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Annual Radioactive Effuent Release Report for 2012
	ML13116A215
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/26/2013
From:	Pyle S; Entergy Operations
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	ocan041307
	Download: ML13116A215 (243)
	v • d • e

0CAN041307

April 26, 2013

U.S. Nuclear Regulatory Commission

Attn: Document Control Desk

Washington, DC 20555

SUBJECT:

Annual Radioactive Effluent Release Report for 2012 Arkansas Nuclear One, Units 1 and 2

Docket Nos. 50-313 and 50-368

License Nos. DPR-51 and NPF-6

Dear Sir or Madam:

Arkansas Nuclear One, Units 1 and 2 (ANO-1 and ANO-2) Technical Specifications (TSs)

5.6.3 and 6.6.3, respectively, require the submittal of an Annual Radioactive Effluent Release

Report (ARERR) prior to May 1 of each year. The information to fulfill this reporting

requirement for ANO-1 and ANO-2 for the 2012 calendar year is enclosed.

Liquid and gaseous release data show that the dose from both ANO-1 and ANO-2 was

considerably below the Offsite Dose Calculati on Manual (ODCM) limits. The data reveals that radioactive effluents had an overall minimal dose contribution to the surrounding environment.

Carbon-14 (C-14) is a naturally occurring isotope of carbon. C-14 is produced in commercial

nuclear reactors, but the amounts produced are much less than those produced naturally.

Radioactive effluents from commercial nuclear power plants have decreased to the point that

C-14 can become a principle radionuclide in gaseous effluents, as defined in Regulatory

Guide 1.21. Therefore, concentrations and offsite dose from C-14 have been estimated and

included in this report for ANO.

Pursuant to ANO-1 TS 5.5.1 and ANO-2 TS 6.5.1, a copy of the revision (Revision 20) of the

ODCM that was effective by the end of calendar year 2012 is submitted as Attachment 1 to the ARERR.

As noted in the ARERR, the Process Control Program, EN-RW-105, was not revised in 2012.

A copy of the latest revision to this program is also attached, (Attachment 2) for information

only.

During preparation of this submittal, the graph representing the ANO-1 historical gaseous

effluents was noted to be incorrect due to an editorial error. The supporting data for the graph

has since been verified as accurate and the corrected page for the report submitted in 2012 is

included as Attachment 3 of this submittal.

Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802

Tel 479-858-4704 Stephenie Pyle Manager, Licensing A rkansas Nuclear One

0CAN041307 Page 2 of 2

There are no new regulatory commitments contained in this submittal.

Should you have any questions regarding this report, please contact me.

Sincerely,

ORIGINAL SIGNED BY STEPHENIE L. PYLE

SLP/rwc

Enclosure:

Annual Radioactive Effluent Release Report for 2012

Attachments: 1. Offsite Dose Calculation Manual 2. EN-RW-105, "Process Control Program"

3. Revised ARERR Graph for ANO-1 Historical Gaseous Effluents

cc: Mr. Arthur T. Howell Regional Administrator U. S. Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511

NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310

London, AR 72847 U. S. Nuclear Regulatory Commission

Attn: Mr. Kaly Kalyanam

MS O-8 B1

One White Flint North

11555 Rockville Pike

Rockville, MD 20852

Mr. Bernard R. Bevill

Arkansas Department of Health

Radiation Control Section

4815 West Markham Street Slot #30 Little Rock, AR 72205

ENCLOSURE TO 0CAN041307 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2012

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 1 of 113 TABLE OF CONTENTS

1. INTRODUCTION..................................................................................................................2

2. REGULATORY LIMITS........................................................................................................2

3.

SUMMARY

OF LIQUID EFFLUENT DATA..........................................................................4

4.

SUMMARY

OF GASEOUS EFFLUENT DATA..................................................................13

5.

SUMMARY

OF RADIATION DOSES.................................................................................22

6.

SUMMARY

OF DOSE TO MEMBERS OF THE PUBLIC..................................................24

7. HISTORICAL EFFLUENT DATA........................................................................................25

8. SOLID WASTE

SUMMARY

...............................................................................................41

9. UNPLANNED RELEASES...............................................................................................107

10. RADIATION INSTRUMENTATION..................................................................................107

11. CHANGES TO THE PROCESS CONTROL PROGRAM.................................................107

12. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL....................................107

13. LLD LEVELS....................................................................................................................108

14. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM...................................108

15.

SUMMARY

OF HOURLY METEOROLOGICAL DATA....................................................108

16. DESCRIPTION OF MAJOR CHANGES TO RADIOACTIVE WASTE SYSTEMS...........108

17. RADIOACTIVE GROUND WATER MONITORING PROGRAM DATA............................108

18. CARBON-14 REPORTING..............................................................................................110

19. ADDITIONAL NOTES......................................................................................................113

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 2 of 113 1. INTRODUCTION Arkansas Nuclear One (ANO) is a two unit site consisting of a Babcock & Wilcox (Unit 1) and a

Combustion Engineering (Unit 2) nuclear steam supply system. Both liquid and gaseous

effluents are released in accordance with the Offsite Dose Calculation Manual (ODCM). This

report is a summary of the effluent data in accordance with Unit 1 Technical Specification (TS) 5.6.3 and Unit 2 TS 6.6.3. This report provides the following information:

A. Routine radioactive effluent release reports covering the operation of the units during the reporting period.

B. Description of unplanned releases to unrestricted areas.

C. Description of changes to the ODCM.

D. Description of changes to the Process Control Program (PCP).

E. Summary of radiation doses due to radiological effluents during the previous calendar year.

F. Radiation dose to members of the public due to activities inside the site boundary.

G. Description of licensee initiated major changes to the radioactive waste systems during the previous calendar year.

H. Items to be reported in the Annual Radioactive Effluent Release Report (ARERR) per other miscellaneous ODCM requirements.

I. Applicable Radioactive Ground Water Monitoring Program data.

J. ARERR data for 2012 Solid Waste Shipments.

K. Carbon-14 release quantification details are discussed in Section 18.

This report covers the period from January 1 through December 31, 2012.

2. REGULATORY LIMITS The ODCM contains the limits to which ANO must adhere. Because of the "as low as

reasonably achievable" (ALARA) philosophy at ANO, actions are taken to reduce the amount of

radiation released to the environment. Liquid and gaseous release data show that the dose

from both Unit 1 and Unit 2 is considerably below the ODCM limits. This data reveals that the

radioactive effluents have an overall minimal dose contribution to the surrounding environment.

The following are the limits required by the ODCM:

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 3 of 113 A. Gaseous Effluents

1. Dose rate due to radioactive materials released in gaseous effluent to unrestricted areas shall be limited to the following:

a. Noble gases Less than or equal to 500 mrem/year to the total body Less than or equal to 3000 mrem/year to the skin

b. Iodine-131, tritium, and for all radionuclides in particulate form with half lives greater than 8 days Less than or equal to 1500 mrem/yr to any organ

2. Dose - Noble Gases Quarterly Less than or equal to 5 mrads gamma Less than or equal to 10 mrads beta Yearly Less than or equal to 10 mrads gamma Less than or equal to 20 mrads beta

3. Dose - Iodine-131, Tritium, and Radionuclides in Particulate Form Quarterly Less than or equal to 7.5 mrems to any organ Yearly Less than or equal to 15 mrems to any organ

B. Liquid Effluents

1. Concentration The concentration of radioactive material released to the discharge canal shall be

limited to the concentration specified in 10 CFR 20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or

entrained noble gases, the total concentration released shall be limited to

2E-4 microcuries/ml.

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 4 of 113 2. Dose Quarterly Less than or equal to 1.5 mrem total body Less than or equal to 5 mrem critical organ Yearly Less than or equal to 3 mrem total body Less than or equal to 10 mrem critical organ

3.

SUMMARY

OF LIQUID EFFLUENT DATA As required by Regulatory Guide 1.21, Revision 1, "Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear

Power Plants," a summary of data for liquid releases is provided in the ARERR. The summary

of liquid effluents for both Unit 1 and Unit 2 is as follows:

Unit 1 Unit 2 Number of releases: 101 38 Total time for all releases (minutes): 341900 23260 Maximum time for a release (minutes): 10270 10280 Average time for a release (minutes): 3385 612 Minimum time for a release (minutes): 85 152

The Unit 1 liquid releases consisted of:

101 Planned Releases 0 Unplanned Releases

The Unit 2 liquid releases consisted of:

38 Planned Releases 0 Unplanned Releases

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 5 of 113 ANNUAL SUMMATION FOR ALL RELEASES BY QUARTER (ALL LIQUID EFFLUENTS) January 1 through June 30, 2012 Unit 1 Type of Effluent Units Quarter 1 Quarter 2 Est. Total Error % A. Fission and Activation Products 1. Total Release (Not Including Tritium, Gases, Alpha) Curies 1.964E-03 1.962E-03 25 2. Average Diluted Concentration During Period Ci/ml 6.250E-12 5.264E-12 3. Percent of Applicable Limit % 2.083E-3 1.755E-03 B. Tritium 1. Total Release Curies 3.310E+01 4.477E+01 25 2. Average Diluted Concentration During Period Ci/ml 1.053E-07 1.201E-07 3. Percent of Applicable Limit % 3.511E-03 4.003E-03 C. Dissolved and Entrained Gases 1. Total Release Curies 4.576E-05 0.000E+00 25 2. Average Diluted Concentration During Period Ci/ml 1.456E-13 0.000E+00 3. Percent of Applicable Limit % 7.279E-08 0.000E+00 D. Gross Alpha Radioactivity 1. Total Release Curies 0.000E+00 8.027E-06 25 E. Waste Vol Released (Pre-Dilution) Liters 3.815E+06 5.923E+06 25 F. Volume of Dilution Water Used Liters 3.143E+11 3.728E+11 25 ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 6 of 113 ANNUAL SUMMATION FOR ALL RELEASES BY QUARTER (ALL LIQUID EFFLUENTS) July 1 through December 31, 2012 Unit 1 Type of Effluent Units Quarter 3 Quarter 4 Est. Total Error % A. Fission and Activation Products 1. Total Release (Not Including Tritium, Gases, Alpha) Curies 1.531E-03 5.849E-03 25 2. Average Diluted Concentration During Period Ci/ml 3.934E-12 1.670E-11 3. Percent of Applicable Limit % 1.311E-03 5.566E-03 B. Tritium 1. Total Release Curies 9.483E+01 1.863E+02 25 2. Average Diluted Concentration During Period Ci/ml 2.437E-07 5.319E-07 3. Percent of Applicable Limit % 8.124E-03 1.773E-02 C. Dissolved and Entrained Gases 1. Total Release Curies 0.000E+00 3.603E-04 25 2. Average Diluted Concentration During Period Ci/ml 0.000E+00 1.029E-12 3. Percent of Applicable Limit % 0.000E+00 5.143E-07 D. Gross Alpha Radioactivity 1. Total Release Curies 0.000E+00 0.000E+00 25 E. Waste Vol Released (Pre-Dilution) Liters 1.359E+07 1.242E+07 25 F. Volume of Dilution Water Used Liters 3.891E+11 3.503E+11 25 ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 7 of 113 UNIT 1 REPORT CATEGORY: ANNUAL LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED TYPE OF ACTIVITY: ALL RADIONUCLIDES REPORTING PERIOD: QUARTER # 1 AND QUARTER # 2 YEAR 2012 CONTINUOUS RELEASES BATCH RELESES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 AG-110M CURIES 0.00E+00 0.00E+00 2.67E-05 0.00E+00 CO-58 CURIES 0.00E+00 0.00E+00 4.50E-04 1.77E-04 CO-60 CURIES 0.00E+00 0.00E+00 7.36E-04 1.74E-04 CR-51 CURIES 0.00E+00 0.00E+00 8.17E-05 0.00E+00 CS-134 CURIES 0.00E+00 0.00E+00 2.49E-05 3.41E-06 CS-137 CURIES 0.00E+00 0.00E+00 1.80E-04 7.90E-04 FE-55 CURIES 0.00E+00 0.00E+00 0.00E+00 7.28E-04 MN-54 CURIES 0.00E+00 0.00E+00 5.16E-05 5.53E-06 NA-24 CURIES 1.99E-05 0.00E+00 1.68E-05 0.00E+00 NB-95 CURIES 0.00E+00 0.00E+00 2.17E-04 6.35E-05 NB-97 CURIES 0.00E+00 0.00E+00 7.99E-06 8.10E-06 SB-124 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SB-125 CURIES 0.00E+00 0.00E+00 4.34E-05 0.00E+00 ZR-95 CURIES 0.00E+00 0.00E+00 1.09E-04 1.29E-05 H-3 CURIES 7.53E-03 1.64E-02 3.31E+01 4.48E+01 G-ALPHA CURIES 0.00E+00 0.00E+00 8.03E-06 0.00E+00 XE-133 CURIES 0.00E+00 0.00E+00 4.58E-05 0.00E+00 Total for Period CURIES 7.62E-03 1.64E-02 3.31E+01 4.48E+01

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 8 of 113 UNIT 1 REPORT CATEGORY: ANNUAL LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED TYPE OF ACTIVITY: ALL RADIONUCLIDES REPORTING PERIOD: QUARTER # 3 AND QUARTER # 4 YEAR 2012 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 AG-110M CURIES 0.00E+00 0.00E+00 3.59E-06 2.82E-04 CO-58 CURIES 0.00E+00 0.00E+00 4.91E-04 1.87E-03 CO-60 CURIES 0.00E+00 0.00E+00 3.42E-04 1.41E-03 CR-51 CURIES 0.00E+00 0.00E+00 0.00E+00 7.74-04 CS-134 CURIES 0.00E+00 0.00E+00 5.72E-06 0.00E+00 CS-137 CURIES 0.00E+00 0.00E+00 2.21E-04 3.08E-05 FE-55 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 MN-54 CURIES 0.00E+00 0.00E+00 5.16E-05 6.53E-05 NA-24 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NB-95 CURIES 0.00E+00 0.00E+00 2.62E-04 8.95E-04 NB-97 CURIES 0.00E+00 0.00E+00 3.05E-06 5.74E-06 SB-124 CURIES 0.00E+00 0.00E+00 6.75E-06 0.00E+00 SB-125 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ZR-95 CURIES 0.00E+00 0.00E+00 1.44E-04 5.22E-04 H-3 CURIES 6.99E-02 8.71E-02 9.48E+01 1.86E+02 G-ALPHA CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 XE-133 CURIES 0.00E+00 0.00E+00 0.00E+00 3.60E-04 Total for Period CURIES 6.99E-02 8.71E-02 9.48E+01 1.86E+02

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 9 of 113 ANNUAL SUMMATION FOR ALL RELEASES BY QUARTER (ALL LIQUID EFFLUENTS) January 1 through June 30, 2012 Unit 2 Type of Effluent Units Quarter 1 Quarter 2 Est. Total Error % A. Fission and Activation Products 1. Total Release (Not Including Tritium, Gases, Alpha) Curies 1.219E-03 3.719E-03 25 2. Average Diluted Concentration During Period Ci/ml 3.877E-12 9.976E-12 3. Percent of Applicable Limit % 1.292E-03 3.325E-03 B. Tritium 1. Total Release Curies 1.082E+02 2.793E+02 25 2. Average Diluted Concentration During Period Ci/ml 3.442E-07 7.491E-07 3. Percent of Applicable Limit % 1.147E-02 2.497E-02 C. Dissolved and Entrained Gases 1. Total Release Curies 0.000E+00 1.363E-03 25 2. Average Diluted Concentration During Period Ci/ml 0.000E+00 3.656E-12 3. Percent of Applicable Limit % 0.000E+00 1.828E-06

D. Gross Alpha Radioactivity 1. Total Release Curies 0.000E+00 0.000E+00 25 E. Waste Vol Released (Pre-Dilution) Liters 1.717E+05 2.092E+06 25 F. Volume of Dilution Water Used Liters 3.143E+11 3.728E+11 25

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 10 of 113 ANNUAL SUMMATION FOR ALL RELEASES BY QUARTER (ALL LIQUID EFFLUENTS) July 1 through December 31, 2012 Unit 2 Type of Effluent Units Quarter 3 Quarter 4 Est. Total Error % A. Fission and Activation Products 1. Total Release (Not Including Tritium, Gases, Alpha) Curies 1.521E-02 4.221E-03 25 2. Average Diluted Concentration During Period Ci/ml 3.910E-11 1.205E-11 3. Percent of Applicable Limit % 1.303E-02 4.017E-03 B. Tritium 1. Total Release Curies 3.505E+02 4.357E+01 25 2. Average Diluted Concentration During Period Ci/ml 9.009E-07 1.244E-07 3. Percent of Applicable Limit % 3.003E-02 4.146E-03 C. Dissolved and Entrained Gases 1. Total Release Curies 5.442E-02 3.619E-04 25 2. Average Diluted Concentration During Period Ci/ml 1.399E-10 1.033E-12 3. Percent of Applicable Limit % 6.993E-05 5.165E-07 D. Gross Alpha Radioactivity 1. Total Release Curies 0.000E+00 0.000E+00 25 E. Waste Vol Released (Pre-Dilution) Liters 1.262E+06 8.719E+05 25 F. Volume of Dilution Water Used Liters 3.891E+11 3.503E+11 25 ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 11 of 113 UNIT 2 REPORT CATEGORY: ANNUAL LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED TYPE OF ACTIVITY: ALL RADIONUCLIDES REPORTING PERIOD: QUARTER # 1 AND QUARTER # 2 YEAR 2012 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 AG-110M CURIES 0.00E+00 0.00E+00 4.31E-05 0.00E+00 BE-7 CURIES 0.00E+00 0.00E+00 1.13E-04 0.00E+00 CO-58 CURIES 0.00E+00 0.00E+00 1.33E-04 3.16E-04 CO-60 CURIES 0.00E+00 0.00E+00 8.32E-05 1.27E-04 CR-51 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS-134 CURIES 0.00E+00 0.00E+00 0.00E+00 3.85E-05 CS-137 CURIES 0.00E+00 0.00E+00 1.76E-05 1.25E-04 FE-55 CURIES 0.00E+00 0.00E+00 7.59E-04 2.45E-03 MN-54 CURIES 0.00E+00 0.00E+00 1.48E-05 2.20E-05 NB-95 CURIES 0.00E+00 0.00E+00 3.30E-05 8.90E-05 NB-97 CURIES 0.00E+00 0.00E+00 0.00E+00 1.08E-05 SB-124 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SB-125 CURIES 0.00E+00 0.00E+00 2.24E-05 5.00E-04 SB-126 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SN-117M CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ZR-95 CURIES 0.00E+00 0.00E+00 0.00E+00 3.77E-05 H-3 CURIES 0.00E+00 3.01E-03 1.08E+02 2.79E+02 G-ALPHA CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 AR-41 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 XE-133 CURIES 0.00E+00 0.00E+00 0.00E+00 1.36E-03 XE-133M CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 XE-135 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for Period CURIES 0.00E+00 3.01E-03 1.08E+02 2.79E+02 ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 12 of 113 UNIT 2 REPORT CATEGORY: ANNUAL LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED TYPE OF ACTIVITY: ALL RADIONUCLIDES REPORTING PERIOD: QUARTER # 3 AND QUARTER # 4 YEAR 2012 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 AG-110M CURIES 0.00E+00 0.00E+00 0.00E+00 1.58E-05 BE-7 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CO-58 CURIES 0.00E+00 0.00E+00 1.73E-03 8.31E-04 CO-60 CURIES 0.00E+00 0.00E+00 2.83E-04 1.31E-04 CR-51 CURIES 0.00E+00 0.00E+00 1.30E-03 1.17E-04 CS-134 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS-137 CURIES 0.00E+00 0.00E+00 8.25E-05 7.54E-05 FE-55 CURIES 0.00E+00 0.00E+00 8.55E-03 2.29E-03 MN-54 CURIES 0.00E+00 0.00E+00 5.72E-05 1.66E-05 NB-95 CURIES 0.00E+00 0.00E+00 3.52E-04 1.05E-05 NB-97 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SB-124 CURIES 0.00E+00 0.00E+00 0.00E+00 8.81E-05 SB-125 CURIES 0.00E+00 0.00E+00 2.66E-03 5.32E-04 SB-126 CURIES 0.00E+00 0.00E+00 0.00E+00 1.20E-05 SN-117M CURIES 0.00E+00 0.00E+00 0.00E+00 1.07E-04 ZR-95 CURIES 0.00E+00 0.00E+00 1.98E-04 0.00E+00 H-3 CURIES 0.00E+00 0.00E+00 3.51E+02 4.36E+01 G-ALPHA CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 AR-41 CURIES 0.00E+00 0.00E+00 0.00E+00 3.33E-05 XE-133 CURIES 0.00E+00 0.00E+00 5.29E-02 3.29E-04 XE-133M CURIES 0.00E+00 0.00E+00 7.12E-04 0.00E+00 XE-135 CURIES 0.00E+00 0.00E+00 8.01E-04 0.00E+00 Total for Period CURIES 0.00E+00 0.00E+00 3.51E+02 4.36E+01

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 13 of 113 4.

