID No. Distance, and Direction Collection Frequency Frequency Analysis (a) lese 5fl0N l

a. Milk 600 To be identif fed as available. Camme isotopic (animels en 601 posture)

,1-131 analyses 642 (anteels on posture) 603 Camme isotopic (other times) 1-131 analysis (other times)

b. Fish and 700 5.5 mfle S$W Atlantic Ocean (e) Nhon in Season - Seefannual Gamme isotopic Inverte- at Discharge Sealannual on edible ;

brates 701 portiens (shrlap) p M2 703-705 Not Spectf fed - Atlantic Ocean (c)(e)

c. Broedleaf 800 0.7 miles NE Intake Canal leien available - Monthly Camme feetapic Vegetation Month!y 301 0.6 miles SW Discharge Canal Monthly 1-131 802 10 miles - Control - Location not Specified (c) 803 0.6 mIIes SSE Spell Pond l

(a) The LLD for each analysis is specified in Table 4.12.1-1 of the Todinical Speelfications for the Brunemick Steam Electric Plant.

(b) Particulate samples will be analyzed for gross bet *, radiation 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more felleming filter' change. Perform gamma scan en each sample ahon gross beta activity is 10 times the noen of the control station.

(c) Control Station - These stations are presumed to be outside the influence of plant ef fluents.

o O (d) Composite samples shall be collected by collecting an aliquot at intervals not exceeding 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

y (e) A sample of one free amiamor, one betten feeder, and one shellfish (shrlap) will be cellected if available. A control sample of each species collected will be obtained if available.

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ATTACHMENT 4 Enviromental Monitoring Program July 1, to December 31, 1987

. : Milk and Vegetable Sample Locations : Land Use Census 4/1 h

ENCLOSURE 1 Milk and Vegetable Sample Locations No milk sample locations were available during this time period.

No vegetable sample locations were deleted during this time period. However, a vegetable sample location (FC-803) was added to the program.

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4/2

i EtiCLOSURE 2 Land Use Census No new locations were identified that are reportable in the Semiannual Radioactive Effluent Release Report as per Technical Specification 3.12.2.a and b.

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4/3

k ATTACHMEftT 5 !

Inoperable Effluent Instrumentation July 1 to December 31, 1987 Enclosure la' Radioactive Liquid Effluent Monitoring Instrumentation Enclosure 2: Radioactive Gaseous Effluent Monitoring Instrumentation 3 Enclosure 3: Liquid Hold-Up Tank l

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1 3 r Et(CLOSURE a ,

Radioactive Liouid Effluent Monitoring Instrumentation i

P The liquid radwaste effluent flow mer.'eurement device (2-G16-FIT- ;

fiO57).-was inoperable for greater than 30 days during this time .!

period. ;

g This instrument was not returned to service within a 30 day ;

period due to the inability to calibrate the instrument within its design' accuracy. ;

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n ENCLOSURE 2 Radioactive Gaseous Effluent Monitoring Instrumentation Unit 1 & 2 main condensor off-gas treatment system explosive gas monitors 1(2)-OG-AIT-4284 (SJAE.A.H2 Analyzer), 1(2)-OG-AIT-4285 (SJAE.A.H2 Analyzer, 1(2)-OG-AIT-4324 (SJAE.B.H2 Analyzer), and 1(2)-OG-AIT-4325 (SJAE.B.H2 Analyzer) were inoperable for wreater chan a 30 day period during July 1, to December 31, 1987. Due to. design problems, these monitors were not returned to service within 30 days.

Units 1 and 2 Reactor and Turbine buildings roof vent flow monitor elements: 1-VA-FE-3356, 1-VA-FE-3358, 2-VA-FE-3356 and 2-VA-FE-3358 were inoperable for greater than a 30 day period during July 1, to December 31, 1987. Due to design problems these monitors were not returned to service within 30 days.

S/3

ENCLOSURE 3 Liquid Hold-Up Tank No liquid hold-up tank exceeded the 10 Ci limit during this time period.

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4 ki ATTACHMENT 6 '

A Najor Modifications to-the Radioactive Waste-Treatment: Systems July 1, to December 31~. 1987 Discussion-of majorLmodifications to the Radioactive Waste. Treatment Systeras , if any, will be submitted with the Final Safety. Analysis Report update'as allowed by footnote-7 to Technical Specification 6.15.

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6/1 1: -

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' ATTACHMENT ' '

Meteorological Data. ,

Brunswick Steam Electric' Plant --

+

' July 1, to. December 31,.1987- .

As'per Technical Specification:6.9.1.10.a footnote 6.-the annual- .

summary of~ meteorological data collected'over the calendar year will.

'be submitted to a file and will be available for'NRC review upon -

request.

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ATTACHMENT 8

~

Potential Dose Assessment Brunswick Steam Electric Plant July 1, to December 31, 1987 Attached is the annual dose assessment for the year. 1987.

Differences in the 1987 Annual' Dose Assessment from previous reports are due to using NRC Computer Programs LADTAP II and GASPAR.

Enclosure 1: Annual Liquid Dose Assessment Enclosure 2: Annual Gaseous Dose Assessment 8/1

Enclosure 1 Annual Liquid Dose Assessment Page 8/2-1 Title 8/2-2 Site Data l

8/2-3-5 Source Te"ms; Ingestion and Shoreline Dose Factor by Age Groups and 1 Organs (Shoreline dose factors are the same for all groups) l 8/2-6 As Low As Reasonably Achievable (Based on population within a 50 mile l dius) Release point at 2000 ft. offshore - Atlantic Ocean 8/2-7 Joses Due to the Consumption of Commercially Harvested Fish and Inver-tebrates (Based on population within a 50 mile radius) 8/2-8 Recreation Population Doses - Shoreline, Swimming, and Boating (Based on population within a 50 mile radius) 8/2

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EVALUATION OF RADIATION DOSES FROM RELEASES OF RADIACTIVITY

IN NUCLEAR POWER PLANTS LIQUID EFFLUENTS REVISION DATE: PNL VAX - OCTOBER 1985

BSEP UNITS I AND 2 LIQUID RELEASES 1987 *

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RADIOLOGICAL ASSESSMENT BRANCH

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DIVISION OF SYSTEMS INTEGRATION

i l U. S. NUCLEAR REGULATORY COMMISSION ' *-

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WASHINGTON, D. C.

