BSEP 02-0085, Radioactive Effluent Release Report for 2001

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Radioactive Effluent Release Report for 2001
ML021220115
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 04/29/2002
From: Noll W
Carolina Power & Light Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 02-0085
Download: ML021220115 (52)
v • d • e


Text

10 CFR 50.36a TS 5.6.3 SERIAL: BSEP 02-0085 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324/LICENSE NOS. DPR-71 AND DPR-62 RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2001 Ladies and Gentlemen:

In accordance with 10 CFR 50.36a and Brunswick Steam Electric Plant (BSEP) Technical Specification 5.6.3, Carolina Power & Light Company submits the enclosed Radioactive Effluent Release Report for BSEP, Unit Nos. I and 2. This report covers the period from January 1, 2001, through December 31, 2001.

No regulatory commitments are contained in this submittal. Please refer any questions regarding this submittal to Mr. Edward T. O'Neil, Manager - Regulatory Affairs, at (910) 457-3512.

Sincerely, William G. Noll Plant General Manager Brunswick Steam Electric Plant CRE/cre

Enclosure:

Radioactive Effluent Release Report for 2001 Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461 CP&L A Progress Energy Company APR 2 9 2002

Document Control Desk BSEP 02-0085 / Page 2 cc (with enclosure):

U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Theodore A. Easlick, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)

ATTN: Ms. Brenda L. Mozafari (Mail Stop OWFN 8G9) 11555 Rockville Pike Rockville, MD 20852-2738 Ms. Jo A. Sanford Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-05 10

BSEP 02-0085 Enclosure RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2001 Brunswick Steam Electric Plant Radioactive Effluent Release Report January 1, through December 31, 2001 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 - 30

5.

Major Modification to the Radioactive Waste Treatment Systems 31

6.

Meteorological Data 32

7. Annual Dose Assessment 33-49
8. Off-Site Dose Calculation Manual (ODCM) and Process Control Program (PCP) Revisions 50 Page 1 of 50

BSEP 02-0085 Enclosure 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 ýtCi (ODCM Appendix H)

(4) Calendar Year for Burning Contaminated Oil (a) < 0.1 % of limits for calendar year (b) 872.tCi (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 50

BSEP 02-0085 Enclosure 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 mremryear 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.LCi/ml**

(2) Dissolved and entrained noble gases: limit = 2.OOE-04 ptCi/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 50

BSEP 02-0085 Enclosure EFFLUENT

4.

Batch Releases A. Liquid (1)

(2)

(3)

(4)

(5)

(6)

ATTACHMENT 1 (cont.)

AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION Number of batch releases:

Total time period for batch releases:

Maximum time period for a batch release:

Average time period for a batch release:

Minimum time period for a batch release:

Average stream flow during periods of release of effluent into a flowing stream:

4.70E+01 5.32E+03 Minutes 3.22E+02 Minutes 1.13E+02 Minutes 1.40E+01 Minutes 8.13E+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:

  • There were no abnormal releases that exceeded 10 CFR 20 or 10 release events that occurred.

Page 4 of 50 0.OOE+00 0.OOE+00 Minutes 0.OOE+00 Minutes 0.OOE+00 Minutes 0.00E+00 Minutes O.OOE+00 0.OOE+00 Curies 0.OOE+00 0.OOE+00 Curies CFR 50 limits. See page 6 for a discussion of

BSEP 02-0085 Enclosure ATTACHMENT 1 (cont.)

EFFLUENT AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION

1. Discussion of Tritium in the Storm Drain Collection Pond Approximately 3.39E+07 gallons containing 9.67E+01 curies of tritium were released from the Storm Drain Collection Pond (SDCP) to the Intake Canal during this reporting period. This resulted in an estimated maximum dose to the individual of 1.83E-04 mrem. The SDCP is a permitted release point.
2. 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 July 6 th for approximately 1.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The SDCB is a permitted release point during periods of inclement weather to protect plant personnel and equipment. Approximately 6.42E+04 gallons containing 1.00E-02 curies of tritium and 1.14E-05 curies of iodine were released during this instance. This resulted in an estimated maximum dose, to the limiting organ (thyroid), of 9.64E-07 mrem. Total body dose related to this release is estimated at 1.44E-08 mrem.
3. Summary SDCP and 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 SDCP 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 50

BSEP 02-0085 Enclosure ATTACHMENT 2 EFFLUENT AND WASTE DISPOSAL DATA Table IA:

Gaseous Effluents - Summation of all Releases Table IB:

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 50

BSEP 02-0085 Enclosure ATTACHMENT 2 (cont.)

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

1. Total release Ci
2. Average release rate for period LCi/sec
3. Percent of ODCM limit B. IODINES Unit
1. Total Iodine-131 release Ci
2. Average release rate for period jCi/sec C. PARTICULATES Unit Quarter 1 1.50E+02 1.93E+01 3.69E-02 Quarter 1 2.33E-03 3.OOE-04 Quarter 1 Quarter 2 1.49E+02 1.90E+01 3.57E-02 Quarter 2 2.71 E-03 3.45E-04 Quarter 2
1. Total release Ci 1.06E-03 5.40E-04
2. Average release rate for period iCi/sec 1.36E-04 6.87E-05
3. Gross Alpha Ci 1.92E-07 4.OOE-08 D. TRITIUM Unit Quarter 1 Quarter 2
1. Total release Ci 4.93E+01 3.36E+01
2. Average release rate for period iCi/sec 6.34E+00 4.27E+00 E. IODINE-131, IODINE-133, TRITIUM AND PARTICULATES Unit Quarter 1 Quarter 2
1. Total release Ci 4.93E+01 3.36E+01
2. Average release rate for period LCi/sec 6.34E+00 4.27E+00
3. Percent of ODCM limit 9.OOE-02 9.67E-02 Quarter 3 1.53E+02 1.92E+01 2.82E-02 Quarter 3 2.64E-03 3.32E-04 Quarter 3 5.89E-04 7.41 E-05 6.76E-08 Quarter 3 3.49E+01 4.40E+00 Quarter 3 3.50E+01 4.40E+00 9.33E-02 Quarter 4 1.55E+02 1.95E+01 3.04E-02 Quarter 4 3.01 E-03 3.79E-04 Quarter 4 6.95E-04 8.74E-05 1.01 E-07 Quarter 4 2.81 E+01 3.54E+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 2.81 E+01 3.54E+00 1.07E-01 Page 7 of 50

BSEP 02-0085 Enclosure 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

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

4 00

2. Average release rate for period
3. Percent of ODCM limit gCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 Page 8 of 50

BSEP 02-0085 Enclosure ATTACHMENT 2 (cont.)

EFFLUENT AND WASTE DISPOSAL DATA Table 1B: Gaseous Effluents - Elevated Releases Continuous Release Nuclides Released

1. FISSION GASES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 krypton-85m Ci 2.79E-01 4.89E+00 6.55E+00 1.23E+00 krypton-87 Ci 9.11 E-01 1.38E+00 8.37E-01 1.54E+00 krypton-88 Ci 7.01 E-02 3.70E+00 1.50E+00

<LLD xenon-133 Ci 1.10E+00 2.50E+01 1.69E+01 5.61E+00 xenon-1 35 Ci 7.41 E+00 8.14E+00 6.31 E+00 7.64E+00 xenon-135m Ci 2.19E+01 2.43E+01 1.53E+01 1.96E+01 xenon-137 Ci 3.32E+01 1.17E+01 4.86E+01 5.50E+01 xenon-1 38 Ci 5.98E+01 5.67E+01 4.23E+01 4.35E+01 total for period 1.25E+02 1.36E+02 1.38E+02 1.34E+02

2. GASEOUS IODINES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 iodine-131 Ci 2.05E-03 2.53E-03 2.48E-03 2.82E-03 iodine-132 Ci 1.22E-02 1.87E-02 1.77E-02 1.98E-02 iodine-133 Ci 1.25E-02 1.68E-02 1.61 E-02 1.91 E-02 iodine-134 Ci 1.92E-02 4.52E-02 2.51 E-02 2.09E-02 iodine-135 Ci 2.05E-02 2.86E-02 2.68E-02 3.1OE-02 total for period 6.64E-02 1.12E-01 8.82E-02 9.36E-02
3. PARTICULATES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 chromium-51 Ci 1.37E-05

