BSEP 06-0045, Radioactive Effluent Release Report for 2005

Radioactive Effluent Release Report for 2005

ML061240333
Person / Time
Site:	Brunswick
Issue date:	04/27/2006
From:	Ivey R Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 06-0045
Download: ML061240333 (37)

Text

Progress Energy 10 CFR 50.36a APR 2 7 2006 SERIAL: BSEP 06-0045 U. S. Nuclear Regulatory Commission AFIN: Document Control Desk

'Washington, DC 20555-0001

Subject:

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 2005 Ladies and Gentlemen:

In accordance with 10 CFR 50.36a and Technical Specification (TS) 5.6.3 for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2, Carolina Power &

Light Company, now doing business as Progress Energy Carolinas, Inc., is submitting the enclosed Radioactive Effluent Release Report for BSEP Unit Nos. 1 and 2. This report covers the period from January 1, 2005, through December 31, 2005.

TS 5.5.1, "Offsite Dose Calculation Manual (ODCM)," requires changes to the ODCM be submitted as part of or concurrent with the Radioactive Effluent Release Report. No changes were made to the ODCM in 2005. As such, the ODCM is not included in this submittal.

No regulatory commitments are contained in this submittal. Please refer any questions regarding this submittal to Mr. Leonard R. Beller, Supervisor - Licensing/Regulatory Programs, at (910) 457-2073.

Sincerely, (l 6 31 C- e Randy C. Ivey Manager - Support Services Brunswick Steam Electric Plant MAT/mat

Enclosure:

Radioactive Effluent Release Report for 2005 Piogress Energy Carolinas, Inc.

Brjnswick Nuclear Plant P.). Box 10429 S uthport, NC 28461

Document Control Desk B SEP 06-0045 / Page 2 cc: (with enclosure):

U. S. Nuclear Regulatory Commission, Region II ATTN: Dr. William D. Travers, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SWV, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Eugene M. DiPaolo, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)

ATfN: 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

Enclosure BSEP 06-OD45 Radioactive Effluent Release Report for 2005

Brunswick Steam Electric Plant Radioactive Effluent Release Report January 1, through December 31, 2005 Table of Contents Attachment Pages

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

2. Effluent and Waste Disposal Data 6 - 23

3. Environmental Monitoring Program 24 - 26

4. Effluent Instrumentation 27 - 30

5. Major Modification to the Radioactive Waste Treatment 31 Systems

6. Meteorological Data 32

7. Annual Dose Assessment 33

8. Off-Site Dose Calculation Manual (ODCM) and Process 34 Control Program (PCP) Revisions Page 1 of 34

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Facility: Brunswick Steam Electric Plant License>: 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. [odine-13 1, 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 [tCi (ODCM Appendix H)

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

C. 'Liquid Effluents (ODCMS 7.3.4)

,1) Calendar Quarter2 (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: D)ose calculations are determined in accordance with the ODCM

'Used for percent of ODCMS limit determination in Attachment 2, Table 1A 2Used for percent of ODCMS limit determination in Attachment 2, Table 2A Page 2 of 34

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 mrem/year to the skin B. [odine-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 jiCi/ml 3 (2) Dissolved and entrained noble gases: limit = 2.OOE-04 [iCi/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 effcrt to approxitrate the total of all individual and sampling errors.

Page 3 of 34

Attachment 1 Effluent and Waste Disposal Report Supplemental Information

4. Batch Releases A. Liquid (1) Number of batch releases: 5.10E+01 (2) Total time period for batch releases: 5.15E+03 Minutes (3) Maximum time period for a batch release: 1.95E+02 Minutes (4) Average time period for a batch release: 1.01E+02 Minutes (5) Minimum time period for a batch release: 2.00E+00 Minutes (6) Average stream flow during periods of release of effluent into a flowing stream: 8.37E+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. Abrnormnal 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 vwere no abnormal releases that exceeded 10 CFR 20 or 10 CFR 50 limits. See page 5 for a discussion of release ev;ents that occurred.

Page 4 of 34

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Discussion of tritium in the Storm Drain Stabilization Pond Approximately 8.40E+07 gallons containing 1.37E+02 curies of tritium were released from the Storm Drain Stabilization Pond (SDSP) to the intake canal over this reporting period. This resulted in an estimated maximum dose to the individual of 2.40E-04 mrem. The SDSP is a permitted release point.