DATE OF RUN 02/11/88 *

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ESEP UNITS I AP40 2 LIQUID RELEASES 1987 DISCHARGE =1.59E+03 CFS SOURCE TERM MULTIPLIERat.00E+00

{

50-MILE POPULATIONm7.37E+05 FRACTION --- ADULT =0.71 TEENAGER =G.I1 CHILO=0.18 SALTWATER SITE i

8/2-2

SOURCE TER3 CATC9 ONLY NO CONTINUOUS IN 1937 PROBLEO IDENTIFYIbG RAOIONUCLIDE AS76 4.02E-OJ NO INTERNAL RECONCENTRATION MODEL EMPLOVED

*

ADULT DOSE FACTORS * *

INGESTION DOSE FACTORS SHORELINE (MREM /PCI INTAME) (MREM /HR)/(PCI/M**2)

NUCLIDE CURIE / YEAR BONE LIVER TOTAL 800Y THYROID AIDNEY LUNG GI-LLI SKIN TOTAL 800Y RECON 1H 3 1.93E+01 0.OOE+00 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 0.00E+00 0.00E+00 1.00E+00 51NA 24 1.12E-02 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 2.90E-08 2.50E-08 1.00E+00 24CR 51 9.59E-02 0.00E+00 0.OOE+00 2.66E-09 1.59E-09 5.86E-10 3.5eE-09 6.69E-07 2.60E-10 2.20E-10 1.00E+00 1 25MN 54 2.57E-01 0.00E+00 4.57E-06 8.72E-07 0.00E+00 1.36E-06 0.00E+00 1.40E-05 6.80E-09 5.80E-09 1.00E+00 26FE 55 2.71E-02 2.75E-06 1.90E-06 4.43E-07 0.00E+00 0.00E+00 1.06E-06 1.09E-06 0.00E+00 0.00E+00 1.00E*00 27CO 58 2.33E-02 0.00E*OO 7.45E-07 1.67E-06 0.OOE+00 0.00E+00 0.00E+00 1.51E-05 8.20E-09 7.00E-09 1.00E+00 2700 60 1.92E-01 0.00E+00 2.14E-06 4.72E-06 0.OOE+00 0.00E+00 0.00E+00 4.02E-05 2.00E-08 1.70E-08 1.00E+00 26FE 59 4.96E-03 4.34E-06 1.02E-05 3.91E-06 0.00E+00 0.00E+00 2.85E-06 3.40E-05 9.40E-09 8.00E-09 1.00E+00 385R 90 6.99E-05 7.58E-03 0.00E+00 1.86E-03 0.00E+00 0.00E+00 0.00E+00 2.19E-04 0.00E*00 0.00E+00 1.OOE+00 39V 91M t.68E-05 9.09E-11 0.00E+00 3.52E-12 0.00E+0C O.00E+00 0.00E+00 2.67E-10 4.40E-09 3.80E-09 1.00E+00 40ZH 95 3.15E-05 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.53E-08 0.00E+00 3.09E-05 5.80E-09 5.00E-09 1.00E+00 41NB 95 3.15E-05 6.22E-09 3.46E-09 1.86E-09 0.00E+00 3.42E-09 0.00E+00 2.10E-05 6.OOE-09 5.10E-09 1.00E+00 437C 99M 2.39E-04 2.47E-10 6.98E-10 8.89E-09 0.OOE+00 1.06E-08 3.42E-10 4.13E-07 1.10E-09 9.60E-10 1.00E+00 449" ~05 1.05E-05 1.54E-08 0.00E+00 6.08E-09 0.00E+00 1.99E-07 0.00E+00 9.42E-06 5.10E-09 4.50E-09 1.00E+00 45HH 105 1.05E-05 1.21E-07 8.85E-08 5.83E-08 0.00E+00 3.76E-07 0.00E+00 1.41E-05 7.70E-10 6.60E-10 1.00E+00 53I 131 1.57E-02 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 0.00E+00 1.57E-06 3.40E-09 2.80E-09 1.00E+00 531 133 2.4tE-02 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 0.00E+00 2.22E-06 4.50E-09 3.70E-09 1.00E+00 55CS 134 5.21E-03 6.22E-05 1.48E-04 1.21E-04 0.OOE+00 4.79E-05 1.59E-05 2.59E-06 1.40E-08 1.20E-08 1.00E+00 5505 137 4.53E-02 7.97E-05 1.09E-04 7.14E-05 0.OOE+00 3.70E-05 1.23E-05 2.11E-06 4.90E-09 4.20E-09 1.00E+00 568A 140 9.53E-04 2.03E-05 2.55E-08 1.33E-06 0.00E+00 8.67E-09 l.46E-08 4.18E-05 2.40E-09 2.10E-09 1.OOE+00 57LA 140 9.53E-04 2.50E-09 1.26E-09 3.33E-10 0.00E+00 0.00E+00 0.00E+00 9.25E-05 1.70E-08 1.50E-08 1.OOE+00 58CE 144 1.01E-04 4.88E-07 2.04E-07 2.62E-08 0.OOE+00 1.21E-07 0.00E+00 1.65E-04 3.70E-10 3.20E-10 1.00E+00 74w 187 1.51E-04 1.03E-07 8.61E-08 3.01E-08 0.00E+00 0.00E+00 0.00E+00 2.82E-05 3.60E-09 3.10E-09 1.OOE+00 30ZN 65 8.50E-06 4.84E-06 1.54E-05 6.96E-06 0.00E+00 1.03E-05 0.00E+00 9.70E-06 4.60E-09 4.00E-09 1.OOE+00 30ZN 69M 3.91E-06 l.70E-07 4.08E-07 3.73E-08 0.00E+00 2.47E-07 0.00E+00 2.49E-05 3.40E-09 2.90E-09 1.00E+00 385R 89 4.72E-03 3.08E-04 0.00E+00 8.84E-06 0.00E+00 0.00E+00 0.OOE+00 4.94E-05 6.50E-13 5.60E-13 1.00E+00 385R 92 1.29E-04 2.15E-06 0.OCE+00 9.30E-08 0.00E+00 0.00E+00 0.00E+00 4.26E-05 1.OOE-08 9.00E-09 1.00E+00 43TC 101 2.33E-04 2.54E-10 3.66E-10 3.59E-09 0.00E*00 6.59E-09 1.87E-10 1.10E-21 3.00E-09 2.70E-09 1.00E+00 4 7AG 110M 3.09E-04 1.60E-07 1.48E-07 8.79E-08 0.OOE+00 2.91E-07 0.00E+00 6.04E-05 2.10E-08 1.80E-08 1.00E+00 5158 125 3.33E-04 1.79E-06 2.OOE-08 4.26E-07 1.82E-09 0.OOE+00 1.38E-06 1.97E-05 3.50E-09 3.10E-09 1.00E+00 53I 132 1.24E-05 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0.00E+00 1.02E-07 2.00E-08 1.70E-08 1.00E+00 52TE 132 5.8tE-07 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0.00E+00 7.71E-05 2.00E-09 l.70E-09 1.00E+00 53I 135 4.06E-04 4.43E-07 1.16E-06 4.28E-07 7.65E-OS 1.86E-06 0.00E+00 1.31E-06 l.40E-08 1.20E-08 1.00E+00 SSCS 136 6.04E-05 6.51E-06 2.57E-05 1.85E-05 0.OOE+00 1.43E-05 1.96E-06 2.92E-06 1.70E-08 1.50E-08 1.00E+00 568A 139 1.07E-04 9.70E-08 6.91E-11 2.84E-09 0.00E+00 6.46E-11 3.92E-11 1.72E-07 2.70E-09 2.40E-09 1.00E+00 57LA 142 1.81E-06 1.28E-10 5.82E-11 1.45E-11 0.00E+00 0.00E+00 0.00E+00 4.25E-07 l.80E-08 1.50E-08 1.00E+00 93NP 239 4.80E-06 1.19E-09 1.17E-lO 6.45E-11 0.00E+00 3.65E-10 0.00E+00 2.40E-05 1.10E-09 9.50E-10 1.00E+00

*

TEENAGER DOSE FACTORS * *

INGESTION DOSE FACTORS SHORELINE (MREM /PCI INTAME) (MREM /HR)/(PCI/M+*2)