SUMMARY

OF GASEOUS EFFLUENT DATA As required by Regulatory Guide 1.21, Revision 1, a summary of data for gaseous releases is

provided in the ARERR. The summary of gaseous effluents for both Unit 1 and Unit 2 is as

follows:

Unit 1 Unit 2 Number of releases: 109 117 Total time for all releases (minutes): 970600 945100 Maximum time for a release (minutes): 10650 10580 Average time for a release (minutes): 8905 8078 Minimum time for a release (minutes): 17 7

The Unit 1 gaseous releases consisted of:

109 Planned vent and tank releases 0 Unplanned releases

The Unit 2 gaseous releases consisted of:

117 Planned vent and tank releases 0 Unplanned releases

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 14 of 113 ANNUAL SUMMATION FOR ALL RELEASES BY QUARTER (ALL AIRBORNE EFFLUENTS) January 1 through June 30, 2012 Unit 1 Type of Effluent Units Quarter 1 Quarter 2 Est. Total Error % A. Fission and Activation Products 1. Total Release Curies 0.000E+00 0.000E+00 25 2. Average Release Rate for Period Ci/Sec 0.000E+00 0.000E+00 3. Percent of Applicable Limit % 0.000E+00 0.000E+00 B. Radioiodines 1. Total Iodine-131 Curies 0.000E+00 0.000E+00 25 2. Average Release Rate for Period Ci/Sec 0.000E+00 0.000E+00 3. Percent of Applicable Limit % 0.000E+00 0.000E+00 C. Particulates 1. Particulates (Half-Lives > 8 Days)Curies 0.000E+00 0.000E+00 25 2. Average Release Rate for Period Ci/Sec 0.000E+00 0.000E+00 3. Percent of Applicable Limit % 0.000E+00 0.000E+00 4. Gross Alpha Radioactivity Curies 2.265E-07 8.324E-08 D. Tritium 1. Total Release Curies 3.763E+00 3.255E+00 25 2. Average Release Rate for Period Ci/Sec 4.773E-01 4.129E-01 3. Percent of Applicable Limit % 6.685E-04 5.782E-04

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 15 of 113 ANNUAL SUMMATION FOR ALL RELEASES BY QUARTER (ALL AIRBORNE EFFLUENTS) July 1 through December 31, 2012 Unit 1 Type of Effluent Units Quarter 3 Quarter 4 Est. Total Error % A. Fission and Activation Products 1. Total Release Curies 0.000E+00 0.000E+00 25 2. Average Release Rate for Period Ci/Sec 0.000E+00 0.000E+00 3. Percent of Applicable Limit % 0.000E+00 0.000E+00 B. Radioiodines 1. Total Iodine-131 Curies 0.000E+00 0.000E+00 25 2. Average Release Rate for Period Ci/Sec 0.000E+00 0.000E+00 3. Percent of Applicable Limit % 0.000E+00 0.000E+00 C. Particulates 1. Particulates (half-lives > 8 days)Curies 0.000E+00 0.000E+00 25 2. Average Release Rate for Period Ci/Sec 0.000E+00 0.000E+00 3. Percent of Applicable Limit % 0.000E+00 0.000E+00 4. Gross Alpha Radioactivity Curies 1.015E-07 1.240E-07 D. Tritium 1. Total Release Curies 3.405E+00 3.467E+00 25 2. Average Release Rate for Period Ci/Sec 4.319E-01 4.398E-01 3. Percent of Applicable Limit % 6.048E-04 6.160E-04

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 16 of 113 UNIT 1 REPORT CATEGORY: ANNUAL AIRBORNE GROUND LEVEL CONTINUOUS AND BATCH RELEASES

TOTALS FOR EACH NUCLIDE RELEASED TYPE OF ACTIVITY: FISSION GASES, IODINES, AND PARTICULATES REPORTING PERIOD: QUARTER # 1 AND QUARTER # 2 YEAR 2012 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 Fission Gases

NONE CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for Period CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Iodines NONE CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for Period CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Particulates

NONE CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for Period CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Other H-3 CURIES 0.00E+00 0.00E+00 3.763E+00 3.255E+00 G-ALPHA CURIES 0.00E+00 0.00E+00 2.265E-07 8.324E-08 Total for Period CURIES 0.00E+00 0.00E+00 3.763E+00 3.255E+00

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 17 of 113 UNIT 1 REPORT CATEGORY: ANNUAL AIRBORNE GROUND LEVEL CONTINUOUS AND BATCH RELEASES

TOTALS FOR EACH NUCLIDE RELEASED TYPE OF ACTIVITY: FISSION GASES, IODINES, AND PARTICULATES REPORTING PERIOD: QUARTER # 3 AND QUARTER # 4 YEAR 2012 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 Fission Gases

NONE CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for Period CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Iodines NONE CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for Period CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Particulates

NONE CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for Period CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Other H-3 CURIES 0.00E+00 0.00E+00 3.405E+00 3.467E+00 G-ALPHA CURIES 0.00E+00 0.00E+00 1.015E-07 1.240E-07 Total for Period CURIES 0.00E+00 0.00E+00 3.405E+00 3.467E+00

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 18 of 113 ANNUAL SUMMATION FOR ALL RELEASES BY QUARTER (ALL AIRBORNE EFFLUENTS) January 1 through June 30, 2012 Unit 2 Type of Effluent Units Quarter 1 Quarter 2 Est. Total Error % A. Fission and Activation Products 1. Total Release Curies 0.000E+00 0.000E+00 25 2. Average Release Rate for Period Ci/Sec 0.000E+00 0.000E+00 3. Percent of Applicable Limit % 0.000E+00 0.000E+00 B. Radioiodines 1. Total Iodine-131 Curies 0.000E+00 0.000E+00 25 2. Average Release Rate for Period Ci/Sec 0.000E+00 0.000E+00 3. Percent of Applicable Limit % 0.000E+00 0.000E+00 C. Particulates 1. Particulates (half-lives > 8 days)Curies 0.000E+00 0.00E+00 25 2. Average Release Rate for Period Ci/Sec 0.000E+00 0.00E+00 3. Percent of Applicable Limit % 0.000E+00 0.00E+00 4. Gross Alpha Radioactivity Curies 2.864E-07 4.375E-07 D. Tritium 1. Total Release Curies 6.384E+00 9.644E+00 25 2. Average Release Rate for Period Ci/Sec 8.097E-01 1.223E+00 3. Percent of Applicable Limit % 1.134E-03 1.713E-03

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 19 of 113 ANNUAL SUMMATION FOR ALL RELEASES BY QUARTER (ALL AIRBORNE EFFLUENTS) July 1 through December 31, 2012 Unit 2 Type of Effluent Units Quarter 3 Quarter 4 Est. Total Error % A. Fission and Activation Products 1. Total Release Curies 5.250E+01 0.000E+00 25 2. Average Release Rate for Period Ci/Sec 6.659E+00 0.000E+00 3. Percent of Applicable Limit % 9.327E-02 0.000E+00 B. Radioiodines 1. Total Iodine-131 Curies 0.000E+00 0.000E+00 25 2. Average Release Rate for Period Ci/Sec 0.000E+00 0.000E+00 3. Percent of Applicable Limit % 0.000E+00 0.000E+00 C. Particulates 1. Particulates (half-lives > 8 days)Curies 0.000E+00 0.000E+00 25 2. Average Release Rate for Period Ci/Sec 0.000E+00 0.000E+00 3. Percent of Applicable Limit % 0.000E+00 0.000E+00 4. Gross Alpha Radioactivity Curies 1.438E-07 9.776E-08 D. Tritium 1. Total Release Curies 8.325E+00 3.627E+00 25 2. Average Release Rate for Period Ci/Sec 1.056E+00 4.601E-01 3. Percent of Applicable Limit % 1.479E-03 6.443E-04

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 20 of 113 UNIT 2 REPORT CATEGORY: ANNUAL AIRBORNE GROUND LEVEL CONTINUOUS AND BATCH RELEASES

TOTALS FOR EACH NUCLIDE RELEASED TYPE OF ACTIVITY: FISSION GASES, IODINES, AND PARTICULATES REPORTING PERIOD: QUARTER # 1 AND QUARTER # 2 YEAR 2012 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 Fission Gases

NONE CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for Period CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines NONE CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for Period CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates

NONE CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for Period CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Other G-ALPHA CURIES 0.00E+00 0.00E+00 2.864E-07 4.375E-07 H-3 CURIES 0.00E+00 0.00E+00 6.384E+00 9.644E+00 Total for Period CURIES 0.00E+00 0.00E+00 6.384E+00 9.644E+00

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 21 of 113 UNIT 2 REPORT CATEGORY: ANNUAL AIRBORNE GROUND LEVEL CONTINUOUS AND BATCH RELEASES

TOTALS FOR EACH NUCLIDE RELEASED TYPE OF ACTIVITY: FISSION GASES, IODINES, AND PARTICULATES REPORTING PERIOD: QUARTER # 3 AND QUARTER # 4 YEAR 2012 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 Fission Gases

AR-41 CURIES 0.00E+00 0.00E+00 5.221E+01 0.00E+00 KR-85 CURIES 0.00E+00 0.00E+00 2.965E-01 0.00E+00 Total for Period CURIES 0.00E+00 0.00E+00 5.250E+01 0.00E+00

Iodines NONE CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for Period CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Particulates

NONE CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for Period CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Other G-ALPHA CURIES 0.00E+00 0.00E+00 1.438E-07 9.776E-08 H-3 CURIES 0.00E+00 0.00E+00 8.325E+00 3.627E+00 Total for Period CURIES 0.00E+00 0.00E+00 8.325E+00 3.627E+00

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 22 of 113 5.

SUMMARY

OF RADIATION DOSES The following is a summary of the annual radiation doses due to radiological effluents during

2012 calculated in accordance with the ODCM.

UNIT 1 Liquid Radwaste Effluents

Dose Limits (mRem): Total Body = 1.5/Qtr 3/Yr, Other Organs = 5/Qtr 10/Yr

Organ Qtr 1 % Qtr 2 % Qtr 3 % Qtr 4 % Year % TBody 0.0002 0.011 0.0004 0.026 0.0002 0.014 0.00030.020 0.00110.036 Bone 0.0001 0.002 0.0004 0.008 0.0001 0.002 0.00000.00 0.00060.006 Liver 0.0002 0.004 0.0006 0.011 0.0003 0.005 0.00030.006 0.00140.014 Thyroid 0.0001 0.001 0.0001 0.001 0.0001 0.002 0.00030.006 0.00050.005 Kidney 0.0001 0.002 0.0002 0.005 0.0002 0.003 0.00030.006 0.00080.008 Lung 0.0001 0.001 0.0001 0.002 0.0001 0.003 0.00030.006 0.00060.006 GI-LLI 0.0001 0.002 0.0001 0.002 0.0002 0.003 0.00040.008 0.00070.007

Gaseous Radwaste Effluents

Iodine, H-3, and Particulate (ITP) - Dose Limits (mRem) = 7.5/Qtr 15/Yr

Organ Qtr 1 % Qtr 2 % Qtr 3 % Qtr 4 % Year % TBody 0.0023 0.031 0.0020 0.027 0.0021 0.028 0.00210.028 0.00860.057 Bone 0.0000 0.000 0.0000 0.000 0.0000 0.000 0.00000.000 0.00000.000 Liver 0.0023 0.031 0.0020 0.027 0.0021 0.028 0.00210.028 0.00860.057 Thyroid 0.0023 0.031 0.0020 0.027 0.0021 0.028 0.00210.028 0.00860.057 Kidney 0.0023 0.031 0.0020 0.027 0.0021 0.028 0.00210.028 0.00860.057 Lung 0.0023 0.031 0.0020 0.027 0.0021 0.028 0.00210.028 0.00860.057 GI-LLI 0.0023 0.031 0.0020 0.027 0.0021 0.028 0.00210.028 0.00860.057 Noble Gas Air Dose Limits (mRad) = Gamma 5/Qtr 10/Yr, Beta 10/Qtr 20/Yr

Type Qtr 1 % Qtr 2 % Qtr 3 % Qtr 4 % Year % Gamma 0.0000 0.00 0.0000 0.00 0.0000 0.00 0.00000.00 0.00000.00 Beta 0.0000 0.00 0.0000 0.00 0.0000 0.00 0.00000.00 0.00000.00

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 23 of 113 UNIT 2 Liquid Radwaste Effluents

Dose Limits (mRem): Total Body = 1.5/Qtr 3/Yr, Other Organs = 5/Qtr 10/Yr

Organ Qtr 1 % Qtr 2 % Qtr 3 % Qtr 4 % Year % TBody 0.0002 0.012 0.0005 0.030 0.0005 0.033 0.00010.006 0.00120.041 Bone 0.0000 0.000 0.0001 0.002 0.0001 0.001 0.00000.001 0.00020.002 Liver 0.0002 0.004 0.0005 0.010 0.0005 0.011 0.00010.002 0.00130.013 Thyroid 0.0002 0.003 0.0004 0.008 0.0005 0.009 0.00010.001 0.00110.011 Kidney 0.0002 0.004 0.0004 0.008 0.0005 0.009 0.00010.002 0.00110.011 Lung 0.0002 0.004 0.0004 0.008 0.0005 0.009 0.00010.001 0.00110.011 GI-LLI 0.0002 0.004 0.0004 0.008 0.0005 0.010 0.00010.002 0.00120.012

Gaseous Radwaste Effluents

Iodine, H-3, and Particulate - Dose Limits (mRem) = 7.5/Qtr 15/Yr

Organ Qtr 1 % Qtr 2 % Qtr 3 % Qtr 4 % Year % Tbody 0.0039 0.052 0.0059 0.079 0.0051 0.068 0.00220.030 0.01720.115 Bone 0.0000 0.000 0.0000 0.000 0.0000 0.000 0.00000.000 0.00000.000 Liver 0.0039 0.052 0.0059 0.079 0.0051 0.068 0.00220.030 0.01720.115 Thyroid 0.0039 0.052 0.0059 0.079 0.0051 0.068 0.00220.030 0.01720.115 Kidney 0.0039 0.052 0.0059 0.079 0.0051 0.068 0.00220.030 0.01720.115 Lung 0.0039 0.052 0.0059 0.079 0.0051 0.068 0.00220.030 0.01720.115 GI-LLI 0.0039 0.052 0.0059 0.079 0.0051 0.068 0.00220.030 0.01720.115 Noble Gas Air Dose Limits (mRad) = Gamma 5/Qtr 10/Yr, Beta 10/Qtr 20/Yr

Type Qtr 1 % Qtr 2 % Qtr 3 % Qtr 4 % Year % Gamma 0.0000 0.000 0.0000 0.000 0.0431 0.862 0.00000.00 0.04310.431 Beta 0.0000 0.000 0.0000 0.000 0.0153 0.153 0.00000.00 0.01530.076

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 24 of 113 6.

SUMMARY

OF DOSE TO MEMBERS OF THE PUBLIC The following is a summary of the annual radiation dose to members of the public (in mrem) due to activities inside the site bo undary. UNIT 1 BONE LIVER TBODY THYROID KIDNEY GI-LLI LUNG SKIN Gaseous Effluent Iodine/Tritium Particulate 0.00E+00 8.554E-03 8.554E-03 8.554E-03 8.554E-03 8.554E-03 8.554E-03 Noble Gas 0.00E+00 0.00E+00 Liquid Effluent Fish 6.045E-04 1.369E-03 1.088E-03 5.193E-04 8.042E-04 7.339E-04 6.146E-04 0.00E+00

Sediment 7.910E-05 9.290E-05 Unit 1 Total 6.045E-04 9.923-03 9.624E-03 9.073E-03 9.348E-03 9.288E-03 9.196E-03 9.290E-05 UNIT 2 Gaseous Effluent Iodine/Tritium Particulate 0.00E+00 1.723E-02 1.723E-02 1.723E-02 1.723E-02 1.723E-02 1.723E-02 Noble Gas 2.868E-02 4.60E-02 Liquid Effluent Fish 2.046E-04 1.327E-03 1.229E-03 1.065E-03 1.140E-03 1.179E-03 1.110E-03 0.00E+00 Sediment 3.68E-05 4.32E-05 Unit 2 Total 2.046E-04 1.856E-02 4.724E-02 1.830E-02 1.837E-02 1.841E-02 1.834E-02 4.604E-02 Site Total 8.091E-04 2.848E-02 5.686E-02 2.737E-02 2.772E-02 2.764E-02 2.754E-02 4.613E-02 Limit (40CFR190) 25 25 75 25 25 25 25 25 % Limit 3.236E-03 1.140E-01 7.581E-02 1.095E-01 1.110E-01 1.110E-01 1.102E-01 1.845E-01

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 25 of 113 7. HISTORICAL EFFLUENT DATA The following graphs show the historical release data for both units on a yearly basis. These

graphs compare data from 2002 through 2012.

UNIT 1 LIQUID EFFLUENTSFISSION AND ACTIVATION PRODUCTS1.00E-021.00E-011.00E+0020022003200420052006200720082009201020112012YEARCURIES UNIT 1 LIQUID EFFLUENTSTRITIUM1.00E+021.00E+0320022003200420052006200720082009201020112012YEARCURIES ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 26 of 113 UNIT 1 LIQUID EFFLUENTSDISSOLVED AND ENTRAINED GASES1.00E-061.00E-05 1.00E-04 1.00E-031.00E-02 1.00E-011.00E+001.00E+011.00E+0220022003200420052006200720082009201020112012YEARCURIES UNIT 1 LIQUID EFFLUENTSTOTAL VOLUME RELEASED1.00E+061.00E+071.00E+0820022003200420052006200720082009201020112012YEARGALLONS

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 27 of 113 UNIT 1 LIQUID EFFLUENTSCRITICAL ORGAN DOSE1.00E-031.00E-021.00E-011.00E+0020022003200420052006200720082009201020112012YEARMREM UNIT 1 LIQUID EFFLUENTSTOTAL BODY DOSE1.00E-031.00E-021.00E-011.00E+0020022003200420052006200720082009201020112012YEARMREM

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 28 of 113 UNIT 1 LIQUID EFFLUENTSCOLLECTIVE DOSES0.0000.0200.0400.0600.0800.1000.1200.14020022003200420052006200720082009201020112012YEAR% LIMITBONELIVERGI-LLITHYROIDKIDNEY LUNG UNIT 1 GASEOUS EFFLUENTSFISSION AND ACTIVATION PRODUCTS1.00E-041.00E-03 1.00E-021.00E-011.00E+001.00E+011.00E+021.00E+031.00E+0420022003200420052006200720082009201020112012YEARCURIES

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 29 of 113 UNIT 1 GASEOUS EFFLUENTSRADIOIODINES1.00E-081.00E-071.00E-061.00E-05 1.00E-041.00E-031.00E-021.00E-011.00E+0020022003200420052006200720082009201020112012YEARCUIRES UNIT 1 GASEOUS EFFLUENTSGross Gamma1.00E-051.00E-041.00E-031.00E-0220022003200420052006200720082009201020112012YEARCURIES ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 30 of 113 UNIT 1 GASEOUS EFFLUENTSParticulates1.00E-091.00E-08 1.00E-071.00E-061.00E-051.00E-041.00E-031.00E-021.00E-0120022003200420052006200720082009201020112012YEARCURIES UNIT 1 GASEOUS EFFLUENTS TRITIUM1.00E+001.00E+011.00E+0220022003200420052006200720082009201020112012YEARCURIES ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 31 of 113 UNIT 1 GASEOUS EFFLUENTS BETA DOSE1.00E-041.00E-031.00E-021.00E-01 1.00E+0020022003200420052006200720082009201020112012YEAR MRAD

UNIT 1 GASEOUS EFFLUENTSTOTAL BODY DOSE1.00E-031.00E-02 1.00E-011.00E+0020022003200420052006200720082009201020112012YEARMREM ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 32 of 113 UNIT 1 GASEOUS EFFLUENTSCRITICAL ORGAN DOSE1.00E-031.00E-021.00E-011.00E+0020022003200420052006200720082009201020112012YEARMREM UNIT 1 GASEOUS EFFLUENTSCOLLECTIVE DOSES0.0000.100 0.2000.3000.4000.5000.600 0.70020022003200420052006200720082009201020112012YEAR% LIMITBONELIVERTHYROIDKIDNEY LUNGGI-LLI

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 33 of 113 UNIT 2 LIQUID EFFLUENTSFISSION AND ACTIVATION PRODUCTS1.00E-021.00E-011.00E+0020022003200420052006200720082009201020112012YEARCURIES UNIT 2 LIQUID EFFLUENTSTRITIUM1.00E+011.00E+021.00E+03 1.00E+0420022003200420052006200720082009201020112012YEARCURIES

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 34 of 113 UNIT 2 LIQUID EFFLUENTSDISSOLVED AND ENTRAINED GASES1.00E-031.00E-02 1.00E-011.00E+00 1.00E+01 1.00E+021.00E+0320022003200420052006200720082009201020112012YEARCURIES UNIT 2 LIQUID EFFLUENTSTOTAL VOLUME RELEASED1.00E+061.00E+071.00E+0820022003200420052006200720082009201020112012YEARGALLONS

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 35 of 113 UNIT 2 LIQUID EFFLUENTSTOTAL BODY DOSE1.00E-041.00E-031.00E-021.00E-011.00E+0020022003200420052006200720082009201020112012YEARMREM UNIT 2 LIQUID EFFLUENTSCRITICAL ORGAN DOSE1.00E-041.00E-031.00E-021.00E-011.00E+0020022003200420052006200720082009201020112012YEARMREM

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 36 of 113 UNIT 2 LIQUID EFFLUENTSCOLLECTIVE DOSES0.0000.0100.0200.030 0.0400.0500.060 0.0700.080 0.090 0.10020022003200420052006200720082009201020112012YEAR% LIMITBONELIVERGI-LLITHYROIDKIDNEY LUNG UNIT 2 GASEOUS EFFLUENTSFISSION AND ACTIVATION PRODUCTS1.00E-021.00E-011.00E+001.00E+011.00E+021.00E+031.00E+0420022003200420052006200720082009201020112012YEARCURIES ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 37 of 113 UNIT 2 GASEOUS EFFLUENTSTRITIUM1.00E+001.00E+011.00E+0220022003200420052006200720082009201020112012YEAR CURIES UNIT 2 GASEOUS EFFLUENTSRADIOIODINES1.00E-071.00E-061.00E-051.00E-041.00E-031.00E-021.00E-0120022003200420052006200720082009201020112012YEARCURIES

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 38 of 113 UNIT 2 GASEOUS EFFLUENTSPARTICULATES1.00E-071.00E-061.00E-051.00E-041.00E-03 1.00E-021.00E-0120022003200420052006200720082009201020112012YEARCURIES UNIT 2 GASEOUS EFFLUENTSGAMMA DOSE1.00E-051.00E-041.00E-031.00E-02 1.00E-011.00E+0020022003200420052006200720082009201020112012YEARCURIES ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 39 of 113 UNIT 2 GASEOUS EFFLUENTSBeta Dose1.00E-041.00E-031.00E-02 1.00E-011.00E+0020022003200420052006200720082009201020112012YEARCURIES UNIT 2 GASEOUS EFFLUENTSTOTAL BODY DOSE1.00E-031.00E-021.00E-011.00E+0020022003200420052006200720082009201020112012YEARMREM

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 40 of 113 UNIT 2 GASEOUS EFFLUENTSCRITICAL ORGAN DOSE1.00E-031.00E-021.00E-011.00E+0020022003200420052006200720082009201020112012YEARMREM UNIT 2 GASEOUS EFFLUENTSCOLLECTIVE DOSES0.0000.500 1.000 1.5002.0002.50020022003200420052006200720082009201020112012YEAR% LIMITBONELIVERTHYROIDKIDNEY LUNGGI-LLI ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 41 of 113

8. SOLID WASTE

SUMMARY

As required by Regulatory Guide 1.21, Revision 1, a summary of data for solid wastes shipped

offsite is provided in the ARERR.

The summary for solid waste shipments for Unit 1 is as follows:

Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2012 to 06/30/2012

Waste Stream: Resins, Filters, and Evaporator Bottom

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 1.10E+03 3.11E+01 6.80E-01 +/- 25% B 5.90E+02 1.67E+01 2.17E+02 +/- 25% C 4.74E+01 1.34E+00 9.50E+00 +/- 25%

All 1.74E+03 4.91E+01 2.27E+02 +/- 25%

Waste Stream: Dry Active Waste

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 2.86E+03 8.10E+01 1.47E-01 +/- 25% B 0.00E+00 0.00E+00 0.00E+00 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 2.86E+03 8.10E+01 1.47E-01

+/- 25%

Waste Stream: Irradiated Components

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 0.00E+00 0.00E+00 0.00E+00 +/- 25% B 0.00E+00 0.00E+00 0.00E+00 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 0.00E+00 0.00E+00 0.00E+00 +/- 25%

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 42 of 113 Waste Stream: Other Waste Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 0.00E+00 0.00E+00 0.00E+00 +/- 25% B 0.00E+00 0.00E+00 0.00E+00 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 0.00E+00 0.00E+00 0.00E+00 +/- 25%

Waste Stream: Sum of All 4 Categories

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 3.96E+03 1.12E+02 7.54E-01 +/- 25% B 5.90E+02 1.67E+01 2.17E+02 +/- 25% C 4.74E+01 1.34E+00 9.50E+00 +/- 25%

All 4.60E+03 1.30E+02 2.27E+02 +/- 25%

Number of Shipments Mode of Transportation Destination 6 Hittman Transport Studsvik Processing Facility 2 Hittman Transport Toxco. Inc 2 R&R Trucking Inc Studsvik Processing Facility 4* Hittman Transport Bear Creek Operations

Combined Waste Type Shipments (U1 and U2 Waste combined)

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 43 of 113 Resins, Filters, and Evaporator Bottoms

Waste Class A Nuclide Name Percent Abundance Curies Cr-51 0.000% 8.89E-08 Mn-54 3.809% 2.59E-02 Fe-55 0.130% 8.86E-04 Fe-59 0.000% 1.46E-10 Co-57 0.136% 9.24E-04 Co-58 0.153% 1.04E-3 Co-60 83.088% 5.65E-01 Ni-63 0.067% 4.54E-04 Zn-65 0.431% 2.93E-03 Zr-95 0.029% 2.00E-04 Nb-95 0.001% 4.35E-06 Sn-113 0.000% 1.44E-07 Sb-125 0.013% 8.95E-05 Cs-134 0.381% 2.59E-03 Cs-137 11.809% 8.03E-02 Hf-181 0.000% 6.27E-11 ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 44 of 113 Resins, Filters, and Evaporator Bottoms

Waste Class B Nuclide Name Percent Abundance Curies H-3 0.089% 1.94E-01 C-14 1.057% 2.29E+00 Mn-54 0.875% 1.90E+00 Fe-55 12.160% 2.63E+01 Co-57 0.070% 1.52E-01 Co-58 0.080% 1.74E-01 Co-60 17.309% 3.75E+01 Ni-59 0.821% 3.94E-01 Ni-63 40.498% 8.78E+01 Zn-65 0.092% 2.00E-01 Sr-89 0.000% 2.18E-10 Sr-90 0.059% 1.28E-01 Tc-99 0.003% 5.81E-03 Sb-125 0.186% 4.03E-01 Cs-134 7.252% 1.57E+01 Cs-137 20.075% 4.35E+01 Ce-144 0.012% 2.52E-02 Pu-239 0.000% 3.62E-05 Pu-240 0.000% 3.62E-05 Am-241 0.000% 2.88E-04 Cm-242 0.000% 4.25E-06 Cm-243 0.000% 2.19E-04 Cm-244 0.000% 2.13E-04

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 45 of 113 Resins, Filters, and Evaporator Bottoms