<LLD

<LLD

<LLD manganese-54 Ci 1.27E-06

<LLD

<LLD

<LLD cobalt-58 Ci 1.64E-05

<LLD

<LLD

<LLD cobalt-60 Ci 8.32E-05

<LLD 2.08E-06

<LLD strontium-89 Ci 1.16E-04 9.96E-05 1.14E-04 5.08E-05 strontium-90 Ci 3.66E-07 3.64E-07 8.74E-07 1.51 E-06 cesium-134 Ci 4.16E-06

<LLD

<LLD

<LLD cesium-137 Ci 3.60E-05

<LLD

<LLD 3.12E-06 barium-140 Ci 2.01 E-04 1.57E-04 1.72E-04 2.32E-04 lanthanum-1 40 Ci 3.47E-04 2.68E-04 2.71 E-04 3.79E-04 total for period 8.19E-04 5.25E-04 5.60E-04 6.66E-04

4. TRITIUM Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 hydrogen-3 Ci 1.15E+01 1.47E+01 1.79E+01 1.08E+01 Page 9 of 50

BSEP 02-0085 Enclosure 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 Quarter 1

<LLD 9.12E+00 1.61 E+01 2.52E+01

2.

GASEOUS IODINES iodine-1 31 iodine-1 32 iodine-133 iodine-1 34 iodine-135 total for period Unit Ci Ci Ci Ci Ci Quarter 1 2.83E-04 1.46E-03 2.30E-03 2.59E-04 2.1OE-03 6.40E-03 Quarter 2 8.41 E-02 6.13E+00 6.70E+00 1.29E+01 Quarter 2 1.85E-04 2.92E-03 2.01 E-03 3.97E-03 2.53E-03 1.16E-02 Quarter 3 7.02E-01 6.26E+00 7.44E+00 1.44E+01 Quarter 3 1.56E-04 2.63E-04 1.38E-03

<LLD 7.39E-04 2.54E-03 Quarter 4

<LLD 5.74E+00 1.50E+01 2.07E+01 Quarter 4 1.93E-04 5.53E-04 1.57E-03

<LLD 4.67E-04 2.78E-03

3.

PARTICULATES chromium-51 manganese-54 cobalt-58 cobalt-60 strontium-89 strontium-90 cesium-137 barium-140 lanthanum-140 total for period

4. TRITIUM hydrogen-3 Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Unit Ci Quarter 1 5.74E-05 2.25E-06 1.44E-05 1.30E-04 9.OOE-06

<LLD 2.80E-06 7.87E-06 1.49E-05 2.39E-04 Quarter 1 3.78E+01 Quarter 2

<LLD

<LLD 4.11 E-07 1.28E-05 2.14E-06

<LLD

<LLD

<LLD

<LLD 1.54E-05 Quarter 2 1.89E+01 Quarter 3 6.30E-06

<LLD

<LLD 2.27E-05 1.09E-06

<LLD

<LLD

<LLD

<LLD 3.01 E-05 Quarter 3 1.70E+01 Quarter 4 1.68E-05

<LLD

<LLD 6.88E-06 4.50E-06 1.27E-07

<LLD

<LLD

<LLD 2.83E-05 Quarter 4 1.74E+01 Page 10 of 50

BSEP 02-0085 Enclosure 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 0.00E+00 Quarter 2 Quarter 3 0.OOE+00 0.00E+00 Quarter 4 0.OOE+00 Page 11 of 50

BSEP 02-0085 Enclosure 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)
2. Average diluted concentration (NOTE 2)
3. Percent of applicable limit B. TRITIUM (NOTE 1)
1. Total release
2. Average diluted concentration (NOTE 2)
3. Percent of applicable limit iiCi/ml Estimated Total Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error 1.08E-03 4.37E-04 5.21 E-04 3.35E-04 4.OOE+01 2.19E-10 4.59E-10 6.89E-10 1.15E-10 2.54E-03 6.29E-04 6.53E-04 5.79E-04 Unit Quarter 1 Quarter 2 Quarter 3 Ci 7.71 E+01 2.06E+00 3.97E+01 ptCi/ml Quarter 4 3.03E+00 1.56E-05 2.16E-06 5.25E-06 1.04E-06 1.56E+00 2.16E-01 5.25E-01 1.04E-01 NA NA Estimated Total Percent Error 4.50E+01 NA NA C. DISSOLVED AND ENTRAINED GASES (NOTE 1)
1. Total release
2. Average diluted concentration (NOTE 2)
3. Percent of applicable limit Unit Quarter 1 Quarter 2 Quarter 3 Ci 8.03E-03 2.17E-03 4.77E-03 pCi/ml Quarter 4 3.59E-03 1.62E-09 2.28E-09 6.30E-10 1.23E-09 8.11E-04 1.14E-03 3.15E-04 6.16E-04 Estimated Total Percent Error 4.OOE+01 NA NA D. GROSS ALPHA RADIOACTIVITY
1. Total release Unit Quarter 1 Ci

< LLD Quarter 2

< LLD Estimated Total Quarter 3 Quarter 4 Percent Error

< LLD

< LLD 4.OOE+01 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 50

BSEP 02-0085 Enclosure ATTACHMENT 2 (cont.)

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

E. VOLUME OF WASTE RELEASED (NOTE 2)

1. Total volume Unit Quarter 1 Quarter 2 liters 9.09E+05 1.30E+05 Quarter 3 8.47E+05 Quarter 4 4.03E+05 F. VOLUME OF DILUTION WATER Unit Quarter 1
1. Total volume liters 4.95E+09 (used during release for average diluted concentration)

Quarter 2 Quarter 3 9.53E+08 7.56E+09 Quarter 4 2.91 E+09 Estimated Total Percent Error 1.50E+01 Estimated Total Percent Error 1.50E+01 G. VOLUME OF COOLING WATER DISCHARGED FROM PLANT

1. Total volume Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error liters 3.54E+11 4.81E+1 1 5.23E+11 4.68E+11 1.50E+01 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 50

BSEP 02-0085 Enclosure ATTACHMENT 2 (cont.)

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

1. FISSION AND ACTIVATION PRODUCTS manganese-54 iron-55 cobalt-58 cobalt-60 strontium-89 strontium-90 iodine-131 iodine-1 33 cesium-134 cesium-137 total for period Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Quarter 1 1.06E-05 2.95E-04 2.09E-05 6.34E-04

<LLD

<LLD 4.77E-06

<LLD 1.89E-05 9.91 E-05 1.08E-03 Quarter 2 2.02E-06 1.01 E-04

<LLD 2.96E-04

<LLD

<LLD

<LLD

<LLD 4.33E-06 3.34E-05 4.37E-04 Quarter 3

<LLD 1.71 E-04

<LLD 2.87E-04

<LLD

<LLD 6.72E-06 1.64E-05 2.17E-06 3.78E-05 5.21 E-04 Quarter 4

<LLD 4.43E-05

<LLD 2.66E-04

<LLD

<LLD 4.98E-07 9.46E-06

<LLD 1.42E-05 3.35E-04

2.

