ML051230379

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Radioactive Effluent Release Report January 1, Through December 31, 2004
ML051230379
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 12/31/2004
From:
Progress Energy Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 05-0020
Download: ML051230379 (34)
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Text

BSEP 05-0020 RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2004

Brunswick Steam Electric Plant Radioactive Effluent Release Report January 1, through December 31, 2004 Table of Contents Attachment Pages

1.

Effluent and Waste Disposal Report Supplemental 2 - 5 Information

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 30 Systems

6.

Meteorological Data 31

7.

Annual Dose Assessment 32

8.

Off-Site Dose Calculation Manual (ODCM) and Process 33 Control Program (PCP) Revisions Page 1 of 33 Effluent and Waste Disposal Report Supplemental Information Facility:

Brunswick Steam Electric Plant Licensee:

Carolina Power & Light Company, now doing business as Progress Energy Carolinas, Inc.

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 Quarterl (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 gtCi (ODCM Appendix H)

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

C. Liquid Effluents (ODCMS 7.3.4)

(1) Calendar Quarter 2 (a)

  • 3 mrem to total body (b)
  • 10 mrem to any organ (2) Calendar Year (a)
  • 6 mrem to total body (b)
  • 10 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 2Used for percent of ODCMS limit determination in Attachment 2, Table 2A Page 2 of 33 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 gCi/ml 3 (2) Dissolved and entrained noble gases: limit = 2.OOE-04 J4Ci/ml 3

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.

3 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 33 Effluent and Waste Disposal Report Supplemental Information

4. Batch Releases A. Liquid (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:

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

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 Releases4 A. Liquid (1) Number of releases:

(2) Total activity released:

B. Gaseous 1.50E+01 7.32E+02 Minutes 2.02E+02 Minutes 4.88E+01 Minutes 5.00E+00 Minutes 8.09E+05 Gallons per Minute O.OOE+00 O.OOE+00 Minutes O.OOE+00 Minutes O.OOE+00 Minutes O.OOE+00 Minutes O.OOE+00 O.OOE+00 Curies (1) Number of releases:

(2) Total activity released:

O.OOE+00 O.OOE+00 Curies 4There 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 33 Effluent and Waste Disposal Report Supplemental Information Discussion of tritium in the Storm Drain Stabilization Pond Approximately 3.47E+07 gallons containing 5.16E+01 curies of tritium were released from the Storm Drain Stabilization Pond (SDSP) to the intake canal during this reporting period. This resulted in an estimated maximum dose to the individual of 6.81E-05 mrem. The SDSP is a permitted release point.

Discussion of releases from the Storm Drain Collector Basin Due to heavy rains from Hurricane Charley, the Storm Drain Collector Basin (SDCB) was released directly to the discharge canal on one occasion in 2004. The SDCB is a permitted release point during periods of inclement weather to protect plant personnel and equipment. On August 14t', the SDCB overboard valves were open for 8.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and approximately 1.47E+05 gallons containing 1.29E-02 curies of tritium were released. This resulted in an estimated maximum dose to the individual of 7.51E-09 mrem.

Summary The SDSP 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 SDSP and/or the SDCB is not included in the average diluted concentration determination or VOLUME OF WASTE RELEASED on, Table 2A.

Page 5 of 33 Effluent and Waste Disposal Data Table IA Gaseous Effluents - Summation of all Releases Table lB 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 33 Effluent and Waste Disposal Data Table IA: Gaseous Effluents - Summation of all Releases A. FISSION AND ACTIVATION GASES