Waste Class C Nuclide Name Percent Abundance Curies H-3 0.330% 3.13E-02 C-14 2.116% 2.01E-01 Sc-46 0.000% 3.09E-11 Cr-51 0.000% 2.12E-17 Mn-54 0.119% 1.13E-02 Fe-55 22.603% 2.15E+00 Fe-59 0.000% 6.71E-13 Co-57 0.012% 1.13E-03 Co-58 0.000% 6.57E-07 Co-60 10.151% 9.64E-01 Ni-59 0.478% 4.54E-02 Ni-63 61.603% 5.85E+00 Zn-65 0.003% 2.56E-04 Sr-89 0.000% 1.45E-13 Sr-90 0.011% 1.04E-03 Zr-95 0.000% 1.70E-08 Nb-95 0.000% 1.26E-13 Tc-99 0.014% 1.29E-03 Ag-110m 0.001% 8.44E-05 Sn-113 0.000% 9.29E-07 Sb-124 0.000% 3.25E-11 Sb-125 1.467% 1.39E-01 Cs-134 0.110% 1.04E-02 Cs-137 0.973% 9.24E-02 Ce-144 0.003% 2.76E-04 Hf-181 0.000% 5.76E-18 Pu-238 0.008% 7.42E-04 Cm-242 0.000% 1.21E-08 Cm-243 0.000% 1.23E-05 Cm-244 0.000% 1.14E-05

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 46 of 113 Resins, Filters, and Evaporator Bottoms Waste Class ALL Nuclide Name Percent Abundance Curies H-3 0.099% 2.25E-01 C-14 1.097% 2.49E+00 Sc-46 0.000% 3.09E-11 Cr-51 0.000% 8.89E-08 Mn-54 0.853% 1.94E+00 Fe-55 12.533% 2.85E+01 Fe-59 0.000% 1.47E-10 Co-57 0.068% 1.54E-01 Co-58 0.077% 1.75E-01 Co-60 17.193% 3.90E+01 Ni-59 0.194% 4.39E-01 Ni-63 41.256% 9.37E+01 Zn-65 0.090% 2.03E-01 Sr-89 0.000% 2.18E-10 Sr-90 0.057% 1.29E-01 Zr-95 0.000% 2.00E-04 Nb-95 0.000% 4.35E-06 Tc-99 0.003% 7.10E-03 Ag-110m 0.000% 8.44E-05 Sn-113 0.000% 1.07E-06 Sb-124 0.000% 3.25E-11 Sb-125 0.239% 5.42E-01 Cs-134 6.922% 1.57E+01 Cs-137 19.239% 4.37E+01 Ce-144 0.011% 2.55E-02 Hf-181 0.000% 6.27E-11 Pu-238 0.000% 7.42E-04 Pu-239 0.000% 3.62E-05 Pu-240 0.000% 3.62E-05 Am-241 0.000% 2.88E-04 Cm-242 0.000% 4.26E-06 Cm-243 0.000% 2.31E-04 Cm-244 0.000% 2.24E-04

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 47 of 113 Dry Active Waste

Waste Class A Nuclide Name Percent Abundance Curies Mn-54 1.027% 1.50E-03 Fe-55 25.205% 3.68E-02 Co-58 6.986% 1.02E-02 Co-60 9.041% 1.32E-02 Ni-63 10.993% 1.61E-02 Zr-95 2.531% 3.70E-03 Nb-95 5.137% 7.50E-03 Sb-125 5.240% 7.65E-03 Cs-134 3.527% 5.15E-03 Cs-137 30.548% 4.46E-02

Dry Active Waste

Waste Class ALL Nuclide Name Percent Abundance Curies Mn-54 1.027% 1.50E-03 Fe-55 25.205% 3.68E-02 Co-58 6.986% 1.02E-02 Co-60 9.041% 1.32E-02 Ni-63 10.993% 1.61E-02 Zr-95 2.531% 3.70E-03 Nb-95 5.137% 7.50E-03 Sb-125 5.240% 7.65E-03 Cs-134 3.527% 5.15E-03 Cs-137 30.548% 4.46E-02

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 48 of 113 Sum of All 4 Categories

Waste Class A Nuclide Name Percent Abundance Curies Cr-51 0.000% 8.89E-08 Mn-54 3.313% 2.74E-02 Fe-55 4.557% 3.77E-02 Fe-59 0.000% 1.46E-10 Co-57 0.112% 9.24E-04 Co-58 1.359% 1.12E-02 Co-60 69.915% 5.78E-01 Ni-63 1.996% 1.65E-02 Zn-65 0.354% 2.93E-03 Zr-95 0.471% 3.90E-03 Nb-95 0.907% 7.50E-03 Sn-113 0.000% 1.44E-07 Sb-125 0.936% 7.74E-03 Cs-134 0.936% 7.74E-03 Cs-137 15.103% 1.25E-01 Hf-181 0.000% 6.27E-11 ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 49 of 113 Sum of All 4 Categories

Waste Class B Nuclide Name Percent Abundance Curies H-3 0.089% 1.94E-01 C-14 1.057% 2.29E+00 Mn-54 0.875% 1.90E+00 Fe-55 12.160% 2.63E+01 Co-57 0.070% 1.52E-01 Co-58 0.080% 1.74E-01 Co-60 17.309% 3.75E+01 Ni-59 0.821% 3.94E-01 Ni-63 40.498% 8.78E+01 Zn-65 0.092% 2.00E-01 Sr-89 0.000% 2.18E-10 Sr-90 0.059% 1.28E-01 Tc-99 0.003% 5.81E-03 Sb-125 0.186% 4.03E-01 Cs-134 7.252% 1.57E+01 Cs-137 20.075% 4.35E+01 Ce-144 0.012% 2.52E-02 Pu-239 0.000% 3.62E-05 Pu-240 0.000% 3.62E-05 Am-241 0.000% 2.88E-04 Cm-242 0.000% 4.25E-06 Cm-243 0.000% 2.19E-04 Cm-244 0.000% 2.13E-04

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 50 of 113 Sum of All 4 Categories

Waste Class C Nuclide Name Percent Abundance Curies H-3 0.330% 3.13E-02 C-14 2.116% 2.01E-01 Sc-46 0.000% 3.09E-11 Cr-51 0.000% 2.12E-17 Mn-54 0.119% 1.13E-02 Fe-55 22.603% 2.15E+00 Fe-59 0.000% 6.71E-13 Co-57 0.012% 1.13E-03 Co-58 0.000% 6.57E-07 Co-60 10.151% 9.64E-01 Ni-59 0.478% 4.54E-02 Ni-63 61.603% 5.85E+00 Zn-65 0.003% 2.56E-04 Sr-89 0.000% 1.45E-13 Sr-90 0.011% 1.04E-03 Zr-95 0.000% 1.70E-08 Nb-95 0.000% 1.26E-13 Tc-99 0.014% 1.29E-03 Ag-110m 0.001% 8.44E-05 Sn-113 0.000% 9.29E-07 Sb-124 0.000% 3.25E-11 Sb-125 1.467% 1.39E-01 Cs-134 0.110% 1.04E-02 Cs-137 0.973% 9.24E-02 Ce-144 0.003% 2.76E-04 Hf-181 0.000% 5.76E-18 Pu-238 0.008% 7.42E-04 Cm-242 0.000% 1.21E-08 Cm-243 0.000% 1.23E-05 Cm-244 0.000% 1.14E-05

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 51 of 113 Sum of All 4 Categories Waste Class ALL Nuclide Name Percent Abundance Curies H-3 0.099% 2.25E-01 C-14 1.097% 2.49E+00 Sc-46 0.000% 3.09E-11 Cr-51 0.000% 8.89E-08 Mn-54 0.854% 1.94E+00 Fe-55 12.550% 2.85E+01 Fe-59 0.000% 1.47E-10 Co-57 0.068% 1.54E-01 Co-58 0.082% 1.85E-01 Co-60 17.199% 3.90E+01 Ni-59 0.194% 4.39E-01 Ni-63 41.263% 9.37E+01 Zn-65 0.090% 2.03E-01 Sr-89 0.000% 2.18E-10 Sr-90 0.057% 1.29E-01 Zr-95 0.002% 3.90E-03 Nb-95 0.003% 7.50E-03 Tc-99 0.003% 7.10E-03 Ag-110m 0.000% 8.44E-05 Sn-113 0.000% 1.07E-06 Sb-124 0.000% 3.25E-11 Sb-125 0.242% 5.50E-01 Cs-134 6.924% 1.57E+01 Cs-137 19.259% 4.37E+01 Ce-144 0.011% 2.55E-02 Hf-181 0.000% 6.27E-11 Pu-238 0.000% 7.42E-04 Pu-239 0.000% 3.62E-05 Pu-240 0.000% 3.62E-05 Am-241 0.000% 2.88E-04 Cm-242 0.000% 4.26E-06 Cm-243 0.000% 2.31E-04 Cm-244 0.000% 2.24E-04 ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 52 of 113 Manifest Number Date Shipped Waste Volume Used Burial Volume Used RSR 12-001 (Combined Waste) 1/5/2012 Yes RSR 12-004 (Combined Waste) 1/12/2012 Yes RSR 12-007 1/16/2012 Yes RSR 12-010 1/23/2012 Yes RSR 12-021 2/15/2012 Yes RSR 12-026 2/29/2012 Yes RSR 12-037 3/29/2012 Yes RSR 12-039 4/5/2012 Yes

RSR 12-043 (Combined Waste) 4/12/2012 Yes RSR 12-044 (Combined Waste) 4/19/2012 Yes RSR 12-050 5/2/2012 Yes RSR 12-058 5/21/2012 Yes RSR 12-064 6/14/2012 Yes RSR 12-065 6/21/2012 Yes Combined Waste indicates that shipment was a mixture of Unit 1 and Unit 2 Waste

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 53 of 113 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 07/01/2012 to 12/31/2012 for Unit 1

Waste Stream: Resin, Filters, and Evaporator Bottom

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 2.67E+01 7.56E-01 6.62E-01 +/- 25% B 7.00E+01 1.98E+00 2.44E+01 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 9.67E+01 2.74E+00 2.50E+01 +/- 25%

Waste Stream: Dry Active Waste

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 2.13E+03 6.00E+01 9.35E-02 +/- 25% B 0.00E+00 0.00E+00 0.00E+00 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 2.13E+03 6.00E+01 9.35E-02

+/- 25%

Waste Stream: Irradiated Components

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 0.00E+00 0.00E+00 0.00E+00 +/- 25% B 0.00E+00 0.00E+00 0.00E+00 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 0.00E+00 0.00E+00 0.00E+00 +/- 25%

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 54 of 113 Waste Stream: Other Waste Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 0.00E+00 0.00E+00 0.00E+00 +/- 25% B 0.00E+00 0.00E+00 0.00E+00 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 0.00E+00 0.00E+00 0.00E+00 +/- 25%

Waste Stream: Sum of All 4 Categories

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 4.28E+03 6.08E+01 7.55E-01 +/- 25% B 7.00E+01 1.98E+00 2.44E+01 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 4.35E+03 6.28E+01 2.52E+01 +/- 25%

Number of Shipments Mode of Transportation Destination 1 Hittman Transport Toxco, Inc.

1 Hittman Transport Studsvik Processing Facility 3* Hittman Transport Bear Creek Operations

Combined Waste Type Shipment (U1 and U2 Waste combined)

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 55 of 113 Resins, Filters, and Evaporator Bottom

Waste Class A Nuclide Name Percent Abundance Curies H-3 0.340% 2.25E-03 C-14 1.828% 1.21E-02 Sc-46 0.000% 1.50E-13 Cr-51 0.000% 3.56E-28 Mn-54 0.029% 1.91E-04 Fe-55 16.163% 1.07E-01 Fe-59 0.000% 1.08E-19 Co-57 0.002% 1.41E-05 Co-58 0.000% 1.36E-11 Co-60 8.776% 5.81E-02 Ni-59 0.560% 3.71E-03 Ni-63 70.091% 4.64E-01 Zn-65 0.000% 2.34E-06 Sr-89 0.000% 8.06E-19 Sr-90 0.011% 7.61E-05 Zr-95 0.000% 1.14E-13 Nb-95 0.000% 9.36E-23 Tc-99 0.019% 1.27E-04 Ag-110m 0.000% 9.19E-07 Sn-113 0.000% 1.13E-09 Sb-125 1.044% 6.91E-03 Cs-134 0.060% 3.95E-04 Cs-137 1.041% 6.89E-03 Ce-144 0.001% 3.39E-06 Hf-181 0.000% 1.53E-21 Pu-238 0.009% 5.83E-05 Cm-242 0.000% 1.70E-10 Cm-243 0.000% 1.21E-06 Cm-244 0.000% 1.10E-06

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 56 of 113 Resins, Filters, and Evaporator Bottom

Waste Class B Nuclide Name Percent Abundance Curies C-14 0.656% 1.60E-01 Mn-54 2.344% 5.72E-01 Fe-55 14.221% 3.47E+00 Co-57 0.071% 1.73E-02 Co-58 0.078% 1.90E-02 Co-60 40.000% 9.76E+00 Ni-59 0.152% 3.71E-02 Ni-63 21.230% 5.18E+00 Zn-65 0.316% 7.70E-02 Sr-90 0.038% 9.37E-03 Cs-134 5.000% 1.22E+00 Cs-137 15.779% 3.85E+00

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 57 of 113 Resins, Filters, and Evaporator Bottom

Waste Class All Nuclide Name Percent Abundance Curies H-3 0.009% 2.25E-03 C-14 0.688% 1.72E-01 Sc-46 0.000% 1.50E-13 Cr-51 0.000% 3.56E-28 Mn-54 2.289% 5.72E-01 Fe-55 14.308% 3.58E+00 Fe-59 0.000% 1.08E-19 Co-57 0.069% 1.73E-02 Co-58 0.076% 1.90E-02 Co-60 39.272% 9.82E+00 Ni-59 0.163% 4.08E-02 Ni-63 22.576% 5.64E+00 Zn-65 0.308% 7.70E-02 Sr-89 0.000% 8.06E-19 Sr-90 0.038% 9.45E-03 Zr-95 0.000% 1.14E-13 Nb-95 0.000% 9.36E-23 Tc-99 0.001% 1.27E-04 Ag-110m 0.000% 9.19E-07 Sn-113 0.000% 1.13E-09 Sb-125 0.028% 6.91E-03 Cs-134 4.882% 1.22E+00 Cs-137 15.428% 3.86E+00 Ce-144 0.000% 3.39E-06 Hf-181 0.000% 1.53E-21 Pu-238 0.000% 5.83E-05 Cm-242 0.000% 1.70E-10 Cm-243 0.000% 1.21E-06 Cm-244 0.000% 1.10E-06

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 58 of 113 Dry Active Waste

Waste Class A Nuclide Name Percent Abundance Curies Mn-54 0.842% 7.85E-04 Fe-55 28.755% 2.68E-02 Co-58 4.077% 3.80E-03 Co-60 9.013% 8.40E-03 Ni-63 12.929% 1.21E-02 Zr-95 1.797% 1.68E-03 Nb-95 2.393% 2.23E-03 Sb-125 5.955% 5.55E-03 Cs-134 2.505% 2.34E-03 Cs-137 31.760% 2.96E-02

Dry Active Waste

Waste Class All Nuclide Name Percent Abundance Curies Mn-54 0.842% 7.85E-04 Fe-55 28.755% 2.68E-02 Co-58 4.077% 3.80E-03 Co-60 9.013% 8.40E-03 Ni-63 12.929% 1.21E-02 Zr-95 1.797% 1.68E-03 Nb-95 2.393% 2.23E-03 Sb-125 5.955% 5.55E-03 Cs-134 2.505% 2.34E-03 Cs-137 31.760% 2.96E-02 ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 59 of 113 Sum of All 4 Categories

Waste Class A Nuclide Name Percent Abundance Curies H-3 0.298% 2.25E-03 C-14 1.603% 1.21E-02 Sc-46 0.000% 1.50E-13 Cr-51 0.000% 3.56E-28 Mn-54 0.129% 9.76E-04 Fe-55 17.722% 1.34E-01 Fe-59 0.000% 1.08E-19 Co-57 0.002% 1.41E-05 Co-58 0.503% 3.80E-03 Co-60 8.808% 6.65E-02 Ni-59 0.491% 3.71E-03 Ni-63 63.053% 4.76E-01 Zn-65 0.000% 2.34E-06 Sr-89 0.000% 8.06E-19 Sr-90 0.010% 7.61E-05 Zr-95 0.222% 1.68E-03 Nb-95 0.295% 2.23E-03 Tc-99 0.017% 1.27E-04 Ag-110m 0.000% 9.19E-07 Sn-113 0.000% 1.13E-09 Sb-125 1.650% 1.25E-02 Cs-134 0.362% 2.73E-03 Cs-137 4.833% 3.65E-02 Ce-144 0.000% 3.39E-06 Hf-181 0.000% 1.53E-21 Pu-238 0.008% 5.83E-05 Cm-242 0.000% 1.70E-10 Cm-243 0.000% 1.21E-06 Cm-244 0.000% 1.10E-06

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 60 of 113 Sum of All 4 Categories

Waste Class B Nuclide Name Percent Abundance Curies C-14 0.656% 1.60E-01 Mn-54 2.344% 5.72E-01 Fe-55 14.221% 3.47E+00 Co-57 0.071% 1.73E-02 Co-58 0.078% 1.90E-02 Co-60 40.000% 9.76E+00 Ni-59 0.152% 3.71E-02 Ni-63 21.230% 5.18E+00 Zn-65 0.316% 7.70E-02 Sr-90 0.038% 9.37E-03 Cs-134 5.000% 1.22E+00 Cs-137 15.779% 3.85E+00

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 61 of 113 Sum of All 4 Categories

Waste Class All Nuclide Name Percent Abundance Curies H-3 0.009% 2.25E-03 C-14 0.686% 1.72E-01 Sc-46 0.000% 1.50E-13 Cr-51 0.000% 3.56E-28 Mn-54 2.283% 5.73E-01 Fe-55 14.358% 3.60E+00 Fe-59 0.000% 1.08E-19 Co-57 0.069% 1.73E-02 Co-58 0.091% 2.28E-02 Co-60 39.149% 9.83E+00 Ni-59 0.163% 4.08E-02 Ni-63 22.534% 5.66E+00 Zn-65 0.307% 7.70E-02 Sr-89 0.000% 8.06E-19 Sr-90 0.038% 9.45E-03 Zr-95 0.007% 1.68E-03 Nb-95 0.009% 2.23E-03 Tc-99 0.001% 1.27E-04 Ag-110m 0.000% 9.19E-07 Sn-113 0.000% 1.13E-09 Sb-125 0.050% 1.25E-02 Cs-134 4.871% 1.22E+00 Cs-137 15.484% 3.89E+00 Ce-144 0.000% 3.39E-06 Hf-181 0.000% 1.53E-21 Pu-238 0.000% 5.83E-05 Cm-242 0.000% 1.70E-10 Cm-243 0.000% 1.21E-06 Cm-244 0.000% 1.10E-06

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 62 of 113 Manifest Number Date Shipped Waste Volume Used Burial Volume Used RSR 12-066 (Combined Waste) 7/10/2012 Yes RSR 12-078 7/19/2012 Yes RSR 12-081 (Combined Waste) 7/23/2012 Yes RSR 12-086 (Combined Waste) 8/1/2012 Yes RSR 12-087 8/7/2013 Yes Combined Waste indicates that shipment was a mixture of Unit 1 and Unit 2 Waste.

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 63 of 113 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2012 to 12/31/2012 for Unit 1

Waste Stream: Resin, Filters, and Evaporator Bottom

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 1.13E+03 3.19E+01 1.34E+00 +/- 25% B 6.60E+02 1.87E+01 2.41E+02 +/- 25% C 4.74E+01 1.34E+00 9.50E+00 +/- 25%

All 1.84E+03 5.19E+01 2.52E+02 +/- 25%

Waste Stream: Dry Active Waste

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 4.99E+03 1.41E+02 2.41E-01 +/- 25% B 0.00E+00 0.00E+00 0.00E+00 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 4.99E+03 1.41E+02 2.41E-01

+/- 25%

Waste Stream: Irradiated Components

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 0.00E+00 0.00E+00 0.00E+00 +/- 25% B 0.00E+00 0.00E+00 0.00E+00 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 0.00E+00 0.00E+00 0.00E+00 +/- 25%

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 64 of 113 Waste Stream: Other Waste Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 0.00E+00 0.00E+00 0.00E+00 +/- 25% B 0.00E+00 0.00E+00 0.00E+00 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 0.00E+00 0.00E+00 0.00E+00 +/- 25%

Waste Stream: Sum of All 4 Categories

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 8.24E+03 1.73E+02 1.58E+00 +/- 25% B 6.60E+02 1.87E+01 2.41E+02 +/- 25% C 4.74E+01 1.34E+00 9.50E+00 +/- 25%

All 8.95E+03 1.93E+02 2.52E+02 +/- 25%

Number of Shipments Mode of Transportation Destination 3 Hittman Transport Toxco Inc.

