Text

Annual Radioactive Effluent Release Report
	ML101260473
Person / Time
Site:	Oconee
Issue date:	04/30/2010
From:	Baxter D; Duke Energy Carolinas
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML101260473 (128)
	v • d • e

DAVE BAXTER kDuke Vice President EEnergy Oconee Nuclear Station Duke Energy April 30, 2010 ON01 VP / 7800 Rochester Highway Seneca, SC 29672 864-873-4460 U.S. Nuclear Regulatory Commission 864-873-4208 fax Document Control Desk dave. baxter@duke-energy.com Washington, D.C. 20555

Subject:

Duke Energy Carolinas, LLC Oconee Nuclear Station, Docket Nos. 50-269, 50-270 and 50-287 2009 Annual Radioactive Effluent Release Report Pursuant to Oconee Nuclear Site Selected Licensee Commitment Manual, SLC 16.11-9, and 10 CFR 50.36a (a) (2), please find attached the Oconee Annual Radioactive Effluent Release Report for the period of January 1, 2009 through December 31, 2009. Also, included in this report are the 2009 Offsite Dose Calculation Manual and the 2009 Process Control Program Manual.

Attachment 1 Radioactive Effluent Releases and Supplemental Information Attachment 2 Solid Waste Disposal Report Attachment 3 Unplanned Offsite Releases Attachment 4 Fuel Cycle Calculation Attachment 5 Inoperable Monitoring Equipment Attachment 6 Groundwater Protection Initiative Attachment 7 SLC 16.11 Radiological Effluent Controls Enclosures Offsite Dose Calculation Manual and Process Control Program Manual - CD Should there be questions concerning this report please contact Judy E. Smith at (864) 873-4309.

Sincerely; Dave axter Site Vice President Oconee Nuclear Site Z~-Ec/Y www. duke-energy. com

U. S. Nuclear Regulatory Commission April 30, 2010 Page 2 xc: Luis Reyes, Regional Administrator

.U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 John Stang, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Andrew Sabisch Senior Resident Inspector Oconee Nuclear Station Susan E. Jenkins, Manager Radioactive & Infectious Waste Management Division of Waste Management South Carolina Department of Health and Environmental Control 2600 Bull St.

Columbia, SC 29201 Mr. William Nestel INPO Records Center 700 Galleria Place, Suite 100 Atlanta, GA 30339-5957

U. S. Nuclear Regulatory Commission April 30, 2010 Page 3 bcc: C. D. Ingram EC07F L. D. Robinson ON01RP K. R. Alter ON03RC ELL NSRB Document Management Russell Keown, Supervisor Analytical & Radiological Environmental Services Division 2600 Bull Street Columbia, SC 29201 803-896-0856/KEOWN RH(@&dhec.sc.gov Sandra Flemming, Director Analytical & Radiological Environmental Services Division 8231 Parklane Road Columbia, SC 29223 803-896-3890/FLEMMISA(dhec.sc.gov Chris Staten Bureau of Land and Waste Management 2600 Bull Street Columbia, SC 29201 Crystal Rippy Bureau of Water 2600 Bull Street Columbia, SC 29201 803-898-3964

Attachment 1 Oconee Nuclear Site Radioactive Effluent Releases and Supplemental Information

OCONEE NUCLEAR STATION EFFLUENT RELEASE DATA (January 1, 2009 through December 31, 2009)

This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents as outlined in Regulatory Guide 1.21, Rev. 1, Appendix B. Radioactive liquid and gaseous wastes are sampled and analyzed per the requirements in Selected Licensee Commitment (SLC) Table 16.11.4-1, "Minimum Sampling Frequency and Analysis Program".

TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1,/10 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2009 Unit QTR 1 QTR 2 QTR 3 QTR 4 'YEAR A. Fission and Activation Gases

1. Total Release Ci 1.41E+00 1.33E+01 4.17E+00 1.72E+00 2.06E+01

2. Avg. Release Rate PCi/sec 1.81E-01 1.69E+00 5.24E-01 2.17E-01 6.52E-01 B. Iodine-131

1. Total Release Ci 6.54E-10 3.60E-04 1.33E-07 1.56E-05 3.76E-04

2. Avg. Release Rate pCi/sec 8.41E-II 4.58E-05 1.67E-08 1.96E-06 1.19E-05 C. Particulates Half Life >= 8 da'ys

1. Total Release Ci 0.OOE+00 1.30E-06 0.OOE+00 1.53E-08 1.32E-06

2. Avg. Release Rate pCi/sec O.OOE+00 1.66E-07 0.OOE+00 1.93E-09 4-.18E-08 D. Tritium

1. Total Release Ci 1.22E+01 1'.22E+01 2.02E+i01 1.21E+01 5.68E+01 2., Avg. Release Rate pCi/sec 1.57E+00 1.55E+00 2.55E+00 1.52E+00 1.80E+O00 E. Grogs Alpha Radioactivity

1. Total Release Ci 01.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

ý2. ,Avg. Release Rate pCi/sec 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0O

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 GASEOUS EFFLUENTS - ELEVATED RELEASES - CONTINUOUS MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2009 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases XE-133 Ci 1.27E+00 2.33E+00 0. OOE+00 0. OOE+00, 3..60E+00 XE-135 Ci 0. OOE+00 2.43E-01 0. OOE+00 0. OOE+00 2.43E-01 Totals for Period... Ci 1.27E+00 2.57E+00 0. 00E+00 0.OOE+00 '3.85E+00

2. Iodines 1-131 Ci 0.OOE+00 3.37E-04 0.OOE+00 1. 56E-05 3.52E-04 1-133 Ci 1.71E-06 7.91E-05 0.OOE+00 2.91E-06' 8.37E-05 Totals for Period... Ci 1l.71E-06 4.16E-04 0.OOE+00 1.85E-05 4.36E-04

3. Particulates Half Life >= 8 days CS-137 Ci .0.00E+00 1. 30E-06 0. OOE+00 0. OOE+00 1. 30E-06 Totals for Period... Ci 0.OOE+00 1.30E-06 0. OOE+00 0. OOE+00 1. 30E-06

4. Tritium H-3 Ci 8.66E+00 8. 95E+00 1. 63E+01 1.08E+01 4. 47E+01 Totals for Period... Ci 8.66E+00 8. 95E+00 1. 63E+01 1. 08E+01 4.47E+01

5. Gross Alpha'Radioactivity

- No Nuclide Activities **

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 GASEOUS EFFLUENTS - ELEVATED RELEASES - BATCH MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2009 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases AR-41 Ci 5.34E-03 1. 97E-02 1.23E-02 6.89E-03 4.43E-02 C-11 Ci 0. OOE+00 0.OOE+00 1. 09E-04 0. OOE+00 1. 09E-04 KR-85 Ci 1.27E-01 9. 60E-01 2.89E+00 1.21E+00 5.19E+00 XE-131M Ci 0.00E+00 3.22E-02 6.72E-02 1. 07E-04 9. 95E-02 XE-133 Ci 1.72E-03 9.65E+00 1.20E+00 5.02E-01 1. 13E+01 XE-133M Ci 1. 92E-05 1. 73E-02 0. OOE+00 0.OOE+00 1. 73E-02 XE-135 Ci 9.41E-05 1. 02E-02 7.72E-04 3.03E-03 1. 41E-02 Totals for Period... Ci 1. 34E-01 1. 07E+01 4.17E+00 1.72E+00 1. 67E+01

2. Iodines 1-131 Ci 6.54E-10 4.21E-06 1.33E-07 1. 86E-10 4.34E-06 1-133 Ci 6.17E-10 2.70E-07 0.OOE+00 0. OOE+00 2.71E-07 Totals for Period... Ci 1.27E-09 4.48E-06 1.33E-07 1. 86E-10 4.61E-06

3. Particulates Half Life >= 8 days CS-137 Ci 0.OOE+00 0. OOE+00 0. OOE+00 1.53E-08 1. 53E-08 Totals for Period... Ci 0.00E+00 0. OOE+00 0. OOE+00 1. 53E-08 1.53E-08

4. Tritium H-3 Ci 1.69E-03 6.78E-02 1. 94E-02 4.88E-02 1. 38E-01 Totals for Period... Ci 1.69E-03 6.78E-02 1. 94E-02 4. 88E-02 1. 38E-01

5. Gross Alpha Radioactivity

-** No Nuclide Activities **

TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2009 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases

- No Nuclide Activities **

2. Iodines 1-131 Ci 0.OOE+00 1. 91E-05 0. 00E+00 0. OO1E+00 1. 91E"05 Totals for Period... Ci 0.OOE+00 1. 91E-05 0. OOE+00 0.OOE+00 1. 91E-05

3. Particulates Half Life >= 8 days

- No Nuclide Activities ** ........

4. Tritium H-3 Ci 3.58E+00 3.16E+00 3.89E+00 1.29E+00 *1.,19E+01 Totals for Period.,.. Ci 3.58E+00 3.16E+00 3.89E+00 1.29E+00 1. 19E+01

5. Gross Alpha Radioactivity

- No Nuclide Activities **

j

TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2009 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases

- No Nuclide Activities **

2. Iodines

- No Nuclide Activities **

3. Particulates Half Life >= 8 days

- No Nuclide Activities **

4. Tritium H-3 Ci 0. OOE+00 3.17E-07 0. 00E+00 2. 68E-07 5.85E-07 Totals for Period... Ci 0.OOE+00 3.17E-07 0. OOE+00 2. 68E-07 5.85E-07

5. Gross Alpha Radioactivity

- No Nuclide Activities **

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2009 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Products

1. Total Release Ci 5.29E-03 8.77E-.03 9.59E-03 1.84E-03 2.55E-02

2. Average Diluted Concentration

a. Continuous Releases pCi/ml 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

b. Batch Releases pCi/ml 3.17E-10 5.19E-10 5.61E-10 1.07E-10 3.76E-10 B. Tritium

1. Total Release Ci 1.37E+02 2.89E+02 1.47E+02 1.54E+02 7.28E+02

2. Average Diluted Concentration

a. Continuous Releases pCi/ml 1.31E-08 1.33E-08 8.64E-09 2.76E-09 9.41E-09

b. Batch Releases pCi/ml 8.19E-06 1.71E-05 8.60E-06 9.02E-06 1.07E-05 C. Dissolved and Entrained Gases

1. Total Release Ci 0.OOE+00 7.03E-04 0.OOE+00 0.OOE+00 7.03E-04

2. Average Diluted Concentration

a. Continuous Releases pCi/ml 0.O0E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

b. Batch Releases pCi/ml 0.OOE+00 4.16E-11 0.OOE+00 0.OOE+00 1.04E-11 D. Gross Alpha Radioactivity

1. Total.Release Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

2. Average Diluted Concentration

a. Continuous Releases .Ci/ml 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00

b. Batch Releases pCi/ml 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 E. Volume of Liquid Waste

1. Continuous Releases liters 5.96E+08 6.32E+08 5.50E+08 8.42E+08 2. 62E+09

2. Batch Releases liters 7.54E+05 3.17E+06 1.07E+06 2.31E+06 7.30E+06 F. Volume of Dilution Water

1. Continuous Releases liters 1.67E+10 1.69E+10 1.71E+I0* 1.71E+10 6.78E+10

2. Batch Releases liters 1.67E+10 1.69E+10 1.71E+10 1.71E+10 6.78E+10

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 LIQUID EFFLUENTS - CONTINUOUS MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2009 Unit QTR 1 QTR 2 QTR'3 QTR 4 YEAR

1. Fission and Activation Products

- No Nuclide Activities **

2. Tritium H-3 Ci 2.27E-01 2.34E-01 1. 53E-01. 4. 95E-02 6.63E-01 Totals for Period... Ci 2.27E-01 2.34E-01 1. 53E-01. 4. 95E-02 6.63E-01

3. Dissolved and Entrained Gases

- No Nuclide Activities ** ........

4. Gross, Alpha Radioactivity

- No Nuclide Activities **

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 LIQUID EFFLUENTS - BATCH MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2009 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Products AG-I10M Ci 1.28E-04 0.OOE+00 5. 62E-05 2.85E-05 2.13E-04 CO-57 Ci 3.OOE-05 2.46E-05 0. 00E+00 0. OOE+00 5.45E-05 CO-58 Ci 3.89E-03 8.19E-03 2.06E-03 1. 32E-03 1. 55E-02 CO-60 Ci 3.03E-04 1.77E-04 0. OOE+00 0. OOE+00 4. 80E-04 CR-51 Ci 3.19E-04 7.10E-05 0. OOE+00 0. OOE+00 3. 90E-04 CS-134 Ci 0.OOE+00 0.OOE+00 1. 16E-04 0. OOE+00 1. 16E-04 CS-137 Ci 2.20E-05 1.13E-05 0.OOE+00 4.27E-05 7.59E-05 1-131 Ci 0.OOE+00 1.30E-04 0. OOE+00 0. OOE+00 1. 30E-04 MN-54 Ci 8.15E-05 3.06E-05 0. OOE+00 0. OOE+00 1. 12E-04 NB-95 Ci 3.49E-04 1.37E-04 0.OOE+00 0.OOE+00 4.86E-04 SB-124 Ci 0.OOE+00 0.OOE+00 3.56E-04 0. ORE+00 3.56E-04 SB-125 Ci O.OOE+00 0.OOE+00 6. 99E-03 4.41E-04 7.44E-03 ZR-95 Ci 1.73E-04 0.OOE+00 0. OOE+00 0. OOE+00 1. 73E-04 Totals for Period... Ci 5.29E-03 8.77E-03 9.59E-03 1. 84E-03 2.55E-02

2. Tritium H-3 Ci 1.37E+02 2.89E+02 1. 47E+02 1. 54E+02 7.27E+02 Totals for Period... Ci 1.37E+02 2.89E+02 1. 47E+02 1. 54E+02 7.27E+02

3. Dissolved and Entrained Gases XE-133 Ci 0. OOE+00 7.03E-04 0. OOE+00 0. OOE+00 7.03E-04 Totals for Period... Ci 0.OOE+00 7.03E-04 0. OOE+00 0. OOE+00 7.03E-04

4. Gross Alpha Radioactivity

- No Nuclide Activities **

OCONEE NUCLEAR STATION SUPPLEMENTAL INFORMATION

t OCONEE NUCLEAR STATION 2009 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION I. REGULATORY LIMITS - STATION A. NOBLE GASES - AIR DOSI B. LIQUID EFFLUENTS - DOSE

1. CALENDAR QUARTER - GAMMA DOSE = 15 MRAD 1. CALENDAR QUARTER - TOTAL BODY DOSE = 4.5 MREM

2. CALENDAR QUARTER - BETA DOSE = 30 MRAD 2. CALENDAR QUARTER - ORGAN DOSE = 15 MREM

3. CALENDAR YEAR - GAMMA DOSE = 30 MRAD 3. CALENDAR YEAR - TOTAL BODY DOSE = 9 MREM

4. CALENDAR YEAR - BETA DOSE = 60 MRAD 4. CALENDAR YEAR - ORGAN DOSE = 30 MREM C. IODINE - 131 AND 133, TRITIUM, PARTICULATES W/T 1/2 > 8 DAYS - ORGAN DOSE

1. CALENDAR QUARTER = 22.5 MREM

2. CALENDAR YEAR = 45 MREM II. MAXIMUM PERMISSIBLE EFFLUENT CONCENTRATIONS I

A. GASEOUS EFFLUENTS - INFORMATION FOUND IN OFFSITE DOSE CALCULATION MANUAL B. LIQUID EFFLUENTS - INFORMATION FOUND IN 10CFR20, APPENDIX B, TABLE 2, COLUMN 2 III. AVERAGE ENERGY - NOT APPLICABLE IV. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY ANALYSES OF SPECIFIC RADIONUCLIDES IN SELECTED OR COMPOSITED SAMPLES AS DESCRIBED IN THE SELECTED LICENSEE COMMITMENTS ARE USED TO DETERMINE THE RADIONUCLIDE COMPOSITION OF THE EFFLUENT. SUPPLEMENTAL REPORT, PAGE 2, PROVIDES A

SUMMARY

DESCRIPTION OF THE METHOD USED FOR ESTIMATING OVERALL ERRORS ASSOCIATED WITH RADIOACTIVITY MEASUREMENTS.