NUCLIOE CURIE /vEAR BONE LIVER TOTAL 800Y THvROID MIONEY LUNG GI-LLI SKIN TOTAL BODY RECON 1H 3 1.93E+01 0.00E+00 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 11NA 24 1.12E-02 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 24CR 53 9.59E-02 0.00E+00 0.00E+00 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 25MN 54 2.57E-Ot 0.00E+00 5.90E-06 1.17E-06 0.00E+00 1.76E-06 0.00E+00 1.21E-05 26FE 55 2.71E-02 3.78E-06 2.68E-06 6.25E-07 0.00E+00 0.00E+00 1.70E-06 1.16E-06 27C0 58 2.33E-02 0.OOE+00 9.72E-07 2.24E-06 0.00E+00 0.00E+00 0.00E+00 1.34E-05 27CO 6C 1.93E-01 0.00E+00 2.81E-06 6.33E-06 0.00E+00 0.00E+00 0.00E+00 3.66E-05 26FE 59 4.96E-03 5.87E-06 1.37E-05 5.29E-06 0.OOE+00 0.OOE+00 4.32E-06 3.24E-05 385R 90 6.99E-05 8.300-03 0.00C+00 2.05E-03 0.00E+00 0.00E+00 0.00E+00 2.33E-04 39v 40ZR 95 91M 1.68E-05 1.29E-10 0.OOE+00 4.93E-12 0.00E+00 0.00E+00 0.00E+00 6.09E-09 8/2-3 3.15E-05 4.12E-08 1.30E-08 8.94E-09 0.00E+00 1.91E-08 0.00E+00 3.00E-05 41NB 95 3.15E-05 8.22E-09 4.56E-09 2.51E-09 0.00E+00 4.42E-09 0.00E+00 1.95E-05 43TC 99M 2.39E-04 3.32E-10 9.26E-10 1.20E-08 0.00E+00 1.38E-08 5.14E-10 6.08E-07

+ +

44Ru 103 1.05E-05 2.l!E-C3 0.00E+00.0.46E-09 0.00E*00 2.75E-07 0.00E+00 1.70E-05 -

45RH 105 1.05E-05 8.73E-07 1.25E-G7 C.2!E-08 0.0;E+00 5.31E-07-0.00E+00 1.5IE-05 531 131 1.57E-C2 5.CSE-06 0.1EE-06 4.CCE-01 2.3IE-03 1.41E-05 0.00E*00 1.S2E-06 531 133 2.41E-02 2.01E-06 3.41E-06 8.04E-06 4.76E-04 5.98E-06 0.00E+00 2.58E-06 55CS 134 5.2tE-03 8.37E-05 1.97E-04 9.14E-05 0.OOE+00 6.26E-05 2.39E-05 2.45E-06 55CS 137 4.53E-02 1.12E-04 1.49E-04 5.19E-05 0.00E+00 5.07E-05 1.97E-05 2.12E-06 568A 140 9.53E-04 2.84E-05 3.48E-08 1.83E-06 0.00E+00 1.18E-08 2.34E-08 4.38E-05 57LA 140 9.53E-04 3.48E-09 1.71E-09 4.55E-10 0.00E+00 0.00E+00 0.00E+00 9.82E-05 58CE 144 1.01E-04 6.96E-07 2.88E-07 3.74E-08 0.00E+00 1.72E-07 0.00E+00 1.75E-04 74w 187 1.51E-04 8.46E-07 1.19E-07 4.17E-08 0.00E+00 0.00E+00 0.00E+00 3.22E-05 JOZN 65 8,50E-06 5.76E-06 2.00E-05 9.33E-06 0.00E+00 1.28E-05 0.00E+00 8.47E-06 30ZN 69M 3.91E-06 2.40E-07 5.66E-07 5.19E-08 0.00E+00 3.44E-07 0.00E+00 3.11E-05 385R 89 4.72E-03 4.40E-04 0.00E+00 1.26E-05 0.00E*00 0.00E+00 0.00E+00 5.24E-05 385R 92 8.29E-04 3.05E-06 0.00E+00 1.30E-07 0.00E+00 0.00E+00 0.00E+00 7.77E-05 437C 101 2.33E-04 3.60E-10 5.12E-lO 5.03E-09 0.00E+00 9.26E-09 3.12E-10 8.75E-17 4 7AG 110m 3.09E-04 2.05E-07 1.94E-07 1.18E-07 0.00E+00 3.70E-07 0.00E+00 5.45E-05 5158 125 3.33E-04 2.48E-06 2.71E-08 5.80E-07 2.37E-09 0.00E+00 2.18E-06 1.93E-05 531 132 1.24E-05 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0.00E+00 3.18E-07 52TE 132 5.81E-07 3.49E-06 2.2tE-06 2.00E-06 2.33E-06 2.12E-05 0.OOE+00 7.00E-05 53I 135 4.06E-04 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 0.OOE+00 1.74E-06 55CS 136 6.04E-05 8.59E-06 3.38E-05 2.27E-05 0.00E+00 1.84E-05 2.90E-06 2.72E-06 568A 139 f.07E-04 1.39E-07 9.78E-11 4.05E-09 0.00E+00 9.22E-11 6.74E-11 1.24E-06 57LA 142 f.81E-06 1.79E-10 7.95E-11 1.98E-11 0.00E*00 0.00E+00 0.00E+00 2.42E-06 93NP 2J9 4.80E-06 1.76E-09 1.66E-10 9.22E-st 0.00E+00 5.21E-10 0.00E+00 2.67E-05

*

CHILD DOSE FACTORS * *

INGESTION DOSE FACTORS SHORELINE (MkEM/PCI INTAME) (MREM /HR)/(PCI/M**2)