1. Total release
2. Average release rate for period
3. Percent of ODCM limit B. IODINES
1. Total Iodine - 131 release
2. Average release rate for period C. PARTICULATES
1. Total release
2. Average release rate for period
3. Gross Alpha D. TRITIUM
1. Total release
2. Average release rate for period Unit Ci pCi/sec Unit Ci pCi/sec Unit Ci pCi/sec Ci Unit Ci pCi/sec Quarter 1 2.96E+01 3.76E+00 5.63E-03 Quarter 1 2.792-03 3.55E-04 Quarter 1 6.69E-04 8.5 lE-05 2.06E-07 Quarter I 4.292+01 5.46E+00 Quarter 2 1.77E+01 2.25E+00 2.072-03 Quarter 2 2.622-03 3.34E-04 Quarter 2 1.68E-04 2.142-05 0.00E+00 Quarter 2 2.792+01 3.552+00 Quarter 3 3.33E+01 4.19E+00 5.63E-03 Quarter 3 2.79E-03 3.51 E-04 Quarter 3 1.86E-04 2.35E-05 0.00E+00 Quarter 3 4.51E+01 5.68E+00 Quarter 4 3.23E+01 4.06E+00 6.45E-03 Quarter 4 2.23E-03 2.80E-04 Quarter 4 1.52E-04 1.9 IE-05 0.00E+00 Quarter 4 4.54E+01 5.711E+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 Page 7 of 33 Effluent and Waste Disposal Data Table IA: Gaseous Effluents - Summation of all Releases E. IODINE-131.IODINE-133. TRITIUM AND PARTICULATES Unit Quarter 1 Quarter 2
1. Total release Ci 4.29E+01 2.79E+01
2. Average release rate for period AiCi/sec 5.46E+00 3.55E1+00
3. Percent of ODCM limit 1.29E-01 8.93E-02 F. PARTICULATES VIA BURINING CONTAMINATED OIL Unit Quarter I Quarter 2
1. Total release Ci O.OOE+00 O.OOE+00
2. Average release rate for period jtCi/sec O.OOE+00 0.00E+00
3. Percent of ODCM limit 0.00E+00 O.OOE+00 Quarter 3 4.51E+01 5.68E+00 9.73E-02 Quarter 3 0.00E+00 0.00E+00 0.00E+00 Quarter 4 4.54E+01 5.72E+00 8.07E-02 Quarter 4 0.00E+00 0.00E+00 O.OOE+00 Page 8 of 33 Effluent and Waste Disposal Data Table 1B: Gaseous Effluents - Elevated Releases Continuous Release Nuclides Released
1. FISSION GASES krypton-85m krypton-87 krypton-88 xenon-133 xenon-133m xenon-135 xenon-135m xenon-137 xenon-138 total for period Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Quarter I 3.98E-01 S LLD

< LLD 1.08E+01

< LLD 1.44E+00 1.63E+00

< LLD 7.02E+00 2.13E+01 Quarter 2 5.99E-01

< LLD

< LLD 1.33E+01 7.76E-02 1.36E+00 1.07E+00

< LLD 4.5 1E-01 1.69E+01 Quarter 3 1.92E+00 8.29E-02 1.46E-01 1.69E+01

< LLD 2.52E+00 1.41E+00 1.10E+00 4.79E+00 2.88E+01 Quarter 4 1.45E+00 3.34E-01 2.76E-01 1.13E+01

< LLD 4.63E+00 6.1 lE+00

< LLD 7.26E+00 3.131E+01

2. GASEOUS IODINES iodine-131 iodine-132 iodine-133 iodine-134 iodine-135 total for period Unit Ci Ci Ci Ci Ci Ci Quarter I 1.73E-03 7.29E-03 7.46E-03 7.76E-03 1.10E-02 3.52E-02 Quarter 2 2.5 1E-03 9.301E-03 8.55E-03 1.13E-02 1.36E-02 4.53E-02 Quarter 3 2.66E-03 1.62E-02 1.30E-02 2.09E-02 2.22E-02 7.5 IE-02 Quarter 4 2.15E-03 2.15E-02 1.69E-02 4.07E-02 2.90E-02 1.IOE-01
3. PARTICULATES chromium-51 manganese-54 cobalt-58 cobalt-60 zinc-65 strontium-89 strontium-90 cesium-134 cesium-137 barium-140 lanthanum-140 total for period Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Quarter 1 9.90E-06 6.08E-06 7.45E-06 2.83E-05 5.14E-06 2.78E-05 4.24E-07 2.73E-06 5.27E-06 7.91E-05 1.47E-04 3.19E-04 Quarter 2 1.95E-05

< LLD 1.06E-05 1.14E-05

<LLD 1.83E-05 3.61E-07

< LLD

< LLD 2.28E-05 1.79E-05 1.01E-04 Quarter 3

< LLD

< LLD

< LLD 1.60E-06

< LLD 2.60E-05 3.20E-07

< LLD

< LLD 5.45E-05 8.1 IE-05 1.63E-04 Quarter 4 S LLD

< LLD

< LLD

< LLD

< LLD 3.1 IE-05 4.06E-07

< LLD 9.66E-07 5.37E-05 4.17E-05 1.28E-04

4. TRITIUM Unit Ci Quarter I Quarter 2 Quarter 3 Quarter 4 5.101E+00 1.22E+01 2.27E+01 1.811E+01 hydrogen-3 Page 9 of 33 Effluent and Waste Disposal Data Table IC: Gaseous Effluents - Ground Level Releases Continuous Release Nuclides Released
1. FISSION GASES xenon-133 xenon-135 total for period Unit Ci Ci Ci Quarter I 7.07E+00 1.18E+00 8.25E+00 Quarter 2

< LLD 8.04E-01 8.04E-01 Quarter 3 3.5 1E+00 9.22E-01 4.43E+00 Quarter 4

< LLD 9.68 E-01 9.68E-01

2.