2 R&R Trucking Inc Studsvik Processing Facility 7 Hittman Transport Studsvik Processing Facility 7* Hittman Transport Bear Creek Operation

Combined Waste Type Shipment (U1 and U2 Waste combined)

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 65 of 113 Resins, Filters, and Evaporator Bottom

Waste Class A Nuclide Name Percent Abundance Curies H-3 0.168% 2.25E-03 C-14 0.903% 1.21E-02 Sc-46 0.000% 1.50E-13 Cr-51 0.000% 8.89E-08 Mn-54 1.947% 2.61E-02 Fe-55 8.051% 1.08E-01 Fe-59 0.000% 1.46E-10 Co-57 0.070% 9.38E-04 Co-58 0.078% 1.04E-03 Co-60 46.500% 6.23E-01 Ni-59 0.277% 3.71E-03 Ni-63 34.661% 4.64E-01 Zn-65 0.219% 2.93E-03 Sr-89 0.000% 8.06E-19 Sr-90 0.006% 7.61E-05 Zr-95 0.015% 2.00E-04 Nb-95 0.000% 4.35E-06 Tc-99 0.009% 1.27E-04 Ag-110m 0.000% 9.19E-07 Sn-113 0.000% 1.45E-07 Sb-125 0.522% 7.00E-03 Cs-134 0.223% 2.99E-03 Cs-137 6.507% 8.72E-02 Ce-144 0.000% 3.39E-06 Hf-181 0.000% 6.27E-11 Pu-238 0.004% 5.83E-05 Cm-242 0.000% 1.70E-10 Cm-243 0.000% 1.21E-06 Cm-244 0.000% 1.10E-06

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 66 of 113 Resins, Filters, and Evaporator Bottom

Waste Class B Nuclide Name Percent Abundance Curies H-3 0.080% 1.94E-01 C-14 1.017% 2.45E+00 Mn-54 1.026% 2.47E+00 Fe-55 12.353% 2.98E+01 Co-57 0.070% 1.69E-01 Co-58 0.080% 1.93E-01 Co-60 19.610% 4.73E+01 Ni-59 0.179% 4.31E-01 Ni-63 38.581% 9.30E+01 Zn-65 0.115% 2.77E-01 Sr-89 0.000% 2.18E-10 Sr-90 0.057% 1.37E-01 Tc-99 0.002% 5.81E-03 Sb-125 0.167% 4.03E-01 Cs-134 7.021% 1.69E+01 Cs-137 19.647% 4.74E+01 Ce-144 0.010% 2.52E-02 Pu-239 0.000% 3.62E-05 Pu-240 0.000% 3.62E-05 Am-241 0.000% 2.88E-04 Cm-242 0.000% 4.25E-06 Cm-243 0.000% 2.19E-04 Cm-244 0.000% 2.13E-04 ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 67 of 113 Resins, Filters, and Evaporator Bottoms

Waste Class C Nuclide Name Percent Abundance Curies H-3 0.330% 3.13E-02 C-14 2.116% 2.01E-01 Sc-46 0.000% 3.09E-11 Cr-51 0.000% 2.12E-17 Mn-54 0.119% 1.13E-02 Fe-55 22.603% 2.15E+00 Fe-59 0.000% 6.71E-13 Co-57 0.012% 1.13E-03 Co-58 0.000% 6.57E-07 Co-60 10.151% 9.64E-01 Ni-59 0.478% 4.54E-02 Ni-63 61.603% 5.85E+00 Zn-65 0.003% 2.56E-04 Sr-89 0.000% 1.45E-13 Sr-90 0.011% 1.04E-03 Zr-95 0.000% 1.70E-08 Nb-95 0.000% 1.26E-13 Tc-99 0.014% 1.29E-03 Ag-110m 0.001% 8.44E-05 Sn-113 0.000% 9.29E-07 Sb-124 0.000% 3.25E-11 Sb-125 1.467% 1.39E-01 Cs-134 0.110% 1.04E-02 Cs-137 0.973% 9.24E-02 Ce-144 0.003% 2.76E-04 Hf-181 0.000% 5.76E-18 Pu-238 0.008% 7.42E-04 Cm-242 0.000% 1.21E-08 Cm-243 0.000% 1.23E-05 Cm-244 0.000% 1.14E-05

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 68 of 113 Resins, Filters, and Evaporator Bottom

Waste Class All Nuclide Name Percent Abundance Curies H-3 0.090% 2.28E-01 C-14 1.057% 2.66E+00 Sc-46 0.000% 3.11E-11 Cr-51 0.000% 8.89E-08 Mn-54 0.996% 2.51E+00 Fe-55 12.709% 3.20E+01 Fe-59 0.000% 1.47E-10 Co-57 0.068% 1.71E-01 Co-58 0.077% 1.94E-01 Co-60 19.384% 4.88E+01 Ni-59 0.191% 4.80E-01 Ni-63 39.403% 9.93E+01 Zn-65 0.111% 2.80E-01 Sr-89 0.000% 2.18E-10 Sr-90 0.055% 1.38E-01 Zr-95 0.000% 2.00E-04 Nb-95 0.000% 4.35E-06 Tc-99 0.003% 7.23E-03 Ag-110m 0.000% 8.53E-05 Sn-113 0.000% 1.07E-06 Sb-124 0.000% 3.25E-11 Sb-125 0.218% 5.49E-01 Cs-134 6.720% 1.69E+01 Cs-137 18.861% 4.75E+01 Ce-144 0.010% 2.55E-02 Hf-181 0.000% 6.27E-11 Pu-238 0.000% 8.00E-04 Am-241 0.000% 2.88E-04 Cm-242 0.000% 4.26E-06 Cm-243 0.000% 2.33E-04 Cm-244 0.000% 2.26E-04

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 69 of 113 Dry Active Waste

Waste Class A Nuclide Name Percent Abundance Curies Mn-54 0.952% 2.29E-03 Fe-55 26.500% 6.36E-02 Co-58 5.833% 1.40E-02 Co-60 9.000% 2.16E-02 Ni-63 11.750% 2.82E-02 Zr-95 2.242% 5.38E-03 Nb-95 4.054% 9.73E-03 Sb-125 5.500% 1.32E-02 Cs-134 3.121% 7.49E-03 Cs-137 30.917% 7.42E-02

Dry Active Waste

Waste Class All Nuclide Name Percent Abundance Curies Mn-54 0.952% 2.29E-03 Fe-55 26.500% 6.36E-02 Co-58 5.833% 1.40E-02 Co-60 9.000% 2.16E-02 Ni-63 11.750% 2.82E-02 Zr-95 2.242% 5.38E-03 Nb-95 4.054% 9.73E-03 Sb-125 5.500% 1.32E-02 Cs-134 3.121% 7.49E-03 Cs-137 30.917% 7.42E-02

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 70 of 113 Sum of All 4 Categories

Waste Class A Nuclide Name Percent Abundance Curies H-3 0.142% 2.25E-03 C-14 0.766% 1.21E-02 Sc-46 0.000% 1.50E-13 Cr-51 0.000% 8.89E-08 Mn-54 1.796% 2.84E-02 Fe-55 10.854% 1.71E-01 Fe-59 0.000% 1.46E-10 Co-57 0.059% 9.38E-04 Co-58 0.952% 1.50E-02 Co-60 40.804% 6.45E-01 Ni-59 0.235% 3.71E-03 Ni-63 31.181% 4.93E-01 Zn-65 0.186% 2.93E-03 Sr-89 0.000% 8.06E-19 Sr-90 0.005% 7.61E-05 Zr-95 0.353% 5.58E-03 Nb-95 0.616% 9.73E-03 Tc-99 0.008% 1.27E-04 Ag-110m 0.000% 9.19E-07 Sn-113 0.000% 1.45E-07 Sb-125 1.278% 2.02E-02 Cs-134 0.663% 1.05E-02 Cs-137 10.215% 1.61E-01 Ce-144 0.000% 3.39E-06 Hf-181 0.000% 6.27E-11 Pu-238 0.004% 5.83E-05 Cm-242 0.000% 1.70E-10 Cm-243 0.000% 1.21E-06 Cm-244 0.000% 1.10E-06

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 71 of 113 Sum of All 4 Categories

Waste Class B Nuclide Name Percent Abundance Curies H-3 0.080% 1.94E-01 C-14 1.017% 2.45E+00 Mn-54 1.026% 2.47E+00 Fe-55 12.353% 2.98E+01 Co-57 0.070% 1.69E-01 Co-58 0.080% 1.93E-01 Co-60 19.610% 4.73E+01 Ni-59 0.179% 4.31E-01 Ni-63 38.581% 9.30E+01 Zn-65 0.115% 2.77E-01 Sr-89 0.000% 2.18E-10 Sr-90 0.057% 1.37E-01 Tc-99 0.002% 5.81E-03 Sb-125 0.167% 4.03E-01 Cs-134 7.021% 1.69E+01 Cs-137 19.647% 4.74E+01 Ce-144 0.010% 2.52E-02 Pu-239 0.000% 3.62E-05 Pu-240 0.000% 3.62E-05 Am-241 0.000% 2.88E-04

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 72 of 113 Sum of All 4 Categories

Waste Class C Nuclide Name Percent Abundance Curies H-3 0.330% 3.13E-02 C-14 2.116% 2.01E-01 Sc-46 0.000% 3.09E-11 Cr-51 0.000% 2.12E-17 Mn-54 0.119% 1.13E-02 Fe-55 22.603% 2.15E+00 Fe-59 0.000% 6.71E-13 Co-57 0.012% 1.13E-03 Co-58 0.000% 6.57E-07 Co-60 10.151% 9.64E-01 Ni-59 0.478% 4.54E-02 Ni-63 61.603% 5.85E+00 Zn-65 0.003% 2.56E-04 Sr-89 0.000% 1.45E-13 Sr-90 0.011% 1.04E-03 Zr-95 0.000% 1.70E-08 Nb-95 0.000% 1.26E-13 Tc-99 0.014% 1.29E-03 Ag-110m 0.001% 8.44E-05 Sn-113 0.000% 9.29E-07 Sb-124 0.000% 3.25E-11 Sb-125 1.467% 1.39E-01 Cs-134 0.110% 1.04E-02 Cs-137 0.973% 9.24E-02 Ce-144 0.003% 2.76E-04 Hf-181 0.000% 5.76E-18 Pu-238 0.008% 7.42E-04 Cm-242 0.000% 1.21E-08 Cm-243 0.000% 1.23E-05 Cm-244 0.000% 1.14E-05 ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 73 of 113 Sum of All 4 Categories

Waste Class All Nuclide Name Percent Abundance Curies H-3 0.091% 2.30E-01 C-14 1.057% 2.68E+00 Sc-46 0.000% 3.12E-11 Cr-51 0.000% 1.78E-07 Mn-54 1.003% 2.54E+00 Fe-55 12.727% 3.22E+01 Fe-59 0.000% 2.93E-10 Co-57 0.068% 1.72E-01 Co-58 0.083% 2.09E-01 Co-60 19.562% 4.95E+01 Ni-59 0.191% 4.84E-01 Ni-63 39.442% 9.98E+01 Zn-65 0.112% 2.83E-01 Sr-89 0.000% 2.18E-10 Sr-90 0.055% 1.39E-01 Zr-95 0.002% 5.78E-03 Nb-95 0.004% 9.74E-03 Tc-99 0.003% 7.35E-03 Ag-110m 0.000% 8.62E-05 Sn-113 0.000% 1.22E-06 Sb-124 0.000% 3.25E-11 Sb-125 0.225% 5.69E-01 Cs-134 6.697% 1.69E+01 Cs-137 18.850% 4.77E+01 Ce-144 0.010% 2.55E-02 Hf-181 0.000% 1.25E-10 Pu-238 0.000% 8.59E-04 Am-241 0.000% 2.88E-04 Cm-242 0.000% 4.26E-06 Cm-243 0.000% 2.34E-04 Cm-244 0.000% 2.27E-04

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 74 of 113 Manifest Number Date Shipped Waste Volume Used Burial Volume Used RSR 12-001 (Combined Waste) 1/5/2012 Yes RSR 12-004 (Combined Waste) 1/12/2012 Yes RSR 12-007 1/16/2012 Yes RSR 12-010 1/23/2012 Yes RSR 12-021 2/15/2012 Yes RSR 12-026 2/29/2012 Yes RSR 12-037 3/29/2012 Yes RSR 12-039 4/5/2012 Yes

RSR 12-043 (Combined Waste) 4/12/2012 Yes RSR 12-044 (Combined Waste) 4/19/2012 Yes RSR 12-050 5/2/2012 Yes RSR 12-058 5/21/2012 Yes RSR 12-064 6/14/2012 Yes RSR 12-065 6/21/2012 Yes

RSR 12-066 (Combined Waste) 7/10/2012 Yes RSR 12-078 7/19/2012 Yes RSR 12-081 (Combined Waste) 7/23/2012 Yes RSR 12-086 (Combined Waste) 8/1/2012 Yes RSR 12-087 8/7/2013 Yes Combined Waste indicates that shipment was a mixture of Unit 1 and Unit 2 Waste

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 75 of 113 The summary for solid waste shipments for Unit 2 is as follows:

Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2012 to 06/30/2012

Waste Stream: Resins, Filters, and Evaporator Bottom

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 6.86E+01 1.94E+00 3.71E+00 +/- 25% B 6.00E+02 1.70E+01 2.37E+02 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 6.69E+02 1.89E+01 2.41E+02 +/- 25%

Waste Stream: Dry Active Waste

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 2.86E+03 8.10E+01 1.47E-01 +/- 25% B 0.00E+00 0.00E+00 0.00E+00 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 2.86E+03 8.10E+01 1.47E-01

+/- 25%

Waste Stream: Irradiated Components

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 0.00E+00 0.00E+00 0.00E+00 +/- 25% B 0.00E+00 0.00E+00 0.00E+00 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 0.00E+00 0.00E+00 0.00E+00 +/- 25%

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 76 of 113 Waste Stream: Other Waste Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 0.00E+00 0.00E+00 0.00E+00 +/- 25% B 0.00E+00 0.00E+00 0.00E+00 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 0.00E+00 0.00E+00 0.00E+00 +/- 25%

Waste Stream Sum of All 4 Categories

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 2.93E+03 8.29E+01 3.86E+00 +/- 25% B 6.00E+02 1.70E+01 2.37E+02 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 3.53E+03 9.99E+01 2.41E+02

+/- 25%

Number of Shipments Mode of Transportation Destination 7 Hittman Transport Studsvik Processing Facility 3 Hittman Transport Toxco. Inc. 4* Hittman transport Bear Creek Operations

Combined Waste Type Shipment.

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 77 of 113 Resins, Filters, and Evaporator Bottom

Waste Class A Nuclide Name Percent Abundance Curies H-3 0.036% 1.33E-03 C-14 3.693% 1.37E-01 Sc-46 0.000% 2.68E-08 Cr-51 0.000% 3.45E-11 Mn-54 0.728% 2.70E-02 Fe-55 55.795% 2.07E+00 Fe-59 0.000% 1.15E-08 Co-57 0.034% 1.27E-03 Co-58 0.004% 1.31E-04 Co-60 12.918% 4.79E-01 Ni-59 0.061% 2.26E-03 Ni-63 20.396% 7.57E-01 Zn-65 0.024% 9.08E-04 Sr-89 0.000% 5.24E-11 Sr-90 0.020% 7.47E-04 Zr-95 0.000% 1.41E-05 Nb-95 0.000% 7.13E-09 Tc-99 0.036% 1.32E-03 Ag-110m 0.189% 7.02E-03 Sn-113 0.003% 9.82E-05 Sb-125 0.984% 3.65E-02 Cs-134 0.168% 6.22E-03 Cs-137 4.803% 1.78E-01 Ce-144 0.041% 1.52E-03 Hf-181 0.000% 2.42E-11 Pu-238 0.001% 2.17E-05 Cm-242 0.000% 2.03E-06 Cm-243 0.000% 3.30E-06 Cm-244 0.000% 3.14E-06

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 78 of 113 Resins, Filters, and Evaporator Bottom

Waste Class B Nuclide Name Percent Abundance Curies H-3 0.019% 4.41E-02 C-14 1.139% 2.70E+00 Mn-54 3.114% 7.38E+00 Fe-55 17.257% 4.09E+01 Co-57 0.113% 2.67E-01 Co-58 1.975% 4.68E+00 Co-60 5.190% 1.23E+01 Ni-59 0.335% 7.94E-01 Ni-63 56.118% 1.33E+02 Zn-65 0.175% 4.15E-01 Sr-89 0.001% 2.67E-03 Sr-90 0.065% 1.54E-01 Tc-99 0.004% 1.03E-02 Ag-110m 0.005% 1.29E-02 Sn-113 0.000% 2.97E-04 Sb-125 0.650% 1.54E+00 Cs-134 3.852% 9.13E+00 Cs-137 10.000% 2.37E+01 Ce-144 0.004% 9.22E-03 Pu-238 0.000% 1.53E-04 Pu-239 0.000% 8.15E-05 Pu-240 0.000% 8.15E-05 Pu-241 0.004% 1.01E-02 Am-241 0.000% 3.20E-04 Cm-242 0.000% 2.04E-05 Cm-243 0.000% 1.12E-04 Cm-244 0.000% 1.09E-04

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 79 of 113 Resins, Filters, and Evaporator Bottom

Waste Class All Nuclide Name Percent Abundance Curies H-3 0.019% 4.54E-02 C-14 1.177% 2.84E+00 Sc-46 0.000% 2.68E-08 Cr-51 0.000% 3.45E-11 Mn-54 3.073% 7.41E+00 Fe-55 17.830% 4.30E+01 Fe-59 0.000% 1.15E-08 Co-57 0.111% 2.68E-01 Co-58 1.942% 4.68E+00 Co-60 5.303% 1.28E+01 Ni-59 0.330% 7.96E-01 Ni-63 55.501% 1.34E+02 Zn-65 0.173% 4.16E-01 Sr-89 0.001% 2.67E-03 Sr-90 0.064% 1.55E-01 Zr-95 0.000% 1.41E-05 Nb-95 0.000% 7.13E-09 Tc-99 0.005% 1.16E-02 Ag-110m 0.008% 1.99E-02 Sn-113 0.000% 3.95E-04 Sb-125 0.654% 1.58E+00 Cs-134 3.791% 9.14E+00 Cs-137 9.908% 2.39E+01 Ce-144 0.004% 1.07E-02 Hf-181 0.000% 2.42E-11 Pu-238 0.000% 1.75E-04 Pu-239 0.000% 8.15E-05 Pu-240 0.000% 8.15E-05 Pu-241 0.004% 1.01E-02 Am-241 0.000% 3.20E-04 Cm-242 0.000% 2.24E-05 Cm-243 0.000% 1.15E-04 Cm-244 0.000% 1.12E-04

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 80 of 113 Dry Active Waste

Waste Class A Nuclide Name Percent Abundance Curies Mn-54 1.027% 1.50E-03 Fe-55 25.205% 3.68E-02 Co-58 6.986% 1.02E-02 Co-60 9.041% 1.32E-02 Ni-63 10.993% 1.61E-02 Zr-95 2.531% 3.70E-03 Nb-95 5.137% 7.50E-03 Sb-125 5.240% 7.65E-03 Cs-134 3.527% 5.15E-03 Cs-137 30.548% 4.46E-02

Dry Active Waste

Waste Class ALL Nuclide Name Percent Abundance Curies Mn-54 1.027% 1.50E-03 Fe-55 25.205% 3.68E-02 Co-58 6.986% 1.02E-02 Co-60 9.041% 1.32E-02 Ni-63 10.993% 1.61E-02 Zr-95 2.531% 3.70E-03 Nb-95 5.137% 7.50E-03 Sb-125 5.240% 7.65E-03 Cs-134 3.527% 5.15E-03 Cs-137 30.548% 4.46E-02

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 81 of 113 Sum of All 4 Categories

Waste Class A Nuclide Name Percent Abundance Curies H-3 0.035% 1.33E-03 C-14 3.558% 1.37E-01 Sc-46 0.000% 2.68E-08 Cr-51 0.000% 3.45E-11 Mn-54 0.740% 2.85E-02 Fe-55 54.722% 2.11E+00 Fe-59 0.000% 1.15E-08 Co-57 0.033% 1.27E-03 Co-58 0.268% 1.03E-02 Co-60 12.791% 4.92E-01 Ni-59 0.059% 2.26E-03 Ni-63 20.073% 7.73E-01 Zn-65 0.024% 9.08E-04 Sr-89 0.000% 5.24E-11 Sr-90 0.019% 7.47E-04 Zr-95 0.096% 3.71E-03 Nb-95 0.195% 7.50E-03 Tc-99 0.034% 1.32E-03 Ag-110m 0.182% 7.02E-03 Sn-113 0.003% 9.82E-05 Sb-125 1.147% 4.42E-02 Cs-134 0.295% 1.14E-02 Cs-137 5.787% 2.23E-01 Ce-144 0.039% 1.52E-03 Hf-181 0.000% 2.42E-11 Pu-238 0.001% 2.17E-05 Cm-242 0.000% 2.03E-06 Cm-243 0.000% 3.30E-06 Cm-244 0.000% 3.14E-06

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 82 of 113 Sum of All 4 Categories

Waste Class B Nuclide Name Percent Abundance Curies H-3 0.019% 4.41E-02 C-14 1.139% 2.70E+00 Mn-54 3.114% 7.38E+00 Fe-55 17.257% 4.09E+01 Co-57 0.113% 2.67E-01 Co-58 1.975% 4.68E+00 Co-60 5.190% 1.23E+01 Ni-59 0.335% 7.94E-01 Ni-63 56.118% 1.33E+02 Zn-65 0.175% 4.15E-01 Sr-89 0.001% 2.67E-03 Sr-90 0.065% 1.54E-01 Tc-99 0.004% 1.03E-02 Ag-110m 0.005% 1.29E-02 Sn-113 0.000% 2.97E-04 Sb-125 0.650% 1.54E+00 Cs-134 3.852% 9.13E+00 Cs-137 10.000% 2.37E+01 Ce-144 0.004% 9.22E-03 Pu-238 0.000% 1.53E-04 Pu-239 0.000% 8.15E-05 Pu-240 0.000% 8.15E-05 Pu-241 0.004% 1.01E-02 Am-241 0.000% 3.20E-04 Cm-242 0.000% 2.04E-05 Cm-243 0.000% 1.12E-04 Cm-244 0.000% 1.09E-04

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 83 of 113 Sum of All 4 Categories

Waste Class ALL Nuclide Name Percent Abundance Curies H-3 0.019% 4.54E-02 C-14 1.177% 2.84E+00 Sc-46 0.000% 2.68E-08 Cr-51 0.000% 3.45E-11 Mn-54 3.074% 7.41E+00 Fe-55 17.845% 4.30E+01 Fe-59 0.000% 1.15E-08 Co-57 0.111% 2.68E-01 Co-58 1.946% 4.69E+00 Co-60 5.308% 1.28E+01 Ni-59 0.330% 7.96E-01 Ni-63 55.507% 1.34E+02 Zn-65 0.173% 4.16E-01 Sr-89 0.001% 2.67E-03 Sr-90 0.064% 1.55E-01 Zr-95 0.002% 3.71E-03 Nb-95 0.003% 7.50E-03 Tc-99 0.005% 1.16E-02 Ag-110m 0.008% 1.99E-02 Sn-113 0.000% 3.95E-04 Sb-125 0.657% 1.58E+00 Cs-134 3.793% 9.14E+00 Cs-137 9.926% 2.39E+01 Ce-144 0.004% 1.07E-02 Hf-181 0.000% 2.42E-11 Pu-238 0.000% 1.75E-04 Pu-239 0.000% 8.15E-05 Pu-240 0.000% 8.15E-05 Pu-241 0.004% 1.01E-02 Am-241 0.000% 3.20E-04 Cm-242 0.000% 2.24E-05 Cm-243 0.000% 1.15E-04 Cm-244 0.000% 1.12E-04

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 84 of 113 Manifest Number Date Shipped Waste Volume Used Burial Volume Used RSR 12-001 (Combined Waste) 1/5/2012 Yes RSR 12-004 (Combined Waste) 1/12/2012 Yes RSR 12-008 1/19/2012 Yes RSR 12-012 1/25/2012 Yes RSR 12-016 2/1/2012 Yes RSR 12-017 2/8/2012 Yes RSR 12-028 3/7/2012 Yes RSR 12-030 3/15/2012 Yes

RSR 12-043 (Combined Waste) 4/12/2013 Yes RSR 12-044 (Combined Waste) 4/19/2012 Yes RSR 12-045 4/18/2012 Yes RSR 12-047 4/26/2012 Yes RSR 12-051 5/10/2012 Yes RSR 12-055 5/14/2012 Yes Combined Waste indicates that shipment was a mixture of Unit 1 and Unit 2 Waste

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 85 of 113 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 07/01/2012 to 12/31/2012 for Unit 2

Waste Stream: Resin, Filters, and Evaporator Bottom

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 1.57E+03 4.44E+01 1.64E+00 +/- 25% B 1.08E+01 3.06E-01 6.16E+00 +/- 25% C 1.71E+01 4.84E-01 8.06E+01 +/- 25%

All 1.60E+03 4.52E+01 8.84E+01 +/- 25%

Waste Stream: Dry Active Waste

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 4.29E+03 1.21E+02 1.48E-01 +/- 25% B 0.00E+00 0.00E+00 0.00E+00 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 4.29E+03 1.21E+02 1.48E-01 +/- 25%

Waste Stream: Irradiated Components

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 0.00E+00 0.00E+00 0.00E+00 +/- 25% B 0.00E+00 0.00E+00 0.00E+00 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 0.00E+00 0.00E+00 0.00E+00 +/- 25%

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 86 of 113 Waste Stream: Other Waste Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 0.00E+00 0.00E+00 0.00E+00 +/- 25% B 0.00E+00 0.00E+00 0.00E+00 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 0.00E+00 0.00E+00 0.00E+00 +/- 25%

Waste Stream: Sum of All 4 Categories

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 5.86E+03 1.65E+02 1.79E+00 +/- 25% B 1.08E+01 3.06E-01 6.16E+00 +/- 25% C 1.71E+01 4.84E-01 8.06E+01 +/- 25%

All 5.89E+03 1.66E+02 8.86E+01 +/- 25%

Number of Shipments Mode of Transportation Destination 2 Hittman Transport Bear Creek Operations 4 Hittman Transport Toxco, Inc 3* Hittman Transport Bear Creek Operation

Combined Waste Type Shipment

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 87 of 113 Resins, Filters and Evaporator Bottoms

Waste Class A Nuclide Name Percent Abundance Curies H-3 0.165% 2.70E-03 Be-7 0.000% 1.58E-10 C-14 1.677% 2.75E-02 Sc-46 0.000% 1.03E-09 Cr-51 1.482% 2.43E-02 Mn-54 0.738% 1.21E-02 Fe-55 30.610% 5.02E-01 Fe-59 0.000% 1.01E-12 Co-57 0.043% 6.97E-04 Co-58 1.963% 3.22E-02 Co-60 10.671% 1.75E-01 Ni-59 0.411% 6.74E-03 Ni-63 47.195% 7.74E-01 Zn-65 0.177% 2.91E-03 Sr-89 0.000% 4.62E-13 Sr-90 0.016% 2.65E-04 Zr-95 0.147% 2.41E-03 Nb-95 0.273% 4.47E-03 Tc-99 0.115% 1.89E-03 Ag-110m 0.019% 3.08E-04 Sn-113 0.000% 1.51E-06 Sb-124 0.000% 2.91E-12 Sb-125 1.738% 2.85E-02 Cs-134 0.436% 7.15E-03 Cs-137 2.195% 3.60E-02 Ce-144 0.006% 9.84E-05 Hf-181 0.000% 1.51E-14 Pu-238 0.001% 1.15E-05 Cm-242 0.000% 8.99E-08 Cm-243 0.001% 1.82E-05 Cm-244 0.001% 1.70E-05