Discussion of releases from the Storm Drain Collector Basin Due to heavy rains from Hurricane Ophelia, Tropical Storm Tammy, and other unusual heavy rain events, the Storm Drain Collector Basin (SDCB) was released directly to the discharge canal on seven occasions in 2005. The SDCB is a permitted release point during periods of inclement weather to protect plant personnel and equipment. Approximately 1.83E+06 gallons containing 1.28E+HO curies of tritium were released. This resulted in an estimated maximum dose to the individual of 1.79E-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 34

Attachment 2 Effluent and Waste Disposal Data Table 1A Gaseous Effluents - Summation of all Releases Table 1B Gaseous Effluents - Elevated Releases Table 1C Gaseous Effluents - Ground Level Releases Table I'D Gaseous Effluents - Ground Level Releases for Burning Contaminated Oil Table 2 A Liquid Effluents - Summation of all Releases Table 21B Liquid Effluents - Batch Mode Lower Limits of Detection Table 3 A Solid Waste and Irradiated Fuel Shipments - Waste Class A Table 31B Solid Waste and Irradiated Fuel Shipments - Waste Class B Table 30 Solid Waste and Irradiated Fuel Shipments - Waste Class C Combustion of Waste Oil Page 6 of 34

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 Qua irter 4 Percent Error I. Total release Ci 3.811E+01 5.09E+01 4.57E+01 7.45)E+O1 4.50E+01

2. Av{erage release rate for period gCi/sec 4.90E+00 6.47E+00 5.76E+00 9.4"3E+00 NIA

3. Percent of ODCM lirnit  % 1.14E-02 8.25E-03 1.04E-02 1.6:33E-02 N4A B. IODINES Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total Iodine - 131 re.ease Ci 2.36E-03 3.98E-03 7.8 1E-03 6.27E-03 3.50(E+01

2. Average release ra.e for period gCi/sec 3.03E-04 5.06E-04 9.83E-04 7.89E-04 N4A C. PARTICULATES Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total release Ci 6.38E-04 9.19E-04 6.18E-04 5.14E-04 3.50E+01

2. Average release ral:e for period pCi/sec 8.20E-05 1.17E-04 7.77E-05 6.47E-05 N4A

3. Gross Alpha Ci 0.00E+00 0.001E+00 O.OOE+00 0.00E+00 3.50E+01 D. TRIT[UM Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total release Ci 4.77E+01 4.55E+01 6.63E+01 7.12E+01 3.OOE+01

2. Av/erage release rale for period pCi/sec 6.14E+00 5.79E+00 8.34E+00 8.95E+00 N4A Page 7 of 34

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 1 Quarter 2 Quarter 3 Quarter 4

1. Total release Ci 4.77E+01 4.56E+01 6.64E+01 7.12E+01

2. Average release rate for period giCi/sec 6.14E+00 5.79E+00 8.35E+00 8.95E+00

3. Percent of ODCM liinit  % 1.02E-01 1.38E-01 3.24E-01 2.13E-01 F. PAR1'ICULATES VIA BURINING CONTAMINATED OIL Unit Quarter I Quarter 2 Quarter 3 Quarter 4

1. Total release Ci 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00

2. A verage release rate for period piCi/sec 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00

3. Percent of ODCM limnit  % 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 8 of 34

Attachment 2 Effluent and Waste Disposal Data Table 1B: Gaseous Effluents - Elevated Releases Continuous Release Nuclides Released

1. FISS [ON GASES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 argoni-41 Ci 7.53E-02 3.28E-01 < LLD < LLI) krypton-85 Ci < LLD < LLD 7.23E-04 < LLI) krypton-85m Ci 2.07E+00 1.15E+O0 4.04E+00 5.47E+00 krypton-87 Ci 6.48E-01 9.32E-02 5.57E-01 3.11E+00 krypton-88 Ci 2.55E+00 1.69E-01 1.03E+00 4.52E+00 xenon-133 Ci 8.36E+00 1.48E+01 1.51E+O1 2.63E+01 xenon-133m Ci 8.8 1E-02 3.60E-01 < LLD 5.50E+00 xenon-135 Ci 6.53E+00 4.29E+00 3.06E+00 < LL) xeno:i-135m Ci 2.94E+00 6.32E+00 7.10E+00 9.06E+00 xenoa-137 Ci <LLD <LLD <LLD <LL1) xenoi-138 Ci 1.32E+01 1.12E+01 1.15E+01 1.99E+01 total for period Ci 3.64E+01 3.86E+01 4.25E+01 7.38E+01