DISSOLVED AND ENTRAINED GASES Unit xenon-133 Ci xenon-135 Ci total for period Ci Quarter 1 1.16E-03 6.86E-03 8.03E-03 Quarter 2 2.25E-04 1.95E-03 2.17E-03 Quarter 3 5.84E-04 4.18E-03 4.77E-03 Quarter 4 6.48E-04 2.94E-03 3.59E-03 Page 14 of 50

BSEP 02-0085 Enclosure LOWER LIMITS OF DETECTION Units: RCi/ml

1. LIQUID RELEASES Alpha Cr-51 Mn-54 Fe-55 Co-58 Fe-59 Co-60 Zn-65 Sr-89 Sr-90 Mo-99 1-131 1-133 Cs-134 Cs-137 Ce-141 Ce-144 Kr-87 Kr-88 Xe-133 Xe-133m Xe-1 35 Xe-135m Xe-1 38
2. GASEOUS RELEASES Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-1 37 Xe-138 2.48E-08 1.44E-07 2.35E-08 2.57E-08 1.46E-08 2.39E-08 3.79E-08 2.70E-08 1.38E-08 1.34E-08 1.17E-07 1.39E-08 1.42E-08 2.88E-08 2.62E-08 1.97E-08 8.34E-08 3.24E-08 4.35E-08 4.71 E-08 1.30E-07 1.34E-08 4.58E-08 1.33E-07 1.33E-08 1.37E-08 1.32E-08 3.43E-08 4.16E-09 9.62E-07 1.58E-07
3. IODINES AND PARTICULATES Alpha Cr-51 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Sr-89 Sr-90 Mo-99 1-131 Cs-1 34 Cs-137 Ba-140 La-140 Ce-141 Ce-144 1.59E-15 4.67E-13 4.44E-1 4 3.19E-14 1.01 E-13 1.21 E-13 2.28E-13 1.46E-15 1.12E-15 4.72E-1 3 5.43E-14 7.41 E-14 5.04E-14 1.71 E-13 1.37E-13 6.22E-14 2.48E-13 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 50

BSEP 02-0085 Enclosure 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)

Total curie quantity (estimated)

2.

Type of Waste Unit

a.

Spent resins, filter, sludges

b.

Dry active waste, compacted/non-compacted

c.

Irradiated components

d.

Others (describe) meter 3 Curies meter 3

Curies meters 3

Curies meters 3

Curies 1.72E+02 9.32E+01 Estimated Total Period

%Error 3.75E+01 4.52E+01 1.00E+01 1.34E+02 4.80E+O1 1.00E+01 O.OOE+00 O.OOE+00 N/A O.OOE+00 O.OOE+00 N/A

3.

Estimate of major radionuclides composition

a.

C-14 Mn-54 Fe-55 Co-60 Ni-63 Cs-137 Zn-65

b.

Fe-55 Co-60 Ni-63 Cs-134 Cs-137 4.46E+00 %

1.40E+00 %

2.36E+01 %

5.60E+01 %

6.86E+00 %

6.38E+00 %

1.22E+00 %

6.70E+01 %

2.77E+01 %

1.43E+00 %

1.52E+00 %

1.29E+00 %

c.

N/A

d.

N/A NOTE:

Solid Radioactive Waste listed above was shipped shipped to licensed disposal facility.

for processing to various waste processing services or directly Page 16 of 50

BSEP 02-0085 Enclosure 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

a.

Resin Dewatered &

Type A or STP

b.

Dry active waste Solidified*

Compacted/

Non-compacted Type A or STP No. of shipments 2.70E+01 1.20E+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 Transpo 2.70E+01 Highway 1.20E+01 Highway

b.

Irradiated Fuel Number of Shipments Mode of Transpo 0

N/A N/A N/A

'rtation N/A N/A Destination Barnwell, SC Envirocare of Utah Destination N/A rtation Page 17 of 50

BSEP 02-0085 Enclosure 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 Unit

a.

Spent resins, filter, sludges

b.

Dry active waste, compacted/non-compacted

c.

Irradiated components

d.

Others (describe) meter 3 Curies meter 3

Curies meters 3

Curies meters 3

Curies 3.20E+01 1.15E+03 Estimated Total Period

%Error 3.20E+01 1.15E+03 1.00E+01 O.OOE+00 O.OOE+00 N/A O.OOE+00 O.OOE+00 N/A O.OOE+00 O.OOE+00 N/A

3.

Estimate of major radionuclides composition

a.

Cr-51 Mn-54 Fe-55 Co-58 Co-60 Ni-63 Zn-65 Cs-134 Cs-137 1.53E+00 %

1.26E+00 %

1.40E+01 %

2.38E+00 %

6.06E+01 %

9.86E+00 %

1.55E+00 %

1.26E+00 %

7.54E+00 %

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 50

BSEP 02-0085 Enclosure 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 shi Type A/Type B

a.

Resin and filters Dewatered &

Type B 1.60E+01

b.

Dry active waste Solidified*

Compacted/

Non-compacted

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 Transpo 1.60E+01 Highway

b.

Irradiated Fuel Number of Shipments Mode of Transpo 0

N/A pments N/A N/A N/A N/A N/A rtation rtation N/A Destination Barnwell, SC Destination N/A Page 19 of 50

BSEP 02-0085 Enclosure 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 Unit

a.

Spent resins, filter, sludges

b.

Dry active waste, compacted/non-compacted

c.

Irradiated components

d.

Others (describe) meter 3 Curies meter 3

Curies meters 3

Curies meters 3

Curies 5.50E+00 2.04E+01 Estimated Total Period

%Error 5.50E+00 2.04E+01 1.OOE+01 O.OOE+00 O.OOE+00 N/A O.OOE+00 O.OOE+00 N/A O.OOE+00 O.OOE+00 N/A

3.

Estimate of maior radionuclides composition

a.

Fe-55 Co-60 Ni-63 Cs-137 6.42E+01 2.95E+01 3.82E+00 2.55E+00

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 20 of 50

BSEP 02-0085 Enclosure 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 No. of shipments Type A/Type B

a.

Resin and filters Dewatered &

Type B 1.00E+00

b.

Dry active waste Solidified*

Compacted/

Non-compacted

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 Transpo 1.OOE+00 Highwa'

b.

Irradiated Fuel Number of Shipments Mode of Transpc 7.OOE+00 Rail N/A N/A N/A N/A N/A N/A irtation y

Destination Barnwell, S.C.

Destination New Hill, N.C.

rtation Page 21 of 50

BSEP 02-0085 Enclosure ATTACHMENT 2 (cont.)

COMBUSTION OF WASTE OIL No contaminated waste oil was incinerated during this report period.

Page 22 of 50

BSEP 02-0085 Enclosure ATTACHMENT 3 ENVIRONMENTAL MONITORING PROGRAM : :

Milk and Vegetable Sample Location Land Use Census Page 23 of 50

BSEP 02-0085 Enclosure ATTACHMENT 3 (cont.)

ENVIRONMENTAL MONITORING PROGRAM : Milk and Vegetation 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 50

BSEP 02-0085 Enclosure ATTACHMENT 3 (cont.)

ENVIRONMENTAL MONITORING PROGRAM : Land Use Census The 2001 Land Use Census did not identify any locations that are reportable in the Radioactive Effluent Release Report for 2001. The following is a summary of the nearest resident and garden locations identified within five miles of the plant. No milk animals were found within five miles of the plant. Three beef cattle with pasture were found 0.9 miles from the plant, in the SE and SSE sectors.

Direction Residence Garden NNE 0.8 miles 1.2 miles NE None None ENE None None E

None None ESE 1.5 miles None SE 0.9 miles None SSE 1.0 miles None S

1.1 miles 1.1 miles SSW 1.2 miles 1.5 miles SW 1.0 miles 2.9 miles WSW 1.2 miles 1.2 miles W

0.8 miles 1.1 miles WNW 0.8 miles 1.0 miles NW 0.9 miles 1.0 miles NNW 0.8 miles 4.4 miles N

0.7 miles 0.9 miles Page 25 of 50

BSEP 02-0085 Enclosure ATTACHMENT 4 EFFLUENT INSTRUMENTATION : : :

Radioactive Liquid Effluent Monitoring Instrumentation Radioactive Gaseous Effluent Monitoring Instrumentation Liquid Hold-Up Tank Page 26 of 50

BSEP 02-0085 Enclosure ATTACHMENT 4 (cont.)

EFFLUENT INSTRUMENTATION : Radioactive Liquid Effluent Monitoring Instrumentation Although no Radioactive Liquid Effluent Monitoring Instruments were inoperable for a period of greater than 30 days, the Unit 2 Main Service Water System Effluent Radioactivity Monitor remained out-of-service under Technical Requirements Manual (TRM) conditions for over 39 days during the associated refueling outage.

