ML081430505: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
(2 intermediate revisions by the same user not shown)
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:~Duke kEnergy.April 30, 2008 DAVE BAXTER Vice President Oconee Nuclear Station Duke Energy Corporation ON01 VP17800 Rochester Highway Seneca, SC 29672 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 864-885-4460 864-885-4208 fax dabaxter@dukeenergy.
{{#Wiki_filter:~Duke DAVE BAXTER kEnergy.                                           Vice President Oconee Nuclear Station Duke Energy Corporation April 30,  2008                                    ON01 VP17800 Rochester Highway Seneca, SC 29672 864-885-4460 U.S. Nuclear Regulatory Commission                 864-885-4208 fax dabaxter@dukeenergy.com Document Control Desk Washington, D.C. 20555
com  


==Subject:==
==Subject:==
.
. Duke Energy Carolinas, LLC Oconee Nuclear Station, Docket Nos. 50-269, 50-270 and 50-287 2007 Annual Radioactive Effluent Release Report Gentlemen:
Duke Energy Carolinas, LLC Oconee Nuclear Station, Docket Nos. 50-269, 50-270 and 50-287 2007 Annual Radioactive Effluent Release Report Gentlemen:
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, 2007 through December 31, 2007.
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 31, 2007.Attachment Attachment Attachment Attachment Attachment Attachment Attachment Enclosures the period of January 1, 2007 through December I Radioactive Effluent Releases II Supplemental Information III Solid Waste Disposal Report IV Inoperable Monitoring Equipment V Unplanned Offsite Releases VI Assessment of Radiation Dose from Radioactive Effluents to Members of the Public VII SLC 16.11 Radiological Effluent Controls Offsite Dose Calculation Manual and Process Control Program Manual Should there be questions concerning this report please contact Judy E. Smith at (864) 885-4309.Very truly yours, Dave Baxter Site Vice President Oconee Nuclear Site Attachments C(www. duke-energy.
Attachment  I   Radioactive Effluent Releases Attachment  II Supplemental Information Attachment  III Solid Waste Disposal Report Attachment  IV Inoperable Monitoring Equipment Attachment  V   Unplanned Offsite Releases Attachment  VI Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Attachment  VII SLC 16.11 Radiological Effluent Controls Enclosures      Offsite Dose Calculation Manual and Process Control Program Manual Should there be questions concerning this report please contact Judy E. Smith at (864) 885-4309.
corn U. S. Nuclear Regulatory Commission April 30, 2008 Page 2 xc: L. N. Olshan, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 0-14 H25 Washington, D. C. 20555 V. M. McCree, Regional Administrator, Acting U. S. Nuclear Regulatory Commission  
Very truly yours, Dave Baxter Site Vice President Oconee Nuclear Site Attachments C(
-Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Andy Hutto Senior Resident Inspector Oconee Nuclear Station S. E. Jenkins, Manager Division of Radioactive Waste Management Bureau of Land and Waste Management Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 U. S. Nuclear Regulatory Commission April 30, 2008 Page 3 bcc without attachments:
www. duke-energy. corn
C. D. Ingram EC07F J. A. Twiggs ON01RP B. G. Davenport ON03RC W. S. Pursley ON01RW bcc with attachments:
 
ELL NSRB R. L. Gill Document Management Attachment I Oconee Nuclear Site Effluent Release Data OCONEE NUCLEAR STATION EFFLUENT RELEASE DATA (January 1, 2007 through December 31, 2007)This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents as outlined in Regulatory Guide 1.21, Appendix B.
U. S. Nuclear Regulatory Commission April 30, 2008 Page 2 xc:   L. N. Olshan, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 0-14 H25 Washington, D. C. 20555 V. M. McCree, Regional Administrator, Acting U. S. Nuclear Regulatory Commission - Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia   30303 Andy Hutto Senior Resident Inspector Oconee Nuclear Station S. E. Jenkins, Manager Division of Radioactive Waste Management Bureau of Land and Waste Management Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201
TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS  
 
-SUMMATION OF ALL RELEASES Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2007 A. Fission and Activation
U. S. Nuclear Regulatory Commission April 30, 2008 Page 3 bcc       without attachments:
: 1. Total Release 2. Avg. Release Rate B. Iodine-131
C. D. Ingram         EC07F J. A. Twiggs         ON01RP B. G. Davenport     ON03RC W. S. Pursley       ON01RW bcc       with attachments:
: 1. Total Release 2. Avg. Release Rate C. Particulates Half Life 1. Total Release 2. Avg. Release Rate D. Tritium 1. Total Release 2. Avg. Release Rate Unit QTR' I Gases Ci 8.49E+01 14Ci/sec 1.09E+01 Ci 1.55E-05/ACi/sec 1.99E-06>= 8 days Ci 1.OOE-06 ,&Ci/sec 1.29E-07 Ci 1.43E+01/LCi/sec 1.83E+00 QTR 2 QTR 3 QTR 4 YEAR 9.06E+01 5.83E+01 1.05E+02 3.39E+02 1.15E+01 7.34E+00 1.32E+01 1.08E+01 1.05E-04 0.00E+00 2.56E-03 2.68E-03 1.34E-05 0.00E+00 3.22E-04 8.49E-05 2.71E-05 3.68E-06 4.66E-09 3.17E-05 3.44E-06 4.62E-07 5.87E-10 1.01E-06 1.01E+01 1.59E+01 1.68E+01 5.71E+01 1.29E+00 2.00E+00 2.11E+00 1.81E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 E. Gross Alpha Radioactivity
ELL NSRB R. L. Gill Document Management
: 1. Total Release Ci 0.00E+00 2. Avg. Release Rate pCi/sec 0.00E+00 TABLE lB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS  
 
-ELEVATED RELEASES -CONTINUOUS MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR 1. Fission and Activation Gases KR-85M Ci 0.OOE+00 XE-133 Ci 7.71E+01 XE-133M Ci 0.OOE+00 XE-135 Ci 7.85E+00 Totals for Period...
Attachment I Oconee Nuclear Site Effluent Release Data
Ci 8.49E+01 2. Iodines 1-131 Ci 1.55E-05 1-133 Ci 1.94E-06 1-135 Ci 0.OOE+00 Totals for Period...
 
Ci 1.74E-05 3. Particulates Half Life >= 8 days CS-137 Ci 1 1.00E-06 Totals for Period...
OCONEE NUCLEAR STATION EFFLUENT RELEASE DATA (January 1, 2007 through December 31,               2007)
Ci 1.OOE-06 4. Tritium H-3 Ci 9.96E+00 Totals for Period...
This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents as outlined in Regulatory Guide 1.21, Appendix B.
Ci 9.96E+00 1.20E-01 8.28E+01 0.OOE+00 6. 96E+00 8. 99E+01 1.02E-04 1.10E-05 0. 00E+00 1. 13E-04 0. OOE+00 0.OOE+00 9.01E+00 9.01E+00 8.16E-02 5.48E+01 0. OOE+00 3. 11E+00 5. 80E+01 0. OOE+00 1. OOE-05 0. OOE+00 1. OOE-05 0.OOE+00 0. OOE+00 1.48E+01 1.48E+01 0.OOE+00 1. 99E+01 2.28E+00 3.73E-01 2.25E+01 2.50E-03 6.22E-04 1.28E-04 3.25E-03 0.OOE+00 0.OOE+00 1.42E+01 1.42E+01 2.02E-01 2.35E+02 2.28E+00 1.83E+01 2.55E+02 2.61E-03 6.45E-04 1.28E-04 3.39E-03 1.00E-06 1.00E-06 4.80E+01 4.80E+01 5. Gross Alpha Radioactivity
 
** No Nuclide Activities  
TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Oconee Nuclear Station Units 1, 2,         & 3 REPORT FOR 2007       Unit      QTR' I  QTR 2    QTR 3    QTR 4    YEAR A. Fission and Activation Gases
**
: 1. Total Release       Ci        8.49E+01 9.06E+01 5.83E+01 1.05E+02 3.39E+02
TABLE lB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS  
: 2. Avg. Release Rate   14Ci/sec  1.09E+01 1.15E+01 7.34E+00 1.32E+01 1.08E+01 B. Iodine-131
-ELEVATED RELEASES -BATCH MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2007 I. Fission and Activation AR-41 KR-85 KR-85M XE- 13 IM XE-133 XE- 133M XE-135 Totals for Period...2. lodines 1-131 1-133 Totals for Period...3. Particulates Half Life CO-58 Totals for Period...4. Tritium H-3 Totals for Period...Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR Gases Ci 2.92E-03 2.01E-02 1.21E-02 0.OOE+00 3.52E-02 Ci 0.00E+00 3.80E-01 3.12E-01 2.89E+00 3.58E+00 Ci 0.OOE+00 0.OOE+00 0.OOE+00 2.57E-05 2.57E-05 Ci 0.OOE+00 2.01E-03 0.OOE+00 5.35E-01 5.37E-01 Ci 9.23E-04 2.58E-01 4.04E-02 7.40E+01 7.43E+01 Ci 0.OOE+00 2.29E-04 0.OOE+00 3.27E-01 3.27E-01 Ci 6.47E-05 4.19E-05 1.98E-04 1.09E-01 1.09E-01 Ci 3.90E-03 6.60E-01 3.65E-01 7.79E+01 7.89E+01 Ci 0.OOE+00 1.97E-09 0.OOE+00 1.23E-05 1.23E-05 Ci 0.OOE+00 0.OOE+00 O.OOE+00 4.94E-07 4.94E-07 Ci 0.OOE+00 1.97E-09 0.OOE+00 1.28E-05 1.28E-05>= 8 days Ci O.OOE+00 0.OOE+00 0.OOE+00 4.66E-09 4.66E-09 Ci 0.OOE+00 0.OOE+00 0.00E+00 4.66E-09 4.66E-09 Ci 4.90E-04 4.36E-02 1.12E-02 5.60E-01 6.15E-01 Ci 4.90E-04 4.36E-02 1.12E-02 5.60E-01 6.15E-01 5. Gross Alpha Radioactivity
: 1. Total Release       Ci        1.55E-05 1.05E-04 0.00E+00 2.56E-03 2.68E-03
** No Nuclide Activities  
: 2. Avg. Release Rate   /ACi/sec  1.99E-06 1.34E-05 0.00E+00 3.22E-04 8.49E-05 C. Particulates Half Life >= 8 days
**
: 1. Total Release        Ci       1.OOE-06 2.71E-05 3.68E-06 4.66E-09 3.17E-05
TABLE iC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS  
: 2. Avg. Release Rate    ,&Ci/sec 1.29E-07 3.44E-06 4.62E-07 5.87E-10 1.01E-06 D. Tritium
-GROUND RELEASES -CONTINUOUS MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2007 1. Fission and Activation XE-133 Totals for Period...2. lodines 1-131 Totals for Period...3. Particulates Half Life CO-58 CO-60 Totals for Period...4. Tritium H-3 Totals for Period...Unit QTR 1 Gases Ci 0.OOE+00 Ci O.OOE+00 Ci 0.OOE+00 Ci O.OOE+00>= 8 days Ci O.OOE+00 Ci 0.OOE+00 Ci 0.OOE+00 Ci 4.29E+00 Ci 4.29E+00 QTR 2 QTR 3 QTR 4 YEAR 0. OOE+00 0.OOE+00 3.77E-06 3.77E-06 2.51E-05 1. 94E-06 2.71E-05 1.10E+00 1.10E+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 3.68E-06 0. OOE+00 3.68E-06 1.08E+00 1.08E+00 4.86E+00 4.86E+00 4.87E-05 4.87E-05 0. OOE+00 0. OOE+00 0. OOE+00 2. 04E+00 2.04E+00 4. 86E+00 4.86E+00 5.24E-05 5.24E-05 2.88E-05 1.94E-06 3.07E-05 8.51E+00 8.51E+00 5. Gross Alpha Radioactivity
: 1. Total Release        Ci        1.43E+01 1.01E+01 1.59E+01 1.68E+01 5.71E+01
** No Nuclide Activities
: 2. Avg. Release Rate    /LCi/sec  1.83E+00 1.29E+00 2.00E+00 2.11E+00 1.81E+00 E. Gross Alpha Radioactivity
**
: 1. Total Release        Ci        0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
TABLE iC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS  
: 2. Avg. Release Rate    pCi/sec  0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00
-GROUND RELEASES -BATCH MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR 1. Fission and Activation Gases** No Nuclide Activities  
 
**2. lodines** No Nuclide Activities  
TABLE lB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS         - ELEVATED RELEASES         - CONTINUOUS MODE Oconee Nuclear Station Units 1, 2,           & 3 REPORT FOR 2007           Unit     QTR 1     QTR 2     QTR 3     QTR 4     YEAR
**3. Particulates Half Life >= 8 days** No Nuclide Activities  
: 1. Fission and Activation Gases KR-85M                     Ci       0.OOE+00 1.20E-01  8.16E-02  0.OOE+00 2.02E-01 XE-133                    Ci       7.71E+01  8.28E+01 5.48E+01  1. 99E+01 2.35E+02 XE-133M                    Ci       0.OOE+00  0.OOE+00 0. OOE+00 2.28E+00  2.28E+00 XE-135                    Ci       7.85E+00  6. 96E+00 3. 11E+00 3.73E-01  1.83E+01 Totals for Period...       Ci       8.49E+01 8. 99E+01 5. 80E+01 2.25E+01  2.55E+02
**4. Tritiium H-3 Totals for Period...Ci 1.79E-02 Ci 1.79E-02 5.64E-07 5.64E-07 0. OOE+i00 0 .OOE+00 2.83E-07 2.83E-07 1.79E-02 1.79E-02 5. Gross Alpha Radioactivity
: 2. Iodines 1-131                      Ci        1.55E-05 1.02E-04 0. OOE+00 2.50E-03  2.61E-03 1-133                      Ci        1.94E-06  1.10E-05  1. OOE-05 6.22E-04  6.45E-04 1-135                      Ci        0.OOE+00 0. 00E+00 0. OOE+00 1.28E-04  1.28E-04 Totals for Period...       Ci        1.74E-05  1. 13E-04 1. OOE-05 3.25E-03 3.39E-03
** No Nuclide Activities  
: 3. Particulates Half Life >= 8 days CS-137                    Ci      1 1.00E-06 0. OOE+00 0.OOE+00 0.OOE+00  1.00E-06 Totals for Period...      Ci        1.OOE-06  0.OOE+00  0. OOE+00 0.OOE+00  1.00E-06
**
: 4. Tritium H-3                        Ci        9.96E+00  9.01E+00  1.48E+01  1.42E+01 4.80E+01 Totals for Period...        Ci        9.96E+00  9.01E+00  1.48E+01  1.42E+01  4.80E+01
TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID EFFLUENTS  
: 5. Gross Alpha Radioactivity
-SUMMATION OF ALL RELEASES Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Products 1. Total Release Ci 3.23E-03 2. Average Diluted Concentration
  ** No Nuclide Activities **
: a. Continuous Releases pCi/ml 0.00E+00 b. Batch Releases gCi/ml 1.93E-10 B. Tritium 1. Total Release Ci 2.66E+02 2. Average Diluted Concentration
 
: a. Continuous Releases ACi/ml 2.46E-08 b. Batch Releases pCi/ml 1.59E-05 C. Dissolved and Entrained Gases 1. Total Release Ci 6.59E-04 2. Average Diluted Concentration
TABLE lB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS         EFFLUENTS   -   ELEVATED RELEASES     - BATCH MODE Oconee Nuclear Station Units 1, 2,             & 3 REPORT FOR 2007               Unit      QTR 1    QTR 2    QTR 3    QTR 4    YEAR I. Fission and Activation Gases AR-41                         Ci        2.92E-03 2.01E-02 1.21E-02  0.OOE+00 3.52E-02 KR-85                        Ci        0.00E+00 3.80E-01 3.12E-01  2.89E+00 3.58E+00 KR-85M                        Ci        0.OOE+00 0.OOE+00 0.OOE+00  2.57E-05 2.57E-05 XE- 13 IM                    Ci       0.OOE+00 2.01E-03 0.OOE+00 5.35E-01 5.37E-01 XE-133                        Ci        9.23E-04 2.58E-01 4.04E-02  7.40E+01 7.43E+01 XE- 133M                      Ci       0.OOE+00 2.29E-04 0.OOE+00 3.27E-01 3.27E-01 XE-135                        Ci       6.47E-05 4.19E-05 1.98E-04  1.09E-01 1.09E-01 Totals for Period...          Ci       3.90E-03 6.60E-01 3.65E-01  7.79E+01 7.89E+01
: a. Continuous Releases uCi/ml 0.OOE+00 b. Batch Releases pCi/ml 3.94E-11 D. Gross Alpha Radioactivity
: 2. lodines 1-131                        Ci        0.OOE+00 1.97E-09 0.OOE+00 1.23E-05 1.23E-05 1-133                        Ci        0.OOE+00 0.OOE+00 O.OOE+00 4.94E-07 4.94E-07 Totals for Period...          Ci       0.OOE+00 1.97E-09 0.OOE+00 1.28E-05 1.28E-05
: 1. Total Release Ci 0.OOE+00 2. Average Diluted Concentration
: 3. Particulates Half Life >= 8 days CO-58                        Ci        O.OOE+00 0.OOE+00 0.OOE+00 4.66E-09 4.66E-09 Totals for Period...          Ci       0.OOE+00 0.OOE+00 0.00E+00 4.66E-09 4.66E-09
: a. Continuous Releases pCi/ml 0.00E+00 b. Batch Releases pCi/ml 0.OOE+00 E. Volume of Liquid Waste 1. Continuous Releases liters 7.19E+08 2. Batch Releases liters 1.75E+06 F. Volume of Dilution Water 1. Continuous Releases liters 1.67E+10 2. Batch Releases liters 1.67E+10 4.12E-03 2.33E-03 9.81E-03 1.95E-02 0.OOE+00 0.OOE+00 O.00E+O0 0.OOE+00 2.44E-10 1.36E-10 5.74E-10 2.87E-10 2.55E+02 1.47E+02 2.43E+02 9.11E+02 1.48E-08 1.629-08 1.86E-08 1.85E-08 1.51E-05 8.56E-06 1.42E-05 1.34E-05 3..83E-04 2.21E-04 4.96E-04 1.76E-63 0.OOE+00 0.OOE+.00 0.OOE+00 0.00E+00 2.26E-11 1.29E-11 2.90E-11 2.59E-11 0.OOE+00 0.OOE00 O .OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 7.67E+08 4.53E+08 6.11E+08 2.55E+09 3.23E+06 9.13E+05 3.19E+06 9.08E+06 1.69E+10 1.71E+10 1.71E+10 6.78E+10 1.69E+10 1.71E+10 1.71E+10 6.78E+10 TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID EFFLUENTS
: 4. Tritium H-3                            Ci       4.90E-04 4.36E-02 1.12E-02 5.60E-01 6.15E-01 Totals for Period...          Ci       4.90E-04 4.36E-02 1.12E-02 5.60E-01 6.15E-01
-CONTINUOUS MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 200.7 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR 1. Fission and Activation Products** No Nuclide Activities  
: 5. Gross Alpha Radioactivity
**2. Tritium H-3 Totals for Period...Ci 4.28E-01 Ci 4.28E-01 2.61E-01 2.61E-01 2.84E-01 2.84E-01 3.29E-01 1.30E+00 3.29E-01 1.30E+00 3. Dissolved and Entrained Gases** No Nuclide Activities
  ** No Nuclide Activities     **
**4. Gross Alpha Radioactivity
 
** No Nuclide Activities
TABLE iC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS       EFFLUENTS   - GROUND RELEASES       - CONTINUOUS MODE Oconee Nuclear Station Units 1, 2,           & 3 REPORT FOR   2007             Unit    QTR 1    QTR 2    QTR 3    QTR 4    YEAR
**
: 1. Fission and Activation Gases XE-133                       Ci      0.OOE+00 0. OOE+00 0. OOE+00 4.86E+00  4. 86E+00 Totals for Period...         Ci      O.OOE+00 0.OOE+00  0. OOE+00 4.86E+00  4.86E+00
TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID EFFLUENTS
: 2. lodines 1-131                        Ci       0.OOE+00 3.77E-06  0. OOE+00 4.87E-05  5.24E-05 Totals for Period...          Ci       O.OOE+00 3.77E-06  0. OOE+00 4.87E-05  5.24E-05
-BATCH MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR 1.. Fission and Activation AG-11OM CO-57 CO-58 CO-60 CR-51 CS-137 1-131 NB-95 SB-125 ZR-95 Totals for Period...2. Tritium H-3 Products Ci 4.55E-05 3.75E-04 4.00E-05 2.31E-04 6.92E-04 Ci 0.OOE+00 0.00E+00 0.OOE+00 1.47E-05 1.47E-05 Ci 1.51E-03 3.54E-03 2.23E-03 8.53E-03 1.58E-02 Ci 0.OOE+00 0.OOE+00 1.97E-05 2.19E-05 4.16E-05 Ci 0.OOE+00 0.OOE+00 O.OOE+00 3.74E-04 3.74E-04 Ci 0.OOE+00 3.99E-05 0.OOE+00 3.14E-04 3.54E-04 Ci 0.OOE+00 0.OOE+00 O.OOE+00 2.02E-04 2.02E-04 Ci O.OOE+00 0.00E+00 0.OOE+00 5.21E-05 5.21E-05 Ci 1.67E-03 1.62E-04 0.OOE+00 7.44E-05 1.91E-03 Ci 0.OOE+00 0.OOE+00 4.25E-05 0.00E+00 4.25E-05 Ci 3.23E-03 4.12E-03 2.33E-03 9.81E-03 1.95E-02 Ci 2.65E+02 2.55E+02 1.46E+02 2.43E+02 9.09E+02 Totals for Period...
: 3. Particulates Half Life >= 8 days CO-58                        Ci       O.OOE+00 2.51E-05  3.68E-06  0. OOE+00 2.88E-05 CO-60                        Ci      0.OOE+00 1. 94E-06 0. OOE+00 0. OOE+00 1.94E-06 Totals for Period...         Ci      0.OOE+00 2.71E-05  3.68E-06 0. OOE+00 3.07E-05
Ci 3. Dissolved and Entrained Gases XE-133 Ci XE-133M Ci Totals for Period...
: 4. Tritium H-3                          Ci      4.29E+00 1.10E+00  1.08E+00 2. 04E+00 8.51E+00 Totals for Period...         Ci      4.29E+00 1.10E+00 1.08E+00 2.04E+00 8.51E+00
Ci 4. Gross Alpha Radioactivity
: 5. Gross Alpha Radioactivity
** No Nuclide Activities
  **  No Nuclide Activities    **
**2.65E+02 2.55E.-02 1.46E+02 2.43E+02 9.09E+02 6.59E-04 3.83E-04 0.OOE+00 0.OOE+00 6.59E-04 3.83E-04 2.21E-04 0. OOE+00 2.21E-04 2.78E-04 2.18E-04 4.96E-04 1.54E-03 2.18BE-04 1.76E-03 Attachment II Oconee Nuclear Site Supplemental Information OCONEE NUCLEAR STATION 2007 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION I. REGULATORY LIMITS -STATION A. NOBLE GASES -AIR DOSE 1. CALENDAR QUARTER -2. CALENDAR QUARTER -3. CALENDAR YEAR -4. CALENDAR YEAR -C. IODINE -131 AND 133, 1. CALENDAR QUARTER =2. CALENDAR YEAR -GAMMA DOSE = 15 MRAD BETA DOSE = 30 MRAD GAMMA DOSE = 30 MRAD BETA DOSE = 60 MRAD B. LIQUID EFFLUENTS
 
-DOSE 1. CALENDAR QUARTER -TOTAL 2. CALENDAR QUARTER -ORGAN 3. CALENDAR YEAR -TOTAL 4. CALENDAR YEAR -ORGAN BODY DOSE = 4.5 MREM DOSE = 15 MREM BODY DOSE = 9 MREM DOSE = 30 MREM TRITIUM, PARTICULATES W/T 1/2 > 8 DAYS -ORGAN DOSE 22.5 MREM 45 MREM II. MAXIMUM PERMISSIBLE EFFLUENT CONCENTRATIONS A. GASEOUS EFFLUENTS  
TABLE iC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS       EFFLUENTS   - GROUND RELEASES     - BATCH MODE Oconee Nuclear Station Units 1, 2,             & 3 REPORT FOR 2007             Unit     QTR 1   QTR 2   QTR 3     QTR 4   YEAR
-INFORMATION FOUND IN OFFSITE DOSE CALCULATION MANUAL B. LIQUID EFFLUENTS  
: 1. Fission and Activation Gases
-INFORMATION FOUND IN 1OCFR20, 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.
  ** No Nuclide Activities   **
SUPPLEMENTAL REPORT, PAGE 2, PROVIDES A  
: 2. lodines
  ** No Nuclide Activities   **
: 3. Particulates Half Life >= 8 days
  ** No Nuclide Activities   **
: 4. Tritiium H-3                           Ci       1.79E-02 5.64E-07 0. OOE+i00 2.83E-07 1.79E-02 Totals for Period...          Ci      1.79E-02 5.64E-07 0. OOE+00  2.83E-07 1.79E-02
: 5. Gross Alpha Radioactivity
  ** No Nuclide Activities **
 
TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Oconee Nuclear         Station Units 1, 2,       & 3 REPORT FOR 2007           Unit     QTR 1     QTR 2     QTR 3     QTR 4   YEAR A. Fission and Activation Products
: 1. Total Release           Ci     3.23E-03 4.12E-03  2.33E-03  9.81E-03 1.95E-02
: 2. Average Diluted Concentration
: a. Continuous Releases pCi/ml 0.00E+00   0.OOE+00  0.OOE+00  O.00E+O0 0.OOE+00
: b. Batch Releases       gCi/ml 1.93E-10   2.44E-10  1.36E-10  5.74E-10 2.87E-10 B. Tritium
: 1. Total Release           Ci     2.66E+02 2.55E+02  1.47E+02  2.43E+02 9.11E+02
: 2. Average Diluted Concentration
: a. Continuous Releases ACi/ml 2.46E-08    1.48E-08  1.629-08  1.86E-08 1.85E-08
: b. Batch Releases       pCi/ml 1.59E-05  1.51E-05  8.56E-06  1.42E-05 1.34E-05 C. Dissolved and Entrained Gases
: 1. Total Release          Ci      6.59E-04  3..83E-04 2.21E-04  4.96E-04 1.76E-63
: 2. Average Diluted Concentration
: a. Continuous Releases uCi/ml 0.OOE+00   0.OOE+00  0.OOE+.00 0.OOE+00 0.00E+00
: b. Batch Releases       pCi/ml 3.94E-11  2.26E-11  1.29E-11  2.90E-11 2.59E-11 D. Gross Alpha Radioactivity
: 1. Total Release          Ci      0.OOE+00 0.OOE+00 0.OOE00 O .OOE+00 0.OOE+00
: 2. Average Diluted Concentration
: a. Continuous Releases pCi/ml 0.00E+00    0.00E+00  0.OOE+00  0.OOE+00 0.OOE+00
: b. Batch Releases      pCi/ml 0.OOE+00  0.OOE+00  O.OOE+00  0.OOE+00 0.OOE+00 E. Volume of Liquid Waste
: 1. Continuous Releases    liters  7.19E+08  7.67E+08  4.53E+08  6.11E+08 2.55E+09
: 2. Batch Releases          liters  1.75E+06  3.23E+06  9.13E+05  3.19E+06 9.08E+06 F. Volume of Dilution Water
: 1. Continuous Releases    liters  1.67E+10  1.69E+10  1.71E+10  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 1/1/07 TO 1/1/08 LIQUID EFFLUENTS - CONTINUOUS MODE Oconee Nuclear Station Units 1, 2,          & 3 REPORT FOR 200.7              Unit    QTR 1    QTR 2    QTR 3   QTR 4    YEAR
: 1. Fission and Activation Products
  **  No Nuclide Activities    **
: 2. Tritium H-3                            Ci      4.28E-01 2.61E-01 2.84E-01 3.29E-01 1.30E+00 Totals for Period...          Ci      4.28E-01 2.61E-01 2.84E-01 3.29E-01 1.30E+00
: 3. Dissolved and Entrained Gases
  ** No Nuclide Activities     **
: 4. Gross Alpha Radioactivity
  **  No Nuclide Activities    **
 
TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID EFFLUENTS      - BATCH MODE Oconee Nuclear Station Units 1, 2,            & 3 REPORT FOR 2007            Unit    QTR 1    QTR 2    QTR 3    QTR 4    YEAR 1.. Fission and Activation Products AG-11OM                    Ci      4.55E-05 3.75E-04  4.00E-05  2.31E-04 6.92E-04 CO-57                      Ci      0.OOE+00 0.00E+00 0.OOE+00  1.47E-05 1.47E-05 CO-58                      Ci      1.51E-03 3.54E-03  2.23E-03  8.53E-03 1.58E-02 CO-60                       Ci      0.OOE+00 0.OOE+00  1.97E-05  2.19E-05 4.16E-05 CR-51                      Ci      0.OOE+00 0.OOE+00  O.OOE+00  3.74E-04 3.74E-04 CS-137                      Ci       0.OOE+00 3.99E-05  0.OOE+00 3.14E-04 3.54E-04 1-131                      Ci       0.OOE+00 0.OOE+00 O.OOE+00  2.02E-04 2.02E-04 NB-95                        Ci       O.OOE+00 0.00E+00 0.OOE+00 5.21E-05 5.21E-05 SB-125                      Ci       1.67E-03 1.62E-04  0.OOE+00 7.44E-05 1.91E-03 ZR-95                      Ci       0.OOE+00 0.OOE+00 4.25E-05  0.00E+00 4.25E-05 Totals for Period...       Ci      3.23E-03 4.12E-03  2.33E-03  9.81E-03 1.95E-02
: 2. Tritium H-3                        Ci      2.65E+02 2.55E+02  1.46E+02  2.43E+02 9.09E+02 Totals for Period...       Ci       2.65E+02 2.55E.-02 1.46E+02 2.43E+02 9.09E+02
: 3. Dissolved and Entrained Gases XE-133                     Ci       6.59E-04 3.83E-04  2.21E-04  2.78E-04 1.54E-03 XE-133M                    Ci      0.OOE+00  0.OOE+00 0. OOE+00 2.18E-04 2.18BE-04 Totals for Period...       Ci      6.59E-04 3.83E-04 2.21E-04 4.96E-04 1.76E-03
: 4. Gross Alpha Radioactivity
  **  No Nuclide Activities  **
 
Attachment II Oconee Nuclear Site Supplemental Information
 
OCONEE NUCLEAR STATION 2007       EFFLUENT AND WASTE DISPOSAL       SUPPLEMENTAL   INFORMATION I. REGULATORY       LIMITS     -   STATION A. NOBLE GASES - AIR DOSE                               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 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==
==SUMMARY==
DESCRIPTION OF THE METHOD USED FOR ESTIMATING OVERALL ERRORS ASSOCIATED WITH RADIOACTIVITY MEASUREMENTS.
DESCRIPTION OF THE METHOD USED FOR ESTIMATING OVERALL ERRORS ASSOCIATED WITH RADIOACTIVITY MEASUREMENTS.
V. BATCH RELEASES A. LIQUID EFFLUENT 1. 1.14E+02 = TOTAL NUMBER OF BATCH RELEASES 2. 2.25E+04 = TOTAL TIME (MIN.) FOR BATCH RELEASES.3. 2.56E+02 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.4. 1.97E+02 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.5. 1.13E+02 = MINIMUM TIME (MIN.) FOR A BATCH RELEASE.6. 3.41E+04 = AVERAGE DILUTION WATER FLOW DURING RELEASES (GPM).B. GASEOUS EFFLUENT 1. 6.70E+01 = TOTAL NUMBER OF BATCH RELEASES.2. 1.16E+05 = TOTAL TIME (MIN.) FOR BATCH RELEASES.3. 3.51E+04 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.4. 1.73E+03 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.5. 1.OOE+00 = MINIMUM TIME (MIN.) FOR A BATCH RELEASE.VI. ABNORMAL RELEASES A. LIQUID 1. NUMBER OF RELEASES = 0 2
V. BATCH RELEASES A. LIQUID EFFLUENT
: 1. 1.14E+02 = TOTAL NUMBER OF BATCH RELEASES
: 2. 2.25E+04 = TOTAL TIME (MIN.) FOR BATCH RELEASES.
: 3. 2.56E+02 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.
: 4. 1.97E+02 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.
: 5. 1.13E+02 = MINIMUM TIME (MIN.) FOR A BATCH RELEASE.
: 6. 3.41E+04 = AVERAGE DILUTION WATER FLOW DURING RELEASES        (GPM).
B. GASEOUS EFFLUENT
: 1. 6.70E+01 = TOTAL NUMBER OF BATCH RELEASES.
: 2. 1.16E+05 = TOTAL TIME (MIN.) FOR BATCH RELEASES.
: 3. 3.51E+04 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.
: 4. 1.73E+03 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.
: 5. 1.OOE+00 = 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                   
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE  
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE  


==SUMMARY==
==SUMMARY==
REPORT Oconee Nuclear Station Units 1, 2, & 3 ist Quarter 2007 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS=======
REPORT Oconee Nuclear Station Units 1, 2,                                             & 3 ist Quarter 2007 IODINE,                 H3,         and PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 1 2007 Critical Critical Dose       Limit     Max % of Period-Limit                                                                   Age     Organ     (mrem)   (mrem)   Limit Q1 - Maximum Organ Dose                                                         CHILD   THYROID   6.42E-03   2.25E+01 2.85E-02 Maximum Organ Dose Receptor Location: 1.0 Mile SE Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)
Quarter 1 2007 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit..............................................................................
Nuclide                                                       Percentage H-3                                                           9.86E+01 NOBLE GAS DOSE LIMIT ANALYSIS==-......=======-....-======= Quarter 1 2007 Dose       Limit     % of Period-Limit                                                                                       (mrad) . (mrad)   Limit Q1 - Maximum Gamma Air Dose                                                                       2.24E-03   1.50E+01 1.49E-02 Maximum Gamma Air Dose Receptor Location:                                                   1.0 Mile SW Major Isotopic Contributors (5% or greater to total)
Q1 -Maximum Organ Dose CHILD THYROID 6.42E-03 2.25E+01 2.85E-02 Maximum Organ Dose Receptor Location:
Nuclide                                                       Percentage XE-133                                                       6.43E+01 XE-135                                                       3.56E+01 Q1 - Maximum Beta Air Dose                                                                         5.31E-03   3.OOE+01 1.77E-02 Maximum Beta Air Dose Receptor Location:                                                   1.0 Mile SW Major Contributors                                         (5% or greater to total)
1.0 Mile SE Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 9.86E+01 NOBLE GAS DOSE LIMIT ANALYSIS==-......=======-....-=======
Nuclide                                                       Percentage XE-133                                                       8.07E+01 XE-135                                                       1.93E+01
Quarter 1 2007 Dose Limit % of Period-Limit (mrad) .(mrad) Limit Q1 -Maximum Gamma Air Dose 2.24E-03 1.50E+01 1.49E-02 Maximum Gamma Air Dose Receptor Location:
 
1.0 Mile SW Major Isotopic Contributors (5% or greater to total)Nuclide Percentage XE-133 6.43E+01 XE-135 3.56E+01 Q1 -Maximum Beta Air Dose 5.31E-03 3.OOE+01 1.77E-02 Maximum Beta Air Dose Receptor Location:
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE  
1.0 Mile SW Major Contributors (5% or greater to total)Nuclide Percentage XE-133 8.07E+01 XE-135 1.93E+01 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE  


==SUMMARY==
==SUMMARY==
REPORT Oconee Nuclear Station Units 1, 2, & 3 2 nd Quarter 2007 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS=======
REPORT Oconee Nuclear             Station Units 1, 2,               & 3 2 nd   Quarter 2007 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 2 2007 Critical     Critical       Dose     Limit     Max % of Period-Limit                     Age           Organ           (mrem) (mrem)     Limit Q2 - Maximum Organ Dose           CHILD       THYROID         5.27E-03 2.25E+01   2.34E-02 Maximum Organ Dose Receptor Location:         1.0 Mile SW Critical   Pathway: Vegetation Major Isotopic Contributors (5% or greater           to total)
Quarter 2 2007 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2 -Maximum Organ Dose CHILD THYROID 5.27E-03 2.25E+01 2.34E-02 Maximum Organ Dose Receptor Location:
Nuclide                 Percentage H-3                     6.06E+01 1-131                   3.B7E+01 NOBLE GAS DOSE LIMIT ANAIYSIS         -Quarter                           2 2007 Dose     Limit     % of Period-Limit                                                   (mrad) (mrad)     Limit Q2 - Maximum Gamma Air Dose                                   2.28E-03 1.50E+01   1.52E-02 Maximum Ganmna Air Dose Receptor Location:           1.0 Mile SW Major Isotopic Contributors (5% or greater           to total)
1.0 Mile SW Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 6.06E+01 1-131 3.B7E+01 NOBLE GAS DOSE LIMIT ANAIYSIS -Quarter 2 2007 Dose Limit % of Period-Limit (mrad) (mrad) Limit Q2 -Maximum Gamma Air Dose 2.28E-03 1.50E+01 1.52E-02 Maximum Ganmna Air Dose Receptor Location:
Nuclide                 Percentage XE-133                 6.81E+01 XE-135                 3.11E+01 Q2 - Maximum Beta Air Dose                                     5.59E-03 3.00E+01   1.86E-02 Maximum Beta Air Dose Receptor Location:           1.0 Mile SW Major Contributors     (5% or greater to total)
1.0 Mile SW Major Isotopic Contributors (5% or greater to total)Nuclide Percentage XE-133 6.81E+01 XE-135 3.11E+01 Q2 -Maximum Beta Air Dose 5.59E-03 3.00E+01 1.86E-02 Maximum Beta Air Dose Receptor Location:
Nuclide                 Percentage XE-133                 8.28E+01 XE-135                 1.62E+01
1.0 Mile SW Major Contributors (5% or greater to total)Nuclide Percentage XE-133 8.28E+01 XE-135 1.62E+01 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE  
 
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE  


==SUMMARY==
==SUMMARY==
REPORT Oconee Nuclear Station Units 1, 2, & 3 3 rd Quarter 2007 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS=======
REPORT Oconee Nuclear Station Units 1, 2,                                 & 3 3 rd   Quarter 2007 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 3 2007 Critical       Critical       Dose     Limit     Max % of Period-Limit                     Age '           Organ           (mrem)   (mrem)   Limit Q3   - Maximum Organ Dose         CHILD           THYROID         4.77E-03 2.25E+01 2.12E-02 Maximum Organ Dose Receptor Location:           1.0 Mile SW Critical   Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)
Quarter 3 2007 Critical Critical Dose Limit Max % of Period-Limit Age ' Organ (mrem) (mrem) Limit Q3 -Maximum Organ Dose CHILD THYROID 4.77E-03 2.25E+01 2.12E-02 Maximum Organ Dose Receptor Location:
Nuclide                 Percentage H-3                     9.99E+01 NOBLE GAS DOSE LIMIT ANALYSIS==========================               Quarter 3 2007 Dose       Limit     % of Period-Limit                                                       (mrad)   (mrad)   Limit Q3 - Maximum Garmma Air Dose                                       1.35E-03, 1.50E+01 9.02E-03 Maximum Gamma Air Dose Receptor Location:                 1.0 Mile SW Major Isotopic Contributors (5% or greater               to total)
1.0 Mile SW Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 9.99E+01 NOBLE GAS DOSE LIMIT ANALYSIS==========================
Nuclide                 Percentage XE-133                   7.58E+01 XE-135                   2.34E+01 Q3 - Maximum Beta Air Dose                                         3.50E-03 3.OOE+01 1.17E-02 Maximum Beta Air Dose Receptor Location:               1.0 Mile SW Major Contributors     (5% or greater       to total)
Quarter 3 2007 Dose Limit % of Period-Limit (mrad) (mrad) Limit Q3 -Maximum Garmma Air Dose 1.35E-03, 1.50E+01 9.02E-03 Maximum Gamma Air Dose Receptor Location:
Nuclide                 Percentage XE-133                 8.72E+01 XE-135                 1.16E+01
1.0 Mile SW Major Isotopic Contributors (5% or greater to total)Nuclide Percentage XE-133 7.58E+01 XE-135 2.34E+01 Q3 -Maximum Beta Air Dose 3.50E-03 3.OOE+01 1.17E-02 Maximum Beta Air Dose Receptor Location:
 
1.0 Mile SW Major Contributors (5% or greater to total)Nuclide Percentage XE-133 8.72E+01 XE-135 1.16E+01 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE  
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE  


==SUMMARY==
==SUMMARY==
REPORT Oconee Nuclear Station Units 1, 2, & 3 4th Quarter 2007 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS=======
REPORT Oconee Nuclear Station Units 1, 2,                           & 3 4th Quarter         2007 IODINE, H3,   and PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 4 2007 Critical       Critical Dose     Limit     Max % of Period-Limit                       Age             Organ     (mrem) (mrem)   Limit Q4 - Maximum Organ Dose             INFANT         THYROID   7.26E-02 2.25E+01 3.23E-01 Maximum Organ Dose Receptor Location:             4.5 Mile NE Critical     Pathway: Goat Milk Major Isotopic Contributors (5% or greater to total)
Quarter 4 2007 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 -Maximum Organ Dose INFANT THYROID 7.26E-02 2.25E+01 3.23E-01 Maximum Organ Dose Receptor Location:
Nuclide                   Percentage 1-131                     9.94E+01 NOBLE GAS DOSE LIMIT ANALYSIS===-======================         Quarter 4 2007 Dose     Limit     % of Period-Limit                                                   (mrad) (mrad)   Limit Q4 -     Maximum Gamma Air Dose                               2.08E-03 1.50E+01 1.39E-02 Maximum Gamma Air Dose Receptor Location:               1.0 Mile SW Major Isotopic Contributors (5% or greater to total)
4.5 Mile NE Critical Pathway: Goat Milk Major Isotopic Contributors (5% or greater to total)Nuclide Percentage 1-131 9.94E+01 NOBLE GAS DOSE LIMIT ANALYSIS===-======================
Nuclide                   Percentage XE-133                     9.51E+01 Q4 - Maximum Beta Air Dose                                   6.49E-03 3.OOE+01 2.16E-02 Maximum Beta Air Dose Receptor Location:               1.0 Mile SW
Quarter 4 2007 Dose Limit % of Period-Limit (mrad) (mrad) Limit Q4 -Maximum Gamma Air Dose 2.08E-03 1.50E+01 1.39E-02 Maximum Gamma Air Dose Receptor Location:
.Major Contributors       (5% or greater     to total)
1.0 Mile SW Major Isotopic Contributors (5% or greater to total)Nuclide Percentage XE-133 9.51E+01 Q4 -Maximum Beta Air Dose 6.49E-03 3.OOE+01 2.16E-02 Maximum Beta Air Dose Receptor Location:
Nuclide                   Percentage XE-133                     9.08E+01
1.0 Mile SW.Major Contributors (5% or greater to total)Nuclide Percentage XE-133 9.08E+01 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE  
 
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE  


==SUMMARY==
==SUMMARY==
REPORT Oconee Nuclear Station Units 1, 2, & 3 AMUAL 2007 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS=======
REPORT Oconee Nuclear Station Units 1, 2,                       & 3 AMUAL       2007 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS======= Annual 2007 Critical   Critical     Dose     Limit     Max % of Period-Limit                     Age       Organ       (mrem)   (mrem)   Limit Yr - Maximum Organ Dose           INFANT     THYROID     7.67E-02 4.50E+01 1.70E-01 Maximum Organ Dose Receptor Location:       4.5 Mile NE Critical   Pathway: Goat Milk Major Isotopic Contributors (5% or greater to total)
Annual 2007 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Yr -Maximum Organ Dose INFANT THYROID 7.67E-02 4.50E+01 1.70E-01 Maximum Organ Dose Receptor Location:
Nuclide                 Percentage 1-131                   9.84E+01 NOBLE GAS DOSE LIMIT ANALYSIS===-======================     Annual 2007 Dose     Limit     % of Period-Limit                                             (mrad)   (mrad)   Limit Yr - Maximum Ganmna Air Dose                             7.96E-03 3.00E+01 2.65E-02 Maximum Gamma Air Dose Receptor Location:           1.0 Mile SW Major Isotopic Contributors (5% or greater to total)
4.5 Mile NE Critical Pathway: Goat Milk Major Isotopic Contributors (5% or greater to total)Nuclide Percentage 1-131 9.84E+01 NOBLE GAS DOSE LIMIT ANALYSIS===-======================
Nuclide                 Percentage XE-133                 7.54E+01 XE-135                 2.35E+01 Yr - Maximum Beta Air Dose                               2.09E-02 6.OOE+01 3.48E-02 Maximum Beta Air Dose Receptor       Location:   1.0 Mile SW Major Contributors     (5% or greater to total)
Annual 2007 Dose Limit % of Period-Limit (mrad) (mrad) Limit Yr -Maximum Ganmna Air Dose 7.96E-03 3.00E+01 2.65E-02 Maximum Gamma Air Dose Receptor Location:
Nuclide                 Percentage XE-133                 8.55E+01 XE-135                 I*.15E+01
1.0 Mile SW Major Isotopic Contributors (5% or greater to total)Nuclide Percentage XE-133 7.54E+01 XE-135 2.35E+01 Yr -Maximum Beta Air Dose 2.09E-02 6.OOE+01 3.48E-02 Maximum Beta Air Dose Receptor Location:
 
1.0 Mile SW Major Contributors (5% or greater to total)Nuclide Percentage XE-133 8.55E+01 XE-135 I*.15E+01 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE  
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE  


==SUMMARY==
==SUMMARY==
REPORT Oconee Nuclear Station Units 1, 2, & 3 1St Quarter 2007 BATCH LIQUID RELEASES Critical Critical Dose Period-Limit Age Organ (mrem)Quarter 1 2007 ======Limit Max % of (mrem) Limit Q1 -Maximum Organ Dose Q1 -Total Body Dose CHILD CHILD GI-LLI 1.85E-02 1.50E+01 1.24~E-01 1.85E-02 4.50E+00 4.11E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5%Nuclide Percentage H-3 9.95E+01 or greater to total)or greater to total)Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5%Nuclide Percentage H-3 9.97E+01 CONTINUOUS LIQUID RELEASES (CTP 3)Critical Period-Limit Age Q1 -Maximum Organ Dose CHILD Q1 -Total Body Dose CHILD Critical Dose Organ (mrem)LIVER 2.86E-05 2.86E-05 Quarter Limit (mrem)1 2007 ......Max % of Limit 1.50E-*01 1.90E-04 4.50E+00 6.34E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 1. 00E+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 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE  
REPORT Oconee Nuclear             Station Units 1, 2,           & 3 1St Quarter 2007 BATCH LIQUID RELEASES                                       Quarter 1 2007 ======
Critical    Critical    Dose    Limit     Max % of Period-Limit                    Age        Organ        (mrem)  (mrem)   Limit Q1 - Maximum Organ Dose         CHILD       GI-LLI       1.85E-02 1.50E+01 1.24~E-01 Q1 - Total Body Dose            CHILD                    1.85E-02 4.50E+00 4.11E-01 Maximum Organ Critical   Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide               Percentage H-3                   9.95E+01 Total Body Critical   Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide               Percentage H-3                   9.97E+01 CONTINUOUS LIQUID RELEASES   (CTP 3)                       Quarter 1 2007 ......
Critical    Critical     Dose    Limit    Max % of Period-Limit                     Age         Organ        (mrem)  (mrem)    Limit Q1 - Maximum Organ Dose         CHILD       LIVER       2.86E-05 1.50E-*01 1.90E-04 Q1 - Total Body Dose            CHILD                    2.86E-05 4.50E+00 6.34E-04 Maximum Organ Critical   Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide               Percentage H-3                   1. 00E+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 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE  


==SUMMARY==
==SUMMARY==
REPORT Oconee Nuclear Station Units 1, 2, & 3 2 nd Quarter 2007 BATCH LIQUID RELEASES----------
REPORT Oconee Nuclear Station Units               1, 2,   & 3 2 nd Quarter 2007 BATCH LIQUID RELEASES----------                         Quarter 2 2007 ......
Critical Critical Dose Period-Limit Age Organ (mrem)Q2 -Maximum Organ Dose CHILD Q2 -Total Body Dose ADULT Quarter 2 Limit (mrem)1.50E+01 4.50E+00 2007 ......Max % of Limit 1.35E-01 4.20E-01 LIVER 2.03E-02 1.89E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 CS-137 8 .72E+01 1.25E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 9.01E+01 CS-137 9.34E+00 CONTINUOUS LIQUID RELEASES (CTP 3)Critical Period-Limit Age Q2 -Maximum Organ Dose CHILD Q2 -Total Body Dose CHILD Quarter 2 2007 ======Critical Dose Limit Max % of Organ (mrem) (mrem) Limit LIVER 1.73E-05 1.50E+01 1.15E-04 1.73E-05 4.50E+00 3.85E-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.OOE+02 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE  
Critical Critical Dose       Limit    Max % of Period-Limit                     Age     Organ     (mrem)    (mrem)   Limit Q2 - Maximum Organ Dose           CHILD   LIVER    2.03E-02  1.50E+01  1.35E-01 Q2 - Total Body Dose             ADULT             1.89E-02  4.50E+00 4.20E-01 Maximum Organ Critical     Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide                 Percentage H-3                     8 .72E+01 CS-137                  1.25E+01 Total Body Critical     Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide                 Percentage H-3                     9.01E+01 CS-137                 9.34E+00 CONTINUOUS LIQUID RELEASES (CTP 3)                     Quarter 2 2007 ======
Critical Critical Dose       Limit     Max % of Period-Limit                      Age      Organ     (mrem)   (mrem)   Limit Q2 - Maximum Organ Dose          CHILD    LIVER     1.73E-05 1.50E+01 1.15E-04 Q2 - Total Body Dose              CHILD              1.73E-05 4.50E+00 3.85E-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.OOE+02
 
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE  


==SUMMARY==
==SUMMARY==
REPORT Oconee Nuclear Station Units 1, 2, & 3 3rd Quarter 2007 BATCH LIQUID RELEASES---------------===--=---=---=----
REPORT Oconee Nuclear Station Units 1, 2,                   & 3 3rd Quarter       2007 BATCH LIQUID RELEASES---------------===--=---=---=---- Quarter 3 2007 ======
Critical Critical Dose Period-Limit Age Organ (mrem)Q3 -Maximum Organ Dose ADULT GI-LLI 1.03E-02 Q3 -Total Body Dose CHILD 1.02E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 9.47E+01 CO-58 5.14E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 9.93E+01 CONTINUOUS LIQUID RELEASES (CTP 3)--=-=--=-=---=======
Critical Critical Dose     Limit    Max % of Period-Limit                       Age     Organ     (mrem) (mrem)    Limit Q3 - Maximum Organ Dose             ADULT   GI-LLI   1.03E-02 1.50E+01  6.89E-02 Q3 - Total Body Dose               CHILD             1.02E-02 4.50E+00  2.27E-01 Maximum Organ Critical     Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Critical Critical Dose Period-Limit Age Organ (mrem)Q3 -Maximum Organ Dose CHILD LIVER 1.92E-05 Q3 -Total Body Dose CHILD 1.92E-05 Quarter 3 Limit (mrem)1.50E+01 4.50E+00 2007 ======Max % of Limit 6.89E-02 2.27E-01 Quarter 3 Limit (mrem)1.50E+01 4.50E+00 2007 Max % of Limit 1.28E-04 4.27E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5%Nuclide Percentage H-3 1.00E+02 or greater to total)Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H ---- 3--- ------H-3 1.00E+02 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE  
Nuclide                 Percentage H-3                     9.47E+01 CO-58                   5.14E+00 Total Body Critical     Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide                 Percentage H-3                     9.93E+01 CONTINUOUS LIQUID RELEASES (CTP 3)--=-=--=-=---======= Quarter 3 2007 Critical Critical Dose     Limit    Max % of Period-Limit                       Age     Organ     (mrem) (mrem)    Limit Q3   - Maximum Organ Dose         CHILD   LIVER   1.92E-05 1.50E+01  1.28E-04 Q3   - Total Body Dose             CHILD             1.92E-05 4.50E+00 4.27E-04 Maximum Organ Critical   Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide                 Percentage H-3                     1.00E+02 Total Body Critical   Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide                 Percentage H --                     ------
H-3                     1.00E+02
 
