ML071240280

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Enclosure 1 - Brunswick, Unit 1 and 2, BSEP 07-0036, Radioactive Effluent Release Report for 2006
ML071240280
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 04/30/2007
From:
Progress Energy Carolinas
To:
Office of Nuclear Reactor Regulation
References
BSEP 07-0036
Download: ML071240280 (37)
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Text

Enclosure 1 BSEP 07-0036 Radioactive Effluent Release Report for 2006

Brunswick Steam Electric Plant Radioactive Effluent Release Report January 1, through December 31, 2006 Table of Contents Attachment PaRa_

1. Effluent and Waste Disposal Report Supplemental 2 - 5 Information
2. Effluent and Waste Disposal Data 6 - 24
3. Environmental Monitoring Program 25 - 27
4. Effluent Instrumentation 28-31
5. Major Modification to the Radioactive Waste Treatment 32 Systems
6. Meteorological Data 33
7. Annual Dose Assessment 34
8. Off-Site Dose Calculation Manual (ODCM) and Process 35 Control Program (PCP) Revisions Page 1 of 35

Attachment 1 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 Quarter' (a) _<15 mrem to any organ (2) Calendar Year (a) _<30 mrem to any organ (3) Calendar Quarter for Burning Contaminated Oil0 (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 p.Ci (ODCM Appendix H)

C. Liquid Effluents (ODCMS 7.3.4) 2 (1) Calendar Quarter (a) < 3 mrem to total body (b) < 10 mrem to any organ (2) Calendar Year (a) < 6 mrem to total body (b) < 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 1A 2 Used for percent of ODCMS limit determination in Attachment 2, Table 2A Page 2 of 35

Attachment 1 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 mremryear 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 ýtCi/ml 3 (2) Dissolved and entrained noble gases: limit = 2.OOE-04 [tCi/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. lodines (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.

3Used 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 35

Attachment 1 Effluent and Waste Disposal Report Supplemental Information

4. Batch Releases A. Liquid (1) Number of batch releases: 6.1 OE+O 1 (2) Total time period for batch releases: 5.88E+03 Minutes (3) Maximum time period for a batch release: 3.OOE+02 Minutes (4) Average time period for a batch release: 9.64E+01 Minutes (5) Minimum time period for a batch release: 1.20E+01 Minutes (6) Average stream flow during periods of release of effluent into a flowing stream: 7.32E+05 Gallons per Minute B. Gaseous (1) Number of batch releases: O.OOE+00 (2) Total time period for batch releases: O.OOE+00 Minutes (3) Maximum time period for a batch release: O.OOE+00 Minutes (4) Average time period for a batch release: O.OOE+00 Minutes (5) Minimum time period for a batch release: O.OOE+00 Minutes
5. Abnormal Releases 4 A. Liquid (1) Number of releases: O.OOE+00 (2) Total activity released: O.OOE+00 Curies B. Gaseous (1) Number of releases: O.OOE+00 (2) Total activity released: O.OOE+00 Curies 4 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 35

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Discussion of tritium in the Storm Drain Stabilization Pond Approximately 3.30E+07 gallons containing 1.02E+02 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 1.41E-04 mrem. The SDSP is a permitted release point.

Discussion of releases from the Storm Drain Collector Basin Due to heavy rain events, the Storm Drain Collector Basin (SDCB) was released directly to the discharge canal on five occasions in 2006. The SDCB is a permitted release point during periods of inclement weather to protect plant personnel and equipment. Approximately 5.96E+05 gallons containing 7.27E-01 curies of tritium and 2.33E-03 curies of iodine were released. This resulted in an estimated maximum dose to the individual of 1.49E-06 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 35

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 1D 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 35

Attachment 2 Effluent and Waste Disposal Data Table IA: Gaseous Effluents - Summation of all Releases A. FISSION AND ACTIVATION GASES Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Qu arter 4 Percent Error