V. BATCH RELEASES A. LIQUID EFFLUENT

1. 8.60E+01 = TOTAL NUMBER OF BATCH RELEASES

2. 1.87E+04 = TOTAL TIME (MIN.) FOR BATCH RELEASES.

3. 2.62E+02 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.

4. 2.17E+02 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.

5. 5.00E+00 = MINIMUM TIME (MIN.) FOR A BATCH RELEASE.

6. 3.41E+04 = AVERAGE DILUTION WATER FLOW DURING RELEASES (GPM).

B. GASEOUS EFFLUENT

1. 5.70E+01 = TOTAL NUMBER OF BATCH RELEASES.

2. 1.20E+05 = TOTAL TIME (MIN.) FOR BATCH RELEASES.

3. 5.44E+04 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.

4. 2.11E+03 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.

5. 4.80E+01 = MINIMUM TIME. (MIN.) FOR A BATCH RELEASE.

VI. ABNORMAL RELEASES A. LIQUID

1. NUMBER OF RELEASES = 0

2. TOTAL ACTIVITY RELEASED (CURIES) = 0 B. GASEOUS

1. NUMBER OF RELEASES = 0

2. TOTAL ACTIVITY RELEASED (CURIES) = 0

SUPPLEMENTAL REPORT PAGE 2 OCONEE NUCLEAR STATION The estimated percentage of error for both Liquid and Gaseous effluent release data at Oconee Nuclear Station has been determined to be +/- 25.2%. This value was derived by taking the square root of the sum of the squares of the following discrete individual estimates of error:

(1) Flow rate determining devices = +/-20%

(2) Counting error = +/-15%

(3) Sample preparation error : +/- 3%

OCONEE NUCLEAR STATION Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (January 1, 2009 through December 31, 2009)

This attachment includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of this report, as well as the total dose for the calendar year. The effluent dose calculations consider radionuclides identified as part of the liquid and gaseous-wastes sample and analysis program. Radioactive liquid and gaseous wastes are sampled and analyzed per the requirements in Selected Licensee Commitment (SLC) Table 16.11.4-1, "Minimum .SamplingFrequency and Analysis Program". Attachment 4, 'Fuel Cycle Calculation", also includes an assessment of radiation doses to the maximum exposed member of the public from all uranium fuel cycle sources within 8 km of Oconee for the calendar year of this report to show conformance with 40 CFR 190. Methods for calculating the dose contribution from liquid and gaseous effluents are given in the ODCM.

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 1 St Quarter 2009

-- IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS==ý-= Quarter 1 2009 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q1 - Maximum Organ Dose CHILD THYROID 5.31E-03 2.25E+01 2.36E-02 Maximum Organ Dose Receptor Location: 1.0 Mile SE Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.OOE+02

-= NOBLE GAS DOSE LIMIT ANALYSIS - --- Quarter 1 2009 Dose Limit % of Period-Limit (mrad) (mrad) Limit Ql - Maximum Gamma Air Dose 2.66E-05 1.50E+01 1.77E-04 Maximum Gamma Air Dose Receptor Location: 1.0 Mile SW Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage XE-133 8.96E+01 AR-41 9.91E+00 Ql - Maximum Beta Air Dose 8.49E-05 3.OOE+01 2.83E-04 Maximum Beta Air Dose Receptor Location: 1.0 Mile SW Major Contributors (5% or greater to total)

Nuclide Percentage XE-133 8.35E+01 KR-85 1.54E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 2 nd Quarter 2009

- IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS=-- Quarter 2 2009 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose CHILD THYROID 1.16E-02 2.25E+01 5.17E-02 Maximum Organ Dose Receptor Location: 1.0 Mile SW Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage 1-131 6.03E+01 H-3 3.93E+01

- NOBLE GAS DOSE LIMIT ANALYSIS- - Quarter 2 2009 Dose Limit % of Period-Limit (mrad) (mrad) Limit Q2 - Maximum Gamma Air Dose 2.61E-04 1.50E+01 1.74E-03, Maximum Gamma Air Dose Receptor Location: 1.0 Mile SW Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage XE-133 8.58E+01 XE-135 9.88E+00 Q2 - Maximum Beta Air Dose 8.06E-04 3.OOE+01 2.69E-03 Maximum Beta Air Dose Receptor Location: 1.0 Mile SW Major Contributors (5% or greater to total)

Nuclide Percentage XE-133 8.28E+01 KR-85 1.23E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 3 rd Quarter 2009

- IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS=----=== Quarter 3 2009 ==

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose CHILD THYROID 7.05E-03 2.25E+01 3.13E-02 Maximum Organ Dose Receptor Location: 1.0 Mile SW Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H------ ----

H-3 1.00E+02

-- NOBLE GAS DOSE LIMIT ANALYSIS==-- Quarter 3 2009 Dose Limit % of Period-Limit (mrad) (mrad) Limit Q3 - Maximum Gamma Air Dose 3.17E-05 1.50E+01 2.12E-04 Maximum Gamma Air Dose Receptor Location: 1.0 Mile SW Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage XE-133 7.06E+01 AR-41 1.91E+01 KR-85 8.30E+00 Q3 - Maximum Beta Air Dose 3.72E-04 3.OOE+01 1.24E-03 Maximum Beta Air Dose Receptor Location: 1.0 Mile SW Major Contributors (5% or greater to total)

Nuclide Percentage KR-85 8.04E+01 XE-133 1.79E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 4t Quarter 2009

- IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS=... Quarter 4 2009 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose CHILD THYROID 4.10E-03 2.25E+01 1.82E-02 Maximum Organ Dose Receptor Location: 1.0 Mile SW Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage Hý-3 9.27E+01 1-131 7.24E+00 NOBLE GAS DOSE LIMIT ANALYSIS Quarter 4 2009 Dose Limit % of Period-Limit (mrad) (mrad) Limit Q4 - Maximum Gamma Air Dose 1.42E-05 1.50E+01 9.46E-05 Maximum Gamma Air Dose Receptor Location: 1.0 Mile SW Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage XE-133 6.61E+01 AR-41 2.39E+01*

KR-85 7.77E+00 Q4 - Maximum Beta Air Dose 1.55E-04 3.00E+01 .5.15E-04 Maximum Beta Air Dose Receptor Location: 1.0 Mile SW Major Contributors (5% or greater to total)

Nuclide Percentage KR-85 8.09E+01 XE-133 1. 81E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 ANNUAL 2009 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS = Annual 2009 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose CHILD THYROID 2.75E-02 4.50E+01 6.12E-02 Maximum Organ Dose Receptor Location: 1.0 Mile SW Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 7.32E+01 1-131 2.66E+01

- NOBLE GAS DOSE LIMIT ANALYSIS Annual 2009

Dose Limit % of Period-Limit (mrad) (mrad) Limit Yr - Maximum Gamma Air Dose 3.34E-04 3.00E+01 1.lIE-03 Maximum Gamma Air Dose Receptor Location: 1.0 Mile SW Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage XE-133 8.39E+01 XE-135 7.85E+00 AR-41 6.54E+00 Yr - Maximum Beta Air Dose 1.42E-03 6.OOE+01 2.36E-03 Maximum Beta Air Dose Receptor Location: 1.0 Mile SW Major Contributors (5% or greater to total)

Nuclide Percentage XE-133 5.87E+01 KR-85 3.78E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 LIQUID ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 1 st Quarter 2009

=== BATCH LIQUID RELEASES Quarter 1 2009 *-

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (trem) Limit Qi - Maximum Organ Dose ADULT GILLI 7.74E-02 1.50E+01 5.16E-01 Ql - Total Body Dose ADULT 1.03E-02 4.50E+00 2.29E-01 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage NB-95 8. 64E+01 H-3 1. 18E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 8.88E+01 CS-137 9.44E+00 CONTINUOUS LIQUID RELEASES (CTP 3) Quarter 1 2009 ...

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (trem) Limit Ql - Maximum Organ Dose CHILD LIVER 1.52E-05 1.50E+01 1.01E-04 Q1 - Total Body Dose CHILD 1.52E-05 4.50E+00 3.38E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1. OOE+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00E+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 LIQUID ANNUAL DOSE SUMARY REPORT Oconee Nuclear Station Units 1, 2, & 3 2 nd Quarter 2009

- BATCH LIQUID RELEASES Quarter 2 2009 -

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose ADULT GILLI 4.76E-02 1.50E+01 3.17E-01 Q2 - Total Body Dose CHILD 2.05E-02 4.50E+00 4.55E-01 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage NB-95 5.49E+01 H-3 4.06E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.80E+01 CONTINUOUS LIQUID RELEASES (CTP 3) Quarter 2 2009 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose CHILD LIVER 1.57E-05 1.50E+01 1.04E-04 Q2 - Total Body Dose CHILD 1.57E-05 4.50E+00 3.48E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1. OOE+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00OE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 LIQUID ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 3 rd Quarter 2009

-= BATCH LIQUID RELEASES Quarter 3 2009 Critica 1 Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (trem) Limit Q3 - Maximum Organ Dose ADULT LIVER 2.05E-02 1.50E+01 1.36E-01 Q3 - Total Body Dose ADULT 1.86E-02 4.50E+00 4.12E-01 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage CS-134 5.19E+01 H-3 4.80E+01 Total Body Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 5.29E+01 CS-134 4.68E+01 CONTINUOUS LIQUID RELEASES (CTP 3) Quarter 3 2009 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose CHILD LIVER 1.03E-05 1.50E+01 6.84E-05 Q3 - Total Body Dose CHILD 1.03E-05 4.50E+00 2.28E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or gre ater to total)

Nuclide Percentage H-3 1. OOE+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00E+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 LIQUID ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 4h Quarter 2009

--- BATCH LIQUID RELEASES Quarter 4 2009 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose CHILD LIVER 1.34E-02 1.50E+01 8.96E-02 Q4 - Total Body Dose ADULT 1.22E-02 4.50E+00 2.72E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 7.97E+01 CS-137 2.02E+01 Total Body Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 8.43E+01 CS-137 1. 54E+01

-- CONTINUOUS LIQUID RELEASES (CTP 3) Quarter 4 2009 -

Critical Critical Dose Limit Max % of

'Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose CHILDI LIVER 3.27E-06 1.50E+01 2.18E-05 Q4 - Total Body Dose CHILD 3.27E-06 4.50E+00 7.28E-05 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1. OOE+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00OE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 LIQUID ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 ANNUAL 2009

-- BATCH LIQUID RELEASES Annual 20 09 Critical Critical Dose Limit Max % of Period-Limit Age Organ (torer) (toren) Limit Yr - Maximum Organ Dose ADULT GILLI 1.46E-01 3.OOE+01 4.87E-01 Yr - Total Body Dose ADULT 6.12E-02 9:00E+00 6.80E-01 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage NB-95 6. 36E+01 H-3 3.33E+01 Total Body Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 7.94E+0i CS-134 1. 42E+01 CS-137 5. 49E+00

-- CONTINUOUS LIQUID RELEASES (CTP 3) Annual 2009 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose CHILD LIVER 4.43E-05 3.OOE+01 1.48E-04 Yr - Total Body Dose CHILD 4.43E-05 9.00E+00 4.92E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total),

Nuclide Percentage H-3 1. OOE+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00OE+02

OCONEE NUCLEAR STATION 2009 METEOROLOGICAL JOINT FREQUENCY. DISTRIBUTIONS OF WIND SPEED, WIND DIRECTION, AND ATMOSPHERIC STABILITY USING WINDS AT THE 10 METER LEVEL (Hours of Occurrence)

Oconee Nuclear Station The SAS System The FREQ Procedure Table of STAB by CALM STAB CALM Frequeency CALM WIND Total 1 0 580 580 2 0 505 505 3 0 617 617 4 1 3749 3750 5 2 2802 2804 6 1 332 333 7 0 115 115 Total 4 8700 8704 Frequency Missing_= 56 1

The SAS System SECTOR N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW No. No. No. No. No. No. No. No. No. No. No. No. No. No. No. No.

STAB WSCLS A 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0.75-1.00 0 0 0 0 1 0 0 0 0 1 0 1.00-1.25 2 0 0 1 0 0 0 0 0 0 1 1.25-1.50 2 0 1 0 0 0" 1 4 0 1 2 1.50-2.00 7 5 0 2 2 20 44 21 8 1*

2.00-3. 00 3 6 20 12 3 4 43 117 53 4 2 3.00-4 .00 1 7 16 5 0 1 9 29 6 6 0 4.00-5. 00 0 1 5 0 0 0 4 12 3 4 2 5.00-6.00 0 0 0 0 0 0 3 1 4 2 o1 6.00-8 .00 0 0 0 0 0 0 '0 0 0 0 0 8.00-10.00 0 0 0 0 0 0 0 0 0 0 0 10.01-99.99 0 0 0 0 0 0 0 0 0 0 0 B 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0.75-1.00 .0 0 0 0 0 0 0 0 0 0 11 0

1.00-1.25 0 0 0 0 0 0 2 1 0 0 0 1.25-1.50 4 0 0 1 1 3 2 7 1 3 2 1 .50-2.00 12 5 5 1 4 9 31 22 14 2 .00-3. 00 0 2 13 24 10 6 2 4 8 36 53 21 9 2 1 2 2

3.00-4.00 2 0 1 10 0 1 0 0 0 12 26 2 0 2 2 4 4.00-5.00 0 0 0 5 0 0 0 0 0 1 5 6 2 3 4 0 5.00-6.00 0 0 0 0 0 0 0 0 0 0 2 4 2 3 1 3 6.00-8.00 0 0 0 0 0 0 0 0 0 0 1 1 0 5 10 1 8.00-1,0.00 0 0 0 0 0 0 0 0 0 0 0 2 2 0 0 0 10.01-99.99 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 C 0.46-0.75 0 '0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.75-1.00 0 0 0 0 0 1 0 1 0 0 0 1 0 0 0 0 1.00-1.25 1 0 1 0 2 3 0 0 2 1 6 2 1 2 1 1 1.25-1.50 3 7 4 1 1 0 2 4 4 5 9 9 10 6 4 2 1.50-2.00 5 9 21 11 11 4 3 5 8 10 26 1,4 4 9 4 2 2.00-3.00 3 5 13 19 16 2 8 4 7 33 43 16 4 2 1 2 3.00-4.00 0 0 5 15 2 0 0 0 0 26 20 9 3 2 3 3 4.00-5.00 1 0 1 2 1 0 0 0 0 8 10 8 2 3 4 2 5.00-6.00 0 0 0 0 0 0 0 0 0 0 3 5 3 8 8 0 6.00-8.00 0 0 0 0 0 0 0 0 0 0 3 8 6 6 9 2 8.00-10.00 0 .0 0 0 0 0 0 0 0 0 1 2 1 1 0 '0 10.01-99.99 0 0 0 0 0 0 0 0 0 0 0 '0 0 0 0 0 0.46-0.75 6 2 0 2 1 2 3 3 1 2 4 3 4 3 4 5 0.75-1.00 22 12 11 12 9 8 13 10 14 12 20 22 14 24 22 27 1.00-1.25 26 19 17 19 13 13 25 14 16 17 25 22 32 25 22 31 1.25-1.50 25 28 31 49 34 20 25 31 31 21 38 25 35 24 19 29 3B

1.50-2.00 27 17 96 141 99 41 ,38 37 ~34 40 67 55 39 2 23 19 166 2 .00-3. 00 14 130 278 81 21 19 12 30 93 137 73 35 29 18 22 3.00-4 .00 6 11 48 76 9 2 2 0 3 42 104 77 35 22 15 9 4 .00-5. 00 2 4 15 17 2 0 0 0 0 16 57 46 39 26 13 5 5.00-6.00 0 0 ~4 1 0 0 0 0 0 2 24 21 21 17 11 1

6. 00-8 .00 0 0 0 0 0 0 0 0 0 0 7 12 13 5 3 1 8 .00-10. 00 0 0 0 0 0 0 0 0 0 2 .2 2 4 2 0 *0 10.01-99.99 0 0 0 0 0 0 0 0 0 0 0 0 1 *0 0 0 E 0. 46-0.75 13 13 6 6 10 5 4 5 2 2 1 5 10 16 11 22 0.75-1.00 70 63 42 43 29 21 25 J18 17 21 16 28 27 51 100 85 1.00-1.25 63 31 33 36 39 34 31 24 32 18 21 19 19 48 55 48 1.25-1.50 18 16 29 52 54 57 40 33 26 15 29 12 18 27 38 18 1.,50-2 .00 10 10 34 65 58 38 56 49 35 39 39 20 19 13 14 18 2.00-3.00 7 4 21 38 31 16 12 11 15 34 43 32 23 15 16 5

3. 00-4 .00 1 0 0 9 7 2 0 0 7 8 20 25 10 1 2 1 4 .00-5.00 0 0 0 1 0 0 0 1 0 1 10 20 4 2 1 0 5.0076.00 0 0 1 1 0 0 0 0 0 0 4 2 0 0 1 0 6.00-8.00 0 0 0 0 0 0 0 0 0 0 0 0 *0 0 0 0 8.00-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.