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE  


==SUMMARY==
==SUMMARY==
REPORT Oconee Nuclear Station Units 1, 2, & 3 4 th Quarter 2007 BATCH LIQUID RELEASES ==Critical Critical Dose Period-Limit Age Organ (mrem)Q4 -Maximum Organ Dose ADULT LIVER 3.75E-02 Q4 -Total Body Dose ADULT 3.03E-02 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)Nuclide Percentage CS-137 5.64E+01 H-3 4.32E+01 Total Body Critical.Pathway:
REPORT Oconee Nuclear Station Units 1, 2,                 & 3 4 th   Quarter 2007 BATCH LIQUID RELEASES                           ==   Quarter 4 2007 ......
Fresh Water Fish Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 5.34E+01 CS-137 4.57E+01 Quarter 4 Limit (mrem)1.50E+01 4.50E+00 2007 ......Max % of Limit 2.50E-01 6.74E-01 CONTINUOUS LIQUID RELEASES (CTP 3)Critical Period-Limit Age Q4 -Maximum Organ Dose CHILD Q4 -Total Body Dose CHILD Quarter Critical Dose Limit Organ (mrem) (mrem)4 2007 ======Max % of Limit LIVER 2.20E-05 1.50E+01 1.47E-04 2.20E-05 4.50E+00 4.89E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 1.00E+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 1.OOE+02 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE  
Critical Critical Dose     Limit    Max % of Period-Limit                     Age     Organ     (mrem)   (mrem)    Limit Q4 - Maximum Organ Dose           ADULT   LIVER     3.75E-02 1.50E+01  2.50E-01 Q4 - Total Body Dose             ADULT             3.03E-02 4.50E+00  6.74E-01 Maximum Organ Critical     Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)
Nuclide                 Percentage CS-137                   5.64E+01 H-3                     4.32E+01 Total Body Critical.Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)
Nuclide                 Percentage H-3                     5.34E+01 CS-137                 4.57E+01 CONTINUOUS LIQUID RELEASES (CTP 3)                   Quarter 4 2007 ======
Critical Critical Dose      Limit    Max % of Period-Limit                     Age     Organ     (mrem)   (mrem)   Limit Q4 - Maximum Organ Dose          CHILD    LIVER   2.20E-05 1.50E+01 1.47E-04 Q4 - Total Body Dose              CHILD            2.20E-05 4.50E+00 4.89E-04 Maximum Organ Critical   Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide                 Percentage H-3                     1.00E+02 Total Body Critical   Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide                 Percentage H-3                     1.OOE+02
 
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE  


==SUMMARY==
==SUMMARY==
REPORT Oconee Nuclear Station Units 1, 2, & 3 ANNUAL 2007 BATCH LIQUID RELEASES-------------.....................
REPORT Oconee Nuclear Station Units 1, 2,                                             & 3 ANNUAL 2007 BATCH LIQUID RELEASES-------------.....................                         Annual 2007 .......  =
Critical Critical Dose Period-Limit Age Organ (mrem)Annual Limit (mrem)2007 ....... =Max % of Limit Yr -Maximum Organ Dose CHILD Yr -Total Body Dose ADULT LIVER 8.59E-02 3.00E+01 2.86E-01 7.69E-02 9.OOE+00 8.54E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 CS-137 7.35E+01 2.62E+01 Total Body Critical Pathway: Fresh WaterFish Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 7.90E+01 CS-137 2.03E+01 CONTINUOUS LIQUID RELEASES (CTP 3)Critical Period-Limit Age Yr -Maximum Organ Dose CHILD Yr -Total Body Dose CHILD Critical Dose Organ (mrem)LIVER 8.71E-05 8.71E-05 Annual 2007 ...... --Limit Max % of (mrem) Limit 3.OOE+01 2.90E-04 9.OOE+00 9.68E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage 1.00E+02 H-3 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 1.00E+02 Oconee Nuclear Station 2007 Radioactive Effluent Releases 40CFR190 Uranium Fuel Cycle Dose Calculation Results In accordance with the requirements of 40CFRI90, 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.
Critical                 Critical       Dose     Limit    Max % of Period-Limit                         Age                       Organ           (mrem) (mrem)   Limit Yr - Maximum Organ Dose             CHILD                     LIVER           8.59E-02 3.00E+01 2.86E-01 Yr - Total Body Dose                ADULT                                    7.69E-02 9.OOE+00   8.54E-01 Maximum Organ Critical   Pathway: Potable Water Major Isotopic Contributors (5% or greater                           to total)
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.
Nuclide               Percentage H-3                   7.35E+01 CS-137                2.62E+01 Total Body Critical   Pathway: Fresh WaterFish Major Isotopic Contributors (5% or greater                           to total)
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. 2007 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 = 9.69E-02 mrem Maximum Location:
Nuclide               Percentage H-3                   7.90E+01 CS-137                 2.03E+01 CONTINUOUS LIQUID RELEASES (CTP 3)                                               Annual 2007 ......  --
1.0 Mile, South-West Sector Critical Age: Adult Gas non-NG Contribution:
Critical                 Critical      Dose      Limit    Max % of Period-Limit                         Age                       Organ            (mrem)  (mrem)    Limit Yr - Maximum Organ Dose             CHILD                     LIVER          8.71E-05 3.OOE+01  2.90E-04 Yr - Total Body Dose                 CHILD                                     8.71E-05 9.OOE+00   9.68E-04 Maximum Organ Critical   Pathway: Potable Water Major Isotopic Contributors (5% or greater                           to total)
14%Gas NG Contribution:
Nuclide               Percentage H-3                    1.00E+02 Total Body Critical   Pathway: Potable Water Major Isotopic Contributors (5% or greater                           to total)
7%Liquid Contribution:
Nuclide               Percentage H-3                   1.00E+02
79%Maximum Organ (other than TB) Dose = 1.36E-01 mrem Maximum Location:
 
1.0 Mile, South-West Sector Critical Age: Child Critical Organ: Thyroid Gas Contribution:
Oconee Nuclear Station 2007 Radioactive Effluent Releases 40CFR190 Uranium Fuel Cycle Dose Calculation Results In accordance with the requirements of 40CFRI90, 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:
52%Liquid Contribution:
I. 2007 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).
48%II. 2007 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 i0CFR72.212 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)  
Maximum Total Body Dose =       9.69E-02 mrem Maximum Location: 1.0 Mile, South-West Sector Critical Age:     Adult Gas non-NG Contribution:       14%
(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".
Gas NG Contribution:       7%
The following two pages are taken from the Oconee Nuclear Site, "Independent Spent Fuel Storage Installation", 1OCFR72.212 Evaluation report.
Liquid Contribution:       79%
C. 10CFR72.212(b)(2)(i)(C)-
Maximum Organ (other than TB)       Dose = 1.36E-01 mrem Maximum Location: 1.0 Mile,     South-West Sector Critical Age:     Child Critical Organ:       Thyroid Gas Contribution:       52%
Requirements of 72.104"...the requirements of§ 72.104 have been met." 10 CFR 72.104, as clarified by ISG-13 3 9 , stipulates that the licensee perform dose evaluations which establish that any real individual beyond the controlled area boundarynot 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 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).
Liquid Contribution:       48%
In accordance with these requirements, Duke Energy Corporation has performed dose calculations that model the characteristics (initial enrichment, bumup 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.4 0 Calculation OSC-867541 develops the radiation source terms used in subsequent shielding and skyshine calculations using the SCALE Code System-42 More specifically, the SAS2 Module of the SCALE Code System was used to create a problem-dependent pin-cell model for the purpose of building cell-Oconee Nuclear Site IOCFR72.212 Written Evaluations, Rev. 2 Page 22 of 32 weighted, multigroup cross section sets for use in subsequent depletion calculations.
II. 2007 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 i0CFR72.212 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 ORIGEN-S Module 4 3 of 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.
The following two pages are taken from the Oconee Nuclear Site, "Independent Spent Fuel Storage Installation",
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-870644 to evaluate the shielding characteristics of a single Horizontal Storage Module. The MCNP Monte Carlo particle transport computer code 4 5 was used to perform the transport calculations and to write a surface flux file for use in subsequent skyshine calculations.
10CFR72.212 Evaluation report.
Appropriate software quality controls have been implemented for the computer codes andidata used in these analyses (specifically, Calculation DPC-1201.30 001046 contains the verification and validation for MCNP5, while SDQA-70321-COM documents the quality control measures in place for MCNP5).Calculation OSC-8716 4 7 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 hours of occupancy per year) the annual dose at the nearest controlled area boundary (approximately 300 meters) is below the 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 I mile (-1600 meters) from the ISFSI, or 1.36 miles from the centerline of the site.4 8 Oconee NuclearSite 1OCFR72.212 Written Evaluations, Rev. 2 Page 23 of 32 Attachment VII SLC 16.11 Radiological Controls Effluent Radioactive Liquid Effluents 16.11.1%.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.1 Radioactive Liquid Effluents COMMITMENT Establish conditions for the controlled release of radioactive liquid effluents.
C. 10CFR72.212(b)(2)(i)(C)- Requirements of 72.104
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 &#xfd;tCi/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 07/12/01 I Radioactive Liquid Effluents 16.11.1 d. Chemical Treatment Ponds (CTP 1 and 2)1. The quantity of radioactive material in the Chemical Treatment Ponds (CTP) shall be limited so That, for all radionuclides identified, excluding noble gases and tritium, the sum of the ratios of activity (in curies) to the limits in 10 CFR 20, Appendix B, Table 2, column 2 shall not exceed .1.7 x 106.AJ < 1.7 x 10'j Cj Where Aj = pond inventory limit for single radionuclide "j" (curies)Cj = 10 CFR 20, Appendix B, Table 2, Column 2, concentration for single radionuclide "j" (curies)2. No powdex resin shall be transferred to the CTPS unless the sum of the activity of the radionuclides identified is less than 0.1% of the limit identified in Commitment d.1.Qz < 1.0x 10-3 i Aj where Qj = radionuclide'activityin resin Aj = pond inventory limit for radionuclide "j" 3. The total radionuclide inventory of used powdex resin transferred to the Chemical Treatment Ponds over the previous 13 weeks, shall not exceed 0.4% of the pond radionuclide inventory limit.Decay of radionuclides may be taken into account in determining inventory levels.Qj 1 + Qj2 + Qj 3 +- ------+ Qj, < .004 x Aj where, Qj Total inventory of radionuclide j in a transfer n Number of transfers to the Chemical Treatment Ponds during the previous 13 -week period.-NOTE -------------------------------------------
        "...the requirements of&sect; 72.104 have been met."
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.16.1 1.1 -2 07/12/01 1 Radioactive Liquid Effluents 16.11.1 APPLICABILITY:
10 CFR 72.104, as clarified by ISG-13 39 , stipulates that the licensee perform dose evaluations which establish that any real individual beyond the controlled area boundarynot 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 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).
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.16.1 1.1-3 07/12/01 I Radioactive Liquid Effluents 16.11.1 CONDITION REQUIRED ACTION COMPLETION TIME B. Calculated dose from the release of radioactive materials in liquid effluents exceeds any of the limits in Commitment b.B.1 ---------NOTE-------
In accordance with these requirements, Duke Energy Corporation has performed dose calculations that model the characteristics (initial enrichment, bumup 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. 40 Calculation OSC-867541 develops the radiation source terms used in subsequent shielding and skyshine calculations using the SCALE Code System-42 More specifically, the SAS2 Module of the SCALE Code System was used to create a problem-dependent pin-cell model for the purpose of building cell-Oconee Nuclear Site IOCFR72.212 Written Evaluations, Rev. 2                                       Page 22 of 32
Not required during unusual operating conditions that result in activation of the Oconee Emergency Plan.Submit report to the regional NRC Office which includes the following:
 
: 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.
weighted, multigroup cross section sets for use in subsequent depletion calculations. The ORIGEN-S Module 43of 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.
: 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 141.30 days from the end of the quarter during which the release occurred 16.11.1-4 07/12/01 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&#xfd;without treatment and includes the following:
The results of the radiation source term calculation were used as input to Calculation OSC-870644 to evaluate the shielding characteristics of a single Horizontal Storage Module. The MCNP Monte Carlo particle transport computer code 45 was used to perform the transport calculations and to write a surface flux file for use in subsequent skyshine calculations.
in excess of the specified limit, a. Cause of equipment or subsystem inoperability.
Appropriate software quality controls have been implemented for the computer codes andidata used in these analyses (specifically, Calculation DPC-1201.30       001046 contains the verification and validation for MCNP5, while SDQA-70321-COM documents the quality control measures in place for MCNP5).
Calculation OSC-8716 47 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 hours of occupancy per year) the annual dose at the nearest controlled area boundary (approximately 300 meters) is below the 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 I mile 48
(-1600 meters) from the ISFSI, or 1.36 miles from the centerline of the site.
Oconee NuclearSite 10CFR72.212 Written Evaluations, Rev. 2                                       Page 23 of 32
 
Attachment VII SLC 16.11 Radiological Effluent Controls
 
Radioactive Liquid Effluents 16.11.1
%.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 &#xfd;tCi/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                                         07/12/01 I
 
Radioactive Liquid Effluents 16.11.1
: d. Chemical Treatment Ponds (CTP 1 and 2)
: 1. The quantity of radioactive material in the Chemical Treatment Ponds (CTP) shall be limited so That, for all radionuclides identified, excluding noble gases and tritium, the sum of the ratios of activity (in curies) to the limits in 10 CFR 20, Appendix B, Table 2, column 2 shall not exceed .1.7 x 106.
AJ     <       1.7 x 10' j       Cj Where Aj = pond inventory limit for single radionuclide "j" (curies)
Cj = 10 CFR 20, Appendix B, Table 2, Column 2, concentration for single radionuclide "j"(curies)
: 2. No powdex resin shall be transferred to the CTPS unless the sum of the activity of the radionuclides identified is less than 0.1% of the limit identified in Commitment d.1.
Qz     <       1.0x 10-3 i       Aj where Qj = radionuclide'activityin resin Aj = pond inventory limit for radionuclide "j"
: 3. The total radionuclide inventory of used powdex resin transferred to the Chemical Treatment Ponds over the previous 13 weeks, shall not exceed 0.4% of the pond radionuclide inventory limit.
Decay of radionuclides may be taken into account in determining inventory levels.
                                        + Qj, < .004 x Aj Qj1 + Qj2 + Qj 3 +- ------
where, Qj     Total inventory of radionuclide j in a transfer n   Number of transfers to the Chemical Treatment Ponds during the previous 13 - week period.
                                -NOTE -------------------------------------------
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.
16.1 1.1 -2                                                 07/12/01 1
 
Radioactive Liquid Effluents 16.11.1 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.
16.1 1.1-3                                 07/12/01 I
 
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.
16.11.1-4                                       07/12/01 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&#xfd; 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.
: b. Corrective action to restore equipment and prevent recurrence.
D. Total radioactive D.1 Submit report to the 30 days inventory of used regional NRC Office powdex resins describing the reason(s)transferred to the for exceeding ihe limit and Chemical Treatment plans for future operation.
D. Total radioactive       D.1 Submit report to the       30 days inventory of used             regional NRC Office powdex resins                 describing the reason(s) transferred to the           for exceeding ihe limit and Chemical Treatment           plans for future operation.
Ponds over previous 13,weeks greater than 0.4% of the pond radionuclide inventory limit.SURVEILLANCE REQUIREMENTS ,SURVEILLANCE FREQUENCY SR 16.11.1.1 N/A N/A 16.11.1-5 07/12/01 1 Radioactive Liquid Effluents 16.11.1 BASES The concentration commitment is provided to ensure that the concentration of radioactive.
Ponds over previous 13,weeks greater than 0.4% of the pond radionuclide inventory limit.
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.
SURVEILLANCE REQUIREMENTS
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 result in the activation of the Oconee 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 II.D of Appendix A to 10 CFR Part 50.16.11.1-6 071/0 Radioactive Liquid Effluents, 16.11.1 The inventory limits of the chemical treatment ponds are based on limiting the consequences of an uncontrolled release of the pond inventory.
                        ,SURVEILLANCE                               FREQUENCY SR 16.11.1.1     N/A                                         N/A 16.11.1-5                                     07/12/01 1
The short term ,rate limit (2 mrem/hr) of 10 CFR 20.1301 is applied to 10 CFR 20.1302 in the following expression:
 
-Ai x 106 JICi x gal < 2 mrem/hr x 8760 hr 1.3 x 10 gal Curie 3785 ml 500 mrem/yr yr 10 x Cj Ai < 1.7x10 6 Cj Where Aj = pond inventory limit for radionuclide "j" (curies)Cj = 10 CFR 20, Appendix B, Table 2, Column 2, concentration radionuclide "j" 1.3 x 106 gal = estimated volume of smaller chemical treatment pond The transfer limits provide assurance that activity input to the CTP will be minimized.
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 result in the activation of the Oconee 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 II.D of Appendix A to 10 CFR Part 50.
16.11.1-6                                       071/0
 
Radioactive Liquid Effluents, 16.11.1 The inventory limits of the chemical treatment ponds are based on limiting the consequences of an uncontrolled release of the pond inventory. The short term ,rate limit (2 mrem/hr) of 10 CFR 20.1301 is applied to 10 CFR 20.1302 in the following expression:
    -Ai       x   106 JICi   x     gal     <   2 mrem/hr     x 8760 hr 1.3 x 10 gal           Curie       3785 ml         500 mrem/yr         yr 10 x Cj 6
Ai < 1.7x10 Cj Where   Aj = pond inventory limit for radionuclide "j" (curies)
Cj = 10 CFR 20, Appendix B, Table 2, Column 2, concentration radionuclide "j" 1.3 x 106 gal = estimated volume of smaller chemical treatment pond The transfer limits provide assurance that activity input to the CTP will be minimized.


==REFERENCES:==
==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 16.1 1.1-7 07/12/01 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.
: 1. 10 CFR Part 20, Appendix B.
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  
: 2. 40 CFR Part 141.
[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:
: 3. 10 CFR Part 50, Appendices A and I.
: i. During any calendar quarter:< 15 mrad for gamma radiation30 mrad for beta radiation ii. During any calendar year:30 mrad for gamma radiation60 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:
: 4. 40 CFR Part 190.
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.
: 5. Offsite Dose Calculation Manual.
2.&#xfd; 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.------------------------------
: 6. Regulatory Guide 1.109.
NOTE ---------------------------------------------
: 7. NUREG-1301 16.1 1.1-7                                     07/12/01 1
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.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:
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.
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.
: 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:
I 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:
: 1. The dose rate limit for noble gases shall be:
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.
                                <500 mrem/yr to the total body
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.
                                <3000 mrem/yr to the skin; and
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 IOCFR20.1302).
: 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.
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 IOCFR20.106 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 10CFR50.36a 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 I0CFR50 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.
: b. Dose
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.
: 1. The air dose due to noble gases released in gaseous effluent from the site shall be limited to the following:
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.
: 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.&#xfd;   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 IOCFR20.1302). 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 IOCFR20.106 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 10CFR50.36a 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 I0CFR50 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==
==11.2 REFERENCES==
:
1   10 CFR Part 20, Appendix 8.
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.16-1 1.2-6 01/31/00 I 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 16.11.1 .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........................................  
: 2. 10 CFR Part 50, Appendices A and I.
------ NOTE- -----------------------
: 3. Regulatory Guide 1.109.
Correction to setpoints determined in accordance with Commitment c may be permitted without declaring the channel inoperable.
: 4. 40 CFR Part 190.
APPLICABILITY:
: 5. Offsite Dose Calculation Manual.
According to Table 16.11.3-1 and Table 16.11.3-2.
16-1 1.2-6                     01/31/00 I
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.
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.2 Suspend release of Immediately effluent monitored by the channel.16.11.3-1 12/04/07 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.
: 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 16.11.1 .a are not exceeded.
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.
: 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.
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.1 6.11.3-2 12/04/07 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 limit of detection of at least 10-7 I tCi/ml.16.11.3-3 12/04/07 1 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME G. As required by Required Action B.1 and referenced in Table 16.11.3-1. (Liquid Radwaste Effluent Line Flow Rate Monitor)---- --------------
: c.       The setpoints shall be determined in accordance with the methodology described in the ODCM and shall be recorded.
NOTE ------------------
                      ....................................... NOTE-Correction to setpoints determined in accordance with Commitment c may be permitted without declaring the channel inoperable.
Not required during short, controlled outages of liquid effluent monitoring  
APPLICABILITY:         According to Table 16.11.3-1 and Table 16.11.3-2.
'instrumentation.
ACTIONS CONDITION                           REQUIRED ACTION                   COMPLETION TIME A. Alarm/trip setpoint less       A.1           Declare channel             Immediately conservative than                           inoperable.
Short controlled outages are defined as planned removals from service for durations not to exceed 1 hour, for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures.
required for one or more effluent                 OR monitoring instrument channels.                     A.2           Suspend release of         Immediately effluent monitored by the channel.
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.-------------------------------------------
16.11.3-1                                         12/04/07 1
G.1 Suspend release of radioactive effluents by this pathway.OR G.2 Estimate flow rate during actual releases.Immediately Immediately AND Once per 4 hours thereafter 16.11.3-4 12/04/07 I Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION { COMPLETION TIME H. As required by Required Action B.1 and referenced in Table 16.11.3-1. (RIA-35, #3 Chemical Treatment Pond Composite Sampler and Sampler Flow Monitor (Turbine Building Sumps Effluent))
 
--- ---------------
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.
NOTE ------------------
AND B.2   Restore the                 30 days instrument(s) to OPERABLE status.
Not required during short, controlled outages of liquid effluent monitoring instrumentation.
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.
Short controlled outages are defined as planned removals from service for durations not to exceed 1 hour, for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures.
AND C.2     Restore the               30 days instrument(s) to OPERABLE status.
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 radioactive effluents by this pathway.OR H.2 Collect and analyze grab samples for gross radioactivity (beta and/or gamma) at a lower limit of detection of at least 10-7 lCi/ml.Immediately Immediately AND Once per 12 hours thereafter 16.11.3-5 12/04/07 I Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME As required by Required Action C.1 and referenced in Table 16.11.3-2 for effluent releases from waste gas tanks (RIA-37, RIA-38)or containment purges (RIA-45).--------------
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.
NOTE---------
16.11.3-2                                         12/04/07 1
Not required during short, controlled outages of gaseous effluent monitoring instrumentation.
 
Short controlled outages are defined as planned removals from service for durations not to exceed 1 hour, for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures.
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.
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 independent samples.AND 1.1.2 Conduct two independent data entry checks for release rate calculations AND 1.1.3 Conduct two independent valve lineups of the effluent pathway.OR Prior to initiating subsequent release Prior to initiating subsequent release Prior to initiating subsequent release Immediately 11.2 Suspend release of radioactive effluents by this pathway.16.11.3-6 12/04/07 1 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME J. As required by Required Action C.1 and referenced in Table 16.11.3-2. (Effluent Flow Rate Monitor (Unit Vent, Containment Purge, Interim Radwaste Exhaust, Hot Machine Shop Exhaust, Radwaste Facility Exhaust, Waste Gas Discharge))
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.
NOTE ----------
F. As required by Required F.1       Suspend release of         Immediately Action B.1 and                     radioactive effluents by referenced in Table               this pathway.
Not required during short, controlled outages of gaseous effluent monitoring instrumentation.
16.11.3-1. (RIA-54)
Short controlled outages are defined as planned removals from service for durations not to exceed 1 hour, for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures.
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 limit of detection I tCi/ml.
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 radioactive effluents by this pathway.OR J.2 Immediately Immediately AND Once per 4 hours thereafter Estimate flow rate 16.11.3-7 12/04/07 1 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION R REQUIRED ACTION COMPLETION TIME K. As required by Required Action C.1 and referenced in Table 16.11.3-2. (RIA-45, RIA-53, 4RIA-45)------------
of at least 10-7 16.11.3-3                                         12/04/07 1
NOTE ---------N------Not required during short, controlled outages of gaseous effluent monitoring instrumentation.
 