Event Summary:

The Unit 2 Service Water Monitor event consisted of declaring the referenced monitor inoperable due to the monitor indication being below minimum required background counts. The condition occurred due to the securing of hydrogen water chemistry (HWC) injection to the shutdown unit and the associated reduction in background activity. An active TRM (A2-01-0336) was initiated on February 24, 2001, at 1020 hours0.0118 days <br />0.283 hours <br />0.00169 weeks <br />3.8811e-4 months <br />. This required Off-site Dose Calculation Manual Surveillance (ODCMS) compensatory measure actions as stated below:

D. As required by Required D. 1 Collect and analyze a grab Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Compensatory Measure sample for gross A. 1 and referenced in radioactivity (beta or Table 7.3.1-1.

gamma) of the associated effluent. The LLD shall be < 1.0 E-7 pCi/gm.

AND D.2 Restore the channel to 30 days OPERABLE status.

At 21:37 on the same day, the Units 1 and 2 service water systems were cross-tied, eliminating the monitoring pathway.

This action removed the applicability of the compensatory measure as referenced by the following:

ODCMS 7.3.0.2 If the ODCMS is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Compensatory measure(s) is not required, unless otherwise stated.

This crosstie restored the one required channel per function (ODCMS Table 7.3.1-1) for the associated service water pathway. The logical connector (AND) and the Senior Reactor Operator (SRO) notes for the TRM denoted that the subsequent action (D.2) should be reevaluated when the system is no longer cross-tied. The TRM remained in effect until unit restart and monitor evaluation, denoting that the background setpoint needed to be adjusted. Compensatory measures Page 27 of 50

BSEP 02-0085 Enclosure ATTACHMENT 4 (cont.)

EFFLUENT INSTRUMENTATION : Radioactive Liquid Effluent Monitoring Instrumentation (cont.)

began when the service water system was split on March 23, 2001, at 1804 hours0.0209 days <br />0.501 hours <br />0.00298 weeks <br />6.86422e-4 months <br />. The initial TRM was effective for over 39 days prompting a subsequent action as denoted below:

I. Required Compensatory

1. 1 Prepare and submit, in the Upon submittal of current Measure B.3, C.2, D.2, Radioactive Effluent calendar year Radioactive E.2, F.2, or G.2 and Release Report, the reason Effluent Release Report associated Completion the channel was not Time not met.

restored to OPERABLE status within 30 days.

As noted previously, Unit 2 restart and HWC restoration did not eliminate the minimum background problem with the Main Service Water Radioactivity Monitor and required action by Chemistry and Instrumentation and Controls personnel to determine and install new values. The maintenance activity was not scheduled proactively due to the associated parties deciding to wait for the appropriate plant conditions to complete the monitor evaluation. Due to the environmental condition (i.e. the background radiation level surrounding the monitor) contributing to the operability status of the monitor, this approach was necessary to prevent rework and reinstallation of background setpoints. When conditions warranted and the resources were available, the work was completed and the TRM was canceled on April 4, 2001, at 1402 hours0.0162 days <br />0.389 hours <br />0.00232 weeks <br />5.33461e-4 months <br />. In summary, the monitor operability concern was only evident during the time the required channels per function were applicable. This would apply to the period outside the crosstie event and result in a total inoperability of 12.3 days.

This item was determined not to be reportable but is being included in this report for informational purposes.

Page 28 of 50

BSEP 02-0085 Enclosure ATTACHMENT 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 29 of 50

BSEP 02-0085 Enclosure 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 30 of 50

BSEP 02-0085 Enclosure 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. Any major modifications to the radioactive waste treatment systems will be submitted with the UFSAR in accordance with 10 CFR 50.71(e).

Page 31 of 50

BSEP 02-0085 Enclosure 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 32 of 50

BSEP 02-0085 Enclosure ATTACHMENT 7 ANNUAL DOSE ASSESSMENT : : :

2001 Annual Liquid Dose Assessment 2001 Annual Gaseous Dose Assessment 2001 Dose Assessment Summary Page 33 of 50

BSEP 02-0085 Enclosure ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2001 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 34 of 50

BSEP 02-0085 Enclosure ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2001 Annual Liquid Dose Assessment (cont.)

Site Specific Data BSEP UNITS 1 AND 2 LIQUID RELEASES 2001, DISCHARGE = 2.04E+03 CFS SOURCE TERM MULTIPLIER = 1.OOE+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 35 of 50

BSEP 02-0085 Enclosure ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2001 Annual Liquid Dose Assessment (cont.)

Source Term COST-BENEFIT ANALYSIS 0

NUCLIDE RELEASE PERSON-REM DOSE PERSON-REM PER CURIE1 CI/YR TOTAL BODY THYROID TOTAL BODY THYROID 1H 3

1.22E+02 2.41E-03 2.41E-03 1.98E-05 1.98E-05 25MN 54 1.27E-05 1.40E-06 1.14E-08 1.11E-01 9.03E-04 26FE 55 6.11E-04 2.09E-04 3.00E-13 3.42E-01 4.90E-10 27CO 58 2.08E-05 8.14E-07 5.39E-09 3.91E-02 2.59E-04 27CO 60 1.48E-03 1.97E-04 2.22E-05 1.33E-01 1.50E-02 531 131 1.20E-05 5.15E-08 2.93E-05 4.30E-03 2.44E+00 531 133 2.58E-05 3.95E-10 7.92E-08 1.53E-05 3.07E-03 54XE 133 2.62E-03 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 54XE 135 1.59E-02 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 55CS 134 2.54E-05 2.30E-05 1.13E-07 9.04E-01 4.45E-03 55CS 137 1.84E-04 9.96E-05 1.55E-06 5.40E-01 8.40E-03 0 TOTAL 2.94E-03 2.46E-03 Page 36 of 50

BSEP 02-0085 Enclosure ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2001 Annual Liquid Dose Assessment (cont.)

As Low As Reasonably Achievable Maximum Individual Dose (Page 1 of 2)

AS LOW AS REASONABLY ACHIEVABLE I

ADULT DOSES (MREM PER YEAR INTAKE)

___________________________________DOSE_________________________________

BONE

2. 18E-06
3. lOE-06 2.59E-05 2.20E-05 1.31E-08 6.54E-09 2.59E-05 2.73E-05 USAGE (KG/YR,HR/YR) 21.0 5.0 500.0 100.0 100.0 LIVER TOTAL BODY 6.25E-06
3. 55E-06 2.20E-05 1.31E-08
6. 54E-09
3. 19E-05 DILUTION 30.0 30.0 30.0 30.0 30.0 5.25E-06 2.26E-06 2.20E-05 1.31E-08 6.54E-09 2.96E-05 TIME (HR) 24.00 24.00 0.00 0.00 0.00 THYROID 4.51E-06 1.20E-06 2.20E-05 1.31E-08 6.54E-09 2.78E-05 SHOREWIDTH FACTOR=0.5 TEEN DOSES (MREM PER YEAR INTAKE)

___________________________________-DOSE___________________________________

BONE 2.29E-06 3.24E-06 2.59E-05 2.20E-05 1.31E-08 6.54E-09 2.59E-05 2.76E-05 USAGE (KG/YR,HR/YR) 16.0 3.8 500.0 100.0 100.0 LIVER 5.34E-06 3.45E-06 2.20E-05 1.31E-08

6. 54E-09 3.09E-05 DILUTION 30.0 30.0 30.0 30.0 30.0 TOTAL BODY
4. 15E-06 2.04E-06 2.20E-05 1.31E-08
6. 54E-09 2.82E-05 TIME (HR) 24.00 24.00 0.00 0.00 0.00 THYROID 3.49E-06 9.43E-07 2.20E-05 1.31E-08 6.54E-09 2.65E-05 3. 53E-06
8. 54E-07 2.20E-05 1.31E-08
6. 54E-09
2. 64E-05 SHOREWIDTH FACTOR=0.5 Page 37 of 50 0