10.01-99.99 0 0 0 0 .0 0 0 0 0 0 0 0 0 0 0 0 0.46-0.75 2 .1 0 .0 0 0 0 0 0 0 0 0 5 9 8 3 0.75-1.00 0 1 2 5 3 3 2 0 3 4 4 10 9 40 32 5 1.00-1. 25 5 2 0 1 3 2 2 2 3 1 2 2 5 23 17 3 4

1.25-1.50 0 1 1 1 0 3 3 0 1 5 1 18 23 0

1. 50-2. 00 0 0 0 2 5 2 0 0 2 1 1 4 6 1 2.00-3.00 0 0 1 1 1 2 0 1 0 0 1 0 3.00-4 .00 0 0 1 0 1 1 0 0 3 3 0 0 0 0 4 .00-5.00 0 0* 0 0~ 0 0~ 0 0 0 0 0 0 0 0 5.00-6.00 0 0 0 0 0 0 0 0 0 0 0 0 0 ' 0

6. 00-8 .00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8.00-10.00 0 o 0 0 0 0 0 0 0. 0 0 0 0 0

10. 01-99.99 0 0 0 0 0 0 0 0 0 0 ~0 0 0 0 G 0.46-0.75 0 0 0 0 0 0 0 0 0 0 3 1 3 0 0.7 5-1.00 0 0 0 0 .0 0 0 0 1 2 10 14 9 3 1.00-1.25 1 0 0 1 *0 0 0 0 0 2 8 18 8 0 1.25-1.50 1 0 0 0 0 0 0 0 3 0 2 12 3 1 1.50-2.00 0 0 0 0 0 0 0 1 0 0 0 2 0 0 2.00-3.00 0 0 0 0 0 0 0 0 2 0 0 0 1 0

3. 00--4 .00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4 .00-5.00 0 ~0 0 0~ 0 0 0 0 0 0 0 0 0~ 0 5.00-6.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6.00-8.00 0 0 0 0 0 0 0 0 0 0 0 *0 0 0 8.00-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10.01-99.99 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5

Attachment 2 Oconee Nuclear Site Solid Waste Disposal Report

OCONEE NUCLEAR STATION ANNUAL RADWASTE REPORT 3121/2010 DUKE POWER COMPANY OCONEE NUCLEAR STATION SOLID RADIOACTIVE WASTE SHIPPED TO A DISPOSAL FACILITY REPORT PERIOD: JANUARY - DECEMBER YEAR: 2009 TOTAL TYPES OF WASTE NUMBER OF NUMBER OF WASTE CLASS CONTAINER BURIAL VOLUME ACTIVITY SHIPPED SHIPMENTS CONTAINERS A-U A-S B C TYPE CU. FT. CU. M. CURIES

1) WASTE FROM LIQUID SYSTEM (A) DEWATERED POWDEX RESIN 0 0 0 0 0 0 STC 0 0.00 0.00 (B) DEWATERED BEAD RESIN 5 5 0 0 5 0 TYPE A 601.5 17.03 605.96 (C) EVAPORATOR CONCENTRATES 0 0 0 0 0 0 0 0.00 0.00 (D) DEWATERED MECHANICAL FILTERS

1. PRIMARY FILTER MEDIA 2 2 0 0 0 2 TYPE A 240.6 6.81 7.96

2. SECONDARY FILTER MEDIA 1 1 1 0 0 0 STC 0 0.00 0.0003 (F) SOLIDIFIED (CEMENT) OIL, ACIDS,SLUDGES 0 0.00 0 0 0 0 0 STC 0.00

2) DRY SOLID WASTE (A) DRY ACTIVE WASTE (COMPACTED) (1) 39 39 39 0 0 0 STC 5935.8 168.09 2.14 (2) 23 23 23 0 0 0 STC 2480.23 70.23 0.12 (B) DRY ACTIVE WASTE (NON-COMPACTED) 1 0 0 0 1 TYPE A 120.3 3.41 13.70 (C) DRY ACTIVE WASTE (BROKERED) 0 0 0 0 0 0 0 0.00 0.00 (D) IRRADIATED COMPONENTS 0 0 0 0 0 0 TYPE B 0 0.00 0.00 TOTAL 71 71 63 0 5 3 9378.47 265.57 629.88 NOTE: (1) SHIPMENTS FROM DURATEK ENVIROCARE OF UTAH OR CNSI @ BARNWELL (DAW)

(2) SHIPMENTS FROM DURATEK TO ENVIROCARE OF UTAH OR CNSI @ BARNWELL (METAL)

SHIPMENTS MADE FROM OTHER COMPANYS SO INFORMATION IS NOT KNOWN Page 1 of 12

Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY- DECEMBER WASTE TYPE: POWDEX RESIN ISOTOPE: % ABUNDANCE/LINER # OF LINERS SHIPPED TO ENVIROCARE 0 # OF SHIPMENTS TO ENVIROCARE 0 TOTAL AVE.

CR-51 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

MN-54 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0-00 0.00 0.00 0.00 0.00 #DIV/0!

CO-57 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!

CO-58 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV10!

CO-60 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIVIO!

NB-95 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

ZR-95 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIVO!

CS-134 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!

RU-103 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DJV/OI AG-110m 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!

SB-125 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

1-131 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CS-137 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

H-3 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

NI-63 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

FE-55 0.0000 0.0000. 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

SR-90 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

TE-125m 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CS-136 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

XE-133 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

C-14 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

PU-241 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

TRU 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

FE-59 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

SB-124 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

RU-106 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CE-144 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

TE-132 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

AM-241 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00. 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/01 TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.00 #DIV/0!

CLASS C 0 0 0, 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS B 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AU 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CURIES 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CU. FT. 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CU. M 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 RSR#

Page 2 of 12

Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY - DECEMBER WASTE TYPE: PRIMARY RESIN

OF LINERS SHIPPED TO CNSI 5 ISOTOPE: % ABUNDANCE/LINER # OF SHIPMENTS TO CNSI 5 TOTAL AVE-CR-51 0.0000 0.0000 0.0000 0.0190 0.0000 0.0000 0.0000 0.0000 0w0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0190 0.0038 MN-54 1.5877 1.7327 1.6301 1.7552 1.5441 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 8.2498 1.6500 CO-57 0.5735 0.6057 0.7421 0.5518 1.0316, 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 3.5047 0.7009 CO-58 42.9159 34.9511 13.8752 27.9903 37.5414 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 157.2739 31.4548 CO-60 2.9541 3.2878 5.5717 3.9023 3.9174 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 19.6333 3.9267 NB-95 0.0000 0.0000 0.0009 0.0196 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0205 0.0041 ZR-95 0.0000 0.0000 0.0000 0.0129 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0129 0.0026 CS-134 7.6113 8.9451 5.5455 9.3564 5.0599 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 36.5183 7.3037 RU-106 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 AG-110m 0.1145 0.1955 0.4909 0.0185 0.0695 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.8889 0.1778 SB-125 0.0000 0.3569 1.3411 0.0274 1.7628 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 3.4882 0.6976 1-131 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 CS-1 37 10.3922 12.6327 13.8510 13.4151 6.3004 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 56.5914 11.3183 H-3 0.0037 0.0096 0.0821 0.0050 0.0021 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.1025 0.0205 NI-63 26.4616 29.0272 46.0086 34.4971 34.6034 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 170.5979 34.1196 FE-55 5.6291 6.3682 9.5471 7.5466 7.5409 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 36.6319 7.3264 SR-90 0.2434 0.2962 0.4030 0.3133 0.1479 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 1.4038 0.2808 TE-125m 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 CS-136 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 XE-133 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 -0.0000 0.0000 C-14 0.1838 0.1999 0.4225 0.2386 0.2403 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 1.2851 0.2570 PU-241 0.0212 0.0258 0.0319 0.0274 0.0129 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.1192 0.0238 1-129 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 TC-99 0.0146 0.0178 0.0224 0.0188 0.0089 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0825 0.0165 CM-242 0.0001 0.0001 0.0001 0.0001 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0004 0.0001 AM-241 0.0004 0.0005 0.0006 0.0005 0.0002 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0022 0.0004 PU-239/40 0.0003 0.0004 0.0005 0.0004 0.0002 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0018 0.0004 PU-238 0.0006 0.0007 0.0009 0.0008 0.0004 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0034 0.0007 CM-243144 0.0004 0.0005 0.0006 0.0005 0.0002 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0022 0.0004 Be-7 1.0873 1.1004 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 2.1877 0.4375 SB-124 0.0000 0.0000 0.0035 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0035 0.0007 SN-113 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 CE-144 0.0801 0.1091 0.1149 0.1139 0.0526 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0,0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.4706 0.0941 FE-59 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 ZN-65 0.0000 0.0000 0.0961 0.0068 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.1029 0.0206 NI-59 0.1241 0.1361 0.2167 0.1618 0.1629 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.8016 0.1603 SR-89 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 TOTAL 100.00 100.00 100.00 100.00 100.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 499.20 99.84 CLASS C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS B 1 1 1 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5 CLASS AS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AU 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 3 of 12

Oconee Nuclear Station Annual Report CURIES 113 67.5 4.46 114 307 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 605.96 CU. FT. 120.3 120.3 120.3 120.3 120.3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 601.5 CU. M 3.41 3.41 3.41 3.41 3.41 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 17.03 RSR# 09-2005 09-2008 09-2015 09-2017 09-2038 Page 4 of 12

Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY - DECEMBER WASTE TYPE: COMPACTED DAW (DURATEK)

OF SHIPMENTS FROM ONS TO DURATEK 24 # OF CONTAINERS FROM ONS TO DURATEK 45

OF SHIPMENTS FROM PROCESSOR TO ENVIROCARE 39 # OF CONTAINERS FROM PROCESSOR TO ENVIROCARE 39

OF SHIPMENTS FROM PROCESSOR TO BARNWELL 0 # OF CONTAINERS FROM PROCESSOR TO BARNWELL 0 CU. FT.. CURIES CU. FT. DISPOSAL C1TO DISPOSAL RSR # SHIPPED SHIPPED FACILITY FACILITY COMPLETED 08-2035 0 0.0000 0.443 0.00063 08-2062 0 0.0000 212.000 0.00840 08-2065 0 0.0000 71.529 0.00723 08-2070 0 0.0000 115.143 0.03211 08-2071 0 0.0000 240.857 0.16847 08-2072 0 0.0000 387.143 0.00823 08-2080 0 0.0000 250.000 0.11866 08-2085 0 0.0000 181.429 0.03424 08-2088 0 0.0000 203.143 0.01213 09-2001 1868.8 0.0379 193.243 0.03703 09-2002 1868.8 0.1230 227.429 0.12316 09-2003 1868.8 0.1350 159.429 0.13475 09-2007 934.4 0.0363 264.986 0.08307 09-2010 1556.65 0.0126 194.000 0.01258 09-2011 1868.8 0.0328 191.714 0.03279 09-2019 1868.8 0.0162 177.000 0.01613 09-2020 1868.8 0.0874 175.143 0.08746 09-2021 1868.8 0.0422 188.000 0.04724 09-2022 1868.8 0.2850 240.857 0.28559 09-2027 1868.8 0.1050 208.571 0.10468 09-2028 1868.8 0.1940 199.143 0.19415 09-2039 934.4 0.0223 204.643 0.04166 09-2040 1868.8 0.0278 181.714 0.02780 09-2041 1868.8 0.0098 147.929 0.14793 09-2045 1868.8 0.0216 182.429 0.02018 09-2046 934.4 0.0308 196.000 0.03170 09-2048 1868.8 0.0384 200.571 0.03847 09-2050 1868.8 0.0125 158.286 0.01250 09-2058 1868.8 0.0685 173.357 0.06750 09-2059 1868.8 0.1340 224.857 0.13421 09-2060 1868.8 0.0680 164.857 0.06668 09-2061 1805.8 0.0902 0.000 0.00000 09-2064 1868.8 0.0020 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0,00000 TOTAL 41672.85 1.633 5935.84 2.13738 TOTAL CURIES BURIED 2.137 TOTAL CUBIC FEET BURIED 5935.84 TOTAL CUBIC METERS 168.09 Page 5 of 12

Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY - DECEMBER WASTE TYPE: UNCOMPACTED DAW

OF SHIPMENTS FROM ONS TO CNSI

OF CONTAINERS FROM ONS TO CNSI RSR CUBIC NUMBER FEET CURIES A-U A-S B C 09-2016 120.3 13.7 0 0 0 0 0 0 0 .0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 120.3 13.7 TOTAL CUBIC METERS 3.41 Page 6 of 12

Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY - DECEMBER WASTE TYPE: METAL (CNSI,DURATEK,ENVIROCARE)

OF SHIPMENTS TO DECON FACILITY 9 # OF SHIPMENTS TO ENVIROCARE: 23

OF CONTAINERS TO DECON FACILITY 10 # OF CONTAINERS TO ENVIROCARE: 23 DECON/DISP. CU. FT.. CURIES CU. FT. TO CURIES TO RSR # FACILITY TO PROCESSOR TO PROCESSOR DISPOSAL FACILITY DISPOSAL FACILITY COMPLETED 08-2023 0 0 7.71 0.00000 08-2038 0 0 0.67 0.00026 08-2040 0 0 67.48 0.00244 08-2048 0 0 0.71 0.00002 08-2087 0 0 298.86 0.00543 08-2060 0 0 213.14 0.00814 08-2065 0 0 56.76 0.00574 09-2001 0 0 3.04 0.00085 09-2004 1167.99 0.0511 237.59 0.00000 09-2006 934.4 0.00795 511.71 0.00795 09-2007 934.4 0.0818 123.59 0.03506 09-2033 934.4 0.011 316.00 0.01057 09-2039 503.1 0.0396 90.47 0.02015 09-2041 0 0 6.64 0.00054 09-2043 934.4 0.0049 442.86 0.00488 09-2044 67.13 0.017 88.29 0.01663 09-2045 0 0 14.71 0.00142 09-2046 934.4 0.00109 0.00 0.00000 09-2047 934.4 0.0049 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 TOTAL 7344.62 0.21934 2480.23 0.12009 TOTAL CUBIC METERS 70.23354 Page 7 of 12

Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY - DECEMBER WASTE TYPE: IRRADIATED COMPONANT

OF CONTAINERS SHIPPED TO CNSI/DURATEK ISOTOPE: % ABUNDANCEILINER # OF SHIPMENTS TO CNSI/DURATEK 0 TOTAL AVE.

CR-51 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

MN-54 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CO-57 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CO-58 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIVI0!

CO-60 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

NB-95 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

ZR-95 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CS-134 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

RU-103 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

AG-110m 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

SB-125 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

1-131 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CS-137 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIVIO!

H-3 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

NI-63 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

FE-55 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

NI-59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

TE-125m 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CS-136 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

XE-133 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

C-14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

PU-241 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0000 #DIV/0!

TRU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

FE-59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

SB-124 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

RU-106 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CE-144 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

TA-182 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CM-242 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0000 #DIV/0!

PU-238 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0000 #DIV/0!

