Text

Radioactive Effluent Release Report for 2002, Enclosure 1 Through Index, Section 5
	ML031260321
Person / Time
Site:	Brunswick
Issue date:	04/28/2003
From:	Noll W; Carolina Power & Light Co
To:	; Office of Nuclear Reactor Regulation
References
	BSEP 03-0003, TS 5.6.3
	Download: ML031260321 (159)
	v • d • e

BSEP 03-003 RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2002 Brunswick Steam Electric Plant Radioactive Effluent Release Report January 1, through December 31, 2002 ATTACHMENTS PAGES

1. Effluent and Waste Disposal Report Supplemental Information 2 - 5

2. Effluent and Waste Disposal Data 6 - 22

3. Environmental Monitoring Program 23 -25

4. Effluent Instrumentation 26 - 29

5. Major Modification to the Radioactive Waste Treatment Systems 30

6. Meteorological Data 31

7. Annual Dose Assessment 32 - 48

8. Off-Site Dose Calculation Manual (ODCM) and Process Control Program (PCP) Revisions 49 - 51 Page 1 of 51

BSEP 03-003 ATTACHMENT 1 EFFLUENT AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION Facility:

Brunswick Steam Electric Plant Licensee:

Carolina Power and Light Company

1. Regulatory Limits A. Fission and activation gases (Off-Site Dose Calculation Manual Specification (ODCMS) 7.3.8)

(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 (ODCMS 7.3.9)

(1) Calendar Quarter*

(a) < 15 mrem to any organ (2) Calendar Year (a) < 30 mrem to any organ (3) Calendar Quarter for Burning Contaminated Oil*

(a) < 0.1 % of limits for calendar quarter of (1)

(b) 436 tiCi (ODCM Appendix H)

(4) Calendar Year for Burning Contaminated Oil (a) < 0.1 % of limits for calendar year (b) 872 tLCi (ODCM Appendix H)

C. Liquid effluents (ODCMS 7.3.4)

(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 ODCM

Used for percent of ODCMS limit determination in Attachment 2, Table IA

- Used for percent of ODCMS limit determination in Attachment 2, Table 2A Page 2 of 51

BSEP 03-003 ATTACHMENT 1 (cont.)

EFFLUENT AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION

2.

Maximum permissible concentration and dose rates which determine maximum instantaneous release rates.

A. Fission and activation gases (ODCMS 7.3.7.a)

(1) < 500 mrem/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 (ODCMS 7.3.7.b)

(1) < 1500 mrem/year to any organ C. Liquid effluents (ODCMS 7.3.3)

The concentration of radioactive material released in liquid effluents to unrestricted areas after dilution in the discharge canal shall be limited to 10 times the concentrations specified in Appendix B, Table 2, Column 2 to 10 CFR 20.1001 -20.2401 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to the value given in the ODCM specifications.

(1) Tritium: limit = 1.00E-03 pCi/ml**

(2) Dissolved and entrained noble gases: limit = 2.OOE-04 riCi/ml**

3. Measurements and Approximations of Total Radioactivity A. Fission and activation gases (1) Analyses for specific radionuclides in representative grab samples by gamma spectroscopy.

B. Iodines (1) Analysis for specific radionuclides collected on charcoal cartridges by gamma spectroscopy.

C. Particulates (1) Analysis for specific radionuclides collected on filter papers by gamma spectroscopy.

D. Particulates for Burning Oil (1) Analysis for specific radionuclides by grab samples of each batch of oil to be burned.

E. Liquid Effluents (1) Analysis for specific radionuclides of individual releases by gamma spectroscopy.

- Used as applicable limits for Attachment 2, Table 2A.

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.

Page 3 of 51

BSEP 03-003 ATTACHMENT 1 (cont.)

EFFLUENT AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION

4.

Batch Releases A. Liquid (1) Number of batch releases:

4.OOE+01 (2) Total time period for batch releases:

4.66E+03 Minutes (3) Maximum time period for a batch release:

2.63E+02 Minutes (4) Average time period for a batch release:

1. 17E+02 Minutes (5) Minimum time period for a batch release:

1.40E+01 Minutes (6) Average stream flow during periods of release of effluent into a flowing stream:

8.27E+05 Gallons per Minute B. Gaseous (1) Number of batch releases:

(2) Total time period for batch releases:

(3) Maximum time period for a batch release:

(4) Average time period for a batch release:

(5) Minimum time period for a batch release:

5.

Abnormal releases*

A. Liquid (1) Number of releases:

(2) Total activity released:

B. Gaseous (1) Number of releases:

(2) Total activity released:

0.OOE+00 0.OOE+00 Minutes 0.OOE+00 Minutes 0.OOE+00 Minutes 0.OOE+00 Minutes O.OOE+00 0.OOE+00 Curies O.OOE+00 O.OOE+00 Curies

There were no abnormal releases that exceeded 10 CFR 20 or 10 CFR 50 limits. See page 5 for a discussion of release events that occurred.

Page 4 of 51

BSEP 03-003 ATTACHMENT 1 (cont.)

EFFLUENT AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION

1. Discussion of Releases from the Storm Drain Collector Basin Due to heavy rains, the Storm Drain Collector Basin (SDCB) was released directly to the discharge canal on September 23, 2002, for approximately 0.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . The SDCB is a permitted release point during periods of inclement weather to protect plant personnel and equipment. Approximately 3.44E+04 gallons containing 1.67E-03 curies of tritium were released during this instance. This resulted in an estimated maximum dose to the individual of 7.15E-10 mrem.

2. Summary SDCB curie totals are included in the quarterly summaries for FISSION AND ACTIVIATION PRODUCTS and TRITIUM on Attachment 2, Table 2A when applicable.

The quantity of rainwater released from the storm drain stabilization pond and/or the SDCB is not included in the average diluted concentration determination or VOLUME OF WASTE RELEASED on Attachment 2, Table 2A.

Page 5 of 51

BSEP 03-003 ATTACHMENT 2 EFFLUENT AND WASTE DISPOSAL DATA Table IA:

Gaseous Effluents - Summation of all Releases Table 1B:

Gaseous Effluents - Elevated Releases Table IC:

Gaseous Effluents - Ground Level Releases Table ID:

Gaseous Effluents - Ground Level Releases for Burning Contaminated Oil Table 2A:

Liquid Effluents - Summation of all Releases Table 2B:

Liquid Effluents - Batch Mode Lower Limits of Detection Table 3A:

Solid Waste and Irradiated Fuel Shipments - Waste Class A Table 3B:

Solid Waste and Irradiated Fuel Shipments - Waste Class B Table 3C:

Solid Waste and Irradiated Fuel Shipments - Waste Class C Combustion of Waste Oil Page 6 of 51

BSEP 03-003 ATTACHMENT 2 (cont.)

EFFLUENT AND WASTE DISPOSAL DATA Table 1A: Gaseous Effluents - Summation of all Releases A. FISSION AND ACTIVATION GASES Unit Quarter 1 Quarter 2

1. Total release Cl 1.68E+02 6.06E+01

2. Average release rate for period iCVsec 2.17E+01 7.70E+00

3. Percent of ODCM limit 6.12E-02 1.26E-02 B. IODINES Unit Quarter 1 Quarter 2

1. Total Iodine-131 release Cl 3.73E-03 1.72E-03

2. Average release rate for period gCi/sec 4.79E-04 2.18E-04 C. PARTICULATES Unit Quarter 1 Quarter 2

1. Total release Ci 1.26E-03 7.19E-04

2. Average release rate for period ptCi/sec 1.61 E-04 9.15E-05

3. Gross Alpha Ci 1.61 E-07 0.OQE+00 D. TRITIUM Unit Quarter 1 Quarter 2

1. Total release Ci 4.68E+01 2.22E+01

2. Average release rate for period ptCi/sec 6.01 E+00 2.82E+00 E. IODINE-131, IODINE-133, TRITIUM AND PARTICULATES Unit Quarter 1 Quarter 2

1. Total release Ci 4.68E+01 2.22E+01

2. Average release rate for period iCi/sec 6.02E+00 2.82E+00

3. Percent of ODCM limit 1.71 E-01 6.32E-02 Quarter 3 8.11 E+01 1.02E+01 1.46E-03 Quarter 3 3.14E-03 3.95E-04 Quarter 3 5.08E-04 6.39E-05 0.OOE+00 Quarter 3 2.75E+01 3.46E+00 Quarter 3 2.76E+01 3.47E+00 1.1 6E-01 Quarter 4 3.13E+01 3.94E+00 6.31 E-03 Quarter 4 1.74E-03 2.19E-04 Quarter 4 4.86E-04 6.11E-05 0.OOE+00 Quarter 4 2.1 OE+01 2.64E+00 Estimated Total Percent Error 4.50E+01 NA NA Estimated Total Percent Error 3.50E+01 NA Estimated Total Percent Error 3.50E+01 NA 3.50E+01 Estimated Total Percent Error 3.OOE+01 NA Quarter 4 2.1 OE+01 2.64E+00 6.44E-02 Page 7 of 51

BSEP 03-003 ATTACHMENT 2 (cont.)

EFFLUENT AND WASTE DISPOSAL DATA Table IA: Gaseous Effluents - Summation of all Releases (cont.)

F. PARTICULATES VIA BURINING CONTAMINATED OIL Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4

1. Total release Ci O.OOE+00 O.OOE+00 O.OQE+00 0.OQE+00

2. Average release rate for period ACi/sec O.OOE+00 0.OOE+00 O.OQE+00 O.OOE+00

3. Percent of ODCM limit O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 8 of 51

BSEP 03-003 ATTACHMENT 2 (cont.)

EFFLUENT AND WASTE DISPOSAL DATA Table IB: Gaseous Effluents - Elevated Releases Continuous Release Nuclides Released

1. FISSION GASES krypton-85m krypton-87 krypton-88 xenon-1 33 xenon-1 33m xenon-1 35 xenon-1 35m xenon-1 37 xenon-1 38 total for period Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Quarter 1 5.15E+00 2.54E+00 3.31 E+00 1.34E+01

< LLD 1.63E+01 2.45E+01 6.75E+00 7.23E+01 1.44E+02 Quarter 2 3.80E+00 2.06E+00 2.02E+00 2.05E+01

< LLD 5.77E+00 8.76E+00

< LLD 1.21 E+01 5.50E+01 Quarter 3 2.26E+00 1.02E+00 1.06E+00 3.27E+01 3.34E-02 5.91 E+00 9.19E+00 1.82E+00 5.50E+00 5.94E+01 Quarter 4

< LLD

< LLD 5.59E+00

< LLD 8.04E+00 9.44E+00

< LLD 7.21 E+00 3.06E+01

2. GASEOUS IODINES iodine-1 31 iodine-132 iodine-1 33 iodine-134 iodine-1 35 total for period Unit Ci Ci Ci Ci Ci Ci Quarter 1 2.76E-03 1.75E-02 1.65E-02 2.49E-02 2.80E-02 8.97E-02 Quarter 2 1.58E-03 7.67E-03 9.86E-03 2.90E-03 1.55E-02 3.75E-02 Quarter 3 2.29E-03 1.12E-02 1.31 E-02 1.26E-02 1.90E-02 5.82E-02 Quarter 4 1.31 E-03 1.34E-02 1.12E-02 2.46E-03 1.99E-02 4.83E-02

3. PARTICULATES chromium-51 manganese-54 cobalt-58 cobalt-60 strontium-89 strontium-90 ruthenium-1 06 cesium-1 37 barium-140 lanthanum-140 total for period Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Quarter 1 4.66E-05 2.89E-05 5.98E-05 1.53E-04 3.19E-05 9.47E-07 3.20E-05 3.81 E-06 1.25E-04 2.13E-04 6.96E-04 Quarter 2

<LLD dLLD

<LLD 6.54E-06 5.00E-05 1.18E-06

<LLD 3.24E-06 1.85E-04 3.48E-04 5.94E-04 Quarter 3

<LLD

<LLD 7.83E-06 2.52E-05 7.36E-07

<LLD

<LLD 1.28E-04 2.41 E-04 4.03E-04 Quarter 4

<LLD

<LLD 1.55E-05 1.71 E-05 1.08E-06

<LLD 1.18E-06 8.28E-05 1.14E-04 2.32E-04

4. TRITIUM Unit Ci Quarter 1 5.64E+00 Quarter 2 Quarter 3 Quarter 4 5.25E+00 1.06E+01 7.83E+00 hydrogen-3 Page 9 of 51

BSEP 03-003 ATTACHMENT 2 (cont.)

EFFLUENT AND WASTE DISPOSAL DATA Table IC: Gaseous Effluents - Ground Level Releases Continuous Release Nuclides Released

1. FISSION GASES xenon-1 33 xenon-1 35 xenon-1 35m total for period Unit Ci Ci Ci Ci Quarter 1

< LLD 1.59E+01 8.50E+00 2.44E+01 Quarter 2 3.57E+00 1.95E+00

< LLD 5.52E+00 Quarter 3 1.83E+01 2.75E+00 6.07E-01 2.16E+01 Quarter 4

< LLD 6.75E-01

2. GASEOUS IODINES iodine-1 31 iodine-1 32 iodine-1 33 iodine-1 34 iodine-1 35 total for period Unit Ci Ci Ci Ci Ci Ci Quarter 1 9.72E-04 8.67E-04 1.79E-03

< LLD 9.77E-04 4.61 E-03 Quarter 2 1.32E-04

< LLD 8.68E-04

< LLD 6.29E-06 1.01 E-03 Quarter 3 8.54E-04

< LLD 5.21 E-04

< LLD

< LLD 1.37E-03 Quarter 4 4.30E-04 9.38E-04 1.01 E-03

< LLD 4.62E-04 2.84E-03

3. PARTICULATES chromium-51 manganese-54 cobalt-58 iron-59 cobalt-60 strontium-89 strontium-90 cesium-1 37 barium-1 40 lanthanum-140 cerium-i41 total for period Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Quarter 1 2.77E-04 2.69E-05 2.75E-05 2.12E-05 1.88E-04 1.24E-05 1.79E-08 2.14E-06 1.06E-06

< LLD 3.95E-06 5.60E-04 Quarter 2 3.30E-05 4.74E-07 4.83E-06

< LLD 8.36E-05 4.54E-07 1.38E-07 3.OOE-06 8.22E-08

< LLD

< LLD 1.26E-04 Quarter 3 2.91 E-05 2.78E-06 2.1 8E-06

< LLD 5.17E-05 2.24E-06 9.50E-08 1.25E-05 4.29E-06

< LLD

< LLD 1.05E-04 Quarter 4

< LLD 2.94E-06 5.44E-05

< LLD 5.52E-05 6.89E-06 6.67E-07

< LLD 5.98E-05 7.39E-05

< LLD 2.54E-04

4. TRITIUM Unit Ci Quarter 1 4.11E+01 Quarter 2 1.69E+01 Quarter 3 1.70E+01 Quarter 4 1.31 E+01 hydrogen-3 Page 10 of 51

BSEP 03-003 ATTACHMENT 2 (cont.)

EFFLUENT AND WASTE DISPOSAL DATA Table ID: Gaseous Effluents - Ground Level Releases For Burning Contaminated Oil Nuclides Released

1. PARTICULATES Unit Ci Quarter 1 O.OOE+OQ Quarter 2 O.OOE+OQ Quarter 3 O.OOE+OO Quarter 4 O.OOE+00 No releases made Page 11 of 51

BSEP 03-003 ATTACHMENT 2 (cont.)

EFFLUENT WASTE AND DISPOSAL DATA Table 2A: Liquid Effluents - Summation of all Releases A. FISSION AND ACTIVATION PRODUCTS (NOTE 1)

Unit

1. Total release Ci (excluding tritium, gases, and alpha)

Quarter 1 Quarter 2 9.59E-04 1.73E-04 Quarter 3 3.97E-04 Quarter 4 2.26E-04 Estimated Total Percent Error 4.OOE+01

2. Average diluted concentration (NOTE 2)

3. Percent of applicable limit AiGVmI 1.75E-1 0 6.73E-1 1 4.30E-1 0 4.01 E-1 1 1.71 E-03 2.01 E-04 5.19E-04 3.06E-04 NA NA B. TRITIUM (NOTE 1)

Unit Quarter 1 Ci 3.58E+00 Quarter 2 9.86E-01 Quarter 3 3.75E-01 Estimated Total Quarter 4 Percent Error 1.48E+00 4.50E+01

1. Total release

2. Average diluted concentration (NOTE 2)

3. Percent of applicable limit liCi/ml 6.55E-07 3.83E-07 4.07E-07 2.62E-07 NA NA 6.55E-02 3.83E-02 4.07E-02 2.62E-02 C. DISSOLVED AND ENTRAINED GASES (NOTE 1)

Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error Cl 1.74E-04 1.97E-05 0.OOE+00 6.58E-05 4.OOE+01

1. Total release

2. Average diluted concentration (NOTE 2)

3. Percent of applicable limit AiCVmI 3.1 BE-1 1 7.66E-12 0.OOE+00 1.1 7E-1 1 NA NA

%1

.59E-05 3.83E-06 0.OOE+00 5.85E-06 D. GROSS ALPHA RADIOACTIVITY Unit Quarter 1 Ci

< LLD Quarter 2

< LLD Quarter 3

< LLD Quarter 4

< LLD Estimated Total Percent Error 4.00E+01

1. Total release NOTE 1: Includes radionuclides released via abnormal and/or non-routine releases NOTE 2: Does not include rainwater (i e. Storm Drain Collection Basin and/or Storm Drain Collection Pond)

Page 12 of 51

BSEP 03-003 ATTACHMENT 2 (cont.)

EFFLUENT AND WASTE DISPOSAL DATA Table 2A: Liquid Effluents - Summation of all Releases (cont.)

E. VOLUME OF WASTE RELEASED (NOTE 2)

Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error liters 7.21 E+05 3.1 OE+05 9.43E+04 7.20E+05 1.50E+01

1. Total volume F. VOLUME OF DILUTION WATER Unit Quarter 1

1. Total volume liters 5.47E+09 (used during release for average diluted concentration)

Quarter 2 2.57E+09 Quarter 3 9.24E+08 Estimated Total Quarter 4 Percent Error 5.62E+09 1.50E+01 G. VOLUME OF COOLING WATER DISCHARGED FROM PLANT Unit Quarter 1 liters 3.48E+1 1 Quarter 2 4.73E+1 1 Quarter 3 5.14E+1 1 Quarter 4 4.62E+1 1 Estimated Total Percent Error 1.50E+01

1. Total volume NOTE 1: Includes radionuclides released via abnormal and/or non-routine releases NOTE 2: Does not include rainwater (i e. Storm Drain Collection Basin and/or Storm Drain Collection Pond)

Page 13 of 51

BSEP 03-003 ATTACHMENT 2 (cont.)

EFFLUENT AND WASTE DISPOSAL DATA Table 2B: Liquid Effluents - Batch Mode Nuclides Released

1. FISSION AND ACTIVATION PRODUCTS Unit iron-55 Ci cobalt-60 Ci strontium-89 Ci strontium-90 Ci yitrium-91 m CI iodine-1 31 Ci iodine-133 Ci iodine-1 35 Ci cesium-1 37 Ci barium-1 40 Ci lanthium-140 Ci total for period Ci Quarter 1 9.24E-05 2.55E-04

< LLD

< LLD 1.38E-05 2.34E-04 2.64E-04 3.52E-05 2.26E-05 2.09E-05 2.12E-05 9.59E-04 Quarter 2 2.76E-05 6.67E-05

< LLD

< LLD 1.16E-05 1.81 E-05

< LLD 3.14E-05

< LLD

< LLD 1.73E-04 Quarter 3 2.20E-04 1.54E-04

< LLD

< LLD 1.78E-06

< LLD

< LLD 2.18E-05

< LLD

< LLD 3.97E-04 Quarter 4 9.80E-05 8.84E-05

< LLD

< LLD 4.72E-06 9.22E-06

< LLD 2.55E-05

< LLD

< LLD 2.26E-04

2.

DISSOLVED AND ENTRAINED GASES Unit xenon-133 Ci xenon-1 35 Ci xenon-1 35m Ci total for period Ci Quarter 1 7.97E-05 7.57E-05 1.82E-05 1.74E-04 Quarter 2 1.07E-05 9.05E-06

< LLD 1.97E-05 Quarter 3

< LLD

< LLD 0.OOE+00 Quarter 4 1.19E-05 5.39E-05

< LLD 6.58E-05 Page 14 of 51

BSEP 03-003 ATTACHMENT 2 (cont.)

EFFLUENT AND WASTE DISPOSAL DATA LOWER LIMITS OF DETECTION Units: gCi/ml

1. LIQUID RELEASES

2. GASEOUS RELEASES Alpha Cr-51 Mn-54 Fe-55 Co-58 Fe-59 Co-60 Zn-65 Sr-89 Sr-90 Y-91m Mo-99 1-131 1-133 1-135 Cs-1 34 Cs-1 37 Ba-1 40 La-140 Ce-141 Ce-144 Kr-87 Kr-88 Xe-133 Xe-1 33m Xe-135 Xe-1 35m Xe-1 38 3.73E-08 1.60E-07 2.05E-08 2.36E-08 1.72E-08 2.52E-08 2.32E-08 7.19E-08 4.59E-08 3.40E-08 2.56E-08 1.26E-07 1.69E-08 2.21 E-08 9.84E-08 2.45E-08 2.59E-08 5.38E-08 4.67E-08 2.51 E-08 9.98E-08 Kr-85m Kr-87 Kr-88 Xe-133 Xe-1 33m Xe-135 Xe-137 Xe-138 4.77E-09 9.18E-09 1.81 E-08 1.29E-08 4.92E-08 3.25E-09 1.20E-06 1.69E-07

3. 10DINES AND PARTICULATES Alpha Cr-51 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Sr-89 Sr-90 Mo-99 Ru-106 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-1 41 Ce-1 44 1.97E-1 5 5.04E-1 3 3.76E-1 4 6.65E-1 4 5.78E-1 4 5.05E-1 4 1.35E-1 3 1.77E-15 1.40E-15 5.74E-1 3 6.59E-13 6.06E-14 7.40E-14 6.02E-1 4 2.53E-13 1.09E-13 8.79E-14 3.58E-13 3.92E-08 6.02E-08 3.58E-08 1.31 E-07 1.58E-08 8.30E-08 1.74E-07 NOTES:

1. The above values represent typical "a priori" LLDs for isotopes where values of "<LLD" are indicated in Tables IA, 1B, IC, 2A, and 2B. Also included are isotopes specified in ODCMS 7.3.3 and 7.3.7.

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 the summary data.

Page 15 of 51

BSEP 03-003 ATTACHMENT 2 (cont.)

EFFLUENT AND WASTE DISPOSAL DATA Table 3A: Solid Waste and Irradiated Fuel Shipments - Waste Class A Waste Class A

1. Total volume shipped (cubic meters) 5.52E+02 Total curie quantity (estimated) 2.43E+00

2.

Tvpe of Waste Estimated Total

%Error Unit Period

a.

Spent resins, filter, sludges meter3 Curies O.OOE+00 O.OOE+00

b.

Dry active waste, compacted/non-compacted meter3 Curies 5.52E+02 2.43E+00 1.00E+01 1.00E+01

c.

Irradiated components

d.

Others (describe) meters3 Curies meters3 Curies O.OOE+00 0.00E+00 O.OOE+00 0.00E+00

3.

Estimate of maior radionuclides composition

a.

N/A

b.

Fe-55 Co-60 Ni-63 Cs-137 Ce-144 3.94E+01 %

5.09E+01 %

3.73E+00 %

1.27E+00 %

4.08E+oo %

c.

N/A

d.

N/A NOTE:

Solid Radioactive Waste listed above was shipped for processing to various waste processing services or directly shipped to a licensed disposal facility.

Page 16 of 51

BSEP 03-003 ATTACHMENT 2 (cont.)

EFFLUENT AND WASTE DISPOSAL DATA Table 3A: Solid Waste and Irradiated Fuel Shipments - Waste Class A (cont.)

4.

Cross reference table, waste stream, form, and container type Stream Form Container Type Type A/Type B No. of shipments

a.

Resin/Filters

b.

Dry active waste Dewatered &

Solidified*

Compacted/

Non-compacted Type A or STP 1.40E+01

c.

Irradiated components

d.

Others (describe)

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

5.

Shipment Disposition

a.

Solid Waste Number of Shipments Mode of Transportation 6.00E+00 Rail 8.00E+00 Highway

b.

Irradiated Fuel Number of Shipments Mode of Transportation 0

N/A Destination Clive, UT.

Oak Ridge, TN.

Destination N/A Page 17 of 51

BSEP 03-003 ATTACHMENT 2 (cont.)

EFFLUENT AND WASTE DISPOSAL DATA Table 3B: Solid Waste and Irradiated Fuel Shipments - Waste Class B Waste Class B

1.

Total volume shipped (cubic meters)

Total curie quantity (estimated)

2.

Type of Waste 4.79E+00 1.71E+01 Estimated Total Period

%Error 4.79E+00 1.00E+01 1.71E+01 1.00E+01 Unit

a.

Spent resins, filter, sludges meter3 Curies

b.

Dry active waste, compacted/non-compacted meter3 Curies

c.

Irradiated components

d.

Others (describe) meters3 Curies meters3 Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

3.

Estimate of maior radionuclides composition

a.

Cr-51 Mn-54 Fe-55 Co-58 Co-60 Ni-63 Cs-134 Cs-137 1.10E+00 %

2.10E+00 %

1.13E+01 %

1.20E+00 %

5.05E+01 %

1.98E+01 %

1.30E+00 %

1.19E+01 %

b.

N/A

c.

N/A

d.

N/A NOTE:

Solid Radioactive Waste was shipped either directly for disposal or to a waste processor for processing and then transported for disposal by the processor Page 18 of 51

BSEP 03-003 ATTACHMENT 2 (cont.)

EFFLUENT AND WASTE DISPOSAL DATA Table 3B: Solid Waste and Irradiated Fuel Shipments - Waste Class B (cont.)

4.

Cross reference table, waste stream, form, and container type Stream Form Container Type No. of shipments Type A/Type B

a.

Resin/Filters Dewatered &

Type B 1.00E+00 Solidified*

Compacted/

Non-compacted

b.

Dry active waste

c.

Irradiated components

d.

Others (describe)

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

5.

Shipment Disposition

a.

Solid Waste Number of Shipments Mode of Transportation 1.001E+00 Highway

b.

Irradiated Fuel Number of Shipments Mode of Transportation 0

N/A Destination Barnwell, SC.

Destination N/A Page 19 of 51

BSEP 03-003 ATTACHMENT 2 (cont.)

EFFLUENT AND WASTE DISPOSAL DATA Table 3C: Solid Waste and Irradiated Fuel Shipments - Waste Class C Waste Class C

1. Total volume shipped (cubic meters)

Total curie quantity (estimated)

2.

Type of Waste 3.71E+00 7.16E+04 Estimated Total Period

%Error 2.83E+00 1.00E+01 2.07E+02 1.00E+01 Unit

a.

Spent resins, filter, sludges meter3 Curies

b.

Dry active waste, compacted/non-compacted

meter, Curies 0.00E+00 0.00E+00

c.

Irradiated components

d.

Others (describe) meters3 Curies meters3 Curies 8.870E-01 7.14E+04 1.00E+01 1.OOE+01 O.OOE+00 0.00E+00

3.

Estimate of major radionuclides composition

a.

Fe-55 Co-60 Ni-63

b.

N/A

c.

Cr-51 Mn-54 Fe-55 Co-60 Ni-63 5.70E+01 %

3.69E+01 %

5.06E+oo %

9.20E-01 %

1.39E+00 %

4.39E+01 %

4.84E+01 %

4.60E+00 %

d.

N/A NOTE:

Solid Radioactive Waste was shipped directly for disposal.

Page 20 of 51

BSEP 03-003 ATTACHMENT 2 (cont.)

EFFLUENT AND WASTE DISPOSAL DATA Table 3C: Solid Waste and Irradiated Fuel Shipments - Waste Class C (cont.)

4.

Cross reference table, waste stream, form, and container type Stream Form Container Type Type AlType B

a.

Resin/Filters Dewatered &

Type B No. of shipments 3.OOE+00 Solidified*

Compacted/

Non-compacted

b.

Dry active waste

c.

Irradiated components Type B

d.

Others (describe)

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

5.

Shipment Disposition

a.

Solid Waste Number of Shipments Mode of Transportation 7.OOE+00 Highway

b.

Irradiated Fuel Number of Shipments Mode of Transportation 1.OE+01 Rail 4.OOE+00 Destination Barnwell, SC.

Destination New Hill, NC.

Page 21 of 51

BSEP 03-003 ATTACHMENT 2 (cont.)

EFFLUENT AND WASTE DISPOSAL DATA COMBUSTION OF WASTE OIL No contaminated waste oil was incinerated during this report period.

Page 22 of 51

BSEP 03-003 ATTACHMENT 3 ENVIRONMENTAL MONITORING PROGRAM : :

Milk and Vegetable Sample Location Land Use Census Page 23 of 51

BSEP 03-003 ATTACHMENT 3 (cont.)

ENVIRONMENTAL MONITORING PROGRAM : Milk and Vegetable Sample Location No milk animals are located in the area evaluated by the last Land Use Census, therefore, no milk sampling locations were available during this time period.

Vegetation sample locations remained unchanged.

Page 24 of 51

BSEP 03-003 ATTACHMENT 3 (cont.)

ENVIRONMENTAL MONITORING PROGRAM : Land Use Census The 2002 Land Use Census did not identify any locations that are reportable in the Radioactive Effluent Release Report for 2002.

The following is a summary of the nearest resident and garden locations identified within five miles of the plant for each of the 16 meteorological sectors. No milk animals were found within five miles of the plant.

Direction NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW N

Residence 0.8 miles None None None 1.5 miles 0.9 miles 1.0 miles 1.1 miles 1.2 miles 1.0 miles 1.2 miles 0.8 miles 0.8 miles 0.9 miles 0.8 miles 0.7 miles Garden 1.2 miles None None None None None None 1.8 miles 1.6 miles 1.5 miles 1.2 miles 0.8 miles 1.0 miles 4.8 miles 4.4 miles 0.9 miles Page 25 of 51

BSEP 03-003 ATTACHMENT 4 EFFLUENT INSTRUMENTATION :

Radioactive Liquid Effluent Monitoring Instrumentation :

Radioactive Gaseous Effluent Monitoring Instrumentation :

Liquid Hold-Up Tank Page 26 of 51

BSEP 03-003 ATTACHMENT 4 (cont.)

EFFLUENT INSTRUMENTATION : Radioactive Liquid Effluent Monitoring Instrumentation No Radioactive Liquid Effluent Monitoring Instruments were inoperable for a period of greater than 30 days.

Page 27 of 51

BSEP 03-003 ATIACHMENT 4 (cont.)

EFFLUENT INSTRUMENTATION : Radioactive Gaseous Effluent Monitoring Instrumentation No Radioactive Gaseous Effluent Monitoring Instruments were inoperable for a period of greater than 30 days.

Page 28 of 51

BSEP 03-003 ATTACHMENT 4 (cont.)

EFFLUENT INSTRUMENTATION : Liquid Hold-Up Tank No Liquid Hold-Up Tank exceeded the 10-Curie limit of ODCMS 7.3.6 during this reporting period.

Page 29 of 51

BSEP 03-003 ATTACHMENT 5 MAJOR MODIFICATION TO THE RADIOACTIVE WASTE TREATMENT SYSTEMS In accordance with ODCMS 7.5.1, major changes to the liquid, gaseous, and solid Radioactive Waste Treatment Systems shall be reported to the NRC as part of the Radioactive Effluent Release Report or as part of the Updated Final Safety Analysis Report (UFSAR) update. Although major modifications to the radioactive waste treatment systems will typically be submitted with the UFSAR in accordance with 10 CFR 50.71(e), a temporary modification that was installed on the Unit 1 Turbine Building ventilation system is described below:

The Unit 1 refueling outage in March 2002 incorporated a temporary modification to the Turbine Building ventilation system that provided a once-through unfiltered pathway to the environment.

Normal building ventilation operates with approximately 200,000 cfm supplied into the building, a recirculation system, and an air filtration effluent pathway designed to exhaust 15,500 cfm.

Brunswick's Turbine Buildings contain both units' secondary equipment and any system breach will communicate between units due to the 70' elevation turbine deck interface and the slight pressure differences between passage doors. The unique feature in Brunswick's Turbine Building pressure boundary is the ventilation system utilized for building cooling. Approximately 90% of the building air recirculates through an air wash system that, coupled with a chiller system, cools and maintains the temperature for equipment protection.

The effect from this recirculated ventilation method is to concentrate any radiological contaminants inside the buildings. The main removal method due to this recirculation system is typically isotopic decay. The aforementioned once-through ventilation system modification resulted in providing, depending on the number of fans operating, a dilution input of 80,000 to 140,000 cfm of outside air to the Unit 1 Turbine Building. The discharge from the once-through modification released about the same volume to maintain the building in a negative pressure condition. Unfortunately, the design of the Turbine Building envelope, as previously mentioned, will lead to communication of air quality between the operating and shutdown units. This design, coupled with the breaching of contaminated systems during repair work on the shutdown unit, resulted in low level iodine and noble gas releases from this once-through pathway. The system operated for approximately 17 days and accounted for 8.48E+13 cc of release volume. The ventilation system was restored to its normal configuration when the temporary modification was removed.

The once-through pathway contributed the following to the 2002 annual source term:

Category Curies Noble Gas 3.34 1-131 2.41 E-04 1-133 1.22E-04 Page 30 of 51

BSEP 03-003 ATTACHMENT 6 METEOROLOGICAL DATA Per Technical Specification 5.6.3 and ODCMS 7.4.2, the annual summary of meteorological data collected over the calendar year has been retained in a file and is available for NRC review upon request.

Page 31 of 51

BSEP 03-003 AITACHMENT 7 ANNUAL DOSE ASSESSMENT : : :

2002 Annual Liquid Dose Assessment 2002 Annual Gaseous Dose Assessment 2002 Dose Assessment Summary Page 32 of 51

BSEP 03-003 ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2002 Annual Liquid Dose Assessment Included are:

Site Specific Data Source Term As Low As Reasonably Achievable Maximum Individual Dose Summary - Total Integrated and Recreation Population Dose Page 33 of 51

BSEP 03-003 ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2002 Annual Liquid Dose Assessment (cont.)

Site Specific Data BSEP UNITS 1 AND 2 LIQUID RELEASES 2002, DISCHARGE = 2.01E+03 CFS SOURCE TERM MULTIPLIER = 1.00E+00 SALTWATER SITE NO RECONCENTRATION MODEL 50-MILE POPULATION = 3.18E+05 FRACTION ---

ADULT=0.71 TEENAGER=0. 11 CHILD=0. 18 DOSE FACTOR LIBRARY CONTAINS 698 ENTRIES Page 34 of 51

BSEP 03-003 ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2002 Annual Liquid Dose Assessment (cont.)