2. GASEOUS IODINES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 iodinz-131 Ci 1.89E-03 3.49E-03 6.61E-03 6.17E-1)3 iodine-132 Ci 1.32E-02 1.08E-02 2.33E-02 2.60E-02 iodinz-133 Ci 1.16E-02 1.24E-02 2.36E-02 2.20E-02 iodine-134 Ci 2.20E-02 1.61E-02 4.05E-02 3.91E-02 iodine-135 Ci 1.87E-02 1.97E-02 3.52E-02 3.39E-02 total for period Ci 6.74E-02 6.25E-02 1.29E-01 1.27E-0I1

3. PARTICULATES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 chromnium-51 Ci 1.69E-05 5.41E-06 <LLD <LLI) mani;anese-54 Ci 1.23E-05 3.82E-05 < LLD < LL) cobaht-58 Ci 4.42E-05 1.87E-04 < LLD < LL1) cobalt-60 Ci 1.42E-04 1.48E-04 6.66E-06 1. 14E-06 zinc-65 Ci 1.22E-05 < LLD < LLD < LL1) strontium-89 Ci 2.59E-05 5.36E-05 9.66E-05 8.50E-05 strontium-90 Ci 3.71E-07 6.04E-07 1.2 1E-06 6.09E-D7 cesium-134 Ci < LLD 2.01E-05 < LLD < LL])

cesium-137 Ci 8.75E-06 1.78E-05 1.42E-06 4.45E-06 barium-140 Ci 2.89E-05 6.25E-05 1.69E-04 1.36E-04 lanthanum-140 Ci 2.66E-05 1.12E-04 3.20E-04 2.37E-04 ruthenium-106 Ci < LLD 2.35E-05 < LLD < LLD tellutium-129m Ci < LLD 5.78E-05 < LLD < LLD total for period Ci 3.19E-04 7.26E-04 5.94E-04 4.64E-04 Page 9 of 34

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

4. TRITIUM Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 hydrogen-3 Ci 1.84E+01 1.68E+01 2.92E+01 3.70E+31 Page 10 of 34

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

1. FISSION GASES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 krypton-85m Ci < LLD < LLD < LLD 2.25E-02 krypton-87 Ci < LLD < LLD 5.19E-02 < LLD xenon-133 Ci < LLD 1.15E+01 1.68E+00 < LLD xenon-135 Ci 1.68E+00 7.25E-01 1.44E+00 1.11 E+00 xenon-135m Ci < LLD < LLD 5.96E-02 < LLD xenon- 137 Ci < LLD < LLD 6.64E-02 < ILD total for period Ci 1.68E+00 1.22E+01 3.29E+00 1.13E+00

2. GASEOUS IODINES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 iodine-131 Ci 4.69E-04 4.93E-04 1.20E-03 1.04E-04 iodine-132 Ci 1.68E-04 3.85E-06 5.93E-03 < ILD iodine-133 Ci 1.06E-03 9.52E-05 4.75E-03 3.91E-04 iodine-134 Ci < LLD < LLD < LLD < LLD iodine-135 Ci 9.50E-05 1.30E-05 5.26E-03 < LLD total for period Ci 1.79E-03 6.05E-04 1.711E-02 4.96E-04

3. PARTICULATES Unit Quarter I Quarter 2 Quarter 3 Quar ter 4 chro mium-51 Ci 1.38E-04 8.29E-05 < LLD < LLD manganese-54 Ci 3.74E-06 7.3 lE-06 < LLD < LLD cobalt-58 Ci 2.73E-05 2.14E-05 2.1 IE-06 1.55E-06 cobalt-60 Ci 1.37E-04 8.08E-05 1.33E-05 1.93E-05 zinc-65 Ci < LLD < LLD < LLD < I.LD strortium-89 Ci 1.33E-05 < LLD 7.42E-06 < I.LD strortium-90 Ci < LLD < LLD < LLD < I.LD cesium-134 Ci < LLD < LLD < LLD 1.05E-05 cesium-137 Ci < LLD < LLD 6.77E-07 1.9ClE-05 barium-140 Ci 1.80E-07 < LLD < LLD < I.LD lanthanum-140 Ci 3.32E-07 < LLD < LLD < ILD total for period Ci 3.19E-04 1.92E-04 2.35E-05 5.02.E3-05

4. TRFIUM Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 hydrDgen-3 Ci 2.94E+01 2.88E+01 3.7 1E+01 3.42E+01 Page 11 of 34

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 Xeleases made Ci O.OOE+OO O.OOE+OO O.OOE+OO 0.00],+00 Page 12 of 34