0 SKIN oPATHWAY FISH INVERT SHORELINE SWIMMING BOATING TOTAL 0

FISH INVERT SHORELINE SWIMMING BOATING KIDNEY

4. 54E-06 1.lIE-06 2.20E-05 1.31E-08 6.54E-09 2.77E-05 0 0 LUNG
5. 20E-06 2.27E-06
2. 20E-05
1. 31E-08
6. 54E-09 2.95E-05 GI-LLI 7.52E-06 7.77E-06 2.20E-05 1.31E-08
6. 54E-09 3.73E-05 SKIN 0PATHWAY FISH INVERT SHORELINE SWIMMING BOATING TOTAL 0

FISH INVERT SHORELINE SWIMMING BOATING 4.35E-06 2.28E-06 2.20E-05 1.31E-08

6. 54E-09 2.87E-05 GI-LLI
5. 64E-06
5. 60E-06 2.20E-05 1.31E-08
6. 54E-09 3.33E-05 KIDNEY LUNG

BSEP 02-0085 Enclosure ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2001 Annual Liquid Dose Assessment (cont.)

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

  • *
  • AS LOW AS REASONABLY ACHIEVABLE * *
  • CHILD DOSES SKIN BONE 2.99E-06
4. 41E-06 2.59E-05 2.20E-05 1.31E-08 6.54E-09 2.59E-05 2.95E-05 USAGE (KG/YR,HR/YR) 6.9 1.7 500.0 100.0 100.0 DOSE LIVER
4. 66E-06 3.32E-06 2.20E-05 1.31E-08
6. 54E-09
3. OOE-05 DILUTION 30.0 30.0 30.0 30.0 30.0 (MREM PER YEAR INTAKE)

TOTAL BODY 3.59E-06 2.16E-06

2. 20E-05 1.31E-08
6. 54E-09 2.78E-05 TIME (HR) 24.00 24.00 0.00 0.00 0.00 THYROID
2. 90E-06
8. 36E-07
2. 20E-05 1.31E-08
6. 54E-09 2.58E-05 SHOREWIDTH FACTOR=0.5 Page 38 of 50 0

0 0PATHWAY FISH INVERT SHORELINE SWIMMING BOATING TOTAL 0

FISH INVERT SHORELINE SWIMMING BOATING KIDNEY 2.92E-06

7. 32E-07 2.20E-05 1.31E-08 6.54E-09 2.57E-05 LUNG 3.64E-06
2. 03E-06 2.20E-05 1.31E-08 6.54E-09 2.77E-05 GI-LLI 3.62E-06 2.50E-06
2. 20E-05 1.31E-08 6.54E-09
2. 82E-05

BSEP 02-0085 Enclosure ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2001 Annual Liquid Dose Assessment (cont.)

Summary - Total Integrated and Recreation Population Dose ANNUAL RADIOLOGICAL EFFLUENT REPORTING RADIATION DOSES FROM LIQUID EFFLUENTS RUN DATE:

04/10/02 RUN TIME:

11:31:23 TOTAL INTEGRATED AND RECREATION POPULATION DOSES FROM LIQUID EFFLUENTS (PERSON-REM)

PATHWAY 0

SPORT FISH 0

COM FISH 0

SPORT INVERT 0

COM INVERT 0

DRINKING WATER 0

SHORELINE 0

SWIMMING 0

BOATING 0

IRRI VEG 0

IRRI LEAFY VEG 0

IRRI MILK 0

IRRI MEAT 0

ALL PATHWAYS BONE 1.312E-03 7.225E-05

0. OOOE+00
6. 303E-05
0. OOOE+00 2.380E-05 3.729E-08 1.766E-08
0. OOOE+00 0. OOOE+00
0. OOOE+00 0. OOOE+00
1. 471E-03 LIVER
3. 306E-03
1. 823E-04
0. OOOE+00
6. 602E-05
0. OOOE+00
2. 380E-05
3. 729E-08
1. 766E-08
0. OOOE+00
0. OOOE+00
0. OOOE+00
0. OOOE+00 TOTAL BODY 2.724E-03 1.502E-04
0. OOOE+00 4.188E-05
0. OOOE+00 2.380E-05 3.729E-08 1.766E-08
0. OOOE+00
0. OOOE+00
0. OOOE+00
0. OOOE+00 THYROID 2.293E-03 1.262E-04
0. OOOE+00
1. 964E-05
0. OOOE+00
2. 380E-05
3. 729E-08 1.766E-08 0 OOOE+00
0. OOOE+00
0. OOOE+00
0. OOOE+00 KIDNEY 2.336E-03 1.289E-04
0. OOOE+00 1.915E-05 0. OOOE+00 2.380E-05 3.729E-08 1.766E-08
0. OOOE+00
0. OOOE+00
0. OOOE+00
0. OOOE+00 LUNG 2 722E-03
1. 502E-04
0. OOOE+00 4.210E-05 0. OOOE+00 2. 380E-05
3. 729E-08
1. 766E-08
0. OOOE+00 0. OOOE+00
0. OOOE+00 0. OOOE+00 GI-LLI
3. 733E-03
2. 059E-04 0

. OOOE+00 1.248E-04

0. OOOE+00 2.380E-05 3.729E-08
1. 766E-08
0. OOOE+00
0. OOOE+00
0. OOOE+00
0. 0O0E+00 SKIN
0. OOOE+00 0 OOOE+00 0 OOOE+00 0 O00E+00
0. OOOE+00 2.798E-05
0. 000*E+00
0. OOOE+00
0. OOOE+00
0. OOOE+00
0. OOOE+00
0. OOOE+00 3.578E-03 2.940E-03 2.462E-03 2.508E-03 2.938E-03 4.087E-03 2.798E-05 Page 39 of 50 1CP&L LADTAP

BSEP 02-0085 Enclosure ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2001 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 lodines, 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 lodines, Particulates, and Tritium for Existing Pathways Page 40 of 50

BSEP 02-0085 Enclosure ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2001 Annual Gaseous Dose Assessment (cont.)

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

GR01YREC GR01YRGC GR01YRMC 1CP&L ANNUAL RADIOLOGICAL EFFLUENT REPORTING RUN DATE:

04/16/02 GASRPT INPUT SOURCE TERNS RUN TIME:

09:21:29 2001 SOURCE TERM (ELEVATED MODE)

BSEP UNITS 1&2 1 H -

3 5.490E+01 24 CR-51 1.370E-05 25 MN-54 1.266E-06 27 CO-58 1.639E-05 27 CO-60 8.526E-05 36 KR-85 M 1.294E+01 36 KR-87 4.667E+00 36 KR-88 5.270E+00 38 SR-89 3.801E-04 38 SR-90 3.112E-06 53 I -131 9.874E-03 53 I -132 6.842E-02 53 I -133 6.454E-02 53 I -134 1.103E-01 53 I -135 1.069E-01 54 XE-133 4.861E+01 54 XE-135 2.950E+01 54 XE-135 M 8.113E+01 54 XE-137 1.485E+02 54 XE-138 2.023E+02 55 CS-134 4.163E-06 55 CS-137 3.915E-05 56 BA-140 7.619E-04 57 LA-140 1.265E-03 SOURCE TERM (GROUND LEVEL) 2001 BSEP UNITS 1 AND 2 1 H -

3 7.665E+01 38 SR-89 1.247E-05 38 SR-90 1.270E-07 53 I -131 9.208E-05 53 I -132 4.367E-04 53 I -133 5.419E-04 53 I -135 2.588E-04 54 XE-133 8.499E-02 54 XE-135 5.556E+00 54 XE-135 M 5.848E-02 56 BA-140 7.870E-06 57 LA-140 1.489E-05 Page 41 of 50

BSEP 02-0085 Enclosure ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2001 Annual Gaseous Dose Assessment (cont.)