NUCLIDE I

1H 3

l 26FE 55 l

27CO 60 1

39Y 91M I 53I 131 l

53I 133 l

53I 135 l

54XE 133 l

54XE 135 l

54XE 135M I 55CS 137 56BA 140 l

57LA 140 l

TOTAL Source Term l

PERSON-REM DOSE _

__PERSON-REM PER CURIE__

l TOTAL BODY I THYROID I-TOTAL BODY I THYROID RELEASE CI/YR 6.42E+00 4.38E-04 5.64E-04 1.38E-05 2.52E-04 2.91E-04 3.52E-05 1.02E-04 1.39E-04 1.82E-05 1.01E-04 2.09E-05 2.12E-05 1.29E-04 1.52E-04 7.59E-05

1. 08E-10

1. 1OE-06 4.53E-09 9.63E-10

0. OOE+00 0.OOE+00

0. OOE+00 5.56E-05 4.88E-08 9.46E-10 4.13E-04 1.29E-04 2.18E-13 8.56E-06 1.08E-10 6.24E-04 9.09E-07

9. 63E-10 0.OOE+00

0. OOE+00

8. 64E-07 3.60E-10 9.44E-10 7.63E-04

2. 01E-05 3.47E-01 1.35E-01 7.85E-06 4.36E-03

1. 55E-05 2.73E-05 0.OOE+00 0.OOE+00

0. OOE+00 5.49E-01 2.34E-03 4.46E-05

2. 01E-05 4.98E-10 1.52E-02 7.85E-06 2.48E+00 3.12E-03 2.73E-05

0. OOE+00

0. OE+00

0. OOE+00 8.53E-03 1.73E-05 4.45E-05 Page 35 of 51

BSEP 03-003 A1TACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2002 Annual Liquid Dose Assessment (cont.)

As Low As Reasonably Achievable Maximum Individual Dose (Page 1 of 2) 1 AS LOW AS REASONABLY ACHIEVABLE 0

0 A D U L T D O S E S (MREM PER YEAR INTAKE) 0PATHWAY FISH INVERT SHORELINE SWIMMING BOATING TOTAL SKIN 1.02E-05 1.02E-05 BONE

1. 54E-06 2.26E-06 8.71E-06 6.3OE-09 3.15E-09 1.25E-05 DOSE_

LIVER 1.43E-06 1.74E-06 8.71E-06 6.30E-09 3.15E-09 1.19E-05 TOTAL BODY 6.82E-07 6.85E-07 8.71E-06 6.30E-09 3.15E-09 1.01E-OS THYROID 2.17E-06 2.36E-06 8.71E-06

6. 30E-09 3.15E-09 1.33E-05 KIDNEY

3. 06E-07 8.03E-08 8.71E-06 6.30E-09 3.15E-09 9.11E-06 LUNG 7.96E-07 9.20E-07 8.71E-06 6.30E-09

3. 15E-09

1. 04E-05 GI-LLI 1.70E-06 3.17E-06 8.71E-06 6.30E-09 3.15E-09 1.36E-05 0

FISH INVERT SHORELINE SWIMMING BOATING USAGE (KG/YR,HR/YR) 21.0 5.0 500.0 100.0 100.0 DILUTION 30.0 30.0 30.0 30.0 30.0 TIME (HR) 24.00 24.00 0.00 0.00 0.00 SHOREWIDTH FACTOR=0.5 0

0 T E E N D O S E S (MREM PER YEAR INTAKE)

=0PATHWAY FISH INVERT SHORELINE SWIMMING BOATING TOTAL SKIN 1.02E-05 1.02E-05 BONE

1. 61E-06 2.36E-06 8.71E-06 6.30E-09 3.15E-09 1.27E-05 DOSE LIVER 1.46E-06 1.84E-06 8.71E-06 6.30E-09 3.15E-09 1.20E-05 TOTAL BODY 5.96E-07 6.94E-07 8.71E-06 6.3OE-09 3.15E-09 1.OOE-05 THYROID 2.OOE-06 2.21E-06 8.71E-06 6.30E-09 3.15E-09 1.29E-05 KIDNEY 2.54E-07 6.78E-08 8.71E-06 6.3OE-09 3.15E-09 9.04E-06 LUNG 8.66E-07 1.10E-06 8.71E-06 6.30E-09 3.15E-09 1.07E-05 GI-LLI 1.26E-06 2.32E-06 8.71E-06 6.3OE-09 3.15E-09 1.23E-05 0

FISH INVERT SHORELINE SWIMMING BOATING USAGE (KG/YR,HR/YR) 16.0 3.8 500.0 100.0 100.0 DILUTION 30.0 30.0 30.0 30.0 30.0 TIME (HR) 24.00 24.00 0.00 0.00 0.00 SHOREWIDTH FACTOR=0.5 Page 36 of 51

BSEP 03-003 ATITACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2002 Annual Liquid Dose Assessment (cont.)

As Low As Reasonably Achievable Maximum Individual Dose (Page 2 of 2)

*

AS LOW AS REASONABLY ACHIEVABLE * *

0 0

C H I L D D O S E S (MREM PER YEAR INTAKE)

OPATHWAY FISH INVERT SHORELINE SWIMMING BOATING TOTAL SKIN 1.02E-05 1.02E-05 BONE 2.11E-06 3.21E-06 8.71E-06 6.30E-09 3.15E-09 1.40E-05

_____DOSE_

LIVER 1.38E-06 1.85E-06 8.71E-06 6.30E-09 3.15E-09 1.19E-05 TOTAL BODY 6.07E-07 8.44E-07 8.71E-06 6.3OE-09 3.15E-09 1.02E-05 THYROID 2.07E-06 2.40E-06 8.71E-06 6.30E-09 3.15E-09 1.32E-05 KIDNEY 2.13E-07 5.92E-08 8.71E-06 6.30E-09

3. 15E-09 8.99E-06 LUNG 7.48E-07 9.92E-07 8.71E-06 6.3OE-09 3.15E-09 1.05E-05 GI-LLI 5.58E-07 9.17E-07 8.71E-06 6.30E-09 3.15E-09

1. 02E-05 0

FISH INVERT SHORELINE SWIMMING BOATING USAGE (KG/YR,HR/YR) 6.9 1.7 500.0 100.0 100.0 DILUTION 30.0 30.0 30.0 30.0 30.0 TIME (HR) 24.00 24.00 0.00 0.00 0.00 SHOREWIDTH FACTOR=0.5 Page 37 of 51

BSEP 03-003 ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2002 Annual Liquid Dose Assessment (cont.)

Summary - Total Integrated and Recreation Population Dose A NNUUAL RADIOLOGICAL EFFLUENT REPORTING RADIATION DOSES FROM LIQUID EFFLUENTS 1CP&L LADTAP RUN DATE:

04/15/03 RUN TIME:

11:04:06 TOTAL INTEGRATED AND RECREATION POPULATION DOSES FROM LIQUID EFFLUENTS (PERSON-REM)

PATHWAY I

SPORT FISH I

COM FISH I

SPORT INVERT I

COM INVERT I

DRINKING WATER I

SHORELINE I

SWIMMING I

BOATING I

IRRI VEG I

IRRI LEAFY VEG

)

IRRI MILK

)

IRRI MEAT BONE 9.225E-04 5.080E-05 0.OOOE+00 4.575E-05

0. OOOE+00 9.408E-06 1.794E-08 8.499E-09

0. OOOE+00 0.OOOE+00 0.OOOE+00

0. OOOE+00 LIVER 7.995E-04 4.404E-05 0.OOOE+00 3.328E-05 0.OOOE+00 9.408E-06 1.794E-08 8.499E-09 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 TOTAL BODY 3.701E-04 2.039E-05 0.00OE+00 1.341E-05 0.OOOE+00 9.408E-06 1.794E-08 8.499E-09 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 THYROID 7.031E-04 3.145E-05 0.OOOE+00 1.905E-05 0.OOOE+00 9.408E-06 1.794E-08 8.499E-09 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 KIDNEY 1.567E-04 8.607E-06 0.OOOE+00 1.263E-06 0.00OE+00 9.408E-06 1.794E-08 8.499E-09

0. OOOE+00 0.OOOE+00 0.00OE+00 0.00OE+00 LUNG 4.474E-04 2.465E-05 0.OOOE+00 1.793E-05

0. OOOE+00 9.408E-06 1.794E-08 8.499E-09 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 GI-LLI 8.079E-04 4.450E-05 0.OOOE+00 4.861E-05

0. OOOE+00 9.408E-06 1.794E-08 8.499E-09 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 SKIN 0.OOOE+00 0.OOOE+00

0. OOOE+00

0. OOOE+00 1.106E-05 0.OOOE+00 0.00OE+00 0.OOOE+00 0.000E+00 0.OOOE+00

0. OOOE+00 0 ALL PATHWAYS 1.028E-03 8.863E-04 4.134E-04 7.630E-04 1.760E-04 4.994E-04 9.104E-04 1.106E-05 Page 38 of 51

BSEP 03-003 ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2002 Annual Gaseous Dose Assessment Included are:

Source Term for the Three Release Modes and the Site Aggregate Total 50 Mile Integrated Population Dose by Pathways and Organs Hypothetical Maximum Individual Organ Dose Due to Iodine, Particulates, and Tritium for a Cow Milk Pathway at 4.75 Miles Northeast Maximum Site Boundary Dose by Age Group and Organs for All Pathways Estimated Individual Organ Dose Using the 2001 Land Use Census for the Worst Sector and Existing Pathway Maximum Site Boundary Dose Due to Iodine, Particulates, and Tritium for Existing Pathways Page 39 of 51

BSEP 03-003 AYTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2002 Annual Gaseous Dose Assessment (cont.)

Source Term for the Three Release Modes and the Site Aggregate (Page 1 of 2)

GR02YREC GR02YRGC GR02YRMC 1CP&L ANNUAL RADIOLOGICAL EFFLUENT REPORTING RUN DATE:

04/15/03 GASRPT INPUT SOURCE TERMS RUN TIME:

16:44:15 2002 SOURCE TERM (ELEVATED MODE) BSEP UNITS 1&2 1 H -

3 2.928E+01 24 CR-51 4.655E-05 25 MN-54 2.894E-05 27 CO-58 5.980E-05 27 CO-60 1.833E-04 36 KR-85 M 1.120E+01 36 KR-87 5.613E+00 36 KR-88 6.386E+00 38 SR-89 1.243E-04 38 SR-90 3.936E-06 44 RU-106 3.203E-05 53 I -131 7.937E-03 53 I -132 4.977E-02 53 I -133 5.073E-02 53 I -134 4.283E-02 53 I -135 8.239E-02 54 XE-133 7.211E+01 54 XE-133 M 3.344E-02 54 XE-135 3.634E+01 54 XE-135 M 5.185E+01 54 XE-137 8.574E+00 54 XE-138 9.714E+01 55 CS-137 8.233E-06 56 BA-140 5.209E-04 57 LA-140 9.165E-04 SOURCE TERM (GROUND LEVEL) 2002 BSEP UNITS 1 AND 2 1 H -

3 7.202E+01 38 SR-89 1.480E-05 38 SR-90 1.641E-07 53 I -131 8.713E-04 53 I -133 8.477E-04 53 I -135 4.098E-05 54 XE-133 1.525E+01 54 XE-135 1.658E+01 56 BA-140 1.142E-06 58 CE-141 3.947E-06 Page 40 of 51

BSEP 03-003 ATIACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2002 Annual Gaseous Dose Assessment (cont.)

Source Term for the Three Release Modes and the Site Aggregate (Page 2 of 2)

ANNUAL RADIOLOGICAL EFFLUENT REPORTING RUN DATE:

04/15/03 GASRPT INPUT SOURCE TERMS RUN TIME:

16:44:15 BRUNSWICK UNIT 1 AND 2, MIXED MODE CONTINUOUS GASEOUS RELEASES, 2002 1 H -

3 1.613E+01 24 CR-51 3.395E-04 25 MN-54 3.308E-05 27 CO-58 8.889E-05 27 CO-60 3.781E-04 38 SR-89 7.170E-06 38 SR-90 7.536E-07 53 I -131 1.515E-03 53 I -132 1.805E-03 53 I -133 3.341E-03 53 I -135 1.404E-03 54 XE-133 6.574E+00 54 XE-135 4.671E+00 54 XE-135 M 9.105E+00 55 CS-137 1.763E-05 56 BA-140 6.408E-05 57 LA-140 7.392E-05 AGGREGATE SOURCE TERM 1 H -

3 1.1744E+02 24 CR-51 3.8601E-04 25 MN-54 6.2021E-05 27 CO-58 1.4869E-04 27 CO-60 5.6142E-04 36 KR-85 M 1.1203E+01 36 KR-87 5.6130E+00 36 KR-88 6.3860E+00 38 SR-89 1.4624E-04 38 SR-90 4.8539E-06 44 RU-106 3.2030E-05 53 I -131 1.0324E-02 53 I -132 5.1575E-02 53 I -133 5.4920E-02 53 I -134 4.2829E-02 53 I -135 8.3835E-02 54 XE-133 9.3936E+01 54 XE-133 M 3.3440E-02 54 XE-135 5.7591E+01 54 XE-135 M 6.0957E+01 54 XE-137 8.5740E+00 54 XE-138 9.7137E+01 55 CS-137 2.5864E-05 56 BA-140 5.8611E-04 57 LA-140 9.9042E-04 58 CE-141 3.9470E-06 Page 41 of l

BSEP 03-003 ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2002 Annual Gaseous Dose Assessment (cont.)

Total 50 Mile Integrated Population Dose by Pathways and Organs ANNUAL RADIOLOGICAL EFFLUENT REPORTING ALARA ANNUAL INTEGRATED POPULATION DOSE

SUMMARY

(MANREM) 1CP&L GASRPT RUN DATE:

04/15/03 RUN TIME:

16:44:15 2002 SOURCE TERM (ELEVATED MODE) BSEP UNITS 1&2 SOURCE TERM (GROUND LEVEL) 2002 BSEP UNITS 1 AND 2 BRUNSWICK UNIT 1 AND 2, MIXED MODE CONTINUOUS GASEOUS RELEASES, 2002

- TOTAL **

PLUME GROUND PLANE INHALATION VEGETATION COW MILK MEAT & POULTRY TOTAL BODY 5.120E-02 6.385E-03 12.47%

1.518E-03 2.96%

3.773E-02 73.69%

3.582E-03 7.00%

9.011E-05 0.18%

1.897E-03 3.71%

GI-TRACT 5.130E-02 6.385E-03 12.45%

1.518E-03 2.96%

3.775E-02 73.58%

3. 587E-03 6.99%

8.976E-05 0.17%

1. 975E-03 3.85%

BONE 8.031E-03 6.385E-03 79.50%

1.518E-03 18.90%

5. 888E-05 0.73%

6.358E-05 0.79%

1.038E-06 0.01%

4. 713E-06 0.06%

LIVER

5. 123E-02 6.385E-03 12.46%

1.518E-03 2.96%

3. 776E-02 73.71%

3. 580E-03 6.99%

9.053E-05 0.18%

1. 897E-03 3.70%

KIDNEY 5.128E-02 6.385E-03 12.45%

1.518E-03 2.96%

3. 780E-02 73.72%

3.586E-03 6.99%

9.107E-05 0.18%

1.899E-03 3.70%

THYROID 6.721E-02 6.385E-03 9.50%

1.518E-03 2.26%

4.928E-02 73.32%

7.341E-03 10.92%

3.769E-04 0.56%

2.312E-03 3.44%

LUNG

5. 153E-02 6.580E-03 12.77%

1.518E-03 2.95%

3.788E-02 73.52%

3.566E-03 6.92%

8.954E-05 0.17%

1.894E-03 3.68%

SKIN 6.387E-02 1.884E-02 29.49%

1.786E-03 2.80%

3.770E-02 59.03%

3. 565E-03 5.58%

8.953E-05 0.14%

1.894E-03 2.97%

Page 42 of 51

BSEP 03-003 ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2002 Annual Gaseous Dose Assessment (cont.)

Hypothetical Maximum Individual Organ Dose Due to Iodines, Particulates, and Tritium for a Cow Milk Pathway at 4.75 Miles NE 1CP&L GASRPT ANNUAL RADIOLOGICAL EFFLUENT REPORTING RADIATION DOSES AT SELECTED LOCATIONS RUN DATE:

RUN TIME:

04/16/03 17 :12 : 14 2002 SOURCE TERM (ELEVATED MODE) BSEP UNITS 1&2 SOURCE TERM (GROUND LEVEL) 2002 BSEP UNITS 1 AND 2 BRUNSWICK UNIT 1 AND 2, MIXED MODE CONTINUOUS GASEOUS RELEASES, 2002 SPECIAL LOCATION

42 COW MILK METERS DIR PL GR IN V CM GM 7644.0 NE 0 1 1

1 1

0 M

0 ANNUAL BETA AIR DOSE = 8.069E-04 MILLRADS ANNUAL GAMMA AIR DOSE = 6.753E-04 MILLRADS ADULT GROUND PLANE INHALATION VEGETATION COW MILK TOTAL BODY 4.914E-03 1.251E-04 1.396E-03 2.532E-03 8.616E-04 GI-TRACT

4. 924E-03 1.251E-04 1.397E-03 2.545E-03 8.573E-04 BONE 1.866E-04 1.251E-04 1.676E-06 4.346E-05

1. 642E-05 LIVER 4.919E-03 1.251E-04 1.397E-03

2. 527E-03

8. 697E-04 KIDNEY

4. 934E-03 1.251E-04 1.398E-03 2.529E-03

8. 811E-04 THYROID 1.253E-02 1.251E-04 1.737E-03 4.228E-03 6.439E-03 LUNG 4.894E-03 1.251E-04 1.400E-03

2. 519E-03 8.503E-04 SKIN 4.911E-03 1.471E-04 1.395E-03 2.518E-03 8.501E-04 TEENAGER 5.555E-03 5.558E-03 2.131E-04

5. 568E-03 5.590E-03 1.624E-02 5.528E-03 5.542E-03 GROUND PLANE INHALATION VEGETATION COW MILK CHILD GROUND PLANE INHALATION VEGETATION COW MILK INFANT 1.251E-04 1.405E-03

2. 899E-03

1. 126E-03 7.642E-03 1.251E-04 1.243E-03 4.491E-03 1.782E-03 3.555E-03 1.251E-04 1.406E-03

2. 910E-03

1. 117E-03 7.609E-03 1.251E-04 1.243E-03

4. 484E-03

1. 757E-03 3.501E-03 1.251E-04 2.188E-06

5. 656E-05 2.928E-05

3. 067E-04 1.251E-04 2.729E-06

1. 092E-04 6.969E-05

2. 652E-04 1.251E-04 1.407E-03

2. 894E-03 1.142E-03

7. 661E-03 1.251E-04 1.244E-03 4.481E-03 1.810E-03

3. 641E-03 1.251E-04

1. 408E-03

2. 894E-03 1.163E-03

7. 692E-03 1.251E-04 1.246E-03 4.480E-03 1.842E-03 3.656E-03 1.251E-04

1. 841E-03 4.305E-03 9.966E-03 2.788E-02 1.251E-04 1.761E-03

6. 640E-03 1.935E-02

4. 675E-02

1. 251E-04

1. 411E-03 2.884E-03

1. 108E-03

7. 589E-03 1.251E-04 1.247E-03 4.467E-03 1.750E-03 3.499E-03 1.471E-04 1.404E-03 2.883E-03

1. 107E-03

7. 604E-03 1.471E-04 1.242E-03 4.466E-03 1.750E-03 3.516E-03 GROUND PLANE INHALATION COW MILK 1.251E-04 7.148E-04 2.715E-03 1.251E-04 7.144E-04

2. 662E-03

1. 251E-04 1.931E-06 1.382E-04 1.251E-04

7. 162E-04

2. 800E-03 Page 43 of 51 1.251E-04 7.166E-04 2.814E-03 1.251E-04

1. 189E-03 4.544E-02 1.251E-04 7.182E-04

2. 656E-03 1.471E-04 7.140E-04 2.654E-03

BSEP 03-003 ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2002 Annual Gaseous Dose Assessment (cont.)

Maximum Site Boundary Dose by Age Group and Organs for All Pathways (Page 1 of 2) 1CP&L GASRPT ANNUAL RADIOLOGICAL EFFLUENT REPORTING RADIATION DOSES AT SELECTED LOCATIONS RUN DATE:

RUN TIME:

04/15/03 16:44:15 2002 SOURCE TERM (ELEVATED MODE) BSEP UNITS 1&2 SOURCE TERM (GROUND LEVEL) 2002 BSEP UNITS 1 AND 2 BRUNSWICK UNIT 1 AND 2, MIXED MODE CONTINUOUS GASEOUS RELEASES, 2002 SPECIAL LOCATION

3 SITE BOUNDARY METERS DIR PL GR IN V CM GM 1127.0 NE 1

1 1 1 1

1 M

1 ANNUAL BETA AIR DOSE = 1.739E-02 MILLRADS ANNUAL GAMMA AIR DOSE = 1.222E-02 MILLRADS TOTAL BODY 1.483E-01 GI-TRACT 1.485E-01 BONE 1.047E-02 LIVER KIDNEY 1.486E-01 1.490E-01 THYROID 3.782E-01 LUNG 1.479E-01 SKIN 1.604E-01 ADULT PLUME GROUND PLANE INHALATION VEGETATION COW MILK GOAT MILK MEAT & POULTRY 7.945E-03 1.275E-03

2. 818E-02

5. 102E-02 1.734E-02 3.525E-02 7.322E-03 7.945E-03 1.275E-03

2. 818E-02 5.114E-02 1.727E-02 3.513E-02 7.596E-03 7.945E-03 1.275E-03 1.635E-05 6.067E-04 2.502E-04 3.605E-04 1.874E-05

7. 945E-03 1.275E-03 2.819E-02 5.097E-02 1.746E-02

3. 541E-02 7.321E-03 7.945E-03 1.275E-03 2.820E-02

5. 101E-02 1.765E-02

3. 561E-02 7.329E-03 7.945E-03 1.275E-03 3.208E-02 7.801E-02

1. 067E-01 1.425E-01 9.696E-03 8.120E-03 1.275E-03 2.819E-02 5.086E-02 1.717E-02 3.502E-02 7.309E-03

2. 042E-02 1.500E-03 2.817E-02 5.085E-02 1.717E-02 3.502E-02 7.309E-03 TEENAGER 1.690E-01 1.689E-01 1.114E-02 1.695E-01 1.703E-01

5. 094E-01

1. 683E-01 1.808E-01 PLUME GROUND PLANE INHALATION VEGETATION COW MILK GOAT MILK MEAT & POULTRY 7.945E-03 1.275E-03 2.836E-02

5. 842E-02 2.264E-02 4.598E-02 4.370E-03 7.945E-03 1.275E-03 2.836E-02

5. 852E-02 2.250E-02 4.576E-02 4.535E-03 7.945E-03 1.275E-03 2.138E-05 7.971E-04 4.478E-04 6.412E-04 1.493E-05

7. 945E-03 1.275E-03 2.837E-02 5.836E-02 2.289E-02 4.631E-02 4.370E-03

7. 945E-03 1.275E-03 2.839E-02 5.838E-02 2.323E-02 4.668E-02 4.377E-03

7. 945E-03 1.275E-03 3.325E-02 8.078E-02 1.642E-01 2.158E-01 6.089E-03 8.120E-03 1.275E-03 2.838E-02

5. 823E-02 2.236E-02

4. 563E-02 4.360E-03 2.042E-02 1.500E-03 2.835E-02 5.822E-02 2.236E-02 4.561E-02 4.360E-03 Page 44 of 51

BSEP 03-003 ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2002 Annual Gaseous Dose Assessment (cont.)

Maximum Site Boundary Dose by Age Group and Organs for All Pathways (Page 2 of 2) 1CP&L GASRPT ANNUAL RADIOLOGICAL EFFLUENT REPORTING RADIATION DOSES AT SELECTED LOCATIONS RUN DATE:

RUN TIME:

04/15/03 16:44:15 2002 SOURCE TERM (ELEVATED MODE) BSEP UNITS 1&2 SOURCE TERM (GROUND LEVEL) 2002 BSEP UNITS 1 AND 2 BRUNSWICK UNIT 1 AND 2, MIXED MODE CONTINUOUS GASEOUS RELEASES, 2002 SPECIAL LOCATION

3 SITE BOUNDARY METERS DIR PL GR IN V CM GM 1127.0 NE 1

1 1 1 1 1 M

1 CHILD PLUME GROUND PLANE INHALATION VEGETATION COW MILK GOAT MILK MEAT & POULTRY TOTAL BODY 2.386E-01 7.945E-03 1.275E-03 2.508E-02 9.050E-02 3.584E-02 7.270E-02 5.281E-03 GI-TRACT 2.377E-01 7.945E-03 1.275E-03 2.508E-02 9.038E-02 3.544E-02 7.219E-02 5.371E-03 BONE 1.344E-02 7.945E-03 1.275E-03

2. 671E-05 1.573E-03 1.070E-03 1.521E-03 2.641E-05 LIVER 2.395E-01 7.945E-03 1.275E-03 2.509E-02

9. 037E-02 3.625E-02 7.328E-02 5.279E-03 KIDNEY 2.406E-01 7.945E-03 1.275E-03 2.510E-02 9.038E-02

3. 677E-02 7.384E-02 5.288E-03 THYROID 8.987E-01 7.945E-03 1.275E-03 3.071E-02 1.246E-01 3.167E-01 4.097E-01 7.877E-03 LUNG 2.374E-01 8.120E-03 1.275E-03

2. 509E-02

9. 019E-02

3. 533E-02 7.209E-02 5.267E-03 SKIN 2.498E-01

2. 042E-02 1.500E-03

2. 507E-02

9. 018E-02 3.533E-02 7.207E-02 5.267E-03 INFANT 1.887E-01 1.868E-01 1.434E-02

1. 917E-01

1. 922E-01 1.696E+00

1. 868E-01 1.993E-01 PLUME GROUND PLANE INHALATION COW MILK GOAT MILK 7.945E-03 1.275E-03 1.442E-02 5.455E-02

1. 105E-01 7.945E-03 1.275E-03 1.442E-02 5.371E-02

1. 095E-01 7.945E-03 1.275E-03 1.878E-05

2. 144E-03 2.960E-03

7. 945E-03 1.275E-03 1.444E-02 5.584E-02 1.122E-01 7.945E-03 1.275E-03 1.444E-02 5.611E-02 1.124E-01

7. 945E-03 1.275E-03

1. 957E-02 7.373E-01 9.298E-01 8.120E-03 1.275E-03 1.443E-02 5.361E-02 1.094E-01

2. 042E-02 1.500E-03 1.442E-02 5.360E-02 1.093E-01 Page 45 of 51

BSEP 03-003 AT¶IACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2002 Annual Gaseous Dose Assessment (cont.)

Estimated Individual Organ Dose Using the 2002 Land Use Census for the Worst Sector and Existing Pathway 1CP&L ANNUAL RADIOLOGICAL EFFLUENT REPORTING RUN DATE:

04/15/03 GASRPT RADIATION DOSES AT SELECTED LOCATIONS RUN TIME:

16:44:15 2002 SOURCE TERM (ELEVATED MODE) BSEP UNITS 1&2 SOURCE TERM (GROUND LEVEL) 2002 BSEP UNITS 1 AND 2 BRUNSWICK UNIT 1 AND 2, MIXED MODE CONTINUOUS GASEOUS RELEASES, 2002 SPECIAL LOCATION METERS DIR PL GR IN V CM GM M

21 RESIDENCE 1609.0 SSE 1

1 1 0

0 0

0 ANNUAL BETA AIR DOSE = 3.530E-02 MILLRADS ANNUAL GAMMA AIR DOSE = 2.290E-02 MILLRADS ADULT PLUME GROUND PLANE INHALATION TEENAGER PLUME GROUND PLANE INHALATION CHILD PLUME GROUND PLANE INHALATION INFANT PLUME GROUND PLANE INHALATION TOTAL BODY 7.915E-02 1.483E-02 2.720E-04 6.405E-02 7.956E-02 1.483E-02 2.720E-04 6.446E-02 7.211E-02 1.483E-02 2.720E-04 5.701E-02 4.788E-02 1.483E-02 2.720E-04 3.278E-02 GI-TRACT 7.915E-02

1. 483E-02 2.720E-04 6.405E-02 7.956E-02 1.483E-02 2.720E-04 6.446E-02 7.209E-02 1.483E-02 2.720E-04

5. 699E-02 4.787E-02 1.483E-02 2.720E-04 3.277E-02 BONE 1.513E-02 LIVER KIDNEY 7.917E-02 7.919E-02 1.483E-02 1.483E-02 2.720E-04 2.720E-04 3.255E-05 6.407E-02 1.514E-02 7.958E-02 1.483E-02 1.483E-02 2.720E-04 2.720E-04 4.258E-05 6.448E-02 1.515E-02 7.213E-02 1.483E-02 1.483E-02 2.720E-04 2.720E-04 5.320E-05 5.702E-02 1.514E-02 4.791E-02 1.483E-02 1.483E-02 2.720E-04 2.720E-04 3.734E-05 3.280E-02 1.483E-02 2.720E-04 6.409E-02 7.961E-02 1.483E-02 2.720E-04 6.451E-02 7.215E-02 1.483E-02 2.720E-04 5.705E-02 4.791E-02 1.483E-02 2.720E-04 3.281E-02 THYROID 8.719E-02 1.483E-02 2.720E-04 7.209E-02 8.959E-02 1.483E-02 2.720E-04 7.449E-02 8.357E-02 1.483E-02 2.720E-04 6.847E-02 5.838E-02 1.483E-02 2.720E-04 4.328E-02 LUNG

7. 951E-02

1. 518E-02 2.720E-04

6. 405E-02

7. 993E-02 1.518E-02 2.720E-04

6. 447E-02 7.247E-02 1.518E-02 2.720E-04 5.701E-02 4.825E-02 1.518E-02 2.720E-04

3. 279E-02 SKIN

1. 037E-01 3.934E-02 3.201E-04 6.404E-02

1. 041E-01 3.934E-02 3.201E-04 6.444E-02

9. 664E-02 3.934E-02 3.201E-04 5.698E-02 7.242E-02 3.934E-02 3.201E-04 3.277E-02 Page 46 of 51

BSEP 03-003 ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2002 Annual Gaseous Dose Assessment (cont.)

Maximum Site Boundary Dose Due to Iodines, Particulates, and Tritium for Existing Pathways 1CP&L GASRPT ANNUAL RADIOLOGICAL EFFLUENT REPORTING RADIATION DOSES AT SELECTED LOCATIONS RUN DATE:

04/16/03 RUN TIME:

17:12:14 2002 SOURCE TERM (ELEVATED MODE) BSEP UNITS 1&2 SOURCE TERM (GROUND LEVEL) 2002 BSEP UNITS 1 AND 2 BRUNSWICK UNIT 1 AND 2, MIXED MODE CONTINUOUS GASEOUS SPECIAL LOCATION METERS DIR PL GR IN V CM GM

8 SITE BOUNDARY 1127.0 SSE 0

1 1 0

0 0

ANNUAL BETA AIR DOSE = 6.859E-02 MILLRADS ANNUAL GAMMA AIR DOSE = 4.449E-02 MILLRADS RELEASES, 2002 M

0 ADULT GROUND PLANE INHALATION TEENAGER GROUND PLANE INHALATION CHILD GROUND PLANE INHALATION INFANT GROUND PLANE INHALATION TOTAL BODY 1.206E-01 3.467E-04 1.203E-01 1.214E-01 3.467E-04 1.210E-01 1.074E-01 3.467E-04 1.070E-01 6.191E-02 3.467E-04 6.156E-02 GI-TRACT 1.206E-01 3.467E-04 1.203E-01 1.214E-01 3.467E-04 1.210E-01 1.074E-01 3.467E-04 1.070E-01 6.189E-02 3.467E-04 6.154E-02 BONE

4. 082E-04 3.467E-04 6.148E-05 4.271E-04 3.467E-04

8. 041E-05 4.471E-04 3.467E-04 1.004E-04 4.171E-04 3.467E-04 7.046E-05 LIVER 1.207E-01 3.467E-04 1.203E-01 1.214E-01 3.467E-04 1.211E-01 1.074E-01 3.467E-04 1.071E-01 6.195E-02 3.467E-04 6.160E-02 KIDNEY 1.207E-01 3.467E-04 1.203E-01 1.215E-01 3.467E-04 1.211E-01 1.075E-01 3.467E-04

1. 071E-01

6. 196E-02 3.467E-04 6.161E-02 THYROID 1.358E-01 3.467E-04 1.355E-01 1.403E-01 3.467E-04 1.400E-01 1.290E-01 3.467E-04 1.287E-01 8.174E-02 3.467E-04 8.139E-02 LUNG 1.206E-01 3.467E-04 1.203E-01 1.214E-01 3.467E-04 1.211E-01 1.074E-01 3.467E-04

1. 071E-01 6.192E-02 3.467E-04

6. 158E-02 SKIN 1.207E-01 4.081E-04 1.203E-01 1.214E-01 4.081E-04 1.210E-01 1.074E-01 4.081E-04 1.070E-01 6.194E-02 4.081E-04

6. 153E-02 Page 47 of5l

BSEP 03-003 ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2002 Dose Assessment Summary I.

Liquid Effluents:

Maximum Dose to Individual: (mrem)

Limit: (mrem)

Child - Bone 1.40E-05 2.OOE+01 Child - Total Body 1.02E-05 6.OOE+00 Total Integrated and Recreation Population Dose: (person-rem)

Total Body 4.13E-04 II. Gaseous Effluents Noble Gas Air Dose at Site Boundary: (mrad)

Limit: (mrad)

Gamma 4.45E-02 2.OOE+01 Beta 6.86E-02 4.OOE+01 Iodine-131, Iodine-133, Tritium and Particulates: (mrem)

Maximum hypothetical dose at site boundary for all pathways (infant thyroid):

1.70E+00 Maximum hypothetical dose due to iodines, particulates, and tritium at 4.75 miles for the cow milk pathway per ODCM (infant thyroid): 6.22E-02 Estimated organ dose due to iodines, particulates, and tritium for existing pathways to maximum exposed individual (teenager thyroid):

8.96E-02 Total 50 Mile Annual Integrated Population Dose: (person-rem)

Thyroid:

6.72E-02 Total Body:

5.12E-02 Limit: 3.00E+01 Page 48 of 51

BSEP 03-003 ATTACHMENT 8 OFF-SITE DOSE CALCULATION MANUAL (ODCM) AND PROCESS CONTROL PROGRAM (PCP) REVISIONS The PCP was not revised during the report period. ODCM Revision 26 was effective on 8/19/02.

An analysis of the fourteen major changes is as follows:

ODCM Analysis:

Item

1. Updated the List of Effective Pages for Revision 26.

The list of effective pages and revision bars denotes the method the ODCM utilizes to track changes and to meet the intent for administrative controls in Technical Specifications 5.5.1.

2. Enhanced the ODCM introduction section to reference that the annual dose assessment will be performed utilizing the methodology of the ODCM. Appendix H reference to NRC approved computer codes was included in this enhancement.

A Progress Energy Nuclear Generation Group peer group initiative prompted an evaluation of the annual dose assessment methodology. The evaluation led to deleting the requirements for utilizing LADTAP and GASPARS computer codes for assessing integrated population dose and dose to each pathway. The existing site effluent management software will now be used for the annual assessment. The site program utilizes the ODCM methodology to calculate dose to the maximum exposed individual for liquid and gaseous discharges. Based on the fact that 10CFR50.36a, Technical specifications on effluents from nuclear power reactors, criteria for estimating the maximum potential radiation doses to the public resulting from effluent releases is met utilizing the site software, there is no need to perform integrated population dose calculations. The aforementioned LADTAP and GASPARS computer codes will still be available for evaluation of an on-demand event. Additionally, worst-case receptors are verified by the annual Land Use Census and substantiated using the ODCM methodology.

3. Added the Low-Level Warehouse as a release point in the ODCM methodology.

4. Added the Low-Level Warehouse to the gaseous radwaste effluent system figure.

Enhanced site solid radioactive waste processing capabilities led to establishing effluent monitoring at the Low-Level Warehouse facility. A continuous particulate sampler, with local alarming function, has been installed on the effluent of the ventilation system and will be in service during all facility venting operations. The effluent from this facility will be included in the ground level release criteria of the ODCM. The facility has HEPA filters on the exhaust of the ventilation system and preliminary sample results indicate that all effluent data is below the lower limit of detection.