Short controlled outages are defined as planned removals from service for durations not to exceed 1 hour, for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures.
Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION                             REQUIRED ACTION                                   COMPLETION TIME G. As required by Required ---- -------------- NOTE ------------------
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.-------------------------------------------
Action B.1 and          Not required during short, referenced in Table    controlled outages of liquid 16.11.3-1. (Liquid      effluent monitoring '
K.1 Suspend release of radioactive effluents by this pathway.OR K.2.1 Collect grab sample.AND Immediately Immediately ,AND Once per 8 hours 24 hours from collection of sample K.2.2 Analyze grab samples for gross activity (beta and/or gamma).16.11.3-8 12/04/07 I  
Radwaste Effluent Line  instrumentation. Short controlled Flow Rate Monitor)      outages are defined as planned removals from service for durations not to exceed 1 hour, 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.
-Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME L. As required by Required Action C.1 and referenced in Table 16.11.3-2. (Unit Vent Monitoring Iodine Sampler, Unit Vent Monitoring Particulate Sampler, Interim Radwaste Building Ventilation Monitoring Iodine Sampler, Interim Radwaste Building Ventilation Monitoring Particulate Sampler, Hot Machine Shop Iodine Sampler, Hot Machine Shop Particulate Sampler, Radwaste Facility Iodine Sampler, Radwaste Facility Particulate Sampler)---- --------------
G.1                      Suspend release of                    Immediately radioactive effluents by this pathway.
NOTE----------
OR G.2                      Estimate flow rate                    Immediately during actual releases.
Not required during short, controlled outages of gaseous effluent monitoring instrumentation.
AND Once per 4 hours thereafter 16.11.3-4                                                     12/04/07 I
Short controlled outages are defined as planned removals from service for durations not to exceed 1 hour, 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.-------------------------------------------
Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION                     REQUIRED ACTION                   { COMPLETION TIME H. As required by Required --- --------------- NOTE ------------------
L.1 Suspend release of radioactive effluents by this pathway.OR L.2.1 ---------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 hour, 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.
The collection time of each sample shall not exceed 7 days.Collect samples continuously using auxiliary sampling equipment.
H.1             Suspend release of           Immediately radioactive effluents by this pathway.
AND L.2.2 Analyze each sample.Immediately Immediately 48 hours from end of each sample collection 16.11.3-9 12/04/07 1 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME M. As required by Required Action C.1 and referenced in Table 16.11.3-2 for effluent from ventilation system or condenser air ejectors. (RIA-40)--------NOTE ---------Not required during short, controlled outages of gaseous effluent monitoring instrumentation.
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 hours of at least 10-7 lCi/ml. thereafter 16.11.3-5                                         12/04/07 I
Short controlled outages are defined as planned removals from service for durations not to exceed 1 hour, 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.-------------------------------------------
Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION                     REQUIRED ACTION                   COMPLETION TIME As required by Required -------------- NOTE---------
M.1 Continuously monitor release through the unit vent.SOR M.2 Suspend release of radioactive effluents by this pathway.OR M.3.1 Collect grab sample.AND, M.3.2 Analyze grab sample for gross activity (beta and/or gamma).Immediately Immediately Immediately AND Once per 8 hours 24 hours from collection of grab sample 16.11.3-10 12/04/07 .1 Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.3.1-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 hour, 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.
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.During each release via this pathway SR 16.11.3.2-NOTE ----------------------------
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.
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 hours SR 16.11.3.3 Perform Source Check. 24 hours SR 16.11.3.4 Perform Source Check. 31 days SR 16.11.3.5 Perform Source Check. 92 days 16.11.3-11 12/04/0.7 1
OR 11.2           Suspend release of           Immediately radioactive effluents by this pathway.
Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE FREQUENCY SR 16.11.3.6----------
16.11.3-6                                         12/04/07 1
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------------
Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION                 REQUIRED ACTION                   COMPLETION TIME J. As required by Required --- - ------------
NOTE ---------------
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).Perform CHANNEL FUNCTIONAL TEST.92 days SR16.11.3.8 Perform CHANNEL FUNCTIONAL TEST. 92 days 16.11.3-12 12/04/07 1 Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE FREQUENCY SR 16.11.3.9---------------
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 Purge, Interim         removals from service for Radwaste Exhaust, Hot   durations not to exceed 1 hour, 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.
NOTE ---------------------------
J.1        Suspend release of           Immediately radioactive effluents by this pathway.
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.
OR J.2        Estimate flow rate          Immediately AND Once per 4 hours thereafter 16.11.3-7                                          12/04/07 1
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.)
 
Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION          R                REQUIRED ACTION                                    COMPLETION TIME K. As required by Required            ------------    ---------
N------
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 hour, 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 hours AND K.2.2                     Analyze grab samples                   24 hours from collection for gross activity (beta                 of sample and/or gamma).
16.11.3-8                                                       12/04/07 I
 
                                                                        -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 hour, 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)
L.1                        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 hours from end of each sample collection 16.11.3-9                                                      12/04/07 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 hour, 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.
SOR M.2                       Suspend release of                    Immediately radioactive effluents by this pathway.
OR M.3.1                     Collect grab sample.                    Immediately AND Once per 8 hours AND, M.3.2                    Analyze grab sample for                24 hours from collection gross activity (beta                    of grab sample and/or gamma).
16.11.3-10                                                        12/04/07 .1
 
Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE                                            FREQUENCY 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.
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 hours SR 16.11.3.3 Perform Source Check.                                  24 hours SR 16.11.3.4 Perform Source Check.                                    31 days SR 16.11.3.5  Perform Source Check.                                  92 days 16.11.3-11                                          12/04/0.7 1
 
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.
SR16.11.3.8  Perform CHANNEL FUNCTIONAL TEST.                     92 days 16.11.3-12                                      12/04/07 1
 
Radioactive Effluent Monitoring Instrumentation 16.11.3 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.
12 months Perform CHANNEL CALIBRATION.
SR 16.11.3.10 Perform CHANNEL CALIBRATION.
SR 16.11.3.10 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 hours prior to each release via associated pathway 16.11.3-13                                       12/04/07 1
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 hours prior to each release via associated pathway 16.11.3-13 12/04/07 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 Monitors Providing Automatic Termination of Release a. Liquid Radwaste Effluent Line Monitor, RIA-33 b. Turbine Building Sump, RIA-54 2, Monitors not Providing Automatic Termination of Release Low Pressure Service Water RIA-35 3. Flow Rate Measuring Devices a. Liquid Radwaste Effluent Line Flow Rate Monitor (0LW CR0725 or OLW SS0920)b. Liquid Radwaste Effluent Line Minimum Flow* Device c. Turbine Building Sump Minimum Flow Device d. Low Pressure Service Water Minimum Flow Device 1 At all times SR 16.11.3.1 SR 16.11.3.3 SR 16.11.3.6 SR 16.11.3.9 SR 16.11.3.2 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9 E F 1 At all times At all times SR 16.11.3.2 SR 16.11.3.4 SR 16.11.3.7 SR 16.11,3.9 H 1 At all times NA NA NA NA NA NA SR 16.11.3.1 SR 16.11.3.10 SR 16.11.3.1 SR 16.11.3.10 SR 16.11.3.1 SR 16.11.3.10 SR 16.11.3.1 SR 16.11.3.10 G NA NA NA 16.11.3-14 12/04/07 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 (at 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.
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 Monitors Providing Automatic Termination of Release
It no hydro units are operating, leakage tlow will be assumed to be 38 cfs based on historical data.16.11.3-15 1/40 12/04/07 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 1. Unit Vent Monitoring System a. Noble Gas Activity Monitor Providing Alarm and Automatic Termination of Containment Purge Release (RIA-45 -Purge Isolation Function)b. Noble Gas Activity Monitor Providing Alarm.(RIA-45 -Vent Stack Monitor Function)c. Iodine Sampler d. Particulate Sampler e. Effluent Flow Rate Monitor (Unit Vent Flow)(GWD CR0037 for Unit 2)(MSC CR0O01 for Units 1& 3)t. Sampler Flow Rate Monitor (a) (Annunciator)
: a. Liquid Radwaste Effluent     1                  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
: g. Effluent Flow Rate Monitor (Containment Purge) (PR CR0082 for Unit 2)(MSC CR0001 for Units 1 & 3)h. CSAE Off Gas Monitor (RIA-40)2. Interim Radwaste Building Ventilation Monitoring System a. Noble Gas Activity Monitor (RIA -53)b. Iodine Sampler c. Particulate Sampler d. Effluent Flow Rate Monitor (Interim Radwaste Exhaust)(GWD FT0082)e. Sampler Flow Rate Monitor(a) (Annunciator) 1 At All Times SR 16.11.3.2 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9 At all times At All Times At All Times At All Times 1 1 1 SR 16.11.3.2 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9 SR 16.11.3.2 SR 16.11.3.2 SR 16.11.3.2 SR 16.11.3.10 K L L j 1 At All Times SR 16.11.3.2 SR 16.11.3.10 During Containment Purge Operation During Operation of CSAE At All Times At All Times At All Times At All Times SR 16.11.3.2 SR 16.11.3.10 SR 16.11.3.2 SR 16.11.3.5 SR 16.11.3.8 SR 16.11.3.9 SR 16.11.3.2 SR 16.11.3.4 SR 16.11,3.7 SR 16.11.3.9 SR 16.11.3.2 SR 16.11.3.2 SR 16.11.3.2 SR 16.11.3.10 SR 16.11.3.2 SR 16.11.3.10 NA M M K L L 1 1 1 1 At All Times NA 16.11.3-16 12/04/07 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 b. Particulate Sampler c. Effluent Flow Rate Monitor (Hot Machine Shop Exhaust)(Totalizer)
: 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
: d. Sampler Flow Rate Monitor (a) (Annunciator)
: 3. Flow Rate Measuring Devices
: 4. Radwaste Facility Ventilation Monitoring System a. Noble Gas Activity Monitor (4-RIA-45)
: 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. Iodine Sampler c. Particulate Sampler d. Effluent Flow Rate Monitor (Radwaste Facility Exhaust) (OVS CR2060)e. Sampler Flow Rate Monitor (a) (Annunciator)
: b. Liquid Radwaste Effluent    NA                  NA              SR 16.11.3.1     NA Line Minimum Flow                                                SR 16.11.3.10
: 5. Waste Gas Holdup Tanks a. Noble Gas Activity Monitor -Providing Alarm and Automatic Termination of Release (RIA-37,-38)b
      *Device
: b. Effluent Flow Rate Monitor (Waste Gas Discharge Flow) (MSC CRO001)At All Times At All Times At All Times SR 16.11.3.2 SR 16.11.3.2 SR 16.11.3.2 SR 16.11.3.10 SR 16.11.3.2 SR 16.11.3.10 L L J NA At All Times At All Times At All Times At AliTimes At All Times 1 SR 16.11.3.2 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9 SR 16.11.3.2 SR 16.11.3.2 SR 16.11.3.2 SR 16.11.3.10 SR 16.11.3.2 SR 16.11.3.10 SR 16.11.3.1 SR 16.11.3.6 SR 16.11.3.9 SR 16.11.3.12 SR 16.11.3.1 SR 16.11.3.10 K L L J NA 1 At All Times 1 During Waste Gas Holdup Tank Releases During Waste Gas Holdup Tank Releases 1 J (a)Alarmsindicating 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 12/04/07 1 Radioactive Effluent Monitoring Instrumentation 16.11.3 BASES The radioactive liquid effluent instrumerhtation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases.
: c. Turbine Building Sump        NA                NA              SR 16.11.3.1     NA Minimum Flow Device                                                SR 16.11.3.10
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.
: 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                                         12/04/07 1
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 1 6.11.2. 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 hours end every 12 hours upon RIA removal from service. SLC 16.1 1.3 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, durihg 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 hour. One hour is the accepted reasonable time to initiate collect and change samples.Therefore.
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
for the defined short, controlled outages (not to exceed 1 hour), 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.
: e. Keowee Hydroelectric             NA                     NA                       SR 16-11.3.11         NA Tailrace Discharge (at
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.
: 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. It no hydro units are operating, leakage tlow will be assumed to be 38 cfs based on historical data.
16.11.3-15                                                           1/40 12/04/07 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
: 1. Unit Vent Monitoring System
: a. Noble Gas Activity               1                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                               At all 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                   1                At All Times  SR 16.11.3.2          L 1
: d. Particulate Sampler                               At All Times  SR 16.11.3.2          L 1
: e. Effluent Flow Rate                                 At All Times  SR 16.11.3.2          j Monitor (Unit Vent Flow)                                         SR 16.11.3.10 (GWD CR0037 for Unit 2)(MSC CR0O01 for Units 1& 3)
: t. Sampler Flow Rate                                 At All Times  SR 16.11.3.2          NA Monitor (a) (Annunciator)                                       SR 16.11.3.10
: g. Effluent Flow Rate               1          During Containment SR 16.11.3.2          M Monitor (Containment                           Purge Operation  SR 16.11.3.10 Purge) (PR CR0082 for Unit 2)(MSC CR0001 for Units 1 & 3)
: h. CSAE Off Gas Monitor                           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
: b. Iodine Sampler                    1                At All Times SR 16.11.3.2           L 1
: 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 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                                          12/04/07 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                                          At All Times       SR 16.11.3.2         L
: b. Particulate Sampler                                    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                                      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 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 AliTimes        SR 16.11.3.2          L
: d. Effluent Flow Rate                1                    At All Times        SR 16.11.3.2         J Monitor (Radwaste                                                          SR 16.11.3.10 Facility Exhaust) (OVS CR2060)
: e. Sampler Flow Rate                  1                    At All Times        SR 16.11.3.2         NA Monitor (a)(Annunciator)                                                    SR 16.11.3.10
: 5. Waste Gas Holdup Tanks
: a. Noble Gas Activity                1               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 Termination of Release                                                      SR  16.11.3.12 (RIA-37,-38)b
: b. Effluent Flow Rate                 1              During Waste Gas        SR 16.11.3.1          J Monitor (Waste Gas                              Holdup Tank Releases      SR 16.11.3.10 Discharge Flow) (MSC CRO001)
(a)Alarmsindicating 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                                                12/04/07 1
 
Radioactive Effluent Monitoring Instrumentation 16.11.3 BASES The radioactive liquid effluent instrumerhtation 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 1 6.11.2. 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 hours end every 12 hours upon RIA removal from service. SLC 16.1 1.3 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, durihg 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 hour. One hour is the accepted reasonable time to initiate collect and change samples.
Therefore. for the defined short, controlled outages (not to exceed 1 hour), 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:==
==REFERENCES:==
: 1. 10 CFR 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 12/04/07 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.
: 1. 10 CFR Part 20.
APPLICABILITY:
: 2. 10 CFR Part 50, Appendix A.
At all times ACTIONS_________
: 3. Offsite Dose Calculation Manual.
CONDITION REQUIRED ACTION COMPLETION TIME A. NA A.1 NA NA SURVEILLANCE REQUIREMENTS
: 4. UFSAR, Section 7.2.3.4.
_________SURVEILLANCE FREQUENCY SR 16.11.4.1 N/A N/A 16.11.4-1 16.11.4-111/10/04 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 Condensate Test Tank, Condensate Monitoring Tank, Laundry-Hot Shower Tank, Waste and Recycle Monitor Tanks a. Principal Gamma Emitters(c) including Dissolved Noble Gases Composite Grab Sample prior to release of each batch(h) .<5E-06 pCi/ml (Ce- 144)<5E-07 pICi/mI (Other Gamma Nuclides)<1 E-05 gCi/ml (Dissolved Gases)<1E-06 pCi/ml (1-131)b. Radiochemical Analysis Sr-89 and Sr-90 c. Tritium Quarterly from all composited batches(f)
16.11.3-18                                         12/04/07 1
Monthly Composite Monthly Composite Continuous monitor, weekly sample(e)<5E-08 pCi/ml<1 E-05 MCi/ml d.a.Gross Alpha Activity Iodine Spectrum (a)2. Unit Vent Sampling (includes Waste Gas Decay Tanks, Reactor Building Purges, Auxiliary-Building Ventilation, Spent Fuel Pool Ventilation, Air Ejectors)<1E-07 IpCi/ml< 1E-10 pCi/cc (I- 133)0)<1E-12 pCi/cc (I-131)0)b. Particulates (a)i. Ce-144 & Mo-99 ii. Other Principle Gamma Emitters (d)iii. Gross Alpha Activity iv. Radiochemical Analysis Sr-89, Sr-90 c. Gases by Principle Gamma Emitters(d)
 
: d. Tritium a. Principle Gamma Emitters(d)
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.
Weekly Composite(e)
APPLICABILITY:     At all times ACTIONS_________
Weekly Composite(e)
CONDITION                   REQUIRED ACTION                 COMPLETION TIME A. NA                         A.1 NA                         NA SURVEILLANCE REQUIREMENTS                                       _________
Monthly, using composite samples of one week Quarterly Composite Weekly Grab Sample Weekly Grab Sample Grab Sample prior to release of each batch Grab Sample prior to release of each batch Grab sample each purge Grab sample each purge<5E-10 VCi/cc(j)<1E-1i Ci/cc(j)<1E-11 i.Ci/cc<1E:I i gaCicc<1 E-04 iCVcc<1 E-06 pCi/cc 3. Waste Gas Decay Tank b. Tritium<1 E-04 t[Ci/cc (gases)<1E-10 p.Ci/cc (particulates and iodines)<5E-09 p.Ci/cc (Ce-1i44 and Mo-99)<1 E-06 pCi/cc<1 E-04 pCi/cc (gases)< 1 E- 10 p.Ci/cc (particulates and iodines)<5E-09 pCi/cc (Ce-144 and Mo-99)4. Reactor Building a. Principle Gamma Emitters(d)
SURVEILLANCE                                      FREQUENCY SR 16.11.4.1     N/A                                           N/A 16.11.4-1                                     16.11.4-111/10/04
: b. Tritium<1 E-06 gCi/cc 16.11.4-2 11110104 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. Backwash Receiving Tanks 6. #3 Chemical Treatment Pond Effluent(')
 
Principle Gamma Emitters including dissolved Noble Gases a. Principle Gamma Emitters(c)
Operational Safety Review 16.11.4
: b. 1-131 c. Tritium d. Gross Alpha Activity e. Sr-89 & Sr-90 f. Dissolved and Entrained gases (Gamma Emitters)Grab Sample pdor to release of each batch Weekly Continuous Composite(g)
                                                            -Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program Item                       Check                         Frequency                 Lower Limit of Detection (b) of Lab Analysis for Waste Condensate Test     a.     Principal Gamma       Composite Grab Sample     <5E-06 pCi/ml   (Ce-144)
Weekly Continuous Composite(g)
Tank, Condensate            Emitters(c) including prior to release of each  <5E-07 pICi/mI   (Other Gamma Nuclides)
Monthly Continuous Composite(g)
Monitoring Tank,            Dissolved Noble      batch(h)      .          <1 E-05 gCi/ml   (Dissolved Gases)
Monthly Continuous Composite(g)
Laundry-Hot                  Gases                                          <1E-06 pCi/ml   (1-131)
Quarterly Continuous Composite(g)
Shower Tank, Waste and Recycle Monitor Tanks
Monthly Grab NA<5E-07 pCilml<1 E-06 pCi/ml<1-E-05 pCi/ml<1E-07 gCi/ml<5E-08 pCi/ml<1 E-05 pCVml Radwaste Facility Ventilation a.b.Iodine Spectrum(a)
: b.     Radiochemical         Quarterly from all        <5E-08 pCi/ml Analysis Sr-89 and   composited batches(f)
Particulate(a)
Sr-90
Continuous monitor, weekly sample(e)(1-133) <1E-09 ipCVcc (1-131) <1E-11 igCVcc i. Ce-1 44 and Mo-99 ii. Other Principle Gamma Emitters(d) iii. Gross Alpha Activity iv. Radiochemical Analysis Sr-89, Sr-90 Weekly Composite(e)
: c.     Tritium               Monthly Composite         <1 E-05 MCi/ml
Weekly Composite(e)
: d.     Gross Alpha Activity Monthly Composite        <1E-07 IpCi/ml
Monthly, using composite samples of one week Quarterly Composite Weekly Grab Sample<5E-10 ViCicc(j)<1E-1 1 liCi/cc(j)
: 2. Unit Vent Sampling   a.      Iodine Spectrum (a)  Continuous monitor,       < 1E-10 pCi/cc (I-133)0)
<i1E-1 I <1E-11 pCilcc<1E-04 lxCicc c. Gases by Principle Gamma(d)Emitters d. Tritium Weekly Grab Sample<1 E-06 pCi/cc 16.11.4-3 11/10/04 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 8. Hot Machine Shop Ventilation
(includes Waste                                    weekly sample(e)         <1E-12 pCi/cc (I-131)0)
: a. Iodine Spectrum Weekly Sample(e)(1-133) <1E-10 pCi/cc(j)(1-131) <1 E-12 i+/-Ci/ccU)b.Particulate Ce-144 and Mo-99 ii. Other Principle Gamma Emitters (d)iii. Gross Alpha Activity iv. Radiochemical Analysis Sr-89, Sr-90 c. Gases by Principle Gamma Emitters d. Tritium Weekly Composite(e)
Gas Decay Tanks, Reactor Building Purges, Auxiliary    b.     Particulates (a)
Weekly Composite(e)
    -Building Ventilation, Spent Fuel Pool        i.       Ce-144 & Mo-99     Weekly Composite(e)      <5E-10 VCi/cc(j)
Monthly, using composite samples of one week.Quarterly Composite NA NA<5E-10 ttCi/cc(j)
Ventilation, Air Ejectors) ii. Other Principle   Weekly Composite(e)       <1E-1i    Ci/cc(j)
<1 E-1 I pCi/ccaj)<1 E-1 1 liCVcc<1E-11 VCi/cc NA NA Interim Radwaste Building Ventilation a.Iodine Spectrum Weekly sample(e)(1-133) <1 E-10 .CVcc(j)(1-131) <1E-12 pCVcc(j)b.i.Particulate Ce-144 and Mo-99 ii. Other Principle Gamma Emitters(d) iii. Gross Alpha Activity iv. Radiochemical Analysis Sr-89, Sr-90 c. Gases by Principle Gamma(d)Emitters d. Tritium Weekly Composite(e)
Gamma Emitters (d) iii. Gross Alpha        Monthly, using composite <1E-11 i.Ci/cc Activity            samples of one week iv. Radiochemical      Quarterly Composite       <1E:I i gaCicc Analysis Sr-89, Sr-90
Weekly Composite(e)
: c. Gases by Principle    Weekly Grab Sample       <1 E-04 iCVcc Gamma Emitters(d)
Monthly, using composite samples of one week Quarterly Composite Weekly Grab Sample Weekly Grab Sample<5E-10 pCVcc(j)<1E-11 i+/-CVcc<1E-11 [LCi/cc<1 E-04 iVCVcc<1 E-06 VCi/cc 16.11.4-4 11/10/04 1 Operational Safety Review 16.11.4 (a) Samples shall be changed at least once every 24 hours and analysis shall be completed within 48 hours after changing ion or after removal from sampler).(b) The LLD is defined for purposes of these commitments as the smallest concentration 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):
: d. Tritium                Weekly Grab Sample       <1 E-06 pCi/cc
LLD= 4.66 sb E x V x 2.22E06 x Y x exp (.XAt)Where: LLD is the "a priori" lower limit of detection as defined above (as micro Curies per unit mass orvolume),)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), is the radioactive decay constant for the particular nuclideis the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).
: 3. Waste Gas Decay      a. Principle Gamma        Grab Sample prior to      <1 E-04 t[Ci/cc (gases)
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.
Tank                          Emitters(d)            release of each batch    <1E-10 p.Ci/cc (particulates and iodines)
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.
                                                                                    <5E-09 p.Ci/cc (Ce-1i44 and Mo-99)
It should be recognized that the LLD Is an a Pdriori (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:
: b. Tritium               Grab Sample prior to      <1 E-06 pCi/cc release of each batch
Mn-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 g/CVml. This list does not mean that only these nuclides are to be considered.
: 4. Reactor Building      a.      Principle Gamma      Grab sample each purge    <1 E-04 pCi/cc (gases)
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:
Emitters(d)                                    < 1E- 10 p.Ci/cc (particulates and iodines)
Kr-87. Kr-88, Xe-133. Xe-133m, Xe-135. and Xe-138 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.
                                                                                    <5E-09 pCi/cc (Ce-144 and Mo-99)
This list does not mean that only these nuclides are to be detected and reported.
: b.      Tritium                Grab sample each purge  <1 E-06 gCi/cc 16.11.4-2                                                    11110104      1
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 11/10/04 I Operational Safety Review 16.11.4 (h) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling 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. Inpu~t flow during the continuous release.0) When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10.16.11.4-6 16.1.4-611/10/04 1
 