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 88 of 113 Resins, Filters and Evaporator Bottoms

Waste Class B Nuclide Name Percent Abundance Curies Co-60 17.398% 1.07E+00 Cs-134 28.293% 1.74E+00 Cs-137 54.309% 3.34E+00

Resins, Filters and Evaporator Bottoms

Waste Class C Nuclide Name Percent Abundance Curies H-3 0.001% 8.34E-04 Be-7 0.000% 1.07E-04 C-14 0.867% 7.00E-01 Cr-51 0.000% 4.43E-06 Mn-54 1.958% 1.58E+00 Fe-55 44.857% 3.62E+01 Fe-59 0.000% 1.97E-08 Co-57 0.054% 4.39E-02 Co-58 0.130% 1.05E-01 Co-60 22.800% 1.84E+01 Ni-63 27.509% 2.22E+01 Zn-65 0.121% 9.78E-02 Sr-89 0.000% 4.88E-08 Sr-90 0.017% 1.35E-02 Zr-95 0.020% 1.59E-02 Nb-95 0.004% 3.31E-03 Tc-99 0.002% 1.69E-03 Ag-110m 0.004% 3.37E-03 Sn-113 0.029% 2.36E-02 Sb-124 0.000% 1.68E-07 Sb-125 1.264% 1.02E+00 Cs-134 0.053% 4.26E-02 Cs-137 0.257% 2.07E-01 Ce-144 0.009% 7.09E-03 Hf-181 0.000% 1.73E-09 Cm-242 0.000% 3.30E-07

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 89 of 113 Resins, Filters and Evaporator Bottoms

Waste Class ALL Nuclide Name Percent Abundance Curies H-3 0.004% 3.53E-03 Be-7 0.000% 1.07E-04 C-14 0.822% 7.28E-01 Sc-46 0.000% 1.03E-09 Cr-51 0.027% 2.43E-02 Mn-54 1.799% 1.59E+00 Fe-55 41.471% 3.67E+01 Fe-59 0.000% 1.97E-08 Co-57 0.050% 4.46E-02 Co-58 0.155% 1.37E-01 Co-60 22.198% 1.96E+01 Ni-59 0.008% 6.74E-03 Ni-63 25.959% 2.30E+01 Zn-65 0.114% 1.01E-01 Sr-89 0.000% 4.88E-08 Sr-90 0.016% 1.38E-02 Zr-95 0.021% 1.83E-02 Nb-95 0.009% 7.78E-03 Tc-99 0.004% 3.58E-03 Ag-110m 0.004% 3.68E-03 Sn-113 0.027% 2.36E-02 Sb-124 0.000% 1.68E-07 Sb-125 1.185% 1.05E+00 Cs-134 2.022% 1.79E+00 Cs-137 4.049% 3.58E+00 Ce-144 0.008% 7.19E-03 Hf-181 0.000% 1.73E-09 Pu-238 0.000% 1.15E-05 Cm-242 0.000% 4.20E-07 Cm-243 0.000% 1.82E-05 Cm-244 0.000% 1.70E-05

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 90 of 113 Dry Active Waste

Waste Class A Nuclide Name Percent Abundance Curies CR-51 0.517% 7.65E-04 Mn-54 1.301% 1.93E-03 Fe-55 18.108% 2.68E-02 Co-57 0.045% 6.67E-05 C0-58 4.358% 6.45E-03 Co-60 10.047% 1.49E-02 Ni-63 32.297% 4.78E-02 Zn-65 0.247% 3.65E-04 Zr-95 1.261% 1.87E-03 Nb-95 1.639% 2.43E-03 Sb-125 4.831% 7.15E-03 Cs-134 2.201% 3.26E-03 Cs-137 23.169% 3.43E-02

Dry Active Waste

Waste Class All Nuclide Name Percent Abundance Curies CR-51 0.517% 7.65E-04 Mn-54 1.301% 1.93E-03 Fe-55 18.108% 2.68E-02 Co-57 0.045% 6.67E-05 C0-58 4.358% 6.45E-03 Co-60 10.047% 1.49E-02 Ni-63 32.297% 4.78E-02 Zn-65 0.247% 3.65E-04 Zr-95 1.261% 1.87E-03 Nb-95 1.639% 2.43E-03 Sb-125 4.831% 7.15E-03 Cs-134 2.201% 3.26E-03 Cs-137 23.169% 3.43E-02

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 91 of 113 Sum of All 4 Categories

Waste Class A Nuclide Name Percent Abundance Curies H-3 1.33E-03 0.035% C-14 1.37E-01 3.558% Sc-46 2.68E-08 0.000% Cr-51 3.45E-11 0.000% Mn-54 2.85E-02 0.740% Fe-55 2.11E+00 54.722%

Fe-59 1.15E-08 0.000% Co-57 1.27E-03 0.033%

Co-58 1.03E-02 0.268%

Co-60 4.92E-01 12.791% Ni-59 2.26E-03 0.059%

Ni-63 7.73E-01 20.073% Zn-65 9.08E-04 0.024% Sr-89 5.24E-11 0.000%

Sr-90 7.47E-04 0.019% Zr-95 3.71E-03 0.096% Nb-95 7.50E-03 0.195% Tc-99 1.32E-03 0.034% Ag-110m 7.02E-03 0.182% Sn-113 9.82E-05 0.003%

Sb-125 4.42E-02 1.147%

Cs-134 1.14E-02 0.295%

Cs-137 2.23E-01 5.787% Ce-144 1.52E-03 0.039% Hf-181 2.42E-11 0.000% Pu-238 2.17E-05 0.001% Cm-242 2.03E-06 0.000%

Cm-243 3.30E-06 0.000%

Cm-244 3.14E-06 0.000%

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 92 of 113 Sum of All 4 Categories

Waste Class B Nuclide Name Percent Abundance Curies Co-60 17.398% 1.07E+00 Cs-134 28.293% 1.74E+00 Cs-137 54.309% 3.34E+00

Sum of All 4 Categories

Waste Class C Nuclide Name Percent Abundance Curies H-3 0.001% 8.34E-04 Be-7 0.000% 1.07E-04 C-14 0.867% 7.00E-01 Cr-51 0.000% 4.43E-06 Mn-54 1.958% 1.58E+00 Fe-55 44.857% 3.62E+01 Fe-59 0.000% 1.97E-08 Co-57 0.054% 4.39E-02 Co-58 0.130% 1.05E-01 Co-60 22.800% 1.84E+01 Ni-63 27.509% 2.22E+01 Zn-65 0.121% 9.78E-02 Sr-89 0.000% 4.88E-08 Sr-90 0.017% 1.35E-02 Zr-95 0.020% 1.59E-02 Nb-95 0.004% 3.31E-03 Tc-99 0.002% 1.69E-03 Ag-110m 0.004% 3.37E-03 Sn-113 0.029% 2.36E-02 Sb-124 0.000% 1.68E-07 Sb-125 1.264% 1.02E+00 Cs-134 0.053% 4.26E-02 Cs-137 0.257% 2.07E-01 Ce-144 0.009% 7.09E-03 Hf-181 0.000% 1.73E-09 Cm-242 0.000% 3.30E-07 ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 93 of 113 Sum of All 4 Categories

Waste Class ALL Nuclide Name Percent Abundance Curies H-3 0.004% 3.53E-03 Be-7 0.000% 1.07E-04 C-14 0.821% 7.28E-01 Sc-46 0.000% 1.03E-09 Cr-51 0.027% 2.43E-02 Mn-54 1.799% 1.59E+00 Fe-55 41.466% 3.67E+01 Fe-59 0.000% 1.97E-08 Co-57 0.050% 4.46E-02 Co-58 0.166% 1.47E-01 Co-60 22.188% 1.97E+01 Ni-59 0.008% 6.74E-03 Ni-63 25.948% 2.30E+01 Zn-65 0.114% 1.01E-01 Sr-89 0.000% 4.88E-08 Sr-90 0.016% 1.38E-02 Zr-95 0.025% 2.20E-02 Nb-95 0.017% 1.53E-02 Tc-99 0.004% 3.58E-03 Ag-110m 0.004% 3.68E-03 Sn-113 0.027% 2.36E-02 Sb-124 0.000% 1.68E-07 Sb-125 1.192% 1.06E+00 Cs-134 2.026% 1.79E+00 Cs-137 4.094% 3.63E+00 Ce-144 0.008% 7.19E-03 Hf-181 0.000% 1.73E-09 Pu-238 0.000% 1.15E-05 Cm-242 0.000% 4.20E-07 Cm-243 0.000% 1.82E-05 Cm-244 0.000% 1.70E-05

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 94 of 113 Manifest Number Date Shipped Waste Volume Used Burial Volume Used RSR 12-066 (Combined Waste) 7/10/2012 Yes RSR 12-073 7/16/2012 Yes RSR 12-081 (Combined Waste) 7/23/2012 Yes RSR 12-086 (Combined Waste) 8/1/2012 Yes RSR 12-125 11/29/2012 Yes RSR 12-126 12/4/2012 Yes RSR 12-127 12/6/2012 Yes RSR 12-131 12/11/2012 Yes RSR 12-130 12/12/2012 Yes Combined Waste indicates that shipment was a mixture of Unit 1 and Unit 2 Waste.

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 95 of 113 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2012 to 12/31/2012 for Unit 2

Waste Stream: Resin, Filters, and Evaporator Bottoms

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 1.57E+03 4.63E+01 5.35E+00 +/- 25% B 6.11E+02 1.73E+01 2.43E+02 +/- 25% C 1.71E+01 4.84E-01 8.06E+01 +/- 25%

All 2.20E+03 6.41E+01 3.29E+02 +/- 25%

Waste Stream: Dry Active Waste

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 7.15E+03 2.02E+02 2.95E-01 +/- 25% B 0.00E+00 0.00E+00 0.00E+00 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 7.15E+03 2.02E+02 2.95E-01

+/- 25%

Waste Stream: Irradiated Components

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 0.00E+00 0.00E+00 0.00E+00 +/- 25% B 0.00E+00 0.00E+00 0.00E+00 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 0.00E+00 0.00E+00 0.00E+00 +/- 25%

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 96 of 113 Waste Stream: Other Waste Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 0.00E+00 0.00E+00 0.00E+00 +/- 25% B 0.00E+00 0.00E+00 0.00E+00 +/- 25% C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 0.00E+00 0.00E+00 0.00E+00 +/- 25%

Waste Stream: Sum of All 4 Categories

Volume Waste Class Ft 3 M 3 Curies Shipped % Error (Ci)

A 8.79E+03 2.48E+02 5.65E+00 +/- 25% B 6.11E+02 1.73E+01 2.43E+02 +/- 25% C 1.71E+01 4.84E-01 8.06E+01 +/- 25%

All 9.42E+03 2.66E+02 3.29E+02 +/- 25%

Number of Shipments Mode of Transportation Destination 7* Hittman Transport Bear Creek Operations 2 Hittman transport Bear Creek Operations 7 Hittman Transport Toxco, Inc 7 Hittman Transport Studsvik Processing Facility

Combined Waste Type Shipment.

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 97 of 113 Resin, Filters, and Evaporator Bottoms

Waste Class A Nuclide Name Percent Abundance Curies H-3 0.075% 4.03E-03 Be-7 0.000% 1.58E-10 C-14 3.075% 1.65E-01 Sc-46 0.000% 2.78E-08 Cr-51 0.454% 2.43E-02 Mn-54 0.731% 3.91E-02 Fe-55 48.075% 2.57E+00 Fe-59 0.000% 1.15E-08 Co-57 0.037% 1.97E-03 Co-58 0.604% 3.23E-02 Co-60 12.224% 6.54E-01 Ni-59 0.168% 9.00E-03 Ni-63 28.617% 1.53E+00 Zn-65 0.071% 3.82E-03 Sr-89 0.000% 5.29E-11 Sr-90 0.019% 1.01E-03 Zr-95 0.045% 2.42E-03 Nb-95 0.084% 4.47E-03 Tc-99 0.060% 3.21E-03 Ag-110m 0.137% 7.33E-03 Sn-113 0.002% 9.97E-05 Sb-124 0.000% 2.91E-12 Sb-125 1.215% 6.50E-02 Cs-134 0.250% 1.34E-02 Cs-137 4.000% 2.14E-01 Ce-144 0.030% 1.62E-03 Hf-181 0.000% 2.42E-11 Pu-238 0.001% 3.32E-05 Cm-242 0.000% 3.23E-06 Cm-243 0.000% 3.30E-06 Cm-244 0.000% 3.14E-06

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 98 of 113 Resin, Filters, and Evaporator Bottoms

Waste Class B Nuclide Name Percent Abundance Curies H-3 0.018% 4.41E-02 C-14 1.111% 2.70E+00 Mn-54 3.037% 7.38E+00 Fe-55 16.831% 4.09E+01 Co-57 0.110% 2.67E-01 Co-58 1.926% 4.68E+00 Co-60 5.502% 1.34E+01 Ni-59 0.327% 7.94E-01 Ni-63 54.733% 1.33E+02 Zn-65 0.171% 4.15E-01 Sr-89 0.001% 2.67E-03 Sr-90 0.063% 1.54E-01 Tc-99 0.004% 1.03E-02 Ag-110m 0.005% 1.29E-02 Sn-113 0.000% 2.97E-04 Sb-125 0.634% 1.54E+00 Cs-134 4.473% 1.09E+01 Cs-137 11.128% 2.70E+01 Ce-144 0.004% 9.22E-03 Pu-238 0.000% 1.53E-04 Pu-239 0.000% 8.15E-05 Pu-240 0.000% 8.15E-05 Pu-241 0.004% 1.01E-02 Am-241 0.000% 3.20E-04 Cm-242 0.000% 2.04E-05 Cm-243 0.000% 1.12E-04 Cm-244 0.000% 1.09E-04

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 99 of 113 Resins, Filters and Evaporator Bottoms

Waste Class C Nuclide Name Percent Abundance Curies H-3 0.001% 8.34E-04 Be-7 0.000% 1.07E-04 C-14 0.867% 7.00E-01 Cr-51 0.000% 4.43E-06 Mn-54 1.958% 1.58E+00 Fe-55 44.857% 3.62E+01 Fe-59 0.000% 1.97E-08 Co-57 0.054% 4.39E-02 Co-58 0.130% 1.05E-01 Co-60 22.800% 1.84E+01 Ni-63 27.509% 2.22E+01 Zn-65 0.121% 9.78E-02 Sr-89 0.000% 4.88E-08 Sr-90 0.017% 1.35E-02 Zr-95 0.020% 1.59E-02 Nb-95 0.004% 3.31E-03 Tc-99 0.002% 1.69E-03 Ag-110m 0.004% 3.37E-03 Sn-113 0.029% 2.36E-02 Sb-124 0.000% 1.68E-07 Sb-125 1.264% 1.02E+00 Cs-134 0.053% 4.26E-02 Cs-137 0.257% 2.07E-01 Ce-144 0.009% 7.09E-03 Hf-181 0.000% 1.73E-09 Cm-242 0.000% 3.30E-07

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 100 of 113 Resin, Filters, and Evaporator Bottoms

Waste Class ALL Nuclide Name Percent Abundance Curies H-3 0.015% 4.90E-02 Be-7 0.000% 1.07E-04 C-14 1.083% 3.56E+00 Sc-46 0.000% 2.78E-08 Cr-51 0.007% 2.43E-02 Mn-54 2.735% 9.00E+00 Fe-55 24.216% 7.97E+01 Fe-59 0.000% 3.12E-08 Co-57 0.095% 3.13E-01 Co-58 1.464% 4.82E+00 Co-60 9.855% 3.24E+01 Ni-59 0.244% 8.03E-01 Ni-63 47.639% 1.57E+02 Zn-65 0.157% 5.17E-01 Sr-89 0.001% 2.67E-03 Sr-90 0.051% 1.69E-01 Zr-95 0.006% 1.83E-02 Nb-95 0.002% 7.78E-03 Tc-99 0.005% 1.52E-02 Ag-110m 0.007% 2.36E-02 Sn-113 0.007% 2.40E-02 Sb-124 0.000% 1.68E-07 Sb-125 0.798% 2.63E+00 Cs-134 3.321% 1.09E+01 Cs-137 8.347% 2.75E+01 Ce-144 0.005% 1.79E-02 Hf-181 0.000% 1.75E-09 Pu-238 0.000% 1.86E-04 Pu-239 0.000% 8.15E-05 Pu-240 0.000% 8.15E-05 Pu-241 0.003% 1.01E-02 Am-241 0.000% 3.20E-04 Cm-242 0.000% 2.40E-05 Cm-243 0.000% 1.15E-04 Cm-244 0.000% 1.12E-04

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 101 of 113 Dry Active Waste

Waste Class A Nuclide Name Percent Abundance Curies CR-51 0.260% 7.65E-04 Mn-54 1.165% 3.43E-03 Fe-55 21.633% 6.36E-02 Co-57 0.023% 6.67E-05 Co-58 5.663% 1.67E-02 Co-60 9.548% 2.81E-02 Ni-63 21.735% 6.39E-02 Zn-65 0.124% 3.65E-04 Zr-95 1.893% 5.57E-03 Nb-95 3.376% 9.93E-03 Sb-125 5.034% 1.48E-02 Cs-134 2.860% 8.41E-03 Cs-137 26.833% 7.89E-02 Dry Active Waste

Waste Class All Nuclide Name Percent Abundance Curies CR-51 0.260% 7.65E-04 Mn-54 1.165% 3.43E-03 Fe-55 21.633% 6.36E-02 Co-57 0.023% 6.67E-05 Co-58 5.663% 1.67E-02 Co-60 9.548% 2.81E-02 Ni-63 21.735% 6.39E-02 Zn-65 0.124% 3.65E-04 Zr-95 1.893% 5.57E-03 Nb-95 3.376% 9.93E-03 Sb-125 5.034% 1.48E-02 Cs-134 2.860% 8.41E-03 Cs-137 26.833% 7.89E-02 ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 102 of 113 Sum of All 4 Categories

Waste Class A Nuclide Name Percent Abundance Curies H-3 0.071% 4.03E-03 Be-7 0.000% 1.58E-10 C-14 2.917% 1.65E-01 Sc-46 0.000% 2.78E-08 Cr-51 0.444% 2.51E-02 Mn-54 0.754% 4.25E-02 Fe-55 46.730% 2.64E+00 Fe-59 0.000% 1.15E-08 Co-57 0.036% 2.03E-03 Co-58 0.868% 4.90E-02 Co-60 12.093% 6.82E-01 Ni-59 0.160% 9.00E-03 Ni-63 28.278% 1.59E+00 Zn-65 0.074% 4.18E-03 Sr-89 0.000% 5.29E-11 Sr-90 0.018% 1.01E-03 Zr-95 0.142% 7.99E-03 Nb-95 0.255% 1.44E-02 Tc-99 0.057% 3.21E-03 Ag-110m 0.130% 7.33E-03 Sn-113 0.002% 9.97E-05 Sb-124 0.000% 2.91E-12 Sb-125 1.415% 7.98E-02 Cs-134 0.386% 2.18E-02 Cs-137 5.193% 2.93E-01 Ce-144 0.029% 1.62E-03 Hf-181 0.000% 2.42E-11 Pu-238 0.001% 3.32E-05 Cm-242 0.000% 3.23E-06 Cm-243 0.000% 3.30E-06 Cm-244 0.000% 3.14E-06 ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 103 of 113 Sum of All 4 Categories

Waste Class B Nuclide Name Percent Abundance Curies H-3 0.018% 4.41E-02 C-14 1.111% 2.70E+00 Mn-54 3.037% 7.38E+00 Fe-55 16.831% 4.09E+01 Co-57 0.110% 2.67E-01 Co-58 1.926% 4.68E+00 Co-60 5.502% 1.34E+01 Ni-59 0.327% 7.94E-01 Ni-63 54.733% 1.33E+02 Zn-65 0.171% 4.15E-01 Sr-89 0.001% 2.67E-03 Sr-90 0.063% 1.54E-01 Tc-99 0.004% 1.03E-02 Ag-110m 0.005% 1.29E-02 Sn-113 0.000% 2.97E-04 Sb-125 0.634% 1.54E+00 Cs-134 4.473% 1.09E+01 Cs-137 11.128% 2.70E+01 Ce-144 0.004% 9.22E-03 Pu-238 0.000% 1.53E-04 Pu-239 0.000% 8.15E-05 Pu-240 0.000% 8.15E-05 Pu-241 0.004% 1.01E-02 Am-241 0.000% 3.20E-04 Cm-242 0.000% 2.04E-05 Cm-243 0.000% 1.12E-04 Cm-244 0.000% 1.09E-04

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 104 of 113 Sum of All 4 Categories

Waste Class C Nuclide Name Percent Abundance Curies H-3 0.001% 8.34E-04 Be-7 0.000% 1.07E-04 C-14 0.867% 7.00E-01 Cr-51 0.000% 4.43E-06 Mn-54 1.958% 1.58E+00 Fe-55 44.857% 3.62E+01 Fe-59 0.000% 1.97E-08 Co-57 0.054% 4.39E-02 Co-58 0.130% 1.05E-01 Co-60 22.800% 1.84E+01 Ni-63 27.509% 2.22E+01 Zn-65 0.121% 9.78E-02 Sr-89 0.000% 4.88E-08 Sr-90 0.017% 1.35E-02 Zr-95 0.020% 1.59E-02 Nb-95 0.004% 3.31E-03 Tc-99 0.002% 1.69E-03 Ag-110m 0.004% 3.37E-03 Sn-113 0.029% 2.36E-02 Sb-124 0.000% 1.68E-07 Sb-125 1.264% 1.02E+00 Cs-134 0.053% 4.26E-02 Cs-137 0.257% 2.07E-01 Ce-144 0.009% 7.09E-03 Hf-181 0.000% 1.73E-09 Cm-242 0.000% 3.30E-07 ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 105 of 113 Sum of All 4 Categories

Waste Class All Nuclide Name Percent Abundance Curies H-3 0.015% 4.90E-02 Be-7 0.000% 1.07E-04 C-14 1.080% 3.56E+00 Sc-46 0.000% 2.78E-08 Cr-51 0.008% 2.51E-02 Mn-54 2.728% 9.00E+00 Fe-55 24.162% 7.97E+01 Fe-59 0.000% 3.12E-08 Co-57 0.095% 3.13E-01 Co-58 1.465% 4.83E+00 Co-60 9.843% 3.25E+01 Ni-59 0.243% 8.03E-01 Ni-63 47.514% 1.57E+02 Zn-65 0.157% 5.17E-01 Sr-89 0.001% 2.67E-03 Sr-90 0.051% 1.69E-01 Zr-95 0.007% 2.39E-02 Nb-95 0.005% 1.77E-02 Tc-99 0.005% 1.52E-02 Ag-110m 0.007% 2.36E-02 Sn-113 0.007% 2.40E-02 Sb-124 0.000% 1.68E-07 Sb-125 0.800% 2.64E+00 Cs-134 3.323% 1.10E+01 Cs-137 8.333% 2.75E+01 Ce-144 0.005% 1.79E-02 Hf-181 0.000% 1.75E-09 Pu-238 0.000% 1.86E-04 Pu-239 0.000% 8.15E-05 Pu-240 0.000% 8.15E-05 Pu-241 0.003% 1.01E-02 Am-241 0.000% 3.20E-04 Cm-242 0.000% 2.40E-05 Cm-243 0.000% 1.15E-04 Cm-244 0.000% 1.12E-04

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 106 of 113 Manifest Number Date Shipped Waste Volume Used Burial Volume Used RSR 12-001 (Combined Waste) 1/5/2012 Yes RSR 12-004 (Combined Waste) 1/12/2012 Yes RSR 12-008 1/19/2012 Yes RSR 12-012 1/25/2012 Yes RSR 12-016 2/1/2012 Yes RSR 12-017 2/8/2012 Yes RSR 12-028 3/7/2012 Yes RSR 12-030 3/15/2012 Yes

RSR 12-043 (Combined Waste) 4/12/2013 Yes RSR 12-044 (Combined Waste) 4/19/2012 Yes RSR 12-045 4/18/2012 Yes RSR 12-047 4/26/2012 Yes RSR 12-051 5/10/2012 Yes RSR 12-055 5/14/2012 Yes

RSR 12-066 (Combined Waste) 7/10/2012 Yes RSR 12-073 7/16/2012 Yes RSR 12-081 (Combined Waste) 7/23/2012 Yes RSR 12-086 (Combined Waste) 8/1/2012 Yes RSR 12-125 11/29/2012 Yes RSR 12-126 12/4/2012 Yes RSR 12-127 12/6/2012 Yes RSR 12-130 12/12/2012 Yes RSR 12-131 12/11/2012 Yes Combined Waste indicates that shipment was a mixture of Unit 1 and Unit 2 Waste.