Page 49 of 51

BSEP 03-003 ATTACHMENT 8 (cont.)

OFF-SITE DOSE CALCULATION MANUAL (ODCM) AND PROCESS CONTROL PROGRAM (PCP) REVISIONS

5. Updated Table 3.2-2 to reflect the 2002 Land Use and Garden Census.

The Land Use and Garden Census information is included in the Off-Site Dose Calculation Manual (ODCM) to aid in evaluating worst sector receptor environmental sampling requirements.

The census is required to be conducted annually to determine the location of the nearest resident, garden, and milk or beef animal in each of the 16 meteorological sectors surrounding the plant.

The resident portion of the census conducted in June of 2002 identified no changes in the distance of the nearest residents for all 16 sectors. The garden portion of the census identified changes in the distances of the nearest garden in 4 sectors, with 3 in the less conservative direction. All changes have been evaluated with no changes required in current sampling locations. The changes requiring evaluation were in the S, SW, and W sectors. Each change was evaluated against the criteria in ODCMS 7.3.16. The results conclude that the changes have a calculated dose less that than the values calculated by ODCMS TR 7.3.9.1 and are < 120% from the current sample locations identified in ODCMS Table 7.3.15-1. The evaluations were performed using 2001 annual source term. No milk animals were identified. The ODCM is being updated to reflect these new locations.

6. Revised section 4.0, Radiological Environmental Monitoring Program, to reference Figure F-2. Duplicate Figure 4.0-lb was deleted.

7. Enhanced Table 4.0-1, note (b), to specify the appropriate criteria for performing gamma isotopic analysis on environmental air particulate samples.

8. Enhanced sampling criteria for environmental fish and invertebrates to clarify the number of control samples needed.

9. Adjusted Co-58 limits for the level of radioactivity in environmental samples to reflect the standard branch technical position.

10. Enhanced LLD criteria for 1-131 to denote options when no drinking water pathway is present.

Section 4.0, Radiological Environmental Monitoring Program, was revised to include comments and suggestions following an E&C radiological environmental assessment. The changes include deleting a duplicate figure indicating gaseous effluent release streams (see Figure F-2), specifying the appropriate criteria for the number of control samples for fish and invertebrates, clarifying the criteria for air particulate sampling gamma isotopic requirements, and adding enhancements to detection limits for Co-58 and I-131 that correspond to the Branch Technical Position for Radiological Effluent Technical Specifications.

Page 50 of 51

BSEP 03-003 ATTACHMENT 8 (cont.)

OFF-SITE DOSE CALCULATION MANUAL (ODCM) AND PROCESS CONTROL PROGRAM (PCP) REVISIONS

11. Revised section 5.0, Interlaboratory Comparison Studies, to reference the criteria established in the NRC Inspection Manual (Procedure 84750).

The Harris E&EC laboratory performs the environmental sample analysis for Brunswick. AR 50067 denoted the laboratory's challenges with the previous three-sigma criteria for acceptability due to the lack of participants in the current program to provide good statistical analysis. Since the end of the EPA Crosscheck program, the nuclear utilities have participated in a variety of equivalent programs. However, the number of participants in a particular program typically is not sufficient to provide good statistical sampling. The HE&EC participates in the Analytics Crosscheck Program that fails to provide the required number of participants. Due to this limitation, an NGG peer group concluded that the most appropriate acceptance criteria for a small population would be the NRC Inspection Manual method. All NGG nuclear facilities will be adopting this methodology in future ODCM revisions.

12. Updated the definition for Rated Thermal Power (RTP) to reflect the Unit 1 power uprate.

Section 7.0, Definitions, was updated to reflect the up-rated MWt for Unit 1. Unit 2 value remained the same.

13. Deleted test requirements note related to "High - voltage low" for circuit failure channel functional testing.

Testing requirements (TR) in Section 7.0 for gaseous and liquid instruments included the term "High - voltage low" in parentheses next to the circuit failure test. It is apparent that this criterion was related to a qualifying term for power supply for antiquated instruments. Instruments and Controls (I&C) and engineering stated that the "High - voltage low" testing of the currently installed instruments results in duplication of other test requirements and is an invasive test not needed to meet the channel functional test. Additionally, this "High - voltage low" criteria is not part of the description for channel functional test in the Branch Technical Position for Radiological Effluent Technical Specifications or any of the ODCM's of the NGG fleet. Based on this evidence, the note was removed.

14. Corrected typographical errors on Figure F-i and F-2.

Changed MED LOW PURITY LIQUID WASTES for the Floor Drain Collection Tank on Figure F-1 to MED/ LOW PURITY LIQUID WASTES. Corrected the 1-8 min delay annotation to 1.8 min delay on Figure F-2 for the associated holdup line for gaseous radwaste effluent systems.

Page 51 of 51

BSEP 03-003 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 OFFS1TE DOSE CALCULATION MANUAL REVISION 26

BRUNSWICK STEAM ELECTRIC PLANT OFF-SITE DOSE CALCULATION MANUAL (ODCM)

REVISION 26 DOCKET NOS. 50-324 50-325 CAROLINA POWER & LIGHT COMPANY

,e- /Dt

\\

.2 Effective Date Approved By:

l LIST OF EFFECTIVE PAGES ODCM NOTE:

FOR ELECTRONIC USERS, revision levels as shown on this page are correct; footers that show Rev. 26 that are not reflected on this page are there due to l

limitations associated with the Word format in the electronic version.

Page~s ii - xi 1-1 2-1 15 3 3-23 3-24 3 3-30 3-31 3 3-66 4 4-2 4 4-4 4 4-8 4 4-10 4-11 deleted - see F-3 5-1 5 5-3 6 6-4 7-0 7-i iv 7.1.1 7.1.1-2 7.1.1-3 7.1.1 7.1.1-5 7.1.2 7.1.2-3 7.1.3 7.1.3-12 7.1.4 7.1.4-5 7.2.0-1 7.3.0 7.3.0-4 7.3.1 7.3.1-4 7.3.1-5 7.3.1 7.3.1-7 7.3.2 7.3.2-6 7.3.2-7 7.3.2 7.3.2-11 7.3.2-12 7.3.3 7.3.3-8 7.3.4 7.3.4-2 7.3.5 7.3.5-2 7.3.6 7.3.6-2 7.3.7-1 7.3.7-2 7.3.7 7.3.7-5 7.3.8 7.3.8-2 7.3.9 7.3.9-2 7.3.10-1 Revision 26 25 26 25 25 26 25 26 25 25 26 25 26 25 26 25 25 25 25 26 25 25 25 25 25 25 25 26 25 25 26 25 26 25 25 25 25 25 26 25 25 25 25 Pagegs) 7.3.11 7.3.11-2 7.3.12-1 7.3.13-1 7.3.14 7.3.14-3 7.3.15 7.3.15-6 7.3.15-7 -7.3.15-8 7.3.15 7.3.15-10 7.3.15-11 7.3.15 7.3.15-13 7.3.15-14 7.3.16 7.3.16-4 7.3.17-1 7.4.0 7.4.0-3 7.5.0-1 B 7.3.0 B 7.3.0-10 B 7.3.1-1 B 7.3.2 B 7.3.2-2 B 7.3.3-1 B 7.3.4-1 B 7.3.5-1 B 7.3.6-1 B 7.3.7-1 B 7.3.8-1 B 7.3.9-1 B 7.3.10-1 B 7.3.11-1 B 7.3.12-1 B 7.3.13-1 B 7.3.14-1 B 7.3.15-1 B 7.3.16-1 B 7.3.17-1 A A-28 B B-36 c C-16 D-A E E-3 F-1 F F-3 G-1 H H-3 H-4 H-5 Revision 25 25 25 25 25 26 25 26 25 26 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 26 25 25 26 25 ODCM (BSEP) i Rev. 26

TABLE OF CONTENTS Title Section Page SECTION 1 INTRODUCTION INTRODUCTION.....................

1-1 SECTION 2 LIQUID EFFLUENTS INDEX TO SECTION 2................

2-1 2.1 COMPLIANCE WITH 10CFR PART 20 (LIQUIDS).2-3 2.2 COMPLIANCE WITH 10CFR PART 50 (LIQUIDS).2-11 SECTION 3 GASEOUS EFFLUENTS INDEX TO SECTION 3...3-................,,.,,.,.,

3-1 3.1 MONITOR ALARM SETPOINT DETERMINATION.................................................. 3-4 3.2 COMPLIANCE WITH 10CFR20 (GASEOUS)................................................,.,.3-17 3.3 COMPLIANCE WITH 10CFR50 (GASEOUS)................................................,.,.,.3-35 SECTION 4 RADIOLOGICAL ENVIRONMENTAL PROGRAM INDEX TO SECTION 4...............

4-1 SECTION 5 INTERLABORATORY COMPARISON STUDIES INDEX TO SECTION 5.......................

5-1 5.1 OBJECTIVE.......................

5-2 5.2 PROGRAM.......................

5-2 SECTION 6 TOTAL DOSE (40CFR190) COMPLIANCE INDEX TO SECTION 6....................

6-1

6.1 INTRODUCTION

6-2 6.2 GENERAL..........

. 6-2 6.3 CALCULATIONS OF TOTAL BODY DOSE.6-3 6.4 THYROID DOSE...........

6-4 SECTION 7 OFFSITE DOSE CALCULATION MANUAL SPECIFICATIONS AND BASES INDEX TO SECTION 7................

7-i 7.1 USE AND APPLICATION..................

7.1.1-1 7.2 NOT USED......

7.2.0-1 7.3 OFFSITE DOSE CALCULATION MANUAL SPECIFICATION (ODCMS) AND TEST REQUIREMENT (TR) APPLICABILITY...................................

,.,.7.3.0-1 ODCM (BSEP) ii Rev. 25

TABLE OF CONTENTS Section 7.4 7.5 B7.3 APPENDIX A APPENDIX B APPENDIX C APPENDIX D APPENDIX E APPENDIX F APPENDIX G APPENDIX H Title Page REPORTING REQUIREMENTS.....................

7.4.0-1 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS..

7.5.0-1 BASES............................................................................................................. B 7.3.0-1 METEOROLOGICAL DISPERSION FACTOR COMPUTATIONS........................... A-3 CALCULATIONS OF Vi AND Bi VALUES FOR THE ELEVATED PLUME.

B-4 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES AND TRITIUM.C-2 LOWER LIMIT OF DETECTION (LLD).D-1 RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS.........................................

E-1 LIQUID AND GASEOUS EFFLUENT SYSTEM DIAGRAMS.F-1 ODCM SOFTWARE PACKAGE.....................

G-1 METHODOLOGY AND CALCULATIONS FOR BURNING WASTE OIL.H-1 ODCM (BSEP)

Hii Rev. 25

LIST OF TABLES No.

SECTION 2 2.1-1 2.2-1 SECTION 3 3.1-1 3.1-2 3.2-1 3.2-2 3.2-3 3.2-4 3.2-5 3.3-1 THRU 3.3-19 SECTION 4 4.0-1 SECTION 7 7.3.1-1 7.3.2-1 Title Page ECs FOR SELECTED RADIONUCLIDES...................................

............... 2-10 Ait VALUES FOR THE ADULT..................................................

2-13 GASEOUS SOURCE TERMS..................................................

3-15 DOSE FACTORS AND CONSTANTS....................

.............................. 3-16 RELEASES FROM BRUNSWICK STEAM ELECTRIC PLANT.............................. 3-30 DISTANCE TO CONTROLLING LOCATIONS AS MEASURED FROM THE BRUNSWICK PLANT CENTER..................................................

3-31 DISTANCE TO SITE BOUNDARIES BASED UPON BRUNSWICK PLANT CENTER AND DIRECTION FROM THE STACK....................................... 3-32 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS...................

............. 3-33 P, VALUES FOR AN INFANT FOR THE BRUNSWICK STEAM ELECTRIC PLANT..................................................

3-34 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT..................................................................................................................... 3-48 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM..............

............. 4-4 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION..........................................................................................

7.3.1-7 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION.......................................................................................... 7.3.2-9 ODCM (BSEP) iv Rev. 25

LIST OF TABLES No.

SECTION 7 (Cont'c 7.3.3-1 7.3.3-2 7.3.7-1 7.3.1 5-1 7.3.15-2 7.3.15-3 APPENDIX A A-1 A-2 A-3 A-4 A-5 A-6 I)

Title Paqe RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM......................................................................................................... 7.3.3-3 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM FOR POTENTIAL RELEASE PATHWAYS WHICH HAVE EXCEEDED TRIGGER LEVELS...................................................

7.3.3-6 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM..........................................................................................................

7.3.7-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM................... 7.3.15-6 LIMITS FOR THE LEVEL OF RADIOACTIVITY IN ENVIRONMENTAL SAMPLES........................................................................................................ 7.3.15-11 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS....................................................................................................... 7.3.15-12 X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE TURBINE BUILDINGS...............................................

A-5 DEPLETED X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE TURBINE BUILDINGS.................................... A-6 D/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE TURBINE BUILDINGS....

A-7 X/O VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE TURBINE BUILDINGS...

A-8 DEPLETED X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE TURBINE BUILDINGS...

A-9 D/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE TURBINE BUILDINGS...

A-10 ODCM (BSEP) v Rev. 25

LIST OF TABLES No.

APPENDIX A (Cont A-7 A-8 A-9 A-1 0 A-i 1 A-1 2 A-1 3 A-1 4 A-1 5 A-1 6 A-17 A-1 8 A-1 9

'd)

Title Page X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE REACTOR BUILDINGS...................................................... A-11 DEPLETED X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE REACTOR BUILDINGS................................................... A-12 DIQ VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE REACTOR BUILDINGS.....................................................

A-1 3 X/O VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE REACTOR BUILDINGS...................................................... A-14 DEPLETED X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE REACTOR BUILDINGS...................................................A-15 D/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE REACTOR BUILDINGS....................................................

A-16 X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE STACK....................................................

A-17 DEPLETED X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE STACK....................................................

A-18 DIQ VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE STACK.....................................................,

A-19 X/O VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE STACK....................................................

A-20 DEPLETED XIQ VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE STACK....................................................

A-21 DIQ VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE STACK....................................................

A-22 BRUNSWICK PLANT SITE INFORMATION TO BE USED FOR GROUND LEVEL CALCULATIONS WITH NRC "XOQDOQ" PROGRAM.............................. A-23 ODCM (BSEP) vi Rev. 25

LIST OF TABLES No.

APPENDIX A (Coni A-20 APPENDIX B B-1 B-2 B-3 B-4 B-5 B-6 B-7 B-8 B-9 B-1 0 itd)

Title Page BRUNSWICK PLANT SITE INFORMATION TO BE USED FOR ELEVATED RELEASE CALCULATIONS WITH NRC "XOQDOQ' PROGRAM................................................

A-26 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES ENE SITE BOUNDARY.......

B-5 JOINT FREQUENCY DISTRIBUTION FOR ENE SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT.B-6 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES N SITE BOUNDARY.......

B-7 JOINT FREQUENCY DISTRIBUTION FOR N SECTOR (%) PERIOD 1-1-77THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT................ B-8 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NNE SITE BOUNDARY........

B-9 JOINT FREQUENCY DISTRIBUTION FOR THE NNE SECTOR

(%)PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT.

B-10 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NE SITE BOUNDARY.........

B-11 JOINT FREQUENCY DISTRIBUTION FOR NE SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT.

B-12 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES E SITE BOUNDARY.......

B-13 JOINT FREQUENCY DISTRIBUTION FOR E SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT.............. B-14 ODCM (BSEP) vii Rev. 25

LIST OF TABLES No.

APPENDIX B (Cont' B-11 B-1 2 B-13 B-14 B-1 5 B-1 6 B-17 B-1 8 B-19 B-20 B-21 B-22 d)

Title Page DOSE PARAMETERS FOR FINITE ELEVATED PLUMES ESE SITE BOUNDARY.....................................................

B-15 JOINT FREQUENCY DISTRIBUTION FOR ESE SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT.............. B-16 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SE SITE BOUNDARY................................................................................. B-17 JOINT FREQUENCY DISTRIBUTION FOR SE SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT.............. B-18 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SSE SITE BOUNDARY.............................................................................

.......................... B-19 JOINT FREQUENCY DISTRIBUTION FOR SSE SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT.............. B-20 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES S SITE BOUNDARY............................................................................................................ B-21 JOINT FREQUENCY DISTRIBUTION FOR S SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT.............. B-22 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SSW SITE BOUNDARY....................................................

B-23 JOINT FREQUENCY DISTRIBUTION FOR SSW SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT.............. B-24 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SW SITE BOUNDARY....................................................

B-25 JOINT FREQUENCY DISTRIBUTION FOR SW SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT.............. B-26 viii Rev. 25 ODCM (BSEP)

LIST OF TABLES No.

Title Page APPENDIX B (Cont'd)

B-23 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES WSW SITE BOUNDARY...................................................

, B-27 B-24 JOINT FREQUENCY DISTRIBUTION FOR WSW SECTOR (%)

PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT..

B-28 B-25 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES W SITE BOUNDARY..........

B-29 B-26 JOINT FREQUENCY DISTRIBUTION FOR W SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT.............. B-30 B-27 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES WNW SITE BOUNDARY.......

B-31 B-28 JOINT FREQUENCY DISTRIBUTION FOR WNW SECTOR (%)

PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT...

B-32 B-29 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NW SITE BOUNDARY........

B-33 B-30 JOINT FREQUENCY DISTRIBUTION FOR NW SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT.............. B-34 B-31 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NNW SITE BOUNDARY......

8, B-35 B-32 JOINT FREQUENCY DISTRIBUTION FOR NNW SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT.............. B-36 ODCM (BSEP) ix Rev. 25

LIST OF TABLES No.

APPENDIX C C-1 C-2 C-3 Title Page PARAMETERS FOR COW AND GOAT MILK PATHWAYS.................................. C-14 PARAMETERS FOR THE MEAT PATHWAY..........................................

C-15 PARAMETERS FOR THE VEGETABLE PATHWAY............................................ C-16 ODCM (BSEP) x Rev. 25

LIST OF FIGURES No.

Title Paqe 4.0-1a BSEP Sample Point Locations..........................

4-10 4.0-1 b BSEP Sample Point Locations..........................

4-11 7.1.1-1 Site Boundary..........................

7.1.1-5 F-1 Liquid Radwaste Effluent System..........................

F-2 F-2 Gaseous Radwaste Effluent System..........................

F-3 ODCM (BSEP) xi Rev. 25

INTRODUCTION The Off-Site Dose Calculation Manual (ODCM) provides the information and methodologies to be used by the Brunswick Steam Electric Plant (BSEP) to show compliance with 1 OCFR20, 1 OCFR50.36a, Appendix I of 1 OCFR50, and 40CFR190 and to assure compliance with ODCM Specifications (ODCMS).

The ODCM is based on "Radiological Effluent Technical Specifications for BWR's" (NUREG 0473, Draft), "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" (NUREG 0133), and guidance from the United Stated Nuclear Regulatory Commission (NRC). Specific plant procedures for implementation of this manual are provided elsewhere. These procedures will be utilized to assure compliance with ODCMS and Test Requirements (TRs) provided in the Radioactive Effluents Control Program.

The ODCM has been prepared as generically as possible to minimize the need for future revisions. Any changes to the ODCM will be reviewed and approved as indicated in the Administrative Control section of the BSEP Technical Specifications.

The Radioactive Effluent Release Report prepared after January 1 of each year will include an assessment of the annual radiation doses to members of the public from radioactive liquid and gaseous effluents using the methodology in the ODCM for the report period. This report will be inclusive of the requirements outlined in the BSEP Technical Specifications and ODCM Specifications.

ODCM (BSEP) 1-1 Rev. 26 l

INDEX 2.0 LIQUID EFFLUENT............................................

2-3 2.1 COMPLIANCE WITH 1 OCFR PART 20 (LIQUIDS).................................... 2-3 2.1.1 Batch Releases............................................ 2-3 2.1.2 Continuous Releases............................................ 2-8 2.1.3 Stabilization Pond Releases............................................

2-9 2.2 COMPLIANCE WITH 10CFR PART 50 (LIQUIDS).................................. 2-11 2.2.1 Cumulation of Doses.2-11 2.2.2 Projection of Doses.2-12 ODCM (BSEP) 2-1 Rev. 25

Table No.

SECTION 2 2.1-1 2.2-1 LIST OF TABLES Title Page ECs FOR SELECTED RADIONUCLIDES

............................ 2-10 A,, VALUES FOR THE ADULT............................

2-13 ODCM (BSEP) 2-2 Rev. 25

2.0 LIQUID EFFLUENT 2.1 COMPLIANCE WITH 10CFR PART 20 (LIQUIDS) 2.1.1 Batch Releases A batch release is the discharge of liquid waste of a discrete volume.

Batch releases from the BSEP liquid radwaste system may occur from the waste sample tank, floor drain sample tank, detergent drain tank and the salt water tanks. The maximum release rate possible due to pump capacity is 200 GPM from all release tanks except the detergent drain tank, which has a maximum release rate of 50 GPM.

All of the above liquid radwaste discharges go to the circulating water discharge canal. Circulating water leakage collected in the circulating water pits and low purity, low activity liquids are transferred to the salt water release tanks where they are recirculated, sampled, and released to the environment. For any batch release, if the radwaste monitor effluent is inoperable, then two independent samples are analyzed and must be within 15% of each other before the release is approved. The two samples may differ by more than 15% upon approval of the E&C Supervisor or equivalent. The maximum release rate is determined so that 1 OCFR Part 20 limits are not exceeded after dilution in the discharge canal.

The sampling and analysis frequency and the type of analysis required by the BSEP ODCM Specifications is given in Table 7.3.3-1.

All applicable instrument numbers may be found in Appendix E.

1.

Prerelease The radioactive content of each batch release will be determined prior to release in accordance with Table 7.3.3-1 of the BSEP ODCM Specifications. Compliance with 1 OCFR Part 20 will be shown in the following manner:

a.

Minimum acceptable dilution factor:

DFo

=

(Eq. 2.1-1)

Where:

DFo

=

Minimum acceptable dilution factor determined from analysis of liquid effluent to be released C

=

Concentration of radionuclide i in the batch to be released, PtC/ml ECQ

=

Annual average effluent concentration limit of radionuclide i from Appendix B, Table 2, Column 2 of 10CFR20, giCi/ml.

ODCM (BSEP) 2-3 Rev. 25

DFB

=

(1 0) (DFo)

(Eq. 2.1-2)

Where:

DFB

=

Conservative dilution factor used by BSEP to calculate maximum release rate prior to release in order to assure compliance with 1 OCFR Part 20 10

=

A factor of 10 less than 1 OUR Part 20 limits as specified in Appendix B, Table 2, Column 2. This factor represents one layer of conservatism for all releases at BSEP DFO

=

Minimum acceptable dilution factor per Equation 2.1-1

b.

Maximum release rate:

MRR

=

n-2(RPFcw) + p-i (RPFsw)

(Eq. 2.1-3) 2 (DFB)

Where:

MRR

=

Maximum release rate of the batch to be released, GPM n

=

Number of operating circulating water pumps p

=

Number of operating service water pumps RPFcw =

Minimum rated pump flow of each circulating water pump

=

1.357 E5 GPM RPFsw =

Rated pump flow of each service water pump 8 E3 GPM 2

=

Engineering factor to prevent spurious alarms caused by deviations in the mixtures of radionuclides which affect the monitor response DFB

=

Minimum acceptable dilution factor (DF0) made conservative by a factor of 10 per Equation 2.1-2 ODCM (BSEP) 2-4 Rev. 25

c.

Monitor Alarm/Trip Setpoint:

Monitor alarm/trip setpoints are determined to ensure that the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas does not exceed the limits specified in 10CFR Part 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. An effluent concentration (EC) of 2 E-4 giCi/ml has been established for noble gases dissolved or entrained in liquid effluents, based on the assumption that Xenon-135 is the controlling radionuclide. (NUREG 0133)

SP

=

CT (Em) [(n-i) (RPFcWl) + (p-i) (RPFsW)] + Bkg (Eq. 2.1-4)

Where:

SP

=

Monitor alarm/trip setpoint, cps Em

=

The monitor efficiency for the mixture of radionuclides in the liquid effluent prior to dilution, cps/ptCi/ml CT

=

3 E-7 pCi/ml; engineering factor to ensure that the final concentration for the mixture of radionuclides will be less than 1 OCFR Part 20 limits at unrestricted areas n

=

Number of operating circulating water pumps p

=

Number of operating service water-pumps RPFcw =

1.357 E5 GPM RPFsw =

8 E3 GPM RR

=

200 GPM; maximum design release rate Bkg

=

Background count rate due to internal contamination and the radiation levels in the area in which the monitor is installed when the detector sample chamber is filled with an uncontaminated fluid, cps SP = 3 E-7 (E,) [(n-i) (1.357 E5) + (p-i) (8.0 E3)] + 8kg (Eq. 2.1-5) 200 ODCM (BSEP) 2-5 Rev. 25

d.

Calculated concentration at unrestricted area:

Conci =

(Ce) (MRR)

(Eq. 2.1-6)

(n - 1) (RPFcw) + (p - 1) (RPFsw)

Where:

Conc, =

Calculated concentration of radionuclide i at the unrestricted area, tiCiml C

=

Concentration of radionuclide i in the batch to be released, ItCiml MRR

=

Maximum release rate of the batch to be released (see Equation 2.1-3), GPM n

=

Number of operating circulating water pumps p

=

Number of operating service water pumps RPFcw =

1.357 E5 GPM RPFsw =

8 E3 GPM

e.

10CFR Part 20 Prerelease Compliance Check:

Before initiating the batch release, one final check for compliance with 1 OCFR Part 20 will be performed. If the calculated dilution factor at the unrestricted area is less than or equal to 1, then 1 OCFR Part 20 limits have been met. The following equation must be true:

E; (Conc/ECQ) < 1 (Eq. 2.1-7)

Where:

Conci

=

Concentration of radionuclide i at the unrestricted area per Equation 2.1-6, pCi/ml EC;

=

Annual average effluent concentration limit of radionuclide i from Appendix B, Table 2, Column 2 of 1 OCFR20, pCi/ml.

ODCM (BSEP) 2-6 Rev. 25

ConClik Where:

ConCik Ci Veff Vdil

2.

Postrelease The actual concentration of each radionuclide following release from a batch tank will be calculated to show final compliance with 1 OCFR Part 20 as follows:

a.

Actual concentration at unrestricted area:

(Cl) (VeH)

(Eq. 2.1-E Vd.l The actual concentration of radionuclide i at the unrestricted area during release k, pCilml Concentration of radionuclide i in tne batch released, piCVml Actual volume of liquid effluent released, gal Actual volume of dilution water during release k, gal

[n (RPFcw) + P (RPFsw)] (tk)

B)

Where:

n p

RPFcw RPFsw tk Where:

Conck ECQ Number of operating circulating water pumps Number of operating service water pumps 1.357 E5 GPM 8 E3 GPM Total release time, min

b.

1 OCFR Part 20 Postrelease Compliance Check:

To show final compliance with 1 OCFR Part 20, the following relationship must hold:

Yj (Concik/EC,) < 1 (Eq. 2.1-9)

The actual concentration of radionuclide i during release k (from Equation 2.1-8), jtCi/ml Annual average effluent concentration limit of radionuclide i from Appendix B, Table 2, Column 2 of 10CFR20, pCi/ml.

ODCM (BSEP) 2-7 Rev. 25

2.1.2 Continuous Releases A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume or system that has an input flow during the continuous release. Planned continuous releases do not presently occur at BSEP, although the potential does exist in the service water system. Weekly tests are performed during system operation as specified in Table 7.3.3-1 of the BSEP ODCM Specifications. If a continuous release does occur, the concentration of various radionuclides in the unrestricted area would be calculated using Equation 2.1-8 with Ci being the concentration of radionuclide i in the continuous release stream. To show compliance with 10CFR Part 20, the sum of the concentration of radionuclide i in the unrestricted area due to both continuous and batch releases divided by that isotope's EC must again be less than 1.

1.

Service Water Effluent Monitor Setpoint Determination This procedure determines the monitor alarm setpoints that indicate the abnormal presence of radionuclides in the service water liquid effluents released from the site to unrestricted areas. This procedure is applicable to any service water effluent monitor.

a.

Determine the monitor efficiency factor, EF, in ICi/ml cps EF

=

(Em) (Cf)

(Eq. 2.1-10)

Where:

Em

=

The detector efficiency (dpmlml/cps) from the appropriate RST C

=

Conversion factor, (1 pCi/2.22 x 1 06 dpm)

b.

Determine the monitor trigger level setpoint, TLS, in cps TLS

=

TUEF + Bkg (Eq. 2.1-11)

Where:

TL

=

The alarm trigger level (iLCi/ml) as per ODCM TR 7.3.3.2

=

5.0 x 10.6 jiCi/ml Bkg

=

Monitor background, (cps)

ODCM (BSEP) 2-8 Rev. 25

2.1.3 Stabilization Pond Releases Prerelease and post-release compliance checks similar to those of Section 2.1.1 may be performed for releases from the stabilization pond. Prerelease calculations will be based on a gamma isotopic assay of a grab sample prior to release. Post-release calculations will be based on a composite sample that is collected in proportion to flow during the release period (if possible). Dilution flow will be estimated from the minimum number of circulating water and service water pumps that were in use during the release period. Typical release times are on the order of days. (Note: Calculated doses as in Section 2.2 will be compiled along with those resulting from normal radwaste discharges.)

ODCM (BSEP) 2-9 Rev. 25

TABLE 2.1-1 ECs FOR SELECTED RADIONUCLIDES Radionuclide ECiiCi/ml)

H-3 1 E-3 Na-24 5 E-5 Cr-51 5 E-4 Mn-54 3 E-5 Co-58 2 E-5 Fe-59 1 E-5 Co-60 3 E-6 Cu-64 2 E-4 Zn-65 5 E-6 Zn-69m 6 E-5 Sr-89 8 E-6 Sr-90 5 E-7 Sr-91 2 E-5 Zr-95 2 E-5 Mo-99 2 E-5 1-131 1 E-6 1-132 1 E-4 1-133 7 E-6 Cs-1 34 9 E-7 1-134 4 E-4 1-135 3 E-5 Cs-137 1 E-6 La-141 5 E-5 Np-239 2 E-5 Am-241 2 E-8 Noble Gases 2 E-4 ODCM (BSEP) 2-10 Rev. 25

2.2 COMPLIANCE WITH 10CFR PART 50 (LIQUIDS) 2.2.1 Cumulation of Doses ODCM TR 7.3.4.1 requires that the cumulative dose contributions from liquid effluents be determined at least once per 31 days, and a cumulative summation of these total body and any organ doses should be maintained for each calendar quarter. The cumulative dose contributions will consider the dose contributions from the maximum exposed individual's consumption of fish and invertebrates.

At BSEP the adult is considered as the maximum exposed individual.

The dose or dose commitment limits based on 1 OCFR Part 50, Appendix I, are defined in ODCM Specification 7.3.4 a and b. Since only batch releases occur at BSEP, the equations in the following sections pertain only to batch releases. The dose contribution for all batch releases for the quarter will be calculated using the following equation:

D-

=

X [E (AIT tk CAk Fk)]

(Eq. 2.2-1)

Where:

D

=

The cumulative dose commitment to the total body or any organ r, from the liquid effluents releases, mrem tk

=

The length of time of release k over which Cik and Fk are averaged for each liquid release, hours Cik

=

The concentration of radionuclide i in the undiluted liquid effluent during release k from any liquid release, pCi/ml Fk

=

The near-field average dilution factor for Cik during any liquid effluent release. It is defined as the ratio of the volume of undiluted liquid waste released to the product of the dilution volume from the site discharge to unrestricted receiving water times 1. (1 is the site-specific applicable factor for the mixing effect of the BSEP discharge structure as defined in NUREG 0133.)

Ven (See Equation 2.1-8).

Vdil Ar

=

The ingestion dose commitment factor to the total body or any organ

-r for each identified gamma and beta emitter i (as presented in Table 2.2-1). Values are for an adult, mrem-ml per hr-ptCi

=

1.14 E5 (5 BI, + 21 BF,) DCF,;

ODCM (BSEP) 2-11 Rev. 25

Where:

1.14 E5=

(10 -PCi 103ml)(

hyr )

5

=

Maximum adult invertebrate consumption rate from Table E-5 of Regulatory Guide 1.109, Rev. 1, kg/yr Bli

=

Bioaccumulation factor for radionuclide i in invertebrates from Table A-1 of Regulatory Guide 1.109, Rev. 1, pCi/kg per pCVL 21

=

Maximum adult fish consumption rate from Table E-5 of Regulatory Guide 1.109, Rev. 1, kg/yr BFi

=

Bioaccumulation factor for radionuclide i in fish from Table A-1 of Regulatory Guide 1.109, Rev. 1, pCVkg per pCi/L DCFn

=

Dose conversion factor for radionuclide i for adults for a particular organ r from Table E-1 1 of Regulatory Guide 1.109, Rev. 1, and BSEP File: B10-10530, Letter to J. W. Davis, "Dose Factors for Hf-1 81 and Sn-113," May 24, 1988, and NUREG CR4653 for Am-241, mrem/pCi.

2.2.2 Proiection of Doses Dose projections for this section are required at least once per 31 days in ODCM TR 7.3.5.2.

The projection of doses for liquid effluents can be accomplished by projecting the dose(s) computed for the current month into the next month. The doses will be projected using Equation 2.2-1. Where possible, credit for expected operational evolutions (i.e., major planned liquid releases, etc.), can be taken in the dose projections.

This may be accomplished by using the source-term data from similar historical operating experiences where practical.

ODCM (BSEP) 2-12 Rev. 25

TABLE 2.2-1 Ait VALUES FOR THE ADULT (MREM/HR PER MICRO-CI/ML)

Note: Nuclides not listed in this table are assigned a value of zero.