1. Total release Ci 1.87E+02 5.71E+02 7.84E+02 7.1' 7E+02 4.50E+01
2. Average release rate for period ptCi/sec 2.41E+01 7.27E+01 9.87E+01 9.012E+01 NA
3. Percent of ODCM limit  % 3.80E-02 1.84E-01 5.06E-01 1.5 IE-01 NA B. IODINES Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error
1. Total Iodine - 131 release Ci 2.02E-02 4.06E-02 5.43E-02 3.76E-02 3.50E+01
2. Average release rate for period ktCi/sec 2.60E-03 5.16E-03 6.83E-03 4.74E-03 NA C. PARTICULATES Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error
1. Total release Ci 1.59E-03 7.91E-03 2.14E-02 9.95E-03 3.50E+01
2. Average release rate for period .tCi/sec 2.05E-04 1.01E-03 2.69E-03 1.25E-03 NA
3. Gross Alpha Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.50E+01 D. TRITIUM Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error
1. Total release Ci 6.15E+01 6.53E+01 8.36E+01 4.25E+01 3.OOE+01
2. Average release rate for period lpCi/sec 7.9 1E+00 8.30E+00 1.05E+01 5.34E+00 NA Page 7 of 35

Attachment 2 Effluent and Waste Disposal Data Table IA: Gaseous Effluents - Summation of all Releases E. IODINE- 131, IODINE- 133, TRITIUM AND PARTICULATES Unit Quarter I Quarter 2 Quarter 3 Quarter 4

1. Total release Ci 6.16E+O1 6.56E+01 8.42E+01 4.28E+01
2. Average release rate for period jiCi/sec 7.93E+00 8.34E+00 1.06E+01 5.38E+00
3. Percent of ODCM limit  % 8.53E-01 1.46E+00 1.98E+00 1.32E+00 F. PARTICULATES VIA BURINING CONTAMINATED OIL Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 I. Total release Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
2. Average release rate for period [tCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
3. Percent of ODCM limit  % O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 8 of 35

Attachment 2 Effluent and Waste Disposal Data Table IB: Gaseous Effluents - Elevated Releases Continuous Release Nuclides Released

1. FISSION GASES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 krypton-85m Ci 1.37E+01 2.17E+O1 7.74E+00 6.89E+00 krypton-87 Ci 7.41E+00 1.51E+01 2.12E+01 1.66E+01 krypton-88 Ci 9.03E+00 1.77E+01 1.48E+01 9.78E+00 xenon-133 Ci 5.70E+01 6.14E+01 2.15E+01 2.65E+O1 xenon-133m Ci < LLD 1.10E+00 < LLD < LLD xenon-135 Ci 1.19E+O1 5.76E+01 5.88E+01 4.74E+01 xenon-135m Ci 1.79E+01 6.87E+01 8.15E+01 6.81E+01 xenon-137 Ci 1.72E+01 1.37E+02 2.46E+02 3.23E+02 xenon- 138 Ci 5.04E+01 1.44E+02 2.24E+02 1.85E+02 total for period Ci 1.84E+02 5.25E+02 6.75E+02 6.83E+02
2. GASEOUS IODINES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 iodine-131 Ci 1.66E-02 3.77E-02 5.22E-02 3.66E-02 iodine-1.32 Ci 9.20E-02 2.1IE-0 I 3.15E-01 1.77E-0 t iodine-133 Ci 8.60E-02 2.74E-01 4.86E-01 2.83E-01 iodine-134 Ci 1.98E-01 6.07E-01 9.63E-01 6.61E-01 iodine- 135 Ci 1.43E-01 4.60E-01 8.66E-01 4.79E-01 total for period Ci 5.36E-01 1.59E+00 2.68E+00 1.64E+00
3. PARTICULATES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 chromium-51 Ci < LLD < LLD < LLD < LLD manganese-54 Ci < LLD < LLD < LLD < LLD cobalt-58 Ci 3.06E-05 < LLD 2.22E-05 < LLD cobalt-60 Ci 1.20E-05 < LLD < LLD 4.29E-06 zinc-65 Ci < LLD < LLD < LLD < LLD strontium-89 Ci 3.30E-04 1.95E-03 2.58E-03 1.86E-03 strontium-90 Ci 4.16E-06 7.04E-06 4.26E-05 1.18E-05 niobium-95 Ci < LLD < LLD < LLD < LLD cesium-134 Ci < LLD < LLD < LLD < LLD cesium-137 Ci < LLD 8.68E-06 < LLD 8.37E-06 barium-140 Ci 2.51E-04 2.03E-03 6.46E-03 2.83E-03 lanthanum- 140 Ci 4.19E-04 3.50E-03 1.13E-02 4.95E-03 total for period Ci 1.05E-03 7.50E-03 2.04E-02 9.66E-03 Page 9 of 35