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 107 of 113

9. UNPLANNED RELEASES

An unplanned release is the unintended discharge of a volume of liquid or airborne radioactivity to

unrestricted areas.

During 2012, there were zero unplanned releases (liquid or gaseous) to an unrestricted area on

ANO-1.

During 2012, there were zero unplanned releases (liquid or gaseous) to an unrestricted area on

ANO-2.

10. RADIATION INSTRUMENTATION As required by ODCM Appendix 1, any radioactive effluent instrumentation inoperable for more

than 30 days shall be reported in the ARERR.

There was zero radioactive effluent instrumentation inoperable for more than 30 days in 2012.

11. CHANGES TO THE PROCESS CONTROL PROGRAM As required by ODCM Section 5.0, a description of changes made to the Process Control Program (EN-RW-105) shall be included in the ARERR for the period in which the change was made

effective. There were no changes to EN-RW-105 for 2012.

12. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL In accordance with Unit 1 and Unit 2 TS, changes to the ODCM shall be included in the ARERR for

the period in which the change(s) was made effective.

During 2012 the ODCM was reformatted to conform to ANO's Licensing Basis Document template.

Appendices 1 and 2 were combined into one appendix for both Unit 1 and Unit 2.

Major change was to assign an applicable analysis frequency for ODCM required samples. This

change was to eliminate the possibility that a sample was taken but never analyzed. These

analysis frequencies were applied to both Effluent and Environmental sampling requirements.

Each limitation was also assigned an additional action to write a condition report immediately after

the limitation is violated.

Sample point STR-6 was added to sampling requirement for the Radiological Environmental

Monitoring Program (REMP).

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 108 of 113 13. LLD LEVELS In accordance with ODCM Appendix 1 lower limits of detection (LLDs) higher than required shall

be documented in the ARERR.

During 2012, there were no LLDs higher than required.

14. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

In accordance with ODCM Appendix 1 Limitations L2.5.1.B and L2.5.2.A, unavailability of milk or

fresh, leafy vegetable samples, or an increase in an environmental sample location's calculated

dose commitment must be identified in the ARERR.

A. Changes in Sample Locations

During 2012, there were no changes to milk or fresh leafy vegetable sample locations or

instances where milk or fresh leafy vegetable samples were unavailable.

B. Increase in Calculated Dose Commitment

There were no environmental sampling locations identified during 2012 that would yield a

calculated dose commitment greater than the values currently being calculated.

15.

SUMMARY

OF HOURLY METEOROLOGICAL DATA

In accordance with ODCM Appendix 1 Section 5.2, in lieu of including a summary of the

meteorological data in this report, the 2012 data is retained at ANO. This data is available for NRC

review.

16. DESCRIPTION OF MAJOR CHANGES TO RADIOACTIVE WASTE SYSTEMS

There were no major changes made to the Unit 1 or Unit 2 liquid and gaseous radwaste systems

or the solid radwaste system during 2012.

17. RADIOACTIVE GROUND WATER MONITORING PROGRAM DATA NEI 07-07, "Industry Ground Water Protection Initiative - Final Guidance Document,"

Objective 2.4, "Annual Reporting", requires documentation of all on-site ground water sample

results and a description of any significant on-site leaks/spills into ground water for each calendar

year in the ARERR as contained in the appropriate reporting procedure.

A. NEI 07-07 Objective 2.4, "Annual Reporting", Acceptance Criteria "b.i" requires that ground water sample results that are taken in support of the Ground Water Protection Initiative (GPI)

but are not part of the REMP program (e.g. samples obtained during the investigatory phase

of the action plan) are reported in the ARERR. Additionally, Entergy's procedure EN-CY-111, "Radiological Ground Water Monitoring Program," Step 5.9.3 requires that a listing of non-

REMP wells and a summary of pertinent sample results from the Radiological Ground Water ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 109 of 113 Monitoring Program (RGWMP) are reported in the ARERR and an estimate of the doses to a member of the public associated with off-site releases of licensed radioactive material via

ground water is included in the ARERR.

In 2012, there were no "non-REMP" designated ground water wells installed at ANO. There

were no new "REMP" designated ground water wells installed in 2012. There were four

previously installed (prior to 2010) "REMP" designated ground water wells. The results of the

samples collected from the "REMP" designated ground water wells are included in the 2012

Annual Radiological Environmental Operating Report (AREOR) as required by NEI 07-07.

The AREOR for the calendar year 2012 has not been submitted as of the date of this

transmittal. The AREOR will be submitted to the NRC in accordance with the ANO-1 and

ANO-2 TSs.

ANO did not show any positive results during storm water sampling activities in 2012.

ANO did not show any positive results during ground water sampling activities in 2012.

B. NEI 07-07 Objective 2.4, Acceptance Criteria "c.ii" requires that a description of all spills or leaks that were communicated per NEI 07-07 Objective 2.2, "Voluntary Communication" be

included in the ARERR. Additionally, Entergy's procedure EN-RP-113, "Response to

Contaminated Spills/Leaks," requires that the following be included in the ARERR:

1. Spills/leaks documented on Attachment 9.1 that were released to the environment or outside the spent fuel pool enclosure, SHALL be documented in the next ARERR.

2. The documentation in the ARERR report will contain: (a) Description of event (b) Impact of event (c) Remediation of event (d) Radioactive contamination content and levels of event (e) Discussion of impact on groundwater, if any In 2012, there were no spills/leaks that required communication per NEI 07-07 Objective 2.2 or

inclusion in the ARERR per EN-RP-113.

A PCRS search was conducted using radioactive spill(s) as the search criteria. No items were

found.

Entergy's procedure EN-CY-108, "Monitoring of Non-Radioactive Systems," requires that verified

positive results associated with the sampling of designated nonradioactive or cross-contaminated

systems are to be included in the site's AR ERR, unless already reported under an existing monitored ODCM release point.

In 2012, there were no verified positive results associated with the sampling of designated

nonradioactive or cross-contaminated systems.

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 110 of 113 18. Carbon-14 Reporting The purpose of this section is to provide the required input for Carbon-14 (C-14) effluent source

term calculations. In Revision 2 of Regulatory Guide (RG) 1.21, the NRC has recommended that

U.S. nuclear power plants evaluate whether C-14 is a principle gaseous effluent, and if so, report

the amount of C-14 released.

C-14 is a naturally occurring isotope of carbon. C-14 is produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally. Radioactive effluents

from commercial nuclear power plants have decreased to the point that C-14 can become a

principle radionuclide in gaseous effluents, as defined in RG 1.21. Therefore, concentrations and

offsite dose from C-14 have been estimated and included in this report for ANO. This is the

second time that information for C-14 has been provided for ANO.

In 2010, ANO and other facilities participated in an EPRI task force to build a model to accurately

estimate C-14 releases, given some key site-specific plant parameters (e.g., mass of the primary

coolant, average thermal neutron cross section, rated thermal power). For purposes of industry

standardization, the output from the EPRI model is presented in this report in the following

spreadsheets.

ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 111 of 113 Facility Name:

Arkansas Nuclear One - Unit 1 Reactor Type WPWR WPWR, CEPWR, or BWR Reactor Power Rating 2568 Megawatts (thermal) Equivalent Full Power Operation 365 Days Critical Receptor Undepleted X/Q 5.00E-07 sec/m 3 Fractional Equilibrium Ratio, p 1.00 RG-1.109 Equation C-8; assu me 1.0 for continuous release Milk Ingestion Pathway Y Enter "Y"' to assume milk inges tion pathway, "N" to ignore pathway Meat Ingestion Pathway Y Enter "Y"' to assume meat inges tion pathway, "N" to ignore pathway Leafy Vegetable Ingestion Pathway Y Enter "Y"' to assume leafy vegetable ingestion pathway, "N" to ignore pathway Garden Produce Ingestion Pathway Y Enter "Y"' to assume garden produce (non-leafy vegetable+fruit+grain) ingestion pathway, "N" to ignore pathway Custom C-14 Production Rate 8.92 Ci Produced; Enter 'D' to assume default values Custom Gaseous Release Fraction D % C-14 production released as a gaseous effl uent; Enter 'D' to assume default values Custom Gaseous Release Rate D Ci Released; Enter 'D' to assume default values Custom Carbon Dioxide Fraction D % C-14 released as Carbon Dioxide; Enter 'D' to assume default values Normalized values listed in this section are taken from EPRI Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents", 2010, pages 4-28 and 3-26 Parameter WPWR CEPWR BWR Site Values Normalized Production - Ci/GWt-yr 3.4 3.9 5.1 8.92 Ci Produced Gaseous Release Fraction 98% 98% 99% 98% % Released Normalized Release - Ci/GWt-yr 3.33 3.82 5.05 8.74 Ci Released C-14 Carbon Dioxide Fraction 30% 30% 95% 30% %CO 2 Total Dioxide C-14 Release - Ci 8.74E+00 2.62E+00 MAXIMUM DOSE VALUES Organ Age mrem/yr RG-1.109 Bone Child 2.41E-01 RG-1.109 T.Body/Other Child 4.81E-02 ICRP-72 CEDE Teen 7.29E-02 ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 112 of 113 Facility Name:

Arkansas Nuclear One - Unit 2 Reactor Type CEPWR WPWR, CEPWR, or BWR Reactor Power Rating 3026 Megawatts (thermal) Equivalent Full Power Operation 365 Days Critical Receptor Undepleted X/Q 5.00E-07 sec/m 3 Fractional Equilibrium Ratio, p 1.00 RG-1.109 Equation C-8; assu me 1.0 for continuous release Milk Ingestion Pathway Y Enter "Y"' to assume milk inges tion pathway, "N" to ignore pathway Meat Ingestion Pathway Y Enter "Y"' to assume meat inges tion pathway, "N" to ignore pathway Leafy Vegetable Ingestion Pathway Y Enter "Y"' to assume leafy vegetable ingestion pathway, "N" to ignore pathway Garden Produce Ingestion Pathway Y Enter "Y"' to assume garden produce (non-leafy vegetable+fruit+grain) ingestion pathway, "N" to ignore pathway Custom C-14 Production Rate 11.166612 Ci Produced; Enter 'D' to assume default values Custom Gaseous Release Fraction D % C-14 production released as a gaseous effl uent; Enter 'D' to assume default values Custom Gaseous Release Rate D Ci Released; Enter 'D' to assume default values Custom Carbon Dioxide Fraction D % C-14 released as Carbon Dioxide; Enter 'D' to assume default values Normalized values listed in this section are taken from EPRI Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents", 2010, pages 4-28 and 3-26 Parameter WPWR CEPWR BWR Site Values Normalized Production - Ci/GWt-yr 3.4 3.9 5.1 11.17 Ci Produced Gaseous Release Fraction 98% 98% 99% 98% % Released Normalized Release - Ci/GWt-yr 3.33 3.82 5.05 10.94 Ci Released C-14 Carbon Dioxide Fraction 30% 30% 95% 30% %CO 2 Total Dioxide C-14 Release - Ci 1.09E+01 3.28E+00 MAXIMUM DOSE VALUES Organ Age mrem/yr RG-1.109 Bone Child 3.02E-01 RG-1.109 T.Body/Other Child 6.03E-02 ICRP-72 CEDE Teen 9.13E-02 ANO-1 & 2 Radioactive Effluent Release Report for 2012 Page 113 of 113 19. Additional Notes SPING 3 (Fuel Handling Area) was out-of-service for maintenance. Ventilation pathway was still

active; therefore, Chemistry is required to collect gas grab samples from this effluent pathway once

every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (reference ODCM L.2.2.1.C.1).

SPING 3 was sampled 8/2/2012 @ 0350. Primary turnover (1052.023A) stated the next SPING 3

gas sample was due 8/2/2012 @ 1450 (1/11 hrs); however, Chemistry failed to collect the 1450 sample.

When the Night Shift chemist reported to work, he questioned the Day Shift chemist about the

status of the 1450 sample. The Day Shift chemist realized a required sample was missed, and he

immediately grabbed a SPING 3 gas sample. Gamma specs indicated sample results of less than

minimum detectable radioactivity (MDA).

Per ODCM L.2.2.1.E:

If Required Action(s) and/or Completion Time(s) of Condition C [L.2.2.1.C.1] and/or Condition D

not met, then E.1 requires the following action:

Suspend the release of radioactive effluents monitored by the affected channel (completion time

of immediately)

In summary, the SPING 3 gas sample required by ODCM L.2.2.1.C.1 due at 1550 (1/12 hours) on

8/2/2012 was not collected until 1800.

SPING 3 ventilation was not secured because the required action (gas sample) was collected and

analyzed before this action could be taken.

ATTACHMENT 1 TO 0CAN041307 OFFSITE DOSE CALCULATION MANUAL

ARKANSAS NUCLEAR ONE OFFSITE DOSE CALCULATION MANUAL REVISION 20 Changes are indicated by beginning the affected information with a revision bar on the right side of the page which stops at the end of the change. Deletions of entire paragraphs or sections have a revision bar to the right of the page where text was deleted. The amendment number is indicated at the bottom of the affected page near the left margin and indicates the latest revision to the information contained on that page. Absence of a revision bar on a replacement page means the page was reprinted for word processing purposes only. However, general formatting

changes may have been made to all pages.

ARKANSAS NUCLEAR ONE ODCM Revision 20 2 TABLE OF CONTENTS

Section Title Page

1.0 INTRODUCTION

..............................................................................................................5

2.0 LIQUID EFFLUENTS.......................................................................................................5 2.1 Radioactive Liquid Effluent Monitor Setpoint........................................................5 2.2 Liquid Dose Calculation........................................................................................7 2.2.1 Dose Calculations for Aquatic Foods.....................................................7 2.2.2 Dose Calculations for Potable Water.....................................................9 2.3 Liquid Projected Dose Calculation.....................................................................10

3.0 GASEOUS EFFLUENTS................................................................................................10 3.1 Gaseous Monitor Setpoints................................................................................10 3.1.1 Batch Release Setpoint Calculations...................................................10 3.1.2 Eberline SPING (Final Effluent) Monitor Setpoint Calculations...........11 3.2 Airborne Release Dose Rate Effects..................................................................13 3.2.1 Noble Gas Release Rate.....................................................................13 3.2.2 I-131, Tritium and Particulate Release Dose Rate Effects..................15 3.3 Dose Due to Noble Gases..................................................................................15 3.3.1 Beta and Gamma Air Doses from Noble Gas Releases......................15 3.4 Dose Due to I-131, Tritium and Particulates in Gaseous Effluents....................16 3.4.1 Total Dose from Atmospherically Released Radionuclide...................17 3.5 Gaseous Effluent Projected Dose Calculation...................................................24 3.6 Dose to the Public Inside the Site Boundary......................................................24 3.6.1 Liquid Releases...................................................................................24 3.6.2 Airborne Release.................................................................................25

4.0 ENVIRONMENTAL SAMPLING STATIONS - RADIOLOGICAL...................................26

5.0 REPORTING REQUIREMENTS....................................................................................27 5.1 Annual Radiological Environmental Operating Report.......................................27 5.2 Radioactive Effluent Release Report.................................................................28 ARKANSAS NUCLEAR ONE ODCM Revision 20 3 TABLE OF CONTENTS (continued)

Figure Title Page FIGURE 4-1 Radiological Sample Stations (Far Field)....................................................30 FIGURE 4-1A Radiological Sample Stations (Near Field).................................................31 FIGURE 4-1B Radiological Sample Stations (Site Map)....................................................32 FIGURE 4-2 Maximum Area Boundary for Radioactive Release Calculation (Exclusion Areas)........................................................................................33

Table Title Page TABLE 4-1 Environmental Sampling Stations - Radiological........................................34

APPENDIX 1 RADIOLOGICAL EFFLUENT CONTROLS

Section Title Page 1.0 DEFINITIONS................................................................................................................

40 2.0 LIMITATION AND SURVEILLANCE APPLICABILITY...................................................43

2.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION........45 2.1.1 Radioactive Liquid Effluent Monitoring Instrumentation..........................45 2.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION...48 2.2.1 Radioactive Gaseous Effluent Monitoring Instrumentation.....................48 2.3 RADIOACTIVE LIQUID EFFLUENTS..................................................................53 2.3.1 Liquid Radioactive Material Release......................................................53 2.4 RADIOACTIVE GASEOUS EFFLUENTS............................................................57 2.4.1 Gaseous Radioactive Material Release..................................................57 2.5 RADIOLOGICAL ENVIRONMENTAL MONITORING..........................................62 2.5.1 Sample Locations...................................................................................62 2.5.2 Land Use Census...................................................................................70 2.5.2 Interlaboratory Comparison Program.....................................................72

ARKANSAS NUCLEAR ONE ODCM Revision 20 4 APPENDIX 1 RADIOLOGICAL EFFLUENT CONTROLS BASES Section Title Page B 2.0 LIMITATION AND SURVEILLANCE APPLICABILITY..................................................73

B 2.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION....76 B 2.1.1 Radioactive Liquid Effluent Monitoring Instrumentation.................76 B 2.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION..............................................................81 B 2.2.1 Radioactive Gaseous Effluent Monitoring Instrumentation............81 B 2.3 RADIOACTIVE LIQUID EFFLUENTS.............................................................87 B 2.3.1 Liquid Radioactive Material Release.............................................87 B 2.4 RADIOACTIVE GASEOUS EFFLUENTS........................................................93 B 2.4.1 Gaseous Radioactive Material Release.........................................93 B 2.5 RADIOLOGICAL ENVIRONMENTAL MONITORING.....................................98 B 2.5.1 Sample Locations..........................................................................98 B 2.5.2 Land Use Census........................................................................101 B 2.5.2 Interlaboratory Comparison Program...........................................103

ARKANSAS NUCLEAR ONE ODCM Revision 20 5

1.0 INTRODUCTION

The Offsite Dose Calculation Manual (ODCM) provides guidance for making release rate and dose calculations for radioactive liquid and gaseous effluents from Arkansas Nuclear One -

Units 1 and 2 (ANO-1 and ANO-2). The methodology is drawn from NUREG-0133, Rev. 0.

Parameters contained within this manual were taken from NUREG-0133 and Regulatory Guide (RG) 1.109 except as noted for site specific values. These numbers and the calculational

method may be changed as provided for in the Technical Specifications (TSs).

The following references are utilized in conjunction with the limitations included in this manual

concerning the indicated subjects:

Subject ANO-1 ANO-2 Process Control Program (PCP) EN RW-105 EN RW-105 Radioactive Effluent Controls Program TS 5.5.4 TS 6.5.4 Annual Radiological Environmental Monitoring Report TS 5.6.2 TS 6.6.2 Radioactive Effluent Release Report TS 5.6.3 TS 6.6.3 ODCM TS 5.5.1 TS 6.5.1

2.0 LIQUID EFFLUENTS

2.1 Radioactive Liquid Effluent Monitor Setpoint

ODCM Limitation L 2.1.1, "Radioactive Liquid Effluent Instrumentation," requires that the radioactive liquid effluents be monitored with the alarm/trip setpoints adjusted to ensure that the limits of the radioactive liquid effluent concentration limitations are not exceeded. These concentrations are for the site. The alarm/trip setpoint on the liquid effluent monitor is dependent upon the dilution water flow rate, radwaste tank flow rate, isotopic composition of the radioactive liquid to be discharged, a gross gamma count of the liquid to be discharged, background count rate of the monitor, and the efficiency of the monitor. Due to the fact that these are variables, an adjustable setpoint is used. The setpoint must be calculated and the monitor setpoint set prior to the release of each batch of radioactive liquid effluents. The

following methodology is used for the setpoint determination for the following monitors.

ANO-1: RE-4642 - Liquid Radwaste Monitor ANO-2: 2RE-2330 - Liquid Radwaste Monitor 2RE-4423 - Liquid Radwaste Monitor

1) A sample from each tank (batch) to be discharged is obtained and counted for gross gamma (Cs-137 equivalent) and a gamma isotopic analysis is performed.

2) A dilution factor (DF) for the tank is calculated based upon the results of the gamma isotopic analysis and the Maximum Permissible Concentration (MPC) of each detected

radionuclide.

ARKANSAS NUCLEAR ONE ODCM Revision 20 6 DF is calculated as follows:

DF = i (C i/MPC i) + C TNG/MPC TNG where: DF = dilution factor;

C i = concentration of isotope "i", (µCi/ml);

MPC i = maximum permissible concentration of isotope "i", (from 10 CFR 20, Appendix B, Table II, Column 2 in µCi/ml);

C TNG = total concentration of noble gases (µCi/ml); and MPC TNG = 2 x 10

-4 (µCi/ml) per Limitation L 2.3.1.a

3) The dilution water flowrate is normally the number of ANO-1 circulating water pumps in operation at the time of release. Each circulating water pump has an approximate flowrate of 191,500 gallons per minute (gpm) (this flowrate may be reduced due to throttling of circulating water pump flow and/or circulating water bay configuration).

However, under specific conditions and under strict controls, lower dilution water

flowrates utilizing service water and cooling tower blowdown flowrates may be used.

4) The theoretical release rate, F m, of the tank (batch) to be released is expressed in terms of the dilution water flowrate, such that for each volume of dilution water released, a

given volume of liquid radwaste may be combined. This may be expressed as follows:

F m = DV/DF where: F m = theoretical release rate (gpm); DV = Dilution volume (gpm). When ANO-1 circulating water pumps are running, DV is the number of ANO-1 circulating water pumps in operation multiplied by the approximate flowrate of an ANO-1 circulating water pump (normally 191,500 gpm) or an indicated flow rate. The minimum total flow rate shall be greater than or equal to 100,000 gpm. Otherwise DV is dilution volume

provided by service water and cooling tower blowdown flowrate; and DF = dilution factor as calculated in Step 2 above.

Note: In the above equation, the theoretical release rate (F m) approaches zero as the dilution factor increases. The actual flowrate (F A) will normally be equal to the theoretical release rate for high activity releases. For low activity releases, the theoretical release rate becomes large and may exceed the capacity of the pump discharging the tank. In these cases, the actual release rate may be set

to the maximum flowrate of the discharge pump.

5) The monitor setpoint is calculated by incorporating the monitor reading prior to starting the release (i.e., background countrate), and a factor which is the amount of increase in the release concentration that would be needed to exceed the radioactive liquid

concentration limitation. The monitor setpoint is expressed as follows:

ARKANSAS NUCLEAR ONE ODCM Revision 20 7 M L = A*(K*F M/F A) + B where: M L = monitor setpoint (counts per minute or "cpm"); A = allocation fraction for the specific unit. (Typically, these values are set at 0.45, but may be adjusted up or down as needed. However, the total site

allocation can not exceed 1.0.) K = monitor countrate (cpm) expected based on the gross activity of the release (this value is obtained from a graph of activity (µCi/ml) versus output

countrate for the monitor (cpm));

F M/F A = number of times the activity would have to increase to exceed the radioactive liquid effluent-concentration limitation; and B = background countrate (cpm) prior to the release.

To permit the computer to calculate the setpoint, an equation for the expected countrate (K) is expressed as follows:

K = Offset

S A Slope where: Log of the detector response in cpm Slope = Log of activity concentration in Ci/ml S A = Gross gamma (Cs-137 equivalent) activity for the tank ( Ci/ml); and Offset = detector response (cpm) for the minimum detectable sample activity calculated from the calibration data.

Note: I&C personnel use varying concentrations of Cs-137 to determine the response curve; therefore, a Cs-137 equivalent activity must

be used to accurately predict the countrate.

Combining terms, the equation for determining the monitor setpoint may be expressed

as follows:

M L = A[(Offset

S A Slope)F M/F A] + B 2.2 Liquid Dose Calculation

The "dose" or "dose commitment" to an individual in the unrestricted area shall be less than or equal to the limits specified in 'Radioactive Liquid Effluents - Dose' Limitations. The dose limits are on a per reactor basis. This value is calculated using the adult as the maximum exposed

individual via the aquatic foods (Sport Freshwater Fish) and the potable water pathways.