Nuclide Bone Liver T.Body Thyroid Kidney Lunq GI-LLI H 3 O.OOE-01 2.82E-01 2.82E-01 2.82E-01 2.82E-01 2.82E-01 2.82E-01 C 14 1.45E 04 2.90E 03 2.90E 03 2.90E 03 2.90E 03 2.90E 03 2.90E 03 NA 24 4.57E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01 P 32 1.67E 07 1.04E 06 6.45E 05 O.OOE-01 O.OOE-01 O.OOE-01 1.89E 06 CR 51 O.OOE-01 O.OOE-01 5.58E 00 3.34E 00 1.23E 00 7.40E 00 1.40E 03 MN 54 O.OOE-01 7.06E 03 1.35E 03 O.OOE-01 2.1OE 03 O.OOE-01 2.16E 04 MN 56 O.OOE-01 1.78E 02 3.15E 01 O.OOE-01 2.26E 02 O.OOE-01 5.67E 03 FE 55 5.11 E 04 3.53E 04 8.23E 03 O.OOE-01 O.OOE-01 1.97E 04 2.03E 04 FE 59 8.06E 04 1.90E 05 7.27E 04 O.OOE-01 O.OOE-01 5.30E 04 6.32E 05 CO 57 O.OOE-01 1.42E 02 2.36E 02 O.OOE-01 O.OOE-01 O.OOE-01 3.59E 03 CO 58 O.OOE-01 6.03E 02 1.35E 03 O.OOE-01 O.OOE-01 O.OOE-01 1.22E 04 CO 60 O.OOE-01 1.73E 03 3.82E 03 O.OOE-01 O.OOE-01 O.OOE-01 3.25E 04 NI 63 4.96E 04 3.44E 03 1.67E 03 O.OOE-01 O.OOE-01 O.OOE-01 7.18E 02 NI 65 2.02E 02 2.62E 01 1.20E 01 O.OOE-01 O.OOE-01 O.OOE-01 6.65E 02 CU 64 O.OOE-01 2.14E 02 1.01 E 02 O.OOE-01 5.40E 02 O.OOE-01 1.83E 04 ZN 65 1.61 E 05 5.13E 05 2.32E 05 O.OOE-01 3.43E 05 O.OOE-01 3.23E 05 ZN 69 3.43E 02 6.56E 02 4.56E 01 O.OOE-01 4.26E 02 O.OOE-01 9.85E 01 BR 83 O.OOE-01 O.OOE-01 7.25E-02 O.OOE-01 O.OOE-01 O.OOE-01 1.04E-01 BR 84 O.OOE-01 O.OOE-01 9.39E-02 O.OOE-01 O.OOE-01 O.OOE-01 7.37E-07 BR 85 O.OOE-01 O.OOE-01 3.86E-03 O.OOE-01 O.OOE-01 O.OOE-01 1.80E-18 RB 86 O.OOE-01 6.24E 02 2.91 E 02 O.OOE-01 O.OOE-01 O.OOE-01 1.23E 02 RB 88 O.OOE-01 1.79E 00 9.49E-01 O.OOE-01 O.OOE-01 O.OOE-01 2.47E-11 RB 89 O.OOE-01 1.19E 00 8.34E-01 O.OOE-01 O.OOE-01 O.OOE-01 6.89E-14 SR 89 4.99E 03 O.OOE-01 1.43E 02 O.OOE-01 O.OOE-01 O.OOE-01 8.00E 02 SR 90 1.23E 05 O.OOE-01 3.01 E 04 O.OOE-01 O.OOE-01 O.OOE-01 3.55E 03 SR 91 9.18E 01 O.OOE-01 3.71 E 00 O.OOE-01 0.00E-01 O.OOE-01 4.37E 02 SR 92 3.48E 01 O.OOE-01 1.51 E 00 O.OOE-01 O.OOE-01 O.OOE-01 6.90E 02 Y 90 6.06E 00 O.OOE-01 1.63E-01 O.OOE-01 O.OOE-01 O.OOE-01 6.42E 04 Y 91M 5.73E-02 O.OOE-01 2.22E-03 O.OOE-01 O.OOE-01 O.OOE-01 1.68E-01 Y 91 8.88E 01 O.OOE-01 2.37E 00 O.OOE-01 O.OOE-01 O.OOE-01 4.89E 04 Y 92 5.32E-01 0.00E-01 1.56E-02 0.00 -01 0.00E-01 0.00E-01 9.32E 03 Y 93 1.69E 00 O.OOE-01 4.66E-02 O.OOE-01 OOOE-01 O.OOE-01 5.35E 04 ODCM (BSEP) 2-13 Rev. 25

TABLE 2.2-1 (Cont'd)

Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI ZR 95 1.59E 01 5.11 E 00 3.46E 00 O.OOE-01 8.02E 00 0O.OOE-01 1.62E 04 ZR 97 8.81 E-01 1.78E-01 8.13E-02 O.OOE-01 2.68E-01 O.OOE-01 5.51E 04 NB 95 4.47E 02 2.49E 02 1.34E 02 O.OOE-01 2.46E 02 O.OOE-01 1.51 E 06 MO 99 O.OOE-01 1.28E 02 2.43E 01 O.OOE-01 2.89E 02 O.OOE-01 2.96E 02 TC 99M 1.30E-02 3.66E-02 4.66E-01 O.OOE-01 5.56E-01 1.79E-02 2.17E 01 TC 101 1.33E-02 1.92E-02 1.88E-01 O.OOE-01 3.46E-01 9.81 E-03 5.77E-14 RU 103 1.07E 02 O.OOE-01 4.60E 01 O.OOE-01 4.07E 02 O.OOE-01 1.25E 04 RU 105 8.89E 00 O.OOE-01 3.51E 00 O.OOE-01 1.15E 02 O.OOE-01 5.44E 03 RU 106 1.59E 03 O.OOE-01 2.01 E 02 O.OOE-01 3.06E 03 O.OOE-01 1.03E 05 AG 110M 1.56E 03 1.45E 03 8.60E 02 O.OOE-01 2.85E 03 O.OOE-01 5.91E 05 SN 113 2.18E 03 8.43E 01 2.05E 03 2.96E 01 6.16E 01 O.OOE 01 3.80E 04 TE 125M 2.17E 02 7.86E 01 2.91 E 01 6.52E 01 8.82E 02 O.OOE-01 8.66E 02 TE 127M 5.48E 02 1.96E 02 6.68E 01 1.40E 02 2.23E 03 O.OOE-01 1.84E 03 TE 127 8.90E 00 3.20E 00 1.93E 00 6.60E 00 3.63E 01 O.OOE-01 7.03E 02 TE 129M 9.31E 02 3.47E 02 1.47E 02 3.20E 02 3.89E 03 O.OOE-01 4.69E 03 TE 129 2.54E 00 9.55E-01 6.19E-01 1.95E 00 1.07E 01 O.OOE-01 1.92E 00 TE 131M 1.40E 02 6.85E 01 5.71E 01 1.08E 02 6.94E 02 O.OOE-01 6.80E 03 TE 131 1.59E 00 6.66E-01 5.03E-01 1.31 E 00 6.99E 00 O.OOE-01 2.26E-01 TE 132 2.04E 02 1.32E 02 1.24E 02 1.46E 02 1.27E 03 O.OOE-01 6.24E 03 1130 3.96E 01 1.17E 02 4.61 E 01 9.91 E 03 1.82E 02 O.OOE-01 1.01 E 02 1131 2.18E 02 3.12E 02 1.79E 02 1.02E 05 5.35E 02 O.OOE-01 8.23E 01 1132 1.06E 01 2.85E 01 9.96E 00 9.96E 02 4.54E 01 O.OOE-01 5.35E 00 1133 7.45E 01 1.30E 02 3.95E 01 1.90E 04 2.26E 02 O.OOE-01 1.16E 02 1134 5.56E 00 1.51 E 01 5.40E 00 2.62E 02 2.40E 01 O.OOE-01 1.32E-02 1135 2.32E 01 6.08E 01 2.24E 01 4.01E 03 9.75E 01 O.OOE-01 6.87E 01 CS 134 6.84E 03 1.63E 04 1.33E 04 O.OOE-01 5.27E 03 1.75E 03 2.85E 02 CS 136 7.16E 02 2.83E 03 2.04E 03 O.OOE-01 1.57E 03 2.16E 02 3.21 E 02 CS 137 8.77E 03 1.20E 04 7.85E 03 O.OOE-01 4.07E 03 1.35E 03 2.32E 02 CS 138 6.07E 00 1.20E 01 5.94E 00 O.OOE-01 8.81 E 00 8.70E-01 5.12E-05 BA 139 7.85E 00 5.59E-03 2.30E-01 O.OOE-01 5.23E-03 3.17E-03 1.39E 01 BA 140 1.64E 03 2.06E 00 1.08E 02 O.OOE-01 7.02E-01 1.18E 00 3.38E 03 BA 141 3.81 E 00 2.88E-03 1.29E-01 O.OOE-01 2.68E-03 1.63E-03 1.80E-09 BA 142 1.72E 00 1.77E-03 1.08E-01 O.OOE-01 1.50E-03 1.OOE-03 2.43E-18 LA 140 1.57E 00 7.94E-01 2.10E-01 O.OOE-01 O.OOE-01 O.OOE-01 5.83E 04 ODCM (BSEP) 2-14 Rev. 25

TABLE 2.2-1 (Cont'd)

Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI LA 142 8.06E-02 3.67E-02 9.13E-03 O.OOE-01 O.OOE-01 O.OOE-01 2.68E 02 CE 141 3.43E 00 2.32E 00 2.63E-01 O.OOE-01 1.08E 00 O.OOE-01 8.86E 03 CE 143 6.04E-01 4.46E 02 4.94E-02 O.OOE-01 1.97E-01 O.OOE-01 1.67E 04 CE 144 1.79E 02 7.47E 01 9.59E 00 O.OOE-01 4.43E 01 O.OOE-01 6.04E 04 PR 143 5.79E 00 2.32E 00 2.87E-01 O.OOE-01 1.34E 00 O.OOE-01 2.54E 04 PR 144 1.90E-02 7.87E-03 9.64E-04 O.OOE-01 4.44E-03 O.OOE-01 2.73E-09 ND 147 3.96E 00 4.58E 00 2.74E-01 O.OOE-01 2.68E 00 O.OOE-01 2.20E 04 HF 181 1.72E 02 9.66E-01 1.94E 01 6.14E-01 8.08E-01 O.OOE-01 1.27E 04 W 187 9.16E 00 7.66E 00 2.68E 00 O.OOE-01 O.OOE-01 O.OOE-01 2.51 E 03 NP 239 3.53E-02 3.47E-03 1.91 E-03 O.OOE-01 1.08E-02 O.OOE-01 7.11 E 02 AM 241 4.76E 05 4.44E 05 3.41E 04 O.OOE-01 2.56E 05 O.OOE 01 4.67E 04 F 18 6.66E 00 O.OOE-01 7.38E-01 O.OOE-01 O.OOE-01 O.OOE-01 1.97E-01 SB 124 2.76E 02 5.22E 00 1.09E 02 6.70E-01 O.OOE-01 2.15E 02 7.84E 03 ODCM (BSEP) 2-15 Rev. 25

INDEX 3.0 GASEOUS EFFLUENTS............................................

3-4 3.1 MONITOR ALARM SETPOINT DETERMINATION................................... 3-4 3.1.1 Setpoint Based on Conservative Radionuclide Mix (Ground and Mixed Mode Releases)..................

3-4 3.1.2 Setpoint Based on Conservative Radionuclide Mix (Long-Term Elevated Release.3-7 3.1.3 Condenser Air Ejector Monitor Alarm Setpoint.3-10 3.1.4 Condenser Off-Gas Treatment System (AOG) Monitor Alarm Setpoint Determination.....................................

3-13 3.2 COMPLIANCE WITH 1 OCFR20 (GASEOUS).....................................

3-17 3.2.1 Noble Gases.....................................

3-17 3.2.2 1-131, 1-133, Particulates, and Tritium.....................................

3-23 3.3 COMPLIANCE WITH 10CFR50 (GASEOUS).....................................

3-35 3.3.1 Noble Gases.....................................

3-35 3.3.2 1-131, 1-133, Particulates, and Tritium.....................................

3-40 4A ODCM (BSEP) 3-1 Rev. 25

LIST OF TABLES Title Table No.

SECTION 3 3.1-1 3.1-2 3.2-1 3.2-2 3.2-3 3.2-4 3.2-5 3.3-1 3.3-2 3.3-3 3.3-4 3.3-5 3.3-6 3.3-7 3.3-8 Paoe GASEOUS SOURCE TERM.........

.............................................. 3-15 DOSE FACTORS AND CONSTANTS...................

.................................... 3-16 RELEASES FROM BRUNSWICK STEAM ELECTRIC PLANT.............................. 3-30 DISTANCE TO CONTROLLING LOCATIONS AS MEASURED FROM THE BRUNSWICK PLANT CENTER.......................................................

3-31 DISTANCE TO SITE BOUNDARIES BASED UPON BRUNSWICK PLANT CENTER AND DIRECTION FROM THE STACK...................................................

3-32 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS................................ 3-33 Pi VALUES FOR AN INFANT FOR THE BRUNSWICK STEAM ELECTRIC PLANT...................................................................................................................... 3-34 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT - GROUND............... 3-48 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -

VEGETABLE/ADULT....................................................... 3-49 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -

VEGETABLE/TEEN.......................................................

3-50 R VALUES-FOR BRUNSWICK STEAM ELECTRIC PLANT -

VEGETABLE/CHILD.......................................................

3-51 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT - MEAT/ADULT........ 3-52 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT - MEAT/TEEN.......... 3-53 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT - MEAT/CHILD......... 3-54 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT - COW MILK/ADULT.......................................................

3-55 ODCM (BSEP) 3-2 Rev. 25

LIST OF TABLES Table No.

Title Page 3.3-9 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT - COW MILK/TEEN.........

3-56 3.3-10 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT - COW MILK/CHILD.

3-57 3.3-11 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT - COW MILK/INFANT.35.................

3-58 3.3-12 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT - GOAT MILK/ADULT.

3-59 3.3-13 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT - GOAT MILK/TEEN.

3-60 3.3-14 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT - GOAT MILK/CHILD......

3-61 3.3-15 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT - GOAT MILK/INFANT........

3-62 3.3-16 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -

INHALATION/ADULT.

3-63 3.3-17 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -

INHALATIONITEEN.

3-64 3.3-18 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -

INHALATIONICHILD.............

3-65 3.3-19 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -

INHALATION/INFANT..............

3-66 ODCM (BSEP) 3-3 Rev. 25

3.0 GASEOUS EFFLUENTS 3.1 MONITOR ALARM SETPOINT DETERMINATION This procedure determines the monitor alarm setpoint that indicates if the dose rate in the unrestricted areas due to noble gas radionuclides in the gaseous effluent released from the site to areas at and beyond the site boundary exceeds 500 mrem/year to the whole body or exceeds 3000 mremlyear to the skin. (NUREG-0133) 3.1.1 Setpoint Based on Conservative Radionuclide Mix (Ground and Mixed Mode Releases)

The following method applies to gaseous releases via the Units 1 and 2 Turbine Building Vents and via the Units 1 and 2 Reactor Building Vents when determining the high alarm setpoint for the Turbine Building Vent Gas Monitors and Reactor Building Vent Gas Monitors.

1.

Determine the "mix" (noble gas radionuclide composition) of the gaseous effluent (the "mix" can be determined from actual data or by using GALE code results of Table 3.1-1):*

a.

Determine the gaseous source terms that are representative of the "mix" of the gaseous effluent. Gaseous source terms are the noble gas activities in the effluent.

Gaseous sNjirce terms can be obtained from:

Table 3.1-1; Turbine Building Vent Release Table 3.1-1; Reactor Building Vent Release Actual release data

b.

Determine S. (the fraction of the total noble gas radioactivity in the gaseous effluent comprised by noble gas radionuclide i) for each individual noble gas radionuclide in the gaseous effluent.

Si

=

A (3.1-1)

Ai

=

The radioactivity of noble gas radionuclide i in gaseous effluent from Table 3.1-1, Turbine Building Vent Release; Table 3.1-1, Reactor Building Vent Release: or from analysis of gaseous effluent.

If actual plant data is used, the dose constants need to be confirmed.

ODCM (BSEP) 3-4 Rev. 25

2.

Determine Qt (the maximum acceptable total release rate of all noble gas radionuclides in the gaseous effluent, 0tCi/sec) based upon the whole body exposure limit.

500 (X/ Q)F.(KjS.)

(3.1-2)

(XI/Q).

The highest calculated annual average relative concentration of effluents released via the Turbine Building Vent for any area at or beyond the site boundary for all sectors (sec/M 3) from Table A-1, Appendix A 7.50 E-6 sec/iM3 The highest calculated annual average relative concentration of effluents released via the Reactor Building Vent for any area at or beyond the site boundary for all sectors (sec/M 3) from Table A-7, Appendix A 2.0 E-7 sec/iM3 (X / Q)b Ki

=

The total whole body dose factor due to gamma emissions from noble gas radionuclide rimrem/yeartLCVm3) from Table 3.1-2.

3.

Determine Qt based upon the skin exposure limit.

3000 (x/Q)ZJ(Li + 1.1 W)S]

(3.1-3)

L1 +.1M; =

The total skin dose factor due to emissions from noble gas radionuclide i (mrem/year/LCViM3) from Table 3.1-2.

NOTE:

The Turbine Building radiation monitors are designed to input the monitor high alarm setpoint in ttCi/sec or tCi/cc. The monitor setpoint in l.Ci/sec can be obtained by multiplying the lowest Q. value (obtained from Sections 3.1.1.2 and 3.1.1.3) by the Tm value found in Section 3.1.1.5.b. The pCi/cc setpoint can be obtained by dividing the jptCi/sec setpoint by the design flow rate in cc/sec. The equations for calculating the setpoint in cpm are included for completeness and may be used if desired.

ODCM (BSEP) 3-5 Rev. 25 d.{

4.

Determine Ct (the maximum acceptable total radioactivity concen-tration of all noble gas radionuclides in the gaseous effluent,

.Ci/sec/cfm).

C

=

t (3.1-4) f I

NOTE:

Use the lower of the Q. values obtained in Sections 3.1.1.2 and 3.1.1.3.

f

=

The maximum acceptable effluent flow rate at the point of release (cfm) based on design flow rates

=

15,500 cfm (Turbine Building Vent)

=

172,800 cfm (Reactor Building Vent)

5.

Determine the monitor high alarm setpoint above background:

a.

Determine CR (the calculated monitor count rate above background attributed to the noble gas radionuclides, net cpm).

CR

=

Ct (3.1-5)

Em Em

=

The detection efficiency of the monitor for the "mix" of noble gas radionuclides in the gaseous effluent (jiC/sec/cfm~cpm) from E&RC files

b.

Determine HSP (the monitor high alarm setpoint with background, cpm).

HSP

=

TmCR + Bkg (3.1-6)

Tm

=

Fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded during simultaneous releases from several pathways

=

0.10 for the Unit 1 Turbine Building Vent Gas Monitor

=

0.10 for the Unit 2 Turbine Building Vent Gas Monitor

=

0.20 for the Unit 1 Reactor Building Vent Gas Monitor

=

0.20 for the Unit 2 Reactor Building Vent Gas Monitor ODCM (BSEP) 3-6 Rev. 25

Bkg

=

The background count rate (cpm) due to internal contamination and the radiation levels in the area in which the monitor is installed when the detector sample chamber is filled with uncontaminated air

c.

The monitor high alarm setpoint including background (cpm) shall be set at or below the HSP value determined above.

3.1.2 Setpoint Based on Conservative Radionuclide Mix (Long-Term Elevated Release The following method applies to gaseous releases via the stack when determining the high-high alarm setpoint for the Stack Monitor during continuous release via the stack.

1.

Determine the "mix" (noble gas radionuclide composition) of the gaseous effluent (the "mix" can be determined from actual data or by using GALE code results of Table 3.1-1):,

a.

Determine the gaseous source terms that are representative of the "mix" of the gaseous effluent. Gaseous source terms are the noble gases radionuclide activity concentrations in the effluent.

Gaseous source teams can be obtained from:

Table 3.1-1; Stack Release Actual Release Data X

b.

Determine S, (the fraction of the total radioactivity in the gaseous effluent comprised by noble gas radionuclide i) for each individual noble gas radionuclide in the gaseous effluent.

S

=

A (3.1-7)

Ai

=

The radioactivity of noble gas radionuclide i in gaseous effluent from Table 3.1-1, Stack Release, or from analysis of gaseous effluent.

2.

Determine Qt (the maximum acceptable total release rate of all noble gas radionuclides in the gaseous effluent, PLCisec) based upon the whole body exposure limit.

If actual plant data is used, the dose constants need to be confirmed.

ODCM (BSEP) 3-7 Rev. 25

500

=

500 (3.1-8)

Vi

=

The constant for noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume (mrem/year/LICVsec) from Table 3.1-2

3.

Determine Qt based upon the skin exposure limit.

Qt

=3000 (3.1-9) l:, [(1(%/Q)s + 1.1B.),](

L,(y/Q)s + 1.1B,

=

The total skin dose constant for long-term releases (greater than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year) due to emissions from noble gas radionuclide i (mrem/year/jiCi/sec) from Table 3.1-2).

NOTE:

The stack radiation monitor is designed to input the monitor high-high alarm setpoint in gCVsec or gCi/cc. The monitor setpoint in jACi/sec can be obtained by multiplying the lowest Ot value (obtained from Sections 3.1.2.2 and 3.1.2.3 by the Tm value found in Section 3.1.2.5.b. The pCVcc setpoint can be obtained by dividing the pCi/sec setpoint by the design flow rate in cc/sec. The equations for calculating the setpoint in cps are included for completeness and may be used if desired.

4.

Determine Ct (the.total maximum acceptable radioactivity concentration of nbble gas radionuclides in the gaseous effluent, jiCVsec/cfm).

C

=

ot (3.1-10) f NOTE:

Use the lowest of the Q. values obtained in Sections 3.1.2.2 and 3.1.2.3.

f

=

The maximum acceptable effluent flow rate at the point of release (cfm) based on design flow rates

=

86,000 cfm (stack)

ODCM (BSEP) 3-8 Rev. 25

5.

Determine the monitor high-high alarm setpoint above background:

a.

Determine the CR (the calculated monitor count rate above background attributed to the noble gas radionuclides, net cpm).

CR

=

Ct (3.1-11)

Em Em

=

The detection efficiency of the monitor for the "mix" of noble gas radionuclides in the gaseous effluent (iCi/sec/cfmocpm) from E&RC files

b.

Determine HHSP (the monitor high-high alarm setpoint with background, cpm).

HHSP TmCR + Bkg (3.1-12)

Tm

=

Fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded during simultaneous releases from several pathways

=

0.40 for the Stack Monitor Bkg

=

The background count rate (cpm) due to internal contamination and the radiation levels in the area in which the monitor is installed when the detector sample chamber is filled with uncontaminated air

c.

The monitor high-high alarm setpoint including background (cpm) shall be set at or below the HHSP value determined above.

ODCM (BSEP) 3-9 Rev. 25

3.1.3 Condenser Air Eiector Monitor Alarm Setpoint This procedure determines the alarm setpoint for the Condenser Air Ejector Monitor that will provide reasonable assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a small fraction of the limits of 1 OCFR1 00 in the event of an inadvertent release via the condenser air ejector.

1.

The following method applies to gaseous releases via the Units 1 and 2 condenser air ejectors when determining the maximum allowable alarm setpoint for the Condenser Off-gas Radiation Monitors.

a.

Determine 0, the allowable release rate ([tCisec) at the air ejector for the noble gas radionuclides.

Technical Specification 3.7.5 limits the gross radioactivity rate of noble gases measured at the main condenser air ejector to less than or equal to 243,600,tCi/sec (after 30 minutes' decay). Assume that the noble gas concentrations at the air ejector (t = 0) are representative of the GALE code. Since the holdup time between the air ejector and the stack (down the 30-minute holdup line) can vary due to operational conditions, the mix of the noble gases at the stack should be determined based on the actual decay time not to exceed 30 minutes.

This mix can then be applied to the 243,600 ACisec limit and then back-calculated to determine the allowable release rate at the air ejector, 0. As an example, assume that the holdup time is 30 minutes. The mix of the noble gases after 30 minutes' decay (t = 30 minutes) can be determined by the following table.

ODCM (BSEP) 3-10 Rev. 25

Nuclide GALE Code Steam (pgCVgm) gCilsec' e-Xt pCisec Fraction Rev.0 t=0 t=0 t=30m t=30m of Mix Steam (guUgm) t = 30m (for 3400 MWt)

(for 2558 MWt)

Kr-83m 1.1E-3 8.28E-4 1.16E+3 8.3E-1 9.57E+2 2.84E-2 Kr-85m 1.9E-3 1.43E-3 2.OOE+3 9.2E-1 1.85E+3 5.49E-2 Kr-85 6.OE-6 4.51 E-6 6.31 E+O 1.OE+0 6.31 E+O 1.87E-4 Kr-87 6.6E-3 4.97E-3 6.94E+3 7.6E-1 5.28E+3 1.57E-1 Kr-88 6.6E-3 4.97E-3 6.94E+3 8.8E-1 6.14E+3 1.82E-1 Kr-89 4.1 E-2 3.08E-2 4.31 E+4 1.4E-3 5.99E+1 1.78E-3 Kr-90 9.OE-2 6.77E-2 9.46E+4 1.7E-17 1.64E-12 4.88E-17 Xe-131m 4.7E-6 3.54E-6 4.94E+0 1.OE+0 4.93E+0 1.47E-4 Xe-1 33m 9.OE-5 6.77E-5 9.46E+1 9.9E-1 9.40E+1 2.79E-3 Xe-133 2.6E-3 1.96E-3 2.73E+3 1.OE+0 2.73E+3 8.1 OE-2 Xe-1 35m 8.4E-3 6.32E-3 8.83E+3 2.6E-1 2.28E+3 6.78E-2 Xe-135 7.2E-3 5.42E-3 7.57E+3 9.6E-1 7.28E+3 2.16E-1 Xe-137 4.7E-2 3.54E-2 4.94E+4 4.4E-3 2.17E+2 6.44E-3 Xe-1 38 2.8E-2 2.11 E-2 2.94E+4 2.3E-1 6.76E+3 2.01 E-1 TOTAL 3.37E+4 1.OOE+O TOTAL 337E+4 1.OO+

Applying this mix to 243,600,uCisec (after 30 minutes' delay) and back calculating to t = 0 will yield the allowable giOUsec per noble gases at the air ejectors; i.e.:

'Steam Flow = (1 1.088 E6 Ibs / hr) (0.26bg / hs

= 1.40E + 6 gm/ sec ODCM (BSEP) 3-11 Rev. 25

Nuclide Fraction of Mix Tech Spec e-Xt Tech Spec t = 30 min (giCi/sec) t = 30 min (liCi/sec) t = 30 min t = 0 Kr-83m 2.84E-2 6.92E+3 8.3E-1 8.37E+3 Kr-85m 5.49E-2 1.34E+4 9.2E-1 1.45E+4 Kr-85 1.87E-4 4.56E+1 1.OE+0 4.56E+1 Kr-87 1.57E-1 3.82E+4 7.6E-1 5.02E+4 Kr-88 1.82E-1 4.44E+4 8.8E-1 5.02E+4 Kr-89 1.78E-3 4.33 E+2 1.4E-3 3.12E+5 Kr-90 4.88E-17 1.19E-11 1.7E-17 6.85E+5 Xe-131m 1.47E-4 3.57E+1 1.OE+0 3.58E+1 Xe-1 33m 2.79E-3 6.80E+2 9.9E-1 6.85E+2 Xe-133 8.1 OE-2 1.97E+4 1.OE+o 1.98E+4 Xe-135m 6.78E-2 1.65E+4 2.6E-1 6.39E+4 Xe-1 35 2.16E-1 5.27E+4 9.6E-1 5.48E+4 Xe-1 37 6.44E-3 1.57E+3 4.4E-3 3.58E+5 Xe-1 38 2.01 E-1 4.89E+4 2.3E-1 2.13E+5 TOTALS 1.OOE+O 2.44E+5 1.83E+6 Therefore:

Q

=-1.83E+6 pCi/sec (for 30 minutes' holdup)

b.

Determine Cm (the total radioactivity concentration of noble gases) in the condenser air ejector gas ([iCVsec/cfm).

Cm Q

f

=

0/f (3.1-13)

=

The allowable release rate (pCi/sec) at the air ejector for-noble gases

=

The main condenser air inleakage rate plus the radiolytic gas flow rate (cfm)

I ODCM (BSEP) 3-12 Rev. 25

c.

Determine the monitor high-high alarm setpoint above background.

(1)

Determine MR (the calculated monitor response attributed to the noble gas radionuclides, mR/hr).

MR

=

Cm (3.1-14)

Em

=

The detection efficiency of the monitor for the "mix" of noble gas radionuclides in the gaseous stream [(,uCi/sec)/(mR/hrecfm)] from E&RC files (2)

The monitor high-high alarm setpoint (mR/hr) should be set at or below the MR value determined above.

3.1.4 Condenser Off-Gas Treatment SVstem (AOG) Monitor Alarm Setpoint Determination This method determines the monitor alarm setpoint that includes sufficient noble gas activity to cause an alarm at the stack effluent noble gas monitor.

1.

Determine Qt (the maximum acceptable total release rate of all noble gas radionuclides in the gaseous effluent, piCi/sec) based upon the whole body exposure (see Equation 3.1-8) and skin exposure (see Equation 3.1-9).

NOTE:

Use the lowest of the Qt values obtained.

2.

Determine Os (the site adjusted maximum release rate, gCVsec, for effluent releases via the stack).

Qs

=

Qt x Tm (3.1-15)

Tm

=

Fraction of radioactivity from the site that may be released via the stack to ensure that the site boundary limit is not exceeded during simultaneous releases from several pathways

=

0.4 for the stack monitor ODCM (BSEP) 3-13 Rev. 25

3.

Determine HSP (high alarm setpoint in tCOi/cc).

HSP

=

Q. f (3.1-16) f

=

Maximum design flow rate of the AOG System

=

70,800 cc/sec (150 cfm)

4.

The monitor high alarm setpoint shall be set at or below the HSP value determined above.

ODCM (BSEP) 3-14 Rev. 25

TABLE 3.1-1 GASEOUS SOURCE TERMS**

(Ci/year/unit)

Turbine Bldg Vent Reactor Bldg Vent Stack Radionuclide A, (Cilyr)

S.

A, (Ci/yr)

S.

A, (Ci/yr)

S.

Kr-83m 3.2E+4 2.78E-2 Kr-85m 6.8E+1 1.97E-2 6.OEO 1.73E-2 6.2E+4 5.40E-2 Kr-85 2.1 E+2 1.83E-4 Kr-87 1.9E+2 5.51 E-2 6.OEO 1.73E-2 1.8E+5 1.57E-1 Kr-88 2.3E+2 6.67E-2 6.OEO 1.73E-2 2.1 E+5 1.83E-1 Kr-89 3.OE+3 2.61 E-3 Xe-131 mn 1.7E+2 1.48E-4 Xe-133m 3.2E+3 2.78E-3 Xe-133 2.8E+2 8.12E-2 1.3E+2 3.75E-1 9.4E+4 8.18E-2 Xe-135m 6.5E+2 1.88E-1 9.2E+1 2.65E-1 7.6E+4 6.61 E-2 Xe-1 35 6.3E+2 1.83E-1 6.8E+1

.1.96E-1 2.5E+5 2.18E-1 Xe-137 8.6E+3 7.48E-3 Xe-138 1.4E+3 4.06E-1 1.4E+1 4.03E-2 2.3E+5 2.OOE-1 Ar-41 2.5E+1 7.20E-2 TOTAL 3.45E+3 3.47E+2 1.1 5E6

< 1.0E-1

- Source terms are based upon GALE code and not actual releases.

ODCM (BSEP) 3-15 Rev. 25

TABLE 3.1-2 DOSE FACTORS AND CONSTANTS Radio Total Whole Body Total Skin Total Body Dose Total Skin Dose Nuclide Dose Factor -

Dose Factor Constant For Constant for (K,)

(L, + 1.1 M,)

Long-Term Long-Term (mrem/yr/pCVm3)

(mrem/yr/tlCVm3)

Releases Releases (V.)

(L,(X/Q),+ 1.1 B.)

(mrem/yr/pCVsec)

(mrem/yr/jgCVsec)

Kr-83m 7.56E-2 2.12E+1 2.93E-9 6.57E-7 Kr-85m 1.17E+3 2.81 E+3 1.22E-4 2.36E-4 Kr-85 1.61 E+1 1.36E+3 1.74E-6 3.64E-5 Kr-87 5.92E+3 1.65E+4 5.39E-4 1.14E-3 Kr-88 1.47E+4 1.91 E+4 1.36E-3 2.31 E-3 Kr-89 1.66E+4 2.91 E+4 9.47E-4 1.81 E-3 Xe-131 m 9.15E+1 6.48E+2 2.96E-5 6.39E-5 Xe-1 33m 2.51 E+2 1.35E+3 2.23E-5 6.58E-5 Xe-1 33 2.94E+2 6.94E+2 2.40E-5 4.95E-5 Xe-i35m 3.12E+3 4.41 E+3 2.94E-4 5.08E-4 Xe-1 35 1.81 E+3 3.97E+3 1.92E-4 3.64E-4 Xe-1 37 1.42E+3 V 1.39E+4 8.47E-5 4.46E:4 Xe-1 38 8.83E+3 1.43E+4 8.60E-4 1.52E-3 Ar-41 8.84E+3 1.29E+4 1.01 E-3 1.73E-3 ODCM (BSEP) 3-16 Rev. 25

3.2 COMPLIANCE WITH 10CFR20 (GASEOUS) 3.2.1 Noble Gases The gaseous effluent monitors' setpoints are utilized to show compliance with 1 OCFR20 for noble gases. However, because they are based upon a conservative mix of radionuclides, the possibility exists that the setpoints could be exceeded and yet 1 OCFR20 limits may not be exceeded. Therefore, the following methodology has been provided in the event that if the alarm/trip setpoints are exceeded, a determination may be made as to whether the actual releases have exceeded 10CFR20.

The dose rate in unrestricted areas resulting from noble gas effluents is limited to 500 mrem/year to the total body and 3000 mrem/year to the skin. Based upon NUREG 0133, the following are used to show compliance with 10CFR20.

~ [V'016

+ Ki(x/Q), Qv ]

500 mrem /yr (3.2-1)

Zi { [L(XQ)s + 1.1B1] Qi + (L + 1.1M,) (zIQ), Qjv } < 3000 mrem/yr (3.2-2) where:

Ki

=

The total body dolse factor due to gamma emissions for noble gas radionuclide i, mrem/year per tCi/rM3 L

=

The skin dose factor due to beta emissions for noble gas radionuclide i, mrem/year per Ci/VM 3 M

=

The air dose factor due to gamma emissions for noble gas radionuclide i, mrad/year per pCi/M3 V1

=

The constant for each identified noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume mrem/year per pCi/sec B.

=

The constant for long-term releases (greater than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year) for each identified noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume in mrad/year per pCilsec ODCM (BSEP) 3-17 Rev. 25

1.1

=

The ratio of the tissue to air absorption coefficients over the energy range of the photon of interest, mrem/mrad Qi

=

The release rate of noble gas radionuclide i in gaseous effluents from free-standing stack, tCi/sec 0,y

=

The release rate of noble gas radionuclide i in gaseous effluents from all vent releases, pCVsec At the Brunswick Steam Electric Plant (BSEP), gaseous releases may occur from:

1.

The Turbine Building vent,

2.

The Reactor Building vent

3.

The stack Releases from the Turbine Building are ground level. The sources of these releases are steam leakage through valve stems, pump seals, and flanged connections. Releases from the Reactor Building are considered mixed mode in nature, and the source is also leakage through valve stems, pump seals, and flanged connections.

Releases from the stack are considered elevated. Their sources are the main condenser's steam jet air ejectors, Radwaste Building and AOG Building ventilation system exhausts, mechanical vacuum pump exhausts during startup, and gland seal off-gases.

Noble gas releases may occur from all three points. To show compliance with 10CFR20, Expressions 3.2-1 and 3.2-2 are now in terms of the actual release points for BSEP.

For the total body dose:

[

/Q)

500 mrem/yr (3.2-3)

'Any effluents due to exfiltration from planned openings in the Turbine Building, Radwaste Building or AOG Building are combined with the Turbine Building's vent releases.

ODCM (BSEP) 3-18 Rev. 25

For the skin dose:

X. [L.(X/Q)s + 11B] QI+ I [Lo + 1.1M,] (X/Q)rb Q,,b+ X/°tb Qb- ]o3000 mrem/yr (3.2-4)

Where:

=

Release rate of radionuclide i from the stack, gC0sec Q'tb atb

=

Release rate of radionuclide i from the two Reactor Buildings, pCVsec

=

Release rate of radionuclide i from the two Turbine Buildings, p0Ci/sec (X I Q)S

=

(X / Q),b =

(x/Q). =

Annual average relative concentration for releases from the stack, sec/M 3 Annual average relative concentration for releases from the Reactor Buildings, sec/M 3 Annual average relative concentration for releases from the Turbine Buildings, sec/M 3 All other terms remain the same as those defined previously.