GASEOUS IODTNES iodine-131 iodine-132 iodine-133 iodine-134 iodine-135 total for period Unit Ci Ci Ci Ci Ci Ci Quarter 1 1.07E-03 2.36E-06 8.85E-04

< LLD 5 LLD 1.96E-03 Quarter 2

1. IIE-04 4.15E-07 4.58E-04

< LLD

< LLD 5.70E-04 Quarter 3 1.38E-04

< LLD 3.97E-04

< LLD

< LLD 5.35E-04 Quarter 4 8.07E-05 1.13E-06 6.3 IE-04

< LLD

<LLD 7.13E-04

3.

PARTICULATES chromium-51 manganese-54 cobalt-58 cobalt-60 zinc-65 strontium-89 strontium-90 cesium-134 cesium-137 barium-140 lanthanum-140 total for period Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Quarter I 2.08E-04 2.588E-06 1.96E-05

1. IIE-04 I < LLD 6.388E-06

< LLD

< LLD 2.38E-06

< LLD S LLD 3.50E-04 Quarter 2 2.44E-05 1.86E-06 5.79E-06 2.77E-05

< LLD 1.19E-06

< LLD 1.85E-06 4.54E-06

< LLD

< LLD 6.73E-05 Quarter 3

< LLD 7.56E-07 1.96E-06 1.13E-05

< LLD

< LLD

< LLD 3.67E-06 5.24E-06

< LLD

< LLD 2.30E-05 Quarter 4

< LLD

< LLD 1.35E-05 1.0IE-05

< LLD

< LLD 2.77E-07

< LLD

< LLD

< LLD

< LLD 2.39E-05

4. TRITIUM Unit Ci Quarter 1 3.78E+01 Quarter 2 1.57E+01 Quarter 3 2.24E+01 Quarter 4 2.73E+01 hydrogen-3 Page 10 of 33 Effluent and Waste Disposal Data Table ID: Gaseous Effluents - Ground Level Releases For Burning Contaminated Oil Nuclides Released
1. PARTICULATES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 No releases made Ci O.OOE+OO O.OOE+OO O.OOE1+OO O.OOE+OO Page 11 of 33 Effluent and Waste Disposal Data Table 2A: Liquid Effluents - Summation of all Releases A. FISSION AND ACTIVATION PRODUCTS (NOTE 1)

Estimated Total Percent Error 4.OOE+01 Unit Quarter I Ci 3.77E-04 Quarter 2 8.14E-04 Quarter 3 6.77E-05 Quarter 4 0.OOE+00

1. Total release (excluding tritium, gases, and alpha)
2. Average diluted concentration (NOTE 2)

PCi/mi 3.05E-10 8.99E-10 6.69E-10 0.00E+00 NA NA

3. Percent of applicable limit 9.39E-04 1.05E-03 8.05E-05 0.OOE+00 B. TRITIUM (NOTE 1)

Estimated Total Percent Error 4.50E+01 Unit Quarter I Ci 1.29E+01 Quarter 2 1.20E+01 Quarter 3 2.88E+01 Quarter 4 0.OOE+00

1. Total release
2. Average diluted concentration (NOTE 2)

PtCi/ml 1.05E-05 1.33E-05 2.85E-04 O.OOE+00 NA NA

3. Percent of applicable limit 1.05E+00 1.33E+00 2.85E+01 0.OOE+00 C. DISSOLVED AND ENTRAINED GASES (NOTE 1)

Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error Ci 9.20E-06 4.56E-05 0.OOE+00 0.OOE+00 4.OOE+01