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 1 Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total release Ci 1.40E-03 2.26E-04 5.27E-04 9.66E-05 4.04E+01 (excluding tritium, gases, and alpha)

2. Avierage diluted 2.91E-1 l concentration 5.59E-10 5.68E-11 8.09E-I I NA pCi/ml (NOTE 2)

3. Pcrcent of 2.08E-03 1.31IE-03 1.35E-03 1.32E-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 6.23E+01 3.71E+O1 6.01E+01 5.19E+01 4.20E+01

2. A verage diluted concentration 2.49E3-05 9.3213-06 9.2313-06 1.5613-05 pCi/ml NA (NOTE 2)

3. Percent of applicable limit 2.49E+00 9.32E-01 9.2313-01 1.56E+00 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 5.36E-05 5.32E-04 4.70E-04 9.89E-04 4.O01E+01

2. Avrerage diluted ccncentration 2.80E-11I 1.331E-10 7.21E-1 I 2.98E-10 pCi/ml NA (NOTE 2)

3. Percent of applicable limit 1.07E-05 6.69E-05 3.61E-05 1.49E-04 NA D. GROSS ALPHA RADIOACTIVITY Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total release Ci < LLD < LLD < LLD < LLD 4.00E+0 I 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 13 of 34

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 3.66E+05 6.15E+05 8.94E+05 5.15E+05 1.50E+Ol F. VOLUJME OF DILUTION WATER Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total volume liters 2.50E+09 3.98E+09 6.52E+09 3.32E+09 1.5E+01 (used during release for average diluted cc ncentration)

G. VOLUJME OF COOLING WATER DISCHARGED FROM PLANT Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total volume liters 3.49E+1 1 4.61E+1 1 5.02E+I1 4.62E+1 1 1.:50E+O1 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 14 of 34

Attachment 2 Effluent and Waste Disposal Data Table 2B: Liquid Effluents - Batch Mode Nuclides Released

1. FISSION AND ACTIVATION PRODUCTS 1 Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 man zanese-54 Ci 1.80E-04 2.16E-06 1.1 3E-04 < LLD iron- 55 Ci 1.19E-04 1.32E-04 < LLD < LLD Cobalt-58 Ci 2.05E-05 < LLD < LLD < LLD cobalt-60 Ci 6.83E-04 8.49E3-05 2.34E-04 9.2 JE-05 strontium-89 Ci < LLD < LLD < LLD < LLD strontium-90 Ci < LLD < LLD < LLD < LLD iodine-131 Ci 1.44E-06 < LLD < LLD 2.341E-07 iodine-133 Ci < LLD < LLD < LLD < LLD cesium-134 Ci 1.75E-04 1.8IE-06 6.58E-05 < LLD cesitim-137 Ci 2.26E-04 4.61E-06 1.13E-04 3.64E-06 total for period Ci 1.40E-03 2.26E-04 5.27E-04 9.66E-05

2. DISS'OLVED AND ENTRAINED GASES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 xencn-133 Ci 8.28E-06 1.12E-04 1.34E-04 1.75E-04 xenc'n-135 Ci 4.53E-05 4.20E-04 3.36E-04 8. 14E-04 total for period Ci 5.366E-05 5.32E-04 4.70E-04 9.891E-04 Page 15 of 34

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

1. LIQUID RELEASES 2. GASEOUS RELEASES Alpha 2.19E-08 Kr-85m 2.79E-09 H-3 2.46E-06 Kr-87 7.58E-0)

Cr-51 1.37E-07 Kr-88 1.30E-03 Mn-54 1.26E-08 Xe-133 5.26E-0)

Fe-55 7.54E-08 Xe-133m 2.151E-03 Co-58 1.90E-08 Xe-135 3.53E-30 Fe-59 5.241E-08 Xe-135m 4.56E-03 Co-60 2.37E-08 Xe-137 1.70E-07 Zn-65 4.13E-08 Xe-138 1.391E-07 Sr-89 3.77E-08 Sr-90 2.35E-08 Mo-99 1.29E-07 3. IODINES AND PARTICULATES 1-131 2.021E-08 I-133 2.21E-08 Alpha 2.22E-15 1-135 9.3 11-08 H-3 1.55E-l l Cs-134 2.611E-08 Cr-51 2.981E-13 Cs-137 1.95E-08 Mn-54 3.72E-14 Ba-140 7.26E-08 Co-58 4.38E-14 La-140 3.981E-08 Fe-59 1.04E-1 3 Ce-141 2.57E-08 Co-60 5.841E-14 Ce-144 9.26E-08 Zn-65 6.72E-14 Sr-89 3.101E-15 Kr-87 4.59E-08 Sr-90 9.5611-16 Kr-88 4.77E-08 Mo-99 2.69E-13 Xe-133 3.971E-08 I-131 2.54E-1.4 Xe-133m 1.37E-07 Cs-134 6.70E-14 Xe-135 2.021E-08 Cs-137 3.62E-1.4 Xe-135m 8.15E-08 Ba-140 9.72E-1.4 Xe-138 2.16E-07 La-140 4.80E-14 Ce-141 3.86E-14 Ce-144 1.69E-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 "< LLD," that nuclide is considered not present and the LLD activity listed is not considered in the summary data.