The determination of controlling location for implementation of 10CFR20 for noble gases is a function of the radionuclide mix, the isotopic release rate, and the meteorology.

The incorporation of these variables into Expressions 3.2-3 and 3.2-4 result in the following expressions for the controlling locations for the BSEP. This location is 0.7 miles, the NE site boundary.

ODCM (BSEP) 3-19 Rev. 25

For the total body:

XV, Q, +,,K. (2.0 x 10-7 QCb + 2.9 x 10-6 0,tb) < 500 mrem/yr (3.2-5)

For the skin:

Y:j (2.5x10-8 L, + 1.1B,)Qs +

(3.2-6)

X, (L + 1.1 M() (2.0 x 1°-7 QUb + 2.9 x 10-6 Qitb )<

3000 mrem / yr The radionuclide mix was based upon source terms calculated using the NRC GALE code. They are presented in Table 3.2-1 as a function of release point. It should be noted, however, that the releases in Table 3.2-1 do not reflect the actual BSEP release data to date. The releases to date have been substantially less. This table was used as a calculational tool to determine the controlling location.

The X/Q values utilized in the equations for implementation of 10CFR20 are based upon the maximum long-term annual average (X / Q} in the unrestricted area. Table 3.2-2 presents the distances from the Reactor and Turbine Buildings to the nearest unrestricted area for each of the 16 sectors as well as to the nearest residence, vegetable garden, cow, goat, and beef animal. Table 3.2-3 presents the distances and directions from the stack to the same site boundaries of Table 3.2-2. Note that only distance has changed in relation to Table 3.2-2.

Long-term annual (X/Q) values for the stack, Reactor Building, and Turbine Building release points from BSEP to the special locations in Table 3.2-2 are presented in Appendix A. A description of the derivation is also provided in this appendix.

1/Q values at the limiting site boundary for releases from the Turbine Building, Reactor Building, and stack were obtained from Tables A-1, A-7, and A-13, respectively, of the appendix.

To determine the controlling location for implementation of 1 OCFR20, the two or three highest site boundary X/Q values for each release point were utilized in conjunction with the radionuclide mix and release rate for each release point. Since mixed mode and elevated releases occur from BSEP, their maximum X/Q value may not decrease with distance; i.e., the site boundary may not have the ODCM (BSEP) 3-20 Rev. 25

highest X/Q values. Therefore, long-term annual average X/Q values were calculated at the midpoint of the 10 standard distances as given in Table A-4 of Appendix A. The highest two or three X/Q values for each release point at a distance greater than the site boundary were used in conjunction with the radionuclide mix to determine the controlling location. A particular combination of release point mix and meteorology dominates in the determination of the controlling location. For BSEP, it is the stack, and the dominant factor in determining a control location becomes the VI values. The controlling location is at the NE at the site boundary due to its higher V1 values.

Values for K1, Li, and M, which were used in the determination of the controlling locations and which are to be used by BSEP in Expressions 3.2-5 and 3.2-6 to show compliance with 1 OCFR20, are presented in Table 3.2-4. These values originate from NUREG 0472, Revision 0, and were taken from Table B-1 of the NRC Regulatory Guide 1.109, Revision 1. The values have been multiplied by 10 to convert picocuries 1 to microcuries' for use in Expressions 3.2-5 and 3.2-6.

Values for V, and Bi for the finite plume model can be expressed as shown in Equations 3.2-7 and 3.2-8. They were calculated at the site boundary of each of the 16 sectors using the NRC code RABFIN.

Values for V1 and B. for each of the 16 sectors are presented in Appendix B.

B

=

K X f k AX Ma E11 (3.2-7) rd i

.=

The results of numerical integration over the plume spatial distribution of the airborne activity as defined by the meteorological condition of wind speed (ij) and atmospheric stability class "K" for a particular wind direction K

=

A numerical constant representing unit conversions 260 mrad (radians)(m 3)(transformation) x 16 sectors x sec(Mev)(Ci) 2A radians 106 Ci 3.15 x 10 7 sec ACi yr

=

2.1 x 104 mrad (M3) (transformation} /year (Mev) ([iOi)

ODCM (BSEP) 3-21 Rev. 25

rd

=

The distance from the release point to the receptor location, meters A =

The mean wind speed assigned to the jth wind speed class, meters/sec fik

=

The joint frequency of occurrence of the jth wind speed class and the kth stability class (dimensionless)

Al

=

The number of photons of energy corresponding to the Ith energy group emitted per transformation of the ith radionuclide, number/transformation E

=

The energy assigned to the Ith energy group, MeV pa

=

The energy absorption coefficient in air for photon energy El, meters-The V; factor is computed with conversion from air dose to tissue depth dose, thus; V1

=

1.1 K/rd XxZj fk All Pa EIl e" TTd (3.2-8)

Where:

-IT The tissue energy absorption coefficient for photons of energy El, cm'/gm Td

=

The tissue densitjlthickness taken to represent the total body dose (5 gm/cm2) 1.1

=

The ratio of the tissue to air absorption coefficients over the energy range of photons of interest, mrem/mrad ODCM (BSEP) 3-22 Rev. 25

3.2.2 1-131, 1-133. Particulates, and Tritium*

The dose rate in unrestricted areas resulting from the release of radioiodines 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.

z1 Pi (WsQ1s + WVQjV) < 1500 mrem/ yr (3.2-9)

Where:

P.

=

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

=

mrem/year per ACi/m 3 for inhalation pathways and for tritium

=

mrem/year per IiCi/sec per m-2 for food and ground plane pathways OS

=

The release rate of radionuclide i in gaseous effluents from free-standing stack, pCi/sec QV

=

The release rate of radionuclide i in gaseous effluents from all vents releases, LCi/sec WV The highest calcdlated annual average dispersion parameter for estimating the dose to an individual at the controlling location due to all vent releases

=

sec/m 3 for the inhalation pathway

=

meters 2 for the food and ground plane pathways

For ODCM calculations performed to comply with ODCM TRs 7.3.7.2 and 7.3.9.1, the 1-133 values used are determined by actual analysis.

ODCM (BSEP) 3-23 Rev. 25

Ws The highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location due to stack releases sec/M 3 for the inhalation pathway meters 2 for the food and ground plane pathways Radioiodines, particulates, and tritium may be released from the stack, Reactor Buildings, and Turbine Buildings at BSEP.

Radioiodines and particulates may also be released from other sources such as decontamination, waste processing, and burning of waste oil in the incinerator. Effluents from the decontamination and waste processing facilities in the Radioactive Materials Container and Storage Building, Low Level Warehouse, and hot shop, incinerator -

and any building exfiltration 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:

+ WibQ[rb+ wthQ122 )

1500 mrem/ yr (3.2-10)

Where:

Ws Wrb W

The annual average dispersion parameter for the stack

=

The annual averagg-,dispersion parameter for the Reactor Buildings

=

Annual average dispersion parameter for the Turbine Buildings Ith

=

Release of radionuclide i from the two Reactor Buildings, JtCVsec

=

Release of radionuclide i from the two Turbine Buildings, IiCi/sec REP) 3-24 Rev. 26 l

ODCM (BS

1Ss

=

~

Release of radionuclide i from the stack, giCi/sec All other terms are the same as those defined previously.

In the calculation to show compliance with 1 OCFR20, only the inhalation, ground plane, cow milk, and goat milk pathways are considered for BSEP. In determining the dose at a particular location, W is a function of pathway. For the food and ground plane pathways, W is in terms of D/Q (i.e., deposition). If the inhalation pathway is considered, W is in terms of X/Q. Incorporation of the various pathways into Expression 3.2-10 results in the following:

YE,Pl (X / Q)S' QIS + (X/Q)l, QO

+ (X/Q)btb Q

+h I ( IG + riM)

(3.2-11)

[

(D/Q)s Q 1 S + (D / Q), Q b + (D / Q),b Qb ] < 1500 mrem/yr Where:

PiG iM

=

Dose parameter for radionuclide i for the inhalation pathway, mrem/year per pCisec3

=

Dose parameter for radionuclide i for the ground plane pathway, mrem/year per gQi/sec per M-2

=

Dose parameter for radionuclide i for either the cow milk or goat milk pathway, mrem/year per pCi/sec per m 2 (X / Q)rb =

(X / Q)tb=

Annual average relative concentrations for releases from the Reactor Buildings, sec/M3 Annual average relative concentrations for releases from the Turbine Buildings, sec/m3 (x / Q)5 =

Annual average relative concentrations for releases from the stack, sec/M 3 ODCM (BSEP) 3-25 Rev. 25

(D/Q)%, =

(D/Q),b =

(D/Q)s =

Annual average deposition for releases from the Reactor Buildings, mr2 2

Annual average deposition for releases from the Turbine Buildings, m Annual average deposition for releases from the stack, m-2 In the case of tritium, the W parameter for the food pathway (cow or goat milk) is based upon x/Q. Since tritium is a weak beta emitter, the ground plane contribution is zero for tritium. Therefore, the left-hand side of Expression 3.2-10 can be written as the following:

For tritium:

DT

=

(PTI + PTM)[(XIQ)S QTS + (X/Q),h CTrb + (X/Q). Q Tt (3.2-12)

Where:

DT

=

Dose rate due to tritium releases, mrem/year PT I TM aTS 0 Trb QTtb

=

Dose parameter for tritium for the inhalation pathway, mrem/year per pCVm3

=

Dose parameter for tritium for the milk pathway, mrem/year per jiCL 3

=

Release rate of tritium from the stack, GCVsec

=

Release rate of tritium from the two Reactor Buildings, ttCiVsec

=

Release rate of tritium from the two Turbine Buildings, jiCVsec ODCM (BSEP) 3-26 Rev. 25

Since Pi, for tritium equals 647 and PiM equals 2380, Equation 3.2-12 reduces to:

DT 3.0 x 103 (x /Q)X QT5 + (X/CQ),b QTrb + (X/Q),b QTtb (3.2-13)

To show compliance with 1 OCFR20, Expressions 3.2-1 1 and 3.2-13 are evaluated first at the limiting site boundary. It should be noted that the sum of the dose rates from radioiodines and particulates and from tritium must be summed and their combined dose rates be less than 1500 mremlyear to show compliance with 10CFR20. If the 1500 mrem/year limit is exceeded at the limiting site boundary when all pathways are considered present at the site boundary but the inhalation pathway contributes less than 1500 mrem/year, then Expressions 3.2-11 and 3.2-13 are evaluated at the limiting real pathway location. The limiting site boundary location is 0.7 miles NE.

Expression 3.2-11 becomes:

For radioiodines and particulates:

X1, Pi, (2.5x 10-8 Qis

+ 2.0 x 10-7 Q0,.

+ 2.9x 10-6 Qtb) +

Xi(PiG + pM)(1.4x10-9 Q5 + 4.3x10-9 0 b+ 1.9x10 8 Qatb )<1500mrem/yr (3.2-14)

For BSEP, the limiting "hypothetical" teal pathway location is the cow milk pathway 4.75 miles NE. At this location, Expression 3.2-11 becomes:

x, P 1(2.4 x 10-8 Qj5

+ 4.1 x 10-8 Q,,b

+ 1.4 x 10-7 Qtb ) + Zi (P;G + PIM)

(2.2x 10 1-0 Q's

+ 2.7x 10-'° Q,,b

+ 5.7x 10-'° Q~tb) <1500 mrem/yr (3.2-15)

ODCM (BSEP) 3-27 Rev. 25

For tritium, at the limiting site boundary, Equation 3.2-13 becomes:

For tritium:

IDT

=

3.0 X 103 (2.5 X 1 0r 0TS + 2.0 x 10- Q Trb + 2.9 X 1 0 6T)

(3.2-16)

At the "hypothetical" limiting real pathway location, Equation 3.2-13 becomes:

For tritium:

DT 3.0 X 10 3 (2.4 x 10-8 Q TS + 4.1 xl10-8 Q Tb + 1.4 X 10-7 Q Tt)

(3.2-17)

The determination of controlling location for implementation of 10CFR20 for radioiodines and particulates is a function of the same two parameters as for noble gases plus a third receptor pathway location. The radionuclide mix was again based upon the source terms calculated using the GALE code. The mix and the source terms are presented in Table 3.2-1 as a function of release point.

In the determination of the controlling site boundary location, the highest two or three site boundary X/Q and D/Q values for each release point were utilized in conjunction with the radionuclide mix and the release ra~te for each release point. At BSEP, the release rate which dominates comes from the stack. The higher values for X/Q and D/Q for the NE sector at the site boundary make it the dominant meteorological sector and the control location.

In the determination of receptor controlling location, the highest two or three D/Q values from each release point to the pathway locations of Table 3.2-2 are utilized in conjunction with the radionuclide mix and release rate for each release point. For BSEP, the controlling location is a hypothetical cow milk pathway 4.75 miles NE of the Reactor Building and Turbine Buildings.

ODCM (BSEP) 3-28 Rev. 25

Values for Pi were calculated for an infant for various radionuclides for the inhalation, ground plane, cow milk, and goat milk pathways using the methodology of NUREG 0133. The Pi values are presented in Table 3.2-5. The values of Pi reflect, for each radionuclide, the maximum organ dose factor for each individual pathway of exposure.

Because the goat milk pathway is not present at BSEP, the cow milk pathway P. values were utilized in the determination of the various controlling locations. For the case of an infant being present at the site boundary or at the real pathway location, the ground plane pathway is not considered as a reasonable exposure pathway for the infant (i.e., PG = 0). However, Pi values are presented in Table 3.2-5 for completeness. Appendix C presents the methodology which was utilized in calculating P. values.

Annual average D/Q values at the special locations for the stack, Reactor Building, and Turbine Building release points, respectively, which were utilized in Expressions 3.2-14 through 3.2-17 were obtained from the tables presented in Appendix A. The X/Q values in Expressions 3.2-14 through 3.2-17 were also obtained from the tables presented in Appendix A. D/Q values at the limiting site boundary location and the limiting real pathway location for releases from the Turbine Buildings, the Reactor Buildings, and the stack were obtained from Tables A-3, A-9, and A-15, respectively, of Appendix A.

X/Q values at these same locations for these same release points were obtained from Tables A-1, A-7, and A-13 of Appendix A. A description of the derivation of the X/Q and D/Q values is provided in Appendix A.

V ODCM (BSEP) 3-29 Rev. 25

TABLE 3.2-1 RELEASES FROM BRUNSWICK STEAM ELECTRIC PLANT' (CVyr per unit)

Isotope Turbine Building Reactor Building Stack (Ground Level)

(Mixed Mode)

(Elevated)

Kr-83m 0

0 3.2E4 Kr-85m 6.8E1 6.0EO 6.2E4 Kr-85 0

0 2.1 E2 Kr-87 1.9E2 6.0EO 1.8E5 Kr-88 2.3E2 6.0EO 2.1 E5 Kr-89 0

0 3.0E3 Xe-131 m 0

0 1.7E2 Xe-1 33m 0

0 3.2E3 Xe-133 2.8E2 1.3E2 9.424 Xe-1 35m 6.5E2 9.221 7.6E4 Xe-1 35 6.3E2 6.8E1 2.5E5 Xe-1 37 0

0 8.6E3 Xe-138 1.4E3 1.4E1 2.3E5 Ar-41 0

2.5E1 0

1-131 1.9E-2 3.4E-1 5.1 1-133 7.6E-2 1.4 2.1 El Cr-51 1.3E-4 6.0E-4 9.0E-3 Mn-54 6.0E-6 6.0E-3 3.6E-2 Fe-59 5.0E-6 \\

8.0E-4 1.5E-2 Co-58 6.0E-6 1.2E-3 4.5E-3 Co-60 2.OE-5 2.0E-2 9.OE-2 Zn-65 2.0E-6 4.0E-3 1.OE-3 Sr-89 6.OE-5 1.8E-4 5.OE-4 Sr-90 2.0E-7 1.OE-5 3.0E-4 Zr-95 1.OE-6 8.0E-4 5.0E-5 Sb-1 24 3.0E-6 4.0E-4 5.0E-5 Cs-1 34 3.0E-6 8.0E-3 4.5E-3 Cs-1 36 5.0E-7 6.0E-4 4.5E-4 Cs-137 6.0E-6 1.1 E-2 9.0E-3 Ba-140 1.1 E-4 8.0E-4 1.OE-4 Ce-1 41 6.0E-6 2.0E-4 2.6E-3 C-14 0

0 9.5 H-3 0

3.0E1 0

Calculations based upon GALE code and not actual releases.

ODCM (BSEP) 3-30 Rev. 25

TABLE 3.2-2 DISTANCE TO CONTROLLING LOCATIONS AS MEASURED FROM THE BRUNSWICK PLANT CENTER (Mi)

NNE 0.7 0.8 1.2 NE 0.7 4.75*

ENE 0.7 E

0.7 ESE 0.7 1.5 SE 0.7 0.9 SSE 0.7 1.0 S

0.8 1.1 1.8 SSW 0.8 1.2 1.6 SW 0.7 1.0 1.5 WSW 0.7 1.2 1.2 W

0.7 0.8 0.8 WNW 0.6 X

0.8 1.0 NW 0.6 0.9 4.8 NNW 0.6 0.8 4.4 N

0.7 0.7 0.9

[

I

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

ODCM (BSEP) 3-31 Rev. 26 l.

TABLE 3.2-3 DISTANCE TO SITE BOUNDARIES BASED UPON BRUNSWICK PLANT CENTER AND DIRECTIONS FROM THE STACK J

Based on Center of Brunswick Plant Direction Site Boundary Distance (Mi)

NNE 0.7 NE 0.7 ENE 0.7 E

0.7 ESE 0.7 SE 0.7 SSE 0.7 S

0.8 SSW 0.8 SW 0.7 WSW 0.7 W

0.7 WNW 0.6 NW 0.6 NNW 0.6 N

0.7 From Stack to Site Boundaries of Table 3.2-2 Direction Distance (Mi)

NNE 0.7 NE 0.7 ENE 0.7 E

0.6 ESE 0.6 SE 0.6 SSE 0.6 S

0.6 SSW 0.7 SW 0.7 WSW 0.7 W

0.8 WNW 0.7 NW 0.7 NNW 0.7 N

0.8 ODCM (BSEP) 3-32 Rev. 25

TABLE 3.2-4 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS*

Total Body Skin Gamma Air Beta Air

- Radionuclide Dose Factor Dose Factor Dose Factor Dose Factor Ki L,

M1 N.

(mrem/yr per (mrem/yr per (mradlyr per (mrad/yr per pCVm3 )

PCiVm 3 )

iCVm3) gCVM3)

Kr-83m 7.56E-02**

1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61 E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01 E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131 m 9.15E+01 4.76E+02 1.56E+02 1.11 E+03 Xe-133m 2.51 E+02 9.94E+02 3.27E+02 1.48E+03 Xe-1 33 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11 E+02 3.36E+03 7.39E+02 Xe-1 35 1.81 E+03 1.86E+03 1.92E+03 2.46E+03 Xe-1 37 1.42E+03 1.22E+04 1.51 E+03 1.27E+04 Xe-1 38 8.83E+03 4.13E+03 9.21 E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

The listed dose factors are for radionuclides that may be detected in gaseous effluents.

- 7.56E-02 = 7.56 x 1 o2 ODCM (BSEP) 3-33 Rev. 25

TABLE 3.2-5 PI VALUES FOR AN INFANT FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

Isotope Inhalation Ground Plane Cow Milk Goat Milk H-3 6.47E2 0

2.38E3 4.86E3 P-32 2.03E6 0

1.60E1 1 1.93E1 1 Cr-51 1.28E4 6.67E6 4.79E6 5.65E5 Mn-54 1.OOE6 1.09E9 3.89E7 4.68E6 Fe-59 1.02E6 3.92E8 3.93E8 5.11 E6 Co-58 7.77E5 5.29E8 6.06E7 7.28E6 Co-60 4.51 E6 4.40E9 2.1 OE8 2.52E7 Zn-65 6.47E5 6.89E8 1.90E10 2.29E9 Rb-86 1.90E5 1.28E7 2.22E10 2.67E9 Sr-89 2.03E6 3.16E4 1.27E10 2.66E10 Sr-90 4.09E7 1.21 El 1 2.55E1 1 Y-91 2.45E6 1.52E6 5.26E6 6.32E5 Zr-95 1.75E6 3.48E8 8.28E5 9.95E4 Nb-95 4.79E5 1.95E8 2.06E8 2.48E7 Ru-103 5.52E5 1.55E8 1.05E5 1.27E4 Ru-106 1.16E7 2.99E8 1.44E6 1.73E5 Ag-1 Om 3.67E6 3.14E9 1.46E10 1.75E9 Sn-113 2.30E5 5.19E7 2.25E7 2.25E6 Te-127m 1.31 E6 t 1.18E5 1.04E9 1.24E8 Te-129m 1.68E6 2.86E7 1.40E9 1.68E8 Cs-134 7.03E5 2.81 E9 6.79E10 2.04E11 Cs-136 1.35E5 2.13E8 5.76E9 1.73E10 Cs-137 6.12E5 1.15E9 6.02E10 1.81 E11 Ba-140 1.60E6 2.94E7 2.41 E8 2.89E7 Ce-141 5.17E5 1.98E7 1.37E7 1.65E6 Ce-144 9.84E6 5.84E7 1.33E8 1.60E7 1-131 1.48E7 2.46E7 1.06E12 1.27E12 1-132 1.69E5 1.78E6 1.39E2 1.64E2 1-133 3.56E6 3.54E6 9.80E9 1.18E10 1-135 6.96E5 3.67E6 2.27E7 2.68E7 Hf-1 81 6.73E5 4.02E8 6.55E5 7.86E4 Am-241 4.41 E5 4.96E7 6.01 E7 7.21 E6

Units are mrem/yr per piCVm 3 for H-3 and the inhalation pathway and mrem/yr per p/CUsec per m 2 for the food and ground plane pathways.

ODCM (BSEP) 3-34 Rev. 25

3.3 COMPLIANCE WITH 10CFR50 (GASEOUS) 3.3.1 Noble Gases

1.

Cumulation of DosesSection II.B.1 of Appendix I of 1 OCFR50 limits the releases of gaseous effluents from each reactor such that the estimated annual gamma air dose is limited to 10 millirad and the beta air dose is limited to 20 millirad. Based upon NUREG 0133, the air dose in the unrestricted area due to noble gases released in gaseous effluents can be determined by the following expressions:

During any calendar quarter, for gamma radiation:

3.17x10-8 I {M, [(/Q) Q + (X/q)v

] + BQ,, + bhq } < 5mrad (3.3-1)

During any calendar quarter, for beta radiation:

3.17x104 ZiN, [ (x/Q), 0Q

+ (X/q)v q + (X/Q), QOS + (XIq)s qs ] < 10mrad (3.3-2)

During any calendar year, for gamma radiation:

3.17x10 8XIMl[(X/Q)IQV

+Q. /q) qX ] + BIQq + Ws I < 10 mrad (3.3-3)

During any calendar year, for beta radiation:

3.17 x 10 I N. [ (XIQ), O,, + (X/q)v qy + (xIQ)s QoS + (XIq)s qs ] < 20 mrad (3.3-4)

Where:

M The air dose factor due to gamma emissions for each identified noble gas radionuclide i, mrad/year per piCilm 3 N,

=

The air dose factor due to beta emissions for each identified noble gas radionuclide i, mrad/year per pCimi3 (XI Q) =

The annual average relative concentration for areas at or beyond the unrestricted area boundary for long-term vent releases (greater than 500 hrs/year), sec/m3 ODCM (BSEP) 3-35 Rev. 25

(X/q)v =

The relative concentration for areas at or beyond the unrestricted area boundary for short-term vent releases (equal to or less than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), sec/M 3 (x /Q)S =

The annual average relative concentration for areas at or beyond the unrestricted area boundary for long-term, free-standing stack releases (greater than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), secIM3 (X/ q) =

The relative concentration for areas at or beyond the unrestricted area boundary for short-term, free-standing stack releases (equal to or less than 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months year), sec/M 3 q

-S The average release of noble gas radionuclide i in gaseous effluents for short-term stack releases (equal to or less than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year),

gCi q

-v The average release of noble gas radionuclide i in gaseous effluents for short-term vent releases (equal to or less than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year),

pCi QS

=

The average release of noble gas radionuclide i in gaseous effluents for long-term, free-standing stack releases (greater than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), [0Ci Qv

=

The average release of noble gas radionuclide i in gaseous effluents for long-term venrpeleases (greater than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), pCi B1

=

The constant for long-term releases (greater than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year) for each identified noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume, mrad/year per pCi/sec b

=

The constant for short-term releases (equal to or less than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year) for each identified noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume, mrad/year per pCi/sec 3.17 x 10.8 =

The inverse of the number of seconds in a year For BSEP all releases are considered long-term. The incorporation of the stack, Reactor Building, and Turbine Building release points into Expressions 3.3-1 through 3.3-4 results in the following expressions for two units to show compliance with 1 OCFR5O.

ODCM (BSEP) 3-36 Rev. 25

During any calendar quarter or year:

Gamma radiation:

3.17x10 8 I I {M, [(X/Q)rb(Q01bl

+ Q0S

2) + (X/Q)tb (0Qt 1

+ Q~t2)] + B1QO. }

10 mrad per quarter or 20 mrad per year (3.3-5)

Beta radiation:

3.17 x 10- X, N. [ (X / Q)rb (Qlrbt +

QO'2) + (X/ Q)tb (Q0 1

+ Q'tb2) + (X

)S Q'S ]

< 20 mrad per quarter or 40 mrad per year (3.3-6)

Where:

(X / Q)1 b =

Annual average relative concentration for releases from the Reactor Building, sec/m3 Annual average relative concentration for releases from the Turbine Building, sec/m3

=

(Q / Q)S =

Qirbi '

irb2 Q Iti 0

tb2 Annual average relative concentration for releases from the stack, sec/in 3 Release of radionuclide i from Reactor Buildings 1 and 2, respectively, Release of radionuclide i from Turbine Buildings 1 and 2, respectively, gCi

=

Release of radionuclide i from the stack, gLCi At BSEP, the limiting location for noble gases is 0.7 miles NE.

Substitution of the appropriate xJQ values into Expressions 3.3-5 and 3.3-6 results in the following:

ODCM (BSEP) 3-37 Rev. 25

During any calendar quarter or year:

Gamma radiation:

3.17 x 108 Zi { M, [2.0 x 107 (Q bl +

0 rb2 ) + 2.9 x 106 (0itb1 + Qitb2)] + BIQs }

< 10 mrad per quarter or 20 mrad per year (3.3-7)

Beta radiation:

3.17 x 108 X, N, [2.0 x 107 (Qrb1 +

ib2) + 2.9 x 10-(Q~t

+ Q'tb2) + 2.5 X10 is]

< 20 mrad per quarter or 40 mrad per year (3.3-8)

The determination of the controlling locations for implementation of 10CFR50 is a function of parameters such as radionuclide mix, isotopic release, and meteorology.

The incorporation of these parameters into Expressions 3.3-1 through 3.3-4 resulted in the expressions for the controlling locations as presented in Expressions 3.3-7 and 3.3-8. The radionuclide mix was based upon source terms calculated using the NRC GALE Code and is presented in Table 3.2-1 as a function of release point.

The two or three highest site boundary (X / Q) values for each release point were utilized in conjunction with the radionuclide mix and release for each release point to determine the controlling site boundary location. Since mixed mode and elevated releases occur from 6SEP and their maximum X/Q values may not decrease with distance (i.e.,

the site boundary may not have the highest X/Q values); XIQ values were calculated at the midpoint of 10 standard distance intervals out to a distance of 5 miles. The two or three highest X/Q values were considered in conjunction with the radionuclide mix and releases to determine the controlling location.

In the determination of the controlling location, annual average X/Q values are utilized. These values are presented in tables in Appendix A. X/Q values at the limiting site boundary location for releases from the Turbine Buildings, Reactor Buildings, and stack were obtained from Tables A-1, A-7, and A-1 3, respectively, of Appendix A. A description of the derivation of X/Q values is also presented in Appendix A.

ODCM (BSEP) 3-38 Rev. 25

A particular combination of release point mix and meteorology dominates in the determination of the controlling location. For BSEP the controlling release point is the stack. The dominate factor in determining a control location becomes the Bi values. The NE sector at the site boundary is the control location because of its higher Bi values.

Values for Mi and N1, which were used in the determination of the controlling location and which are to be used by BSEP in Expressions 3.3-7 and 3.3-8 to show compliance with 1 OCFR50 were presented in Table 3.2-4. These values originate from NUREG 0472, Revision 0, and were taken from Table B-1 of NRC Regulatory Guide 1.109, Revision 1. The values have been multiplied by 1 06 to convert from picocuries to microcuries.

The following relationship should hold for BSEP to show compliance with ODCM Specification 7.3.8.

For the calendar quarter:

Dy*< 10mrad (3.3-9)

Do < 20mrad (3.3-10)

For the calendar year:

Dy < 20mrad (3.3-11)

D3 < 40mrad (3.3-12)

Where:

Dy

=

The air dose from gamma radiation, mrad D

=

The air dose from beta radiation, mrad 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.

ODCM (BSEP) 3-39 Rev. 25

3.3.2 1-131, 1-133, Particulates. and Tritium'

1.

Cumulation of Doses Section I1.C of Appendix I of 10CFR50 limits the release of radioiodines 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 mrem to any organ. Based upon NUREG 0133, the dose to an organ of an individual from radioiodines and particulates, with half-lives greater than 8 days in gaseous effluents released to unrestricted areas, can be determined by the following expression:

During any calendar quarter or year:

3.17x 10-8x j Ri (WsQs + w5q,5 + WvQv5 + wvqlv)

(3.3-13)

< 7.5 mrem per quarter or 15 mrem per calendar year Where:

Q05

=

Release of radionuclide i for long-term, free-standing stack releases (greater than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), ptCi Q.)

Release of radionuclide i for long-term vent releases (greater than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), jgCi Release of radionUblide i for short-term, free-standing stack releases (equal to or less than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), gCi q

-V Release of radionuclide i for short-term vent releases (equal to or less than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), piCi Ws

=

Dispersion parameter for estimating dose to an individual at the controlling location for long-term, free-standing stack releases (greater than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year)

=

sec/m 3 for the inhalation pathway and tritium

=

meters 2for the food and ground plane pathway

'For ODCM calculations performed to comply with ODCM TRs 7.3.7.2 and 7.3.9.1, the 1-133 values used are determined by actual analysis.

ODCM (BSEP) 3-40 Rev. 25

WV

=

The dispersion parameter for estimating the dose to an individual at the controlling location for long-term vent releases (greater than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year)

=

sec/M3 for the inhalation pathway and tritium

=

meters 2 for the food and ground plane pathway Ws

=

Dispersion parameter for estimating the dose to an individual at the controlling location for short-term stack releases (equal to or less than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year)

=

sec/m 3 for the inhalation pathway and tritium

=

meterrs 2 for the food and ground plane pathway WV

=

The dispersion parameter for estimating the dose to an individual at the controlling location for short-term vent releases (equal to or less than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year)

=

sec/M 3 for the inhalation pathway and tritium

=

meters 2 for the food and ground plane pathway 3.17 x 108 =

The inverse of the number of seconds in a year Ri

=

The dose factor for each identified radionuclide i of the organ of interest, mrem/yr per [OCi/sec per m 2 or mrem/yr per p.CVm3 Radioiodines, particulates, and tritium may be released from the stack, Reactor Buildings, and Turbine Buildings at BSEP.

Radioiodines and particulates, may also be released from other sources such as decontamination facility in the Hot Shop and burning of waste oil in the incinerator. Effluents from the decontamination facilities in the Radioactive Materials Container and Storage Building and hot shop, incinerator and any building exfiltration are combined with the Turbine Building's vent releases. Burning waste oil in the incinerator is limited to 0.1% of 10CFR50 Appendix I (see Appendix H for methodology and calculations). At BSEP all releases 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 1 OCFR50 for a particular organ:

3.17 x 10- ZX RI [WSQlS + Wb (Arbl + Qrb2 ) + Wib (P

+ QOitb2 )]

(3.3-14)

< 15.0 mrem per quarter or 30 mrem per year ODCM (BSEP) 3-41 Rev. 25

Where:

Ws Wrb Wtb QI5

=

Dispersion parameter for releases from the stack

=

Dispersion parameter for releases from the Reactor Building

=

Dispersion parameter for releases from the Turbine Building

=

Release of radionuclide i from the stack, OtCi Q IV'Q Ib2=

Irbl X

I rb2 Istbi '

i tb2 Release of radionuclide i from Reactor Buildings 1 and 2, respectively, gCi Release of radionuclide i from Turbine Buildings 1 and 2, respectively, ici In determining the dose at a particular location, W (as in Section 3.2.2) is a function of the pathway. For the food and ground plane pathway, W is in terms of D/Q. If the inhalation pathway is considered, W is in terms of X/Q. Incorporation of the various pathways into Expression 3.3-14 results in the following:

3.17 x 10-8 xi

{(R.G +R5

+RIV +RB) [(D/ Q)s~o1 + (D/Q) (Q irb +Q ib2) + (D/Q)tb(Qitbl +Q'tb 2 )]+

RI [(x/Q)5Qi5 +

+Qlrb2)

+ (X/O)tb(Qitb1 +Qilb2)]}

< 15 mrem (per quarter) or 30 mrer&r(per year)

(3.3-15)

Where:

RIG

=

Dose factor for an organ for radionuclide i for the ground plane exposure pathway, mrem/yr per piCVsec per m 2

=

Dose factor for an organ for radionuclide i for either the cow milk or goat milk pathway, mrem/yr per g.CUsec per m 2 ODCM (BSEP) 3-42 Rev. 25

RIv

=

Dose factor for an organ for radionuclide i for the vegetable pathway, mrem/yr per gCisec per m 2 R

=

Dose factor for an organ for radionuclide i for the meat pathway.

mrem/yr per ttCi/sec per m-2 Rq

=

Dose factor for an organ for radionuclide i for the inhalation pathway, mrem/yr per pCVM3 (D / Q)rb

=

Annual averagp deposition for releases from the Reactor Buildings, m 2 (D / Q0)b

=

Annual average deposition for releases from the Turbine Buildings, mr2 (D / Q)5

=

Annual average deposition for releases from the stack, m 2 As discussed in Section 3.2.2, for tritium the parameter W for the food pathway is based upon X/Q. The ground plane pathway is not appropriate for tritium. Therefore, the left-hand portion of Expression 3.3-15 may be modified for tritium as:

For tritium:

3.17 x 10 (RTM +RTV +RTB + RTI)

(3.31 6 D (% /

=)( OTs + (X /Q)rIb(QTrbl + 0Tb2) + (X/Q)t(QTt 1 + QTtb2)]

Where:

DT

=

Dose resulting from tritium, mrem RTM

=

Dose factor for an organ for tritium for the milk pathway, mrem/yr per pCVm3 ODCM (BSEP) 3-43 Rev. 25

RTV

=

Dose factor for an organ for tritium for the vegetable pathway, mremnyr per PLCUM 3 RTB

=

Dose factor for an organ for tritium for the beef pathway, mrem/yr per jLCVM 3 RT 1

=

Dose factor for an organ for tritium for the inhalation pathway, mrem/yr per PiCUm 3 QTS

=

Release of tritium from the stack, [iCi aTV 0TQb2 =

Release of tritium from Reactor Buildings 1 and 2, respectively, giCi aTtb, QTtb2 =

Release of tritium from Turbine Buildings 1 and 2, respectively, iiCi To show compliance with 1 OCFR50, Expression 3.3-15 is evaluated at the controlling pathway location. At BSEP the controlling location is a milk cow 4.75 miles in the NE sector. Expression 3.3-15 becomes:

3.17 x 10o-8 X

{(RIG + Rm) [2-2 x 10-' Q,

+ 2.7 x 1 0 (Q 1 +l

+ 5.7 x)1 10(Qt 1 +Q1t 2)]+

R,1 [2.4x10-8 Qi5 + 4.1x10-8 (Q 1+Qb 2 ) + 1-4x10 (Qitbl + Qib2)'1

< 15 mrem / quarter or 30 mrem / year (3.3-17)

For tritium, Equation 3.3-16 reduces to:

DT = 3.1 7x1 0 (RTM + RT, )[2.4x1 - 0QTS + 4.1 x10 8 (OTfbl + QTeb2 ) + 1.4x1 0 (QTthb

+ QTtb2 )]

(3.3-18)

ODCM (BSEP) 3-44 Rev. 25

The determination of a controlling location for implementation of 1 OCFR50 for radioiodines and particulates is a function of:

a.