1. Total release
2. Average diluted concentration (NOTE 2)

AtCi/ml 7.45E-12 5.03E-1I

.OOE+00 0.OOE+00 3.73E-06 2.52E-05 0.00E+00 0.OOE+O0 NA NA

3. Percent of applicable limit D. GROSS ALPHA RADIOACTIVITY Unit Quarter I Ci

< LLD Quarter 2

< LLD Quarter 3

< LLD Quarter 4

< LLD Estimated Total Percent Error 4.OOE+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 Collector Basin and/or Storm Drain Stabilization Pond)

Page 12 of 33 Effluent and Waste Disposal Data Table 2A: Liquid Effluents - Summation of all Releases E. VOLUME OF WASTE RELEASED (NOTE 2)

Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error liters 1.76E+05 9.48E+04 3.54E+03 O.OOE+00 1.50E+01

1. Total volume F. VOLUME OF DILUTION WATER Estimated Total Percent Error 1.50E+01 Unit Quarter 1
1. Total volume liters 1.23E+09 (used during release for average diluted concentration)

Quarter 2 9.05E+08 Quarter 3 1.01E+08 Quarter 4 O.OOE+00 G. VOLUME OF COOLING WATER DISCHARGED FROM PLANT Unit Quarter 1 liters 3.58E+1 1 Quarter 2 4.8 1E+I I Quarter 3 5.18E+1 I Quarter 4 4.56E+1 I 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. Stormn Drain Collection Basin and/or Storm Drain Stabilization Pond)

Page 13 of 33 Effluent and Waste Disposal Data Table 2B: Liquid Effluents - Batch Mode Nuclides Released

1. FISSION AND ACTIVATION PRODUCTS Unit Quarter I Quarter 2 Quarter 3 Quarter 4 magnesium-54 Ci 2.61E-06 1.39E-04 3.89E-06

< LLD iron-55 Ci 6.08E-05 6.07E-05 1.40E-05

< LLD cobalt-60 Ci 2.96E-04 4.55E-04 4.42E-05

< LLD strontium-89 Ci

< LLD

< LLD

< LLD

< LLD strontium-90 Ci

< LLD

< LLD

< LLD

< LLD iodine-131 Ci

< LLD

<LLD

<LLD

<LLD iodine-133 Ci

< LLD

<LLD

< LLD

<LLD cesium-134 Ci

< LLD 2.55E-05 1.13E-06

< LLD cesium-137 Ci 1.38E-05 3.20E-05 4.48E-06

< LLD total for period Ci 3.77E-04 8.14E-04 6.77E-05

< LLD

2.

DISSOLVED AND ENTRAINED GASES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 xenon-133 Ci

< LLD 1.14E-05

< LLD

< LLD xenon-135 Ci 9.20E-06 3.42E-05

< LLD

< LLD total for period Ci 9.20E-06 4.56E-05

< LLD

< LLD Page 14 of 33 Effluent and Waste Disposal Data Lower Limits of Detection Units: p.Ci/ml

1. LIQUID RELEASES
2. GASEOUS RELEASES Alpha H-3 Cr-51 Mn-54 Fe-55 Co-58 Fe-59 Co-60 Zn-65 Sr-89 Sr-90 Mo-99 I-131 1-133 I-135 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 1.22E-08 2.15E-06 1.57E-07 2.02E-08 6.05E-08 2.14E-08 3.57E-08 3.58E-08 3.9 1E-08 3.03E-08 2.27E-08 1.72E-07 1.50E-08 2.30E-08 6.65E-08 2.3 lE-08 1.90E-08 5.77E-08 3.55E-08 2.47E-08 1.02E-07 Kr-85m Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-135m Xe-137 Xe-138 5.18E-09 9.3 1E-09 2.09E-08 9.79E-09 5.24E-08 5.05E-09 5.62E-08 8.42E-07 I.59E-07
3. 1DINES AND PARTICULATES Alpha H-3 Cr-51 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Sr-89 Sr-90 Mo-99 I-131 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 6.43E-16 2.25E-I I 6.37E-13 3.76E-14 3.70E-14 9.23E-14 1.O1E-13 1.65E-13 2.76E-15 1.03E-15 4.06E-13 5.86E-14 8.44E-14 6.22E-14 3.14E-13 1.31E-13 8.28E-14 3.17E-13 3.88E-08 5.53E-08 4.27E-08 1.05E-07 1.80E-08 8.39E-08 2.00E-07 NOTES:
1.

The above values represent typical "a priori" LLDs for isotopes where values of "< LLD" are indicated in Tables IA, IB, 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 "<5 LLD," that nuclide is considered not present and the LLD activity listed is not considered in the summary data.