Page 16 of 34

Attachment 2 Effluent and Waste Disposal Data Table 3C: Solid Waste and Irradiated Fuel Shipments - Waste Class C Waste Class A

1. Total volume shipped (cubic meters) 9.03E+02 Total curie quantity (estimated) 2.37E+01

2. TvMp of Waste Estimated Total Unit Period %Etror

a. Spent resins, filter, sludges meter3 2.78E+01 Curies 1.99E+O1 1.OCE+O 1

b. Dry active waste, compacted/non-compacted meter 3 8.75E+02 Curies 3.79E+00 1.001E+0 1

c. Irradiated components meters 3 0.00E+00 Curies Q.OOE+00 N/A.

d. Others (describe) meters 3 O.OOE+00 Curies 0.00E+00 N/A

3. Estimate of major radionuclides composition

a. H-3 4.20E+00 %

C-14 2.20E+00 %

Mn-54 2.40E+00 %

Fe-55 1.37E+01 %

Co-60 5.09E+01 %

Ni-63 1.43E+01 %

Cs-137 9.10E+00 %

Zn-65 1.50E+00 %

b. Mn-54 2.59E+00 %

Fe-55 3.48E+01 %

Co-60 5.52E+01 %

Ni-63 3.57E+00 %

Zn-65 2.13E+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 :o a licensed disposal facility.

Page 17 of 34

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 Dewatered Type A or GP 5.00E+OO

b. Dry active waste Compacted/ Type A or GP 2.30E+O1 Non-compacted

c. Irradiated components N/A N/A

d. Others (describe) N/A N/A

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

5. Shipment Disposition

a. Solid Waste Number of Shipments Mode of Transportation Destination 1.OOE+O1 Highway Oak Ridge, TN 1.OOE+OO Highway Erwin, TN 1.OOE+OO Highway Richland, WA 8.00E+OO Rail Clive, UT I .OOE+OO Highway Clive, UT 7.00E+OO Highway Wampum, PA

b. Irradiated Fuel Number of Shipments Mode of Transportation Destination 0 N/A N/A Page 18 of 34

Attachment 2 Effluent and Waste Disposal Data Table 3C: Solid Waste and Irradiated Fuel Shipments - Waste Class C Waste Class B

1. Total volume shipped (cubic meters) 1.39E+01 Total curie quantity (estimated) 5.15E+02

2. TVPn of Waste Estimated Total Unit Period %Error

a. Spent resins, filter, sludges meter3 1.39E+01 Curies 5.15E+02 1.OC'E+01

b. Dry active waste, compacted/non-compacted meter3 O.OOE+00 Curies O.OOE+00 N/A

c. Irradiated components meters 3 O.OOE+00 Curies O.OOE+00 N/A

d. Others (describe) meters 3 O.OOE+00 Curies O.OOE+00 N/A

3. Estimate of maior radionuclides composition

a. Cr-51 1.62E+00  %

Mn-54 3.48E+00  %

Fe-55 2.52E+01  %

Co-58 3.54E+00  %

Co-60 5.71E+01  %

Ni-63 2.22E+00  %

Zn-65 3.69E+00  %

Cs-137 2.22E+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.

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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 Type B 4.00E+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

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

5. Shipment Disposition

a. Solid Waste Number of Shipments Mode of Transportation Destination 4.00E+00 Highway Erwin, TN

b. Irradiated Fuel Number of Shipments Mode of Transportation Destination 0 N/A N/A Page 20 of 34

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) 6.70E+00 Total curie quantity (estimated) 3.47E+04

2. T (ypof Waste Estimated Total Unit Period %Error

a. Spent resins, filter, sludges meter3 O.OOE+00 Curies O.OOE+00 N/A

b. Dry active waste, compacted/non-compacted meter 3 O.OOE+00 Curies O.OOE+00 N/A

c. Irradiated components meters 3 6.70E+00 Curies 3.47E+04 1.00E+01

d. Others (describe) meters 3 O.OOE+00 Curies O.OOE+00 N/A

3. Estimate of maior radionuclides composition

a. N/A

b. N/A

c. Fe-55 2.45E+01 %

Co-60 7.25E+01 %

Ni-63 2.02E+00 %

d. N/A NOTE:

Solid Radioactive Waste was shipped directly for disposal.