Operational Safety Review 16.11.4 BASES N/A  
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. Backwash Receiving  Principle Gamma Emitters Grab Sample pdor to      NA Tanks                including dissolved Noble release of each batch Gases
: 6.  #3 Chemical          a. Principle Gamma    Weekly Continuous        <5E-07 pCilml Treatment Pond            Emitters(c)        Composite(g)
Effluent(')
: b.      1-131            Weekly Continuous        <1 E-06 pCi/ml Composite(g)
: c.       Tritium          Monthly Continuous      <1-E-05 pCi/ml Composite(g)
: d.       Gross Alpha      Monthly Continuous      <1E-07 gCi/ml Activity        Composite(g)
: e.      Sr-89 &Sr-90    Quarterly Continuous    <5E-08 pCi/ml Composite(g)
: f.       Dissolved and    Monthly Grab            <1 E-05 pCVml Entrained gases (Gamma Emitters)
Radwaste Facility a.      Iodine          Continuous monitor,      (1-133) <1E-09 ipCVcc Ventilation                Spectrum(a)     weekly sample(e)         (1-131) <1E-11 igCVcc
: b.      Particulate(a)
: i.      Ce-1 44 and Mo- Weekly Composite(e)      <5E-10 ViCicc(j) 99 ii. Other Principle  Weekly Composite(e)     <1E-1 1 liCi/cc(j)
Gamma Emitters(d) iii. Gross Alpha      Monthly, using composite <i1E-1 I g*CVcc Activity        samples of one week iv. Radiochemical    Quarterly Composite      <1E-11 pCilcc Analysis Sr-89, Sr-90
: c.       Gases by        Weekly Grab Sample        <1E-04 lxCicc Principle Gamma(d)
Emitters
: d.       Tritium        Weekly Grab Sample        <1 E-06 pCi/cc 16.11.4-3                                                  11/10/04      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
: 8. Hot Machine Shop    a. Iodine Spectrum    Weekly Sample(e)          (1-133) <1E-10 pCi/cc(j)
Ventilation                                                              (1-131) <1 E-12 i+/-Ci/ccU)
: b.       Particulate Ce-144 and Mo-  Weekly Composite(e)      <5E-10 ttCi/cc(j) 99 ii.       Other Principle  Weekly Composite(e)      <1 E-1 I pCi/ccaj)
Gamma Emitters (d)
                                                                              <1 E-1 1 liCVcc iii.      Gross Alpha      Monthly, using composite Activity        samples of one week.
iv.      Radiochemical    Quarterly Composite      <1E-11 VCi/cc Analysis Sr-89, Sr-90
: c.       Gases by        NA                        NA Principle Gamma Emitters
: d.       Tritium          NA                        NA Interim Radwaste  a.       Iodine Spectrum  Weekly sample(e)           (1-133) <1 E-10 .CVcc(j)
Building                                                              (1-131) <1E-12 pCVcc(j)
Ventilation
: b.       Particulate
: i.      Ce-144 and Mo-   Weekly Composite(e)       <5E-10 pCVcc(j) 99 ii.     Other Principle Weekly Composite(e)
Gamma Emitters(d) iii. Gross Alpha     Monthly, using composite  <1E-11 i+/-CVcc Activity        samples of one week iv.      Radiochemical    Quarterly Composite      <1E-11 [LCi/cc Analysis Sr-89, Sr-90
: c.       Gases by         Weekly Grab Sample        <1 E-04 iVCVcc Principle Gamma(d)
Emitters
: d.       Tritium         Weekly Grab Sample         <1 E-06 VCi/cc 16.11.4-4                                                  11/10/04       1
 
Operational Safety Review 16.11.4 (a)   Samples shall be changed at least once every 24 hours and analysis shall be completed within 48 hours after changing ion or after removal from sampler).
(b)   The LLD is defined for purposes of these commitments as the smallest concentration 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:
LLD is the "a priori" lower limit of detection as defined above (as micro Curies per unit mass orvolume),
                                                                                                                                )
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),
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 Pdriori (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-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 g/CVml. 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-133. Xe-133m, Xe-135. and Xe-138 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 Inwhich 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 inliquid effluents, samples shall be collected continuously inproportion to the rate of flow of the effluent stream. Prior to analysis, all samples taken for the composite shall be thoroughly mixed inorder for the composite sample to be representative of the effluent release.
16.11.4-5                                         11/10/04       I
 
Operational Safety Review 16.11.4 (h)     A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analysis, each batch shall be isolated, and then thoroughly mixed; to assure representative sampling.
(i)     Acontinuous release is the discharge of liquid wastes of a non-discrete volume, e.g., from a volume of a system that has an. Inpu~t flow during the continuous release.
: 0) When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10.
16.11.4-6                                         16.1.4-611/10/04 1
 
Operational Safety Review 16.11.4 BASES N/A


==REFERENCES:==
==REFERENCES:==


N/A 16.11.4-7 11/10/04 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.
N/A 16.11.4-7 11/10/04   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 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 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.
* 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:
APPLICABILITY:     At all times 16.11.5-1                                         10/30/02 1
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.
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.
B. A solidification test as B.1 Suspend solidification of Immediately described in the PCP the batch under test and fails to verify follow PCP guidance for Solidification.
satisfied.
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.
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.
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.
B. A solidification test as 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.
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.
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.
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.
16.11.5-2                                         10/30/02 I
every tenth batch of each type of radioactive waste to be solidified for disposal at a 10 CFR 61 disposal site.I 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 1 OCFR61 waste form criteria for solidified and dewatered radioactive wastes.
 
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.
I 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:==
==REFERENCES:==
: 1. 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities".
: 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".
: 2. 10 CFR Part 50, Appendix A.
: 4. 10 CFR61, "Licensing Requirements for Land Disposal of Radioactive Waste".5. 10 CFR71, "Packaging and Transportation of Radioactive Materials".
: 3. 10 CFR20, "Standards for Protection Against Radiation".
: 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".16.11.5-4 10/30/02 1 Radiological Environmental Monitoring 16.11.6 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.6 Radiological Environmental Monitoring COMMITMENT  
: 4. 10 CFR61, "Licensing Requirements for Land Disposal of Radioactive Waste".
: 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.
: 5. 10 CFR71, "Packaging and Transportation of Radioactive Materials".
: 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 I nterlaboratory 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.-------------------------------------------
: 6. DPCo Process Control Program Manual.
NOTE ---------------------------------------------
: 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)".
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.
: 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".
These new locations will be identified in the Annual Radioactive Effluent Release Report.APPLICABILITY:
16.11.5-4                                       10/30/02 1
At all times 16.11.6-1 02/01/051 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 than a location from deleted from this which samples are monitoring program currently being after October 31 of the obtained.
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.
year in which this land use census was conducted.
: 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.
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.I 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.
: 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.
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.
: d.         The results of the land use census shall be included in the Annual Radiological Environmental Operating Report.
16.11.6-3 102/01/05 1
                      ------------------------------------------- NOTE ---------------------------------------------
Radiological Environmental Monitoring 16.11.6 Table 16.11.6-1 Radiological Environmental Monitoring Program Number of Sampling and Collection Exposure Pathway and/or Sample Time and Frequency of Analysis Sample Frequency (d)Locations (b)1. AIRBORNE Radioiodine and Particulates
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.
: 2. DIRECT RADIATION 5 Continuous sampler operation with sample collection weekly, or more frequently if required by dust loading.40 Quarterly.
APPLICABILITY:       At all times 16.11.6-1                                                   02/01/051
Radioiodine canister: 1-131 analysis weekly. Particulate sampler: Gross beta radioactivity analysis following filter change; and gamma isotopic analysis of composite (by location) quarterly. (c)Gamma dose quarterly.
 
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                                         102/01/05 1
 
Radiological Environmental Monitoring 16.11.6 Table 16.11.6-1 Radiological Environmental Monitoring Program Number of     Sampling and Collection Exposure Pathway and/or   Sample                                 Time and Frequency of Analysis Sample         Locations (b)      Frequency (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
: 3. WATERBORNE
: a. Surface 2 Composite (a) sample over a 1-month period.3 Composite (a) sample over a 1-month period.Gamma isotopic analysis monthly.Composite for tritium analysis quarterly.
: a. Surface                 2       Composite (a) sample       Gamma isotopic analysis monthly.
Composite for gross beta and gamma isotopic analyses monthly.Composite for tritium analysis quarterly.
over a 1-month period.
: b. Drinking c. Sediment from Shoreline 2 Semiannually.
Composite for tritium analysis quarterly.
Gamma isotopic analysis semiannually.
: b. Drinking                3      Composite (a) sample      Composite for gross beta and gamma over a 1-month period.      isotopic analyses monthly.
16.11.6-4 02/01/05 1 Radiological Environmental Monitoring 16.11.6 Table 16.11.6-1 Radiological Environmental Monitoring Program Number of Smln n olcin Tm n rqec fAayi Exposure Pathway and/or me Sampling and Collection SapeSample Frequency (d) Time and Frequency of Analysis Sample Locations (b)4. INGESTION a. Milk 4(e) Semimonthly when Gamma isotopic and 1-131 analysis animals are on pasture; semimonthly when animals are on monthly at other times. pasture; monthly at other times.b. Fish 2 Semiannually.
Composite for tritium analysis quarterly.
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 hours.(b) Sample locations are identified in the ODCM.(c) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours 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.
: c. Sediment from         2       Semiannually.               Gamma isotopic analysis Shoreline                                                  semiannually.
If the 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.
16.11.6-4                                                 02/01/05 1
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.
 
I 16.11.6-5 02/01/05 1 Radiological Environmental Monitoring 16.11.6 Detection (LLD) (a) (c)Table 16.11.6-2 Maximum Values for the Lower Limits of Airborne Broad-leaf Analysis Water Particulate or Fish Milk Vegetation Sediment (pCi/I) Gases (pC/kg, (pCi/I) (pCpgkg, dry)(pCVm 3) wet) (p( kdkg, wet)Gross Beta H 3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs- 137 Ba-140 La- 140 4 1E-02 2,000 15 30 15 15 30 15 15 130 260 130 130 260 I 15(b)15 18 15 15 7E-02 5E-02 6E-02 1 130 150 15 18 60 15 60 60 80 150 180 (a) The LLD is defined, for purposes of these commitments, as the smallest concentration 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):
Radiological Environmental Monitoring 16.11.6 Table 16.11.6-1 Radiological Environmental Monitoring Program Number of       Smln       n   olcin       Tm n       rqec       fAayi Exposure Pathway     and/or SapeSample          me         Sampling   and Collection Frequency (d)         Time and Frequency of Analysis Sample                 Locations (b)
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 02/01/05 I 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)
: 4. INGESTION
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 tractional radiochemical yield (when applicable)
: a. Milk                         4(e)       Semimonthly when animals are on pasture; monthly at other times.
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.
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 hours.
(b)     Sample locations are identified in the ODCM.
(c)     Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours 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 ifspecimens are unobtainable due to hazardous conditions, seasonal unavailability, or to malfunction of automatic sampling equipment. If the 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                                         Broad-leaf Particulate or       Fish         Milk         Vegetation           Sediment Analysis          Water (pCi/I)         Gases               (pC/kg,       (pCi/I)                           (pCpgkg, dry) 3           wet)                         (p(       wet)            kdkg, (pCVm )
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 Nb-95 15 15 I
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            15                                               60 La- 140          15                                                15 (a)     The LLD is defined, for purposes of these commitments, as the smallest concentration 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                                                 02/01/05 I
 
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 tractional 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 posterior (after the fact) limit for a particular measurement.
The LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a posterior (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.
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.
Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances, may render these LLDs unachievable.
(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 1 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 1-131 an LLD of 1 pCi/liter will be achieved.
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 1 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 1-131 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 (pci/I) Gases (pCi/kg, wet) (pci/I) (pcikg, wet)(pCi/rn 3)(pikwt H-3 2E04(a)Mn-54 1 E03 3E04 Fe-59 4E02 1 E04 Co-58 1 E03 3E04 Co-60 3E02 1 E04 Zn-65 3E02 2E04 Zr-Nb-95 4E02 1-131 2(b) 0.9 3 1 E02 Cs-134 30 10 1E03 60 1E03 Cs-137 50 20 2E03 70 2E03 Ba-La-1 40 2E02 3E02 (a)(b)For drinking water samples. This is 40 CFR Part 141 value.If low level 1-131 analyses are performed.
(c) Other peaks which are measurable and identifiable, together with the radionuclides in Table 16.11.6-2, shall be identified and reported.
16.11.6-8 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.
16.11.6-7                                                   02/01/05 1
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.
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 (pci/I)             Gases                 (pCi/kg, wet)   (pci/I)       (pcikg, wet)
Following this period, program changes may be initiated based on operational experience.
(pCi/rn 3 )(pikwt H-3               2E04(a)
The detection capabilities required by Table 16.11.6-2 are considered optimum for routine environmental measurements in industrial laboratories.
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-1 40         2E02                                                       3E02 (a)     For drinking water samples. This is 40 CFR Part 141 value.
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.
(b)    If low level 1-131 analyses are performed.
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:
16.11.6-8                                         02/01/05 1
: 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 r 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.
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 r   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==
==11.6 REFERENCES==
:
: 1. 10 CFR Part 50, Appendix I.
: 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 APPLICABILITY:
: 2. Offsite Dose Calculation Manual.
The annual (calendar year) dose or dose commitment, to any Member of the Public due to releases of radioactivity and to radiation from uranium 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.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 I If COMPLETION TIME , B. Calculated dose Iexceeds limits of.Commitment 16.11.7.-N O "T E _,',_` !!, fil .C I I -i I, Th'is Special Report, a's defined in 10 CFR Part 20.2203(a), shall include an"analysis that estimates the radiation exposure (dose) to a Member of the Public 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.
16.11.6-10                             02/01/05 1
ij'IA I.i 9' I;.1 I ii i t" B.1 Prepare and submit to the Commission a" Special Report that defines the corrective action to be taken to reduce subsequentj!.;
 
releases to prevent,.recurrence of exceeding`;q the specified limits and I p .,ncludesthe schedule.... : llt ::. 0 aclhievin'g  
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 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.
:' : i .,: conformance with the specified limits.30 days~iI;16.11.7-2 01/31/00 I Dose Calculations 16.11.7 CONDITION REQUIRED ACTION COMPLETION TIME C. Calculated dose C.-1 ---------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.
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.
16.11.7-3 03/27/99 Dose Calculations 16.
16.11.7-1                                       01/31/00 I
 
If COMPLETION TIME ,
                                                    - N O "T E _,',_`!!, fil   .       ij'
                                                              -i I, B.      Calculated dose                          C I I IA Iexceeds limits of.      Th'is Special Report, a's defined I.i 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 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.
9' I; B.1             Prepare and submit to the Commission a"               30 days Special Report that defines the corrective action to be taken to
      .1 I reduce subsequentj!.;
releases to prevent,.
recurrence of exceeding ii  t i"                      `;q the specified limits and
                                  .... : I::.p llt.,ncludesthe 0 aclhievin'g schedule
:' :
* i .,:
conformance with the specified limits.
                                                                                                    ~iI; 16.11.7-2                                         01/31/00 I
 
Dose Calculations 16.11.7 CONDITION                       REQUIRED ACTION               COMPLETION TIME C. Calculated dose               C.-1     --------- 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.
of resulting in violation 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==
==11.7 REFERENCES==
:
: 1. 10 CFR Part 20.
: 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 1 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 Chemical Treatment Ponds, SLC 16.11.1 .d 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:
: 2. 40 CFR Part 190.
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.
: 3. Offsite Dose Calculation Manual.
16.11.8-1 09/25/03 I 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.
: 4. 10 CFR Part 50, Appendix I.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.8.1 NA NA BASES Reference applicable commitments.
16.11.7-4         01/31/00 1
 
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 Chemical Treatment Ponds, SLC 16.11.1 .d
: 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                                       09/25/03 I
 
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:==
==REFERENCES:==
: 1. 10 CFR Part 20.2. 40 CFR Part 190.3. Offsite Dose Calculation Manual.16.11.8-2 09/25/03 1 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 an assessment of the radiation dose from radioactive effluents to members of the public due to their activities inside the unrestricted area boundary during the reporting period. All assumptions used in making these assessments (e.g., specific activity, exposure time and location) shall be included in these reports.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:
: 1. 10 CFR Part 20.
: 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.
: 2. 40 CFR Part 190.
The annual average meteorological conditions shall be used for determining the gaseous pathway doses. Approximate and conservative approximate methods are acceptable.
: 3. Offsite Dose Calculation Manual.
The assessment of radiation doses shall be performed in 16.11.9-1 11/14/00 I Radioactive Effluent Release Report 16.11.9 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.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);
16.11.8-2                               09/25/03 1
 
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 an assessment of the radiation dose from radioactive effluents to members of the public due to their activities inside the unrestricted area boundary during the reporting period. All assumptions used in making these assessments (e.g., specific activity, exposure time and location) shall be included in these reports.
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 16.11.9-1                                       11/14/00 I
 
Radioactive Effluent Release Report 16.11.9 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.
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);
: 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.
: d. Type of waste, (e.g., spent resin, compacted dry waste evaporator bottoms);
Methods for calculating the dose contribution from liquid and gaseous effluents are given in the ODCM.APPLICABILITY:
: e. Number of shipments; and,
At all times.16.11.9-2 01/31/00 I 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 I BASES N/A  
: 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                                     01/31/00 I
 
Radioactive Effluent Release Report 16.11.9 ACTIONS CONDITION                   REQUIRED ACTION           COMPLETION TIME A. N/A                       A.1       N/A                 N/A                       I SURVEILLANCE REQUIREMENTS SURVEILLANCE                               FREQUENCY SR 16.11.9.1     N/A                                       N/A BASES N/A


==REFERENCES:==
==REFERENCES:==
: 1. Oconee ITS.2. Offsite Dose Calculation Manual.16.11.9-3 01/31/00 I 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.
: 1. Oconee ITS.
The reports shall also include the results of the land use censuses.
: 2. Offsite Dose Calculation Manual.
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 SL-Cs taken during the report period. In the 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:
16.11.9-3                               01/31/00 I
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:
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.
At all times.16-11-10-1 16.1110-102/25/03 1
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.
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  
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 SL-Cs taken during the report period. In the 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                                       16.1110-102/25/03 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:==
==REFERENCES:==
: 1. Oconee ITS
: 2. Offsite Dose Calculation Manual 16.11.10-2                                    02/25/03 1


1.2.Oconee ITS 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:
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.
At all times.ACTIONS__________________
APPLICABILITY:       At all times.
___CONDITION REQUIRED ACTION COMPLETION TIME A. NA A. 1 NA NA SURVEILLANCE REQUIREMENTS
ACTIONS__________________                                                                     ___
_________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.
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:==
==REFERENCES:==
: 1. Oconee CTS Amendment No. 3/3 SER date July, 1974.
16.11.11-1                                        0/79 03/27/99
Radioactive Material in Outside Temporary Tanks Exceeding Limit 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 5.5.1 3.c.
APPLICABILITY:        At all times.
ACTI ONS                            ___________                              ________
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                                    16.1112-104/10/03 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
                      ---------------------- NOTE 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 A.2        Reduce tank contents    48 hours to within limit.
SURVEILLANCE REQUIREMENTS SURVEILLANCE                                      FREQUENCY SR 16.11.13.1      Verify quantity of radioactive materials in each  24 hours 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                                    03/27/99
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 Gas16.11.14 Mixture 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
                      ------------------------ NOTE-Separate Condition Entry is allowed for each tank.
CONDITION                      REQUIRED ACTION            COMPLETION TIME A. Concentration of            A.1    Reduce Concentration  48 hours 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 hours 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 hours 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 hours 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


1 .Oconee CTS Amendment No. 3/3 SER date July, 1974.16.11.11-1 0/79 03/27/99 Radioactive Material in Outside Temporary Tanks Exceeding Limit 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 5.5.1 3.c.APPLICABILITY:
Enclosure
At all times.ACTI ONS ___________
* ODCM Manual
________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
* PCP Manual}}
_________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 16.1112-104/10/03 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 APPLICABILITY:
The quantity of radioactive material in the Waste Gas Holdup tanks shall not exceed the limit specified in ITS 5.5.13.b.At all times.ACTIONS----------------------
NOTE 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 A.2 Reduce tank contents 48 hours to within limit.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.13.1 Verify quantity of radioactive materials in each 24 hours 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 03/27/99 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 APPLICABILITY:
The concentration of Hydrogen in the Waste Gas Holdup Tanks shall be< 3% by volume.At all times.ACTIONS------------------------
NOTE-Separate Condition Entry is allowed for each tank.CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of A.1 Reduce Concentration 48 hours 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 hours 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 hours 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 hours 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 Enclosure* ODCM Manual* PCP Manual}}

Latest revision as of 01:45, 13 March 2020

2007 Annual Radioactive Effluent Release Report
ML081430505
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 04/30/2008
From: Baxter D
Duke Energy Carolinas, Duke Energy Corp
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML081430505 (130)
v • d • e


Text

~Duke DAVE BAXTER kEnergy. Vice President Oconee Nuclear Station Duke Energy Corporation April 30, 2008 ON01 VP17800 Rochester Highway Seneca, SC 29672 864-885-4460 U.S. Nuclear Regulatory Commission 864-885-4208 fax dabaxter@dukeenergy.com Document Control Desk Washington, D.C. 20555

Subject:

. Duke Energy Carolinas, LLC Oconee Nuclear Station, Docket Nos. 50-269, 50-270 and 50-287 2007 Annual Radioactive Effluent Release Report Gentlemen:

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, 2007 through December 31, 2007.

Attachment I Radioactive Effluent Releases Attachment II Supplemental Information Attachment III Solid Waste Disposal Report Attachment IV Inoperable Monitoring Equipment Attachment V Unplanned Offsite Releases Attachment VI Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Attachment VII SLC 16.11 Radiological Effluent Controls Enclosures Offsite Dose Calculation Manual and Process Control Program Manual Should there be questions concerning this report please contact Judy E. Smith at (864) 885-4309.

Very truly yours, Dave Baxter Site Vice President Oconee Nuclear Site Attachments C(

www. duke-energy. corn

U. S. Nuclear Regulatory Commission April 30, 2008 Page 2 xc: L. N. Olshan, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 0-14 H25 Washington, D. C. 20555 V. M. McCree, Regional Administrator, Acting U. S. Nuclear Regulatory Commission - Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Andy Hutto Senior Resident Inspector Oconee Nuclear Station S. E. Jenkins, Manager Division of Radioactive Waste Management Bureau of Land and Waste Management Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201

U. S. Nuclear Regulatory Commission April 30, 2008 Page 3 bcc without attachments:

C. D. Ingram EC07F J. A. Twiggs ON01RP B. G. Davenport ON03RC W. S. Pursley ON01RW bcc with attachments:

ELL NSRB R. L. Gill Document Management

Attachment I Oconee Nuclear Site Effluent Release Data

OCONEE NUCLEAR STATION EFFLUENT RELEASE DATA (January 1, 2007 through December 31, 2007)

This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents as outlined in Regulatory Guide 1.21, Appendix B.

TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2007 Unit QTR' I QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Gases

1. Total Release Ci 8.49E+01 9.06E+01 5.83E+01 1.05E+02 3.39E+02
2. Avg. Release Rate 14Ci/sec 1.09E+01 1.15E+01 7.34E+00 1.32E+01 1.08E+01 B. Iodine-131
1. Total Release Ci 1.55E-05 1.05E-04 0.00E+00 2.56E-03 2.68E-03
2. Avg. Release Rate /ACi/sec 1.99E-06 1.34E-05 0.00E+00 3.22E-04 8.49E-05 C. Particulates Half Life >= 8 days
1. Total Release Ci 1.OOE-06 2.71E-05 3.68E-06 4.66E-09 3.17E-05
2. Avg. Release Rate ,&Ci/sec 1.29E-07 3.44E-06 4.62E-07 5.87E-10 1.01E-06 D. Tritium
1. Total Release Ci 1.43E+01 1.01E+01 1.59E+01 1.68E+01 5.71E+01
2. Avg. Release Rate /LCi/sec 1.83E+00 1.29E+00 2.00E+00 2.11E+00 1.81E+00 E. Gross Alpha Radioactivity
1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
2. Avg. Release Rate pCi/sec 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00

TABLE lB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS - ELEVATED RELEASES - CONTINUOUS MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases KR-85M Ci 0.OOE+00 1.20E-01 8.16E-02 0.OOE+00 2.02E-01 XE-133 Ci 7.71E+01 8.28E+01 5.48E+01 1. 99E+01 2.35E+02 XE-133M Ci 0.OOE+00 0.OOE+00 0. OOE+00 2.28E+00 2.28E+00 XE-135 Ci 7.85E+00 6. 96E+00 3. 11E+00 3.73E-01 1.83E+01 Totals for Period... Ci 8.49E+01 8. 99E+01 5. 80E+01 2.25E+01 2.55E+02
2. Iodines 1-131 Ci 1.55E-05 1.02E-04 0. OOE+00 2.50E-03 2.61E-03 1-133 Ci 1.94E-06 1.10E-05 1. OOE-05 6.22E-04 6.45E-04 1-135 Ci 0.OOE+00 0. 00E+00 0. OOE+00 1.28E-04 1.28E-04 Totals for Period... Ci 1.74E-05 1. 13E-04 1. OOE-05 3.25E-03 3.39E-03
3. Particulates Half Life >= 8 days CS-137 Ci 1 1.00E-06 0. OOE+00 0.OOE+00 0.OOE+00 1.00E-06 Totals for Period... Ci 1.OOE-06 0.OOE+00 0. OOE+00 0.OOE+00 1.00E-06
4. Tritium H-3 Ci 9.96E+00 9.01E+00 1.48E+01 1.42E+01 4.80E+01 Totals for Period... Ci 9.96E+00 9.01E+00 1.48E+01 1.42E+01 4.80E+01
5. Gross Alpha Radioactivity
    • No Nuclide Activities **

TABLE lB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS - ELEVATED RELEASES - BATCH MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR I. Fission and Activation Gases AR-41 Ci 2.92E-03 2.01E-02 1.21E-02 0.OOE+00 3.52E-02 KR-85 Ci 0.00E+00 3.80E-01 3.12E-01 2.89E+00 3.58E+00 KR-85M Ci 0.OOE+00 0.OOE+00 0.OOE+00 2.57E-05 2.57E-05 XE- 13 IM Ci 0.OOE+00 2.01E-03 0.OOE+00 5.35E-01 5.37E-01 XE-133 Ci 9.23E-04 2.58E-01 4.04E-02 7.40E+01 7.43E+01 XE- 133M Ci 0.OOE+00 2.29E-04 0.OOE+00 3.27E-01 3.27E-01 XE-135 Ci 6.47E-05 4.19E-05 1.98E-04 1.09E-01 1.09E-01 Totals for Period... Ci 3.90E-03 6.60E-01 3.65E-01 7.79E+01 7.89E+01