Radionuclide mix and isotopic release

b.

Meteorology

c.

Exposure pathway

d.

Receptor's age The incorporation of these parameters into Expression 3.3-14 results in the respective equations at the controlling location.

In the determination of the controlling location, the radionuclide mix of radioiodines and particulates was based upon the source terms calculated using the GALE code. This mix was presented in Table 3.2-1 as a function of release point.

In the determination of the controlling location, all of the exposure pathways, as presented in Table 3.2-2, were evaluated. These include cow milk, goat milk, beef and vegetable ingestion, and inhalation ground plane exposure. An infant was assumed to be present at all milk pathway locations. A child was assumed to be present at all vegetable garden and beef animal locations. The ground plane exposure pathway was only considered to be present where an infant was not present. Naturally, inhalation was present everywhere an inctividual was present.

For the determination of the controlling location, the highest D/Q values for each release point and release mode for the vegetable garden, cow milk, and goat milk pathways were selected. At BSEP, no cow milk or goat milk pathways are present. In accordance with NUREG 0133, dose to a "hypothetical" cow milk pathway located 4.75 miles NE was evaluated against existing vegetable garden pathways. The thyroid dose was calculated at each of these locations using the radionuclide mix and releases of Table 3.2-1.

Based upon these calculations, it was determined that the controlling receptor pathway is the "hypothetical" cow milk-infant pathway in the NE sector, at 4.75 miles.

ODCM (BSEP) 3-45 Rev. 25

Tables 3.3-1 through 3.3-19 present R1 values for the total body, GI tract, bone, liver, kidney, thyroid, and lung organs for the ground plane, inhalation, cow milk, goat milk, and vegetable and meat ingestion pathways for the infant, child, teen, and adult age groups as appropriate to the pathways. These values were calculated using the methodology described in NUREG 0133 using a grazing period of eight months. A discussion of their calculation is presented in Appendix C.

In the determination of the controlling location annual average D / Q and X/ Q values are utilized. D/Q values at the limiting real pathway locations for releases from the Turbine Buildings, Reactor Buildings, and the stack were obtained from Tables A-3, A-9, and A-15, respectively, of Appendix A. X/Q values at the same location for these same release points were obtained from Tables A-1, A-7, and A-1 3 of Appendix A. A description of the derivation of the various X/Q and D/Q values is presented in Appendix A.

Long-term D / Q values for the stack, Reactor Buildings, and Turbine Buildings are provided for the midpoints of the following distances:

0.0-0.5 mi.

0.5-1.0 mi.

1.0-1.5 mi.

1.5-2.0 mi.

2.0-2.5 mi.

2.5-3.0 mi.

3.0-3.5 mi.

3.5-4.0 mi.

4.0-4.5 mi.

14.5-5.0 mi.

I These values apl~ar in tables in Appendix A. These tables may be utilized if an additional special location arises which is different from one presented in the special locations of Appendix A.

The following relationships should hold for BSEP to show compliance with BSEP ODCM Specification 7.3.9.

For the calendar quarter:

DT < 15 mrem (3.3-19)

For the calendar year:

DT -

30 mrem (3.3-20)

Where:

DT

=

The dose to any organ T from radioiodines and particulates, mrem ODCM (BSEP) 3-46 Rev. 25

The quarterly limits given above represent one-half the annual design objective of Section I1.C of Appendix I of 10CFR50. If any of the limits of Expressions 3.3-19 or 3.3-20 are exceeded, a special report pursuant to Section IV.A of Appendix I of 1 OCFR50 must be filed with the NRC.

2.

Projection of Doses Dose projections for this section are required at least once per 31 days in ODCM TR 7.3.11.2.

The doses will be projected using Expressions 3.3-17. When the operational conditions are expected to be the same as for the current month, the source term inputs into the equation for the projection can be taken directly from the current month's data. Where possible, credit for expected operational evolutions (i.e., outages, etc.) should be taken in the dose projections. This may be accomplished by using projected reactor-days of operation. For example:

If Unit 1 had 28 reactor-days of operation and the dose to the bone was 0.05 mrem (remember there are 6 organs to consider) and Unit 2 was down at 0 reactor-days, then obtain from Planning & Scheduling the projected number of reactor-days for both Units 1 and 2 in the upcoming month. Suppose that the projected reactor-days for Unit 1 will be 10 reactor-days and for Unit 2, 21 reactor-days. To calculate the projected dose "x":

28/2 + 0/2 vr0/2 + 21/2 0.05 x

x = 0.06 mrem to the bone This projected dose to the bone is less than 0.6 mrem dose limit to any organ. If the dose to the bone or any other organ exceeds 0.6 mrem, the Turbine Building ventilation exhaust treatment system must be operational in the ensuing month.

ODCM (BSEP) 3-47 Rev. 25

TABLE 3.3-1 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Ground Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin CR 51 4.66E 06 4.66E 06 4.66E 06 4.66E 06 4.66E 06 4.66E 06 4.66E 06 5.51 E 06 MN 54 1.34E 09 1.34E 09 1.34E 09 1.34E 09 1.34E 09 1.34E 09 1.34E 09 1.57E 09 FE 59 2.75E 08 2.75E 08 2.75E 08 2.75E 08 2.75E 08 2.75E 08 2.75E 08 3.23E 08 CO 58 3.79E 08 3.79E 08 3.79E 08 3.79E 08 3.79E 08 3.79E 08 3.79E 08 4.44E 09 CO 60 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.52E 10 ZN 65 7.49E 08 7.49E 08 7.49E 08 7.49E 08 7.49E 08 7.49E 08 7.49E 08 8.61 E 08 RB 86 8.99E 06 8.99E 06 8.99E 06 8.99E 06 8.99E 06 8.99E 06 8.99E 06 1.03E 07 SR 89 2.23E 04 2.23E 04 2.23E 04 2.23E 04 2.23E 04 2.23E 04 2.23E 04 2.58E 04 Y 91 1.08E 06 1.08E 06 1.08E 06 1.08E 06 1.08E 06 1.08E 06 1.08E 06 1.22E 06 ZR 95 2.49E 08 2.49E 08 2.49E 08 2.49E 08 2.49E 08 2.49E 08 2.49E 08 2.89E 08 NB 95 1.36E 08 1.36E 08 1.36E 08 1.36E 08 1.36E 08 1.36E 08 1.36E 08 1.60E 08 RU103 1.09E 08 1.09E 08 1.09E 08 1.09E 08 1.09E 08 1.09E 08 1.09E 08 1.27E 08 RU106 4.19E 08 4.19E 08 4.19E 08 4.19E 08 4.19E 08 4.19E 08 4.19E 08 5.03E 08 AG110M 3.48E 09 3.48E 09 3.48E 09 3.48E 09 3.48E 09 3.48E 09 3.48E 09 4.06E 09 SN113 1.44E 07 6.28E 06 1.22E 07 6.21 E 06 1.OOE 07 1.33E 07 8.14E 06 4.09E 07 TE127M 9.15E 04 9.15E 04 9.15E 04 9.15E 04 9.15E 04 9.15E 04 9.15E 04 1.08E 05 TE129M 2.OOE 07 2.OOE 07 2.OOE 07 2.OOE 07 2.OOE 07 2.OOE 07 2.OOE 07 2.34E 07 1131 1.72E 07 1.72E 07 1.72EOQ7 1.72E 07 1.72E 07 1.72E 07 1.72E 07 2.09E 07 1132 1.24E 06 1.24E 06 1.24E 06 1.24E 06 1.24E 06 1.24E 06 1.24E 06 1.46E 06 1133 2.47E 06 2.47E-06 2.47E 06 2.47E 06 2.47E 06 2.47E 06 2.47E 06 3.OOE 06 1135 2.56E 06 2.56E 06 2.56E 06 2.56E 06 2.56E 06 2.56E 06 2.56E 06 2.99E 06 CS134 6.82E 09 6.82E 09 6.82E 09 6.82E 09 6.82E 09 6.82E 09 6.82E 09 7.96E 09 CS136 1.49E 08 1.49E 08 1.49E 08 1.49E 08 1.49E 08 1.49E 08 1.49E 08 1.69E 08 CS137 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.20E 10 BA140 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.34E 07 CE141 1.36E 07 1.36E 07 1.36E 07 1.36E 07 1.36E 07 1.36E 07 1.36E 07 1.53E 07 CE144 6.95E 07 6.95E 07 6.95E 07 6.95E 07 6.95E 07 6.95E 07 6.95E 07 8.03E 07 HF181 1.97E 08 1.63E 08 2.30E 08 1.70E 08 1.76E 08 2.33E 08 1.82E 08 2.82E 08 AM-241 5.16E 08 5.16E 08 5.16E 08 5.16E 08 5.16E 08 5.16E 08 5.16E 08 7.45E 08

R Values in units of mrem/yr per ttCi/m3 for inhalation and tritium, and in units of m2-mremlyr per pCi/sec for all others.

ODCM (BSEP) 3-48 Rev. 25

TABLE 3.3-2 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Vegetable AGE GROUP = Adult Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 2.28E 03 2.28E 03 0.OOE 01 2.28E 03 2.28E 03 2.28E 03 2.28E 03 2.28E 03 P 32 5.91 E 07 1.72E 08 1.53E 09 9.51 E 07 0.00E 01 0.00E 01 0.00E01 0.OOE 01 CR 51 4.60E 04 1.16E 07 0.00E 01 0.00E 01 1.01 E 04 2.75E 04 6.1 OE 04 0.OOE 01 MN 54 5.83E 07 9.36E 08 0.00E 01 3.05E 08 9.09E 07 0.00E 01 0.00E 01 0.00E 01 FE 59 1.12E 08 9.75E 08 1.24E 08 2.93E 08 0.00E 01 0.OOE 01 8.17E 07 0.00E 01 CO 58 6.71 E 07 6.07E 08 0.OOE 01 2.99E 07 0.00E 01 0.OOE 01 0.00E 01 0.OOE 01 CO 60 3.67E 08 3.12E 09 0.OOE 01 1.66E 08 0.OOE 01 0.OOE 01 0.00E 01 0.OOE 01 ZN 65 5.77E 08 8.04E 08 4.01 E 08 1.28E 09 8.54E 08 0.OOE 01 0.OOE 01 0.OOE 01 RB 86 1.03E 08 4.36E 07 0.OOE 01 2.21 E 08 0.OOE 01 0.00E 01 0.OOE 01 0.OOE 01 SR 89 2.87E 08 1.60E 09 1.OOE 10 0.OOE 01 0.OOE 01 0.OOE 01 0.00E01 0.OOE 01 SR 90 1.64E 11 1.93E 10 6.70E 11 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 Y 91 1.34E 05 2.76E 09 5.01 E 06 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.00E 01 ZR 95 2.51 E 05 1.17E 09 1.16E 06 3.71 E 05 5.82E 05 0.OOE 01 0.OOE 01 0.OOE 01 NB 95 4.19E 04 4.73E 08 1.40E 05 7.79E 04 7.70E 04 0.OOE 01 0.OOE 01 0.OOE 01 RU103 2.04E 06 5.53E 08 4.74E 06 0.OOE 01 1.81 E 07 0.OOE 01 0.OOE 01 0.OOE 01 RU106 2.46E 07 1.26E 10 1.94E 08 0.OOE 01 3.75E 08 0.OOE 01 0.OOE 01 0.OOE 01 AG11OM 6.23E 06 4.28E 09 1.13E 07 1.05E 07 2.06E 07 0.OOE 01 0.00E 01 0.OOE 01 SN 113 1.36E 07 2.53E 08 1.44E 07 5.60E 05 4.09E 05 1.96E 05 0.OOE 01 0.OOE 01 TE127M 6.12E 07 1.68E 09 5.02E 08 1.80E 08 2.04E 09 1.28E 08 0.OOE 01 0.OOE 01 TE129M 4.71 E 07 1.50E 09 2.98E 08 1.11 E 08 1.24E 09 1.02E 08 0.00E 01 0.OOE 01 1131 6.61 E 07 3.04E 07 8.07E 07 1.15E 08 1.98E 08 3.78E 10 0.0EO1 0.OOE 01 1132 5.21 E 01 2.80E 01 5.57E 01 1.49E 02 2.37E 02 5.21 E 03 0.OOE 01 0.OOE 01 1133 1.12E 06 3.30E 06 2.11 E 06 3.67E 06 6.40E 06 5.39E 08 0.OOE 01 0.OOE 01 1135 3.91 E 04 1.20E 05 4.05E 04 1.06E 05 1.70E 05 7.00E 06 0.OOE 01 0.OOE 01 CS134 8.83E 09 1.89E 08 4.54E 09 1.08E 10 3.49E 09 0.OOE 01 1.1 6E 09 0.OOE 01 CS136 1.19E 08 1.88E 07 4.19E 07 1.66E 08 9.21 E 07 0.00E 01 1.26E 07 0.00E 01 CS137 5.94E 09 1.76E 08 6.63E 09 9.07E 09 3.08E 09 0.00E 01 1.02E 09 0.OOE 01 BA140 8.40E 06 2.64E 08 1.28E 08 1.61 E 05 5.47E 04 0.OOE 01 9.22E 04 0.OOE 01 CE141 1.48E 04 4.99E 08 1.93E 05 1.31 E 05 6.07E 04 0.00E 01 0.00E 01 0.OOE 01 CE144 1.69E 06 1.06E 10 3.15E 07 1.32E 07 7.80E 06 0.OOE 01 0.00E 01 O.00E 01 HF 181 1.08E 06 7.06E 08 9.51 E 06 5.36E 04 4.48E 04 3.41 E 04 0.OOE 01 0.OOE 01 AM 241 4.12E 09 5.65E 09 5.75E 10 5.37E 10 3.10E 10 0.OOE 01 0.0OE 01 0.OOE 01

R Values in units of mrem/yr per LtiC/m 3 for inhalation and tritium, and in units of m2-mrem/yr per ptCVsec for all others.

ODCM (BSEP) 3-49 Rev. 25

TABLE 3.3-3 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT' PATHWAY = Vegetable AGE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 2.61 E 03 2.61 E 03 0.OOE 01 2.61 E 03 2.61 E 03 2.61 E 03 2.61 E 03 2.61 E 03 P 32 6.80E 07 1.47E 08 1.75E 09 1.09E 08 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 CR 51 6.11 E 04 1.03E 07 0.00E 01 0.00E 01 1.34E 04 3.39E 04 8.72E 04 0.00E 01 MN 54 8.79E 07 9.09E 08 0.00E 01 4.43E 08 1.32E 08 0.00E 01 0.00E 01 0.OOE 01 FE 59 1.60E 08 9.78E 08 1.77E 08 4.14E 08 0.00E 01 0.00E 01 1.30E 08 0.00E 01 CO 58 9.79E 07 5.85E 08 0.OOE 01 4.25E 07 0.00E 01 0.00E 01 0.00E 01 0.00E 01 CO 60 5.57E 08 3.22E 09 0.00E 01 2.47E 08 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 ZN 65 8.68E 08 7.88E 08 5.36E 08 1.86E 09 1.19E 09 0.OOE 01 0.OOE 01 0.OOE 01 RB 86 11.30E 08 4.09E 07 0.OOE 01 2.76E 08 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 SR 89 4.36E 08 1.81 E 09 1.52E 10 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 SR 90 2.05E 11 2.33E 10 8.32E 11 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 Y 91 2.06E 05 3.15E 09 7.68E 06 0.00E 01 0.OOE 01 0.00E 01 0.00E 01 0.OOE 01 ZR 95 3.68E 05 1.23E 09 1.69E 06 5.35E 05 7.86E 05 0.OOE 01 0.OOE 01 0.OOE 01 NB 95 5.77E 04 4.48E 08 1.89E 05 1.05E 05 1.02E 05 0.OOE 01 0.OOE 01 0.OOE 01 RU103 2.90E 06 5.66E 08 6.78E 06 0.OOE 01 2.39E 07 0.OOE 01 0.OOE 01 0.OOE 01 RU106 3.93E 07 1.50E 10 3.12E 08 0.OOE 01 6.02E 08 0.OOE 01 0.OOE 01 0.OOE 01 AG11OM 9.39E 06 4.34E09 1.63E 07 1.54E 07 2.95E 07 0.OOE 01 0.OOE 01 0.OOE 01 SN 113 2.02E 07 2.29E 08 1.91 E 07 8.03E 05 5.65E 05 2.63E 05 0.OOE 01 0.OOE 01 TE127M 9.44E 07 1.98E 09 7.93E 08 2.81E 08 3.22E 09 1.89E 08 0.OOE 01 0.OOE 01 TE129M 6.79E 07 1.61 E 09 4.29E 08 1.59E 08 1.79E 08 1.38E 08 0.OOE 01 0.OOE 01 1131 5.77E 07 2.13E 07 7.68E 07 1.07E 08 1.85E 08 3.14E 10 0.OOE 01 0.OOE 01 1132 4.72E 01 5.72E 01 5.02E 01 1.31 E 02 2.07E 02 4.43E 03 0.OOE 01 0.OOE 01 1133 1.01 E 06 2.51 E 06 1.96E 06 3.32E 06 5.83E 06 4.64E 08 0.OOE 01 0.OOE 01 1135 3.49E 04 1.04E 05 3.66E 04 9.42E 04 1.49E 05 6.06E 06 0.OOE 01 0.OOE 01 CS134 7.54E 09 2.02E 08 6.90E 09 1.62E 10 5.16E 09 0.OOE 01 1.97E 09 0.OOE 01 CS136 1.13E 08 1.35E 07 4.28E 07 1.68E 08 9.16E 07 0.OOE 01 1.44E 07 0.OOE 01 CS137 4.90E 09 2.OOE 08 1.06E 10 1.41E 10 4.78E 09 0.OOE 01 1.86E 09 0.00E 01 BA140 8.88E 06 2.12E 08 1.38E 08 1.69E 05 5.72E 04 0.OOE 01 1.14E 05 0.OOE 01 CE141 2.12E 04 5.29E 08 2.77E 05 1.85E 05 8.70E 04 0.OOE 01 0.OOE 01 0.OOE 01 CE144 2.71 E 06 1.27E 10 5.04E 07 2.09E 07 1.25E 07 0.OOE 01 0.0OE 01 0.OOE 01 HF 181 1.54E 06 6.90E 08 1.38E 07 7.58E 04 6.32E 04 4.63E 04 0.OOE 01 0.OOE 01 AM 241 4.97E 09 6.80E 09 6.89E 10 6.50E 10 3.72E 10 0.OOE 01 0.OOE 01 0.00E 01

R Values in units of mremlyr per taC/m 3 for inhalation and tritium, and in units of m2-mrem/yr per piCi/sec for all others.

ODCM (BSEP) 3-50 Rev. 25

TABLE 3.3-4 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT PATHWAY = Vegetable AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 4.04E 03 4.04E 03 O.OOE 01 4.04E 03 4.04E 03 4.04E 03 4.04E 03 4.04E 03 P 32 1.42E 08 1.01 E 08 3.67E 09 1.72E 08 O.OOE 01 O.OOE 01 O.OOE 01 O.OOE 01 CR 51 1.16E 05 6.15E 06 O.OOE 01 O.OOE 01 1.76E 04 6.44E 04 1.18E 05 O.OOE 01 MN 54 1.73E 08 5.44E 08 O.OOE 01 6.49E 08 1.82E 08 O.OOE 01 O.OOE 01 O.OOE 01 FE 59 3.17E 08 6.62E 08 3.93E 08 6.36E 08 O.OOE 01 O.OOE 01 1.84E 08 O.OOE 01 CO 58 1.92E 08 3.66E 08 O.OOE 01 6.27E 07 O.OOE 01 O.OOE 01 O.OOE 01 O.OOE 01 CO 60 1.11 E 09 2.08E 09 O.OOE 01 3.76E 08 O.OOE 01 O.OOE 01 O.OOE 01 O.OOE 01 ZN 65 1.70E 09 4.81 E 08 1.03E 09 2.74E 09 1.73E 09 O.OOE 01 O.OOE 01 O.OOE 01 RB 86 2.81 E 08 2.94E 07 0.OOE 01 4.56E 08 O.OOE 01 O.OOE 01 O.OOE 01 O.OOE 01 SR 89 1.03E 09 1.40E 09 3.62E 10 O.OOE 01 O.OOE 01 O.OOE 01 O.OOE 01 O.OOE 01 SR 90 3.49E 11 1.86E 10 1.38E 12 O.OOE 01 O.OOE 01 O.OOE 01 O.OOE 01 O.OOE 01 Y 91 4.89E 05 2.44E 09 1.83E 07 O.OOE 01 O.OOE 01 O.OOE 01 O.OOE 01 O.OOE 01 ZR 95 7.44E 05 8.71 E 08 3.80E 06 8.35E-05 1.20E 06 O.OOE 01 O.OOE 01 O.OOE 01 NB 95 1.12E 05 2.91 E 08 4.04E 05 1.57E 05 1.48E 05 O.OOE 01 O.OOE 01 O.OOE 01 RU103 5.86E 06 3.94E 08 1.52E 07 O.OOE 01 3.84E 07 O.OOE 01 O.OOE 01 O.OOE 01 RU106 9.38E 07 1.17E 10 7.52E 08 O.OOE 01 1.02E 09 O.OOE 01 O.OOE 01 O.OOE 01 AG11 OM 1.87E 07 2.78E 09 3.46E 07 2.34E 07 4.35E 07 O.OOE 01 O.OOE 01 O.OOE 01 SN 113 3.98E 07 1.46E 08 3.64E 07 1.18E 06 8.09E 05 4.82E 05 O.OOE 01 O.OOE 01 TE127M 2.26E 08 1.54E 09 1.90E109 5.12E 08 5.42E 09 4.55E 08 O.OOE 01 O.OOE 01 TE129M 1.55E 08 1.22E 09 9.98E 08 2.79E 08 2.93E 09 3.22E 08 O.OOE 01 O.OOE 01 1131 8.16E 07 1.23E 07 1.43E 08 1.44E 08 2.36E 08 4.75E 10 O.OOE 01 O.OOE 01 1132 7.53E 01 1.93E 02 8.91 E 01 1.64E 02 2.51 E 02 7.60E 03 O.OOE 01 O.OOE 01 1133 1.67E 06 1.78E 06 3.57E 06 4.42E 06 7.36E 06 8.21 E 08 O.OOE 01 O.OOE 01 1135 5.54E 04 8.92E 04 6.50E 04 1.17E 05 1.79E 05 1.04E 07 O.OOE 01 O.OOE 01 CS134 5.40E 09 1.38E 08 1.56E 10 2.56E 10 7.93E 09 O.OOE 01 2.84E 09 O.OOE 01 CS136 1.43E 08 7.77E 06 8.04E 07 2.21 E 08 1.18E 08 O.OOE 01 1.76E 07 O.OOE 01 CS137 3.52E 09 1.50E 08 2.49E 10 2.39E 10 7.78E 09 O.OOE 01 2.80E 09 O.OOE 01 BA1 40 1.61 E 07 1.40E 08 2.76E 08 2.42E 05 7.87E 04 O.OOE 01 1.44E 05 O.OOE 01 CE141 4.75E 04 3.99E 08 6.42E 05 3.20E 05 1.40E 05 O.OOE 01 O.OOE 01 O.OOE 01 CE144 6.49E 06 9.94E 09 1.22E 08 3.81 E 07 2.11 E 07 O.OOE 01 O.OOE 01 O.OOE 01 HF 181 3.15E 06 3.17E 08 3.13E 07 1.22E 05 9.78E 04 1.03E 05 O.OOE 01 O.OOE 01 AM 241 7.12E 09 5.34E 09 9.50E 10 8.17E 10 4.35E 10 o.OOE 01 O.OOE 01 0.OOE 01

R Values in units of mrem/yr per pCim 3 for inhalation and tritium, and in units of m2-mrem/yr per pCi/sec for all others.

ODCM (BSEP) 3-51 Rev. 25

TABLE 3.3-5 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Meat AGE GROUP = Adult Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 3.27E 02 3.27E 02 0.OOE 01 3.27E 02 3.27E 02 3.27E 02 3.27E 02 3.27E 02 P 32 1.1 8E 08 3.43E 08 3.05E 09 1.89E 08 0.00E 01 0.00E 01 0.OOE 01 0.00E 01 CR 51 4.27E 03 1.08E 06 0.00E 01 0.00E 01 9.42E 02 2.56E 03 5.67E 03 0.OOE 01 MN 54 1.06E 06 1.71 E 07 0.OOE 01 5.57E 06 1.66E 06 0.OOE 01 0.OOE 01 0.00E 01 FE 59 1.43E 08 1.25E 09 1.59E 08 3.74E 08 0.00E 01 0.00E 01 1.04E 08 0.00E 01 CO 58 2.43E 07 2.20E 08 0.00E 01 1.08E 07 0.00E 01 0.OOE 01 0.00E 01 0.00E 01 CO 60 1.03E 08 8.76E 08 0.OOE 01 4.66E 07 0.00E 01 0.00E 01 0.00E 01 0.OOE 01 ZN 65 3.58E 08 4.98E 08 2.49E 08 7.91 E 08 5.29E 08 0.OOE 01 0.OOE 01 0.OOE 01 RB 86 1.42E 08 6.OOE 07 0.OOE 01 3.04E 08 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 SR 89 5.23E 06 2.92E 07 1.82E 08 0.OOE 01 0.OOE 01 0.OOE 01 0.00E 01 0.OOE 01 SR 90 2.02E 09 2.38E 08 8.22E 09 0.OOE 01 0.OOE 01 0.OOE 01 0.O0EO1 0.OOE 01 Y 91 1.80E 04 3.71 E 08 6.75E 05 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 ZR 95 2.43E 05 1.14E 09 1.12E 06 3.59E 05 5.64E 05 0.OOE 01 0.OOE 01 0.OOE 01 NB 95 4.12E 05 4.65E 09 1.38E 06 7.66E 05 7.58E 05 0.OOE 01 0.OOE 01 0.OOE 01 RU103 2.72E 07 7.38E 09 6.32E 07 0.OOE 01 2.41 E 08 0.OOE 01 0.OOE 01 0.OOE 01 RU106 2.19E 08 1.12E 11 1.73E 09 0.00E 01 3.35E 09 0.00E 01 0.00E 01 0.OOE 01 AG1i OM 2.34E 06 1.61 E 09 4.27E 06 3.95E 06 7.76E 06 0.OOE 01 O.OOE 01 0.OOE 01 SN 113 2.80E 07 5.19E 08 2.97E 07 1.15E 06 8.40E 05 4.03E 05 0.OOE 01 0.OOE 01 TE127M 1.00E 08 2.76E 09 8.22E 08 2.94E 08 3.34E 09 2.1OE 08 0.OOE 01 0.OOE 01 TE129M 1.17E 08 3.73E 09 7.40E 08 2.76E 08 3.09E 09 2.54E 08 0.OOE 01 0.OOE 01 1131 5.77E 06 2.66E 06 7.04E 06 1.01 E 07 1.73E 07 3.30E 09 0.OOE 01 0.OOE 01 1133 1.51E-01 4.46E-01 2.85E-01 4.96E-01 8.66E-01 7.29E 01 0.OOE 01 0.OOE 01 1135 6.07E-17 1.86E-16 6.28E-17 1.64E-16 2.64E-16 1.08E-14 0.OOE 01 0.OOE 01 CS134 7.81 E 08 1.67E 07 4.01 E 08 9.55E 08 3.09E 08 0.OOE 01 1.03E 08 0.OOE 01 CS136 2.14E 07 3.33E 06 7.53E 06 2.97E 07 1.65E 07 0.OOE 01 2.27E 06 0.OOE 01 CS137 4.99E 08 1.47E 07 5.57E 08 7.61 E 08 2.58E 08 0.OOE 01 8.59E 07 0.OOE 01 BA140 1.20E 06 3.77E 07 1.83E 07 2.30E 04 7.82E 03 0.OOE 01 1.32E 04 0.OOE 01 CE141 6.46E 02 2.18E 07 8.42E 03 5.69E 03 2.65E 03 0.OOE 01 0.OOE 01 0.OOE 01 CE144 4.70E 04 2.96E 08 8.75E 05 3.66E 05 2.17E 05 0.OOE 01 0.OOE 01 0.OOE 01 HF 181 1.52E 06 9.97E 08 1.34E 07 7.57E 04 6.33E 04 4.81 E 04 0.OOE 01 0.OOE 01 AM 241 1.80E 07 2.47E 07 2.52E 08 2.35E 08 1.36E 08 0.OOE 01 0.OOE 01 0.OOE 01

R Values in units of mrem/yr per stCVm3 for inhalation and tritium. and in units of m2-mrem/yr per pCi/sec for all others.

ODCM (BSEP) 3-52 Rev. 25

TABLE 3.3-6 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Meat AGE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 1.95E 02 1.95E 02 0.00E 01 1.95E 02 1.95E 02 1.95E 02 1.95E 02 1.95E 02 P32 9.98E 07 2.16E 08 2.58E 09 1.60E 08 0.OOE 01 0.OOE 01 0.OOE 01 0.00E 01 CR 51 3.42E 03 5.75E 05 0.OOE 01 O.OOE 01 7.49E 02 1.90E 03 4.88E 03 0.OOE 01 MN 54 8.43E 05 8.72E 06 0.OOE 01 4.25E 06 1.27E 06 0.OOE 01 0.OOE 01 0.OOE 01 FE 59 1.15E 08 7.02E 08 1.27E 08 2.97E 08 0.00E 01 0.OOE 01 9.36E 07 0.00E 01 CO 58 1.93E 07 1.15E 08 0.00E 01 8.36E 06 0.00E 01 0.00E 01 0.00E 01 0.00E 01 CO 60 8.15E 07 4.71 E 08 0.OOE 01 3.62E 07 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 ZN 65 2.83E 08 2.57E 08 1.75E 08 6.07E 08 3.89E 08 0.OOE 01 0.00E 01 0.00E 01 RB 86 1.19E 08 3.76E 07 0.OOE 01 2.54E 08 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 SR 89 4.40E 06 1.83E 07 1.54E 08 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 SR 90 1.31 E 09 1.49E 08 5.32E 09 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 Y 91 1.52E 04 2.33E 08 5.68E 05 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 0.OOE 01 ZR 95 1.95E 05 6.53E 08 8.97E 05 2.83E 05 4.16E 05 0.OOE 01 0.OOE 01 0.OOE 01 NB 95 3.29E 05 2.55E 09 1.08E 06 5.97E 05 5.79E 05 0.OOE 01 0.OOE 01 0.OOE 01 RU103 2.20E 07 4.30E 09 5.15E 07 0.OOE 01 1.82E 08 0.OOE 01 0.OOE 01 0.OOE 01 RU106 1.84E 08 7.OOE 10 1.46E 09 0.OOE 01 2.81 E 09 0.OOE 01 0.OOE 01 0.00E 01 AG11OM 1.86E 06 8.59E 08 3.23E 06 3.06E 06 5.83E 06 0.OOE 01 0.OOE 01 0.OOE 01 SN 113 2.22E 07 2.51 E 08 2.09E 07 8.80E 05 6.19E 05 2.89E 05 0.OOE 01 0.OOE 01 TE127M 8.25E 07 1.73E 09 6.94E 68 2.46E 08 2.81 E 09 1.65E 08 0.OOE 01 0.OOE 01 TE129M 9.81E 07 2.33E 09 6.20E 08 2.30E 08 2.59E 09 2.OOE 08 0.OOE 01 0.OOE 01 1131 4.40E 06 1.62E 06 5.85E 06 8.20E 06 1.41 E 07 2.39E 09 0.OOE 01 0.OOE 01 1133 1.23E-01 3.06E-01 2.39E-01 4.05E-01 7.10E-01 5.65E 01 0.00E 01 0.OOE 01 1135 4.88E-17 1.46E-16 5.11 E-17 1.32E-16 2.08E-16 8.46E-15 0.OOE 01 0.OOE 01 CS134 3.48E 08 9.34E 06 3.19E 08 7.51E 08 2.39E 08 0.OOE 01 9.11E 07 0.OOE 01 CS136 1.55E 07 1.86E 06 5.87E 06 2.31E 07 1.26E 07 0.OOE 01 1.98E 06 0.OOE 01 CS137 2.14E 08 8.75E 06 4.62E 08 6.15E 08 2.09E 08 0.OOE 01 8.13E 07 0.OOE 01 BA140 9.76E 05 2.34E 07 1.51 E 07 1.86E 04 6.29E 03 O.OOE 01 1.25E 04 0.OOE 01 CE141 5.42E 02 1.35E 07 7.07E 03 4.72E 03 2.22E 03 0.OOE 01 0.OOE 01 0.OOE 01 CE144 3.96E 04 1.85E 08 7.37E 05 3.05E 05 1.82E 05 0.OOE 01 0.00E 01 0.OOE 01 HF 181 1.23E 06 5.50E 08 1.10E 07 6.05E 04 5.04E 04 3.69E 04 0.OOE 01 0.OOE 01 AM 241 1.13E 07 1.55E 07 1.57E 08 1.48E 08 8.49E 07 0.OOE 01 0.OOE 01 0.00E 01

'R Values in units of mrem/yr per ptCym3 for inhalation and tritium, and in units of m2 -mrem/yr per ptCi/sec for all others.