CM-243 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0000 #DIV/01 TOTAL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CLASS C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS B 0 0 0 0 0 - 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AU 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CURIES 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CU. FT. 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CU. M 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 RSR#

Page 8 of 12

OCONEE NUCLEAR STATION SOLID RADV W15e@ERMTear Station Annual Report REPORT PERIOD: JANUARY - DECEMBER WASTE TYPE: PRIMARY FILTERS

OF DRUMS/LINERS TO CNSI 2 ISOTOPE: # OF SHIPMENTS TO CNSI 2 TOTAL AVE.

CR-51 0.28030 1.27 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 10.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.55 0.775 MN-54 1.86580 1.61 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 3.47 1.736 CO-57 0.78210 0.50 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.28 0.640 CO-58 41.93320 52.06 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00. 0.00 0.00 0.00 93.99 46.995 CO/60 7.86840 4.45 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 12.32 6.160 NB-94 0.13000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.13 0.065 TC-99 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 CS-1 34 0.38400 7.84 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 8.23 4.113 RU-103 0.00010 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 AG-110m 0.46030 0.22 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.68 0.342 SB-125 0.19650 0.15 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.35 0.175 1-129 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0000 0.00000 CS-137 1.01300 11.54 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 12.55 6.277 H-3 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 NI-63 11.68480 3.12 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 14.80 7.401 FE-55 23.98200 8.66 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 32.65 16.323 SR-90 0.81510 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.82 0.408 TE-125m 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 CS-136 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 XE-133 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 C-14 7.82130 6.73 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 14.55 7.276 PU-241 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 PU-238 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 PU-239 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 SB-124 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 RU-106 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 CE-144 0.36990 0.29 0.00 0.00. 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.66 0.330 NI-59 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 CE-141 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 AM-241 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 CM-242 0.00050 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.001 CM-243/44 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 NB-95 0.00000 0.51 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.51 0.257 ZR-95 0.22520 0.86 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.09 0.545 HG-203 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00000 0.0000000 SN-113 0.01950 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.042 0.021 CD-109 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0000 0.00000 FE-59 0.02070 0.04 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0563 0.02815 ZN-65 0.14650 0.12 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.2619 0.13095 SR-89 0.00070 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0032 0.00160 BA-140 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0000 0.00000 TOTAL 100.00 100.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 199.73 99.87 CLASS C 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 CLASS B - 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AU 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 9 of 12

CURIES 2.12 5.84 0 0 0 0 0 0 Ocone§ Nucldar Stat~on Anfual Rbport 0 0 0 0 0 0 0 7.96 CU. FT. 120.3 120.3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 240.6 CU. M 3.406581 3.406581 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6.813162 RSR# 09-2013 09-2014 Page 10 of 12

Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY - DECEMBER WASTE TYPE: SECONDARY FILTERS

OF CONTAINERS SHIPPED TO DURATEK # OF CONTAINERS SHIPPED TO CNSI / ENVIROCARE 1

OF SHIPMENTS TO DURATEK # OF SHIPMENTS TO CNSI I ENVIROCARE ISOTOPE: TOTAL AVE.

CR-51 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!

MN-54 0.45 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.45 #DIV/O!

CO-57 0.16 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.16 #DIV/0!

CO-58 1.20 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.20 #DIV/0!

CO-60 4.69 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 4.69 #DIV/0!

NB-95 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

ZR-95 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0l CS-134 0.31 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.31 #DIV/0I RU-1 03 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

AG-110m 11.51 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 11.51 #DIV/01 AG-A08m 0.08 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00. 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.08 #DIV/O!

SB-125 4.99 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 4.99 #DIV/0!

1-131 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CS-137 7.93 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 7.93 #DIV/0!

H-3 48.04 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 48.04 #DIV/0!

NI-63 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

FE-55 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

SR-90 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!

TE-125m 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!

CS-136 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/01 XE-133 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

C-14 20.41 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 20.41 #DIV/01 PU-241 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

TRU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0I FE-59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

SB-124 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/01 RU-106 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CE-144 0.22 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CM-243 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

PU-238 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

PU-239 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

AM-241 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIVI0!

CM-242 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

SR-89 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

TOTAL 100.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 99.78 #DIV/0!

CLASS C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS B 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AU 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 CURIES 0.00027 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.00027 FT3 Shipped 63 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 63 CU. M Shipped 1.7840 0.0000 0.0000 0.0000 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.784 FT3 Buried 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CU. M Buried 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0 RSR# 09-2061 Page 11 of 12

Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY - DECEMBER WASTE TYPE: SOLIDIFIED (CEMENT) OIL, ACIDS, SLUDGES

OF CONTAINERS SHIPPED 0 ISOTOPE: % AEUNDANCE/LINER # OF SHIPMENTS 0 TOTAL AVE-CR-51 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0:00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0O MN-54 0.00 0.00 0.00 0.00. 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CO-57 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!

CO-58 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!

CO-60 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

NB-95 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!

ZR-95 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O0 CS-134 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/01 RU-103 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0I AG-110m 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

SB-125 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

1-131 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CS-137 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0:00 #DIV/O!

H-3 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

NI-63 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 .0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

FE-55 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

SR-90 . 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

TE-125m 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CS-136 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!

XE-133 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

C-14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

PU-241 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/01 TRU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

FE-59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00. #DIV/0!

SB-124 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

RU-106 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CE-144 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CM-242 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00. 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

TOTAL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/01 CLASS C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS B 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AU 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CURIES 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CU. FT. 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CU. M- 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 RSR#

Page 12 of 12

Attachment 3 Oconee Nuclear Site Unplanned Offsite Releases Oconee did not have any unplanned releases in 2009.

Attachment 4 Oconee Nuclear Site Fuel Cycle Calculation

Oconee Nuclear Station 2009 Radioactive Effluent Releases 40CFR190 Uranium Fuel Cycle Dose Calculation Results In accordance with the requirements of 40CFR190, the annual dose commitment to any member of the general public shall be calculated to assure that doses are limited to 25 millirems to the total body or any organ with the exception of the thyroid which is limited to 75 millirems. The fuel cycle dose assessment for Oconee Nuclear Station only includes liquid and gaseous effluent dose contributions from Oconee and direct and air-scatter dose from Oconee's onsite Independent Spent Fuel Storage Installation (ISFSI) since no other uranium fuel cycle facility contributes significantly to Oconee's maximum exposed individual. The combined dose to a maximum exposed individual from Oconee's effluent releases and direct and air-scatter dose from Oconee's ISFSI is well below 40CFR190 'limits as shown by the following summary:

I. 2009 Oconee 40CFR190 Effluent Dose Summary The 40CFR190 effluent dose analysis to the maximum exposed individual from liquid and gas releases includes the dose from noble gases (i.e., total body and skin).

Maximum Total Body Dose = 7.54E-02 mrem Maximum Location: 1.0 Mile, South-West Sector Critical Age: Adult Gas non-NG Contribution: 18%

Gas NG Contribution: <1%

Liquid Contribution: 8.1%

Maximum Organ (other than TB) Dose = 1.60E-01 mrem Maximum Location: 1.0 Mile, South-West Sector Critical Age: Adult Critical Organ: GILLI Gas Contribution: 9%

Liquid Contribution: 91%

II. 2009 Oconee 40CFR190 ISFSI Dose Summary Direct and air-scatter radiation dose contributions from the onsite Independent Spent Fuel Storage Installation (ISFSI) at Oconee have been calculated and documented in the "Oconee Nuclear Site 10CFR72.212-Written Evaluations" report. The maximum dose rate to the nearest resident from the Oconee ISFSI assuming 100% occupancy time is estimated to be much less than 1 mrem/yr.

The following excerpt, "C. 10CFR72.212(b) (2) (i) (C)- Requirements of 72.104",

from the "Oconee Nuclear Site 10CFR72.212 Written Evaluations" report is provided to document the method used to estimate the Oconee ISFSI dose to the nearest "real individual".

The effluent dose calculations consider radionuclides identified as part of the liquid and gaseous wastes sample and analysis program per SLC Table 16.11.4-1.

The following three pages are taken from the Oconee Nuclear Site, "Independent Spent Fuel Storage Installation",

10CFR72.212 Evaluation report.

C. 10CFR72.212(b)(2)(i)(C)- Requirements of 72.104

"...the requirements of§ 72.104 have been met.

10 CFR 72.104, as clarified by ISG-13 3, stipulates that the licensee perform dose evaluations which establish that any real individual beyond the controlled area boundary not sustain a dose equivalent in excess of 0.25 mSv (25 mrem) due to direct radiation from the Independent Spent Fuel Storage Installation and other Oconee Nuclear Site 10CFR72.212 Written Evaluations, Rev. 3 Page 22 of 32

fuel cycle operations in the area. This same dose limit is stipulated by the EPA for the fuel cycle in 40 CFR 190.10(a).

In accordance with these requirements, Duke Energy Corporation has performed dose calculations that model the characteristics (initial enrichment, burnup and cooling time) of existing fuel in Phases I - IV of the Oconee ISFSI, together with the characteristics of assumed "design basis" fuel in Phase V of the Oconee ISFSI.39 Calculation OSC-8675 develops the radiation source terms used in subsequent shielding and skyshine calculations using the SCALE Code System.

More specifically, the SAS2 Module of the SCALE Code System 41 was used to create a problem-dependent pin-cell model for the purpose of building cell-weighted, multigroup cross section sets for use in subsequent depletion calculations. The ORIGEN-S Module2of the SCALE Code System was used to perform the fuel depletion and characterization calculations using the cross section sets created by SAS2. These characterization calculations yielded the photon and neutron source terms to be used as input to subsequent shielding calculations. As mentioned above, problem-dependent cross section sets were developed for these analyses since ORIGEN-S was used within the SAS2 sequence. Duke Energy Corporation Radiological Engineering is experienced in the use of the SCALE Code System, and the SCALE Code System is installed and maintained under the purview of the pertinent software and data quality assurance program.

The results of the radiation source term calculation were used as input to Calculation OSC-8706 43 to evaluate the shielding characteristics of a single Horizontal Storage Module. The MCNP Monte Carlo particle transport computer code44 was used to perform the transport calculations and to write a surface flux file for use in subsequent skyshine calculations.

Appropriate software quality controls have been implemented for the computer codes and data used in these analyses (specifically, Calculation DPC-1201.30 0010 45 cOntains the verification and validation for MCNP5, while SDQA-70321-COM documents the quality control measures in place for MCNP5).

Calculation OSC-871646 uses the surface flux files developed in OSC-8706 in a repeating -array representing all of the Horizontal Storage Modules in the ISFSI, including Phase V fully loaded with spent fuel. The source description in the MCNP input is constructed with source probabilities for each Horizontal Storage Module to represent the appropriate decay time associated with each HSM.

Finally, a skyshine calculation is performed to obtain near- and far-field dose results from Phases I - V of the Oconee ISFSI. The results demonstrate that (conservatively assuming 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months of occupancy per year) the annual dose at the nearest controlled area boundary (approximately 300 meters) is below the Oconee Nuclear Site 10CFR72.212 Written Evaluations, Rev. 3 Page 23 of 32

10 CFR 72.104(a) and 40 CFR 190.10(a) limit of 25 mrem from direct and skyshine radiation. Since it is demonstrated that with a conservative occupancy assumption the doses at the controlled area boundary are within limits, it can easily be concluded that the dose to a "real individual" is within the same limits.

The closest residence to the' ISFSI is in the SW-SSW direction approximately 1 mile (-1600 meters) from the ISFSI, or 1.36 miles from the centerline of the site.47 D. 10CFR72.212(b)(2)(ii)- 10CFR72.48 Applicable to Written Evaluations Required by 10CFR72.212 "The licensee shall evaluate any changes to the written evaluations requiredby this paragraphusing the requirements of §72.48(c). A copy of this record shall be retaineduntil spentfuel is no longer stored under the general license issued under §72.210."

The changes to these written evaluations are evaluated under NSD-21 1, 10CFR72.48 Process13 . Documentation is included as Attachment 4.

IX. 10CFR72.212(b)(3)- Evaluation of Reactor Site Parameters "Review the Safety Analysis Report (SAR) referenced in the Certificate of Compliance and the related NRC Safety Evaluation Report, prior to use of the general license, to determine whether or not the reactor site parameters, including analyses of earthquake intensity and tornado missiles, are enveloped by the cask design bases consideredin these reports. The results of this review must be documented in the evaluation made in paragraph(b)(2) of this section."

A. Tornado Transnuclear completed a design analysis, NUH-004.0219 "NUHOMS HSM Tornado Missile Impact Analysis" 11, to ensure the tornado missile impact analysis is bounded for the Oconee site. The Oconee site is analyzed for 2 specific tornado missiles (1) a 2000 Ibm automobile traveling at 100 mph with 20 square foot contact area and (2) a 12 foot long 8" diameter wooden pole traveling at 250 mph (Oconee UFSAR 3.5.1.3 2). The first case is bounded by the Standardized NUHOMS FSAR 4 massive missile impact analysis of a 3967 Ibm automobile traveling at 126 mph with a frontal area of 20 square feet against the HSM. For the second case, the Transnuclear analysis is for a 13.5" diameter 35' long 1500 Ibm projectile with. a velocity of 294 ft/s. This projectile bounds the Oconee wooden pole missile and is documented in the referenced calculation."

Oconee Nuclear Site 10CFR72.212 Written Evaluations, Rev. 3 Page 24 of 32

Attachment 5 Oconee Nuclear Site Inoperable Monitoring Equipment There were no effluent-monitoring instruments out of service for greater than 30 days.

Attachment 6 Groundwater Protection Initiative

ARERR Groundwater Well Data Section Rev. 2 Duke Energy implemented a Ground Water Protection program in 2007. This initiative was developed to ensure timely and effective management of situations involving inadvertent releases of licensed material to ground water. As part of this program, Oconee had forty-nine -ground water monitoring wells in place during 2009. An investigation into the tritium activity in wells GM-7and GM-7R is on-going and additional wells are being added in 2010. Wells are generally sampled quarterly, with somestate required wells being sampled semi-annually or annually. All samples are being analyzed for tritium and gamma emitters with selected wells being analyzed for Strontium 89 and 90. No gamma activity (other than naturally occurring radionuclides) or Strontium was identified in any of the well samples during 2009.

Results from sampling during 2009 are shown in the table below.

Avg. Tritium Conc. # of Well Name Well Location Conc.(pCi/1) Range Samples BG-4 Ball Field < < 3 MW-3 Landfill < < 2 MW- 1 Landfill < < 2 MW-lID Landfill < < 2 MW-I 3 Landfill < < 2 MW-16 Landfill < < 2 MW-RPO1 Landfarm/Burial < < 4 MW-RP02 Landfarm/Burial < < 4 MW-RP03 Landfarm/Burial < < 4 MW A-1 CTP-1/2 722 307- 1067 3 MW A-2 CTP-1/2 < < 4 MW A-8 CTP-1/2 no samples -_0 MW A-9 CTP-1/2 no samples - 0 MW A-10 CTP-3 501 418-655 4 MW A-11 CTP-3 < < 4 MW A-12 CTP-3 < < 4 MWA-13 CTP-1/2 699 509- 1020 4 MW A-14 CTP-1/2 989 720-1220 4 MWA-17 CTP-1/2 191 160-222 4 MWA-18 CTP-1/2 231 231 4 GM-1R CTP-1/2 329 284-378 4 GM-2R U-1/2 SFP 3,248 2340 - 4160 4 GM-2DR U-1/2 SFP 1,898 1480 - 2220 4 GM-3R U-3 SFP 266 265-.267 4 GM-3DR U-3 SFP 248 199 - 281 4 GM-4 WH-10 336 291 -431 4 GM-5 Rdwst. Bldg. 231 227 - 236 4 GM-5R Rdwst. Bldg. < < 4 GM-6 Outflow to CTP-3 183 179 - 186 4

ARERR Groundwater Well Data Section Rev. 2 GM-6R Outflow to CTP-3 < < 4 GM-7 525 kv Sw. Yard 4,443 1900 - 8400 4 GM-7R 525 kv Sw. Yard 13,283 9530 - 18500 4 GM-8 E of U-3 TB 222 201 -242 4 GM-8R E of U-3 TB 271 181-405. 4 GM-9 E of U-2 TB 302 265 - 338 4 GM-9R E of U-2 TB < < 4 GM-10 525 kv Sw. Yard < < 4 GM-10R 525 kv Sw. Yard < < 4 GM-11 525 kv Sw. Yard < < 4 GM-11R 525 kv Sw. Yard < < 4 GM-12 E of Access Rd. < < 4 GM-12R E of Access Rd. < < 4 GM-13 525 kv Sw. Yard < < 4 GM-13R 525 kv Sw. Yard < < 4 GM-14 Mnt. Trg. Facility < < 4 GM-14R Mnt. Trg. Facility < < 4

011 (IW-1) Ball Field < < 4

013 (IW-2) WH-5 < < 4

015 Brown's Bottom < < 4

These are irrigation wells and may not meet current requirements for ground water well construction.

pCi/1 - pico curies per liter

< - less than minimum detectable activity, typically 250 pCi/liter 20,000 pCi/l - the Environmental Protection Agency drinking water standard for tritium.