2. lodines 1-131 Ci 0.OOE+00 1.97E-09 0.OOE+00 1.23E-05 1.23E-05 1-133 Ci 0.OOE+00 0.OOE+00 O.OOE+00 4.94E-07 4.94E-07 Totals for Period... Ci 0.OOE+00 1.97E-09 0.OOE+00 1.28E-05 1.28E-05
3. Particulates Half Life >= 8 days CO-58 Ci O.OOE+00 0.OOE+00 0.OOE+00 4.66E-09 4.66E-09 Totals for Period... Ci 0.OOE+00 0.OOE+00 0.00E+00 4.66E-09 4.66E-09
4. Tritium H-3 Ci 4.90E-04 4.36E-02 1.12E-02 5.60E-01 6.15E-01 Totals for Period... Ci 4.90E-04 4.36E-02 1.12E-02 5.60E-01 6.15E-01
5. Gross Alpha Radioactivity
    • No Nuclide Activities **

TABLE iC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases XE-133 Ci 0.OOE+00 0. OOE+00 0. OOE+00 4.86E+00 4. 86E+00 Totals for Period... Ci O.OOE+00 0.OOE+00 0. OOE+00 4.86E+00 4.86E+00
2. lodines 1-131 Ci 0.OOE+00 3.77E-06 0. OOE+00 4.87E-05 5.24E-05 Totals for Period... Ci O.OOE+00 3.77E-06 0. OOE+00 4.87E-05 5.24E-05
3. Particulates Half Life >= 8 days CO-58 Ci O.OOE+00 2.51E-05 3.68E-06 0. OOE+00 2.88E-05 CO-60 Ci 0.OOE+00 1. 94E-06 0. OOE+00 0. OOE+00 1.94E-06 Totals for Period... Ci 0.OOE+00 2.71E-05 3.68E-06 0. OOE+00 3.07E-05
4. Tritium H-3 Ci 4.29E+00 1.10E+00 1.08E+00 2. 04E+00 8.51E+00 Totals for Period... Ci 4.29E+00 1.10E+00 1.08E+00 2.04E+00 8.51E+00
5. Gross Alpha Radioactivity
    • No Nuclide Activities **

TABLE iC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases
    • No Nuclide Activities **
2. lodines
    • No Nuclide Activities **
3. Particulates Half Life >= 8 days
    • No Nuclide Activities **
4. Tritiium H-3 Ci 1.79E-02 5.64E-07 0. OOE+i00 2.83E-07 1.79E-02 Totals for Period... Ci 1.79E-02 5.64E-07 0. OOE+00 2.83E-07 1.79E-02
5. Gross Alpha Radioactivity
    • No Nuclide Activities **

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Products

1. Total Release Ci 3.23E-03 4.12E-03 2.33E-03 9.81E-03 1.95E-02
2. Average Diluted Concentration
a. Continuous Releases pCi/ml 0.00E+00 0.OOE+00 0.OOE+00 O.00E+O0 0.OOE+00
b. Batch Releases gCi/ml 1.93E-10 2.44E-10 1.36E-10 5.74E-10 2.87E-10 B. Tritium
1. Total Release Ci 2.66E+02 2.55E+02 1.47E+02 2.43E+02 9.11E+02
2. Average Diluted Concentration
a. Continuous Releases ACi/ml 2.46E-08 1.48E-08 1.629-08 1.86E-08 1.85E-08
b. Batch Releases pCi/ml 1.59E-05 1.51E-05 8.56E-06 1.42E-05 1.34E-05 C. Dissolved and Entrained Gases
1. Total Release Ci 6.59E-04 3..83E-04 2.21E-04 4.96E-04 1.76E-63
2. Average Diluted Concentration
a. Continuous Releases uCi/ml 0.OOE+00 0.OOE+00 0.OOE+.00 0.OOE+00 0.00E+00
b. Batch Releases pCi/ml 3.94E-11 2.26E-11 1.29E-11 2.90E-11 2.59E-11 D. Gross Alpha Radioactivity
1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE00 O .OOE+00 0.OOE+00
2. Average Diluted Concentration
a. Continuous Releases pCi/ml 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00
b. Batch Releases pCi/ml 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 E. Volume of Liquid Waste
1. Continuous Releases liters 7.19E+08 7.67E+08 4.53E+08 6.11E+08 2.55E+09
2. Batch Releases liters 1.75E+06 3.23E+06 9.13E+05 3.19E+06 9.08E+06 F. Volume of Dilution Water
1. Continuous Releases liters 1.67E+10 1.69E+10 1.71E+10 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 1/1/07 TO 1/1/08 LIQUID EFFLUENTS - CONTINUOUS MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 200.7 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Products
    • No Nuclide Activities **
2. Tritium H-3 Ci 4.28E-01 2.61E-01 2.84E-01 3.29E-01 1.30E+00 Totals for Period... Ci 4.28E-01 2.61E-01 2.84E-01 3.29E-01 1.30E+00
3. Dissolved and Entrained Gases
    • No Nuclide Activities **
4. Gross Alpha Radioactivity
    • No Nuclide Activities **

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID EFFLUENTS - BATCH MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR 1.. Fission and Activation Products AG-11OM Ci 4.55E-05 3.75E-04 4.00E-05 2.31E-04 6.92E-04 CO-57 Ci 0.OOE+00 0.00E+00 0.OOE+00 1.47E-05 1.47E-05 CO-58 Ci 1.51E-03 3.54E-03 2.23E-03 8.53E-03 1.58E-02 CO-60 Ci 0.OOE+00 0.OOE+00 1.97E-05 2.19E-05 4.16E-05 CR-51 Ci 0.OOE+00 0.OOE+00 O.OOE+00 3.74E-04 3.74E-04 CS-137 Ci 0.OOE+00 3.99E-05 0.OOE+00 3.14E-04 3.54E-04 1-131 Ci 0.OOE+00 0.OOE+00 O.OOE+00 2.02E-04 2.02E-04 NB-95 Ci O.OOE+00 0.00E+00 0.OOE+00 5.21E-05 5.21E-05 SB-125 Ci 1.67E-03 1.62E-04 0.OOE+00 7.44E-05 1.91E-03 ZR-95 Ci 0.OOE+00 0.OOE+00 4.25E-05 0.00E+00 4.25E-05 Totals for Period... Ci 3.23E-03 4.12E-03 2.33E-03 9.81E-03 1.95E-02

2. Tritium H-3 Ci 2.65E+02 2.55E+02 1.46E+02 2.43E+02 9.09E+02 Totals for Period... Ci 2.65E+02 2.55E.-02 1.46E+02 2.43E+02 9.09E+02
3. Dissolved and Entrained Gases XE-133 Ci 6.59E-04 3.83E-04 2.21E-04 2.78E-04 1.54E-03 XE-133M Ci 0.OOE+00 0.OOE+00 0. OOE+00 2.18E-04 2.18BE-04 Totals for Period... Ci 6.59E-04 3.83E-04 2.21E-04 4.96E-04 1.76E-03
4. Gross Alpha Radioactivity
    • No Nuclide Activities **

Attachment II Oconee Nuclear Site Supplemental Information

OCONEE NUCLEAR STATION 2007 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION I. REGULATORY LIMITS - STATION A. NOBLE GASES - AIR DOSE 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 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. 1.14E+02 = TOTAL NUMBER OF BATCH RELEASES
2. 2.25E+04 = TOTAL TIME (MIN.) FOR BATCH RELEASES.
3. 2.56E+02 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.
4. 1.97E+02 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.
5. 1.13E+02 = MINIMUM TIME (MIN.) FOR A BATCH RELEASE.
6. 3.41E+04 = AVERAGE DILUTION WATER FLOW DURING RELEASES (GPM).

B. GASEOUS EFFLUENT

1. 6.70E+01 = TOTAL NUMBER OF BATCH RELEASES.
2. 1.16E+05 = TOTAL TIME (MIN.) FOR BATCH RELEASES.
3. 3.51E+04 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.
4. 1.73E+03 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.
5. 1.OOE+00 = 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 2007 METEOROLOGICAL JOINT FREQUENCY DISTRIBUTIONS OF WIND SPEED, WIND DIRECTION, AND ATMOSPHERIC STABILITY USING WINDS AT THE 10 METER LEVEL (Hours of Occurrence)

OCONEE NUCLEAR STN. METEOROLOGY (2007) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY A WIND SPEED .CLASS I I

I I 1 1.25-1 1.50-I 2.00-I 3.00-I 4.00-I 5.00-I 6.00-I 11.49 j 1.99 1 2.99 1 3.99 1 4.99 1 5.99 1 7.99 TOTAL I ---------------- +----+- ----------- I NO. I NO. I ND. I NO. I NO. 1.NO. I NO. NO.

I- - - - - - - - - - - - - - - - - - ----------------------------------------- + -

ISECTOR I I I I I I I I I------------------------ I I I I I I I I I-N- I .1 31 I 'I .I I -I 51 I ------------------------------------------------------- ---- - I I-NNE- I 1I 1 6 -I 1

  • .1 1 71 I --- ---- ----- -----------------------------------

I-NE- I .1 21 41 21 1I *I *I 91 I- - - - - - - - - - - - - - - - -+-

- - - ---------- - I I-ENE- I .1 *l 121 31 .1 .1 I l51 I ---------------- --------------------------------

++ - -----

+ - ---- I I-E- 1 21 *I .1 1 I --------------------------------------------------- ---- ---- - I

-ESE- I 1 .1 41 11 .I I *1 SI I --------------------------------------------------- ---- ---- - I j-SSE- I *I I 1 .1 I. 1

  • 1I

-_s- 1 . 1 -11 1 .1 11 I---- --------------------------------------------------- + + - - I

-ssW- 1 I 1I 241 101 31: 1 38 I-SW- ----------------------------------------------------------- - I I 11 12 951 191 41: .1 1 1311 1I---------------------------------------------------------- - I j-WSW- 1 I 41 561 81 11 11 'I 71L

-w- .1 21 ioj 31 31 1 .1 181 I- - - - - - - - - - -- - - - - - - - - - ---------------------------------- --- + I j-WNW- 1 I 1 31 11 21 21 11 101 I- - - - - - - - - - - - - -- - - - -- - - --------------------------------- + + - - I I-NW- 1 .*I 21 41 11 31 21 1I 131 1I - - - - - - - - - - - - -- -- - -- - ------------------------------------ --- + I I-NNW- .I 11 1 .I .1 *I 1I 3 I - - - -- - - -- - - --- -- - - -- -- --------------------------------- + + - - I TOTAL I 11 291 2231 sIl 171 5I 41 3301

OCONEE NUCLEAR STN. METEOROLOGY (2007) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY B WIND SPEED CLASS 1

I I 1 1.25-1 1.50-I 2.00-I 3.00-I 4.00-I 5.00-I 6.00-I 8.00-I 1 1.49 1 1.99 1 2.99 1 3.99 1 4.99 I 5.99 I 7.99 I 9.99 ITOTAL I--------------------------

++ - + - +-+ - -+- +-------------+--I I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. NO.

I-

+ - + - -+- -+- I SECTOR I I I I I I I I I II-N-------------------------------

- 1 -1I 4 I1 2 I1 -1I I

.1 1 .1I I1 61 I-- - - - - --- -- -- - - - - -- - -- -- - ----------------------------------- ----- I I-NNE- I -1 81 71 .1 .1 1 1 1 151 I- - - - - - - - - - - -- - - - - - - - - - ----------------------------------------- + -

I-NE- -1 21 161 21 .1 .1 .1 201 I- - - - - - -- - -- -- --- - -- ------------------------------------------- + -

-ENE- I - I 31 241 121 .I .1 1 391 I ----------------------------------------- *---------- - +---------- I I-E- I -I 21 "il 31 .1 I1 -I 161

-ESE- I .I .I 41 1i 1 .I 1 I SI I- - - - - - - - - - - - - - - - - - - - - - - ------ - ----------------------------- --- -- I I-SE- I .1 21 .I . .. .I I 1 21 I - ----- ----------------------------------------------------------- I j-SSE- I .1 11 21 *1 .1

.I .1 3 I-_s-- - - - - - - - - -- - -- - - - - -.1 - - --.1 - -----------------------------

71 11 -----

-I.1 . I. 1 81 I - - - - - -

- ---- - - - - - --------------------------.....- + - .+-. .+- . .I I-SSW- I 11 101 381 ý8[ 1i .1

-I -I 681 I .------------------------

4.--.-.-----7----+-+-+ - I I-Sw- I 31 181 531 81 51. 31 -I 90 I---------------------------------------------------+ +-+ 4------- - I I-WSW- I 11 141 421 5I 1i 21 71 31 751 I ---------------------------------------------------- +--+-+ 4- -- I I - - - - - - - - - - - - - - -- - -- - -- - ------------------------------------ 44 - + I I-WNW- 1 .1 81 11 21 5I 1I 11 *I 181 I----------------- --- --- --------------------------------------- - I I-NW- 1 .1 31 o 1j 21 I 81 .1 1 I----------------- --- --- --------------------------------------- - I

- I-NN 1 I 31 31 -I .1 .I .I .I I-------------------------------------- - I ITOTAL I 6l 841 2211 611 191 81 171 31 4191

OCONEE NUCLEAR STN. METEOROLOGY (2007) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY C WIND SPEED CLASS I I

I I 1.00-I 1.25-1 1.50-I 2.00-I 3.00-I 4.00-I 5.00-I 6.00-I 8.00-I 1.24 1 1.49 11.99 1 2.99 1 3.99 I 4.99,1 5.99 I 7.99 I 9.99 ITOTAL

+-+-+-+ - I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO.

I-- - - - - - - - - - - - - - -- - -- - --------------------------------------------------

SECTOR I I I I I I I I I

- I I I I I I I I I

-N- 1 -I ii 141 21 ii 1

.1 .1 18[

I-NNE- 1 .1 21 181 I 1I I .1 .1

- 291

-+---.-- +....------- -+-. .+..- . +..-- +-----+------- +------- +....- I

-NE- I .1 21 21 101 ij 11 .1 *1 *1 161 I-ENE- 1 .1 .1 6I 231 161 ii .1 1 .1 461 I- - - - - - - - - - - - - - - - - - - - - - -------------------------------------------- ------ I I-E- 1 . .1 11 191 21 .I .1 1 .1 221 1 ----------------------------------------------- +-+ +- +------ -+-+- +------

I-ESE- 1 *I 21 ill .I .1 1 .1 .1 31 I ----------------------------------------------- +-+ +- +------ -+-+- +-I----

I-SE- .1 .I 31 i .I .1 .1 .1 41 I ----------------------------------------------- +-+ +- +------ -+-+- +------

I-SSE- 1 *I .I 61 8 .I .I 1 1 1 141 I-_s -----

- 7---------------------------------------------+- .1- 21--- 51 + 10o -+ -

.1 -

.1 -+-

1 +-I----

.1 171 1I------------------------------------------------+- -+ +- +- +--+-+- +------

I-ssw- 1 4 31 61 311 231 31 .1 .I .1 661 I-SW- 1 i1 51 241 431 281 31 I 71 1 .1 1121 1I------------------------------------------------+- ----- +-- ---- +- +-----

l-WSW- I I 31 ioj 231 21 5I 41 1 11 481 1I---------------------------------------------------+-+- -+- -- + -+- ---- I l-w- 1 .I .I '51 81 21 .1 i 6I 11 331 1 ----------------------------------------------------------------

+- + - + - -- -+I I-WNW- . -21 81 . .1 5 61 ill 41 361 I - - - -- - - -- - - ---- -- -- + --- -+ -- -+- - ---------------------------

-+ -+ - + - - + - + I I-NW-- .I .I 41 21 .1 21 41 71 21 211 1I---------------------------------------------------+-+- -+- -- +- -+- -+-I T-OTA- 11 I - --

I 21 1 11 11 1 241 61

. I 81 151 ITOTAL 1 1 221 1321 2001 771 201 241 261 81 5101

OCONEE NUCLEAR STN. METEOROLOGY (2007) PROG=XOQFREQ" 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY D WIND SPEED CLASS I I

I I 1 0.4s-1 0.75-I 1.00-I 1.25-I 1.50-I 2.00-I 3-.00-1 4.00-I 5.00-I 6.00-I 8.00-1>9.99 I I 0.74 1 0.99 I 1.24 j 1-49 1 1.99 1 2.99 1 3.99 J 4.99 I 5.99 I 7.99 1 9 99 1 M/S ITOTAL NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. j NO. I NO. I NO. I NO. INO. I I- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -+-- - - - - - -+ - - ----------------

+ -- + - -- ---- - -

ISECTOR I I I I 1 I I I. I I II I I - --I I I I I

-N- I 11 131 231 371 291 131 81 31 11 .I I1 1281 1I - - - - - - - - - - - - - - -- -- - - - - - - - - - - - - - - - ----------------------------------- ++ - + + -- - ---

- I I-NNE- I 41 71 181 401 691 251 131 41 .1 I .1 .1 1801 I--- - -- - - - - ---- - -- --- - --

4-------------+- - -- --- - -- - --------------------------- - ---- I I-NE- I 41 12[ 311 821 1201 501 71 I .I *1 3061 1I- - - --- - - -- - -- - --- + - - - -- -- ---

+- -------------------------

+ ---- +----+-- +-- --- I I-ENE- I 1 31 11j 231 1011 2181 781 201 1 .1 .1 .1 4541 1 ------------------------------------------------------------------ +-+ +----+- ---- I I-E- 21 21 121 20j 511 721 161 21 1 *1 1

  • 1771 1- - - - - - - - - - - - - - - - - - - - - - - ---- - - - - - - - -+ - - - - - - - -+ - -- - - - - -------------

4 ---- - I

-ESE- I I 31 31 ill 311 181 31 .1 .1 1 .II I 691 1I-----------------------------------------------------------4 -+- -+- -+- -I

-SE- I 31 41 S5 121 261 201 .1 I. .I .1 70[

1I- - - -- - - - -- - - - --- -- -++- - --- - -- 4 - ----

4- - - ---------------------------

- ---- + - - 4 --- + -- I I-SSE- I 31 41 5I 141 461 211 -1 .1 1 .1 .1

- 931 I-I -------------------------------------------------------- 4-4 +- --- 4- -+ 4-- --- 4------

21 1i 101 231 471 211 "1 "1 1 .1 .1 4 1041 I-------------------------------------------------+-+-+-----------. ------------ I 1-ssW- I 11 Sl 61 181 501 1071 571 191 21 1 1 . 2651 I ---------------- 4- --- 4 ---

- --- 4 ---

- 4 ---

- 4 - - 4 ----- I I-Sw- I 21 71 191 261 621 1371 1101 731 151 21 1 I 4531

- - -- I

-WSW- I 11 91 211 221 58 731 671 551 341 231 41 *1 3671 1I- - ----- - -------- 4 -------

--- 4 ---

+- 4 - ---- 4 - I 1-w- I 41 121 151 261 511 371 431 441 231 171 1i 2731 I -------------------------------------------------------------- +------------------- I 1-WNW- I 11 15I 231 321 281 261 271 291 171 201 21 .1 2201

4 - I I-NW- I 11 161 26[ 281 251 241 181 ill 10j 121 41 11 1761 1I - - - --- - - - - - - -- -- - -- - -- --- --- - -- ----------------------------------------

4--4 - - 4 - - I I-NNW- I 21 101 171 251 251 10j 151 71 111 21 11 .l 1251 I ------------------------------------------------------------------------------------------------ I TOTAL I 27 11is 2261 3881 7811 9421 S0SI 2741 . 1131 761 121 11 34601

OCONEE NUCLEAR STN. METEOROLOGY (2007) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY E WIND SPEED CLASS I

I I 1 0.45-1 0.75-I 1.00-1 1.25-1 1.50-1 2.00-1.3.00-1 4.00-1 5.00-i 6.00-1 8.00-1 1 1 0.74.1 0.99 1 1.24 11.49 1 1.99 1 2.99 1 3.99 1 4.99 I 5.99 I 7.99 I 9.99 ITOTAL I- +-------+-.....+....-.+....---+-....-.+...-.+...-+..-- +..-+..-- ----- 7-.

NO.

1 I NO. I NO. I NO, I NO. I NO. I NO. NO I NO. I NO. I NO. NO.

- +-..... +-.....-+-.+-- --- --------------------------------- -+ +- I SECTOR I I 1I I I I I I I I I ----------------------- I I I I I I I-N- I 211 701 621 491 291 181 21 .I .1 .1 1 2511 1 ---------------------------------------------------------------------- + - + - + + - + - +-+-+-+- + - + - I j-NNE- I 191 59! 471 401 211 181 41 -l .1 1 .1 2081 j-NE- I 121 ~ 341 371 54 411 81 -1 11 1 1 2211 I-ENE- I 91 291 491 s0 841 801 41 .I .1 .1 .1 3051 I ----------------------------------------------------- +- - - - - - - - -+--.-----+-----

-E- I 161 331 461. 411 471 351 31. .I .1 1 1 2211 1 --- ------------- --- --- --- +- - -- -------- - +- ---- ----------- - ---- +----- I

-ESE- 1 9l 151 331 291 391 31 .1 1 1391 I ------------------------------------------------------- - - - - - - -+------------

-SE- I 6G 141 261 381 401 141 .1 .1 .1 1 1381 I - - - - - - - - - --- - - - -+-..--.-I I-SSE- I 1" 121 141 271 56! ill *I -I -1 1 I 1311 I ------------------------------------------------------------------------------ + - + - +- ---+ -

-s- 41 5I 201 321 411 14! .*I .1 .1 .1 .-1261 I ------------------------------------------------------- - - - - - - -+------- +/------

1-ssW- I ill 141 271 231 371 481 181 11 21 *1 4 181j I ------------------------------------ +---- --- ------------------- - - - ------ --- I-I-SW- I 8I 381. 311 3I 421 521 isj 61 21 .1 .1 22SI I--------------- + ---------------------------------------------

+- +---- --- - -

I-WSW- I 19! 491 321 311 221 411 301 111 il I *1 2361 I------------------------------------------------------+-+- - + - + - + - + - + +- -+-

-+-

I-w- I 19! 58! 341 161 191 161 131 41 11 1 1 1801 I -------------------------- +-+---+-+- ------------------------------- +-+-+- +- .+.-

I-WNW- I '91 1111 481 221 131 101 9!1 21 - 2! 2361 I ------------------------------------------------------ +- +----+- ----- +- 4-I----

I-NW- I 321. 8S5 801 28j 15l 6! 31 .1 21 21 11 2541 1 - - - - - - - - - - - - - -+ ---- -- - -- ------- - -- - --+ -- ------------------------

- + - - + - - 4 -

I-NNW- I 351 1101 861 461 211 8! 41 .I .1 1 .1 3101 I ---------------------------------------------------------------------

+-+ - + - + - +---+- I I-CALM - I 61 .1 .1 I1 I .I .I .I .1 1 61 TOTAL I 2561 7461 6691 5401 5801 4231 1161 221 11i 41 11 33681

OCONEE NUCLEAR STN. METEOROLOGY (2007) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY F WIND SPEED CLASS I I

I I 10.45-i 0.75-I 1.0o- 1.25-I 1.50-I 2.00-i 3.0o-1 4.00-i I 0.74 1 0.99 1 1.24 1.49 1 1.99 1 2.99 1 3.99 I 4.99 ITOTAL I I-- ------- +---- +------- +.....--+....-.-+....-.-+-...- . I NO. I NO. I NO. NO. I NO. I NO. I NO. I NO. I NO.

I-------------------------------------------------- + - + - + + + - +-+- + --.I SECTOR I I I I I I I I I ----------------------- I I I I I I *I I

-N- I s5 31 41 21 1 1 .1- .1 141 I....+ -.. .+ -.. .+ -.. .+. ..- + -.. .+ -.. .+/- .. .+ - I..

-NNE- 3 .1 4~I 1 1 11 I *I I j8 1 ---------------- --- --- ---------------------------------------- - I I-NE- I 21 21 4j1 .I .I .1 .1 8j II-ENE----------------- 1 --- .1--- 41 -----------------------------------

11 .1+ l1 + -- .1 -I - I-I 61 I ---------------- --- --- ---------------------------------------- - I I-E- I 11 41 31 31 5I 'I -.

.1 171 1 -------------------------------------------- +I+- +- -+ - + - + - + - I

-ESE- I 1 ..1 31 21 91 31 .I .1 181 1I- - - - - - - - - - - - - - -- - -- - ----------------------------------------- + -

I-SE- I 11 21 *I 4 91 61 .I .I 221 I- - - - - - - - - - - - - - -- - -- - ----------------------------------------- + -

I-SSE- I 2j 31 21 11 21 11 .1 *1

- i I--- - - - - - - - - - - - - -- - -- - ----------------------------------------- + -

I- - - - - - - - - - - - - - -- - -- - -------------------------------------------

I-SEW- I 11 1I -I 21 31 -I 11 91 I- - - - - - - - - -------------------------- 1* - - ------ I

-Sw- I 31 71 41 31 61 31 I -1I 261 I -- - - - -- - - - --- - -- --- - -------------------------------------------

I-wsw- 1 21 21 10I 9I 1I, if 4j 21 fl 301 I-- - - -- - - -- - - -- - - - ---- --------------------------------

++ + . +- II

-w- I 71 241 61 'I 31 .1 21 .1 431 I --------------------------------------------------------------- - I I-WNW- I 171 651 261 191 31 .1 I .I 1301 I ----------------------------------------------------------- + - t--- I I-NW- I 81 36I 44I 241 21 11 .1 .1 1 5I I-- +-- . . . .+ . . ..--- + -. . . ..- . -.

. . . ..-+ . -. . ..- . .- -.--- --- . . ..-

..- I I-NNW- I 41 101 a1 81 21 'I .1 .1 33 I-- ------------------------------------- +-...... .+- . I I-CALM- I 51 .1 .I -I .I .I .1 .1 51 I ---------------- --- --- --------------------------------------- - I TOTAL I 631 1721 1191 721 481 201 5I 11 5001

OCONEE NUCLEAR STN. METEOROLOGY (2007) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T-STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY G WIND SPEED CLASS I I

I I S0.45-I 0.75-I 1.00-1 1.25-1 1.so-1 2.00-I 3.00-I 4.00-j 1 I 0.74 I 0.99 I 1.24 I 1.49 1 1.99 1 2.99 1 3.99 1 4.99 ITOTAL NO.