Page 15 of 33 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) 8.66E+02 Total curie quantity (estimated) 4.02E+01
2.

Tvpe of Waste Unit

a.

Spent resins, filter, sludges meter3 Curies

b. Dry active waste, compacted/non-compacted meter3 Curies Period 3.39E+01 3.69E1+01 8.33E+02 3.26E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 Estimated Total

%Error 1.00E+01 1.00E+01 N/A N/A

c.

Irradiated components

d.

Others (describe) meters3 Curies meters3 Curies

3.

Estimate of maior radionuclides composition

a.

Mn-54 3.50E+00 %

Fe-55 7.70E+00 %

Co-60 6.84E+01 %

Ni-63 8.70E+00 %

Zn-65 1 AOE+00 %

Cs-137 7.70E+00 %

b. Mn-54 5.60E+00 %

Fe-55 5.57E+01 %

Co-60 3.57E+01 %

Ni-63 1.30E+00 %

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 33 Effluent and Waste Disposal Data Table 3A: Solid Waste and Irradiated Fuel Shipments - Waste Class A

4.

Cross reference table. waste stream, form, and container type Stream Form Container Tvpe No.

Type A/Type B

a.

Resin/Filters Dewatered Type A or STP 7.00 of shipments E+00

b.

Dry active waste Compacted/

Non-compacted Type A or STP 1.90E+0l

c.

Irradiated components

d.

Others (describe)

NIA N/A N/A NIA

5.

Shipment Disposition

a.

Solid Waste Number of Shipments 7.00E+00 3.00E+00 1.001E+00 1.50E+01

b.

Irradiated Fuel Number of Shipments 0

Mode of Transportation Highway Highway Highway Rail Mode of Transportation NIA Destination Oak Ridge, TN Erwin, TN Richland, WA Envirocare of Utah Destination N/A Page 17 of 33 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.

Tvye of Waste Unit

a.

Spent resins, filter, sludges meter3 Curies 1.30E+01 2.97E+02 Estimated Total Period

%Error 1.30E+01 2.97E+02 1.00E+01 O.OOE+00 0.00E+00 N/A 0.00E+00 0.00E+00 N/A O.OOE+00 O.OOE+00 N/A

b.

Dry active waste, compacted/non-compacted meter3 Curies

c.

Irradiated components

d.

Others (describe) meters3 Curies meters3 Curies

3.

Estimate of major radionuclides composition

a.

H-3 Mn-54 Fe-55 Co-58 Co-60 Ni-63 Zn-65 Cs-137 1.40E+00 %

4.00E+00 %

2.07E+01 %

2.70E+00 %

5.76E+01 %

4.80E+00 %

3.80E+00 %

3.70E+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 33 Effluent and Waste Disposal Data Table 3B: Solid Waste and Irradiated Fuel Shipments - Waste Class B

4. Cross reference table, waste stream. form, and container tvle Stream Form Container Tvpe Type A/Type B
a.

Resin/Filters Dewatered Type B No. of shipments 3.OOE+00

b. Dry active waste Compacted/

Non-compacted

c.

Irradiated components

d.

Others (describe)

N/A N/A N/A N/A N/A N/A

5.

Shipment Disposition

a.

Solid Waste Number of Shipments 3.00E+00

b.

Irradiated Fuel Number of Shipments 0

Mode of Transportation Highway Mode of Transportation N/A Destination Erwin, TN Destination N/A Page 19 of 33 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) 3.30E+00 Total curie quantity (estimated) 3.19E+04
2.

Tvpe of Waste

a.

Spent resins, filter, sludges

b.

Dry active waste, compacted/non-compacted

c.

Irradiated components

d.

Others (describe)

Unit Curies Curies meters Curies meters 3 Curies Period O.OOE+00 0.00E+00 0.00E+00 0.00E+00 3.30E+00 3.19E+04 0.00E+00 0.00E+00 Estimated Total

%Error N/A N/A l.OOE+01 N/A

3.

Estimate of major radionuclides composition a.

b.

c.

N/A N/A Fe-55 Co-60 Ni-63 Ta-182 2.14E+01 %

7.53E+01 %

1.50E+00 %

1.00E+00 %

d.

N/A NOTE:

Solid Radioactive Waste was shipped directly for disposal.

Page 20 of 33 Effluent and Waste Disposal Data Table 3C: Solid Waste and Irradiated Fuel Shipments - Waste Class C

4.