Page 21 of 34

Attachment 2 Effluent and Waste Disposal Data Table 3C: Solid Waste and Irradiated Fuel Shipments - Waste Class C Effluent and Waste Disposal Annual Report for January 1, through December 31, 2005 Solid Waste and Irradiated Fuel Shipments

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 3.00E+00

d. Others (describe) N/A N/A

• Solidifi cation agent or absorbent (e.g., cement, urea-formaldehyde)

5. Shi ment Disposition

a. Solid Waste Number of Shipments Mode of Transportation Destination 3.OOE+00 Highway Barnwell, S.C.

b. Irradiated Fuel Number of Shipments Mode of Transportation Destination 7.00E+00 Rail New Hill, N.C.

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

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Attachment 3 Environmental Monitoring Program : Milk and Vegetable Sample Location : Land Use Census Page 24 of 34

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.

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Attachment 3 Environmental Monitoring Program Enclosure 2: Land Use Census The 2005 Land Use Census did not identify any locations that are reportable in the Radioactive Effluent Release Report for 2005.

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 1.8 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 2.4 miles WNW 0.8 miles None NW 0.9 miles 4.8 miles NNW 0.8 miles 0.9 miles N 0.7 miles None Page 26 of 34

Attachment 4 Effluent Instrumentation : Radioactive Liquid Effluent Monitoring Instrumentation : Radioactive Gaseous Effluent Monitoring Instrumentation : Liquid Hold-Up Tank Page 27 of 34

Attachment 4 Effluent Instrumentation Enclosure 1: Radioactive Liquid Effluent Monitoring Instrumentation No Ractoactive 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. Although no major modifications to the radioactive waste treatment systems will be submitted with the UFSAR in accordance with 10 CFR 50.71(e), a temporary modification, in August 2005, was installed in the Unit 2 Turbine Building ventilation system as part of testing. This modification resulted in a temporary, unfiltered pathway to the environment. The system operated for approximately 28 days in this configuration and accounted for approximately 1.50E14 cc of release volume. The ventilation system was restored to its normal configuration when the temporary modification was removed. The once-through pathway contributed the following to the 2005 annual source term:

Category Curies Noble Gas 1.86E+00 I-131 1.109E-03 I-133 4.432E-03 During the once-through ventilation test there was one period where sample flow was lost for particulate and iodine collection for approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and auxiliary sampling was not installed within the 45 minute time requirement of the ODCM. This was due to an inadvertent power loss to the sample pump. There were no alarms in the control room on the temporary sample apparatus and once discovered, power was immediately restored. It is estimated that approximately 8.3E-05 curies cf iodine were released in this period, there were no particulates released in this period.

Page 31 of 34

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 Liquid Effluents (1)

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

GI-LLI 3.78E-04 2.00E+01 Bone 9.81E-05 2.00E+01 Liver 2.27E-04 2.00E+01 Lung 1.47E-04 2.OOE+01 Total Body 1.82E-04 6.00E+00 Thyroid 1.15E-04 2.OOE+01 Kidney 1.30E-04 2.00E+01 Gaseous Effluents (1)

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

Gamma 4.64E-03 2.00E+01 Beta 1.93E-03 4.00E+01 Iodine, Particulates, and Tritium: Critical Age: Infant Controlling location: NE sector at 4.75 mile Assuming a cow milk pathway (mrem) Limit: (mrem)

Thyroid 1.17E-01 3.001E+01 Kidney 2.04E-03 3.00OE+01 Liver 1.99E-03 3.001E+01 Total Body 1.77E-03 3.OOE+01 Skin 1.63E-03 3.001E+01 GILLI 1.63E-03 3.001E+01 Lung 1.61E-03 3.00OE+01 Bone 4.44E-04 3.001E+01 (1)Reference - dose determined using site specific ODCM software Page 33 of 34

Attachment 8 Off-,Site Dose Calculation Manual (ODCM) And Process Control Program (PCP) Revisions The PCP was not revised during the report period. The ODCM was not revised during the report period.

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