ODCM (BSEP) 3-53 Rev. 25

TABLE 3.3-7 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT PATHWAY = Meat AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 2.36E 02 2.36E 02 0.00E 01 2.36E 02 2.36E 02 2.36E 02 2.36E 02 2.36E 02 P 32 1.87E 08 1.34E 08 4.86E 09 2.27E 08 0.OOE 01 0.00E 01 0.00E 01 0.00E 01 CR 51 5.33E 03 2.83E 05 0.00E 01 0.00E 01 8.09E 02 2.96E 03 5.40E 03 0.00E 01 MN 54 11.30E 06 4.08E 06 0.00E 01 4.86E 06 1.36E 06 0.00E 01 0.00E 01 0.00E 01 FE 59 1.82E 08 3.80E 08 2.25E 08 3.65E 08 0.00E 01 0.00E 01 1.06E 08 0.00E 01 CO 58 2.99E 07 5.70E 07 0.OOE 01 9.76E 06 0.00E 01 0.00E 01 0.00E 01 0.00E 01 CO 60 1.27E 08 2.38E 08 0.00E 01 4.30E 07 0.00E 01 0.00E 01 0.00E 01 0.00E 01 ZN 65 4.35E 08 1.23E 08 2.62E 08 6.99E 08 4.40E 08 0.00E 01 0.00E 01 0.OOE 01 RB 86 2.21 E 08 2.32E 07 0.OOE 01 3.60E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 SR 89 8.31 E 06 1.13E 07 2.91 E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 SR 90 1.74E 09 9.26E 07 6.87E 09 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Y 91 2.87E 04 1.43E 08 1.07E 06 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 ZR 95 3.12E 05 3.65E 08 1.59E 06 3.50E 05 5.01 E 05 0.00E 01 0.00E 01 0.00E 01 NB 95 5.17E 05 1.34E 09 1.86E 06 7.23E 05 6.80E 0 0.00E 01 0.00E 01 0.00E 01 RU103 3.58E 07 2.41 E 09 9.31 E 07 0.00E 01 2.34E 08 0.00E 01 0.00E 01 0.00E 01 RU106 3.43E 08 4.27E 10 2.75E 09 0.00E 01 3.71 E 09 0.00E 01 0.00E 01 0.00E 01 AG11 OM 2.89E 06 4.30E 08 5.36E 06 3.62E 06 6.74E 0 0.00E 01 0.00E 01 0.00E 01 SN 113 3.43E 07 1.25E 08 3.14E Q07 1.01 E 06 6.97E 05 4.15E 05 0.00E 01 0.00E 01 TE127M 1.55E 08 1.06E 09 1.312 09 3.52E 08 3.73E 09 3.13E 08 0.00E 01 0.00E 01 TE129M 1.81 E 08 1.42E 09 1.17E 09 3.26E 08 3.43E 09 3.77E 08 0.00E 01 0.00E 01 1131 6.20E 06 9.72E 05 1.09E 07 1.09E 07 1.79E 07 3.61 E 09 0.00E 01 0.00E 01 1133 2.07E-01 2.21E-01 4.43E-01 5.48E-01 9.13E-01 1.02E 02 0.00E 01 0.00E 01 1135 7.87E-17 1.27E-16 9.25E-17 1.66E-16 2.55E-16 1.47E-14 0.00E 01 0.00E 01 CS 134 1.95E 08 4.93E 06 5.63E 08 9.23E 08 2.86E 08 0.00E 01 1.03E 08 0.00E 01 CS 136 1.80E 07 9.78E 05 1.01 E 07 2.78E 07 1.48E 0 0.00E 01 2.21 E 06 0.00E 01 CS 137 1.20E 08 5.1 OE 06 8.51 E 08 8.15E 08 2.65E 08 0.00E 01 9.55E 07 0.00E 01 BA 140 1.63E 06 1.42E 07 2.80E 07 2.45E 04 7.97E 0 0.00E 01 1.46E 04 0.00E 01 CE 141 9.86E 02 8.28E 06 1.33E 04 6.64E 03 2.91 E 03 0.00E 01 0.00E 01 0.00E 01 CE 144 7.42E 04 1.14E 08 1.39E 06 4.36E 05 2.41E 05 0.00E 01 0.00E 01 0.00E 01 HF 181 2.02E 06 3.31 E 08 2.01 E07 7.79E 04 6.26E 04 6.56E 04 0.00E 01 0.00E 01 AM 241 1.27E 07 9.49E 06 1.69E 08 1.45E 08 7.74E 07 0.00E 01 0.00E 01 0.00201

R Values in units of mrem/yr per CVi/m3 for inhalation and tritium, and in units of m2 -mrem/yr per jCisec for all others.

ODCM (BSEP) 3-54 Rev. 25

TABLE 3.3-8 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT' PATHWAY = Cow Milk AGE GROUP = Adult Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 7.69E 02 7.69E 02 O.OOE-01 7.69E 02 7.69E 02 7.69E 02 7.69E 02 7.69E 02 P 32 4.32E 08 1.26E 09 1.12E 10 6.95E 08 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.73E 04 4.36E 06 O.OOE-01 O.OOE-01 3.82E 03 1.04E 04 2.30E 04 O.OOE-01 MN 54 9.76E 05 1.57E 07 O.OOE-01 5.11 E 06 1.52E 06 O.OOE-01 O.OOE-01 O.OOE-01 FE 59 1.60E 07 1.39E 08 1.77E 07 4.17E 07 O.OOE-01 O.OOE-01 1.17E 07 O.OOE-01 CO 58 6.28E 06 5.68E 07 O.OOE-01 2.80E 06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CO 60 2.24E 07 1.91 E 08 O.OOE-01 1.02E 07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.38E 09 1.92E 09 9.59E 08 3.05E 09 2.04E 09 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 7.54E 08 3.19E 08 O.OOE-01 1.62E 09 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 2.50E 07 1.40E 08 8.70E 08 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 7.59E 09 8.94E 08 3.09E 10 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91 1.37E 02 2.81 E 06 5.11 E 03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 1.22E 02 5.71 E 05 5.62E 02 1.80E 02 2.83E 02 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 1.48E 04 1.67E 08 4.95E 04 2.75E 04 2.72E 04 O.OOE-01 O.OOE-01 O.OOE-01 RU 103 2.63E 02 7.14E 04 6.11 E 02 O.OOE-01 2.33E 03 O.OOE-01 O.OOE-01 O.OOE-01 RU 106 1.60E 03 8.17E 05 1.26E 04 O.OOE-01 2.44E 04 O.OOE-01 O.OOE-01 O.OOE-01 AG11OM 2.04E 07 1.40E 10 3.71 E 07 3.44E 07 6.76E 07 O.OOE-01 O.OOE-01 O.OOE-01 SN 113 1.32E 06 2.44E 07 1.40E 06 5.41 E 04 3.96E 04 1.90E 04 O.OOE 01 O.OOE 01 TE127M 4.11E 06 1.13E 08 3.37E ci 1.21E 07 1.37E 08 8.62E 06 O.OOE-01 O.OOE-01 TE129M 6.19E 06 1.97E 08 3.91E 07 1.46E 07 1.63E 08 1.34E 07 O.OOE-01 O.OOE-01 1131 1.59E 08 7.32E 07 1.94E 08 2.77E 08 4.76E 08 9.09E 10 O.OOE-01 O.OOE-01 1132 1.03E-01 5.51E-02 1.10E-01 2.93E-01 4.67E-01 1.03E 01 O.OOE-01 O.OOE-01 1 133 1.40E 06 4.13E 06 2.64E 06 4.59E 06 8.01 E 06 6.75E 08 O.OOE-01 O.OOE-01 1135 9.03E 03 2.76E 04 9.34E 03 2.45E 04 3.92E 04 1.61 E 06 O.OOE-01 O.OOE-01 CS 134 6.71 E 09 1.44E 08 3.45E 09 3.21 E 09 2.66E 09 O.OOE-01 8.82E 08 O.OOE-01 CS 136 4.73E 08 7.46E 07 1.66E 08 6.57E 08 3.65E 08 O.OOE-01 5.01 E 07 O.OOE-01 CS 137 4.22E 09 1.25E 08 4.71 E 09 6.44E 09 2.19E 09 O.OOE-01 7.27E 08 O.OOE-01 BA 140 1.12E 06 3.53E 07 1.71E 07 2.15E 04 7.32E 03 O.OOE-01 1.23E 04 O.OOE-01 CE 141 2.23E 02 7.52E 06 2.91 E 03 1.97E 03 9.14E 02 O.OOE-01 O.OOE-01 O.OOE-01 CE 144 1.15E 04 7.26E 07 2.15E 05 8.97E 04 5.32E 04 O.OOE-01 O.OOE-01 O.OOE-01 HF 181 6.68E 02 4.39E 05 5.91 E 03 3.33E 01 2.79E 01 2.12E 01 O.OOE 01 O.OOE 01 AM 241 1.27E 06 1.74E 06 1.77E 07 1.66E 07 9.56E 06 O.OOE 01 O.OOE 01 0.OOE 01

R Values in units of mrem/yr per Ci/rM3 for inhalation and tritium, and in units of m2-mremlyr per PCi/sec for all others.

ODCM (BSEP) 3-55 Rev. 25

TABLE 3.3-9 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Cow Milk AGE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 1.00E 03 1.00E 03 0.OOE-01 1.00E 03 1.00E 03 1.00E 03 1.00E 03 1.00E 03 P 32 8.OOE 08 1.73E 09 2.06E 10 1.28E 09 0.OOE-01 O.OOE-01 O.OOE-01 0.OOE-01 CR 51 3.02E 04 5.08E 06 O.OOE-01 O.OOE-01 6.63E 03 1.68E 04 4.32E 04 O.00E-01 MN 54 11.69E 06 1.75E 07 O.00E-01 8.52E 06 2.54E 06 0.OOE-01 0.OOE-01 0.00E-01 FE 59 2.79E 07 1.71 E 08 3.1 OE 07 7.23E 07 O.OOE-01 O.00E-01 2.28E 07 0.00E-01 CO 58 1.09E 07 6.50E 07 0.00E-01 4.72E 06 0.OOE-01 O.OOE-01 O.00E-01 0.00E-01 CO 60 3.88E 07 2.25E 08 0.00E-01 1.72E 07 0.00E-01 0.00E-01 O.00E-01 0.OOE-01 ZN 65 2.38E 09 2.16E 09 1.47E 09 5.11 E 09 3.27E 09 O.OOE-01 0.OOE-01 O.OOE-01 RB 86 1.39E 09 4.37E 08 0.OOE-01 2.95E 09 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 SR 89 4.59E 07 1.91 E 08 1.60E 09 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 SR 90 1.08E 10 1.23E 09 4.37E 10 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 Y 91 2.52E 02 3.85E 06 9.40E 03 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 ZR 95 2.13E 02 7.16E 06 9.83E 02 3.10E 02 4.56E 02 0.OOE-01 0.OOE-01 0.OOE-01 NB 95 2.58E 04 2.OOE 08 8.45E 04 4.68E 04 4.54E 04 0.OOE-01 0.OOE-01 0.OOE-01 RU 103 4.65E 02 9.08E 04 1.09E 03 0.OOE-01 3.83E 03 0.OOE-01 0.OOE-01 0.OOE-01 RU 106 2.93E 03 1.11 E 06 2.32E 04 0.OOE-01 4.48E 04 0.OOE-01 0.OOE-01 0.OOE-01 AG11OM 3.53E 07 1.63E 10 6.14E 07 5.81E 07 1.11E 08 0.OOE-01 0.OOE-01 0.OOE-01 SN 113 2.28E 06 2.58E 07 2.15E 06 9.06E 04 6.37E 04 2.97E 04 0.OOE 04 0.OOE 01 TE127M 7.39E 06 1.55E 08 6.22E 07 2.21E 07 2.52E 08 1.48E 07 0.OOE-01 0.OOE-01 TE129M 1.13E 07 2.69E 08 7.15E 07 2.65E 07 2.99E 08 2.31E 07 0.OOE-01 0.OOE-01 1131 2.65E 08 9.75E 07 3.52E 08 4.93E 08 8.48E 08 1.44E 11 0.OOE-01 0.OOE-01 1132 1.83E-01 2.22E-01 1.94E-01 5.09E-01 8.02E-01 1.71E 01 0.OOE-01 0.OOE-01 1133 2.49E 06 6.19E 06 4.82E 06 8.18E 06 1.43E 07 1.14E 09 0.OOE-01 0.OOE-01 1135 1.58E 04 4.74E 04 1.66E 04 4.27E 04 6.75E 04 2.75E 06 0.OOE-01 0.OOE-01 CS 134 6.54E 09 1.75E 08 5.99E 09 1.41E 10 4.48E 09 0.OOE-01 1.71 E 09 0.OOE-01 CS 136 7.48E 08 8.97E 07 2.83E 08 1.11 E 09 6.07E 08 0.OOE-01 9.56E 07 0.OOE-01 CS 137 3.96E 09 1.62E 08 8.54E 09 1.14E 10 3.87E 09 0.OOE-01 1.50E 09 0.OOE-01 BA 140 1.99E 06 4.77E 07 3.09E 07 3.79E 04 1.28E 04 0.OOE-01 2.55E 04 0.OOE-01 CE 141 4.09E 02 1.02E 07 6.33E 03 3.56E 03 1.68E 03 0.OOE-01 0.OOE-01 0.OOE-01 CE 144 2.12E 04 9.93E 07 3.95E 05 1.63E 05 9.76E 04 0.OOE-01 0.OOE-01 0.OOE-01 HF 181 1.18E 03 5.28E 05 1.06E 04 5.81 E 01 4.84E 01 3.55E 01 0.OOE 01 0.OOE 01 AM 241 1.74E 061 2.38E 06 2.42E 07 2.28E 07 1.31 E 07 0.00E 01 0.O0E 01 0,OOE 01

^R Values in units of mrem/yr per uCum3 for inhalation and tritium, and in units of m2-mrem/yr per pCisec for all others.

ODCM (BSEP) 3-56 Rev. 25

TABLE 3.3-10 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Cow Milk AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 1.58E 03 1.58E 03 0.OOE-01 1.58E 03 1.58E 03 1.58E 03 1.58E 03 1.58E 03 P 32 1.96E 09 1.41 E 09 5.09E 10 2.38E 09 0.OOE-01 0.OOE-01 0.OOE-01 0.00E-01 CR 51 6.17E 04 3.27E 06 0.OOE-01 0.OOE-01 9.36E 03 3.42E 04 6.25E 04 0.OOE-01 MN 54 3.39E 06 1.07E 07 0.OOE-01 1.27E 07 3.57E 06 0.00E-01 0.OOE-01 0.00E-01 FE 59 5.79E 07 1.21 E 08 7.18E 07 1.1 6E 08 0.OOE-01 0.OOE-01 3.37E 07 0.OOE-01 CO 58 2.21 E 07 4.20E 07 O.OOE-01 7.21 E 06 0.OOE-01 0.O0E-01 0.OOE-01 0.OOE-01 CO 60 7.90E 07 1.48E 08 0.OOE-01 2.68E 07 0.OOE-01 0.OOE-01 0.00E-01 0.00E-01 ZN 65 4.79E 09 1.35E 09 2.89E 09 7.70E 09 4.85E 09 0.OOE-01 0.OOE-01 0.OOE-01 RB 86 3.36E 09 3.52E 08 0.OOE-01 5.47E 09 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 SR 89 1.1 3E 08 1.54E 08 3.97E 09 0.00E-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 SR 90 1.87E 10 9.95E 08 7.38E 10 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 Y 91 6.21 E 02 3.09E 06 2.32E 04 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 ZR 95 4.47E 02 5.23E 05 2.28E 03 5.02E 02 7.18E 02 0.OOE-01 0.OOE-01 0.OOE-01 NB 95 5.31 E 04 1.37E 08 1.91 E 05 7.42E 04 6.98E 04 0.OOE-01 0.OOE-01 0.OOE-01 RU 103 9.88E 02 6.65E 04 2.57E 03 0.OOE-01 6.47E 03 0.OOE-01 0.OOE-01 0.OOE-01 RU 106 7.14E 03 8.90E 05 5.72E 04 0.OOE-01 7.72E 04 0.OOE-01 0.OOE-01 0.OOE-01 AG110M 7.19E 07 1.07E 10 1.33E 08 9.OOE 07 1.68E 08 0.OOE-01 0.OOE-01 0.OOE-01 SN 113 4.61E 06 1.69E 07 4.22E 08 4.13E 07 4.37E 08 3.66E 07 0.00E 01 0.00E 01 TE127M 1.82E 07 1.24E 08 1.53E 68 4.13E 07 4.37E 08 3.66E 07 0.OOE-01 0.OOE-01 TE129M 2.74E 07 2.15E 08 1.76E 08 4.92E 07 5.18E 08 5.68E 07 0.OOE-01 0.OOE-01 1131 4.88E 08 7.64E 07 8.54E 08 8.59E 08 1.41 E 09 2.84E 11 0.OOE-01 0.OOE-01 1132 3.89E-01 9.95E-01 4.60E-01 8.45E-01 1.29E 00 3.92E 01 0.00E-01 0.00E-01 1133 5.48E 06 5.84E 06 1.17E 07 1.45E 07 2.41 E 07 2.69E 09 0.OOE-01 0.OOE-01 1135 3.35E 04 5.39E 04 3.93E 04 7.07E 04 1.08E 05 6.26E 06 0.OOE-01 0.OOE-01 CS 134 4.78E 09 1.22E 08 1.38E 10 2.27E 10 7.03E 09 0.OOE-01 2.52E 09 0.OOE-01 CS 136 1.14E 09 6.17E 07 6.39E 08 1.76E 09 9.36E 08 0.OOE-01 1.40E 08 0.OOE-01 CS 137 2.91 E 09 1.23E 08 2.06E 10 1.97E 10 6.42E 09 0.OOE-01 2.31 E 09 0.OOE-01 BA 140 4.36E 06 3.78E 07 7.47E 07 6.54E 04 2.13E 04 0.OOE-01 3.90E 04 0.OOE-01 CE 141 9.73E 02 8.17E 06 1.31 E 04 6.55E 03 2.87E 03 0.OOE-01 0.OOE-01 0.OOE-01 CE 144 5.20E 04 7.96E 07 9.74E 05 3.05E 05 1.69E 05 0.OOE-01 0.OOE-01 0.OOE-01 HF 181 2.53E 03 4.16E 05 2.51 E 04 9.79E 01 7.86E 01 8.24E 01 0.OOE 01 0.OOE 01 AM 241 2.55E 06 1.91 E 06 3.40E 07 2.92E 07 1.56E 07 0.OOE 01 0.OOE 01 0.OOE 01

R Values in units of mrem/yr per pCi/m3 for inhalation and tritium, and in units of m2_mrem/yr per pCi/sec for all others.

ODCM (BSEP) 3-57 Rev. 25

TABLE 3.3-11 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT' PATHWAY = Cow Milk AGE GROUP = Infant Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 2.40E 03 2.40E 03 O.OOE-01 2.40E 03 2.40E 03 2.40E 03 2.40E 03 2.40E 03 P 32 4.06E 09 1.42E 09 1.05E 11 6.17E 09 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 9.77E 04 2.85E 06 O.OOE-01 O.OOE-01 1.39E 04 6.38E 04 1.24E 05 O.OOE-01 MN 54 5.37E 06 8.71 E 06 O.OOE-01 2.37E 07 5.25E 06 O.OOE-01 O.OOE-01 O.OOE-01 FE 59 9.23E 07 1.12E 08 1.34E 08 2.34E 08 O.OOE-01 O.OOE-01 6.92E 07 O.OOE-01 CO 58 3.60E 07 3.59E 07 O.OOE-01 1.44E 07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CO 60 1.29E 08 1.30E 08 O.OOE-01 5.47E 07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 6.14E 09 1.12E 10 3.88E 09 1.33E 10 6.45E 09 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 6.86E 09 3.55E 08 O.OOE-01 1.39E 10 0.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 2.17E 08 1.55E 08 7.55E 09 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 2.05E 10 1.OOE 09 8.04E 10 O.OOE-01 0.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91 1.16E 08 3.12E 06 4.36E 04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 7.01 E 02 4.92E 05 4.05E 03 9.88E 02 1.06E 03 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 8.48E 04 1.24E 08 3.56E 05 1.47E 05 1.05E 05 O.OOE-01 O.OOE-01 O.OOE-01 RU 103 1.74E 03 6.33E 04 5.21 E 03 O.OOE-01 1.08E 04 O.OOE-01 O.OOE-01 O.OOE-01 RU 106 1.47E 04 8.95E 05 1.18E 05 O.OOE-01 1.39E 05 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 1.19E 08 9.32E 09 2.46E 08 1.80E 08 2.57E 08 O.OOE-01 O.OOE-01 O.OOE-01 SN 113 6.66E 06 1.37E 07 6.46E 06 2.45E 05 1.32E 05 9.34E 04 O.OOE 01 O.OOE 01 TE127M 3.75E 07 1.25E 08 3.1OE 08 1.03E 08 7.64E 08 8.96E 07 O.OOE-01 O.OOE-01 TE129M 5.57E 07 2.16E 08 3.62E 08 1.24E 08 9.05E 08 1.39E 08 O.OOE-01 O.OOE-01 1131 9.23E 08 7.49E 07 1.78E 09 2.10E 09 2.45E 09 6.90E 11 O.OOE-01 O.OOE-01 1132 6.90E-01 1.57E-00 9.55E-01 1.94E 00 2.16E 00 9.09E 01 O.OOE-01 O.OOE-01 1133 1.05E 07 6.09E 06 2.47E 07 3.60E 07 4.23E 07 6.55E 09 O.OOE-01 O.OOE-01 1135 5.93E 04 5.83E 04 8.17E 04 1.63E 05 1.81 E 05 1.46E 07 O.OOE-01 O.OOE-01 CS 134 4.19E 09 1.13E 08 2.23E 10 4.15E 10 1.07E 10 O.OOE-01 4.38E 09 0.OOE-01 CS 136 1.37E 09 5.58E 07 1.25E 09 3.67E 09 1.46E 09 O.OOE-01 2.99E 08 O.OOE-01 CS 137 2.72E 09 1.20E 08 3.28E 10 3.84E 10 1.03E 10 O.OOE-01 4.18E 09 O.OOE-01 BA 140 7.91E 06 3.77E 07 1.54E 08 1.54E 05 3.65E 04 O.OOE-01 9.43E 04 O.OOE-01 CE 141 11.87E 03 3.21 E 06 2.60E 04 1.59E 04 4.90E 03 O.OOE-01 O.OOE-01 O.OOE-01 CE 144 7.82E 04 8.01 E 07 1.40E 06 5.71 E 05 2.31 E 05 O.OOE-01 O.OOE-01 O.OOE-01 HF 181 4.23E 03 3.94E 05 4.78E 04 2.26E 02 1.32E 02 1.91E 02 O.OOE 01 O.OOE 01 AM 241 2.72E 06 1.92E 06 3.65E 07 3.17E 07 1.64E 07 O.OOE 01 O.OOE 01 O.OOE 01

R Values in units of mrem/yr per LtC/M 3 for inhalation and tritium, and in units of m2-mrem/yr per pC/sec for all others.

ODCM (BSEP) 3-58 ReV. 25

TABLE 3.3-12 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Goat Milk AGE GROUP = Adult Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 1.57E 03 1.57E 03 0.00E-01 1.57E 03 1.57E 03 1.57E 03 1.57E 03 1.57E 03 P 32 5.19E 08 1.51 E 09 1.34E 10 8.34E 08 0.00E-01 0.00E-01 0.00E-01 0.00E-01 CR 51 2.08E 03 5.23E 05 0.00E-01 0.OOE-01 4.58E 02 11.24E 03 2.76E 03 0.00E-01 MN 54 1.17E 05 1.88E 06 0.00E-01 6.14E 05 1.83E 05 0.00E-01 0.00E-01 0.00E-01 FE 59 2.082 05 1.81 E 06 2.31 E 05 5.42E 05 0.00E-01 0.00E-01 1.51 E 05 0.00E-01 CO 58 7.54E 05 6.82E 06 0.00E-01 3.36E 05 0.00E-01 0.00E-01 0.00E-01 0.00E-01 CO 60 2.69E 06 2.29E 07 0.00E-01 1.22E 06 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ZN 65 1.65E 08 2.31 E 08 1.15E 08 3.66E 08 2.45E 08 0.00E-01 0.00E-01 0.00E-01 RB 86 9.05E 07 3.83E 07 0.00E-01 1.94E 08 0.OOE-01 0.00E-01 0.00E-01 0.00E-01 SR 89 5.24E 07 2.93E 08 1.83E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 90 1.59E 10 1.88E 09 6.49E 10 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.OOE-01 Y 91 1.64E 01 3.37E 05 6.13E 02 0.OOE-01 0.00E-01 0.OOE-01 0.00E-01 0.00E-01 ZR 95 1.46E 01 6.85E 04 6.74E 01 2.16E 01 3.39E 01 G.OOE-01 0.00E-01 0.00E-01 NB 95 1.78E 03 2.01 E 07 5.94E 03 3.31 E 03 3.27E 03 0.00E-01 0.OOE-01 0.OOE-01 RU 103 3.16E 01 8.56E 03 7.33E 01 0.00E-01 2.80E 02 0.00E-01 0.00E-01 0.OOE-01 RU 106 1.92E 02 9.81 E 04 1.52E 03 0.OOE-01 2.93E 03 0.OOE-01 0.00E-01 0.00E-01 AGi1 OM 2A5E 06 1.68E 09 4.46E 06 4.12E 06 8.11 E 06 0.OOE-01 0.00E-01 0.00E-01 SN 113 1.32E 05 2.44E 06 1.40E 05 5.41 E 03 3.96E 03 1.90E 03 0.00E 01 0.00E 01 TE127M 4.93E 05 1.36E 07 4.05E 06S 1.45E 06 1.64E 07 1.03E 06 0.00E-01 0.00E-01 TE129M 7.43E 05 2.36E 07 4.69E 06 1.75E 06 1.96E 07 1.61 E 06 0.00E-01 0.00E-01 1131 1.91 E 08 8.78E 07 2.33E 08 3.33E 08 5.71 E 08 1.09E 11 0.00E-01 0.00E-01 1132 1.23E-01 6.61 E-02 1.32E-01 3.52E-01 5.61 E-01 1.23E 01 0.00E-01 0.00E-01 1133 1.68E 06 4.95E 06 3.17E 06 5.51 E 06 9.61 E 06 8.10E 08 0.00E-01 0.00E-01 1135 1.08E 04 3.32E 04 1.12E 04 2.94E 04 4.71 E 04 1.94E 06 0.00E-01 0.00E-01 CS 134 2.01E 10 4.31 E 08 1.03E 10 2.46E 10 7.97E 09 0.00E-01 2.65E 09 0.00E-01 CS 136 1.42E 09 2.24E 08 4.99E 08 1.97E 09 1.10E 09 0.00E-01 1.50E 08 0.00E-01 CS 137 1.27E 10 3.74E 08 1.41 E 10 1.93E 10 6.56E 09 0.00E-01 2.18E 09 0.00E-01 BA 140 1.35E 05 4.23E 06 2.06E 06 2.58E 03 8.78E 02 0.00E-01 1.48E 03 0.00E-01 CE 141 2.68E 01 9.03E 05 3.49E 02 2.36E 02 1.10E 02 0.00E-01 0.00E-01 0.00E-01 CE 144 1.38E 03 8.71 E 06 2.58E 04 1.08E 04 6.39E 03 0.00E-01 0.00E-01 0.00E-01 HF 181 8.022 01 5.26E 04 7.09E 02 3.99E 00 3.34E 00 2.54E 00 0.00E 01 0.00E 01 AM 241 1.52E 05 2.09E 05 2.12E 06 1.99E 06 1.15E 06 0.00 01 0.00201 0.002 01 R Values in units of mrem/yr per ptCiM 3 for inhalation and tritium, and in units of m2-mrem/yr per PCisec for all others.

ODCM (BSEP) 3-59 Rev. 25

TABLE 3.3-13 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Goat Milk AGE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 2.04E 03 2.04E 03 0.OOE-01 2.04E 03 2.04E 03 2.04E 03 2.04E 03 2.04E 03 P 32 9.60E 08 2.08E 09 2.48E 10 1.53E 09 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 CR 51 3.63E 03 6.1OE 05 0.OOE-01 0.00E-01 7.95E 02 2.02E 03 5.18E 03 0.OOE-01 MN 54 2.03E 05 2.1 OE 06 0.00E-01 1.02E 06 3.05E 05 0.OOE-01 0.OOE-01 0.OOE-01 FE 59 3.63E 05 2.22E 06 4.03E 05 9.40E 05 0.OOE-01 0.OOE-01 2.96E 05 0.OOE-01 CO 58 1.30E 06 7.80E 06 0.00E-01 5.66E 05 0.00E-01 0.OOE-01 0.00E-01 0.OOE-01 CO 60 4.66E 06 2.69E 07 0.OOE-01 2.07E 06 0.OOE-01 0.00E-01 0.OOE-01 0.OOE-01 ZN 65 2.86E 08 2.60E 08 1.77E 08 6.13E 08 3.93E 08 0.OOE-01 0.OOE-01 0.OOE-01 RB 86 1.66E 08 5.24E 07 0.OOE-01 3.54E 08 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 SR 89 9.65E 07 4.01 E 08 3.37E 09 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 SR 90 2.27E 10 2.58E 09 9.18E 10 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 Y 91 3.02E 01 4.62E 05 1.13E 03 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 ZR 95 2.56E 01 8.59E 04 1.18E 02 3.72E 01 5.47E 01 0.OOE-01 0.OOE-01 0.OOE-01 NB 95 3.09E 03 2.40E 07 1.01 E 04 5.62E 03 5.45E 03 0.OOE-01 0.OOE-01 0.OOE-01 RU 103 5.58E 01 1.09E 04 1.30E 02 0.00E-01 4.60E 02 0.OOE-01 0.OOE-01 0.OOE-01 RU 106 3.51 E 02 1.34E 05 2.79E 03 0.OOE-01 5.38E 03 0.OOE-01 0.OOE-01 0.OOE-01 AG 1 OM1 4.24E 06 1.96E 09 7.37E 06 6.97E 06 1.33E 07 0.OOE-01 0.OOE-01 0.OOE-01 SN 113 2.28E 05 2.58E 06 2.15E 05 9.06E 03 6.37E 03 2.97E 03 0.OOE 01 0.OOE 01 TE127M 8.87E 05 1.86E 07 7.46E 06 2.65E 06 3.02E 07 1.77E 06 0.OOE-01 0.OOE-01 TE129M 1.36E 06 3.22E 07 8.58E 06 3.19E 06 3.59E 07 2.77E 06 0.OOE-01 0.OOE-01 1131 3.18E 08 1.17E 08 4.22E 08 5.91 E 08 1.02E 09 1.73E 11 0.OOE-01 0.OOE-01 1132 2.19E-01 2.66E-01 2.33E-01 6.11 E-01 9.62E-01 2.06E 01 0.OOE-01 0.OOE-01 1133 2.99E 06 7.43E 06 5.79E 06 9.81 E 06 1.72E 07 1.37E 09 0.OOE-01 0.OOE-01 1135 1.90E 04 5.63E 04 1.99E 04 5.13E 04 8.10E 04 3.30E 06 0.OOE-01 0.OOE-01 CS 134 1.96E 10 5.26E 08 1.80E 10 4.23E 10 1.34E 10 0.OOE-01 5.13E 09 0.OOE-01 CS 136 2.25E 09 2.69E 07 8.50E 08 3.34E 09 1.82E 09 0.OOE-01 2.87E 08 0.OOE-01 CS 137 1.19E 10 4.85E 08 2.56E 10 3.41 E 10 1.16E 10 0.OOE-01 4.51 E 09 0.OOE-01 BA 140 2.39E 05 5.72E 06 3.71 E 06 4.55E 03 1.54E 03 0.OOE-01 3.06E 03 0.OOE-01 CE 141 4.91 E 01 1.22E 06 6.40E 02 4.27E 02 2.01 E 02 0.OOE-01 O.OOE-01 0.OOE-01 CE 144 2.55E 03 1.19E 07 4.74E 04 1.96E 04 1.17E 04 0.00E-01 0.OOE-01 0.OOE-01 HF 181 1.41 E 02 6.34E 04 1.27E 03 6.97E 00 5.81 E 00 4.26E 00 0.OOE 01 0.OOE 01 AM 241 2.09E 05 2.86E 05 2.90E 06 2.74E 06 1.57E 06 0.OOE 01 0.OOE 01 0.00E 01

'R Values in units of mrem/yr per pC/m 3 for inhalation and tritium, and in units of m2-mrem/yr per pCi/sec for all others.

ODCM (BSEP) 3-60 Rev. 25

TABLE 3.3-14 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Goat Milk AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 3.23E 03 3.23E 03 O.OOE-01 3.23E 03 3.23E 03 3.23E 03 3.23E 03 3.23E 03 P 32 2.35E 09 1.69E 09 6.11 E 10 2.86E 09 0.OOE-01 0.OOE-01 0.OOE-01 0.00E-01 CR 51 7.40E 03 3.93E 05 O.00E-01 0.OOE-01 1.12E 03 4.11 E 03 7.50E 03 0.OOE-01 MN 54 4.07E 05 1.28E 06 0.OOE-01 1.53E 06 4.29E 05 0.OOE-01 0.OOE-01 0.OOE-01 FE 59 7.52E 05 1.57E 06 9.34E 05 1.51 E 06 0.OOE-01 0.OOE-01 4.38E 05 0.OOE-01 CO 58 2.65E 06 5.05E 06 0.OOE-01 8.65E 05 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 CO 60 9.48E 06 1.78E 07 0.OOE-01 3.21 E 06 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 ZN 65 5.74E 08 1.62E 08 3.47E 08 9.24E 08 5.82E 08 0.00E-01 0.OOE-01 0.OOE-01 RB 86 4.04E 08 4.22E 07 0.OOE-01 6.57E 08 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 SR 89 2.38E 08 3.23E 08 8.34E 09 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 SR 90 3.93E 10 2.09E 09 1.55E 11 0.OOE-01 0.OOE-01 0.OOE-01 0.00E-01 0.OOE-01 Y 91 7.45E 01 3.71 E 05 2.79E 03 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 ZR 95 5.36E 01 6.28E 04 2.74E 02 6.02E 01 8.62E 01 0.OOE-01 0.OOE-01 0.00E-01 NB 95 6.37E 03 1.65E 07 2.29E 04 8.91 E 03 8.37E 03 0.OOE-01 0.OOE-01 0.OOE-01 RU 103 1.19E 02 7.98E 03 3.09E 02 0.OOE-01 7.77E 02 0.OOE-01 0.OOE-01 0.00E-01 RU 106 8.56E 02 1.07E 05 6.86E 03 0.OOE-01 9.27E 03 0.OOE-01 0.OOE-01 0.OOE-01 AG110M 8.63E 06 1.28E 09 1.60E 07 1.08E 07 2.01E 07 0.00E-01 0.OOE-01 0.OOE-01 SN 113 4.61 E 05 1.69E 06 4.22E 05 1.36E 04 9.38E 03 5.59E 03 0.00E 01 0.OOE 01 TE127M 2.18E 06 1.49E 07 1.84E 67 4.95E 06 5.24E 07 4.40E 06 0.OOE-01 0.OOE-01 TE129M 3.28E 06 2.58E 07 2.12E 07 5.91 E 06 6.21 E 07 6.82E 06 0.OOE-01 0.OOE-01 1131 5.85E 08 9.17E 07 1.02E 09 1.03E 09 1.69E 09 3.41 E 11 0.OOE-01 0.OOE-01 1132 4.67E-01 1.19E 00 5.52E-01 1.01 E 00 1.55E 00 4.71 E 01 0.OOE-01 0.OOE-01 1133 6.58E 06 7.OOE 06 1.41 E 07 1.74E 07 2.90E 07 3.23E 09 0.OOE-01 0.OOE-01 1135 4.01E 04 6.47E 04 4.72E 04 8.49E 04 1.30E 05 7.52E 06 0.OOE-01 0.OOE-01 CS 134 1.43E 10 3.67E 08 4.14E 10 6.80E 10 2.11E 10 0.OOE-01 7.56E 09 0.OOE-01 CS 136 3.41E 09 1.85E 08 1.92E 09 5.27E 09 2.81E 09 0.OOE-01 4.19E 08 0.OOE-01 CS 137 8.72E 09 3.70E 08 6.17E 10 5.91 E 10 1.93E 10 0.OOE-01 6.93E 09 0.OOE-01 BA 140 5.23E 05 4.54E 05 8.96E 06 7.85E 03 2.56E 03 0.OOE-01 4.68E 03 0.OOE-01 CE 141 1.17E 02 9.81 E 05 1.53E 03 7.36E 02 3.45E 02 0.00E-01 0.OOE-01 0.OOE-01 CE 144 6.24E 03 9.55E 06 1.17E 05 3.66E 04 2.03E 04 0.OOE-01 0.00E-01 0.OOE-01 HF181 3.04E 02 4.99E 04 3.02E 03 1.17E 01 9.43E 00 9.89E 00 0.OOEO0 0.0E 01 AM 241 3.06E 05 2.29E 05 4.08E 06 3.50E 06 1.87E 06 0.OOE 01 0.OOE 01 0.OOE 01

R Values in units of mrem/yr per ICIm 3 for inhalation and tritium, and in units of 0 2-mrem/yr per pCi/sec for all others.