I I NO. INO. I NO. INO. NO. I NO. I NO. I NO.

I----------------- --- --- ---------------------------------------- - I SECTOR I I I I I I I I I I II-N - ---------------------- 1 .1 I 2 I1 I1 .1I .1I .1 I .1I I

.1 2 I1 I ---------------- --- --- -----------------------------------

+ + -- - I I- E- E .1 11 . 1 *I

.1 .1 .1 11 I - - - - - - ----- - - - - -- - - - - - - - - - - -------------------------- 4+ -- +. + - I

-ESE- 1 I .1 I 11 .1 1 .*1 1 I.

-- ----- - - - -- - - - - . - -- --- - - -- - - - - -- - - - - --- 4. -- . -- -- - . -- . --- . . I I-SE- 1 I1 I .1 -I *I 11 I--------- ----------------------------------------------- - --- ----- I I-SSE- I .1 .1 1 I 11 I1I .1 11 I---- ------------- - -- ----------------------------------

--- ------- + -

Is- 1 .1 1 1 .1 .1 21 1-- - - - -- - - - - - - - - -- - -- +- +----- -- - -- -- - - -- - - -- ------ - ----- I wsw 1 I 1 .1 .1 .1 11 -1 31 I ------------------------------------------------- +-------------- I

.. . . . . +1. . 31 . . .+ . 1. .+ . . . . .. +1. . . . . . 1. . . .

I-w- I 61 41 .1 I.

1I .I o10 I- - - - - - - - - - - - - - - -+ - --- - - - - - - ---- - - - -------------------------

+ - I

-WEB- I 7[ 231 161 I * .I .I 471 I ...--- + ....-.- +4 - -+- -------------- + - + -

- --+ - -+ ---.I I-NW- I 21 91 1o[ 21 *1 .1 -1 *I 231 I ---------------- +- --- + ---

-+ --- + - - + - + I I-NNW- I 2 21 .I .1 .1 .I .1 41 I ---------------------------------------------- +- - -4 +- - - + +--+------ - -I I-CALM- I 'I .1 I .1

.II I .I 11 I------------------------------------ 4-- + - I ITOTAL I 191 45I 271 31 21 11 1I 1i 991

OCONEE NUCLEAR STN. METEOROLOGY (2007) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS ALL STABILITY CLASSES WIND SPEED CLASS I 1 0.45-1 0.75-1 1.00-1 1.25-1 1.50-1 2.00-1 3.00-1 4.00-1 5.00-1 6.00-1 8.00-1,9.99 I 1 0.74 1 0.99 1 1.24 1 1.49 1 1.99 1 2.99 13.99 1 4.99 1 5.99 1 7.99 1 9.99 1 M/S ITOTAL I-- ---- ---- ---- --- --- --- ------------------------------ ---- I I NO. NO NO. [NO. I NO. NO. I [ NO. NO. NO. NO. [NO. [INO. NO.,N I----------------- --- --- --- --- ----------------------------------------- ----- +- -- --- I

[SECTOR I I I I I I I I I I I I I-I ----------------------- I I I I I I I I I I I I I I-N- 1 271 881 891 891 791 361 121 31 1 1 .1 *1 424[

I------------------------------------ +- -+ -- +- --- -+ -- ----- - + ------- +------------------- - I I-NNE- I 261 67! 691 82[ 1181 641 181- 41[1 1 1 I 448[

I .....----....----....----....--

--....----....----....----....-- +- 4 - - + --- --------------------- +- -- I

[-NE- I 141 401 S01 70[ 1421 191j 631 91 i[ .1 .1 .1 5801 I - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---------------------------------- + -------- - I I-ENE- i .9s 361 611 73[ 1951 357 1131 211 . 1 86S I- - - - - - - - - - - - - - - -+ - ------- - - - - - - - -+-+--+- - - - - - - - - -+ - ---------------

+ - - + - + + -

I-E-1 19[ 39[ 611 64[ 1061 139F 261 21 -1 .1 1 4561 I ---- +---------- +- -

-- +-- -+---

-- - - +..-..+ ....- +-----+-+-

.....-- .....-- ....---..--- I

-ESE- I 101 181 391 421 821 511 81 .i .*[ 1.1 .1 2501 1 - - - - - - - - - - - - - - - - - - - - - - - - +- - - - - - ----------------------- 4- -----------

--- --- 4I I-SE- 1 101 201 311 541 80a 41[ .1 lj .1 1 1 2371 1- - - - - - - - - - - - - - - - - - - - - ------ - - - - - -----------------

+ - 4 ----- 4 -- - - -

+--- - - - -

I-SSE- 1 161 19[ 211 421 1111 451 .1 ,I I 1 1 .1 2541 I ---------------- --- --- -- --- 4 ---

4 - ----- 4- - ---4 - I

-S- I - 81 171 301 591 951 531 11 1 .1 -1 .1 .I 2631 1 --- - - -- - - - -- -- -- --- - -----------------------

4- - 4--------4 -- --- --- 4-.----- ----- ----- -I

[-ssw- I 131 201 341 471 1071 2481 1271 271 41 .1 6271 II-SW---- ------------ --- --- ---

1 13 53 561 691 1641 383[ 1811 911 271 31 "1 1 1040[

I ----------------------------------------------------------- 4- - 4--- 4 4 -- - - 4-I----

[-WSW- 1 221 711 62[ 581 1091 2391 114[ 741 421 311 81 *1 8301 1 - - - - - - - - - -------------------------- - - - - - - - - - --- - -- ----------------

-w-" 361 981 55 441 961 811 711 561 271 241 21 I 590o I--- - - - - -- - - - - - - -- - --4 ------ - --4 -- --4 -- ----------------------------

4 -- 4 --- 4 - 4 ---- 4 I l-WNW- . 1 441 2141 1131 761 611 401 391 411 28[ 351 61 .1 6971 I - - - - - - - - - - - - - - -- - -- - -- - - - -- ------ -------------------------------

4 - 4 - 4--4 - + - 4-I-NW- I 431 1461 160[ 821 s5j 381 23[ 181[. 181 301 71 11 6171 I ----------------------------------------------------- +-------+----------+----+ ----- I

[-NNW- 1 431 1321 111i 81[ 601 241 20[ 71 131 41 1[ .1 4961 1I---------------- --- 4 ---

- 4 ----------------------------

- - + - - 4 ------ +- ---- -- 4-I----

I-CALM- 1 121 1 1 .1 .1 .1 .1 .1 .1 .1 .1 12 1 1_m--------------- +- --- 4- ---

- + ---

--- --- ---------- 4- - + - -- --- --

+-I--

[TOTAL I 3651 1078! 10421 10321 16561 20301 8161 3541 1611 1271 241 11 86861

OCONEE NUCLEAR STATION INFORMATION TO SUPPORT THE NUCLEAR ENERGY INSTITUTE (NEI)

GROUNDWATER PROTECTION INITIATIVE

ARERR Groundwater Well Data Section Rev. 1 Duke Energy has begun implementing the Nuclear Energy Institute (NEI) Groundwater Protection Initiative (July, 2007), a voluntary groundwater investigation project adopted by the United States commercial nuclear power industry. This initiative was developed to ensure timely and effective management of situations involving inadvertent releases of licensed material to ground water. Currently, Oconee has twenty-four functional ground water monitoring wells in place. These wells are generally sampled quarterly, with some state required wells being sampled semi-annually or annually. All samples are being analyzed for tritium and gamma emitters. No gamma activity (other than naturally occurring radionuclides) was identified in any of the well samples during 2007.

Additional wells are currently being installed as part of the NEI initiative.

Results from sampling during 2007 are shown in the table below.

Well Name Well Location Annual Average Tritium Concentration in pCi/1 BG-4 Ball Field <MDA MW-3 Landfill <MDA MW-11 Landfill <MDA MW-11D Landfill 500 MW-13 Landfill <MDA MW-16 Landfill <MDA MW-RP01 Landfarm/Burial <MDA MW-RP02 Landfarm/Burial <MDA MW-RP03 Landfarm/Burial <MDA MW A-1 CTP-1/2 2,343 MW A-2 CTP-1/2 2,427 MW A-8 CTP-1/2 228 MW A-9 CTP-1/2 2,801 MW A-10 CTP-3 412 MW A- 1 CTP-3 <MDA MW A- 12 CTP-3 <MDA MW A-13 CTP-1/2 2,653 MWA-14 CTP-1/2 1,787 MW A- 17 CTP-1/2 <MDA MW A-18 CTP-1/2 <MDA 010 (IW-3) Firing Range <MDA 011 (IW-1) Ball Field <MDA 013 (IW-2) WH 5 <MDA 015 Brown's Bottom <MDA pCi/l - pico curies per liter MDA - Minimum detectable activity

ARERR Groundwater Well Data Section Rev. 1 20,000 pCi/I - the Environmental Protection Agency drinking water standard for tritium.

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

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

Attachment III Oconee Nuclear Site Solid Waste Disposal Report

OCONEE NUCLEAR STATION ANNUAL RADWASTE REPORT 2/10/2008 DUKE POWER COMPANY OCONEE NUCLEAR STATION SOLID RADIOACTIVE WASTE SHIPPED TO A DISPOSAL FACILITY REPORT PERIOD: JANUARY - DECEMBER YEAR: 2007 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 STC 622.2 17.62 0.26 (B) DEWATERED BEAD RESIN 6 0 0 4 2 TYPE A 721.8 20.44 609.07 (C) EVAPORATOR CONCENTRATES 0 0 0 0 0 0 0 0.00 0.00 (D) DEWATERED MECHANICAL FILTERS
1. PRIMARY FILTER MEDIA 1 0 0 0 1 TYPE A 120.3 3.41 45.30
2. SECONDARY FILTER MEDIA 0 0 0 0 0 0 STC 0 0.00 0.0000 (E) SOLIDIFIED (CEMENT) OIL, ACIDS,SLUDGES 0 0 0 0 0 0 STC 0 0.00 0.00
2) DRY SOLID WASTE (A) DRY ACTIVE WASTE (COMPACTED) (1) 48 48 48 0 0 0 STC. 9079.5 257.11 2.81 (2) 25 25 25 0 0 0 STC 3298.39 93.40 0.14 (B) DRY ACTIVE WASTE (NON-COMPACTED) 0 .0 0 0 TYPE A 0 0.00 0.00 (C) DRY ACTIVE WASTE (BROKERED) 0 0 0 0 0 0 0.00 0.00 0"

(D) IRRADIATED COMPONENTS 0 0 0 0 0 TYPE B 0 0.00 0.00 TOTAL 82 84 74 0 4 3 13842.18969 391.97 657.58 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 10

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 3 # OF SHIPMENTS TO ENVIROCARE 1 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 0.00 MN-54 0.02 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 .0.00 0.00 0.00 0.02 0.02 CO-57 0.03 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 0.00 0.03 0.03 CO-58 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 0.00 1.03 1.03 CO-60 0.79 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.79 0.79 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 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 CS-134 0.57 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 0.57 0.57 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 AG-110m 1.14 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 1.14 .1.14 SB-125 0.09 0.00 0.00 0.00 0.00, 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.09 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 10.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CS-137 3.88 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 3.88 3.88 H-3 90.57 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 90.57 90.57 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 FE-55 1.75 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.75 1.75 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 00 0.00 0.00 0.00 0.00 0.00 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 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 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 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 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 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 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 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 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 CE-144 0.13 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.13 0.13 TE-132 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00. 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 TOTAL 100 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 100.00 100.00 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 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 CURIES 0.257 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0. 0 0 0 0 0 0.257 CU. FT. 622.2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 622.2 CU. M 17.61907 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 17.61907 RSR# 07-2004 Page 2 of 10

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

  1. OF LINERS SHIPPED TO CNSI 6 ISOTOPE:  % ABUNDANCEILINER # OF SHIPMENTS TO CNSI 6 TOTAL AVE.

CR-51 0.0000 0.0000 0.0000 3.6434 0.0000 1.9114 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 5.5548 0.9258 MN-54 1.1069 1.1299 1.0851 1.7098. 0.9980 2.4203 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 8.4500 1.4083 CO-57 0.8449 0.8268 0.7662 0.3775 0.4817 0.4359 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 3.7330 0.6222 CO-58 15.8996 11.3135 8.8451 44.0952 51.3404 41.5204 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 173.0142 28.8357 CO-60 4.8304 5.1056 5.2169 4.3540 1.7335 5.2570 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 26.4974 4.4162 NB-95 0.0000 0.0000 0.0000 1.3380 0.0000 1.8376 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 3.1756 0.5293 ZR-95 0.0000 0.0000 0.0000 0.9792 0.0000 1.4272 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 2.4064 0.4011 CS-134 8.2678 8.3981 8.8901 1.4248 2.4199 0.1577 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 29.5585 4.9264 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 0.6000 0.0000 AG-110m 0.1180 0.1271 0.0779 3.2756 0.0819 1.1929 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 4.8734 0.8122 SB-125 0.4664 0.4308 0.3335 0.0547 0.0862 0.5440 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 1.9156 0.3193 1-131 0.0000 0.0000 0.0000 0.0003 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 0.0003 0.0001 CS-137 16,6567 17.6955 18.9295 4.5155 -5.2494 0.6570 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 10.0000 0.0000 0.0000 0.0000 0.0000 0.0000 63.7036 10.6173 H-3 0.0747 0.0753 0.0586 0.0139 0.0000 0.0484 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 0.2709 0.0452 NI-63 45.8817 48.7352 49-4647 15.6586 31.1504 19.0948 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 209.9854 34.9976 FE-55 5.6633 5.9614 6.1183 15:0382 5.7686 18.0093 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 56.5591 9.4265 SR-90 0.1439 0,1523 0.1623 0.0391 0.0332 0.0057 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 0.5365 0.0894 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 0,0000 0.0000 0.0000 1.8492 0.0461 2.2598 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 4.1551 0.6925 PU-241 0.0392 0.0416 0.0444 0.7372 0.0000 2.1926 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 3.0550 0.5092.

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 0.0000 0.0000 0.0000 0.1672 0.0007 0.0244 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 0.1923 0.0321 CM-242 0.0001 0.0001 0.0001 b.oo0 0.0000 0.0266 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 0.0367 0.0061 AM-241 0.0006 0.0007 0.0007 0.0081 0.0015 0.0241 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 0.0357 0.0060 PU-239/40 0.0006 0.0006 0.0006 0.0042 0.0004 0.0125 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 0.0189 0.0032 PU-238 0.0017 0.0018 0.0019 0.0121 0.0009 0.0362 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 0.0546 0.0091 CM-243/44 0.0008 0.0009 0.0010 0.0128 0.0001 0.0383 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 0.0539- 0.0090 Be-7 0.0000 0.0000 0.0000 "0.0000 0.4528 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 0.4528 0.0755 SB-124 0.0000 0.0000 0.0000 0.0027 0.0000 0.0028 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 0.0055 0.0009 SN-113 0.0000 0.0000 0.0000 0.0000 0.0000 0.0505 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 0.0505 0.0084 CE-144 0.0028 0.0029 0.0032 0.1299 0.0126 0.3666 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 0.5180 0.0863 FE-59 0.0000 0.0000 0.0000 0.1291 0.0187 0.1340 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 0.2818 0.0470 ZN-65 0.0000 0.0000 0.0000 0.4196 0.0369 0.3120 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 - 0.7685 0.1281 NI-59 0.0000 0.0000 0.0000 0.0000 0.0860 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 0.0860 0.0143 0.0000 0.0007 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 0.0007 0.0001 SR-89 0.0000 0.0000 0.0000 TOTAL 100.00 100.00 100.00 100.00 100.00 100.00 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 0.00 599.91 99.99 CLASS C 0 0 0 1 0 1 0 0 0 0 0 ,0 0 0 0 0 0 0 0 0 2 CLASS B 1 1 1 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4 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 CURIES 66 68.944 88.7 30.74 346 8.69 0 0 0 0 0 0 0 0 0 0 0 0 0 0 609.074 CU. FT. 120.3 120.3 120.3 120.3 120.3 120.3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 721.8 CU. M 3.41 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 20.44 RSR# 07-2002 07-2007 07-2011 07-2028 07-2030 07-2031 Page 3 of 10

Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY DECEMBER WASTE TYPE: COMPACTED DAW (DURATEK) 4 OF SHIPMENTS FROM ONS TO DURATEK 27 # OF CONTAINERS FROM ONS TO DURATEK 47

  1. OF SHIPMENTS FROM PROCESSOR TO ENVIROCARE 48 # OF CONTAINERS FROM PROCESSOR TO ENVIROCARE 48
  1. OF SHIPMENTS FROM PROCESSOR TO BARNWELL 0 # OF CONTAINERS FROM PROCESSOR TO BARNWELL 0 CU. FT. CURIES CU. FT. DISPOSAL CI TO DISPOSAL RSR # SHIPPED SHIPPED FACILITY FACILITY COMPLETED 07-2003 1868.8 0.0278 198.757 0.00509 07-2005 934.4 0.0003 0.000 0.00000 06-2018 0 0.0000 0.004 0.00000 06-2036 0 0.0000 16.700 0.46186 06-2043 0 0.0000 191.668 0.00159 06-2051 0 0.0000 34.600 0.24009 07-2008 186&.8 0.0137 543.260 0.01223 06-2040 0 0.0000 0.229 0.00045 06-2052 0 0.0000 819.220 0.01237 06-2055 0 0.0000 108,525 0.00738 06-2062 0 0.0000 209.579 0.01467 06-2070 0 0.0000 1034.140 0.05944 06-2072 0 0.0000 768.940 0.01001 06-2043 0 0.0000 174.738 0.00213 06-2050 0 0.0000 3.700 0.00009 06-2051 0 0.0000 33.900 0.15251 07-2012 1868.8 00009 518.307 0.00082 06-2046 0 0.0000 70.730 0.00013 06-2074 0 0.0000 806.780 0.03620 06-2044 0 0.0000 1116.680 0.01613 07-2013 1868.8 0.0126 208.286 0.01255

.07-2015 18688 0.0101 195.143 0.01005 06-2017 0 0.0000 19.500 0.00787 07-2017 934.4 0.0008 65.143 0.00084 07-2018 1868.8 0.1510 221.000 0.14486 07-2020 934.4 0.0166 112.786 0.01701 07-2021 1868.6 0.0388 196.857 0.03874 07-2032 1868.8 0.3560 241.143 0.35582 07-2033 1868.8 00542 82.000 0.04019 07-2034 934.4 000112 102.014 0.00568 07-2035 1868.8 0.0300 81.429 0.00294 07-2036 223.5 3.0000 0.000 0.00000 07-2037 1868.8 1.2500 246.500 0.69260 07-2038 1868.8 0.0143 134.143 0.01320 07-2039 1868.8 0.3040 128.857 0.30029 06-2054 0 0.0000 44.527 0.00002 07-2041 1868.8 0.0845* 349.714 0.13375 07-2042 1868.8 0.0113 0.000 0.00000 07-2044 1868.8 0.0033 0.000 0.00000 07-2046 1868.8 0.0578 0.000 0.00000 07-2048 1597.7 0.0579 0.000 0.00000 07-2054 1868.8 0.3800 0.000 0.00000 07-2058 1868.8 0.2480 0.000 0.00000 07-2060 1868.8 0.3160 0.000 0.00000 07-2061 9344 0.0172 0.000 0.00000 0 0.0000 0.000 0.0000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 TOTAL 43869.2 6.458 9079.50 2.81158 TOTAL CURIES BURIED 2.812 TOTAL CUBIC FEET BURIED 9079.50 TOTAL CUBIC METERS 257.11 Page 4 of 10

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

  1. OF SHIPMENTS FROM ONS TO CNSI
  1. OF CONTAINERS FROM ONS TO CNSI RSR CUBIC NUMBER FEET CURIES A-U A-S B C o 0 0 0 0 0 0 0 0 0 0 0 0 o 0 0 0 0 o o 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 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 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 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 0 0 0 0 0 TOTAL CUBIC METERS 0.00 Page 5 of 10

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

  1. OF SHIPMENTS TO DECON FACILITY 10 # OF SHIPMENTS TO DISPOSAL FACILITY: 25
  1. OF CONTAINERS TO DECON FACILITY 10 # OF CONTAINERS TO DISPOSAL FACILITY 25 DECON/DISP. CU. FT. CURIES CU. FT. TO CURIES TO RSR # FACILITY. TO PROCESSOR TO PROCESSOR DISPOSAL FACILITY DISPOSAL FACILITY COMPLETED 07-2001 GIC 934.4 0.00233 0.00 0.00000 07-2005 934.4 0.0299 338.45 0.02991 06-2066 0 0 449.38 0.00328 06-2065 0 0 598.65 0.05620 06-2072 *GIC 0 0 98.08 0.00028 06-2040 0 0 0.19 0.00040 06-2064 0 0 629.13 0.00502 07-2017 934.4 0.000157 104.86 0.00016 07-2020 319.76 0.0118 164.93 0.01134 06-2017 0 0 11.30 0.00220 06-2068 0 0 350.56 0.00224 07-2034 934.4 0.0284 210.56 0.02382 06-2069 0 0 333.08 0.00623 07-2059 756 0.0228 0.00 0.00000 07-2061 934.4 0.0299 0.00 0.00000 07-2062 934.4 0.00733 0.00 0.00000 07-2063 934.4 0.00783 0.00 0.00000 07-2064 642.1 0.00764 0.00 0.00000 07-2018 0 0 2.23 0.00001 07-2038 0 0 7.00 0.00112 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000

.0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 TOTAL 8258.66 0.148087 3298.39 0.14222 TOTAL CUBIC METERS 93.40179 Page 6 of 10

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

  1. OF CONTAINERS SHIPPED TO CNSI/DURATEK ISOTOPE:  % ABUNDANCE/LINER # 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 #DIV/0!

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!

ZR795 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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/I!

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/I!

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 #DIV/0!

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/OI!

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 O000 '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/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 #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/O!

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 #DIVI0!

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 #DIVIO!

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 #DIVI0!

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/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 #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 U 0 0 0 0 0 0 U 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 7 of 10

OCONEE NUCLEAR STATION SOLID RADWASTE 6155I1 Nuclear Station Annual Report REPORT PERIOD: JANUARY - DECEMBER WASTE TYPE: PRIMARY FILTERS

  1. OF DRUMSUINERS TO CNSI 1 ISOTOPE: # OF SHIPMENTS TO CNSI 1 TOTAL AVE.

CR-51 0.30 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.30 0.296 MN-54 0.25 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.25 0.250 CO-57 0.43 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.43 0.431 CO-58 74.25 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 74.25 74.248 CO-60 1.85 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.85 1.852 NB-94 0.00 0.00 0.00 0.00 . 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 TC-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 0.00 0.00 0.00 0.000 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 0.000 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 0.000 AG-110m 0.65 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.65 0.648 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 0.000 1-129 - 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 0.07 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 . 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.07 0.075 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 0.000 NI-63 10.08 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 0.00 10.08 10.077 FE-55 10.50 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 0.00 10.50 10.496 SR-9O0 0.00 0.00 . 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ý0.00 0.000 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 0.000 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 0.000 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 . 000 0.00 0.00 0.000 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 0.000 PU-241 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 .000 0.00 0.00 0.00 0.04 0.037 PU-238 0.0011 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.001 PU-239 0.0004 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00, 0.00 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 0.02 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 0.00 0.02 0.018 RU-1 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 "0.00 0.00 0.00 0.000 CE-144 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.015 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 0.000 CE-141 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 '0.00 0.00 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 0.0004 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.007 CM-243/44 0.0011 0.00 0.00 0.00 0.00 0.00, 0.00 0.00 0.00. 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.001 NB-95 0.57 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 0.57 0.570 ZR-95 0.85 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 . 0.00 0.00 0.00 . 0.00 0.00 0.85 0.849 HG-203 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 0.08 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 0.00 0.083 0.083 CD-109 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 0.05 0.00 0.00 0.00 0.00 0.00- 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 . 0.00 0.00 0.00 0.00 0.00 0.00 0.0466 0.04660 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 0.00 100.00 100.00 CLASS C 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 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 CURIES 45:3 0 0 0 0 0 0 0 0 0 0 0 *0 0 0 0 0 0 0 0 45.3 CU- FT. 120.3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 120.3 CU.,M 3.406581 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0. 0 0 0 0 3.406581 RSR# 07-2010 Page 8 of 10

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

  1. OF CONTAINERS SHIPPED TODURATEK 0 # OF CONTAINERS SHIPPED TO CNSI"ENVIROCARE 0
  1. OF SHIPMENTS TO OURATEK 0 # OF SHIPMENTS TO CNSI! ENVIROCARE 0 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/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 #DIV/O!

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 #DIV/01 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 #DIV/0!

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 #DIV/0I 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/0I 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 #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 #DIV/O!

AG-110m 0.00 0.00 0.00 1.0.00 0.00 0.00 0.00 0.00 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 SB-125 0.00 0.00 0.00 0.00 000 0.00 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 #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 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIVI01 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 #DIV/0I 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/0I 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/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 #DIVIO!

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/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 #EIV/0I 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 #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 #DIV/0!

TRU 0.00 0.00 0.00 0.00 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 #DIV/O!

1 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/I!

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 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 #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 #DIV/O!

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 #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 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 FT3 Shipped 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CU. M Shipped 0.0000 0.0000 0.0000 0.0000 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 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#

K.

Page 9 of 10

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

  1. OF CONTAINERS SHIPPED 0 ISOTOPE:  % ABUNDANCE/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 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 0.00 #DIV/O!