Attachment 2 Effluent and Waste Disposal Data Table IB: Gaseous Effluents - Elevated Releases Continuous Release

4. TRITIUM Unit Quarter I Quarter 2 Quarter 3 Quarter 4 hydrogen-3 Ci 2.54E+01 2.38E+01 4.03E+01 1.96E+01 Page 10 of 35

Attachment 2 Effluent and Waste Disposal Data Table 1C: Gaseous Effluents - Ground Level Releases Continuous Release Nuclides Released

1. FISSION GASES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 krypton-85m Ci 1.01E-02 7.52E-01 1.33E+00 4.77E-02 krypton-87 Ci < LLD 1.30E+00 7.13E+00 4.04E-0 I krypton-88 Ci < LLD 1.81E+00 5.28E+00 1.44E-01 xenon-133 Ci 2.07E-0 I 1.01E+01 1.14E+0I 1.53E+00 xenon-135 Ci 2.37E+00 1.72E+01 2.72E+01 1.24E+01 xenon-135m Ci < LLD 1.29E+01 3.22E+01 1.84E+01 xenon-137 Ci < LLD < LLD 3.89E+00 < LLD Xenon- 138 Ci < LLD 2.27E+00 2.07E+01 1.13E+00 total for period Ci 2.59E+00 4.64E+01 1.09E+02 3.40E+0I
2. GASEOUS IODINES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 iodine- 131 Ci 3.68E-03 2.83E-03 2.09E-03 1.06E-03 iodine- 132 Ci 6.40E-03 3.22E-03 1.49E-02 6.12E-03 iodine-133 Ci 9.58E-03 5.28E-03 2.OOE-02 9.05E-03 iodine- 134 Ci 8.02E-03 8.25E-03 4.73E-02 2.69E-02 iodine- 135 Ci 1.19E-02 7.66E-03 3.37E-02 1.64E-02 total for period Ci 3.95E-02 2.72E-02 1.18E-01 5.95E-02
3. PARTICULATES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 chromium-51 Ci 1.29E-04 1.7 1E-04 < LLD < LLD manganese-54 Ci 3.75E-06 1.45E-06 < LLD < LLD cobalt-58 Ci 1.80E-05 1.71E-05 < LLD < LLD cobalt-60 Ci 8.4IE-05 1.15E-04 6.23E-05 6.45E-05 zinc-65 Ci < LLD < LLD < LLD < LLD strontium-89 Ci 1.79E-04 1.81E-05 4.77E-04 2.3 1E-05 strontium-90 Ci 2.35E-06 2.54E-07 7.82E-06 1.18E-06 strontium-91 Ci < LLD < LLD < LLD 4.67E-05 niobium-95 Ci 5.3 IE-07 < LLD < LLD < LLD cesium- 134 Ci < LLD 5.18E-06 7.71E-07 1.46E-06 cesium- 137 Ci 2.00E-06 1.22E-05 8.36E-06 7.57E-06 barium-140 Ci 5.18E-05 2.69E-05 2.54E-04 5.85E-05 lanthanum- 140 Ci 7.41E-05 4.28E-05 1.66E-04 9.13E-05 cerium-141 Ci 3.07E-06 < LLD < LLD < LLD total for period Ci 5.48E-04 4.10E-04 9.76E-04 2.94E-04 Page 11 of 35

Attachment 2 Effluent and Waste Disposal Data Table IC: Gaseous Effluents - Ground Level Releases Continuous Release

4. TRITIUM Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 hydrogen-3 Ci 3.61E+01 4.14E+OI 4.34E+01 2.29E+O1 Page 12 of 35