ODCM (BSEP) 3-61 Rev. 25

TABLE 3.3-15 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Goat Milk AGE GROUP = Infant Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 4.90E 03 4.90E 03 0.OOE-01 4.90E 03 4.90E 03 4.90E 03 4.90E 03 4.90E 03 P 32 4.88E 09 1.70E 09 1.26E 11 7.40E 09 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 CR 51 1.17E 04 3.42E 05 O.OOE-01 0.OOE-01 1.67E 03 7.65E 03 1.49E 04 0.00E-01 MN 54 6.45E 05 1.04E 06 0.OOE-01 2.84E 06 6.30E 05 0.OOE-01 0.OOE-01 0.OOE-01 FE 59 1.20E 06 1.45E 06 1.74E 06 3.04E 06 0.OOE-01 0.00E-01 9.OOE 05 0.OOE-01 CO 58 4.31 E 06 4.31 E 06 0.00E-01 1.73E 06 0.OOE-01 0.00E-01 0.00E-01 0.OOE-01 CO 60 1.55E 07 1.56E 07 0.OOE-01 6.56E 06 0.OOE-01 0.00E-01 0.00E-01 0.00E-01 ZN 65 7.36E 08 1.35E 09 4.66E 08 1.60E 09 7.74E 08 0.OOE-01 0.OOE-01 0.OOE-01 RB 86 8.23E 08 4.26E 07 0.OOE-01 1.67E 09 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 SR 89 4.55E 08 3.26E 08 1.59E 10 0.OOE-01 0.00E-01 0.OOE-01 0.OOE-01 0.OOE-01 SR 90 4.30E 10 2.11 E 09 1.69E 11 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 Y 91 1.39E 02 3.75E 05 5.23E 03 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 0.OOE-01 ZR 95 8.41E 01 5.90E 04 4.85E 02 1.19E 02 1.28E 02 0.OOE-01 0.OOE-01 0.OOE-01 NB 95 11.02E 04 1.48E 07 4.27E 04 1.76E 04 1.26E 04 0.OOE-01 0.OOE-01 0.OOE-01 RU 103 2.09E 02 7.60E 03 6.25E 02 0.OOE-01 1.30E 03 0.OOE-01 0.OOE-01 0.OOE-01 RU 106 11.77E 03 1.07E 05 1.41 E 04 0.OOE-01 1.67E 04 0.OOE-01 0.OOE-01 0.OOE-01 AG1 OM 1.43E 07 1.12E 09 2.95E 07 2.16E 07 3.08E 07 0.OOE-01 0.00E-01 0.OOE-01 SN 113 6.66E 05 1.37E 06 6.46E 05 2.45E 04 1.32E 04 9.34E 03 0.OOE 01 0.OOE 01 TE1 27M 4.51E 06 1.50E 07 3.72E 07, 1.23E 07 9.16E 07 1.08E 07 0.OOE-01 0.OOE-01 TE129M 6.69E 06 2.59E 07 4.34E 07 1.49E 07 1.09E 08 1.67E 07 0.OOE-01 0.OOE-01 1131 1.11E 09 8.99E 07 2.14E 09 2.52E 09 2.94E 09 8.28E 11 0.OOE-01 0.OOE-01 1132 8.28E-01 1.88E 00 1.15E 00 2.33E 00 2.59E 00 1.09E 02 0.OOE-01 0.OOE-01 1133 1.27E 07 7.31 E 06 2.97E 07 4.32E 07 5.08E 07 7.86E 09 0.OOE-01 0.00E-01 1135 7.11E 04 7.06E 04 9.81E 04 1.95E 05 2.17E 05 1.75E 07 0.OOE-01 0.OOE-01 CS 134 1.26E 10 3.38E 08 6.68E 10 1.25E 11 3.21E 10 0.OOE-01 1.31E 10 0.OOE-01 CS 136 4.11 E 09 1.67E 08 3.75E 09 1.10E 10 4.39E 09 0.OOE-01 8.98E 08 0.OOE-01 CS 137 8.17E 09 3.61E 08 9.85E 10 1.15E 11 3.10E 10 0.OOE-01 1.25E 10 0.OOE-01 BA 140 9.50E 05 4.53E 06 1.84E 07 1.84E 04 4.38E 03 0.OOE-01 1.13E 04 0.OOE-01 CE 141 2.24E 02 9.85E 05 3.13E 03 1.91E 03 5.88E 02 0.OOE-01 0.OOE-01 0.OOE-01 CE 144 9.39E 03 9.61 E 06 1.67E 05 6.86E 04 2.77E 04 O.OOE-01 0.OOE-01 0.OOE-01 HF 181 5.08E 02 4.72E 04 5.74E 03 2.71 E 01 1.58E 01 2.30E 01 0.OOE 01 0.OOE 01 AM 241 3.26E 05 2.30E 05 4.38E 06 3.80E 06 1.97E 06 0.OOE 01 0.OOE 01 0.OOE 01

R Values in units of mrem/yr per LPCVm 3 for inhalation and tritium. and in units of m2-mrem/yr per pCi/sec for all others.

ODCM (BSEP) 3-62 Rev. 25

TABLE 3.3-16 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Inhalation AGE GROUP = Adult Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 1.26E 03 1.26E 03 O.OOE-01 1.26E 03 1.26E 03 1.26E 03 1.26E 03 1.26E 03 P 32 5.OOE 04 8.63E 04 1.32E 06 7.70E 04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 9.99E 01 3.32E 03 0.00E-01 O.OOE-01 2.28E 01 5.94E 01 1.44E 04 O.OOE-01 MN 54 6.29E 03 7.72E 04 O.OOE-01 3.95E 04 9.83E 03 O.OOE-01 1.40E 06 O.OOE-01 FE 59 1.05E 04 1.88E 05 1.1 7E 04 2.77E 04 0.00E-01 O.OOE-01 1.01 E 06 O.OOE-01 CO 58 2.07E 03 1.06E 05 O.OOE-01 1.58E 03 O.OOE-01 O.OOE-01 9.27E 05 O.OOE-01 CO 60 1.48E 04 2.84E 05 O.OOE-01 1.15E 04 O.OOE-01 O.OOE-01 5.96E 06 O.OOE-01 ZN 65 4.65E 04 5.34E 04 3.24E 04 1.03E 05 6.89E 04 O.OOE-01 8.63E 05 O.OOE-01 RB 86 5.89E 04 1.66E 04 0.OOE-01 1.35E 05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 8.71 E 03 3.49E 05 3.04E 05 O.OOE-01 O.OOE-01 O.OOE-01 1.40E 06 O.OOE-01 SR 90 6.09E 06 7.21 E 05 9.91 E 07 O.OOE-01 O.OOE-01 O.OOE-01 9.59E 06 O.OOE-01 Y 91 1.24E 04 3.84E 05 4.62E 05 O.OOE-01 O.OOE-01 O.OOE-01 1.70E 06 O.OOE-01 ZR 95 2.32E 04 1.50E 05 1.07E 05 3.44E 04 5.41 E 04 O.OOE-01 1.77E 06 O.OOE-01 NB 95 4.20E 03 1.04E 05 1.41 E 04 7.80E 03 7.72E 03 O.OOE-01 5.04E 05 O.OOE-01 RU 103 6.57E 02 1.1OE 05 1.53E 03 O.OOE-01 5.82E 03 O.OOE-01 5.04E 05 O.OOE-01 RU 106 8.71E 03 9.11E 05 6.90E 04 O.OOE-01 1.33E 05 O.OOE-01 9.35E 06 O.OOE-01 AGl 1tOM 5.94E 03 3.02E 05 1.08E 04 9.99E 03 1.97E 04 O.OOE-01 4.63E 06 O.OOE-01 SN 113 6.48E 03 2.48E 04 6.87E 03 2.66E 02 1.97E 02 9.33E 01 2.99E 05 O.OOE 01 TE1 27M 1.57E 03 1.49E 05 1.26E 0,4 5.76E 03 4.57E 04 3.28E 03 9.59E 05 O.OOE-01 TE129M 1.58E 03 3.83E 05 9.75E 03 4.67E 03 3.65E 04 3.44E 03 1.16E 06 O.OOE-01 1131 2.05E 04 6.27E 03 2.52E 04 3.57E 04 6.12E 04 1.19E 07 O.OOE-01 O.OOE-01 1132 1.16E 03 4.06E 02 1.16E 03 3.25E 03 5.18E 03 1.14E 05 O.OOE-01 O.OOE-01 1133 4.51 E 03 8.87E 03 8.63E 03 1.48E 04 2.58E 04 2.15E 06 O.OOE-01 O.OOE-01 1135 2.56E 03 5.24E 03 2.68E 03 6.97E 03 1.11 E 04 4.47E 05 O.OOE-01 O.OOE-01 CS 134 7.27E 05 1.04E 04 3.72E 05 8.47E 05 2.87E 05 O.OOE-01 9.75E 04 O.OOE-01 CS 136 1.10E 05 1.17E 04 3.90E 04 1.46E 05 8.55E 04 O.OOE-01 1.20E 04 O.OOE-01 CS 137 4.27E 05 8.39E 03 4.78E 05 6.20E 05 2.22E 05 O.OOE-01 7.51 E 04 O.OOE-01 BA 140 2.56E 03 2.18E 05 3.90E 04 4.90E 01 1.67E 01 O.OOE-01 1.27E 06 O.OOE-01 CE 141 1.53E 03 1.20E 05 1.99E 04 1.35E 04 6.25E 03 O.OOE-01 3.61 E 05 O.OOE-01 CE 144 1.84E 05 8.15E 05 3.43E 06 1.43E 06 8.47E 05 O.OOE-01 7.76E 06 O.OOE-01 HF 181 5.16E 03 1.29E 05 4.56E 04 2.57E 02 2.15E 02 1.63E 02 5.99E 05 O.OOE 01 AM 241 5.37E 08 3.68E 05 1.34E 10 9.04E 09 4.03E 09 O.OOE 01 4.85E 08 O.OOE 01

R Values in units of mrem/yr per ptCVm3 for inhalation and tritium, and in units of m2-mrem/yr per piCi/sec for all others.

ODCM (BSEP) 3-63 Rev. 25

TABLE 3.3-17 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT' PATHWAY = Inhalation AGE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 1.27E 03 1.27E 03 O.OOE-01 1.27E 03 1.27E 03 1.27E 03 1.27E 03 1.27E 03 P 32 7.15E 04 9.27E 04 1.89E 06 1.09E 05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 11.35E 02 3.00E 03 O.OOE-01 O.OOE-01 3.07E 01 7.49E 01 2.09E 04 O.OOE-01 MN 54 8.39E 03 6.67E 04 O.OOE-01 5.1 OE 04 1.27E 04 O.OOE-01 1.98E 06 O.OOE-01 FE 59 1.43E 04 1.78E 05 1.59E 04 3.69E 04 O.OOE-01 O.OOE-01 1.53E 06 O.OOE-01 CO 58 2.77E 03 9.51 E 04 O.OOE-01 2.07E 03 O.OOE-01 O.OOE-01 11.34E 06 O.OOE-01 CO 60 1.98E 04 2.59E 05 O.OOE-01 1.51 E 04 O.OOE-01 O.OOE-01 8.71 E 06 O.OOE-01 ZN 65 6.23E 04 4.66E 04 3.85E 04 1.33E 05 8.63E 04 O.OOE-01 1.24E 06 O.OOE-01 RB 86 8.39E 04 1.77E 04 O.OOE-01 1.90E 05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 1.25E 04 3.71 E 05 4.34E 05 O.OOE-01 O.OOE-01 O.OOE-01 2.41 E 06 O.OOE-01 SR 90 6.67E 06 7.64E 05 1.08E 08 O.OOE-01 O.OOE-01 O.OOE-01 1.65E 07 O.OOE-01 Y 91 1.77E 04 4.08E 05 6.60E 05 O.OOE-01 O.OOE-01 O.OOE-01 2.93E 06 O.OOE-01 ZR 95 3.15E 04 1.49E 05 1.45E 05 4.58E 04 6.73E 04 O.OOE-01 2.68E 06 O.OOE-01 NB 95 5.66E 03 9.67E 04 1.85E 04 1.03E 04 9.99E 03 O.OOE-01 7.50E 05 O.OOE-01 RU 103 8.95E 02 1.09E 05 2.10E 03 O.OOE-01 7.42E 03 O.OOE-01 7.82E 05 O.OOE-01 RU 106 1.24E 04 9.59E 05 9.83E 04 O.OOE-01 1.90E 05 O.OOE-01 1.61 E 07 O.OOE-01 AG 1 OMI 7.98E 03 2.72E 05 1.38E 04 1.31 E 04 2.50E 04 O.OOE-01 6.74E 06 O.OOE-01 SN 113 8.69E 03 2.03E 04 8.19E 03 3.45E 02 2.46E 02 1.13E 02 4.27E 05 O.OOE 01 TE127M 2.18E 03 1.59E 05 1.80E 04 8.15E 03 6.53E 04 4.38E 03 1.65E 06 O.OOE-01 TE129M 2.24E 03 4.04E 05 1.39E 04 6.57E 03 5.18E 04 4.57E 03 1.97E 06 O.OOE-01 1131 2.64E 04 6.48E 03 3.54E 04 4.90E 04 8.39E 04 1.46E 07 O.OOE-01 O.OOE-01 1132 1.57E 03 1.27E 03 1.59E 03 4.37E 03 6.91 E 03 1.51 E 05 O.OOE-01 O.OOE-01 1133 6.21 E 03 1.03E 04 1.21 E 04 2.05E 04 3.59E 04 2.92E 06 O.OOE-01 O.OOE-01 1135 3.48E 03 6.94E 03 3.69E 03 9.43E 03 1.49E 04 6.20E 05 O.OOE-01 O.OOE-01 CS 134 5.48E 05 9.75E 03 5.02E 05 1.13E 06 3.75E 05 O.OOE-01 1.46E 05 O.OOE-01 CS 136 1.37E 05 1.09E 04 5.14E 04 1.93E 05 1.1OE 05 O.OOE-01 1.77E 04 O.OOE-01 CS 137 3.11 E 05 8.48E 03 6.69E 05 8.47E 05 3.04E 05 O.OOE-01 1.21 E 05 O.OOE-01 BA 140 3.51E 03 2.28E 05 5.46E 04 6.69E 01 2.28E 01 O.OOE-01 2.03E 06 O.OOE-01 CE 141 2.16E 03 1.26E 05 2.84E 04 1.89E 04 8.87E 03 O.OOE-01 6.13E 05 O.OOE-01 CE 144 2.62E 05 8.63E 05 4.88E 06 2.02E 06 1.21 E 06 O.OOE-01 1.33E 07 O.OOE-01 HF 181 7.05E 03 1.21 E 05 6.32E 04 3.48E 02 2.90E 02 2.12E 02 9.39E 05 0.00E 01 AM 241 5.68E 08 3.90E 05 1.42E 10 9.60E 09 4.26E 09 O.OOE 01 8.40E 08 O.OOE 01

R Values in units of mrem/yr per pCVITr3 for inhalation and tritium, and in units of m2-mrem/yr per gCi/sec for all others.

ODCM (BSEP) 3-64 Rev. 25

TABLE 3.3-18 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Inhalation AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H3 1.12E 03 1.12E 03 O.OOE-01 1.12E 03 1.12E 03 1.12E 03 1.12E 03 1.12E 03 P 32 9.86E 04 4.21E 04 2.60E 06 1.14E 05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.54E 02 1.08E 03 O.OOE-01 O.OOE-01 2.43E 01 8.53E 01 1.70E 04 O.OOE-01 MN 54 9.50E 03 2.29E 04 O.OOE-01 4.29E 04 1.00E 04 O.OOE-01 1.57E 06 O.OOE-01 FE 59 1.67E 04 7.06E 04 2.07E 04 3.34E 04 O.OOE-01 O.OOE-01 1.27E 06 O.OOE-01 CO 58 3.16E 03 3.43E 04 O.OOE-01 1.77E 03 O.OOE-01 O.OOE-01 1.1OE 06 O.OOE-01 CO 60 2.26E 04 9.61 E 04 O.OOE-01 1.31 E 04 O.OOE-01 O.OOE-01 7.06E 06 O.OOE-01 ZN 65 7.02E 04 1.63E 04 4.25E 04 1.13E 05 7.13E 04 O.OOE-01 9.94E 05 O.OOE-01 RB 86 1.14E 05 7.98E 03 O.OOE-01 1.98E 05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 1.72E 04 1.67E 05 5.99E 05 O.OOE-01 O.OOE-01 O.OOE-01 2.15E 06 O.OOE-01 SR 90 6.43E 06 3.43E 05 1.01 E 08 O.OOE-01 O.OOE-01 O.OOE-01 1.47E 07 O.OOE-01 Y 91 2.43E 04 1.84E 05 9.13E 05 O.OOE-01 O.OOE-01 O.OOE-01 2.62E 06 O.OOE-01 ZR 95 3.69E 04 6.10E 04 1.90E 05 4.17E 04 5.95E 04 O.OOE-01 2.23E 06 O.OOE-01 NB 95 6.54E 03 3.69E 04 2.35E 04 9.16E 03 8.61 E 03 O.OOE-01 6.13E 05 O.OOE-01 RU 103 1.07E 03 4.47E 04 2.79E 03 O.OOE-01 7.02E 03 O.OOE-01 6.61E 05 O.OOE-01 RU 106 1.69E 04 4.29E 05 1.36E 05 O.OOE-01 1.84E 05 O.OOE-01 1.43E 07 O.OOE-01 AG110 9.13E 03 1.OOE 05 1.68E 04 1.14E 04 2.12E 04 O.OOE-01 5.47E 06 O.OOE-01 SN 113 9.84E 03 7.45E 03 9.01 E 03 2.91 E 02 2.03E 02 1.19E 02 3.40E 05 O.OOE 01 TE127M 3.01 E 03 7.13E 04 2.48E 04 8.53E 03 6.35E 04 6.06E 03 1.48E 06 O.OOE-01 TE129M 3.04E 03 1.81 E 05 1.92E 04 6.84E 03 5.02E 04 6.32E 03 1.76E 06 O.OOE-01 1131 2.72E 04 2.84E 03 4.80E 04 4.80E 04 7.87E 04 1.62E 07 O.OOE-01 O.OOE-01 1132 1.87E 03 3.20E 03 2.11 E 03 4.06E 03 6.24E 03 1.93E 05 O.OOE-01 O.OOE-01 1133 7.68E 03 5.47E 03 1.66E 04 2.03E 04 3.37E 04 3.84E 06 O.OOE-01 O.OOE-01 1135 4.14E 03 4.43E 03 4.91E 03 8.72E 03 1.34E 04 7.91E 05 O.OOE-01 O.OOE-01 CS 134 2.24E 05 3.84E 03 6.50E 05 1.01 E 06 3.30E 05 O.OOE-01 1.21 E 05 O.OOE-01 CS 136 1.16E 05 4.17E 03 6.50E 04 1.71 E 05 9.53E 04 O.OOE-01 1.45E 04 O.OOE-01 CS 137 1.28E 05 3.61 E 03 9.05E 05 8.24E 05 2.82E 05 O.OOE-01 1.04E 05 O.OOE-01 BA 140 4.32E 03 1.02E 05 7.39E 04 6.47E 01 2.11 E 01 O.OOE-01 1.74E 06 O.OOE-01 CE 141 2.89E 03 5.65E 04 3.92E 04 1.95E 04 8.53E 03 O.OOE-01 5.43E 05 O.OOE-01 CE 144 3.61 E 05 3.88E 05 6.76E 06 2.11 E 06 1.17E 06 O.OOE-01 1.19E 07 O.OOE-01 HF 181 8.50E 03 5.31 E 04 8.44E 04 3.28E 02 2.64E 02 2.76E 02 7.95E 05 O.OOE 01 AM 241 4.59E 08 1.75E 05 1.1 OE 10 6.81 E 09 2.82E 09 O.OOE 01 7.47E 08 O.OOE 01

R Values in units of mrem/yr per ytCi/m3 for inhalation and tritium, and in units ot m2-mrem/yr per gCVsec for all others.

ODCM (BSEP) 3-65 Rev. 25

TABLE 3.3-19 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Inhalation AGE GROUP = Infant Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 6.46E 02 6.46E 02 O.OOE-01 6.46E 02 6.46E 02 6.46E 02 6.46E 02 6.46E 02 P 32 7.73E 04 1.61E 04 2.03E 06 1.12E 05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 8.93E 01 3.56E 02 O.OOE-01 O.OOE-01 1.32E 01 5.75E 01 1.28E 04 O.OOE-01 MN 54 4.98E 03 7.05E 03 O.OOE-01 2.53E 04 4.98E 03 O.OOE-01 9.98E 05 O.OOE-01 FE 59 9.46E 03 2.47E 04 1.35E 04 2.35E 04 O.OOE-01 O.OOE-01 1.01 E 06 O.OOE-01 CO 58 11.82E 03 1.11 E 04 O.OOE-01 1.22E 03 O.OOE-01 O.OOE-01 7.76E 05 O.OOE-01 CO 60 1.1 8E 04 3.19E 04 O.OOE-01 8.01 E 03 O.OOE-01 O.OOE-01 4.50E 06 O.OOE-01 ZN 65 3.1OE 04 5.13E 04 1.93E 04 6.25E 04 3.24E 04 O.OOE-01 6.46E 05 O.OOE-01 RB 86 8.81 E 04 3.03E 03 O.OOE-01 1.90E 05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 1.14E 04 6.39E 04 3.97E 05 O.OOE-01 O.OOE-01 O.OOE-01 2.03E 06 O.OOE-01 SR 90 2.59E 06 1.31 E 05 4.08E 07 O.OOE-01 O.OOE-01 O.OOE-01 1.12E 07 O.OOE-01 Y 91 1.57E 04 7.02E 04 5.87E 05 O.OOE-01 0.OOE-01 O.OOE-01 2.45E 06 O.OOE-01 ZR 95 2.03E 04 2.17E 04 1.15E 05 2.78E 04 3.1OE 04 O.OOE-01 1.75E 06 O.OOE-01 NB 95 3.77E 03 1.27E 04 1.57E 04 6.42E 03 4.71 E 03 O.OOE-01 4.78E 05 O.OOE-01 RU 103 6.78E 02 1.61 E 04 2.01 E 03 O.OOE-01 4.24E 03 O.OOE-01 5.51 E 05 O.OOE-01 RU 106 1.09E 04 1.64E 05 8.67E 04 O.OOE-01 1.06E 05 O.OOE-01 1.15E 07 O.OOE-01 AG1IIM 4.99E 03 3.30E 04 9.97E 03 7.21E 03 1.09E 04 O.OOE-01 3.66E 06 O.OOE-01 SN 113 4.89E 03 2.29E 03 4.68E 03 1.74E 02 9.94E 01 6.73E 01 2.30E 05 O.OOE 01 TE127M 2.07E 03 2.73E 04 1.66E 04 6.89E 03 3.75E 04 4.86E 03 1.31 E 06 O.OOE-01 TE129M 2.22E 03 6.89E 04 1.41 E 04 6.08E 03 3 JE 04 5.47E 03 1.68E 06 O.OOE-01 1131 1.96E 04 1.06E 03 3.79E 04 4.43E 04 5.17E 04 1.48E 07 O.OOE-01 O.OOE-01 1132 1.26E 03 1.90E 03 1.69E 03 3.54E 03 3.94E 03 1.69E 05 O.OOE-01 O.OOE-01 1133 5.59E 03 2.15E 03 1.32E 04 1.92E 04 2.24E 04 3.55E 06 O.OOE-01 O.OOE-01 1135 2.77E 03 1.83E 03 3.86E 03 7.59E 03 8.46E 03 6.95E 05 O.OOE-01 O.OOE-01 CS 134 7.44E 04 1.33E 03 3.96E 05 7.02E 05 1.90E 05 O.OOE-01 7.95E 04 O.OOE-01 CS 136 5.28E 04 1.43E 03 4.82E 04 1.34E 05 5.63E 04 O.OOE-01 1.17E 04 O.OOE-01 CS 137 4.54E 04 1.33E 03 5.48E 05 6.11 E 05 1.72E 05 O.OOE-01 7.12E 04 O.OOE-01 BA 140 2.89E 03 3.83E 04 5.59E 04 5.59E 01 1.34E 01 O.OOE-01 1.59E 06 O.OOE-01 CE 141 1.99E 03 2.15E 04 2.77E 04 1.66E 04 5.24E 03 O.OOE-01 5.16E 05 O.OOE-01 CE 144 11.76E 05 1.48E 05 3.19E 06 1.21 E 06 5.37E 05 O.OOE-01 9.83E 06 O.OOE-01 HF 181 5.05E 03 1.90E 04 5.65E 04 2.66E 02 1.59E 02 2.26E 02 6.73E 05 O.OOE 01 AM 241 1.83E 08 6.69E 04 4.41 E 09 2.73E 09 1.11 E 09 O.OOE 01 5.68E 08 O.OOE 01

R Values in units of mrem/yr per yiCi/m3 for inhalation and tritium, and in units of m2-mrem/yr per pCi/sec for all others.

ODCM (BSEP) 3-66 Rev. 25

INDEX 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM..................... 4-3 T.

ODCM (BSEP) 4-1 Rev. 25

LIST OF TABLES Title Table No.

SECTION 4 4.0-1 Page RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.......................................

4-4 ODCM (BSEP) 4-2 Rev. 25

4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Table 4.0-1 contains the sample 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. Figure 4.0-1 shows the location of various sample points. Figure F-2, Gaseous Radwaste Effluent System, denotes the various release pathways.

I 11 ODCM (BSEP) 4-3 Rev. 26 l

TABLE 4.0-1 DIRECT RADIATION 1

1.1 miles E Q

Q Gamma Dosf 2

1.0 miles ESEQ Q

Gamma Dose 3

0.9 miles SE Q

Q Gamma Dose 4

1.1 miles SSE Q

Q Gamma Dose 5

1.1 miles S Q

Q Gamma Dose 6

1.0 miles SSW Q

Q Gamma Dose 7

1.0 miles SW Q

Q Gamma Dose 8

1.2 miles W Q

Q Gamma Dose 9

1.0 miles WNW Q

Q Gamma Dose 10

.9 miles NW Q

a Gamma Dose 11

.9 miles NNW Q

Q Gamma Dose 121

.9 miles NNW Q

Gamma Dose 12 1.0 miles N Q

Q Gamma Dose 13 1.2 miles NNE

.Q Q

Gamma Dose 14

.5 miles NE Q

Q Gamma Dose 15

.9 miles ENE Q

a Gamma Dose 16 1.0 miles WSW Q

Q Gamma Dose 17 1.5 miles ESE Q

Q Gamma Dose I

Refer to Figure 4.0-1 and Figure F-2.

ODCM (BSEP) 4-4 Rev. 26 I

TABLE 4.0-1 (Cont'd)

Exposure Pathway Sample Sample Point Description, Approximate Distance, Sampling and Analysis Analysis (a) and/or Sample ID No.

and Directionw Collection Frequency.

Frequency DIRECT RADIATION lCont'd) 18 1.7 miles SE Q

Q Gamma Dose 77 5.3 miles S Q

0 Gamma Dose 75 4.5 miles S 0

Gamma Dose 76 4.8 miles SSW Q

Q Gamma Dose 22 5.3 miles SW Q

Gamma Dose 23 4.6 miles WSW Q

a Gamma Dose 24 3.0 miles W Q

0 Gamma Dose 25 8.7 miles WNW 0

Gamma Dose 26 5.9 miles NW a

Q Gamma Dose 27 5.0 miles'NNW Q

a Gamma Dose 79 9.5 miles N Q

Q Gamma Dose 78 10.0 miles NNE Q

0 Gamma Dose 30 2.0 miles NE Q

0 Gamma Dose 31 2.6 miles ENE a

Q Gamma Dose 32 5.7 miles ENE Q

Q Gamma Dose 33 4.0 miles E' Q

Q Gamma Dose 34 5.5 miles ENE Q

Q Gamma Dose 81 10.0 miles WNW (c) a 0

Gamma Dose II ODCM (BSEP) 4-5 Rev. 25

TABLE 4.0-1 (Cont'd)

Exposure Pathway Sample Sample Point Description, Appr xirate Distance, Sampling and Analysis Analysis (a) and/or Sample ID No.

s ariDirection

' Collection

,- 'Frequency y-;

Frequency DIRECT RADIATION 36 9.3 miles NE Q

Q Gamma Dose (Cont'd) 37 5.5 miles NW Q

Q Gamma Dose 38 11.0 miles W Q

Q Gamma Dose 39 5.3 miles SW Q

Q Gamma Dose 40 6.9 miles WSW Q

Q Gamma Dose 20 2.0 miles S Q

0 Q

Gamma Dose 21 2.9 miles SSW a

0 Gamma Dose 28 4.2 miles NW 0

Q Gamma Dose 29 2.6 miles SSW 0

0 Gamma Dose 35 7.5 miles SSE 0

Q Gamma Dose ODCM (BSEP) 4-6 Rev. 25

TABLE 4.0-1 (Cont'd)

Exposure Pathway Sample Sample Point Description, Approximate Distance, Sampling and Analysis Analysis (a) and/or Sample ID No.

and Direction Collection Frequency Frequency IRBORNE 200 1.0 miles SW Visitors Center ontinuous sampler W

Radioiodine Radioiodine and operation with Canister 1-131 Particulate sample collected analysis eekly or as required by dust W

Particulate loading, whichever sampler is more frequent 201 0.6 miles NE PMAC ross beta radioactivity analysis following filter change (b) 202 1.0 miles S Substation - Const. Rd.

Q Gamma isotopic analysis of composite by location 203 2.3 miles SSW Southport Substation 204 23 miles NNE Sutton Plant - Control (c) 205 0.6 SSE Spoil Pond ODCM (BSEP) 4-7 Rev. 25

TABLE 4.0-1 (Cont'd)

Exposure Pathway Sample Sample Point Description, Approximate Distance, Sampling and Analysis Analysis (

and/or Sample ID No.

and Direction Collection Frequency Frequency ATERBORNE 400

.7 miles NE Intake Canal - Control (c)

Composite sample Monthly amma d Collection-M Isotopic

a. Surface 401 4.9 miles SSW Discharge Canal at OD Pumps Q

Tritium

b. Sediment 500 4.9 miles SSW Discharge - Beach near OD Pumps Semiannual Semiannual Gamma Isotopic INGESTION 600 To be identified as available With animals on Semi-Gamma

a. Milk pasture -

monthly isotopic and semi-monthly 1-131 601 At other times -

nalyses monthly (animals on pasture) 602 Monthly Gamma isotopic and 603 1-131 analysis (other times)

b. Fish and 700 5.5 mile SSW Atlantic Ocean (e) at Discharge When in Season - Semiannual Gamma Invertebrates (shrimp)

Semiannual isotopic on edible portions 701 703-705 Not Specified - Atlantic Ocean (C)(e)

ODCM (BSEP) 4-8 Rev. 25

TABLE 4.0-1 (Cont'd)

Exposure Pathway Sample Sample Point Description, Approximate Distance, Sampling and Analysis Analysis (a) and/or Sample ID No.

and Direction Collection Frequency Frequency

c. Broadleaf Vegetation 800 0.7 miles NE Intake Canal hen available -

Monthly Gamma Monthly Isotopic 801 0.6 miles SW Discharge Canal Monthly 1-131 802 10 miles - Control - Location not Specified (c) 803 0.6 miles SSE Spoil Pond (a)

(b)

(c)

(d)

(e)

The LLD for each analysis is specified in Table 7.3.15-3 of the ODCM Specifications for the Brunswick Steam Electric Plant.

Particulate samples will be analyzed for gross beta radiation 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more following filter change. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

Control Station - These stations are presumed to be outside the influence of plant effluents.

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 .

A sample of one free swimmer, one bottom feeder, and one shellfish (shrimp) will be collected if available. A control sample of each species collected will be obtained if available.

ODCM (BSEP) 4-9 Rev. 26 l

FIGURE 4.0-1 I

ODCM (BSEP) 4-10 Rev. 26 I'

INDEX 5.0 INTERLABORATORY COMPARISON STUDIES.......................................

5-2 5.1 OBJECTIVE........................................

5-2 5.2 PROGRAM........................................

5-2 5.2.1 Environmental. Sample Analyses Comparison Program.5-2 5.2.2 Effluent Release Analyses Program.5-2 5.2.3 Abnormal Results............................................................................ 5-2 ODCM (BSEP) 5-1 Rev. 25

5.0 INTERLABORATORY COMPARISON STUDIES 5.1 OBJECTIVE The objective of this program is to evaluate the total laboratory analysis process by comparing results with results obtained by a separate laboratory or laboratories for an equivalent sample.

5.2 PROGRAM 5.2.1 Environmental Sample Analyses Comparison Program Environmental samples from the BSEP environs will be analyzed by the Harris Energy & Environmental Center or by a qualified contracting laboratory. These laboratories will participate at least annually in a interlaboratory comparison study.

The results of the laboratories' performances in the study will be provided to BSEP E&RC and will be included in the Annual Radiological Environmental Operating Report. The results will be provided to the NRC upon request.

5.2.2 Effluent Release Analyses Program BSEP E&RC will perform sample analyses for gamma-emitting radionuclides in effluent releases. The E&RC radiochemistry laboratory will partidipate annually-in a corporate interlaboratory comparison study or equivalent study. The results of these studies will be provided to the NRC upon request.

5.2.3 Abnormal Results CP&L laboratory or vendor laboratory results shall be compared to the criteria established in the NRC Inspection Manual (Procedure 84750) for Radioactive Waste Treatment, Effluent, and Environmental Monitoring. The referenced criteria is as follows:

a.

Divide each standard result by its associated uncertainty to obtain resolution (the uncertainty is defined as the relative standard deviation, or sigma, of the standard result as calculated from counting statistics).

CM (BSEP) 5-2 Rev. 26 OD

b.

Divide each laboratory result by the corresponding standard result to obtain the ratio (laboratory result/standard).

c.

The laboratory measurement is in agreement if the value of the ratio falls within the limits shown below for the corresponding resolution:

Resolution

<4 4 - 7 8-15 16 -50 51 - 200

> 200 Ratio 0.5 - 2.0 0.6 - 1.66 0.75 - 1.33 0.80 - 1.25 0.85 - 1.18 If the CP&L laboratory or vendor laboratory results lie outside the ratio criteria, an evaluation will be performed to identify any recommended remedial actions to reduce anomalous errors.

Complete documentation of the evaluation will be available to BSEP and will be provided to the NRC upon request.

V.

.4 ODCM (BSEP) 5-3 Rev. 26 l

BSEP 03-0003, Radioactive Effluent Release Report for 2002, Enclosure 1 Through Index, Section 5

Text

SUMMARY

6.1 INTRODUCTION

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BSEP 03-0003, Radioactive Effluent Release Report for 2002, Enclosure 1 Through Index, Section 5

Text

SUMMARY

6.1 INTRODUCTION

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