NUCLIOE CURIE /VEAR BONE LIVER TOTAL 800Y THYROID KIDNEY LUNG GI-LLI SMIN TOTAL 800Y RECON IH 3 1.93E+01 0.00E+00 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 IINA 24 1.12E-02 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 24CR 51 9.59E-02 0.00E+00 0.00E+00 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 25MN 54 2.57E-On 0.00E+00 1.07E-05 2.85E-06 0.00E+00 3.00E-06 0.00E+00 8.98E-06 26FE 55 2.71E-02 1.15E-05 6.10E-06 1.89E-06 0.00E+00 0.00E+00 3.45E-06 1.13E-06 27C0 58 2.33E-02 0.00E+00 1.80E-06 5.51E-06 0.OOE+00 0.OOE+00 0.00E+00 1.05E-05 27CO 60 1.93E-Ot 0.00E+00 5.29E-06 1.56E-05 0.00E+00 0.00E+00 0.00E+00 2.93E-05 26FE 59 4.96E-03 t.65E-05 2.67E-05 1.33E-05 0.00E+00 0.00E+00 7.74E-06 2.78E-05 385R 90 6.99E-05 1.70E-02 0.00E+00 4.31E-03 0.00E+00 0.00E+00 0.00E+00 2.29E-04 39V 91N 1.68E-05 3.82E-10 0.00E+00 1.39E-11 0.03E+00 0.00E+00 0.00E+00 7.48E-07 40ZR 95 3.15E-05 1.16E-07 2.55E-08 2.27E-08 0.00E+00 3.65E-08 0.00E+00 2.66E-05 41N8 95 3.15E-05 2.25E-08 8.76E-09 6.26E-09 0.00E*00 8.23E-09 0.00E+00 1.62E-05 43TC 99M 2.39E-04 9.23E-10 1.8tE-09 3.00E-08 0.00E+00 2.63E-08 9.19E-10 1.03E-06 44RU 105 1.05E-05 6.45E-08 0.00E+00 2.34E-08 0.00E+00 5.67E-07 0.00E+00 4.21E-05 45HH 105 1.05E-05 5.14E-07 2.76E-07 2.36E-07 0.OOE+04 1.10E-06 0.OOE+00 1.7tE-05 53I 331 1.57E-02 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 0.00E+00 1.54E-06 531 133 2.41E-02 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0.00E+00 2.95E-06 55CS 134 5.2tE-03 2.34E-04 3.84E-04 8.10E-05 0.00E+00 1.19E-04 4.27E-05 2.07E-06 55CS 137 4.53E-02 3.27E-04 3.13E-04 4.62E-05 0.OOE+00 1.02E-04 3.67E-05 f.96E-06 568A 140 9.53E-04 8.3tE-05 7.28E-08 4.85E-06 0.00E+00 2.37E-08 4.34E-08 4.21E-05 57LA 140 9.53E-04 1.01E-08 3.53E-09 1.19E-09 0.00E+00 0.00E+00 0.00E+00 9.84E-05 58CE 144 1.0tE-04 2.08E-06 6.52E-07 1.11E-07 0.OOE+00 3.61E-07 0.00E+00 1.70E-04 74w 187 1.5tE-04 4.29E-07 2.54E-07 1.14E-07 0.00E+00 0.00E+00 0.00E+00 3.57E-05 30ZN 65 8.50E-06 1.37E-05 3.65E-05 2.27E-05 0.00E+00 2.30E-05 0.00E+00 6.41E-06 30ZN 69M 3.91E-06 7.10E-07 1.21E-06 1.43E-07 0.00E+00 7.03E-07 0.00E+00 3.94E-05 385R 89 4.72E-03 1.32E-03 0.00E+00 3.77E-05 0.OOE+00 0.00E+00 0.00E+00 5.11E-05 385R 92 1.29E-04 9.03E-06 0.00E+00 3.62E-07 0.00E+00 0.00E+00 0.00E+00 1.7tE-04 437C 101 2.33E-04 1.07E-09 1.82E-09 1.42E-08 0.00E+00 1.9tE-08 5.92E-10 3.56E-09 47AG 110m 3.09E-04 5.39E-07 3.64E-07 2.91E-07 0.00E+00 6.78E-07 0.00E+00 4.33E-05 5158 325 3.33E-04 7.16E-06 5.52E-08 l.50E-06 6.63E-09 0.00E+00 3.99E-06 1.71E-05 531 132 1.24E-05 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.00E+00 1.73E-06 52TE 132 5.8tE-07 1.0tE-05 4.47E-06 5.40E-06 6.5tE-06 4.15E-05 0.00E+00 4.50E-05 531 135 4.06E-04 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0.00E+00 2.40E-06 55CS 836 6.04E-05 2.35E-05 6.46E-05 4.18E-05 0.00E+00 3.44E-05 5.13E-06 2.27E-06 8/2-h

, 568A 139 1.07E-04 4.14E-07 2.21E-10 1.20E-08 0.00E+00 1.93E-10 1.30E-10 2.39E-05 57LA I42 1.81E-06 5.24E-10 1.67E-lO 5.23E-Il O.00E+00 0.OOE+00 0.00E+00 3.31E-05

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AS LOW AS REASONABLY ACHIEVAILE *

A DUL T D0$ES DOSE __(MREM PER VEAR INTAKE)

PATHWAY SKIN BONE LIVER TOTAL BODY THVROID KIDNEY LUkG /GI-LLI FISH 3.08E-04 8.30E-04 3.21E-04 2.21E-04 1.87E-04 1.06E-04' 2.39E-03 INVERTEBRATE 3.53E-04 5.28E-04 3.03E-04 2.75E-04 3.49E-05 SHORELINE .l.49E-04 2.SSE-03' 4.92E-03 4.19E-03 4.19E-03 4.19E-03 4.19E-03 4.19E-03 4.19E-03 SWIMMING 3.57E-06 4.19E-03 3.57E-06 3.57E-06 3.57E-06 3.57E-06 3.57E-06 3.57E-06 BOATING 1.79E-06 1.79E-06 1.79E-06 1.79E-06 TOTAL 4.92E-03 1.79E-06 8.79E-06 ~ 1.79E-06 4.86E-03 5.56E-03 4.82E-03 4.69E-03 4.42E-03 4.45E-03 8.94E-03 USAGE (KG/VR.HR/YR) DILUTION TIME (HR) 5HOREWIDTH FACTOR =0.5 FISH 29.2 30.0 24.00 INVERTEBRATE 7.3 30.0 24.00 SHORELINE 500.0 30.0 0.00 SMIMMING 100.0 30.0 0.00 80ATILG 100.0 30.0 0.00 T EEN A GER D0$ES DOSE __(MREM PER VEAR INTAKE)

PATHWAv SKIN BONE LIVER TOTAL BOOV THVROID KIDNEY LUNG GI-LLI FISH 4.25E-04 1.11E-03 3.68E-04 2.72E-04 2.45E-04 1.67E-04 2.34E-03 INVERTEBRATE 4.83E-04 7.14E-04 4.00E-04 3.39E-04 4.58E-05 SHORELINE 4.92E-03 2.35E-04 2.17E-03 "

4.19E-03 4.19E-03 4.19E-03 4.19E-03 4.19E-03 4.19E-03 4.19E-03 SWIMMING 3.57E-06 3.57E-06 3.57E-06 3.57E-06 COATING 3.57E-06 3.57E-06. 3.57E-06 1.79E-06 1.79E-06 8.79E-06 1.79E-06 1.79E-06 1.79E-06 1.79E-06 TOTAL 4.92E-03 5.10E-03 6.02E-03 4.96E-03 4.81E-03 4.49E-03 4.60E-03 8.50E-03 USAGE (KG/VR.HR/VR) DILUTION TIME (HR) SHOREWIDTH FACTOR =0.5 FISH 29.2 30.0 24.00 INVERTEBRATE 7.3 30.0 24.00 SHORELINE $00.0 30.0 0.00 Su!MMING 100.0 30.0 0.00 EOATING 100.0 30.0 0.00

CH I L0 D0SES DOSE __(MREM PER YEAR INTAKE) i PATHWAY SKIN BONE LIVER TOTAL BODY THVROID KIDNEY LUNG GI-LLI FISH 1.26E-03 2.16E-03 8.03E-04 6.68E-04 4.4GE-04 j

INVERTESRATE 3.24E-04 1.67E-03 1.44E-03 1.46E-03 1.00E-03 8.32E-04 8.22E-05 4.58E-C4 1.78E-03 SHORELINE 4.92E-03 4.19E-03 4.19E-03 4.19E-03 4.19E-03 4.19E-03 SulMMING 4.19E-03 4.19E-03 3.57E-06 ~3.57E-06 3.57E-06 3.57E-06 3.57E-06 3.57E-06 3.57E BOATING 1.79E-06 1.79E-06 -1.79E-06 1.79E-06 1.79E-06 TOTAL 1.79E-06 1.79E-06 4.92E-03 6.90E-03 7.82E-03 6.00E-03 5.70E-03 4.72E-03 4.98E-03 7.65E-03 USAGE (MG/VR.HR/VR) DILUTION TIME (HR). SHOREWIDTH FACTOR =0.5 FISH 29.2 30.0 24.00 INVERTEBRATE 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 8/2-6