Attachment 2 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+00 O.OOE+00 0.00E+00 O.OOE+00 Page 13 of 35

Attachment 2 Effluent and Waste Disposal Data Table 2A: Liquid Effluents - Summation of all Releases A. FISSION AND ACTIVATION PRODUCTS (NOTE 1)

Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total release Ci 5.14E-04 1.74E-03 6.53E-04 1.29E-03 4.OOE+01 (excluding tritium, gases, and alpha)
2. Average diluted lptCi/ml 1.14E-10 6.53E-10 1.87E-10 2.29E-10 NA concentration (NOTE 2)
3. Percent of 2.84E-03 8.87E-04 8.33E-04 2.95E-03 NA applicable limit B. TRITIUM (NOTE 1)

Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total release Ci 7.99E+O1 3.57E+01 2.41E+01 5.19E+01 4.50E+01
2. Average diluted tC i/ml 1.77E-05 1.34E-05 6.89E-06 9.25E-06 NA concentration (NOTE 2)
3. Percent of applicable limit 1.77E+00 1.34E+00 6.89E-01 9.25E-01 NA C. DISSOLVED AND ENTRAINED GASES (NOTE 1)

Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total release Ci 3.14E-02 6.32E-02 6.82E-03 1.48E-02 4.OOE+01
2. Average diluted concentration jiCi/ml 6.95E-09 2.37E-08 1.95E-09 2.64E-09 NA (NOTE 2)
3. Percent of applicable limit 3.47E-03 1.18E-02 9.76E-04 1.32E-03 NA D. GROSS ALPHA RADIOACTIVITY Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error
1. Total release Ci < LLD < LLD < 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 Collector Basin and/or Storm Drain Stabilization Pond)

Page 14 of 35

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

Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total volume liters 8.08E+05 3.76E+05 4.08E+05 1.04E+06 1.50E+01 F. VOLUME OF DILUTION WATER Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error
1. Total volume liters 4.52E+09 2.67E+09 3.49E+09 5.61E+09 1.5E+01 (used during release for average diluted concentration)

G. VOLUME OF COOLING WATER DISCHARGED FROM PLANT Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total volume liters 3.47E+I1 4.63E+II 4.96E+11 4.28E+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 Stabilization Pond)

Page 15 of 35

Attachment 2 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 manganese-54 Ci 3.89E-05 1.23E-06 < LLD < LLD iron-55 Ci 5.57E-05 < LLD 9.06E-05 3.04E-04 cobalt-58 Ci < LLD < LLD < LLD < LLD cobalt-60 Ci 3.30E-04 6.50E-05 2.20E-04 4.56E-04 strontium-89 Ci < LLD 1.28E-05 < LLD < LLD strontium-90 Ci < LLD 8.04E-06 < LLD < LLD zirconium-95 Ci < LLD < LLD 2.12E-07 < LLD ruthenium-103 Ci < LLD 2.92E-05 < LLD < LLD ruthenium-106 Ci < LLD < LLD 9.88E-06 < LLD iodine-131 Ci < LLD 1.08E-04 2.30E-05 1.03E-04 iodine-132 Ci < LLD 2.26E-04 1.57E-05 < LLD iodine-133 Ci < LLD 4.81E-04 1.30E-04 2.41E-04 iodine-134 Ci < LLD 1.75E-04 < LLD < LLD iodine-135 Ci < LLD 6.24E-04 1.45E-04 1.57E-04 cesium-134 Ci 2.74E-05 1.76E-06 1.27E-06 1.09E-06 cesium-137 Ci 6.21E-05 8.45E-06 1.74E-05 1.81E-05 barium-140 Ci < LLD < LLD < LLD 2.65E-06 lanthanum- 140 Ci < LLD < LLD < LLD 2.81E-06 cerium-144 Ci < LLD < LLD < LLD 1.76E-06 total for period Ci 5.14E-04 1.74E-03 6.53E-04 1.29E-03
2. DISSOLVED AND ENTRAINED GASES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 xenon-133 Ci 8.92E-03 1.25E-02 1.11E-03 3.90E-03 xenon-133m Ci 5.67E-04 9.97E-04 < LLD 2.12E-05 xenon-135 Ci 2.18E-02 4.97E-02 5.71E-03 1.09E-02 xenon-135m Ci 7.45E-05 1.65E-05 < LLD 7.78E-06 total for period Ci 3.14E-02 6.32E-02 6.82E-03 1.48E-02 Page 16 of 35