2.2.1 Dose Calculations for Aquatic Foods

The concentrations of radionuclides in aquatic foods are assumed to be directly related to the concentrations in water. The equilibrium ratios between the two concentrations are called

"bioaccumulation factors."

ARKANSAS NUCLEAR ONE ODCM Revision 20 8 Two different pathways are calculated for aquatic foods: sport and commercial freshwater fish.

The internal dose "d" from the consumption of aquatic foods in pathway "p" to organ "j" of individuals of age group "a" from all nuclides "i" is computed as follows (see Chapter 4 of

NUREG-0133 and RG 1.109-12, equation A-3):

d p (r, ,a,j) = i[{(1100)(e

- i t p)(B i)}(M)(U a)(F)-1 (Q i)(D aij)] The total dose from both aquatic food pathways is then:

D(r, ,a,j) = d p (r, ,a,j) P where: r = user-selected distance from the release point to the receptor location, in kilometers. It may be different from the controlling distance specified for the potable water

pathway (0.4 km); = user-selected sector (one of sixteen 22.5° sectors surrounding the reactor site, designated N, NNE, NE, etc.). This sector may be different from the controlling

sector specified for the potable water pathway (S); A = user-selected age group: infant, child, teen, adult. It is the same controlling age group used in the potable water pathway (adult); J = user-selected organ: bone, liver, total body, thyroid, kidney, lung, GI-LLI. It is the same controlling organ used in the potable water pathway (liver); { } = represents the concentration factor stored in the database; Note: Only one concentration factor is needed to represent the two pathways since sport and commercial use the same bioaccumulation factor for a

given pathway.

1100 = factor to convert from (Ci/yr)/(ft 3/sec) to Ci/liter; i = decay constant of nuclide "i" in hr

-1; t p = environmental transit time, release to receptor; Note: This value should be set to 0 hours0 days 0 hours 0 weeks 0 months (i.e., no decay correction) for the above equation in order to be consistent with the equation presented in Chapter 4 of NUREG-0133. For maximum individual dose calculations, this value is set to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , which is the minimum transit time recommended by

RG 1.109, Appendix A, 2.b.

B i = bioaccumulation factor for nuclide "i", in Ci/kg per Ci/liter. Cesium has a site specific number based on carnivorous and bottom feeder sport fish of 400 Ci/kg per Ci/liter (0CAN048408, dated April 13, 1984); Niobium has a site specific number based upon freshwater fish of 300 Ci/kg per Ci/liter. M = dimensionless mixing ratio (reciprocal of the dilution factor) at the point of exposure; ARKANSAS NUCLEAR ONE ODCM Revision 20 9 U a = annual usage factor that specifies the intake rate for an individual of age group "a", in kilograms/year. The program selects this usage factor in accordance with the

controlling age group "a" as specified previously by the user; F = average flow rate in ft 3/sec. This value is based on total dilution volume for the quarter divided by time into the quarter; Q i = number of curies of nuclide "i" released; and D aij = ingestion dose factor for age group "a", nuclide "i", and organ "j", in mrem per Ci ingested. The program selects the ingestion dose factor according to the user-

specified controlling age group "a" and controlling organ "j".

2.2.2 Dose Calculations for Potable Water

The dose "D" from ingestion of water to organ "j" of individuals of age group "a" due to all nuclides "i" is calculated as follows (See Chapter 4 of NUREG-0133 and NRC RG 1.109-12, equation A-2):

Note: The potable water pathway is used only during the time that the Russellville Water System is using the Arkansas River as a water source. The Russellville Water Works

will notify ANO when they are using the Arkansas River as a water source.

D (r, ,a,j) = i [{(1100)(e

- i t p)}(M)(U a)(F-1)(Q i)(D aij)] where: r = user-selected distance (0.4 km) from the release point to the receptor location, in kilometers. It may be different from the controlling distance selected for the aquatic

food pathway; = user-selected sector; (one of the sixteen 22.5° sectors surrounding the reactor site, designated N, NNE, NE, etc.). It may be different from the controlling sector for the

aquatic food pathway; a = user-selected age group (infant, child, teen, adult). The same controlling age group is used for all liquid pathways (adult); j = user-selected organ (bone, liver, total body, thyroid, kidney, lung, GI-LLI). The same controlling organ is used for all liquid pathways (liver). { } = the expression in brackets represents the concentration factor stored in the database; 1100 = factor to convert from (Ci/yr)/(ft 3/sec) to Ci/liter; M = dimensionless mixing ratio (reciprocal of the dilution factor) at the point of exposure; i = decay constant of nuclide "i" in hr

-1; and t p = environmental transit time, release to receptor.

Note: This value is set to 0 hours0 days 0 hours 0 weeks 0 months (i.e., no decay correction) for the above equation to be consistent with the equation presented in Chapter 4 of

NUREG-0133.

ARKANSAS NUCLEAR ONE ODCM Revision 20 10 U a = annual usage factor that specifies the intake rate for an individual of age group "a", in liters/year. The program selects this usage factor according to the user-specified

controlling age group "a"; F = average flow rate in ft 3/sec; this value is based on total dilution volume for one quarter divided by time into the quarter; Q i = number of curies of nuclide "i" in the release; and D aij = ingestion dose factor, for age group "a", nuclide "i", and organ "j", in mrem per Ci ingested. The program selects the ingestion dose factor according to the user-

specified controlling age group "a" and controlling organ "j".

2.3 Liquid Projected Dose Calculation

The quarterly projected dose is based upon the methodology of Section 2.2 and is expressed as

follows:

D QP = 92(D QC + D RP)/T where: D QP = quarterly projected dose (mrem); 92 = number of days per quarter;

D QC = cumulative dose for the quarter (mrem);

D RP = dose for current release (mrem); and T = current days into quarter;

3.0 GASEOUS EFFLUENTS

3.1 Gaseous Monitor Setpoints

Note: Sections 3.1.1 and 3.1.2 below detail two methods of calculating setpoints at ANO. These methods cover two different sets of monitors of which only one will be in-service

at any one time.

3.1.1 Batch Release Setpoint Calculations 3.1.1.a This section applies to the following gaseous radiation monitors (these releases are also monitored by the SPING monitors in Section 3.1.2):

ANO-1: RE-4830 - Waste Gas Holdup System Monitor* RX-9820 - Reactor Building Purge and Ventilation SPING ANO-2: 2RE-8233 - Containment Building Purge Monitor*

2RE-2429 - Waste Gas Holdup System Monitor* 2RX-9820 - Containment Building Purge and Ventilation SPING

These monitors provide automatic isolation.

ARKANSAS NUCLEAR ONE ODCM Revision 20 11 The setpoints to be used during a batch type of release (i.e., Reactor Building [Containment] Purge, release from the Waste Gas Holdup System or any other non-routine release) will be calculated for each release before it occurs.

3.1.1.b The basic methodology for determining a monitor setpoint is based upon the expected concentration at the monitor (C M). This is in turn based upon the fraction of an MPC assigned to this release point. Batch releases are maintained below the assigned MPC fraction by controlling the release rate. The calculated value of S may not exceed the equivalent of 1 MPC at site boundary. If value of S for RX (2RX) -9820 is less than SPING Channel 5 high alarm setpoint, then the high alarm setpoint may be used as a default value. If the value of S for RE-4830 and 2RE-2429 is less than 50,000 cpm, then 50,000 cpm may be used as a minimum setpoint. If the value of S for 2RE-8233 is less than 1,000 cpm, then 1,000 cpm may

be used as a minimum setpoint.

S = 1.2(C M)(K) + (2.0)(B) where: S = monitor setpoint (cpm);

C M = Xe-133 equivalent concentration at the monitor ( Ci/ml); K = conversion factor determined from response curve of monitor (cpm per Ci/ml). This value is 1.0 when calculating S for RX (2RX) -9820. 2.0 = factor to accommodate random count rate fluctuations; B = background count rate at the monitor (cpm).

1.2 = Safety Factor to correct for instrument uncertainties.

3.1.2 Eberline SPING (Final Effluent) Monitor Setpoint Calculations

3.1.2.a This section applies to the following gaseous radiation monitors:

ANO-1: RX-9820 - Reactor Building Purge and Ventilation SPING RX-9825 - Auxiliary Building Ventilation SPING RX-9830 - Spent Fuel Pool Area Ventilation SPING RX-9835 - Emergency Penetration Room Ventilation SPING ANO-2: 2RX-9820 - Containment Building Purge and Ventilation SPING 2RX-9825 - Auxiliary Building Ventilation SPING 2RX-9830 - Spent Fuel Pool Area Ventilation SPING 2RX-9835 - Emergency Penetration Room Ventilation SPING 2RX-9845 - Auxiliary Building Extension Ventilation SPING 2RX-9850 - Radwaste Storage Building Ventilation SPING

The determination of setpoints for the above monitors is based on an assigned fraction of the MPC of noble gas activity at the site boundary (Xe-133 equivalent) released from the above release points. The total of these fractions is always less than 1.00. The assigned fractions are based on the vent flow rates, atmospheric

dilution rate, and the ventilation system(s) in operation.

ARKANSAS NUCLEAR ONE ODCM Revision 20 12 Note: The fact that an effluent monitor is in alarm does not necessarily mean that radioactive gases are being released at such a rate that the MPC limit is being exceeded. The alarm would indicate that radioactive gases are being released at a rate that is exceeding the fractional allocation of an MPC allotted to that particular release point. Consideration must be given to the

release rate of radioactive gases via all of the release pathways.

The initial fractions of an MPC allocated to the release points are given below. The allocations may be changed as needed, to allow for operational transients, but may

not exceed a site total of 1.00.

Monitor Number Monitor Name Fractional Allocation RX-9820 Reactor Building Purge and Ventilation 0.1000 RX-9825 Auxiliary Building Ventilation 0.2000 RX-9830 Spent Fuel Pool Area Ventilation 0.1500 RX-9835 Emergency Penetration Room Ventilation 0.0001 Monitor Number Monitor Name Fractional Allocation 2RX-9820 Containment Building Purge and Ventilation 0.1000 2RX-9825 Auxiliary Building Ventilation 0.2000 2RX-9830 Spent Fuel Pool Area Ventilation 0.1500 2RX-9835 Emergency Penetration Room Ventilation 0.0001 2RX-9840 PASS Building Ventilation 0.0100 2RX-9845 Auxiliary Building Extension Ventilation 0.0100 2RX-9850 Radwaste Storage Building Ventilation 0.0100 Note: The setpoints to be used during a batch release (i.e., Reactor Building [Containment] Purge or Waste Gas Holdup System) will be calculated for

each release before it occurs.

3.1.2.b SPING monitor setpoints may be calculated as follows:

Xe-133 eq (µCi/cc)

Setpoint ( Ci/cc) = A F(1.3215E-9)(TMPC) where: A = allocation fraction (the fraction of an MPC at the site boundary (of noble gas Xe-133 eq activity) assigned to the particular release

point); Xe-133 eq = Xenon-133 equivalent concentration; F = discharge flow of the particular release point in cubic feet per minute (cfm) 2.8E-6(sec/m

3) 1.3215E-9 = 2.8317E-2(cm/cf) 60(sec/min)

ARKANSAS NUCLEAR ONE ODCM Revision 20 13 where: 2.8E-6 = the annual average gaseous dispersion factor (corrected for radioactive decay) as defined in Section 2.3 of the ANO-2 Safety

Analysis Report (SAR); and TMPC = total MPCs at site boundary.

3.2 Airborne Release Dose Rate Effects 3.2.1 Noble Gas Release Rate 3.2.1.a To calculate the noble gas release dose rate, the average ground-level concentration of radionuclide "i" at the receptor location must first be determined from the following

equation (see RG 1.109-20 equation B-4).

x i () = (3.17 x 10 4)(Q i)[D1X/Q()] where: x i () = average ground level concentration in Ci/m 3 of nuclide "i" at the user-specified controlling distance in sector (1.05 km);

() = one of the sixteen 22.5° sectors surrounding the reactor site, designated N, NNE, NE, etc. (WNW);

3.17 x 10 4 = number of Ci per Ci divided by the number of seconds/year; Q i = release rate of nuclide "i" in curies/yr and D1X/Q() = annual average gaseous dispersion factor (corrected for radioactive decay) in the sector at angle "" at the receptor location in sec/m 3. This value is 2.8E-6 sec/m 3 for short term releases.

The annual dose to the total body and skin due to noble gas can be calculated

according to Sections 3.1.2.b and 3.2.1.c.

3.2.1.b Annual Total Body Dose Rate The annual average total body dose rate to the maximally exposed individual is

calculated as follows:

D T () = (RBPF)(S F)( i [x i ()

DFB i] where: D T () = total body dose rate due to immersion in a semi-infinite cloud of gas at the controlling distance in sector "", in mrem/yr. The program computes one total body dose rate value for each sector in which the user has specified a controlling distance and reports only the maximum

value; = one of sixteen 22.5° sectors surrounding the reactor site, designated N, NNE, NE, etc. (WNW);

ARKANSAS NUCLEAR ONE ODCM Revision 20 14 RBPF = Reactor Building (Containment) Purge Factor - This factor is used to calculate the length of time (fractional duty cycle) that the purge fans will be in operation. It is calculated by comparing the highest dose rate (DOSER) to its applicable release limit, taking into account the allocation factor for the release point (RBPF = Allocation

Limit/DOSER). This factor is calculated only for ANO-1 and ANO-2 Reactor Building (Containment) purges. For all other releases, this

factor is set to 1.0; S F = dimensionless attenuation factor accounting for the dose reduction due to shielding by residential structures. The NRC recommended value is

0.7 (for maximum individual) x i () = average ground-level concentration of nuclide "i" at the receptor location in the sector at angle "" from the release point, as defined in Section 3.2.1.a; and DFB i = total body dose factor for a semi-infinite cloud of radionuclide "i", which includes the attenuation of 5 g/cm² of tissue, in mrem-m 3/ Ci-yr 3.2.1.c Annual Skin Dose Rate The annual dose rate to the skin of the maximally exposed individual due to noble gases is calculated as follows (see RG 1.109-20 equation B-9):

D S () = RBPF[(1.11)(S F)( i (x i ())(DF i) + i (x i ())(DFS i)] where: D S () = skin dose due to immersion in a semi-infinite cloud of gas at the user-specified controlling distance in sector "", in mrem; Note: The program computes a skin dose value for each sector in which the user as specified a controlling distance, but prints

out only the maximum value.

RBPF = Reactor Building [Containment] Purge Factor as defined in Section 3.2.1.b. 1.11 = average ratio of tissue to air energy absorption coefficient;

S F = dimensionless attenuation factor accounting for the dose reduction due to shielding by residential structures. The value is 0.7 (for maximum

individual);

x i () = is the average ground-level concentration of nuclide "i" at the receptor location in the sector at angle "" from the release point, as defined in Section 3.2.1; = one of sixteen 22.5° sectors surrounding the reactor site, designated N, NNE, NE, etc. (WNW);

DF = gamma air dose factor for a semi-infinite cloud of radionuclide "i", in mrad-m 3/ Ci-yr; and DFS i = beta skin dose factor for a semi-infinite cloud of radionuclide "i", which includes the attenuation by the outer "dead" layer of skin, in mrem-m 3/ Ci-yr.

ARKANSAS NUCLEAR ONE ODCM Revision 20 15 3.2.2 I-131, Tritium and Particulate Release Dose Rate Effects The annual dose rate to the maximally exposed individual for I-131, tritium and radionuclides in

particulate form with half-lives greater than eight days is calculated as follows:

DR TOT = (RBPF)(DR I + DR G + DR M) where: RBPF = Reactor Building (Containment) Purge Factor as defined in Section 3.2.1.b;

DR I = dose rate to the controlling age group (infant) associated with the inhalation of radioiodines and particulates, as calculated in Section 3.4.1.b; DR G = dose rate from direct exposure to activity deposited on the ground plane, as calculated in Section 3.4.1.a; and DR M = dose rate to the controlling age group (infant) and the controlling organ for ingestion of food (milk), as calculated in Section 3.4.1.d.

Calculation of the annual dose rate considers the infant as the most restrictive age group. The

organs that are considered as contributing to the dose rate are: skin, bone, liver, total body, thyroid, kidney, lung, and GI-LLI. The food pathway for the infant is considered to be from milk

only. All three pathways will contribute to the total body dose, while the skin will be affected by only the ground plane pathway. The other organs are affected only by the inhalation and food

pathways.

3.3 Dose Due to Noble Gases

The air dose in unrestricted areas due to noble gases released in gaseous effluents shall be less than or equal to 5 mrad for gamma radiation and 10 mrad for beta radiation for any calendar quarter for each unit. The objective of less than or equal to 10 mrad of gamma radiation and 20 mrad of beta radiation for a calendar year per unit (2.5 mrad and 5 mrad

respectively per quarter) should be used for planning releases.

Note: The following equations have been simplified from equations in NUREG-0133, Revision 0, in that there are no free-standing stacks at ANO. The equations were further

simplified in that there are no long term (i.e., continuous) releases. The individual stack

vents are sampled weekly, or are assigned a release period of 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months per sample (i.e., considered as short term (batch) releases). Individual samples are to be taken for

each waste gas release and Reactor (Containment) Building purge.

3.3.1 Beta and Gamma Air Doses from Noble Gas Releases Using the average ground level concentration of radionuclide "i" at the receptor location calculated in Section 3.2.1.a, the associated annual gamma or beta air dose may be calculated

by the following equation (see RG 1.109-20 equation B-5).

D () or D() = i [(x i ())(DF i or DF i)] where: D () or D() = the gamma or beta air dose for the controlling distance in sector "" (only the maximum value is reported), and DF i or DF i = gamma or beta air dose factors for a uniform semi-annual infinite cloud of nuclide "i", in mrad-m 3/ Ci-yr.

ARKANSAS NUCLEAR ONE ODCM Revision 20 16 3.4 Dose Due to I-131, Tritium, and Particulates in Gaseous Effluents

The calculational methodology for determining the dose to an individual from I-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents

released to unrestricted areas as specified in the Limitations is in this section.

The child is the controlling age group unless stated otherwise.

The inhalation and ground plane pathways are considered to exist at all locations. The grass-

cow-milk, grass-cow-meat, and vegetati on pathways are used where applicable.

It is assumed that iodines are in the elemental form.

A dispersion parameter of 2.8E-6 sec/m 3 (per ANO-2 SAR, Section 2.3.4.4) is used for "w" in the inhalation pathway since the majority of gaseous activity released from the site is within the 8 to

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months time frame (i.e., Reactor Building [Containment] purges and Waste Gas Decay tanks).

The equation is:

D TOT = D G + D I + D V + D L + D M + D F where: D TOT = total dose; D G = dose contribution from ground plane deposition as calculated in Section 3.4.1.a; D I = dose contribution from inhalation of radioiodines, tritium, and particulates (> 8 days) as calculated in Section 3.4.1.b; D V = dose contributions from consumption of vegetation (defined as produce) for humans and stored feed for cattle. See Section 3.4.1.c for calculations; D L dose contributions from consumption of fresh leafy vegetables (defined as garden products) for humans and pasture grass for cattle. See Section 3.4.1.c for

calculations; D M = dose contribution from consumption of cow's milk; and Note: Consumption by the cow of both stored feeds and pasture grasses is taken into account when calculating this dose contribution. Concentration factors

for both food sources are calculated.

D F = dose contribution from consumption of meat.

Note: Consumption by the cow of both stored feeds and pasture grasses is taken into account when calculating this dose contribution. Concentration factors

for both types of animal are calculated.

ARKANSAS NUCLEAR ONE ODCM Revision 20 17 3.4.1 Total Dose from Atmospherically Released Radionuclide After the calculation of the concentration factors from the applicable parts of Section 3.4.1, the maximum individual dose as calculated for controlling age group "a" and controlling organ "j", in sector at the controlling distance "r" is given from:

D G (r,,j,a) (Section 3.4.1.a) for ground plane deposition D I (r,,j,a) (Section 3.4.1.b) for inhalation D V (r, ,j,a) = DFI ija U a C i (r,) for produce i D L (r, ,j,a) = DFI ija U a C i (r,) for leafy vegetables i D M (r, ,j,a) = DFI ija U a C i (r,) for cow's milk i D F (r, ,j,a) = DFI ija U a C i (r,) for meat i

where: a = controlling age group (infant, child, teen, or adult); j = controlling organ (bone, liver, total body, thyroid, kidney, lung, or GI-LLI);

r = user-selected distance from the release point to the receptor location in a particular sector, in kilometers (the controlling distance is the same for all

airborne pathways, 1.05 km); = one of sixteen 22.5° sectors surrounding the reactor site, designated N, NNE, NE, etc. (WNW);

DFI ija = dose conversion factor for ingestion of nuclide "i", organ "j", and age group "a", in mrem/ Ci; Note: Values used in these tables are taken from Tables E-11 through E-14 of RG 1.109. DFI ija is selected according to the controlling organ and age group as specified in the database.

U a , U a , U a , U a = ingestion rates for produce, leafy vegetables, cow's milk, and meat, respectively, for individuals in age group "a". Values used are taken from

Table E-5 of RG 1.109.);

C i , D i , C i , D i = concentration of nuclide "i" for produce, leafy vegetables, cow's milk, and meat, respectively, in Ci/kg or Ci/liter.

The program calculates that maximum individual dose for each sector surrounding the plant in which the user has specified a controlling distance for each of the following pathways: A) ground plane deposition; B) inhalation and the ingestion of; C) produce; D) leafy vegetables; E) cow's milk; and F) meat. Only the receptor point receiving the

maximum dose value is printed.

V V L L M M F F V L M F V L M F ARKANSAS NUCLEAR ONE ODCM Revision 20 18 3.4.1.a Dose from Ground Plane Deposition The dose D G from direct exposure to activity deposited on the ground plane is calculated as follows (see RG 1.109-24, equations C-1 and C-2):

D G (R, ,j,a) = {(S F)(1.0 x 10 12)(i[( i-1)(1 - e i b)]}(DOQ(r,))(Q i)(DFG ij) where: r = user-selected distance from the release point to the receptor location in a particular sector, in kilometers. The controlling distance is the same for all

airborne pathways (1.05 km); = one of sixteen 22.5° sectors surrounding the reactor site, designated N, NNE, NE, etc. (WNW); a = user-selected age group (infant, child, teen, adult) which is the same controlling age group used for all airborne pathways (child); j = user-selected organ (bone, liver, total body, thyroid, kidney, lung, GI-LLI) which is the same controlling organ used for all airborne pathways; { } = represents the concentration factor stored in the database;

S F = dimensionless attenuation factor accounting for the dose reduction due to shielding by residential structures. The value is 0.7 (for maximum individual);

1.0 x 10 12 = number of Ci per Ci; i = decay constant of nuclide "i" in hr

-1; t b = length of time over which the accumulation is evaluated (nominally 15 years which is the approximate midpoint of facility operating life or 1.31 x 10 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ); DOQ(r,) = average relative deposition of the effluent at the receptor location "r" in sector

"", considering depletion of the plume during transport, in m 2; Qi = release of nuclide "i" in curies, and

DFG ij = open field ground plane dose conversion factor for organ "j" (total body or skin) from radionuclide "i", in mrem-m 2/Ci-hr. The dose factor is selected according to the user-specified controlling age group "a" and controlling organ "j".

3.4.1.b Dose from Inhalation of Radionuclides in Air The dose DI to organ "j" of age group "a" associated via inhalation of radioiodines and

particulates is (see RG 1.109-25, Equations C-3 and C-4):

D I (r, ,j,a) = (3.17 x 10 4)(R a)(i[(Q i)(D2DPX/Q(r,))(DFA ija)]

where: r = user-selected distance from the release point to the receptor location in a particular sector, in kilometers. The controlling distance is the same for all

airborne pathways (1.05 km); = one of sixteen 22.5° sectors surrounding the reactor site, designated N, NNE, NE, etc. (WNW);

- t ARKANSAS NUCLEAR ONE ODCM Revision 20 19 j = user-selected organ (bone, liver, total body, thyroid, kidney, lung, GI-LLI) and is the same controlling organ as that used for all airborne pathways; a = user-selected age group (infant, child, teen, adult) and is the same controlling age group as that used for all airborne pathways; 3.17 x 10 4 = number of Ci/Ci divided by the number of seconds/year; R a = annual air intake for individuals in age group "a" (in m 3/year). The air intake factor is selected in accordance with the user-specified controlling

age group; Q i = release of nuclide "i" in curies; D2DPX/Q(r,) = annual average atmospheric dispersion factor of the radionuclide at the receptor location "r" in sector "" (in sec/m

3) as calculated; and Note: This includes depletion (for radioiodines and particulates) and radioactive decay of the plume.