,s-e e o I NVF4 T E"43 A T E CONSUMPTION POPULATION DOSES' * *

PERSON-RE2 COMMERCIAL HARVEST

DOSE (PERSON-REM)-------------------------

PATHWAv AGE GROUP USAGE BONE LIVER INVER TOTAL 800Y THYROID KIDNEY LUNG GI-LLI ADULT 5.23E+05 5.50E-06 8.10E-06 4.72E-06 f.79E-06 INVER TEENAGER 5.39E-07 2.30E-06 3.63E-05 6.08E*04 8.76E-07' 1.28E-06 7.23E-07 2.55E-07 8.19E-08 4.2tE-07 3.88E-OS INVER CHILD 4.38E+04 1.88E-06 1.88E-06 1.31E-06 INVER 4.40E-07 1.06E-07 5.94E-07 2.28E-06 :

TOTAL 6.28E+05 8.26E-06 1.13E-05 6.75E-06 2.49E-06 7.26E-07 3.31E-06 4.2SE-05 LOCATION DILUTION CATCH ATLANTIC OCEAN TIME (HR)-INCLUDES FOOO PROCESSING TIME OF 2.40E+02 HR POPULATION =7.37E+05 1.00E+02 3.08E+05 2.40E+02 AVERAGE INDIVIDUAL CONSUMPTION (MG/YR) ADULT =1.00E+00 TEEN =7.50E-01 CHILD =3.30E-01

* + FISH CONSUMPTION POPULATION DOSES * *

PERSON-REM COutcERCIAL HARVEST

DOSE (PERSON-REM)--------~~---------------

PATHWAY AGE GROUP USAGE FISH SONE LIVER TOTAL 800Y THYROID KIDNEY LONG GI-LLI ADULT 3.61E+06 2.96E-04 8.03E-04 3.09E-04 8.86E-05 FISH 1.8tE-04 1.01E-04 2.27E-03 TEENAGER 4.22E+05 4.78E-05 1.24E-04 4.12E-05 1.27E-05 FISH CHILD 2.77E-05 1.85E-05 2.37E-04 2.92E+05 9.80E-05 1.68E-04 6.20E-05 2.09E-05 3.44E-05 2.49E-05 1.28E-04 FISH TOTAL 4.32E+06 4.42E-04 1.10E-03 4.12E-04 1.22E-04 2.43E-04 1.44E-04 2.64E-03 LOCATION DILUTION CATCH ATLANTIC OCEAN TIME (HR)-INCLUDES FOOD PROCESSING TIME OF 2.40E+02 HR POPULATION =7.37E+05 1.00E+02 1.75E+07 2.40E+02 AVERAGE INDIVIOUAL CONSUMPTION (MG/VR) ADULT =6.90E+00 TEEN =5.?OE+00 CHILO=2.20E+00 8/2-7 4

~

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RECREATION POPULATION DOSES * ' Le

LOCATION- SEACHES

.s OILUTIONs 1.OOE+02 ' TRANSIT TIME = 0.OOE+00 HR SWF='O.5 r!

its_ 'l i

DOSE (PERSON-REM)

PATHMAY AGE GROUP USAGE SKIN TOTAL 800Y THYROIO-SHORELINE TOTAL POPUL 1.80E+06 5.32E 4.53E-03 4.53E 33- '

i LOCATION- 0.58EACHES DILUTION = 1.OOE+02 TRANSIT TIME = 0.OOE+00 HR DOSE.(PERSON-REM)

PATHMAY AGE GROUP USAGE . SMIN TOTAL SOOY THYROID Su!MMING TOTAL POPUL 9.50E+05 1.02E-05 1.02E LOCATION- ATLANTIC OCEAN DILUTION = 1.OOE+02 TRANSIT TIME = 0.OOE+00 HR DOSE (PERSON-REM)

PATHMAY AGE GROUP USAGE SKIN TOTAL SODY BOATING THYROID .

TOTAL POPUL 9.OOE+05 4.82E-06 4.82E-06 8/2-8

Ecclosure 2 Annual Gaseoua Dose Assessment iage

.8/3-1 Title 8/3 Source Terms for the Three Release Modes and the Aggregate 8/3-h 8/3-5 Total 50 mile Integrated Population Dose for all Age Groups by Pathways and Organs 8/3-6 Hypothetical Maximum Individual Organ Dose Due to Iodines, Particulates (Ib > 8 days) and Tritium at h.75 Miles. The NE sector yeilds the highest dose.

8/3-7 Maximum Site Boundary Dose by Age Groups and Organs 8/3-8 & True Individual Organ Dose (1987 Land Use census) 8/3-9 8/3-10 Maximum Site Boundary Dose Due to Iodines, Particulates (Tb > 8 days),

Tritium 8/3

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e EVALUATION OF ATMOSPHERIC RELEASES

e COMPUTED 02/09/88

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BRUNSWICK UNITS I AND 2. 50 MILE INTEGRATED DOSE 1987

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e F.F. ECKERMAN. D.G. LASH REVISED 8/19/77

1 RADIOLOGICAL ASSESSMENT ORANCH

a U.S. NUCLEAR REGULATORY COMMISSION

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t Cf &L SE 1-ANNUAL Rt.DIOLOGICAL dFFLUEMT REPORTING : EUN DATE: - C2/1S/60-GASRPT ,

INPUT 500RCE TERM 5 RUN TIME: 15:10:45' -

BRUN5w!CM UNITS 1 ANO 2. ELEVATEO. CONTINUOUS GASEOUS RELEASES, 1987 I H -- 3 2.040E+00 18 AR- di 5.410E+08 24 CR- 51 2.530E-03 '

' 25 MM- 54 2.090E-04 ~

27 CO- 58 2.300E-05

27 CO- 60 1.990E-04 '_

36 MR- 85 M 7.060E+01 36 KR- 87 3.030c+01 36 KR- 88 8.950E+0!

38 SR- 89 3.530E-03 4 38 SR- 90 1.270E-05 44 RU-103 1.670E-06 'j j

53 I -131 1.160E-02 53 I -132 2.540E-02 53 I -133 4.350E-02 53 I -135 2.460E-02 <

4 54 XE-933 1,290E+02 54 ME-135 4.Ot0E+08 ,

i 54 XE-135 M 8.780E+08 54 XE-137 5.960E+02 54 XE-138 2.38CE+02 55 C5-137 6.020E-05 56 BA-140 5.880E-03

, 57 LA-140 4.120E-03 l

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CP&L GASR7T SEXI-CNNUAL O.tDIOLOGIC L EFFLUENT C.EPORTING RUN O.;TE: C2/tO/22 INPUT SOURCE TERM 5 EUN TIME: 15: 13:C5 BRUNSWICK UNITS I AND 2 GROUND LEVEL CONTINUOUS GASEOUS RELEASES. a987 I H - 3 1.310E+00 24 CR- 51 3.360E-07 25 MN- 54 1.400E-06 27 CO- 60 4.700E-07 36 MR- 87 7.060E-02 36 KR- 88 1.210E+00 38 SR- 89 2.260E-05 38 SR- 90 6.290E-08 53 I -131 3.820E-04 53 I -132 9.560E-04 53 I ~133 2.140E-03 53 1 -135 1.430E-03 54 XE-135 8.500E+01 55 C5-137 2.570E-06 56 OA-140 4.750E-05 57 LA-140 3.690E-05 58 CE-141 4.480E-07 8/3-3