Source Term for the Three Release Modes and the Site Aggregate (Page 2 of 2) 1CP&L ANNUAL RADIOLOGICAL EFFLUENT REPORTING RUN DATE:

04/16/02 GASRPT INPUT SOURCE TERMS RUN TIME:

09:21:29 BRUNSWICK UNIT 1 AND 2, MIXED MODE CONTINUOUS GASEOUS RELEASES, 2001 1 H -

3 1.437E+01 24 CR-51 8.046E-05 27 CO-58 1.478E-05 27 CO-60 1.724E-04 38 SR-89 4.242E-06 53 I -131 7.251E-04 53 I -132 4.751E-03 53 I -133 6.726E-03 53 I -134 3.973E-03 53 I -135 4.957E-03 54 XE-133 7.016E-01 54 XE-135 2.170E+01 54 XE-135 M 4.516E+01 55 CS-137 2.796E-06 AGGREGATE SOURCE TERM 1 H -

3 1.4591E+02 24 CR-51 9.4156E-05 25 MN-54 1.2660E-06 27 CO-58 3.1171E-05 27 CO-60 2.5770E-04 36 KR-85 M 1.2940E+01 36 KR-87 4.6675E+00 36 KR-88 5.2701E+00 38 SR-89 3.9679E-04 38 SR-90 3.2389E-06 53 I -131 1.0691E-02 53 I -132 7.3608E-02 53 I -133 7.1808E-02 53 I -134 1.1430E-01 53 I -135 1.1216E-01 54 XE-133 4.9394E+01 54 XE-135 5.6761E+01 54 XE-135 M 1.2635E+02 54 XE-137 1.4846E+02 54 XE-138 2.0232E+02 55 CS-134 4.1630E-06 55 CS-137 4.1943E-05 56 BA-140 7.6977E-04 57 LA-140 1.2795E-03 Page 42 of 50

BSEP 02-0085 Enclosure ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2001 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) 2001 SOURCE TERM (ELEVATED MODE)

BSEP UNITS 1&2 SOURCE TERM (GROUND LEVEL) 2001 BSEP UNITS 1 AND 2 BRUNSWICK UNIT 1 AND 2, RUN DATE:

RUN TIME:

MIXED MODE CONTINUOUS GASEOUS RELEASES, 2001 TOTAL **

PLUME GROUND PLANE INHALATION VEGETATION COW MILK MEAT &

POULTRY TOTAL BODY 4.460E-02 3.746E-03 8.40%

7.798E-04 1.75%

3.467E-02 77.74%

3.477E-03 7.80%

9.549E-05 0.21%

1. 827E-03 4.10%

GI-TRACT

4. 463E-02
3. 746E-03 8.39%

7.798E-04 1.75%

3.470E-02 77.75%

3. 479E-03 7.80%
9. 513E-05 0.21%

1.831E-03 4.10%

BONE

4. 670E-03 3.746E-03 80.21%

7.798E-04 16.70%

4. 803E-05 1.03%

9.062E-05 1.94%

1.183E-06 0.03%

4. 466E-06 0.10%

LIVER

4. 463E-02 3. 746E-03 8.39%

7.798E-04 1.75%

3. 470E-02 77.76%
3. 477E-03 7.79%

9. 594E-05 0.21%

1. 827E-03 4.09%

KIDNEY 4.467E-02 3.746E-03 8.39%

7. 798E-04 1.75%

3.474E-02 77.77%

3.482E-03 7.79%

9.640E-05 0.22%

1. 827E-03 4.09%

THYROID 5.748E-02 3.746E-03 6.52%

LUNG 4.475E-02

3. 829E-03 8.56%

7.798E-04 7.798E-04 1.36%

1.74%

4. 336E-02 75.44%

6.995E-03 12.17%

3.653E-04 0.64%

2. 233E-03 3.88%
3. 475E-02 77.67%
3. 463E-03 7.74%

9.494E-05 0.21%

1. 825E-03 4.08%

Page 43 of 50 1CP&L 04/16/02 09:21:29 SKIN

5. 123E-02 1.028E-02 20.07%
9. 173E-04 1.79%

3. 465E-02 67.63%

3.462E-03 6.76%

9.492E-05 0.19%

1. 825E-03 3.56%

BSEP 02-0085 Enclosure ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2001 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:

04/16/02 09:21:29 2001 SOURCE TERM (ELEVATED MODE)

BSEP UNITS 1&2 SOURCE TERM (GROUND LEVEL) 2001 BSEP UNITS 1 AND 2 BRUNSWICK UNIT 1 AND 2, MIXED MODE CONTINUOUS GASEOUS RELEASES, 2001 SPECIAL LOCATION

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

1 1

1 1

0 ANNUAL BETA AIR DOSE = 4.228E-04 MILLRADS ANNUAL GAMMA AIR DOSE : 5.502E-04 MILLRADS ADULT GROUND PLANE INHALATION VEGETATION COW MILK TOTAL BODY 3.148E-03 6.773E-05 8.945E-04 1.627E-03 5.592E-04 TEENAGER 3.563E-03 GROUND PLANE INHALATION VEGETATION COW MILK CHILD GROUND PLANE INHALATION VEGETATION COW MILK INFANT GROUND PLANE INHALATION COW MILK

6. 773E-05 9.004E-04 1.862E-03 7.321E-04 4.910E-03
6. 773E-05
7. 965E-04 2.885E-03
1. 161E-03 2.300E-03
6. 773E-05
4. 581E-04 1.774E-03 Page 44 of 50 M

0 GI-TRACT 3.150E-03 6.773E-05 8.955E-04 1.633E-03 5.534E-04 3.558E-03 6.773E-05 9.014E-04 1.867E-03

7. 213E-04
4. 869E-03 6.773E-05 7.965E-04 2.875E-03
1. 130E-03 2.236E-03
6. 773E-05
4. 579E-04 1.710E-03 BONE 1.605E-04 6.773E-05 1.476E-06 6.820E-05 2.312E-05 2.058E-04 6.773E-05 1.974E-06
9. 452E-05
4. 161E-05 3.722E-04
6. 773E-05 2.535E-06
2. 019E-04 1.000E-04
2. 668E-04 6.773E-05 1.857E-06 1.972E-04 LIVER 3.158E-03 6.773E-05
8. 957E-04 1.625E-03 5.697E-04 3.584E-03
6. 773E-05
9. 021E-04 1.860E-03
7. 540E-04 4.945E-03
6. 773E-05 7.979E-04 2.881E-03 1.199E-03 2.413E-03
6. 773E-05 4.597E-04 1.886E-03 KIDNEY
3. 174E-03 6.773E-05
8. 970E-04
1. 627E-03 5.830E-04 3. 610E-03 6.773E-05 9.039E-04
1. 860E-03 7.780E-04 4.981E-03 6.773E-05 7.995E-04 2.878E-03 1.235E-03 2.427E-03
6. 773E-05
4. 600E-04
1. 899E-03 THYROID 1.223E-02 6.773E-05 1.166E-03 3.707E-03 7.295E-03 1.633E-02 6.773E-05 1.256E-03 3.589E-03 1.142E-02 2.931E-02 6.773E-05 1.235E-03 5.537E-03 2.247E-02 5.450E-02 6.773E-05 8.591E-04 5.358E-02 LUNG 3.123E-03 6.773E-05
8. 967E-04
1. 614E-03
5. 449E-04
3. 529E-03 6.773E-05
9. 039E-04
1. 848E-03
7. 101E-04
4. 850E-03 6.773E-05
7. 991E-04 2.862E-03 1.122E-03 2.230E-03 6.773E-05
4. 604E-04 1.702E-03 SKIN 3.131E-03
7. 967E-05 8.937E-04 1.613E-03 5.445E-04 3.535E-03
7. 967E-05 8.993E-04 1.847E-03 7.093E-04
4. 856E-03
7. 967E-05 7.953E-04 2.861E-03 1.121E-03 2.237E-03
7. 967E-05 4.573E-04 1.700E-03

BSEP 02-0085 Enclosure ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2001 Annual Gaseous Dose Assessment (cont.)