Attachment 2 Effluent and Waste Disposal Data Lower Limits of Detection Units: WCi/ml

1. LIQUID RELEASES 2. GASEOUS RELEASES Alpha 3.65E-08 Kr-85m 3.93E-09 H-3 2.55E-06 Kr-87 6.23E-09 Cr-51 1.68E-07 Kr-88 1.0IE-08 Mn-54 1.53E-08 Xe-133 5.22E-09 Fe-55 8.60E-08 Xe-133m 3.17E-08 Co-58 1.38E-08 Xe-135 3.73E-09 Fe-59 2.74E-08 Xe-135m 1.82E-08 Co-60 1.67E-08 Xe-137 3.97E-07 Zn-65 3.69E-08 Xe-138 1.27E-08 Sr-89 3.06E-08 Sr-90 2.39E-08 Zr-95 2.41E-08 3. IODINES AND PARTICULATES Mo-99 1.65E-07 Ru-103 1.33E-08 Alpha 1.93E-15 Ru- 106 1.88E-07 H-3 4.18E-1I 1-131 2.14E-08 Cr-51 4.97E-12 1-132 2.83E-08 Mn-54 5.30E-13 1-133 1.95E-08 Co-58 3.OOE-13 1-134 3.50E-08 Fe-59 1.00E- 12 1-135 1.11E-07 Co-60 7.34E-13 Cs-134 1.90E-08 Zn-65 1.13E-12 Cs-137 2.24E-08 Sr-89 2.69E-15 Ba-140 7.97E-08 Sr-90 1.43E-15 La- 140 4.40E-08 Sr-91 5.31E-12 Ce- 141 2.60E-08 Nb-95 2.84E-13 Ce- 144 1.34E-07 Mo-99 3.15E-12 1-131 4.56E-13 Kr-87 4.23E-08 Cs- 134 4.83E-13 Kr-88 5.91E-08 Cs-137 6.34E-13 Xe-133 4.81E-08 Ba-140 1.17E-12 Xe-133m 1.28E-07 La- 140 1.16E-12 Xe- 135 1.62E-08 Ce-141 5.57E-13 Xe-135m 8.1 IE-08 Ce- 144 1.96E-12 Xe-138 2.11E-07 NOTES:
1. The above values represent typical "a priori" LLDs for isotopes where values of "< LLD" are indicated in Tables IA, lB, 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 "< LLD," that nuclide is considered not present and the LLD activity listed is not considered in the summary data.

Page 17 of 35

Attachment 2 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) 6.20E+02 Total curie quantity (estimated) 5.36E+O1
2. Type of Waste Estimated Total Unit Period %Error 3
a. Spent resins, filter, sludges meter 2.37E+0 Curies 4.70E+0 I 1.OOE+01 3
b. Dry active waste, compacted/non-compacted meter 5.96E+0)2 Curies 6.58E+0 30 1.00E+01 3
c. Irradiated components meters O.OOE+0 30 Curies O.OOE+0 30 N/A 3
d. Others (describe) meters O.OOE+0 N0 Curies O.OOE+0 )0 N/A
3. Estimate of maior radionuclides composition
a. C-14 1.1E+00 %

Mn-54 3.1E+00 %

Fe-55 2.2E+01  %

Co-60 5.3E+01  %

Ni-63 1.4E+01  %

Zn-65 2.3E+00  %

Cs-137 2.6E+00  %

b. Fe-55 4.8E+01  %

Co-60 3.9E+01  %

Ni-63 1.OE+01  %

Cs-137 1.OE+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 18 of 35

Attachment 2 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 Type No. of shipments Type A/Type B
a. Resin Dewatered Type A or GP 8.OE+00
b. Dry active waste Compacted/ Type A or GP 2.OE+01 Non-compacted
c. Irradiated components N/A N/A
d. Others (describe) N/A N/A
5. Shipment Disposition
a. Solid Waste Number of Shipments Mode of Transportation Destination 1.30E+01 Highway Oak Ridge, TN 2.OOE+00 Highway Erwin, TN 2.OOE+00 Highway Richland, WA 1.00E+01 Rail Clive, UT 1.00E+00 Highway Clive, UT
b. Irradiated Fuel Number of Shipments Mode of Transportation Destination 0 N/A N/A Page 19 of 35