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GA53PT INPUT SOURCE TERMS RUN TIME ' '15:10:45

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., 84UN5MICM UNITS 1 AND 2. MIXED ts00E CONTINUOUS GASEOUS RELEASES. 1987 i H'3 '2.710E+00 24 CR- 51 9.640E-02 25 MN- 54 4.690E-03 26 FE- 59 7.960E-04 27 CO- 58 2.070E-03 27 CO- 60 4.680E-03 38 SR- 89 2.950E-04 38 SR- 90 4.260E-06 53 1 -131 3.810E-02 '

53 1 -132 1.330E+00 53 1 -133 9.740E-01 53 I -134 7.030E-02 53 I -135 1.970E+00 54 XE-133 4.800E+03 54 xE-135 2.020E+04 55 CS-337 6.790E-05 56 BA-140 1.9 TOE-03 57 LA-140 9.330E-03 '

58 CE-141 1.650E-05 AGGREGATE SOURCE TERM I H- 3 6.0600E+00 18 AR- 48 5.4100E+01 24 CR- 58 9.8930E-02 j 25 MM- 54 4.9004E-03

, 26 FE- 59 7.9600E-04 t

27 CO- 58 2.0930E-03 <

! 2 7 CO- 60 4.8795E-03 36 NR- 85 M 7.0600E+05.

36 KR- 87 3.037tt+03 1 36 KR- 88 9.0710E+0!

j 38 SR- 89 3.8476E-03 a 38 SR- 90 1.7023E-05

, 44 RU-103 1.6700E-06 1

53 1 -131 5.0082E-02 1 53 I -132 1.3564E+00 j

53 1 -133 1.0196E+00 53 I -134 7.0300E-02 53 I -135 t.9960E+00 54 XE-133 4.9290E+03 54 XE-135 2.0325E+04 54 XE-135 M 8.7800E+01 54 XE-337 5.9600E+02 54 XE-138 2.3800E+02 55 C5-137 3.3067E-04 56 BA-140 7.8375E-03 5 57 LA-140

5.4869E-03 i 58 CE-141 1.6948E-05 6

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8/3-4

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CP&L SE31-ANNUAL KADIOLOGICAL EFFLUENT REPORTING RUN DATE: 02/10/h8l l

GASAPT RADIATION DOSES AT 1 ELECTED LOCATIONS -RUN TIME: -15:10:45 , -

! sRUNSw!CK UNITS t AND 2 ELEVATED. CONTINUOUS GASEOUS RELEASES, 1987 s PRUNSWICM UNITS 1 AtsD 2. GROUNO LEVEL CONTINUOUS GAGEOUS RELEASES 4 1987 DRUNSNICK UNITS I AND 2. MIXED MODE CONTINUOUS GASEOUS RELEASES. 1987

'SPECIAL LOCATION METERS DIR PL GR IN V CM GM M 440 COW MILM 7644.0 NE O I I i 1 0 0 ANNUAL 8 ETA AIR DOSE

5.453E-02 MILLRAOS j ANNUAL GAMM4 AIR DOSE = 4.tSEE-02 MILLRADS TOTAL 800Y GI-TRACT BONE LIVER KIDNEY THYROID LONG SMIN l ADULT 3.507E-03 1.810E-03 t.922E-03 t.605E-03 t,722E-03 5.639E 1.387E-03 1.548E-03 l

GROUND PLANE 1.290E-03 8.290E-03 1.290E-03 1.290E-03 1.290E-03 1.290E-03 1.290E-03 1.506E-03 INHALATION 2.402E-05 3.802E-05 1.760E-05 4.517E-05 6.650E-05 3.609E-03 6.293E-05 1.245E-05 wSGETATION 1.053E-04 3.827E-04 4.682E 1.137E-04 1.192E-04 1.292E-02 2.462E-05 2.247E-05 Cow WILM 8.750E-05 9.905E-05 1.462E-04 1.560E-04 2.464E-04 3.858E-02 8.915E-06 7.584E-06 YEENAGER I.585E-03 1.852E-03 2.258E-03 1.754E-03 I.933E-03 7.850E-02 1.47 t E 1.554E-03 l

GROUND PLANE 1.290E-03 1.290E-03 8.290E-03 3.290E-03 t.290E-03 1.290E-03 t.290E-03 1.506E-03 INHALATION 2.822E-05 4.357E-05 2.443E-05 5.721E-05 8.624E-05 4.840E-03 8.823E-05 1.253E-05 VEGETATION t.272E-04 3.84tE-04 6.774E-04 1.326E-04 1.203E-04 1.08tE-02 2.945E-05 2.572E-05 Com MILM 1.395E-04 1.336E-04 2.658E-04 2.735E-04 4.3612-04 6.156E-02 1.26tE-05 9.879E-06 CHILD t.806E-03 t.717E-03 3.533E-03 2.016E-03 2.258E-03 1.492E-Ot 1.429E-03 1.572E-03 GROUNO PLANE t.290E-03 1.290E-03 1.290E-03 1.290E-03 1.290E-03 1.290E-03 1.290E-03 1.506E-03 INHALATION 2.979E-05 3.096E-05 3.288E-05 5.387E-05 7.901E-05 6.174E-03 7.356E-05 1.108E-05 VEGETATION 2.294E-04 2.784E-04 1.563E-03 3.956E-04 1.629E-04 1.70tE-02 4.533E-05. 3.984E-05 Cow WILM 2.564E-04 1.170E-04 6.468E-04 4.759E-04 7.260E-04 1.248E-Of t.978E-05 1.56tE-05 INFANT 3.782E-03 1.430E-03 2.606E-03 2.472E-03 2.601E-03 3.102E-Ot 1.373E-03 1.536E-03 GROUNO PLANE t.290E-03 1.290E-03 1.290E-03 1.290E-03 1.290E-03 1.290E-03 1.290E-03 1.506E-03 INHALATION t 935E-05 1.500E-05 2.550E-05 4.59tE-05 5.042E-05 5.698E-03 5.177E-05 S.370E-06 cow WILM 4.724E-04 1.243E-04 4.290E-03 f.136E-03 1.26tE-03 3.033E-Os 3.135E-05 2.368E-05 8/3-6

- - ~ .- - . -

CP&L SETI-ANNUAL GADIOLOGICAL EFFLUENT EEPORTING EUN DATE: C2/09/88 GA5RPT RADIATION DO!ES AT SELECTED LOCATIONS RUN TIME: 15:C3:53.

BRUN5w!Cn UNITS I AND"2 ELEVATED CONTINUOUS EAJEOUS RELEASES. 1987.