This standard applies only to water that is used for drinking.

1,000,000 pCi/l - the 10CFR20, Appendix B, Table 2, Column 2, Effluent Concentration limit for tritium.

Attachment 7 SLC 16.11 Radiological Effluent Controls

Radioactive Liquid Effluents 16.11.1 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.1 Radioactive Liquid Effluents COMMITMENT Establish conditions for the controlled release of radioactive liquid effluents. Implement the requirements of 10 CFR 20, 10 CFR 50.36a, Appendix A to 10 CFR 50, Appendix I to 10 CFR 50, 40 CFR 141 and 40 CFR 190.

a. Concentration The concentration of radioactive material released at anytime from the site boundary for liquid effluents to Unrestricted Areas [denoted in Figure 2.1-4(a) of the Oconee Nuclear Station Updated Final Safety Analysis Report] shall be limited to 10 times the effluent concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases the concentration shall be limited to 2 x 10-4 itCi/ml total activity.

b. Dose The dose or dose commitment to a Member Of The Public from radioactive materials in liquid effluents to Unrestricted Areas shall be limited to:

1. during any calendar quarter:

4.5 mrem to the total body

_ 15 mrem to any organ; and

2. during any calendar year:

< 9 mrem to the total body

< 30 mrem to any organ.

c. Liquid Waste Treatment The appropriate subsystems of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid waste prior to their discharge, if the projected dose due to liquid effluent releases to unrestricted areas, when averaged over 31 days would exceed 0.18 mrem to the total body or 0.6 mrem to any organ.

16.11.1-1 08/14/08 I

Radioactive Liquid Effluents 16.11.1 NO T E OTE--------------------------

Appendix I dose limits for radioactive liquid effluent releases are applicable only during normal operating conditions which include expected operational occurrences, and are not applicable during unusual operating conditions that result in activation of the Oconee Emergency Plan.

APPLICABILITY: At all times ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of A.1 Restore concentration to Immediately radioactive material within the limit.

released in liquid effluents to Unrestricted Areas exceeds the limits specified in Commitment a.

16.11.1 -2 08/14/08 1

Radioactive Liquid Effluents 16.11.1 CONDITION [ REQUIRED ACTION [COMPLETION TIME B. Calculated dose from B.1 --------- NOTE --------------

the release of Not required during radioactive materials in unusual operating liquid effluents exceeds conditions that result in any of the limits in activation of the Oconee Commitment b. Emergency Plan.

Submit report to the 30 days from the end of regional NRC Office which the quarter during which includes the following: the release occurred

a. Cause(s) for exceeding the limit(s).

b. A description of the program of corrective action initiated to:

reduce the releases of radioactive materials in liquid effluents, and to keep these levels of radioactive materials in liquid effluents in compliance with the above limits, or as low as reasonably achievable.

c. Results of radiological analyses of the drinking water source and the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141.

16.11.1 -3 08/14/08 1

Radioactive Liquid Effluents 16.11.1 CONDITION REQUIRED ACTION COMPLETION TIME C. Radioactive liquid C.1 Submit report to the 30 days waste is discharged regional NRC Office which without treatment and includes the following:

in excess of the specified limit, a. Cause of equipment or subsystem inoperability.

b. Corrective action to restore equipment and prevent recurrence.

I SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.1.1 N/A N/A 16.11.1 -4 08/14/08 I

Radioactive Liquid Effluents 16.11.1 BASES The concentration commitment is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than 10 times the effluent concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. The concentration limit for noble gases is based upon the assumption that Xe-1 35 is the controlling radioisotope and its EC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

The basic requirements for Selected Licensee Commitments concerning effluent from nuclear power reactors are stated in 10 CFR 50.36a. Compliance with effluent Selected Licensee Commitments will ensure that average annual releases of radioactive material in effluents will be small percentages of the limits specified in the old 10 CFR 20.106 (new 10 CFR 20.1302).

The requirements contained in 10 CFR 50.36a further indicate that operational flexibility is allowed, compatible with considerations of health and safety, which may temporarily result in releases higher than such small percentages, but still within the limits specified in the old 10 CFR 20.106 which references Appendix B, Table II concentrations (MPCs). These referenced concentrations are specific values which relate to an annual dose of 500 mrem. It is further indicated in 10 CFR 50.36a that when using operational flexibility, best efforts shall be exerted to keep levels of radioactive materials in effluents as low as reasonably achievable (ALARA) as set forth in 10 CFR 50 Appendix I. Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. Therefore, to accommodate operational flexibility needed for effluent releases, the limits associated with this SLC are based on ten times the instantaneous dose rate value of 50 mrem/year to apply at all times. Compliance with the limits of the new 10 CFR 20.1001 will be demonstrated by operating within the limits of 10 CFR 50, Appendix I, 40 CFR 141 and 40 CFR 190.

Section I of Appendix I of 10 CFR 50 states that this appendix provides specific numerical guides for design objectives and limiting conditions for operation, to assist holders of licenses for light water cooled nuclear power reactors in meeting the requirements to keep releases of radioactive material to unrestricted areas as low as practical and reasonably achievable, during normal reactor operations, including expected operational occurrences. Using the flexibility granted during unusual operating conditions, and the stated applicability of the design objectives for the Oconee Nuclear Station, Appendix I dose limits for radioactive liquid effluent releases are concluded to be not applicable during unusual operating conditions that r6sult in the activation of the Oc nee Emergency Plan.

For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.

The requirements that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This SLC implements the requirements of 10 CFR Part 50.36a.-

General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section Il.D of Appendix A to 10 CFR Part 50.

16.11.1-5 08/14/08 1

Radioactive Liquid Effluents 16.

11.1 REFERENCES

1. 10 CFR Part 20, Appendix B.

2. 40 CFR Part 141.

3. 10 CFR Part 50, Appendices A and I.

4. 40 CFR Part 190.

5. Offsite Dose Calculation Manual.

6. Regulatory Guide 1.109.

7. NUREG-1301 16.11.1-6 08/14/08 1

Radioactive Gaseous Effluents 16.11.2 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.2 Radioactive Gaseous Effluents COMMITMENT Establish conditions for the controlled release of radioactive gaseous effluents. Implement the requirements of 10 CFR 20, 10 CFR 50.36a, Appendix A to 10 CFR 50, Appendix I to 10 CFR 50, and 40 CFR 190.

a. Dose Rate The instantaneous dose rate at the site (exclusion area) boundary for gaseous effluents [Figure 2.1-4(a) of the Oconee Nuclear Station Updated Final Safety Analysis Report] due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:

1. The dose rate limit for noble gases shall be:

<500 mrem/yr to the total body

_< 3000 mrem/yr to the skin; and

2. The dose rate limit for all radioiodines and for all radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than 8 days shall be < 1500 mrem/yr to any organ.

b. Dose

1. The air dose due to noble gases released in gaseous effluent from the site shall be limited to the following:

i. During any calendar quarter:

_ 15 mrad for gamma radiation

30 mrad for beta radiation ii. During any calendar year:

< 30 mrad for gamma radiation

60 mrad for beta radiation

2. The dose to a Member Of The Public from radioiodines, tritium and radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released from the site, shall be limited to the following:

16.11.2.-1 01/31/00 I

Radioactive Gaseous Effluents 16.11.2

i. During any calendar quarter:

< 22.5 mrem to any organ ii. During any calendar year:

45 mrem to any organ.

c. Gaseous Radwaste Treatment

1. The Gaseous Radwaste Treatment System shall be used to reduce the noble gases in gaseous wastes prior to their discharge, if the projected gaseous effluent air dose due to gaseous effluent release from the site, when averaged over 31 days exceeds 0.6 mrad for gamma radiation and 1.2 mrad for beta radiation.

2. The Ventilation Treatment Exhaust System shall be used to reduce radioactive materials other than noble gases in gaseous waste prior to their discharge when the projected doses due to effluent releases to unrestricted areas when averaged over 31 days would exceed 0.9 mrem to any organ.

d. Used Oil Incineration During incineration of used oil contaminated by radioactive material in the Station Auxiliary Boiler, the dose to a Member Of The Public from radioiodines, tritium and radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released from the Station Auxiliary Boiler shall be

0.045 mrem to any organ in any calendar year.

NOTE--

The requirement of c.2 does not apply to the Auxiliary Building Exhaust System since it is not "treated" prior to release.

APPLICABILITY: At all times 16.11.2-2 03/27/99

Radioactive Gaseous Effluents

.16.11.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Dose rate exceeds the A.1 Restore release rate to Immediately limits specified in within limits.

Commitment a. I B. Calculated dose* B.1 Submit report to the 30 days from the end of exceeds specified limits, regional NRC Office which the quarter during which includes the following: the release occurred

a. Cause(s) for exceeding the limit(s),

and

b. A description of the program of corrective action initiated to:

reduce the releases of radioactive materials in gaseous effluents, and to keep these levels of radioactive materials in gaseous effluents in compliance with the specified limits or as low as reasonably achievable.

16.11.2-3 01/31/00 1

Radioactive Gaseous Effluents 16.11.2 CONDITION REQUIRED ACTION COMPLETION TIME C. Radioactive gaseous C.1 Submit a report to the 30 days waste is discharged regional NRC Office which greater than limits includes the following:

specified in Commitment c.1 or a. Cause of equipment c.2. or subsystems inoperability, and AND

b. Corrective action to Radioactive gaseous restore equipment waste is discharged and prevent without treatment for recurrence.

more than 31 days.

SURVEILLANCE REQUIREMENTS SURVEI LLANCE FREQUENCY SR 16.11.2.1 N/A N/A 16.11.2-4 03/27/99

Radioactive Gaseous Effluents 16.11.2 BASES The basic requirements for Selected Licensee Commitments concerning effluent from nuclear power reactors are stated in IOCFR50.36. Compliance with effluent Selected Licensee Commitments will ensure that average annual releases of radioactive material in effluents will be small percentages of the limits specified in the old IOCFR20.106 (new 10CFR20.1302). The requirements contained in IOCFR50.36a further indicate that operational flexibility is allowed, compatible with considerations of health and safety, which may temporarily result in releases higher than such small percentages, but still within the limits specified in the old 10CFR20.106 which references Appendix B, Table II concentrations (MPCs). These referenced concentrations are specific Values which relate to an annual dose of 500 mrem to the total body, 3000 mrem to the skin, and 1500 mrem to an infant via the milk animal-milk-infant pathway. It is further indicated in I0CFR50.36a that when using operational flexibility, best efforts shall be exerted to keep levels of radioactive materials in effluents as low as reasonably achievable (ALARA) as set forth in IOCFR50 Appendix I. Therefore, to accommodate operational flexibility needed for effluent releases, the limits associated with gaseous release rate SLCs will be maintained at the current instantaneous dose rate limit for noble gases of 500 mrem/year to the total body and 3000 mrem/year to/the skin; and for Iodine-1 31, for Iodine-1 33, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days. an instantaneous dose rate limit of 1500 mrem/year.

The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"Revision 1,. October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors."

Equations in the ODCM are provided for determining the actual doses based upon the historical average atmospheric conditions. The release rate commitments for radioiodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides into green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

The requirement that the appropriate portions of these systems be used when specified provides reasonable assurance that the release of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This commitment implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section liD of Appendix I to 10 CFR Part 50.

16.11.2-5 01/31/00 I

Radioactive Gaseous Effluents 16.

11.2 REFERENCES

1 10 CFR Part 20, Appendix 8.

2. 10 CFR Part 50, Appendices A and I.

3. Regulatory Guide 1.109.

4. 40 CFR Part 190.

5. Offsite Dose Calculation Manual.

16.11.2-6 01/31/00 1

Radioactive Effluent Monitoring Instrumentation 16.11.3 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.3 Radioactive Effluent Monitoring Instrumentation COMMITMENT Radioactive Effluent Monitoring Instrumentation shall be OPERABLE as follows:

a. Liquid Effluents The radioactive liquid effluent monitoring instrumentation channels shown in Table 16.11.3-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of SLC 16.1 1.1 .a are not exceeded.

b. Gaseous Process and Effluents The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 16.11.3-2 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of SLC 16.11.2.a are not exceeded.

c. The setpoints shall be determined in accordance with the methodology described in the ODCM and shall be recorded.

NOTE--- ---- ---------------

Correction to setpoints determined in accordance with Commitment c may be permitted without declaring the channel inoperable.

APPLICABILITY: According to Table 16.11.3-1 and Table 16.11.3-2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Alarm/trip setpoint less A.1 Declare channel Immediately conservative than inoperable.

required for one or more effluent OR monitoring instrument channels. A.2 Suspend release of Immediately effluent monitored by the channel.

16.11.3-1 11/20/08 1

Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME B. One or more required B.1 Enter the Condition Immediately liquid effluent monitoring referenced in Table instrument channels 16.11.3-1 for the inoperable, function.

AND B.2 Restore the 30 days instrument(s) to OPERABLE status.

C. One or more required C.1 Enter the Condition Immediately gaseous effluent referenced in Table monitoring instrument 16.11.3-2 for the channels inoperable, function.

AND C.2 Restore the 30 days instrument(s) to OPERABLE status.

D. Required Action and D.1 Explain in next Annual April 30 of following associated Completion Radiological Effluent calendar year Time of Required Action Release Report why B.2 or C.2 not met. inoperability was not corrected in a timely manner.

16.11.3-2 11/20/08 1

Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1.1 Analyze two Prior to initiating Action B.1 and independent samples subsequent release referenced in Table in accordance with 16.11.3-1. (RIA-33) SLC 16.11.4.

AND E.1.2 Conduct two Prior to initiating independent data entry subsequent release checks for release rate calculations AND E.1 .3 Conduct two Prior to initiating independent valve subsequent release lineups of the effluent pathway.

OR E.2 Suspend release of Immediately radioactive effluents by this pathway.

F. As required by Required F.1 Suspend release of Immediately Action B.1 and radioactive effluents by referenced in Table this pathway.

16.11.3-1. (RIA-54)

OR F.2 Collect and analyze Prior to each discrete grab samples for gross release of the sump radioactivity (beta and/or gamma) at a lower limitof detection of at least 10-7 Ci/ml.

16.11.3-3 11/20/08 1

Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME G. As required by Required - ----------------- NOTE---------

Action B.1 and Not required during short, referenced in Table controlled outages of liquid 16.11.3-1. (Liquid effluent monitoring Radwaste Effluent Line instrumentation. Short controlled Flow Rate Monitor) outages are defined as planned removals from service for durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

G.1 Suspend release of Immediately radioactive effluents by this pathway.

OR G.2 Estimate flow rate Immediately during actual releases.

AND Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter 16.11.3-4 11/20/08 1

Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME H. As required by Required --- --------------- NOTE ------------------

Action B.1 and Not required during short, referenced in Table controlled outages of liquid 16.11.3-1. (RIA-35, #3 effluent monitoring Chemical Treatment instrumentation. Short controlled Pond Composite outages are defined as planned Sampler and Sampler removals from service for Flow Monitor (Turbine durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , Building Sumps for purposes of sample filter Effluent)) changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

H.1 Suspend release of Immediately.

radioactive effluents by this pathway.