Attachment 2 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) 1.37E+01 Total curie quantity (estimated) 5.62E+02
2. Type of Waste Estimated Total Unit Period %Error 3
a. Spent resins, filter, sludges meter 1.37E+01 Curies 5.62E+02 I.OOE+01 3
b. Dry active waste, compacted/non-compacted meter O.OOE+00 Curies O.OOE+00 N/A 3
c. Irradiated components meters O.OOE+00 Curies O.OOE+00 N/A 3
d. Others (describe) meters O.OOE+00 Curies O.OOE+00 N/A
3. Estimate of maior radionuclides comoosition
a. Cr-51 4.4E+00  %

Mn-54 3.3E+00  %

Fe-55 2.5E+01  %

Co-58 4.2E+00  %

Co-60 4.9E+01  %

Ni-63 5.4E+00  %

Zn-65 4.3E+00  %

Cs-134 1.OE+00  %

Cs- 137 1.9E+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 35

Attachment 2 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 type Stream Form Container Type No. of shipments Type A/Type B
a. Resin & Filters Dewatered Type B 4.OOE+00
b. Dry active waste Compacted/ N/A N/A Non-compacted
c. Irradiated components N/A N/A
d. Others (describe) N/A N/A
5. Shipment Disposition
a. Solid Waste Number of Shipments Mode of Transportation Destination 4.OOE+00 Highway Erwin, TN
b. Irradiated Fuel Number of Shipments Mode of Transportation Destination 0 N/A N/A Page 21 of 35

Attachment 2 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) 1.33E+01 Total curie quantity (estimated) 9.56E+04
2. Type of Waste Estimated Total Unit Period %Error 3
a. Spent resins, filter, sludges meter O.OOE+00 Curies O.OOE+00 N/A
b. Dry active waste, compacted/non-compacted meter3 O.OOE+00 Curies O.OOE+00 N/A 3
c. Irradiated components meters 1.33E+01 Curies 9.56E+04 1.00E+01 3
d. Others (describe) meters O.OOE+00 Curies O.OOE+00 N/A
3. Estimate of maior radionuclides comnosition
a. N/A
b. N/A
c. Mn-54 2.2E+00  %

Fe-55 4.3E+01  %

Co-60 5.IE+01  %

Ni-63 3.3E+00  %

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 22 of 35

Attachment 2 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 Form Container Type No. of shipments Type A/Type B
a. Resin & Filters Dewatered N/A N/A
b. Dry active waste Compacted/ N/A N/A Non-compacted
c. Irradiated components Type B 6.OOE+00
d. Others (describe) N/A N/A
5. Shipment Disposition
a. Solid Waste Number of Shipments Mode of Transportation Destination 5.OOE+00 Highway Barnwell, SC 1.00E+00 Highway Erwin, TN
b. Irradiated Fuel Number of Shipments Mode of Transportation Destination 7.OOE+00 Rail New Hill, NC Page 23 of 35

Attachment 2 Effluent and Waste Disposal Data Combustion of Waste Oil No contaminated waste oil was incinerated during this report period.

Page 24 of 35

Attachment 3 Environmental Monitoring Program : Milk and Vegetable Sample Location : Land Use Census Page 25 of 35

Attachment 3 Environmental Monitoring Program Enclosure 1: 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.

Page 26 of 35

Attachment 3 Environmental Monitoring Program Enclosure 2: Land Use Census The 2006 Land Use Census did not identify any locations that are reportable in the Radioactive Effluent Release Report for 2006.