BRUN5m!CM UNITS I AND 2 GROUND LEVEL CONTINUOUS Gr3EDUS RELEASES. 1987 BRUNSw!CR UNITS 1 AND 2. MIXED MODE CONTINUOU$ GASEOUS RELEASES, 1987 SPECIAL LOCATION METERS DIR PL GR IN V CM GM M e 3 SITE 800NOARY 1827.0 NE 1 1 1 1 0 0 0 ANNUAL BETA AIR DOSE = 1.487E-Ot MILLRA05 ANNUAL GAMMA AIR DOSE = t.199E-Of MILLRADS TOTAL 800v GI-TRACT 80N2 LIVER KIDNEY THvR010 LUNG SKIN ADULT 9.tS8E-02 9.511E-02 9.575E-02 9.177E-02 9.190E-02 2.653E-01 9.215E-02 2.153E-Of PLUWE 7.363E-02 7.363E-02 7.363E-02 7.363E-02 7.363E-02 7.363E-02 7.511E-02 1.956E-Ot GROUND PLANE t.655E*02 1.655E-02 1.655E-02 1.655E-02 1.655E-02 1.655E-02 1.655E-02 1.929E-02 INHALATION t.507E-04 t.853E-04 4.419E-05 2.033E-04 2.565E-04 9.091E-03 2.420E-04 -1.216E-04 VE GET A T I ON 1.254E-03 4.746E-03 5.535E-03 1.393E-03 1.466E-03 1.658E-Ot 2.470E-04 2.195E-04 TEENAGER 9.185E-02 9.512E-02 9.822E-02 9.203E-02 9.195E-u2 2.411E-01 9.226E-02 2.653E-01 PLOWE 7.363E-02 7.363E-02 7.363E-02 7.363E-02 7.363E-02 7.363E-02 7.2'1E-02 1.956E-01 GROUNO PLANE t.655E-02 s.655E-02 1.655E-02 f.655E-02 1.655E-02 1.655E-02 1.65bi 02 1.929E-02 INHALATION t.617E-04 8.999E-04 6.134E-05 2.340E-04 3.063E-04 1.214E-02 3.037E-U% 1.224E-04 VEGETATION 1.515E-03 4.748E-03 7.987E-03 1.623E-03 1.470E-03 1.388E-Of 2.989E-04 2 %13E-04 CHILD 9.307E-02 9.371E-02 1.087E-01 9.278E-02 9.2430-02 3.241E-Of 9.238E-02 2.154E-01 PtumE 7.363E-02 7.363E-02 7.363E-02 7.363E-02 7.363E-02 7.363E-02 7.511E-02 1.956E-01 GROUNO PLANE 1.655E-02 1.655E-02 1.655E-02 1.655E-02 v.655E-02 t.655E-02 1.655E-02 f.929E-02 INHALATION t.551E-04 1.586E-04 8.254E-05 2.150E-04 2.776E-04 1.542E-02 2.582E-04 1.082E-04 VE GE T8 TON 2.737E-03 3.375E-03 1.840E-02 2.387E-03 1.9755-03 2.185E-Of 4.594E-04 3.893E-04 INFANT 9.027E-02 9.026E-02 9.024E-02 9.0330-02 9.035E-02 1.042E-Of 9.183E-02 2.150E-Of Plume 7.363E-02 7.363E-02 7.363E-02 7.363E-02 7.363E-02 7.363E-02 7.511E-02 1.956E-01 GROUNO PL ANE 1.655E*02 1.655E-02 1.655E-02 1.655E-02 f.655E-02 1.655E-02 1.655E-02 1.929E-02 INHALATION 9.470E-05 8.430E-05 6.392E-05 1.589E-04 1.720E-04 1.400E-02 1.728E-04 6.223E-05 3

8/3-7

CP&L SECI-ANNUAL CADIOLOGICCL EFFLUENT EEPORTING EUN DATT: 02/09/30' G45R27 C.*DISTION DOSES AT SEL7CTED LOCATIONS EUN TIME: 15:D1:1D B4UNSw!CM UNITS 1 AND 2 GRDUND LEVEL CONTINUOUS GASEOUS RELEASES, 1987 BRUNSw!CK UNITS 1 AND 2 MIXED MODE CON 11NUOUS GASEOUS RELEASES. 1987 SRUNSWICK UNITS 1 AND 2. ELEVATED CONTINUOUS GASEOUS RELEASES, 1987 SPECIAL LOCATION METERS DIR PL GR IN V CM GM M C23 RESIDENCE 1609.0 Sw 1 1 1 1 0 0 0 ANNUAL BETA AIR DOSE = 4.415E-02 MILLRADS LNNUAL GAMMA AIR DOSE = 3.404E-02 MILLRADS TOTAL BODY GI-TRACT BONE LIVER KIDNEY THvROID LONG SKIN ADULT 2.746E-02 2.845E-02 2.871E-02 2.750E-02 2.754E-02 7.621E-02 2.764E-02 6.462E-02 PLUME 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.287E-02 5.915E-02 GROUNO PLANE 4.545E-03 4.545E-03 4.545E-03 4.545E-03 4.545E-03 4.545E-03 4.545E-03 5.299E-03 INHALATION 6.923E-05 8.088E-05 1.346E-05 8.381E-05 9.867E-05 2.662E-03 1.006E-04 6.101E-05 VEGETATION 4.087E-04 1.391E-03 1.722E-03 4.380E-04 4.586E-04 4.657E-02 1.180E-04 1.101E-04 TEENAGER 2.754E-02 2.847E-02 2.949E-02 2.758E-02 2.756E-02 6.950E-02 2.768E-02 6.463E-02 PLUME 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.287E-02 5.915E-02 GROUND PLANE 4.545E-03 4.545E-03 4.545E-03 4.545E-03 4.545E-03 4.545E-03 4.545E-03 5.299E-03 INHALATION 7.250E-05 8.516E-05 1.864E-05 9.254E-05 1.128E-04 3.535E-03 1.220E-04 6.140E-05 VEGETATION 4.983E-04 1.401E-03 2.493E-03 5.099E-04 4.671E-04 3.899E-02 1.397E-04 1.261E-04 CHILD 2.792E-02 2.809E-02 3.276E-02 2.782E-02 2.772E-02 9.276E-02 2.774E-02 6.470E-02 PLUME 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2,287E-02 5.915E-02 GROUND PLANE 4.545E-03 4.545E-03 4.545E-03 4.545E-03 4.545E-03 4.545E-03 4.545E-03 5.299E-03 INHALATION 6.747E-05 6.917E-05 2.505E-05 8.414E-05 1.017E-04 4.459E-03 1.050E-04 5.429E-05 VEGETATION 8.767E-04 1.045E-03 5.753E-03 7.550E-04 6.392E-04 6.132E-02 2.154E-04 1.953E-04 INFANT 2.702E-02 2.702E-02 2.700E-02 2.704E-02 2.704E-02 3.102E-02 2.749E-02 6.448E-02 PL UME 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.287E-02 5.915E-02 GROUND PLANE 4.545E-03 4.545E-03 4.545E-03 4.545E-03 4.545E-03 4.545E-03 4.545E-03 5.299E-03 INMALATION 4.036E-05 3.765E-05 1.912E-05 5.825E-05 6.194E-05 4.044E-03 7.047E-05 3.122E-05 8/3-8