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/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. 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/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 0.00 #DIV/O!

CS-1 34 0.00 0.00 0.00 0.00. 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 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 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 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/C!

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/O!

CS-1 37 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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!

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 0,00 000 000 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/01

  1. 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 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/O0 XE-1 33 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 .0.00 0.00 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/0O 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/O!

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/O!

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/O!

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/O!

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/O!

RU-1 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 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0O 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/C!

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/O!

0.00 0.00 #DIV/0f 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 -#D0V/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 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 10 of 10

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

p Attachment V Oconee Nuclear Site Unplanned Offsite Releases

OCONEE NUCLEAR STATION UNPLANNED RELEASES (January 1, 2007 through December 31, 2007)

There were no unplanned liquid or unplanned gaseous radioactive effluent releases to the environment in 2007.

Attachment VI Assessment of Radiation Dose from Radioactive Effluents to Members of the Public

OCONEE NUCLEAR STATION Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (January 1, 2007 through December 31, 2007)

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. This attachment also includes an assessment of radiation doses to the maximum exposed member of the public from all uranium fuel cycle sources within 10 miles 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 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 ist Quarter 2007 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 1 2007 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q1 - Maximum Organ Dose CHILD THYROID 6.42E-03 2.25E+01 2.85E-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 9.86E+01 NOBLE GAS DOSE LIMIT ANALYSIS==-......=======-....-======= Quarter 1 2007 Dose Limit  % of Period-Limit (mrad) . (mrad) Limit Q1 - Maximum Gamma Air Dose 2.24E-03 1.50E+01 1.49E-02 Maximum Gamma Air Dose Receptor Location: 1.0 Mile SW Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage XE-133 6.43E+01 XE-135 3.56E+01 Q1 - Maximum Beta Air Dose 5.31E-03 3.OOE+01 1.77E-02 Maximum Beta Air Dose Receptor Location: 1.0 Mile SW Major Contributors (5% or greater to total)

Nuclide Percentage XE-133 8.07E+01 XE-135 1.93E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 2 nd Quarter 2007 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 2 2007 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose CHILD THYROID 5.27E-03 2.25E+01 2.34E-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 6.06E+01 1-131 3.B7E+01 NOBLE GAS DOSE LIMIT ANAIYSIS -Quarter 2 2007 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Q2 - Maximum Gamma Air Dose 2.28E-03 1.50E+01 1.52E-02 Maximum Ganmna Air Dose Receptor Location: 1.0 Mile SW Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage XE-133 6.81E+01 XE-135 3.11E+01 Q2 - Maximum Beta Air Dose 5.59E-03 3.00E+01 1.86E-02 Maximum Beta Air Dose Receptor Location: 1.0 Mile SW Major Contributors (5% or greater to total)

Nuclide Percentage XE-133 8.28E+01 XE-135 1.62E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 3 rd Quarter 2007 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 3 2007 Critical Critical Dose Limit Max % of Period-Limit Age ' Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose CHILD THYROID 4.77E-03 2.25E+01 2.12E-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 9.99E+01 NOBLE GAS DOSE LIMIT ANALYSIS========================== Quarter 3 2007 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Q3 - Maximum Garmma Air Dose 1.35E-03, 1.50E+01 9.02E-03 Maximum Gamma Air Dose Receptor Location: 1.0 Mile SW Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage XE-133 7.58E+01 XE-135 2.34E+01 Q3 - Maximum Beta Air Dose 3.50E-03 3.OOE+01 1.17E-02 Maximum Beta Air Dose Receptor Location: 1.0 Mile SW Major Contributors (5% or greater to total)

Nuclide Percentage XE-133 8.72E+01 XE-135 1.16E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 4th Quarter 2007 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 4 2007 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose INFANT THYROID 7.26E-02 2.25E+01 3.23E-01 Maximum Organ Dose Receptor Location: 4.5 Mile NE Critical Pathway: Goat Milk Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage 1-131 9.94E+01 NOBLE GAS DOSE LIMIT ANALYSIS===-====================== Quarter 4 2007 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Q4 - Maximum Gamma Air Dose 2.08E-03 1.50E+01 1.39E-02 Maximum Gamma Air Dose Receptor Location: 1.0 Mile SW Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage XE-133 9.51E+01 Q4 - Maximum Beta Air Dose 6.49E-03 3.OOE+01 2.16E-02 Maximum Beta Air Dose Receptor Location: 1.0 Mile SW

.Major Contributors (5% or greater to total)

Nuclide Percentage XE-133 9.08E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 AMUAL 2007 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS======= Annual 2007 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose INFANT THYROID 7.67E-02 4.50E+01 1.70E-01 Maximum Organ Dose Receptor Location: 4.5 Mile NE Critical Pathway: Goat Milk Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage 1-131 9.84E+01 NOBLE GAS DOSE LIMIT ANALYSIS===-====================== Annual 2007 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Yr - Maximum Ganmna Air Dose 7.96E-03 3.00E+01 2.65E-02 Maximum Gamma Air Dose Receptor Location: 1.0 Mile SW Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage XE-133 7.54E+01 XE-135 2.35E+01 Yr - Maximum Beta Air Dose 2.09E-02 6.OOE+01 3.48E-02 Maximum Beta Air Dose Receptor Location: 1.0 Mile SW Major Contributors (5% or greater to total)

Nuclide Percentage XE-133 8.55E+01 XE-135 I*.15E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 1St Quarter 2007 BATCH LIQUID RELEASES Quarter 1 2007 ======

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q1 - Maximum Organ Dose CHILD GI-LLI 1.85E-02 1.50E+01 1.24~E-01 Q1 - Total Body Dose CHILD 1.85E-02 4.50E+00 4.11E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.95E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.97E+01 CONTINUOUS LIQUID RELEASES (CTP 3) Quarter 1 2007 ......

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q1 - Maximum Organ Dose CHILD LIVER 2.86E-05 1.50E-*01 1.90E-04 Q1 - Total Body Dose CHILD 2.86E-05 4.50E+00 6.34E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1. 00E+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 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 2 nd Quarter 2007 BATCH LIQUID RELEASES---------- Quarter 2 2007 ......

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose CHILD LIVER 2.03E-02 1.50E+01 1.35E-01 Q2 - Total Body Dose ADULT 1.89E-02 4.50E+00 4.20E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 8 .72E+01 CS-137 1.25E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.01E+01 CS-137 9.34E+00 CONTINUOUS LIQUID RELEASES (CTP 3) Quarter 2 2007 ======

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose CHILD LIVER 1.73E-05 1.50E+01 1.15E-04 Q2 - Total Body Dose CHILD 1.73E-05 4.50E+00 3.85E-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.OOE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 3rd Quarter 2007 BATCH LIQUID RELEASES---------------===--=---=---=---- Quarter 3 2007 ======

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose ADULT GI-LLI 1.03E-02 1.50E+01 6.89E-02 Q3 - Total Body Dose CHILD 1.02E-02 4.50E+00 2.27E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.47E+01 CO-58 5.14E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.93E+01 CONTINUOUS LIQUID RELEASES (CTP 3)--=-=--=-=---======= Quarter 3 2007 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose CHILD LIVER 1.92E-05 1.50E+01 1.28E-04 Q3 - Total Body Dose CHILD 1.92E-05 4.50E+00 4.27E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00E+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H -- ------

H-3 1.00E+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 4 th Quarter 2007 BATCH LIQUID RELEASES == Quarter 4 2007 ......

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose ADULT LIVER 3.75E-02 1.50E+01 2.50E-01 Q4 - Total Body Dose ADULT 3.03E-02 4.50E+00 6.74E-01 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage CS-137 5.64E+01 H-3 4.32E+01 Total Body Critical.Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 5.34E+01 CS-137 4.57E+01 CONTINUOUS LIQUID RELEASES (CTP 3) Quarter 4 2007 ======

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose CHILD LIVER 2.20E-05 1.50E+01 1.47E-04 Q4 - Total Body Dose CHILD 2.20E-05 4.50E+00 4.89E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00E+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.OOE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 ANNUAL 2007 BATCH LIQUID RELEASES-------------..................... Annual 2007 ....... =

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose CHILD LIVER 8.59E-02 3.00E+01 2.86E-01 Yr - Total Body Dose ADULT 7.69E-02 9.OOE+00 8.54E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 7.35E+01 CS-137 2.62E+01 Total Body Critical Pathway: Fresh WaterFish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 7.90E+01 CS-137 2.03E+01 CONTINUOUS LIQUID RELEASES (CTP 3) Annual 2007 ...... --

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose CHILD LIVER 8.71E-05 3.OOE+01 2.90E-04 Yr - Total Body Dose CHILD 8.71E-05 9.OOE+00 9.68E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00E+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00E+02

Oconee Nuclear Station 2007 Radioactive Effluent Releases 40CFR190 Uranium Fuel Cycle Dose Calculation Results In accordance with the requirements of 40CFRI90, 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. 2007 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 = 9.69E-02 mrem Maximum Location: 1.0 Mile, South-West Sector Critical Age: Adult Gas non-NG Contribution: 14%

Gas NG Contribution: 7%

Liquid Contribution: 79%

Maximum Organ (other than TB) Dose = 1.36E-01 mrem Maximum Location: 1.0 Mile, South-West Sector Critical Age: Child Critical Organ: Thyroid Gas Contribution: 52%

Liquid Contribution: 48%

II. 2007 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 i0CFR72.212 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 following two 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 39 , stipulates that the licensee perform dose evaluations which establish that any real individual beyond the controlled area boundarynot 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 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, bumup 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. 40 Calculation OSC-867541 develops the radiation source terms used in subsequent shielding and skyshine calculations using the SCALE Code System-42 More specifically, the SAS2 Module of the SCALE Code System was used to create a problem-dependent pin-cell model for the purpose of building cell-Oconee Nuclear Site IOCFR72.212 Written Evaluations, Rev. 2 Page 22 of 32

weighted, multigroup cross section sets for use in subsequent depletion calculations. The ORIGEN-S Module 43of 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-870644 to evaluate the shielding characteristics of a single Horizontal Storage Module. The MCNP Monte Carlo particle transport computer code 45 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 andidata used in these analyses (specifically, Calculation DPC-1201.30 001046 contains the verification and validation for MCNP5, while SDQA-70321-COM documents the quality control measures in place for MCNP5).

Calculation OSC-8716 47 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 <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> of occupancy per year) the annual dose at the nearest controlled area boundary (approximately 300 meters) is below the 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 I mile 48

(-1600 meters) from the ISFSI, or 1.36 miles from the centerline of the site.

Oconee NuclearSite 10CFR72.212 Written Evaluations, Rev. 2 Page 23 of 32

Attachment VII SLC 16.11 Radiological Effluent Controls

Radioactive Liquid Effluents 16.11.1

%.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 ýtCi/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 07/12/01 I

Radioactive Liquid Effluents 16.11.1

d. Chemical Treatment Ponds (CTP 1 and 2)
1. The quantity of radioactive material in the Chemical Treatment Ponds (CTP) shall be limited so That, for all radionuclides identified, excluding noble gases and tritium, the sum of the ratios of activity (in curies) to the limits in 10 CFR 20, Appendix B, Table 2, column 2 shall not exceed .1.7 x 106.

AJ < 1.7 x 10' j Cj Where Aj = pond inventory limit for single radionuclide "j" (curies)

Cj = 10 CFR 20, Appendix B, Table 2, Column 2, concentration for single radionuclide "j"(curies)

2. No powdex resin shall be transferred to the CTPS unless the sum of the activity of the radionuclides identified is less than 0.1% of the limit identified in Commitment d.1.

Qz < 1.0x 10-3 i Aj where Qj = radionuclide'activityin resin Aj = pond inventory limit for radionuclide "j"

3. The total radionuclide inventory of used powdex resin transferred to the Chemical Treatment Ponds over the previous 13 weeks, shall not exceed 0.4% of the pond radionuclide inventory limit.

Decay of radionuclides may be taken into account in determining inventory levels.

+ Qj, < .004 x Aj Qj1 + Qj2 + Qj 3 +- ------

where, Qj Total inventory of radionuclide j in a transfer n Number of transfers to the Chemical Treatment Ponds during the previous 13 - week period.

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

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.

16.1 1.1 -2 07/12/01 1

Radioactive Liquid Effluents 16.11.1 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.

16.1 1.1-3 07/12/01 I

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.

16.11.1-4 07/12/01 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 whichý 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.

D. Total radioactive D.1 Submit report to the 30 days inventory of used regional NRC Office powdex resins describing the reason(s) transferred to the for exceeding ihe limit and Chemical Treatment plans for future operation.

Ponds over previous 13,weeks greater than 0.4% of the pond radionuclide inventory limit.

SURVEILLANCE REQUIREMENTS

,SURVEILLANCE FREQUENCY SR 16.11.1.1 N/A N/A 16.11.1-5 07/12/01 1

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 result in the activation of the Oconee 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 II.D of Appendix A to 10 CFR Part 50.

16.11.1-6 071/0

Radioactive Liquid Effluents, 16.11.1 The inventory limits of the chemical treatment ponds are based on limiting the consequences of an uncontrolled release of the pond inventory. The short term ,rate limit (2 mrem/hr) of 10 CFR 20.1301 is applied to 10 CFR 20.1302 in the following expression:

-Ai x 106 JICi x gal < 2 mrem/hr x 8760 hr 1.3 x 10 gal Curie 3785 ml 500 mrem/yr yr 10 x Cj 6

Ai < 1.7x10 Cj Where Aj = pond inventory limit for radionuclide "j" (curies)

Cj = 10 CFR 20, Appendix B, Table 2, Column 2, concentration radionuclide "j" 1.3 x 106 gal = estimated volume of smaller chemical treatment pond The transfer limits provide assurance that activity input to the CTP will be minimized.

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 16.1 1.1-7 07/12/01 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.ý 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 IOCFR20.1302). 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 IOCFR20.106 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 10CFR50.36a 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 I0CFR50 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.

16-1 1.2-6 01/31/00 I

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 16.11.1 .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 12/04/07 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 12/04/07 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 limit of detection I tCi/ml.

of at least 10-7 16.11.3-3 12/04/07 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter 16.11.3-4 12/04/07 I

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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of at least 10-7 lCi/ml. thereafter 16.11.3-5 12/04/07 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 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 11.2 Suspend release of Immediately radioactive effluents by this pathway.

16.11.3-6 12/04/07 1

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 Purge, Interim removals from service for Radwaste Exhaust, Hot durations not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter 16.11.3-7 12/04/07 1

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

N------

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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> AND K.2.2 Analyze grab samples 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from collection for gross activity (beta of sample and/or gamma).

16.11.3-8 12/04/07 I

-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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 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)

L.1 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> from end of each sample collection 16.11.3-9 12/04/07 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 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.

SOR 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> AND, M.3.2 Analyze grab sample for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from collection gross activity (beta of grab sample and/or gamma).

16.11.3-10 12/04/07 .1

Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 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.

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 16.11.3.3 Perform Source Check. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 16.11.3.4 Perform Source Check. 31 days SR 16.11.3.5 Perform Source Check. 92 days 16.11.3-11 12/04/0.7 1

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.

SR16.11.3.8 Perform CHANNEL FUNCTIONAL TEST. 92 days 16.11.3-12 12/04/07 1

Radioactive Effluent Monitoring Instrumentation 16.11.3 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.

SR 16.11.3.10 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to each release via associated pathway 16.11.3-13 12/04/07 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 Monitors Providing Automatic Termination of Release

a. Liquid Radwaste Effluent 1 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 12/04/07 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 (at
4. Continuous Composite Sampler
  1. 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. It no hydro units are operating, leakage tlow will be assumed to be 38 cfs based on historical data.

16.11.3-15 1/40 12/04/07 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

1. Unit Vent Monitoring System
a. Noble Gas Activity 1 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 At all 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 1 At All Times SR 16.11.3.2 L 1
d. Particulate Sampler At All Times SR 16.11.3.2 L 1
e. Effluent Flow Rate At All Times SR 16.11.3.2 j Monitor (Unit Vent Flow) SR 16.11.3.10 (GWD CR0037 for Unit 2)(MSC CR0O01 for Units 1& 3)
t. Sampler Flow Rate At All Times SR 16.11.3.2 NA Monitor (a) (Annunciator) SR 16.11.3.10
g. Effluent Flow Rate 1 During Containment SR 16.11.3.2 M Monitor (Containment Purge Operation SR 16.11.3.10 Purge) (PR CR0082 for Unit 2)(MSC CR0001 for Units 1 & 3)
h. CSAE Off Gas Monitor 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
b. Iodine Sampler 1 At All Times SR 16.11.3.2 L 1
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 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 12/04/07 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 At All Times SR 16.11.3.2 L
b. Particulate Sampler 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 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 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 AliTimes SR 16.11.3.2 L
d. Effluent Flow Rate 1 At All Times SR 16.11.3.2 J Monitor (Radwaste SR 16.11.3.10 Facility Exhaust) (OVS CR2060)
e. Sampler Flow Rate 1 At All Times SR 16.11.3.2 NA Monitor (a)(Annunciator) SR 16.11.3.10
5. Waste Gas Holdup Tanks
a. Noble Gas Activity 1 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 Termination of Release SR 16.11.3.12 (RIA-37,-38)b
b. Effluent Flow Rate 1 During Waste Gas SR 16.11.3.1 J Monitor (Waste Gas Holdup Tank Releases SR 16.11.3.10 Discharge Flow) (MSC CRO001)

(a)Alarmsindicating 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 12/04/07 1

Radioactive Effluent Monitoring Instrumentation 16.11.3 BASES The radioactive liquid effluent instrumerhtation 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 1 6.11.2. 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> end every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> upon RIA removal from service. SLC 16.1 1.3 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, durihg 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />), 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. 10 CFR 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 12/04/07 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 16.11.4-1 16.11.4-111/10/04

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 Condensate Test a. Principal Gamma Composite Grab Sample <5E-06 pCi/ml (Ce-144)

Tank, Condensate Emitters(c) including prior to release of each <5E-07 pICi/mI (Other Gamma Nuclides)

Monitoring Tank, Dissolved Noble batch(h) . <1 E-05 gCi/ml (Dissolved Gases)

Laundry-Hot Gases <1E-06 pCi/ml (1-131)

Shower Tank, 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 <1 E-05 MCi/ml
d. Gross Alpha Activity Monthly Composite <1E-07 IpCi/ml
2. Unit Vent Sampling a. Iodine Spectrum (a) Continuous monitor, < 1E-10 pCi/cc (I-133)0)

(includes Waste weekly sample(e) <1E-12 pCi/cc (I-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 VCi/cc(j)

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

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

c. Gases by Principle Weekly Grab Sample <1 E-04 iCVcc Gamma Emitters(d)
d. Tritium Weekly Grab Sample <1 E-06 pCi/cc
3. Waste Gas Decay a. Principle Gamma Grab Sample prior to <1 E-04 t[Ci/cc (gases)

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

<5E-09 p.Ci/cc (Ce-1i44 and Mo-99)

b. Tritium Grab Sample prior to <1 E-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 p.Ci/cc (particulates and iodines)

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

b. Tritium Grab sample each purge <1 E-06 gCi/cc 16.11.4-2 11110104 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. Backwash Receiving Principle Gamma Emitters Grab Sample pdor to NA Tanks including dissolved Noble release of each batch Gases
6. #3 Chemical a. Principle Gamma Weekly Continuous <5E-07 pCilml Treatment Pond Emitters(c) Composite(g)

Effluent(')

b. 1-131 Weekly Continuous <1 E-06 pCi/ml Composite(g)
c. Tritium Monthly Continuous <1-E-05 pCi/ml Composite(g)
d. Gross Alpha Monthly Continuous <1E-07 gCi/ml Activity Composite(g)
e. Sr-89 &Sr-90 Quarterly Continuous <5E-08 pCi/ml Composite(g)
f. Dissolved and Monthly Grab <1 E-05 pCVml Entrained gases (Gamma Emitters)

Radwaste Facility a. Iodine Continuous monitor, (1-133) <1E-09 ipCVcc Ventilation Spectrum(a) weekly sample(e) (1-131) <1E-11 igCVcc

b. Particulate(a)
i. Ce-1 44 and Mo- Weekly Composite(e) <5E-10 ViCicc(j) 99 ii. Other Principle Weekly Composite(e) <1E-1 1 liCi/cc(j)

Gamma Emitters(d) iii. Gross Alpha Monthly, using composite <i1E-1 I g*CVcc Activity samples of one week iv. Radiochemical Quarterly Composite <1E-11 pCilcc Analysis Sr-89, Sr-90

c. Gases by Weekly Grab Sample <1E-04 lxCicc Principle Gamma(d)

Emitters

d. Tritium Weekly Grab Sample <1 E-06 pCi/cc 16.11.4-3 11/10/04 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

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

Ventilation (1-131) <1 E-12 i+/-Ci/ccU)

b. Particulate Ce-144 and Mo- Weekly Composite(e) <5E-10 ttCi/cc(j) 99 ii. Other Principle Weekly Composite(e) <1 E-1 I pCi/ccaj)

Gamma Emitters (d)

<1 E-1 1 liCVcc iii. Gross Alpha Monthly, using composite Activity samples of one week.

iv. Radiochemical Quarterly Composite <1E-11 VCi/cc Analysis Sr-89, Sr-90

c. Gases by NA NA Principle Gamma Emitters
d. Tritium NA NA Interim Radwaste a. Iodine Spectrum Weekly sample(e) (1-133) <1 E-10 .CVcc(j)

Building (1-131) <1E-12 pCVcc(j)

Ventilation

b. Particulate
i. Ce-144 and Mo- Weekly Composite(e) <5E-10 pCVcc(j) 99 ii. Other Principle Weekly Composite(e)

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

c. Gases by Weekly Grab Sample <1 E-04 iVCVcc Principle Gamma(d)

Emitters

d. Tritium Weekly Grab Sample <1 E-06 VCi/cc 16.11.4-4 11/10/04 1

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

(b) The LLD is defined for purposes of these commitments as the smallest concentration 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:

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

)

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),

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 Pdriori (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-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 g/CVml. 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-133. Xe-133m, Xe-135. and Xe-138 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 Inwhich 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 inliquid effluents, samples shall be collected continuously inproportion to the rate of flow of the effluent stream. Prior to analysis, all samples taken for the composite shall be thoroughly mixed inorder for the composite sample to be representative of the effluent release.

16.11.4-5 11/10/04 I

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

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

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

16.11.4-6 16.1.4-611/10/04 1

Operational Safety Review 16.11.4 BASES N/A

REFERENCES:

N/A 16.11.4-7 11/10/04 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 test as 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.

I 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".

16.11.5-4 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 02/01/051

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.

16.11.6-3 102/01/05 1

Radiological Environmental Monitoring 16.11.6 Table 16.11.6-1 Radiological Environmental Monitoring Program Number of Sampling and Collection Exposure Pathway and/or Sample Time and Frequency of Analysis Sample Locations (b) Frequency (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 Number of Smln n olcin Tm n rqec fAayi Exposure Pathway and/or SapeSample me Sampling and Collection Frequency (d) Time and Frequency of Analysis Sample 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

(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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 ifspecimens are unobtainable due to hazardous conditions, seasonal unavailability, or to malfunction of automatic sampling equipment. If the 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 Broad-leaf Particulate or Fish Milk Vegetation Sediment Analysis Water (pCi/I) Gases (pC/kg, (pCi/I) (pCpgkg, dry) 3 wet) (p( wet) kdkg, (pCVm )

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 Nb-95 15 15 I

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 15 60 La- 140 15 15 (a) The LLD is defined, for purposes of these commitments, as the smallest concentration 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 02/01/05 I

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 tractional 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 posterior (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 1 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 1-131 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 (pci/I) Gases (pCi/kg, wet) (pci/I) (pcikg, wet)

(pCi/rn 3 )(pikwt 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-1 40 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 r 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 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 I

If COMPLETION TIME ,

- N O "T E _,',_`!!, fil . ij'

-i I, B. Calculated dose C I I IA Iexceeds limits of. Th'is Special Report, a's defined I.i 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 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.

9' I; B.1 Prepare and submit to the Commission a" 30 days Special Report that defines the corrective action to be taken to

.1 I reduce subsequentj!.;

releases to prevent,.

recurrence of exceeding ii t i" `;q the specified limits and

.... : I::.p llt.,ncludesthe 0 aclhievin'g schedule

' :
  • i .,:

conformance with the specified limits.

~iI; 16.11.7-2 01/31/00 I

Dose Calculations 16.11.7 CONDITION REQUIRED ACTION COMPLETION TIME C. Calculated dose C.-1 --------- 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.

of resulting in violation 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 1

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 Chemical Treatment Ponds, SLC 16.11.1 .d
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 09/25/03 I

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 09/25/03 1

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 an assessment of the radiation dose from radioactive effluents to members of the public due to their activities inside the unrestricted area boundary during the reporting period. All assumptions used in making these assessments (e.g., specific activity, exposure time and location) shall be included in these reports.

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 16.11.9-1 11/14/00 I

Radioactive Effluent Release Report 16.11.9 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.

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 01/31/00 I

Radioactive Effluent Release Report 16.11.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. N/A A.1 N/A N/A I 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 01/31/00 I

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 SL-Cs taken during the report period. In the 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 16.1110-102/25/03 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 0/79 03/27/99

Radioactive Material in Outside Temporary Tanks Exceeding Limit 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 5.5.1 3.c.

APPLICABILITY: At all times.

ACTI ONS ___________ ________

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 16.1112-104/10/03 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

NOTE 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 A.2 Reduce tank contents 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.13.1 Verify quantity of radioactive materials in each 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 03/27/99

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 Gas16.11.14 Mixture 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

NOTE-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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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

Enclosure

Retrieved from "https://kanterella.com/w/index.php?title=ML081430505&oldid=2569208"