OR H.2 Collect and analyze Immediately grab samples for gross radioactivity (beta AND and/or gamma) at a lower limit of detection Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of at least 10i7 gCi/ml. thereafter 16.1 1.3-5 11/20/08 I

Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME As required by Required -------------- NOTE---------

Action C.1 and Not required during short, referenced in Table controlled outages of gaseous 16.11.3-2 for effluent effluent monitoring releases from waste gas instrumentation. Short controlled tanks (RIA-37, RIA-38) outages are defined as planned or containment purges removals from service for (RIA-45). durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

1.1.1 Analyze two Prior to initiating independent samples. subsequent release AND 1.1.2 Conduct two Prior to initiating independent data entry subsequent release checks for release rate calculations AND 1.1.3 Conduct two Prior to initiating independent valve subsequent release lineups of the effluent pathway.

OR 1.2 Suspend release of Immediately radioactive effluents by this pathway.

1 6.11.3-6 11/20/08 I

Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME J. As required by Required ----------------------

NOTE .. -..----------

Action C.1 and Not required during short, referenced in Table controlled outages of gaseous 16.11.3-2. (Effluent effluent monitoring Flow Rate Monitor (Unit instrumentation. Short controlled Vent, Containment outages are defined as planned NI Purge, Interim removals from service for Radwaste Exhaust, Hot durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , Machine Shop Exhaust, for purposes of sample filter Radwaste Facility changeouts, setpoint Exhaust, Waste Gas adjustments, service checks, Discharge)) and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

J.1 Suspend release of Immediately radioactive effluents by this pathway.

OR J.2 Estimate flow rate Immediately.

AND Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter 1 6.11.3-7 11/20/08 I

Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME K. As required by Required --- --------------- NOTE---------

Action C.1 and Not required during short, referenced in Table controlled outages of gaseous 16.11.3-2. (RIA-45, effluent monitoring RIA-53, 4RIA-45) instrumentation. Short controlled outages are defined as planned removals from service for durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

K.1 Suspend release of Immediately radioactive effluents by this pathway.

OR K.2.1 Collect grab sample. Immediately AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months AND K.2.2 Analyze grab samples 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from collection for gross activity (beta of sample and/or gamma).

16.11.3-8 11/20/08 1

Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME L. As required by Required --- --------------- NOTE----------

Action C.1 and Not required during short, referenced in Table controlled outages of gaseous 16.11.3-2. (Unit Vent effluent monitoring Monitoring Iodine instrumentation. Short controlled Sampler, Unit Vent outages are defined as planned Monitoring Particulate removals from service for Sampler, Interim durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , Radwaste Building for purposes of sample filter Ventilation Monitoring changeouts, setpoint Iodine Sampler, Interim adjustments, service checks, Radwaste Building and/or routine maintenance Ventilation Monitoring procedures. This guidance may Particulate Sampler, Hot be applied successively, Machine Shop Iodine provided that time between Sampler, Hot Machine successive short, controlled Shop Particulate outages is always at least equal Sampler, Radwaste to duration of immediately Facility Iodine Sampler, preceding outage.

Radwaste Facility Particulate Sampler)

LAl Suspend release of Immediately radioactive effluents by this pathway.

OR L.2.1-------- NOTE ------

The collection time of each sample shall not exceed 7 days.

Collect samples Immediately continuously using auxiliary sampling equipment.

AND L.2.2 Analyze each sample. 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months from end of each sample collection 16.11.3-9 11/20/08 1

Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME M. As required by Required --- --------------- NOTE ------------------

Action C.1 and Not required during short, referenced in Table controlled outages of gaseous 16.11.3-2 for effluent effluent monitoring from ventilation system instrumentation. Short controlled or condenser air outages are defined as planned ejectors. (RIA-40) removals from service for durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

M.1 Continuously monitor Immediately release through the unit vent.

OR M.2 Suspend release of Immediately radioactive effluents by this pathway.

OR M.3.1 Collect grab sample. Immediately AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months AND M.3.2 Analyze grab sample for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from collection gross activity (beta of grab sample and/or gamma).

16.11.3-10 11/20/08 1

Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 4-SR 16.11.3.1 -------------------- NOTE ---------------

The Channel Response check shall consist of verifying indications during periods of release.

Channel response checks shall be made at least once per calendar day on days in which continuous, periodic or batch releases are made.

1 Perform Channel Response Check. During each release via this pathway SR 16.11.3.2 -------------------- NOTE ---------------

The Channel Response check shall consist of verifying indications during periods of release.

Channel response checks shall be made at least once per calendar day on days in which continuous, periodic or batch releases are made.

Perform Channel Response Check. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 16.11.3.3 Perform Source Check. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 16.11.3.4 Perform Source Check. 31 days SR 16.11.3.5 Perform Source Check. 92 days 16.11.3-11 11/20/08 I

Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE FREQUENCY SR 16.11.3.6 ---------------

NOTE -------------

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure (downscale only).

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 16.11.3.7 ---------------

NOTE ------------

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure (downscale only).

92 days Perform CHANNEL FUNCTIONAL TEST.

SR 16.11.3.8 Perform CHANNEL FUNCTIONAL TEST. 92 days 16.11.3-12 11/20/08 1

Radioactive Effluent Monitoring Instrumentation 16.11.3

( I SURVEILLANCE FREQUENCY SR 16.11.3.9 ------------------------- NOTE --------------

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with the National Institute of Standards and Technology (NIST). The standards shall permit calibrating the system over its intended range of energy and measurement. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. (Operating plants may substitute previously established calibration procedures for these requirements.)

12 months Perform CHANNEL CALIBRATION.

SR16.11.3.10 Perform CHANNEL CALIBRATION. 12 months SR 16.11.3.11 Perform leak test. When cylinder gates or wicket gates are reworked SR 16.11.3.12 Perform Source Check. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to each release via associated pathway 16.11.3-13 11/20/08 1

Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-1 LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS CONDITION REFERENCED MINIMUM FROM OPERABLE SURVEILLANCE REQUIRED INSTRUMENT CHANNELS APPLICABILITY REQUIREMENTS ACTION B.1

1. Monitors Providing Automatic Termination of Release

a. Liquid Radwaste Effluent I At all times SR 16.11.3.1 E Line Monitor, RIA-33 SR 16.11.3.3 SR 16.11.3.6 SR 16.11.3.9

b. Turbine Building Sump, 1 At all times SR 16.11.3.2 F RIA-54 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9

2. Monitors not Providing Automatic Termination of Release Low Pressure Service Water At all times SR 16.11.3.2 H RIA-35 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9

3. Flow Rate Measuring Devices

a. Liquid Radwaste Effluent 1 At all times SR 16.11.3.1 G Line Flow Rate Monitor SR 16.11.3.10 (0LW CR0725 or OLW SS0920)

b. Liquid Radwaste Effluent NA NA SR 16.11.3.1 NA Line Minimum Flow SR 16.11.3.10 Device

c. Turbine Building Sump NA NA SR 16.11.3.1 NA Minimum Flow Device SR 16.11.3.10

d. Low Pressure Service NA NA SR 16.11.3.1 NA Water Minimum Flow SR 16.11.3.10 Device 16.11.3-14 11/20/08 1

Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-1 LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS CONDITION REFERENCED MINIMUM FROM OPERABLE SURVEILLANCE REQUIRED INSTRUMENT CHANNELS APPLICABILITY REQUIREMENTS ACTION B.1

e. Keowee Hydroelectric NA NA SR 16.11.3.11 NA Tailrace Discharge (a)

4. Continuous Composite Sampler

3 Chemical Treatment 1 At all times SR 16.11.3.2 H Pond Composite Sampler SR 16.11.3.10 and Sampler Flow Monitor (Turbine Building Sumps Effluent)

(a) Flow is determined from the number of hydro units operating. If no hydro units are operating, leakage flow.will be assumed to be 38 cfs based on historical data.

16.11.3-15 11/20/08

Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-2 GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS MINIMUM CONDITION OPERABLE REFERENCED CHANNELS FROM (PER RELEASE SURVEILLANCE REQUIRED INSTRUMENT PATH) APPLICABILITY REQUIREMENTS ACTION C.1 Unit Vent Monitoring System

a. Noble Gas Activity At All Times SR 16.11.3.2 Monitor Providing Alarm SR 16.11.3.4 and Automatic SR 16.11.3.7 Termination of SR 16.11.3.9 Containment Purge Release (RIA Purge Isolation Function)

b. Noble Gas Activity 1 Atall times SR 16.11.3.2 K Monitor Providing Alarm. SR 16.11.3.4 (RIA Vent Stack SR 16.11.3.7 Monitor Function) SR 16.11.3.9

c. Iodine Sampler At All Times SR 16.11.3.2 L

d. Particulate Sampler At All Times SR 16.11.3.2 L

e. Effluent Flow Rate At All Times SR 16.11.3.2 J Monitor (Unit Vent Flow) SR 16.11.3.10 (MSC CR0001)

f. Sampler Flow Rate At All Times SR 16.11.3.2 NA Monitor (a) (Annunciator) SR 16.11.3.10

g. Effluent Flow Rate During Containment SR 16.11.3.2 M Monitor (Containment Purge Operation SR 16.11.3.10 Purge)(MSC CR0001)

h. CSAE Off Gas Monitor 1 During Operation SR 16.11.3.2 M (RIA-40) of CSAE SR 16.11.3.5 SR 16.11.3.8 SR 16.11.3.9

2. Interim Radwaste Building Ventilation Monitoring System

a. Noble Gas Activity At All Times SR 16.11.3.2 K Monitor (RIA - 53) SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9 1

b. Iodine Sampler At All Times SR 16.11.3.2 L 1

c. Particulate Sampler At All Times SR 16.11.3.2 L

d. Effluent Flow Rate 1 At All Times SR 16.11.3.2 J Monitor (Interim SR 16.11.3.10 Radwaste Exhaust)

(GWD FT0082)

e. Sampler Flow Rate 1 At All Times SR 16.11.3.2 NA Monitor(a) (Annunciator) SR 16.11.3.10 16.11.3-16 11/20/08 1

Radioactive Effluent Monitoring Instrumentation 16.11.3 table 16.11.3-2 GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS MINIMUM CONDITION OPERABLE REFERENCED CHANNELS FROM (PER RELEASE SURVEILLANCE REQUIRED INSTRUMENT PATH) APPLICABILITY REQUIREMENTS ACTION C.1

3. Hot Machine Shop Ventilation Sampling System

a. Iodine Sampler 1 At All Times SR 16.11.3.2 L

b. Particulate Sampler 1 At All Times SR 16.11.3.2 L

c. Effluent Flow Rate At All Times SR 16.11.3.2 J Monitor (Hot Machine SR 16.11.3.10 Shop Exhaust)

(Totalizer)

d. Sampler Flow Rate 1 At All Times SR 16.11.3.2 NA Monitor (a) (Annunciator) SR 16.11.3.10

4. Radwaste Facility Ventilation Monitoring System

a. Noble Gas Activity At All Times SR 16.11.3.2 K Monitor (4-RIA-45) SR 16.11.3.4 1 SR 16.11.3.7.

SR 16.11.3.9

b. Iodine Sampler At All Times SR 16.11.3.2 L

c. Particulate Sampler At All Times SR 16.11.3.2 L 1

d. Effluent Flow Rate At All Times SR 16.11.3.2 J Monitor (Radwaste SR 16.11.3.10 Facility Exhaust) (OVS CR2060)

e. Sampler Flow Rate At All Times SR 16.11.3.2 NA 1

Monitor (a)(Annunciator) SR 1,6.11.3.10

5. Waste Gas Holdup Tanks

a. Noble Gas Activity During Waste Gas SR 16.11.3.1 Monitor - Providing Holdup Tank Releases SR 16.11.3.6 Alarm and Automatic SR 16.11.3.9 IJ Termination of Release SR 16.11.3.12 (RIA-37,-38)b 1

b. Effluent Flow Rate During Waste Gas SR 16.11.3.1 Monitor (Waste Gas Holdup Tank Releases SR 16.11.3.10 Discharge Flow) (MSC CR0001)

(a)Alarms indicating low flow may be substituted for flow measuring devices.

(b)Either Normal or High Range monitor is required dependent upon activity in tank being released.

16.11.3-17 11/20/08 1

Radioactive Effluent Monitoring Instrumentation 16.11.3 BASES The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to assure that the alarm/trip will occur prior to exceeding 10 times the limits of 10 CFR Part 20. The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to assure that the alarm/trip will occur prior to exceeding applicable dose limits in SLC 16.11.2. The operability end use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

For certain applicable cases, grab samples or flow estimates are required at frequencies between every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months end every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months upon RIA removal from service. SLC 16.11.3 does not explicitly require Action (grab samples or flow estimates) to be initiated immediately upon RIA removal from service, when removal is for the purposes of sample filter changeouts, setpoint adjustments, service checks, or routine maintenance. Therefore, during the defined short, controlled outages, Action is not required.

For the cases in which Action is defined as continuous ,sampling by auxiliary equipment (Action L) initiation of continuous sampling by auxiliary sampling equipment requires approximately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . One hour is the accepted reasonable time to initiate collect and change samples.

Therefore. for the defined short, controlled outages (not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ), Action is not required.

Failures such as blown instrument fuses, defective indicators, and faulted amplifiers are, in many cases, revealed by alarm or annunciator action. Comparison of output and/or state of independent channels measuring the same variable supplements this type of built-in surveillance. Based on experience in operation of both conventional and nuclear systems, when the unit is in operation, the minimum checking frequency stated is deemed. adequate.

REFERENCES:

1. 10CFR Part 20.

2. 10 CFR Part 50, Appendix A.

3. Offsite Dose Calculation Manual.

4. UFSAR, Section 7.2.3.4.

16.11.3-18 11/20/08 1

Operational Safety Review 16.11.4 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.4 Operational Safety Review COMMITMENT Required sampling should be performed as detailed in Table 16.11.4-1.