Cross reference table, waste stream. form. and container type Stream

a.

Resin/Filters Form Dewatered Container Tvpe Type A/Type B N/A No. of shipments N/A

b.

Dry active waste Compacted/

Non-compacted N/A N/A

c.

Irradiated components

d.

Others (describe)

Type B 2.00E+00 N/A N/A

5. Shipment Disposition
a.

Solid Waste Number of Shipments 2.00E+00

b.

Irradiated Fuel Number of Shipments 1.30E+01 Mode of Transportation Highway Mode of Transportation Rail Destination Barnwell, SC Destination New Hill, NC Page 21 of 33 Effluent and Waste Disposal Data Combustion of Waste Oil No contaminated waste oil was incinerated during this report period.

Page 22 of 33 Environmental Monitoring Program :

Milk and Vegetable Sample Location :

Land Use Census Page 23 of 33 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.

A vegetation sample location was added in the South sector from the plant due to recent population growth. Although not required per ODCM 7.3.16, Land Use Census, the sample point was added as an enhancement to the plant's environmental sampling program. The location (reference ODCM Table 4.0-1, Sample ID No. 804) is being established at the site boundary (0.7 miles). The nearest resident for the South sector remains at 1.1 miles from the plant center.

Page 24 of 33 Environmental Monitoring Program : Land Use Census The 2004 Land Use Census did not identify any locations that are reportable in the Radioactive Effluent Release Report for 2004.

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 Residence Garden NNE 0.8 miles None 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 None 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 4.8 miles NNW 0.8 miles 4.4 miles N

0.7 miles None Page 25 of 33 Effluent Instrumentation : : :

Radioactive Liquid Effluent Monitoring Instrumentation Radioactive Gaseous Effluent Monitoring Instrumentation Liquid Hold-Up Tank Page 26 of 33 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 33 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 33 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 33 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 30 of 33 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 33 Annual Dose Assessment Summary Liquid EMuents (1)

Critical Age:

Adult Controlling location for liquid releases: SW sector at 0.1 miles (mrem)

Limit: (mrem)

GI-LLI Bone Liver Lung Total Body Thyroid Kidney 2.07E-04 4.04E-05 4.912-05 1.841-05 3.47E-05 3.52E-06 6.96E-06 2.002+01 2.002+01 2.002+01 2.002+01 6.00E+00 2.OOE+01 2.00E+01 Gaseous Effluents (1)

Noble Gas:

Critical Age:

Infant Controlling location:

NE sector at 0.7 mile (mrad)

Limit: (mrad) 2.00E+01 4.00E+01 Gamma Beta 1.98E-03 1.432-03 Iodine. Particulates. and Tritium:

Critical Age:

Infant Controlling location:

NE sector at 4.75 mile Assuming a cow milk pathway (mrem)

Limit: (mrem)

Thyroid Kidney Liver Total Body Skin GILLI Lung Bone 5.96E-02 1.56E-03 1.54E-03 1.422-03 1.35E-03 1.35E-03 1.35E-03 2.13E-04 3.00E+01 3.00E+01 3.00E+01 3.00E+01 3.00E+01 3.00E+01 3.00E+01 3.00E+01 (I) Reference - dose determined using site specific ODCM software Page 32 of 33 Off-Site Dose Calculation Manual (ODCM) And Process Control Program (PCP) Revisions The PCP was not revised during the report period. ODCM Revision 28 was effective on May 4, 2004. An analysis of the four major changes is as follows:

ODCM Analysis:

1. Updated the list of effective pages for Revision 28.

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

2. Updated Table 3.2-2 to reflect the 2003 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 2003 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 1 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, SSW, and N sectors. Each change was evaluated against the criteria in ODCMS 7.3.16. The results conclude that the changes have a calculated dose less 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 2002 annual source term. No milk animals were identified. The ODCM is being updated to reflect these new locations.

3. Revised environmental sample locations based on an initiative to verify all locations using a 12 channel GPS.

Progress Energy environmental groups have been tasked with utilizing new technology to confirm the locations of all environment sample points. The minor changes to the original locations were made following independent checks using global positioning system (GPS) equipment.

4. Added broadleaf vegetation sample (804) in the South meteorological sector.

The South sector from the plant has experienced a recent population growth. To enhance our environmental sampling program, an additional vegetation sample is being established at the site boundary (0.7 miles). The nearest resident for the South sector remains at 1.1 miles from the plant center.

Page 33 of 33

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