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 0.7 miles None NE None None ENE None None E None None ESE 1.4 miles None SE 0.9 miles None SSE 0.9 miles None S 1.1 miles 1.9 miles SSW 1.2 miles 1.7 miles SW 1.1 miles 3.0 miles WSW 1.2 miles 1.5 miles W 0.9 miles 0.9 miles WNW 0.9 miles None NW 0.9 miles 1.0 miles NNW 0.8 miles 4.5 miles N 0.8 miles None Page 27 of 35

Attachment 4 Effluent Instrumentation : Radioactive Liquid Effluent Monitoring Instrumentation : Radioactive Gaseous Effluent Monitoring Instrumentation : Liquid Hold-Up Tank Page 28 of 35

Attachment 4 Effluent Instrumentation Enclosure 1: Radioactive Liquid Effluent Monitoring Instrumentation No Radioactive Liquid Effluent Monitoring Instruments were inoperable for a period of greater than 30 days.

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Attachment 4 Effluent Instrumentation Enclosure 2: Radioactive Gaseous Effluent Monitoring Instrumentation No Radioactive Gaseous Effluent Monitoring Instruments were inoperable for a period of greater than 30 days.

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Attachment 4 Effluent Instrumentation Enclosure 3: Liquid Hold-Up Tank No Liquid Hold-Up Tank exceeded the 10-Curie limit of ODCMS 7.3.6 during this reporting period.

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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. No major modifications were made to the radioactive waste treatment systems during this reporting period.

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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.

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Attachment 7 Annual Dose Assessment Summary Liuid Effluents (1)

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

GI-LLI 4.66E-04 2.OOE+01 Bone 1.57E-04 2.OOE+01 Liver 2.87E-04 2.OOE+01 Lung 2.15E-04 2.OOE+01 Total Body 2.21E-04 6.OOE+00 Thyroid 2.1IE-04 2.OOE+01 Kidney 1.65E-04 2.OOE+01 Gaseous Effluents (1)

Noble Gas: Critical Age: Infant Controlling location: NE sector at 0.7 mile (mrad) Limit: (mrad)

Gamma 8.79E-02 2.OOE+01 Beta 4.90E-02 4.OOE+01 nlt-t; nA Pqrt;ý~.Iqt*

JAJnnn nit., a. anti t.t.iatno, nnrt alit.

Trit;nrnm

a. inn nSi ft. Critical Age: Infant Controlling location: NE sector at 4.75 mile Assuming a cow milk pathway (mrem) Limit: (mrem)

Thyroid 8.43E-01 3.OOE+01 Kidney 4.91E-03 3.OOE+01 Liver 4.47E-03 3.OOE+01 Total Body 2.91E-03 3.OOE+01 Skin 1.77E-03 3.OOE+01 GI_LLI 1.89E-03 3.OOE+01 Lung 1.77E-03 3.OOE+01 Bone 2.93E-03 3.OOE+01

(') Reference - dose determined using site specific ODCM software Page 34 of 35

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 29 was effective on January 30, 2006. An analysis of the major changes is as follows:

ODCM Analysis:

1. Updated the list of effective pages for Revision 29.

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. Revised sections to allow prompt troubleshooting of annunciator problems without concerns on LCO impact.

Section 7.3.1 Radioactive Liquid Effluent Monitoring Instrumentation, section B 7.3.1 Radioactive Liquid Effluent Monitoring Instrumentation Bases, section 7.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation and section B 7.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation Bases were revised to include a note that states the annunciator function may be removed from operation for performance of troubleshooting for up to 30 minutes provided the associated function maintains monitoring capability. Upon completion of troubleshooting, or expiration of the 30 minute allowance, the annunciator must be returned to operation or the applicable Condition entered and required Compensatory Measures taken. Since the 1/2-CAC-AT-1264 alarm is used as an EAL entry condition, removal of the 1/2-CAC-AT-1264 annuciator for 30 minutes for troubleshooting is prohibited when there are any fuel handling activities on the refuel floor or activities where there is the potential to cause a decrease in spent fuel pool water level.

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Enclosure 2 BSEP 07-0036 Offsite Dose Calculation Manual Revision 29

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