Maximum Site Boundary Dose by Age Group and Organs for All Pathways (Page 1 of 2)

ANNUAL RADIOLOGICAL EFFLUENT REPORTING RADIATION DOSES AT SELECTED LOCATIONS RUN DATE:

RUN TIME:

04/16/02 09:21:29 2001 SOURCE TERM (ELEVATED MODE)

BSEP UNITS 1&2 SOURCE TERM (GROUND LEVEL) 2001 BSEP UNITS 1 AND 2 BRUNSWICK UNIT 1 AND 2, MIXED MODE CONTINUOUS GASEOUS RELEASES, 2001 SPECIAL LOCATION

  1. 3 SITE BOUNDARY METERS DIR PL GR IN V CM GM M

1127.0 NE 1

1 1

1 1

1 1

ANNUAL BETA AIR DOSE 6.934E-03 MILLRADS ANNUAL GAMMA AIR DOSE = 6.403E-03 MILLRADS TOTAL BODY ADULT 9.428E-02 PLUME GROUND PLANE INHALATION VEGETATION COW MILK GOAT MILK MEAT & POULTRY TEENAGER PLUME GROUND PLANE INHALATION VEGETATION COW MILK GOAT MILK MEAT & POULTRY

4. 253E-03
8. 585E-04
1. 800E-02 3 268E-02 1 116E-02 2 265E-02
4. 681E-03 1.076E-01 4.253E-03 8.585E-04 1.812E-02 3.741E-02 1.458E-02
2. 955E-02 2.794E-03 GI-TRACT 9.417E-02 4.253E-03
8. 585E-04
1. 801E-02 3.276E-02 1.108E-02 2.251E-02
4. 707E-03
1. 073E-01
4. 253E-03 8.585E-04
1. 812E-02 3.747E-02 1.444E-02 2.933E-02
2. 806E-03 BONE
6. 901E-03
4. 253E-03
8. 585E-04
7. 492E-06
9. 651E-04
3. 049E-04 4.886E-04 2.390E-05
7. 902E-03 4.253E-03
8. 585E-04
9. 689E-06 1.338E-03 5. 482E-04 8.755E-04 1.924E-05 LIVER
9. 456E-02
4. 253E-03
8. 585E-04
1. 801E-02 3.264E-02 1.129E-02 2.284E-02
4. 682E-03
1. 082E-01 4.253E-03 8. 585E-04
1. 812E-02 3.737E-02 1.486E-02 2.996E-'02 2.796E-03 Page 45 of 50 1CP&L GASRPT KIDNEY 9.493E-02
4. 253E-03
8. 585E-04 1.801E-02
3. 266E-02
1. 146E-02
2. 299E-02 4.683E-03
1. 088E-01
4. 253E-03
8. 585E-04 1.813E-02 3.737E-02 1.517E-02
3. 025E-02 2.796E-03 THYROID 3.156E-01 4.253E-03 8.585E-04 1.905E-02 5.953E-02 9.809E-02 1.269E-01 6.933E-03 4.362E-01 4.253E-03 8.585E-04 1.949E-02 5.969E-02 1.525E-01 1.950E-01 4.425E-03 LUNG 9.371E-02 4.322E-03
8. 585E-04
1. 801E-02
3. 250E-02
1. 097E-02
2. 239E-02
4. 670E-03 1.068E-01 4.322E-03
8. 585E-04
1. 813E-02
3. 721E-02 1.429E-02 2.917E-02
2. 786E-03 SKIN 1.004E-01 1.087E-02
1. O1OE-03 1.800E-02 3.249E-02
1. 097E-02 2.237E-02 4.670E-03 1.134E-01 1.087E-02 1.010E-03 1.811E-02
3. 720E-02 1.429E-02
2. 914E-02
2. 786E-03

BSEP 02-0085 Enclosure ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2001 Annual Gaseous Dose Assessment (cont.)

Maximum Site Boundary Dose by Age Group and Organs for All Pathways (Page 2 of 2)

ANNUAL RADIOLOGICAL EFFLUENT REPORTING RADIATION DOSES AT SELECTED LOCATIONS RUN DATE:

RUN TIME:

04/16/02 09:21:29 2001 SOURCE TERM (ELEVATED MODE)

BSEP UNITS 1&2 SOURCE TERM (GROUND LEVEL) 2001 BSEP UNITS 1 AND 2 BRUNSWICK UNIT 1 AND 2, MIXED MODE CONTINUOUS GASEOUS RELEASES, 2001 SPECIAL LOCATION

  1. 3 SITE BOUNDARY METERS DIR PL GR IN V CM GM M

1127.0 NE 1

1 1

1 1

1 1

TOTAL BODY CHILD 1.523E-01 PLUME GROUND PLANE INHALATION VEGETATION COW MILK GOAT MILK MEAT & POULTRY INFANT PLUME GROUND PLANE INHALATION COW MILK GOAT MILK

4. 253E-03
8. 585E-04
1. 602E-02
5. 796E-02 2.309E-02
4. 672E-02
3. 376E-03 GI-TRACT
1. 512E-01 4.253E-03
8. 585E-04
1. 602E-02
5. 780E-02 2.270E-02
4. 620E-02 3.376E-03 1.206E-01 1.187E-01 4.253E-03
8. 585E-04
9. 214E-03 3.520E-02 7.106E-02 4.253E-03
8. 585E-04
9. 213E-03
3. 437E-02
7. 001E-02 BONE
1. 142E-02 4.253E-03 8.585E-04
1. 194E-05 2. 853E-03
1. 316E-03 2. 094E-03 3.449E-05
1. 170E-02 4.253E-03
8. 585E-04 8.196E-06 2.592E-03 3.987E-03 LIVER 1.534E-01 4.253E-03 8 585E-04
1. 603E-02
5. 787E-02
2. 357E-02 4.747E-02 3.379E-03 1.241E-01
4. 253E-03
8. 585E-04 9.220E-03 3.663E-02 7.316E-02 KIDNEY 1.543E-01 4.253E-03 8.585E-04
1. 603E-02
5. 784E-02 2.404E-02 4.789E-02
3. 379E-03 THYROID 7.957E-01 4.253E-03 8.585E-04 1.771E-02 9.219E-02 2.981E-01 3.767E-01 5.840E-03 1.242E-01 1.593E+00 4.253E-03
8. 585E-04
9. 221E-03
3. 681E-02 7.305E-02
4. 253E-03 8.585E-04 1.076E-02 7.039E-01
8. 735E-01 LUNG SKIN 1.509E-01 1.575E-01
4. 322E-03
8. 585E-04 1.603E-02
5. 763E-02 2.258E-02
4. 609E-02 3.366E-03 1.186E-01 4.322E-03
8. 585E-04 9.224E-03 3.427E-02 6.994E-02 1.087E-02
1. 010E-03
1. 602E-02 5.762E-02
2. 257E-02
4. 604E-02 3.365E-03 1.252E-01
1. 087E-02
1. 010E-03 9.211E-03 3.424E-02 6.986E-02 Page 46 of 50 1CP&L GASRPT

BSEP 02-0085 Enclosure ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2001 Annual Gaseous Dose Assessment (cont.)