APPLICABILITY: At all times ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. NA? A.1 NA NA SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

-SR 16.11.4.1 N/A N/A 1& 11.4-1 09/30/091

Operational Safety Review 16.11.4 Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program Item. Check Frequency Lower Limit of Detection (b) of Lab Analysis for Waste Decant Monitor a. Principal Gamma Composite Grab Sample <5E-06 l.iCi/ml (Ce-144)

Tank, Turbine Emitters(c) including prior to release of each <5E-07 1iCi/ml (Other Gamma Nuclides)

Building Sump Dissolved Noble batch(h) <1 E-05 iCi/ml (Dissolved Gases)

Monitor Tanks, Gases <1E-06 pCi/ml (1-131)

Waste and Recycle Monitor Tanks

b. Radiochemical Quarterly from all <5E-08 pCi/ml Analysis Sr-89 and composited batches(f)

Sr-90

c. Tritium Monthly Composite <1E-05 jiCi/ml

d. Gross Alpha Activity Monthly Composite <1E-07 pCi/mI

2. Unit Vent Sampling a. Iodine Spectrum (a) Continuous monitor, <1E-10 p.Ci/cc (1-133)0)

(Includes Waste weekly sample(e) <1E-,12 pCi/cc (1-131)0)

Gas Decay Tanks, Reactor Building Purges, Auxiliary b. Particulates (a)

Building Ventilation, Spent Fuel Pool i. Ce-144 & Mo-99 Weekly Composite(e) <5E-10 p.Ci/ccQ)

Ventilation, Air Ejectors) ii. Other Principle Weekly Composite(e) <1E-11 i.Ci/cc(j)

Gamma Emitters (d) iii. Gross Alpha Monthly, using composite <1E-11 pCi/cc Activity samples of one week iv. Radiochemical Quarterly Composite <1E-11 pCi/cc Analysis Sr-89, Sr-90

c. Gases by Principle Weekly Grab Sample <1E-04 p.Ci/cc Gamma Emitters(d)

d. Tritium Weekly Grab Sample <1 E-06 p.Ci/cc

3. Waste Gas Decay a. Principle Gamma Grab Sample prior to <1 E-04 p.Ci/cc (gases)

Tank Emitters(d) release of each batch <1E-10 pCi/cc (particulates and iodines)

<5E-09 pCi/cc (Ce-144 and Mo-99)

b. Tritium Grab Sample prior to <1E-06 pCi/cc release of each batch

4. Reactor Building a. Principle Gamma Grab sample each purge <1 E-04 pCi/cc (gases)

Emitters(d) <1E-10 pCi/cc (particulates and iodines)

<5E-09 pCi/cc (Ce-144 and Mo-99)

b. Tritium Grab sample each purge <1 E-06 p.Ci/cc 16.11.4-2 09/30/09 1

Operational Safety Review 16.11.4 Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program Item Check Frequency Lower Limit of Detection (b) of Lab Analysis for Waste

5. Not Used

6. #3 Chemical a. Principle Gamma Weekly Continuous <5E-07 pCi/ml Treatment Pond Emitters(c) Composite(g)

Effluent(')

b. 1-131 Weekly Continuous <1E-06 pCi/mI Composite(g)

c. Tritium Monthly Continuous < 1E-05 liCi/mlI Composite(g)

d. Gross Alpha Monthly Continuous <1E-07 pCi/ml Activity Composite(g)

e. Sr-89 & Sr-90 Quarterly Continuous <5E-08 pCi/ml Composite(g)

f. Dissolved and Monthly Grab <1E-05 pCi/ml Entrained gases (Gamma Emitters)

7. Radwaste Facility a. Iodine Continuous monitor, (1-133) <1E-09 pCi/cc Ventilation Spectrum(a) weekly sample(e) (1-131) <IE-11 pCi/cc

b. Particulate(a)

i. Ce-144 and Mo- Weekly Composite(e) <5E-10 pCi/cc(j) 99 ii. Other Principle Weekly .Composite(e) <1E-11 pCi/cc(j)

Gamma Emitters(d) iii. Gross Alpha Monthly, using composite <1 E-1 1.pCi/cc Activity samples of one week iv. Radiochemical Quarterly Composite <1E-11 pCi/cc Analysis Sr-89, Sr-90

c. Gases by Weekly Grab Sample 1E-04 pCi/cc Principle Gamma(d)

Emitters

d. Tritium Weekly Grab Sample <1E-06 pCi/cc 16.11.4-3 09/30/09

Operational Safety Review 16.11.4

__ Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program Item Check Frequency Lower Limit of Detection (b) of Lab Analysis for Waste

8. Hot Machine Shop a. Iodine Spectrum Weekly Sample(e) (1-133) <1E-10 pCi/cc(j)

Ventilation (1-131) <1E-12 VCi/cc(j)

b. Particulate

i. Ce-144 and Mo- Weekly Composite(e) <5E-10 pCi/cc(j) 99 ii. Other Principle Weekly Composite(M) <1E-11 pCi/cc(j)

Gamma Emitters (d) iii. Gross Alpha Monthly, using composite < 1E-1 ,iiCi/cc Activity samples of one week iv. Radiochemical Quarterly Composite <1E-11 pCi/cc Analysis Sr-89, Sr-90

c. Gases by NA NA Principle Gamma Emitters

d. Tritium NA NA

9. Interim Radwaste a. Iodine Spectrum Weekly sample(e) (1-133) <1E-10 p.Ci/cc(j)

Building (1-131) <1E-12 ViCi/cc(j)

Ventilation

b. Particulate

i. Ce-144 and Mo- Weekly Composite(e) <5E-10 1iCi/cc(j) 99

<1 E-1 1 l.Ci/ccoj) ii. Other Principle Weekly Composite(e)

Gamma Emitters(d) iii. Gross Alpha Monthly, using composite <1E-11 gCi/cc Activity samples of one week iv. Radiochemical Quarterly Composite <1 E-1 1 g.Ci/cc Analysis Sr-89, Sr-90

c. Gases by Weekly Grab Sample <1 E-04 l.'Ci/cc Principle Gamma(d)

Emitters

d. Tritium Weekly Grab Sample < 1 E-06 g.Ci/cc 16.11.4-4 09/30/09 1

Operational Safety Review 16.11.4 (a) Samples shall be changed at least once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and analysis shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (on or after removal from sampler).

(b) The LLD is defined for purposes of these commitments as the smallest conceritration of radioactive material in a sample that would be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

LLD = 4.66 sb E x V x 2.22E06 x Y x exp (-XAt)

Where:

LLID is the "a priori" lower limit of detection as defined above (as micro Curies per unit mass or volume),

sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per disintegration),

V is the sample size (in units of mass or volume),

2.22E06 is the number of disintegrations per minute per micro Curie, Y is the fractional radiochemical yield (when applicable),

X is the radioactive decay constant for the particular nuclide A*t is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples). NOTE: This assumes decay correction is applied (at the time of analysis) for the duration of sample collection, for the time between collection and analysis, and for the duration of the counting.

Additionally, it does not apply to isolated systems such as Waste Gas Decay Tanks and Waste Monitor Tanks.

Typical values of E, V, Y and A t should be used in the calculation.

It should be recognized that the LLD is an a priori (before the fact) limit representing the capability of a measurement system and not an a posteriori (after the fact) limit for a particular measurement.

(c) The principal gamma emitters for which the LLD control applies include the following radionuclides: Mn'6-54. Fe-59, Co-58, Co-60. Zn-65, Mo-99, Cs-134, Cs-137. and Ce-141. Ce-144 shall also be measured, but with a LLD of 5E-06 VCi/ml. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with the above nuclides shall also be analyzed and reported in the Annual Radioactive Effluent Release Report.

(d) The principal gamma emitters for which the LLD commitment applies exclusively are the following radionuclides: Kr-87. Kr-88, Xe-1 33. Xe-1 33m, Xe-1 35. and Xe-1 38 for gaseous emissions and Mn-54, Fe-59. Co-58, Co-60, Zn-65.-

Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulates. This list does not mean that only these nuclides are to be detected and reported. Other peaks~which are measurable and identifiable, together with the above nuclides shall also be identified and reported.

(e) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with SLC 16.11.2.a, SLC 16.11.2.b.1, and SLC 16.11.2.b.2.

(f) . A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

(g) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

16.11.4-5 09/30/09 1

Operational Safety Review 16.11.4 (h) A batch release is the discharge of liquid wastes of a discrete volume. Prior to samplinig for analysis, each batch shall be isolated, and then thoroughly mixed, to assure representative sampling.

(i) A continuous release is the discharge of liquid wastes of a non-discrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

(j) When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10.

16.11.4-6 09/30/09

Operational Safety Review 16.11.4 BASES N/A

REFERENCES:

N/A 16.11.4-7 09/30/09 1

Solid Radioactive Waste 16.11.5 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.5 Solid Radioactive Waste COMMITMENT Radioactive wastes shall be processed and packaged to ensure compliance with the applicable requirements of 10 CFR Part'20, 10 CFR Part 61, 10 CFR Part 71, and State regulations governing the transportation and disposal of radioactive wastes.

The Solid Radwaste System or an approved alternative process shall be used in accordance with a Process Control Program (PCP), for the solidification of liquid or wet radioactive wastes or the dewatering of wet radioactive wastes to be shipped for direct disposal at a 10 CFR 61 licensed disposal site. Wastes shipped for off site processing in accordance with the processor's specifications and transportation requirements are not required to be solidified or dewatered to meet disposal requirements.

The PCP describes administrative and operational controls used for the solidification of liquid or wet solid radioactive wastes in order to meet applicable 10 CFR 61 waste form requirements.

The PCP describes the administrative and operational controls used for the dewatering of wet radioactive wastes to meet 10 CFR 61 free standing water requirements.

The process parameters used in establishing the PCP shall be based on demonstrated processing of actual or simulated liquid or wet solid wastes and must adequately verify that the final product of solidification or dewatering meets all applicable Federal, State and disposal site requirements.

APPLICABILITY: At all times 16,11.5-1 10/30/02 1

Solid Radioactive Waste 16.11.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Applicable regulatory A.1 Suspend shipments of Immediately requirements for defectively packaged solidified or dewatered solid radioactive wastes wastes are not from the site.

satisfied.

AND A.2 Initiate action to correct Prior to next shipment for PCP, procedures, or disposal of solidified or solid waste equipment dewatered wastes as necessary to prevent recurrence.

B. A solidification testas B.1 Suspend solidification of Immediately described in the PCP the batch under test and fails to verify follow PCP guidance for Solidification. test failures until solidification of the batch is verified by subsequent tests.

AND B.2 The PCP shall be Prior to next solidification modified as required to for shipment of waste for assure Solidification of disposal at a 10 CFR 61 subsequent batches of disposal site waste.

16.11.5-2 10/30/02 I

Solid Radioactive Waste 16.11.5 CONDITION REQUIRED ACTION COMPLETION TIME C. With solidification or C.1 Reprocess or repackage Prior to shipment for dewatering for disposal the waste in accordance disposal of the not performed in with PCP requirements. inadequately processed accordance with the waste that requires PCP. OR solidification or dewatering C.2 Follow PCP or procedure guidance for alternative free standing liquid verification to ensure the waste in each container meets disposal requirements and take appropriate administrative action to prevent recurrence.

D. With the solid waste D.1 Restore the equipment to In a time frame that equipment incapable of OPERABLE status or supports the meeting commitment or provide for alternative commitment not in service, capability to process wastes as necessary to satisfy all applicable disposal requirements.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.5.1 The Process Control Program shall be used Every tenth batch of each to verify the solidification of at least one type of radioactive waste representative test specimen from at least to be solidified.

every tenth batch of each type of radioactive waste to be solidified for disposal at a 10 CFR 61 disposal site.

16.11.5-3 10/30/02

Solid Radioactive Waste 16.11.5 BASES This commitment implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of 10 CFR Part 50, Appendix A and requirements to use a Process Control Program to meet applicable 10CFR61 waste form criteria for solidified and dewatered radioactive wastes.

REFERENCES:

1. 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities".

2. 10 CFR Part 50, Appendix A.

3. 10 CFR20, "Standards for Protection Against Radiation".

4. 10 CFR61, "Licensing Requirements for Land Disposal of Radioactive Waste".

5. 10 CFR71, "Packaging and Transportation of Radioactive Materials".

6. DPCo Process Control Program Manual.

7. NRC Generic Letter 87-12, "Compliance with 10 ,CFR Part 61 And Implementation Of the Radiological Effluent Technical Specifications (Rets) and Attendant Process Control Program (PCP)".

8. NRC Generic Letter 89-01, "Implementation of Programmatic Controls for Radiological Effluent Technical Specifications In the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of Rets to the Offsite Dose Calculation Manual or to the Process Control Program".

16.11.5-41 10/30/02 1

Radiological Environmental Monitoring 16.11.6 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.6 Radiological Environmental Monitoring COMMITMENT a. The radiological environmental monitoring samples shall be collected in accordance with Table 16.11.6-1 and shall be analyzed pursuant to the requirements of Tables 16.11.6-1, 16.11.6-2 and 16.11.6-3.

b. A land use census shall be conducted and shall identify the location of the nearest milk animal and the nearest residence in each of the 16 meteorological sectors within a distance of eight kilometers (five miles). Broad leaf vegetation sampling shall be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.

c. Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program. A summary of the results obtained as part of the Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report. The Interlaboratory Comparison Program shall be described in-the Annual Radiological Environmental Operating Report.

d. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report.

NOTE ---------------------------------- ---

If samples required by Commitment part a, become permanently unavailable from any of the required sample locations, the locations from which samples were unavailable may then be deleted from the program provided replacement samples were obtained and added to the environmental monitoring program, if available. These new locations will be identified in the Annual Radioactive Effluent Release Report.

APPLICABILITY: At all times 16.11.6-1 02/01/05 1

Radiological Environmental Monitoring 16.11.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radiological A.1 Submit a description of May 15 of following environmental the reason for not calendar year monitoring program is conducting the program not conducted as as required and plans to required. prevent a recurrence shall be included in the Annual Radiological Environmental Operating Report.

B. Land use census B.1 ---------. NOTE -----------

identifies a Location The sampling location which yields a having the lowest calculated dose or dose calculated dose or dose commitment (via the commitment (via the same exposure same exposure pathway) 20% greater pathway) may be I than a location from deleted from this which samples are monitoring program currently being after October 31 of the obtained. year in which this land use census was conducted.

Add new location to the 30 days radiological environmental monitoring program.

AND B.2 Identify new locations in April 30 of following the next-Annual calendar year.

Radioactive Effluent Release Report.

16.11.6-2 02/01/05 I

Radiological Environmental Monitoring 16.11,6 CONDITION REQUIRED ACTION COMPLETION TIME C. Interlaboratory C.1 Report corrective May 15 of following Comparison Program actions in the Annual calendar year analyses not performed Radiological as required. Environmental Operating Report.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.6.1 Conduct land use census during growing 12 months season using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.

16.11.6-3 02/01/05 1

Radiological Environmental Monitoring 16.11.6 Table 16.11.6-1 Radiological Environmental Monitoring Program Exposure Pathway and/or Number of Sampling and Collection Time and Frequency of Analysis Sample LocSample Frequencym (d)

Sample ~~Locations (b) Frqec(d

1. AIRBORNE Radioiodine and 5 Continuous sampler Radioiodine canister:

Particulates operation with sample 1-131 analysis weekly. Particulate collection weekly, or sampler: Gross beta radioactivity more frequently if analysis following filter change; and required by dust loading. gamma isotopic analysis of composite (by location) quarterly. (c)

2. DIRECT RADIATION 40 Quarterly. Gamma dose quarterly.

3. WATERBORNE

a. Surface 2 Composite (a) sample Gamma isotopic analysis monthly.

over a 1-month period.

Composite for tritium analysis quarterly.

b. Drinking 3 Composite (a) sample Composite for gross beta and gamma over a 1-month period. isotopic analyses monthly.

Composite for tritium analysis quarterly.

c. Sediment from 2 Semiannually. Gamma isotopic analysis, Shoreline semiannually.

16.11.6-4 02/01/05 1

Radiological Environmental Monitoring 16.11.6 Table 16.11.6-1 Radiological Environmental Monitoring Program Exposure Pathway and/or Number of Sampling and Collection lime and Frequency of Analysis Sample Sample Frequency (d)

Locations (b)

4. INGESTION

a. Milk 4(e) Semimonthly when animals are on pasture; monthly at other times. -

Gamma isotopic and 1-131 analysis semimonthly when animals are on pasture; monthly at other times.

I

b. Fish 2 Semiannually. One Gamma isotopic analysis sample each semiannually on edible portion.

commercially and recreationally important species.

c. Broad-leaf 2 Monthly. Gamma isotopic analysis monthly.

Vegetation (a) Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

(b) Sample locations are identified in the ODCM.

(c) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

(d) Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, or to malfunction of automatic sampling equipment. Ifthe latter, every effort shall be made to complete corrective action prior to the end of the next sampling period.

(e) Samples from milking animals in three locations within 5 km distance having the highest dose potential. If there are none, then one sample from milking animals in each of three areas between 5 to 8 km distant Where doses are calculated to be greater than 1 mrem per year. One sample from milking animals at a control location, as for example 15 to 30 km distant and in the least prevalent wind direction.

16.11.6-5 02/01/05 1

Radiological Environmental Monitoring 16.11.6 Table 16.11.6-2 Maximum Values for the Lower Limits of Detection (LLD) (a) (c)

Airborne Fish Broad-leaf Particulate or Milk VegetationSediment Analysis (pCi/I) Gases (pCi/lg, (pCi/I) (pCi/kg, dry)

(pCi/m 3) wet) (pCi/kg, wet)

Gross Beta 4 1E-02 H3 2,000 Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-95 15 Nb-95 15 1-131 15(b) 7E-02 1 60 Cs-134 15 5E-02 130 15 60 150 Cs-137 18 6E-02 150 18 80 180 Ba-140 La- 140 15 15 60 15 I

(a) The LLD is defined, for purposes of these commitments, as the smallest concentratiofi of radioactive material in a sample with 95% probability of detection and with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

LLD = 4.66 Sb E x V x 2.22 x Y x exp (-XA t)

Where:

LLD is the lower limit of detection as defined above (as pCi per unit mass or volume)

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute) 16.11.6-6 02/01105 1

Radiological Environmental Monitoring 16.11.6 Table 16.11.6-2 Maximum Values for the Lower Limits of Detection (LLD) (a) (c)

E is the counting efficiency (as counts per disintegration)

V is the sample size (in units of mass or volume) 2.22 is the number of disintegrations per minute per picocurie Y is the fractional radiochemical yield (when applicable)

X is the radioactive decay constant for the particular radionuclide A t is the elapsed time between sample collection (or end of the sample collection period) and time of counting Typical values of E, V, Y and A t should be used in the calculation.

The LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of Interfering nuclides, or other uncontrollable circumstances, may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.

(b) LLD for gamma isotopic analysis for 1-131 in drinking water samples. Low level 1-131 analysis on drinking water will not be routinely performed because the calculated dose from 1-131 in drinking water at all locations is less than I mrem per year. Low level 1-131 analyses will be performed if abnormal releases occur which could reasonably result in > 1 pCi/liter of 1-131 in drinking water. For low level analyses of 0- 31 an LLD of 1 pCi/liter will be achieved.

(c) Other peaks which are measurable and identifiable, together with the radionuclides in Table 16.11.6-2, shall be identified and reported.

16.11.6-7 02/01/05 1

Radiological Environmental Monitoring 16.11.6 Table 16.11.6-3 Reporting Levels for Radioactivity Concentrations in Environmental Samples Airborne Broad-leaf Water Particulate or Fish Milk vegetation Analysis (pCi/I) Gases (pCi/kg, wet) (pCi/I)

(pCi/m3) (pCi/kg, wet)

H-3 2E04(a)

Mn-54 1E03 3E04 Fe-59 4E02 1E04 Co-58 1E03 3E04 Co-60 3E02 1E04 Zn-65 3E02 2E04 Zr-Nb-95 4E02 1-131 2(b) 0.9 3 1E02 Cs-134 30 10 1E03 60 1E03 Cs-137 50 20 2E03 70 2E03 Ba-La-140 2E02 3E02 (a) For drinking water samples. This is 40 CFR Part 141 value.

(b) If low level 1-131 analyses are performed.

16.11.6-8 02/01/05 1

Radiological Environmental Monitoring 16.11.6 BASES The environmental monitoring program required by this commitment provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of exposure pathways. The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The detection capabilities required by Table 16.11.6-2 are considered optimum for routine environmental measurements in industrial laboratories. The specified lower limits of detection correspond to less than the 10 CFR 50. Appendix I, design objective dose-equivalent of 45 mrem/year for atmospheric releases to the most sensitive organ and individual. The land use census commitment is provided to assure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are provided if required by the results of this census.

The requirements for participation in an Interlaboratory Comparison Program is provided to assure that independent checks on the precision and accuracy, of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

The following requirement(s) were relocated from the CTS 6.4.4.f during the conversion to ITS.

The station shall have a program to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in UFSAR Chapter 16, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1. Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM;

2. A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census; and,

3. Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

16.11.6-9 02/01/05 1

Radiological Environmental Monitoring 16.

11.6 REFERENCES

1. 10 CFR Part 50, Appendix I.

2. Offsite Dose Calculation Manual.

16.11.6-10 02/01/05 1

Dose Calculations 16.11.7 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.7 Dose Calculations COMMITMENT The annual (calendar year) dose or dose commitment, to any Member of the Public due to releases of radioactivity and to radiation from uranium I fuel cycle sources shall be limited to _*25 mrems to the total body or to any organ, except the thyroid, which shall be limited to _*75 mrems.

APPLICABILITY: At all times ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated doses from A.1 Determine by None the release of calculation, including radioactive materials in direct radiation liquid or gaseous contributions from the effluents exceeding reactor units and from twice the limits of SLC outside storage tanks, 16.11.1.b, SLC whether the limits of 16.11.2.b.1, or SLC Commitment 16.11.7 16.11.2.b.2 have been exceeded.

16.11.7-1 01/31/00 1

Dose Calculations 16.11.7 CONDITION REQUIRED ACTION COMPLETION TIME B. Calculated dose NOTE exceeds limits of This Special Report, as defined Commitment 16.11.7. in 10 CFR Part 20.2203(a), shall include an analysis that estimates the radiation exposure (dose) to a Member of the Public I from uranium fuel cycle sources, (including all effluent pathways and direct radiation), for the calendar year that includes the release(s) covered by this report.

It shall also describe the levels of radiation and concentration of radioactive material involved, and the cause of the exposure levels or concentrations.

BA1 Prepare and submit to the Commission a 30 days Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the specified limits and includes the schedule for achieving conformance with the specified limits.

16.1 1.7-2 01/31/00 I

Dose Calculations 16.11.7 CONDITION REQUIRED ACTION, COMPLETION TIME C. Calculated dose CA. NOTE exceeds limit of Submittal of the report Commitment 16.11.7. is considered a timely request, and a variance AND is granted until staff action on the request is Release condition complete.

resulting in violation of 40 CFR 190 not corrected at time of Include a request for a 30 days from exceeding report submittal. variance in accordance the limit with the provisions of 40 CFR Part 190.

SURVEILLANCE REQUIREMENTS--

SURVEILLANCE FREQUENCY SR 16.11.7.1 Determine cumulative dose contributions from 31 days liquid effluents in accordance with Offsite Dose Calculation Manual.

SR 16.11.7.2 Determine cumulative dose contributions from 31 days gaseous effluents in accordance with Offsite Dose Calculation Manual.

BASES The dose commitment is provided to assure that the release of radioactive material -in liquid and gaseous effluents will be kept "as low as is reasonably achievable." The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I in that conformance with the guides of Appendix I is to be shown by calculations and procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.

16.11.7-3 03/27/99

Dose Calculations 16.

11.7 REFERENCES

1. 10 CFR Part 20.

2. 40 CFR Part 190.

3. Offsite Dose Calculation Manual.

4. 10 CFR Part 50, Appendix I.

16.11.7-4 01/31/00 I

Reports 16.11.8 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.8 Reports COMMITMENT Special reports shall be submitted to the Regional Administrator, Region II,

-within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable SLC:

a. Radioactive Liquid Effluents, Dose, SLC 16.11.1.b Liquid Waste Treatment, SLC 16.11.1.c

b. Radioactive Gaseous Effluents, Dose, SLC 16.11.2.b Gaseous Radwaste Treatment, SLC 16.11.2.c

c. Radiological Environmental Monitoring Program, SLC 16.11.6.a, b, and c

d. Land Use Census, SLC 16.11.6.d

e. Dose Calculations, SLC 16.11.7 APPLICABILITY: At all times.

ACTIONS _

CONDITION REQUIRED ACTION COMPLETION TIME A. Individual milk samples A.1 Submit plan advising 7 days show 1-131 the NRC of the concentrations of 10 proposed action to picocuries per liter or ensure the plant related greater. annual doses will be within the design objective of 45 mrem/yr to the thyroid of any individual.

16.11.8-1 12/21/09 1

Reports 16.11.8 CONDITION REQUIRED ACTION COMPLETION TIME B. Milk samples collected B.1. Submit a plan advising 30 days over a calendar quarter the NRC of the show 1-131 average proposed action to concentrations of 4.8 ensure the plant related picoCuries per liter or annual doses will be greater within the design objective of 45 mrem/yr to the thyroid of any individual.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.8.1 NA NA BASES Reference applicable commitments.

REFERENCES:

1, 10 CFR Part 20.

2, 40 CFR Part 190.

3, Offsite Dose Calculation Manual.

16.11.8-2 12/21/09 I

Radioactive Effluent Release Report 16.11.9 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.9 Radioactive Effluent Release Report COMMITMENT The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.

A single submittal may be made for a multiple unit station. The submittal shall combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the release of radioactive material from each unit.

The Annual Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the station during the reporting period.

The annual Radioactive Effluent Release Report shall include a summary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter.

The Annual Radioactive Effluent Release Report shall include the following information for all unplanned releases to unrestricted areas of radioactive materials in gaseous and liquid effluents:

a. A description of the event and equipment involved;

b. Cause(s) for the unplanned release;

c. Actions taken to prevent recurrence; and,

d. Consequences of the unplanned release.

The Annual Radioactive Effluent Release Report shall include an assessment of radiation doses from the radioactive liquid and gaseous effluents released from the station during each calendar quarter. In addition, the unrestricted area boundary maximum noble gas gamma air and beta air doses shall be evaluated. The annual average meteorological conditions shall be used for determining the gaseous pathway doses. Approximate and conservative approximate methods are acceptable. The assessment of radiation doses shall be performed in accordance with the Offsite Dose Calculation Manual.

The Annual Radioactive Effluent Release Report shall include an explanation of why the inoperability of liquid or gaseous effluent monitoring instrumentation out of service for greater than 30 days was not corrected in a timely manner per SLC 16.11.3.

16.11.9-1 03/22/10 I

Radioactive Effluent Release Report 16.11.9 The Annual Radioactive Effluent Release Report shall include the following information for each type of solid waste shipped offsite during the report period:

a. Total container volume (cubic meters);

b. Total curie quantity (determined by measurement or estimate);

c. Principal radionuclides (determined by measurement or estimate);

d. Type of waste, (e.g., spent resin, compacted dry waste evaporator bottoms);

e. Number of shipments; and,

f. Solidification agent (e.g., cement, or other approved agents (media)).

The Annual Radioactive Effluent Release Report shall include a list and description of unplanned releases from the site to Unrestricted Areas of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Annual Radioactive Effluent Release Report shall include any changes made during the reporting period to the Offsite Dose Calculation Manual (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census.

The Annual Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed Member of the Public from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Methods for calculating the dose contribution from liquid and gaseous effluents are given in the ODCM.

APPLICABILITY: At all times.

16.11.9-2 119 - 03/22/10 1

Radioactive Effluent Release Report 16.11.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. N/A A. 1 N/A N/A SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.9.1 N/A N/A BASES N/A

REFERENCES:

1. Oconee ITS.

2. Offsite Dose.Calculation Manual.

16.11.9-3 03/22/10 1

Radiological Environmental Operating Report 16.11.10 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.10 Radiological Environmental Operating Report COMMITMENT Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 15 of each year.

The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the land use censuses. If harmful effects are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The Annual Radiological Environmental Operating Report shall include a summary of the results obtained as part of the required Interlaboratory Comparison Program. The Interlaboratory Comparison Program shall be described in the Annual Radiological Environmental Operating Report.

The Annual Radiological Environmental Operating Report shall include summarized and tabulated results of the radiological environmental samples required by SLCs taken during the report period. Inthe event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as practical in a supplementary report.

The initial report shall also include the following: a summary description of the radiological environmental monitoring program including sampling methods for each sample type, size and physical characteristics of each sample type, sample preparation methods, analytical methods, and measuring equipment used; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and, the result of land use censuses. Subsequent reports shall describe all substantial changes in these aspects.

APPLICABILITY: At all times.

16.11.10-1 02/25/03 1

Radiological Environmental Operating Report 16.11.10 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. NA A.1 NA NA SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.10.1 NA NA BASES NA

REFERENCES:

1. Oconee ITS

2. Offsite Dose Calculation Manual 16.11.10-2 02/25/03 1

Iodine Radiation Monitoring filters 16.11.11 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.11 Iodine Radiation Monitoring Filters COMMITMENT Assure that the iodine radiation monitoring filters perform their intended function.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. NA A.1 NA NA SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.11.1 Remove and replace iodine radiation 30 days of operation monitoring filters in RIA-44.

SR 16.11.11.2 Discard spare iodine radiation monitoring After 24 months of shelf filters. life.

BASES The purpose of this commitment is to assure the reliability of the iodine radiation monitoring charcoal filters.

REFERENCES:

1. Oconee CTS Amendment No. 3/3 SER date July, 1974.

16.11.11-1 03/27/99

.... *...v *,

,vcu*ai .i uuxsiae. Iemporary Tanks Exceeding Umit 16.11.12 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.12 Radioactive Material in Outside Temporary Tanks Exceeding Limit COMMITMENT The quantity of radioactive material in outside temporary storage tanks shall not exceed the limit specified in ITS 5.5.13.c.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The quantity of A.1 Suspend addition of Immediately radioactive material in radioactive material to outside temporary tank.

storage tank not within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.12.1 Verify the quantity of radioactive material Within 7 days after contained in each of the outside temporary addition of radioactive tanks is within the limit by analyzing a materials to an representative sample of the tanks' contents. outside temporary tank

,OR Verify the quantity of radioactive material in Prior to addition of each of the outside temporary tanks does not radioactive materials to result in exceeding the limit by analyzing a an outside temporary representative sample of radioactive material tank.

to be added.

16.11.12-1 04/10/03 1

Radioactive Material in Outside Temporary Tanks Exceeding Limit 16.11.12 BASES The requirement(s) of this SLC section were relocated from CTS 3.9.1 .c during the conversion to ITS.

The tanks included in this specification are all those outdoor radwaste liquid storage tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system. Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of a tank's contents, the resulting concentrations would be less than the limits of 10CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

REFERENCES N/A 16.11.12-2 04/10/03 1

Radioactive Material in Waste Gas Holdup tank Exceeding Limit 16.11.13 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.13 Radioactive Material in Waste Gas Holdup Tank Exceeding Limit COMMITMENT The quantity of radioactive material in the Waste Gas Holdup tanks shall not exceed the limit specified in ITS 5.5.13.b.

APPLICABILITY: At all times.

ACTIONS S t d rE i wNOTE-Separate Condition Entry is allowed for each tank.

CONDITION REQUIRED ACTION COMPLETION TIME A. The quantity of A.1 Suspend addition of Immediately radioactive material in radioactive material to the Waste Gas Holdup tank.

tank not within limit.

AND AX2 Reduce tank contents 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.13.1 Verify quantity of radioactive materials in each 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when tank is tank is within limit. being filled BASES The requirement(s) of this SLC section were relocated from CTS 3.10.1.b and 3.10.1.c during the conversion to ITS.

16.11.13-1 03/27199

Radioactive Material in Waste Gas Holdup tank Exceeding Limit 16.11.13 Restricting the quantity of radioactivity contained in each waste gas holdup tank provides assurance that in the event of an uncontrolled release of the tank contents, the resulting total body exposure to an individual at the exclusion area boundary will not exceed 0.5 rem.

REFERENCE UFSAR, Section 15.10 16.11.13-2 03/27/99

Explosive Gas Mixture 16.11.14 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.14 Explosive Gas Mixture COMMITMENT The concentration of Hydrogen in the Waste Gas Holdup Tanks shall be

_ 3% by volume.

APPLICABILITY: At all times.

ACTIONS I E-'----.------------

Separate Condition Entry is allowed for each tank.

CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of A.1 Reduce Concentration 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Hydrogen in Waste Gas of Hydrogen to within Holdup tank is > 3% limit.

and *4% by volume.

B. Concentration of B.1 Suspend addition of Immediately Hydrogen in Waste Gas waste gases to tank.

Holdup tank is > 4% by volume. AND B.2 Reduce Concentration 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of Hydrogen to within limit.

16.11.14-1 03/27/99

Explosive Gas Mixture 16.11.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.14.1 Verify Hydrogen concentration in Waste Gas 5 times/week on each Holdup Tank is _< 3% by volume, tank when in service AND once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after isolation of the tank BASES The requirement(s) of this SLC section were relocated from CTS 3.10.2 and Table 4.1-3, Item 13 during the conversion to ITS.

This Commitment is provided to ensure that the concentration of potentially explosive gas mixtures contained in the Waste Gas Holdup Tanks is maintained below the flammability limits of hydrogen. (Administrative controls are used to prevent the hydrogen concentrations from reaching the flammability limit.) These controls include sampling each tank 5 times a week while in service, and/or once in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after isolation of the tank; injection of dilutants to reduce the concentration of hydrogen below its flammability limits provides assurance that the releases of radioactive material will be controlled in conformance with the requirements of GDC 60 of Appendix A to CFR Part 50.

REFERENCES N/A 16.11.14-2 03/27/99

Enclosures

ODCM Manual

PCP Manual j

ML101260473

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11.1 REFERENCES

11.2 REFERENCES

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11.6 REFERENCES

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11.1 REFERENCES

11.2 REFERENCES

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11.6 REFERENCES

11.7 REFERENCES

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