CP&L SECI-4NNUAL CADIOLOGICAL EFFLUENT CEPORTING RUN DATE: 02/09/88 GASRPT RAOIATION DOSES AT SELECTED LOCATIONS RUN TIME: .15:01:19 890NSw!CK UNITS 1 AND 2 GROUND LEVEL CONTINUOUS GASEOUS RELEASES. 1987 BRUNSWICE UNITS 1 AND 2. MIXED MODE CONTINUOUS GASEOUS RELEASES. 1987 BRUNSWICK UNITS I AND 2 ELEVATED CONTINUOUS GASEOUS RELEASES, 1987 SPECIAL LOCATION METERS DIR PL GR IN V CM GM M c33 GARDEN **09.0 SW 1 1 1 1 0 0 0 ANNUAL SETA AIR DO! E r 4.415E-02 MILLRAOS ANNUAL GAMMA AIR DO1E = 3.404E-02 MILLRADS TOTAL BODY GI-TRACT BONE LIVER KIDNEY THYROID LONG SKIN ADULT 2.746E-02 2.845E-02 2.871E-02 2.750E-02 2.754E-02 7.621E-02 2.764E-02 6.462E-02 PLUME 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.287E-02 5.915E-02 GROUNO PLANE 4.545E-03 4.545E-03 4.545E-03 4.545E-03 4.545E-03 4.545E-03 4.545E-03 5.299E-03 INHALATION 6.9230-05 8.088E-05 1.346E-05 8.381E-05 9.867E-05 2.662E-03 1.006E-04 6.101E-05 VEGETATION 4.087E-04 1.391E-03 1.722E-03 4.380E-04 4.586E-04 4.657E-02 1.180E-04 1.101E-04 TEENAGER 2.754E-02 2.947E-02 2.949E-02 2.758E-02 2.756E-02 6.950E-02 2.768E-02 6.463E-02 PLUME 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.i43E-02 2.287E-02 5.915E-02 GROUND PLANE 4.545E-03 4.545E-03 4.545E-03 4.545E-03 4.545E-03 4.545E-03 4.545E-03 5.299E-03 INHALATION 7.250E-05 8.516E-05 1.864E-05 9.254E-05 1.128E-04 3.535E-03 1.220E-04 6.140E-05 VEGETATION 4.913E-04 1.401E-03 2.493E-03 5.099E-04 4.671E-04 3.899E-02 1.397E-04 1.261E CHILD 2.792E-02 2.809E-02 3.276E-02 2.782E-02 2.772E-02 9.276E-02 2.774E-02 6.470E-02 PLUME 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.287E-02 5.915E-02 GROUND PLANE 4.545E-03 4.545E-03 4.545E-03 4.545E-03 4.545E-03 4.545E-03 4.545E-03 5.299E-03 INHALATION 6.747E-05 6.917E-05 2.505E-05 8.414E-05 1.017E-04 4.459E-03 1.050E-04 5.429E-05 VEGETATION 8,767E-04 1.045E-03 5.753E-03 7.550E-04 6.392E-04 6.132E-02 2.154E-04 1.953E-04 INFANT 2.702E-02 2.702E-02 2.700E-02 2.704E-02 2.704E-02 3.102E-02 2.749E-02 6.448E-02 PluvE 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.243E-02 2.287E-02 5.915E-02 GROUND PLANE 4.545E-03 4.545E-03 4.545E-03 4.S45E-03 4.545E-03 4.545E-03 4.545E-03 5.299E-03 INHALATION 4.036E-05 3.765E-05 1.912E-05 5.825E-05 6.194E-05 4.044E-03 7.047E-05 3.122E-05 8/3-9 x

CPEL SEOI-ANNUAL RADIOLOGICAL EFFLUENT REPORTING KUM DATE: 02/1C/00 GASRPT RADIATION DOSES AT SELECTED LOCATIONS RUN TIME: 07:52:33 '

DRUN5 NICK UNITS 1 AND 2 ELEVATED CONTINUOUS GASEOUS RELEASES. 1987 BRUNSWICK UNITS I AND 2. GROUND LEVEL CONTINUOUS GASEOUS RELEASES. 1987 BRUNSWICK UNITS 1 AND 2. MIXED MODE CONTINUOUS GASEOUS RELEASES, 1987 SPECIAL LOCATION METERS OIR PL GR IN V CM GM M a 3 SITE BOUNDARY 1927.0 NE O t I 1. 0 0 0 ax:

ANNUAL 8 ETA AIR DOSE = 1.487E-Ot MILLRADS ANNUAL GAMMA AIR DOSE = 1.II9E-Ot MILLRADS-TOTAL 80Dv GI-TRACT SONE LIVER KIDNEY THVROID

bM(, SKIN A DULT t.795E-02 2.148E-02 2.213E-02 1.834E-02 1.827E-02 1.914E-01 9.7032-02 1.963E-02 GROUNO PLAME 1.655E-02 1.655E-02 1.655E-02 1.655E-02 1.655E-02 1.655E-02 1.005E-02 1.929E-02 INHALATION 1.507E-04 1.853E-04 4.419E-05 2.033E-04 2.565E-04 9.091E-03 2.420E-04 1.216E VEGETATION 1.254E-03 4.746E-03 5.535E-03 1.393E-03 1.466E-03 1.658E-01 2.470E-04 2.195E-04 TEENAGER 1.822E-02 2.549E-02 2.459E-02 '.840E-02 1.832E-02 1.675E-01 1.715E-02 1.966E-02 GROUNO PLANE 1.655E-02 1.655E-02 1.655E-02 1.655E-02 f.655E-02 1.655E-02 1.655E-02 1.929E-02 INHALATION 1.6tFE-04 1.999E-04 6.134E-05 2.340E-04 3.063E 1.214E-02 3.037E-04 1.224E-04 VEGETATION 1.515E-03 4.748E-03 7.987E-03 1.623E-03 1.470E-03 t.388E-01 2.989E-04 2.513E-04 CHILD t.944E-02 2.008E-02 3.503E-02 1.915E-02 1.880E-02 2.504E-01 1.726E-02 1.979E-02 f

GRDUNO PLANE 1.655E-02 1.655E-02 1.655E-02 1.655E-02 t.655E-02 1.655E-02 1.655E-02 f.929E-02 INHALATION t.553E-04 1.586E-04 8.254E-05 2.150E-04 2.776E-04 1.542E-02 2.582E-04 1.082E-04 WEGETATION 2.737E-03 3.375E-03 1.840E-02 2.387E-03 1.975E-03 2.185E-Of 4.594E-04 3.893E-04 INFANT 4.664E-02 1.663E-02 1.66tE-02 1.670E-02 8.672E-02 3.055E-02 f.672E-02 1.935E-02 GROUND PLANE 1.655E-02 1.655E-02 1.655E-02 1.655E-02 t.655E-02 1.655E-02 1.655E-02 INHALATION 1.929E-02 9.470E-05 8.430E-05 6.392E-05 1.589E-04 3.720E-04 1.400E-02 1.728E-04 6.223E-05 4

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l Cp&L

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l Caroline Power & Light Company Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461-0429 February 23, 1988 FILE: B09-13510C SERIAL: BSEP/88-0105 U.S. Nuclear Regulatory Commission A*ITN: Document Control Desh Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLAST UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 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, 1987, through December 31, 1987.

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

Very truly yours, ;

Yu C. R. Dietz, General Manager Brunswick Steam Electric Plant MJP/byc Enclosure cc: Dr. J. N. Grace Mr. E. D. Sylvester BSEP NRC Resident Office l

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BSEP-88-0105, Semiannual Radioactive Effluent Rept,Jul-Dec 1987

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BSEP-88-0105, Semiannual Radioactive Effluent Rept,Jul-Dec 1987

Text

meters" for the food and ground plane pathway vy

= N @ N T

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