Estimated Individual Organ Dose Using the 2001 Land Use Census for the Worst Sector and Existing Pathway ANNUAL RADIOLOGICAL EFFLUENT REPORTING RADIATION DOSES AT SELECTED LOCATIONS RUN DATE:

RUN TIME:

04/16/02 09:21:29 2001 SOURCE TERM (ELEVATED MODE)

BSEP UNITS 1&2 SOURCE TERM (GROUND LEVEL) 2001 BSEP UNITS 1 AND 2 BRUNSWICK UNIT 1 AND 2, MIXED MODE CONTINUOUS GASEOUS RELEASES, 2001 SPECIAL LOCATION

  1. 22 RESIDENCE METERS DIR PL GR IN 1770.0 S

1 1

1 V CM GM M

1 0

0 0

ANNUAL BETA AIR DOSE = 3.802E-03 MILLRADS ANNUAL GAMMA AIR DOSE

= 3.487E-03 MILLRADS ADULT PLUME GROUND PLANE INHALATION VEGETATION TOTAL BODY 6.433E-02 2.310E-03 1.560E-04 2.204E-02 3.982E-02 TEENAGER 7.024E-02 PLUME GROUND PLANE INHALATION VEGETATION CHILD PLUME GROUND PLANE INHALATION VEGETATION INFANT PLUME GROUND PLANE INHALATION 2.310E-03

1. 560E-04 2.218E-02 4.559E-02 9.270E-02 2.310E-03 1.560E-04 1.962E-02 7.062E-02 1.375E-02 2.310E-03 1.560E-04 1.128E-02 Page 47 of 50 1CP&L GASRPT GI-TRACT
6. 435E-02 2.310E-03 1.560E-04 2.205E-02
3. 984E-02
7. 026E-02 2.310E-03 1.560E-04 2. 219E-02
4. 560E-02
9. 267E-02 2.310E-03 1. 560E-04 1.962E-02 7.059E-02 1.375E-02
2. 310E-03 1.560E-04
1. 128E-02 BONE 2.683E-03 2.310E-03
1. 560E-04 6.249E-06
2. 103E-04
2. 766E-03
2. 310E-03 1.560E-04 7.927E-06 2.916E-04 3.097E-03 2.310E-03
1. 560E-04
9. 525E-06 6.212E-04
2. 473E-03 2.310E-03
1. 560E-04
6. 255E-06 LIVER
6. 432E-02 2.310E-03 1.560E-04 2.205E-02 3.981E-02 7.024E-02 2.310E-03
1. 560E-04 2.219E-02 4.558E-02 9.269E-02 2.310E-03
1. 560E-04
1. 962E-02 7.060E-02 1.375E-02 2.310E-03 1.560E-04 1.128E-02 KIDNEY 6.433E-02 2.310E-03
1. 560E-04 2.205E-02
3. 982E-02
7. 024E-02 2.310E-03
1. 560E-04
2. 219E-02
4. 559E-02 9.269E-02 2.310E-03
1. 560E-04
1. 962E-02
7. 060E-02 1.375E-02 2.310E-03
1. 560E-04 1.128E-02 THYROID 7.062E-02 2.310E-03 1.560E-04 2.278E-02 4.538E-02 7.581E-02 2.310E-03 1.560E-04 2.314E-02 5.020E-02 1.010E-01 2.310E-03 1.560E-04 2.080E-02 7.770E-02 1.483E-02 2.310E-03 1.560E-04 1.236E-02 LUNG 6.434E-02 2 349E-03
1. 560E-04 2.205E-02
3. 978E-02
7. 025E-02
2. 349E-03 1.560E-04 2. 219E-02
4. 555E-02 9.268E-02 2.349E-03 1.560E-04 1.962E-02
7. 055E-02 1.379E-02
2. 349E-03
1. 560E-04 1.129E-02 SKIN
6. 772E-02 5.714E-03 1.835E-04 2.204E-02
3. 978E-02
7. 363E-02 5.714E-03 1.835E-04 2.218E-02
4. 555E-02 9.606E-02
5. 714E-03 1.835E-04 1.961E-02 7.055E-02 1.718E-02 5.714E-03
1. 835E-04 1.128E-02

BSEP 02-0085 Enclosure ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2001 Annual Gaseous Dose Assessment (cont.)

Maximum Site Boundary Dose Due to lodines, Particulates, and Tritium for Existing Pathways ANNUAL RADIOLOGICAL EFFLUENT REPORTING RADIATION DOSES AT SELECTED LOCATIONS RUN DATE:

RUN TIME:

04/16/02 09:38:48 2001 SOURCE TERM (ELEVATED MODE)

BSEP UNITS 1&2 SOURCE TERM (GROUND LEVEL) 2001 BSEP UNITS 1 AND 2 BRUNSWICK UNIT 1 AND 2, MIXED MODE CONTINUOUS GASEOUS RELEASES, 2001 SPECIAL LOCATION

  1. 8 SITE BOUNDARY METERS DIR PL GR IN V CM GM 1127.0 SSE 0

1 1

0 0

0 ANNUAL BETA AIR DOSE : 1.669E-02 MILLRADS ANNUAL GAMMA AIR DOSE : 1.338E-02 MILLRADS ADULT GROUND PLANE INHALATION TOTAL BODY 1.228E-01 2.500E-04 1.225E-01 GI-TRACT 1.228E-01 2. 500E-04 1.225E-01 BONE 2.792E-04 2.500E-04 2.918E-05 TEENAGER 1.235E-01 1.236E-01 2.865E-04 GROUND PLANE INHALATION CHILD GROUND PLANE INHALATION INFANT GROUND PLANE INHALATION 2.500E-04

1. 233E-01 2. 500E-04 1.233E-01 2.500E-04
3. 652E-05 1.093E-01 1.093E-01 2.931E-04 2.500E-04
1. 090E-01
2. 500E-04 1.090E-01 6.294E-02 6.294E-02
2. 500E-04 6.269E-02
2. 500E-04 6.269E-02
2. 500E-04 4.306E-05 2.773E-04 2.500E-04 2.733E-05 LIVER 1.228E-01
2. 500E-04 1.225E-01 1.236E-01 2.500E-04 1.233E-01
1. 093E-01 2.500E-04 1.090E-01 6.296E-02 2.500E-04
6. 271E-02 KIDNEY 1.228E-01 2.500E-04 1.225E-01 1.236E-01 2. 500E-04 1.233E-01 1.093E-01 2.500E-04 1.090E-01 6.296E-02 2.500E-04
6. 271E-02 THYROID 1.258E-01 2.500E-04 1.255E-01 1.274E-01 2.500E-04 1.272E-01 1.140E-01 2.500E-04 1.138E-01 6.731E-02 2.500E-04 6.706E-02 LUNG SKIN 1.228E-01 1.228E-01
2. 500E-04 1.225E-01 1.236E-01
2. 500E-04 1.233E-01
1. 093E-01 2.500E-04 1.091E-01 6.298E-02 2.500E-04 6.273E-02
2. 941E-04 1.225E-01 1.236E-01
2. 941E-04
1. 233E-01 1. 093E-01 2.941E-04
1. 090E-01 6.298E-02 2.941E-04
6. 268E-02 Page 48 of 50 ICP&L GASRPT M

0

BSEP 02-0085 Enclosure ATTACHMENT 7 (cont.)

ANNUAL DOSE ASSESSMENT : 2001 Dose Assessment Summary

1. Liquid Effluents:

Maximum Dose to Individual: (mrem)

Limit: (mrem)

Adult GI-LLI 3.73E-05 2.OOE+01 Adult Total Body 2.96E-05 6.OOE+00 Total Integrated and Recreation Population Dose: (person-rem)

Total Body 2.94E-03 II. Gaseous Effluents Noble Gas Air Dose at Site Boundary: (mrad)

Limit: (mrad)

Gamma 1.34E-02 2.OOE+01 Beta 1.67E-02 4.OOE+01 Iodine-131, Iodine-133, Tritium and Particulates: (mrem)

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

1.59E+00 Maximum hypothetical dose due to iodines, particulates, and tritium at 4.75 miles for the cow milk pathway per ODCM (infant thyroid): 5.80E-02 Estimated organ dose due to iodines, particulates, and tritium for existing pathways to maximum exposed individual (child thyroid):

1.01E-01 Total 50 Mile Annual Integrated Population Dose: (person-rem)

Thyroid:

5.75E-02 Total Body:

4.46E-02 Limit:

3.OOE+01 Page 49 of 50

BSEP 02-0085 Enclosure ATTACHMENT 8 OFF-SITE DOSE CALCULATION MANUAL (ODCM) AND PROCESS CONTROL PROGRAM (PCP) REVISIONS The ODCM was not revised during the report period.

The PCP was not revised during the report period.

Page 50 of 50

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