DFA ija = inhalation dose factor for radionuclide "i", organ "j", and age group "a". The inhalation dose factor is selected in accordance with the user-

specified controlling age group "a" and controlling organ "j".

3.4.1.c Dose from Nuclide Concentrations in Vegetation Note: To reduce the computational overhead of the computer, the calculations for dose resulting from nuclide concentrations in forage, produce and leafy vegetables is

performed in three steps.

First, the concentration factors (CF) are computed and stored in the database. The concentration factor includes all the parameters that are considered constant for each nuclide and agricultural activity, such as the radioactive decay constant, removal rate constant, exposure time, etc.

Second, the deposition rate from the plume is multiplied by the concentration factor and the

nuclide activity to produce the nuclide concentration as follows:

C i (r,) = (CF i)(DOQ(r,))(Q i) where: C i (r,) = concentration of nuclide "i" at the receptor location (r,); CF i = concentration factor of nuclide "i";

DOQ(r,) = relative deposition of nuclide "i". For the short term dispersion option, DOQ is replaced by (F x DOQ), where F is the short term dispersion correction factor; Q i = quantity of nuclide "i" released in curies.

For carbon-14 and tritium, the nuclide concentration is calculated from the concentration factor times the decayed and depleted X/Q for radioiodines and particulates (D2DPX/Q), times the quantity of nuclide "i" released in curies. For the short term dispersion option, D2DPX/Q is replaced by F x D2DPX/Q, where F is the short term dispersion correction factor.

V V ARKANSAS NUCLEAR ONE ODCM Revision 20 20 C T (r,) = (CF T)(D2DPX/Q(r,))(Q T) for tritium, and CF V 14 (r,) = (CF 14)(D2DPX/Q(r,))(Q 14) for carbon-14 Third, the nuclide concentrations for a particular pathway (produce, leafy vegetables, cow's milk, and meat) are summed and multiplied by: 1) the ingestion rate for a particular age group and

2) the dose conversion factor:

D(r, ,j,a) = i [(DFI ija)(U a)(C i (r,))] where: r = user-selected distance from the release point to the receptor location in a particular sector, in kilometers (1.05 km); = one of sixteen 22.5° sectors surrounding the reactor site, designated N, NNE, NE, etc. (WNW); j = user-selected organ (bone, liver, total body, thyroid, kidney, lung, GI-LLI), and is the same controlling organ as that used for all airborne pathways; a = user-selected age group (infant, child, teen, adult), and is the same controlling age group as that used for all airborne pathways; DFI ija = dose conversion factor for ingestion of nuclide "i", organ "j", and age group "a", in mrem/ Ci, according to the controlling organ and age group; Ua = annual ingestion rate of food in a particular pathway (kilograms/year or liters/year) for individuals in age group "a", according to the controlling age group; and C i (r,) = concentration of nuclide "i" at the receptor location (r,). 3.4.1.c.1 Calculating Vegetation Concentration Factors NUREG-0133 calculations for radioiodines and particulate radionuclides (except tritium and carbon-14), the concentration factor of nuclide "i" in and on vegetation is estimated as follows:

r CF i = (CONST)((Y v)( i))(e i h)(f) where: CF i = concentration factor of radionuclide "i" in vegetation (forage, produce, or leafy vegetables), in m 2-hr/kg; CONST = 1.14 x 10 8 number of Ci per Ci (10

12) divided by the number of hours per year (8760); r = is the fraction of deposited activity retained on crops, leafy vegetables, or pasture grass, from airborne radioiodine and particulate deposition: r = 1.00 for radioiodines r = 0.20 for particulates Y v = agricultural productivity (yield or vegetation area density), in kg (wet weight)/m 2: Y s = 2.0 kg/m 2 for stored animal feed for grass-animal-man pathways Y = 0.7 kg/m 2 for pasture grass for grass-animal-man pathways V V V V- t V ARKANSAS NUCLEAR ONE ODCM Revision 20 21 Y 1 = 2.0 kg/m 2 for leafy vegetation (fresh) for crop/vegetation-man pathways Y g = 2.0 kg/m 2 for garden produce (stored vegetables) for crop/vegetation-man pathways i = is the decay constant of nuclide "i" in hr

-1; t h = is a holdup time that represents the time interval between harvest and consumption of the food, in hours:

t h = 0 hours0 days 0 hours 0 weeks 0 months for pasture grass consumed by animals t h = 2160 hours0.025 days 0.6 hours 0.00357 weeks 8.2188e-4 months for stored feed consumed by animals t h = 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for leafy vegetables consumed by humans t h = 1440 hours0.0167 days 0.4 hours 0.00238 weeks 5.4792e-4 months for produce consumed by humans f = is the fraction of leafy vegetables or produce grown in garden of interest: f = 0.76 for the fraction of produce ingested, grown in garden of interest (this is f g in equation C-13 of RG 1.109) f = 1.00 for the fraction of leafy vegetables grown in garden of interest (this is f 1 in equation C-13 of RG 1.109) f = 1.00 for all other pathways 3.4.1.c.2 Concentration Factor for Carbon-14 For carbon-14, the concentration factor in and on vegetation is estimated as follows (see RG 1.109-26, equation C-8):

CF V 14 = (2.2 x 10 7)() where: CF V 14 = concentration factor of carbon-14 in and on vegetation, in m 2-hr/kg; and = is defined as the ratio of total annual release time (for C-14 atmospheric releases) to the total annual time during which photosynthesis occurs (taken to be 4400 hours0.0509 days 1.222 hours 0.00728 weeks 0.00167 months ), under the condition that the value of "" should never exceed unity. For continuous C-14 releases, "" is taken to be unity (thus, the value of 2.2 x 10 7 is stored for CF V 14 in lieu of a site specific value for ""). 3.4.1.c.3 Concentration Factor for Tritium The concentration factor for tritium in vegetation is calculated from the tritium concentration in air surrounding the vegetation (see RG 1.109-27, equation C-9):

V 1.2 x 10 7 C F T =H where: CF T = concentration factor for tritium in vegetation (in m 2-hr/kg); and H = absolute humidity at the location of the vegetation, in g/m 3 (the regulatory default value for "H" is 8.0 grams/m 3). Thus, the value 1.5 x 10 6 is stored for CF T in lieu of a site specific value for "H".

V V ARKANSAS NUCLEAR ONE ODCM Revision 20 22 3.4.1.c.4 Nuclide Concentrations in Produce and Leafy Vegetables The concentrations in and on produce and leafy vegetables of all radioiodine and particulate

nulcides "i" (except carbon-14 and tritium) are calculated as follows:

C i (r,) = (CF i)(DOQ(r,))(Q i) for produce; and C i (r,) = (CF i)(DOQ(r,))(Q i) for leafy vegetables

where: CF i = concentration factor of nuclide "i" in produce; CF i = concentration factor of nuclide "i" in leafy vegetables; Note that the difference between CF i and CF i are the values for t h and f 1. DOQ(r,) = relative deposition of the radionuclide "i" at the receptor (r,); and Q i = release of nuclide "i" (in curies).

The C-14 and H-3 nuclide concentrations are calculated from the concentration factors times the decayed and depleted radioiodine relative deposition D2DPX/Q times the fraction grown in

the garden of interest (f g = 0.76, f 1 = 1.0):

C T (r,) = (CF T)(D2DPX/Q(r,))(Q T)(f g) C T (r,) = (CF T)(D2DPX/Q(r,))(Q T)(f 1) for tritium C 14 (r,) = (CF 14)(D2DPX/Q(r,))(Q 14)(f g) C 14 (r,) = (CF 14)(D2DPX/Q(r,))(Q 14)(f 1) for carbon-14 3.4.1.d Nuclide Concentration in Cow's Milk The radionuclide concentration in cow's milk is dependent upon the quantity and contamination level of feed consumed by the animal. The concentration is estimated (see RG 1.109-27, equations C-10 and C-11) as follows:

C i (r,) = {(F m)(Q F)(e i f)[(f p)(f s)(CF i) + (1 - f p)(CF i) + (f p)(1 - f s)(CF i)]}(D(r,)(Q i) where: C i (r,) = is the concentration of nuclide "i" in cow's milk at the receptor location (r,), in Ci/liter; { } = the expression in brackets represents the concentration factor (note that the concentration factor for cow's milk involves two different vegetation concentration

factors (see below));

F m = average fraction of the cow's daily intake of radionuclide "i" (which appears in each liter of milk), in days/liter; Q F = amount of feed consumed by the cow per day, in kg/day (wet weight);

V V L L V V L L V V L L V V L L - t m v v v 1 1 m ARKANSAS NUCLEAR ONE ODCM Revision 20 23 i = decay constant of nuclide "i" in hr

-1; t f = average transport time of the activity from the feed into the milk and to the receptor (a value of 2 days is assumed); fp = fraction of the year that cows graze on pasture; fs = fraction of daily feed that is pasture grass when the cow grazes on pasture;

CF i = vegetation concentration factor of nuclide "i" on pasture grass with the holdup time t h = 0 days, in Ci/kg (refer to the explanation of the vegetation concentration factor calculation);

CF i = vegetation concentration factor of nuclide "i" in stored feeds with the holdup time t h = 90 days, in Ci/kg (refer to the explanation of the vegetation concentration factor calculations);

D(r,) = relative deposition DOQ(r,) of the radionuclides, except carbon-14 and tritium. For carbon-14 and tritium, the decayed and depleted dispersion factor D2DPX/Q(r,) for radioiodines and particulates (in sec/m

3) is used; and Q i = is the release of nuclide "i" in curies.

3.4.1.e Nuclide Concentration in Meat The radionuclide concentration in meat is dependent upon the quantity and contamination level of feed consumed by the animal. The concentration is estimated (see RG 1.109-27, equations

C-11 and C-12) as follows:

C i (r,) = {(F f)(Q F)(e i s)[(f p)(f s)(CF i) + (1- f p)(CF i) +(f p)(1 - f s)(CF i)]}(D(r,)(Q i) where: Note: All parameters used in this pathway are for beef cattle.

C i (r,) = concentration of nuclide "i" in animal flesh at the receptor location (r,) in Ci/liter; { } = the expression in brackets represents the concentration factor (note that the concentration factor for meat involves two different vegetation concentration

factors);

F f = average fraction of the animal's daily intake of radionuclide "i" which appears in each kilogram of flesh (in days/kg);

Q f = amount of feed consumed by the animal per day in kg/day (wet weight); i = decay constant of nuclide "i" in hr

-1; t s = average time from slaughter of the ani mal to consumption by humans (20 days);

f p = fraction of the year that animals graze on pasture; f s = fraction of daily feed that is pasture grass when the animal grazes on pasture; CF i = vegetation concentration factor of nuclide "i" on pasture grass with the holdup time t h = 0 days in Ci/kg (refer to the explanation of the vegetation concentration factor calculation);

CF i = vegetation concentration factor of nuclide "i" in stored feeds with the holdup time t h = 90 days, in Ci/kg (refer to the explanation of the vegetation concentration factor calculation);

v v 1 - t v v v f 1 1 f v v 1 1 ARKANSAS NUCLEAR ONE ODCM Revision 20 24 D(r,) = relative deposition DOQ(r,) of the radionuclides, except carbon-14 and tritium. For carbon-14 and tritium, the decayed and depleted dispersion factor D2DPX/Q(r,) for radioiodines and particulates (in sec/m

3) is used; Q i = is the release of nuclide "i" (in curies).

3.5 Gaseous Effluent Projected Dose Calculation 3.5.1 The quarterly projected dose is based upon the methodology of Sections 3.3 and 3.4, and is expressed as follows:

D QC + D RP D QP = (T )(92) where: D QP = Quarterly projected dose (mrem);

D QC = cumulative dose for the quarter (mrem);

D RP = dose for current release (mrem); T = current days into quarter; and 92 = number of days per quarter.

3.6 Dose to the Public Inside the Site Boundary 3.6.1 Liquid Releases Dose to the public inside the site boundary due to liquid releases will be due to ingestion of fish caught from the discharge canal and exposure to sediment along the discharge canal bank

while fishing.

3.6.1.a Dose Due to Ingestion of Fish Dose due to ingestion of fish is calculated using the methodology given in Section 2.2, Liquid

Dose Calculation.

3.6.1.b Dose Due to Exposure to Shoreline Sediments Dose from external exposure to shoreline sediments is calculated from equation A-7 of RG 1.109, Rev. 1, 10/77.

(U ap)(M p)(W)R apj = 110,000(F (i [(Q i)(T i)(D aipj)(e i p)(1-e i b)] where: R apj = is the total annual dose to organ "j" of individuals of age group "a" from all of the nuclides "i" in pathway in mrem/yr; U ap = is the usage factor that specifies exposure time for the maximum individual of age group "a" in hours from Table E-5 of RG 1.109. Sixty-seven hours for shoreline recreation for a teen was chosen. Adult is the controlling age group for ingestion but the maximum usage factor (teen) was used rather than the adult factor to ensure a

conservative dose estimate;

- t - t ARKANSAS NUCLEAR ONE ODCM Revision 20 25 M p = is the mixing ratio (reciprocal of dilution factor); W = is the shoreline width factor from Table A-2 of RG 1.109. The discharge canal value of 0.1 was chosen; F = is the flow rate of the liquid effluent in ft 3/sec. This was determined by:

.134 ft 31 yr 1 hr F(ft 3/sec) = waste volume (gal/yr)

1 gal

8760 hr

3600 sec where: Q i = is the release of nuclide "i" in Ci/yr; T i = is the radioactive half-life of nuclide "i", in days, from Radioactive Decay Data Tables, Technical Information Center, U. S. Dept. of Energy, 1981; D aipj = is the dose factor specific to age group "a", nuclide "i", and organ "j" from Table E-6 of RG 1.109; i = is the radioactive decay constant of nuclide "i" in hr

-1; t p = is the average transit time for nuclides to reach the point of exposure. A value of 0 hours0 days 0 hours 0 weeks 0 months was chosen due to the proximity of the discharge canal

to the plant; and t b = is the period of time for which sediment is exposed to the contaminated water in hours. The mid-point of plant operating life, 15 years was

chosen per RG 1.109.

3.6.2 Airborne Release 3.6.2.a Dose Due to Noble Gases Dose to fisherman at the discharge canal can be calculated by the ratio of dispersion factor for the discharge canal (1.6E-4 sec/m 3 from Table 2-45 SAR, Unit 1, 100 meters downwind in a southerly direction) and the usage factor of 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months of shoreline recreation to the values used

in Section 3.3 of this manual.

1.6E-467 hr Dose at discharge canal = D T ()

2.8E-6

8760 hr where D T () is the noble gas dose calculated by Section 3.3.

3.6.2.b Dose Due to Iodine, Tritium and Particulates from Gaseous Effluents Section 3.4 calculates total dose for iodine, tritium and particulates as the sum of:

D TOT = D G + D I + D V + D L + D M + D F where: D G = ground plane deposition; D L = consumption of fresh leafy vegetables; D I = inhalation; D m = consumption of milk; and D v = consumption of vegetation; D F = consumption of meat and poultry

ARKANSAS NUCLEAR ONE ODCM Revision 20 26 The only contributions relevant to fishing activities at the discharge canal are ground plane deposition and inhalation. As D G and D I are not independently available, a conservative estimate can be obtained by using the same correction factor developed for noble gas dose to the total dose calculated in Section 3.4 for iodine, tritium and particulates. Depletion of the plume as it travels downwind can be ignored since the fraction remaining in the plume at 100 meters (discharge canal) and 1046 meters (site boundary) are both greater than 90%

according to Figure 3 of RG 1.111.

The only activity inside the plant site by members of the public that might contribute a significant dose is fishing along the banks of the discharge canal. Travel along public roads would involve short exposure time and tours of the facility are conducted according to radiological control

procedures enforced at the plant to control exposure. Fishing is the only uncontrolled activity.

4.0 ENVIRONMENTAL SAMPLING STATIONS - RADIOLOGICAL

Section 1.0 of the ODCM provides reference to the Radioactivty Effluent Controls Program governed by ANO-1 TS 5.5.4 and ANO-2 TS 6.5.4. However, a Radiological Environmental

Monitoring Program is also necessary to m eet the intent of the purpose of the ODCM.

The Radiological Environmental Monitoring Program is established to provide radiation and radionuclide monitoring in the environs surrounding the site. The program provides a method for representative measurements of radioactivity in the highest potential exposure pathways. In addition, the program provides for verification of the accuracy of the effluent monitoring program and modeling of envronmental exposure pathways.

The Radiological Environmental Monitoring Program is established by the ODCM and conforms to the guidance contained in 10 CFR 50, Appendix I. The program also provides for:

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

2. A land use census to ensure that changes in the use of areas at and beyond the site boundary are identified and that modifications to the monitoring program are made, if

required by the results of the 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.

Environmental samples are collected as specified in the Limitations. The approximate locations

of selected sample sites are shown on Figures 4-1, 4-1A, and 4-1B for illustrative purposes.

Table 4-1 lists the approximate distances and directions of the sample stations from the plant.

ARKANSAS NUCLEAR ONE ODCM Revision 20 27 5.0 REPORTING REQUIREMENTS

5.1 Annual Radiological Environmental Operating Report

The Annual Radiological Environmental Operating Report is submitted by May 15 of each year and contains a summary of the Radiological Environmental Monitoring Program for the reporting period. This report meets the requirements of TS 5.6.2 (ANO-1) and TS 6.6.2 (ANO-2), and is consistent with the objectives outlined in the ODCM and 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C. The report is formatted consistent with RG 1.21, Revision 1, to the extent possible. A single submittal is normally prepared incorporating the data for both ANO

units (common information is combined).

The Annual Radiological Environmental Operating Report includes the following:

1. Summarized and tabulated results of all radiological environmental samples and environmental radiation measur ements required by the ODCM.

2. A summary description of the Radiological Environmental Monitoring Program.

3. A map of the sampling locations with concurrent table providing distances and directions from the Reactor (Containment) Building. Because the ODCM contains this information and the ODCM is submitted as part of the Radioactive Effluent Release Report, reference to the Radioactive Effluent Release Report submittal date and letter number may be included in the Annual Radiological Environmental Operating Report in lieu of submitting

the sample location map and table.

4. A summary of the land use census results in accordance with Surveillance S 2.5.2.2.

5. A summary of the Interlaboratory Comparison Program in accordance with, Surveillance S 2.5.3.1.

As required by the Limitations, the report shall include the following for the conditions listed

below:

1. A description of the condition or event and, if applicable, equipment involved.

2. The cause of the condition or event.

3. Actions taken to restore the condition and prevent/minimize recurrence.

4. The consequences of the condition or event.

ARKANSAS NUCLEAR ONE ODCM Revision 20 28 Limitation Required Action Description 2.5.1 A.2 Sample not taken at required location* Sample equipment out-of-service (OOS) Sample frequency not met Monitoring/analysis lower limit of detection (LLD) not met Concentration limits not met Dose from other radionuclides exceed concentration limits2.5.1 B.1 New sample location identified 2.5.2 A.1 New sample location identified 2.5.3 A.1 Interlaboratory Comparison Program requirements not met NA NA Other harmful effects or evidence of irreversible damage detected

The report shall include a summary of information not available for reporting at the time of submittal. Such missing information shall be submitted in a supplemental letter when

data becomes available.

5.2 Radioactive Effluent Release Report

The Radioactive Effluent Release Report is submitted prior to May 1 of each year, but not more than 12 months from the previous year's submittal, and includes a summary of the quantities of radioactive liquid effluents, gaseous effluents, and solid waste released from the site. This report meets the requirements of TS 5.6.3 (ANO-1), TS 6.6.3 (ANO-2), 10 CFR 50.36a, and 10 CFR 50, Appendix I, Section IV.B.1. The report is formatted consistent with RG 1.21, Revision 1. A single submittal is normally prepared incorporating the data from both ANO units (common information is combined).

In general, the Radioactive Effluent Release Report includes the following:

1. A description of changes to the ODCM and PCP implemented during the reporting period. TS 5.6.3 (ANO-1) and TS 6.6.3 (ANO-2) contain a description of the ODCM change

process. 2. A summary of the hourly meteorological data collected over the previous calendar year. In lieu of including this information in the report, it is permissible to retain this summary

available for NRC review, if so noted in the report.

3. A summary of radiation doses due to radiological effluents during the previous calendar year, calculated in accordance with the methodology specified in the ODCM.

4. The radiation dose to members of the public while performing activities inside the site boundary. The calculated dose includes only contributions directly attributed to operation

of the units.

5. A description of major changes to the radioactive waste systems (liquid/gaseous/solid) during the previous calendar year, if not included in the cycle SAR update.

ARKANSAS NUCLEAR ONE ODCM Revision 20 29 As required by the Limitations, the report shall include the following for the conditions listed below:

1. A description of the condition or event and, if applicable, equipment involved.

2. The cause of the condition or event.

3. Actions taken to restore the condition and prevent/minimize recurrence.

4. The consequences of the condition or event.

Limitation Required Action Description 2.1.1 D.1 Liquid radioactive monitoring equipment OOS > 30 days 2.2.1 G.1 Gaseous radioactive monitoring equipment OOS > 30 days 2.3.1 A.2 Liquid radioactive release limits exceeded 2.3.1 F.1 Liquid radioactive monitor LLD exceeded 2.4.1 A.2 Gaseous radioactive release limits exceeded 2.4.1 E.1 Gaseous radioactive monitor LLD exceeded

ARKANSAS NUCLEAR ONE ODCM Revision 20 30 FIGURE 4-1 RADIOLOGICAL SAMPLE STATIONS

ARKANSAS RIVER 13 12 11 10 9 8 7 6 5 4 3 2 1 16 15 14 153 16 116 125 14 111 127 6 137 PINEY BAY USE AREA Dover US HWY 7 TO HARRISON 164 EAST TO MORELAND SR 24 TO MORELAND US HWY 64 RUSSELLVILLE ARKANSAS TECH UNIVERSITY DARDANELLE STATE PARK LAKE DARDANELLE DARDANELLE STATE PARK DARDANELLE LOCK AND DAM DAM SITE EAST PARK HWY 7T HWY 524 HWY 22 HWY 7 HWY 27 HWY 28 HWY 7 HWY 155 MT. NEBO STATE PARK SR 247 TO POTTSVILLE HWY 7 TO HOT SPRINGS DARDANELLE HWY 27 TO DANVILLE (SEE INSET) INTERSTATE 40 TO FORT SMITH U.S. HWY 22 LONDON INTERSTATE 40 U.S. HWY 64 SR 333 0° 20° 40° 60° 80° SR 5 100° 120° 140° 160° 180° 200° 220° 240° 260° 280° 300° 320° 340° HWY 27 HWY 154 HWY 10 HWY 10 HWY 27 HWY 80 Entergy Substation Petit Jean River Cowger Lake City of Danville 55 57 7 DANVILLE INSET Arkansas Nuclear One REMP Sample Locations (Far Field) DELAWARE STATE PARK N S E W J I H G F E D C B A

ARKANSAS NUCLEAR ONE ODCM Revision 20 31 FIGURE 4-1A RADIOLOGICAL SAMPLE STATIONS

Lake Dardanelle Arkansas Nuclear One REMP Sample Locations (Near Field) Revised 24May05 West Access Rd. Cemetery May Rd. Bunker Hill Rd. Bunker Hill Ln. Scott Ln. Training Center SR 333 150 4 149 8S 110 14 8 8 C 3 6 5 6 2 13 109 10 1 147 14 6 145 10 8 15 2 3 151 ARKANSAS NUCLEAR ONE ODCM Revision 20 32 FIGURE 4-1B RADIOLOGICAL SAMPLE STATIONS

Lake Dardanelle Switch Yard 58 63 STR-3 STR-2 STR-4 STR-1 STR-5 West Access Road Arkansas Nuclear One REMP Sample Locations Site Map N S E W STR-6 62 64 ARKANSAS NUCLEAR ONE ODCM Revision 20 33 FIGURE 4-2 MAXIMUM AREA BOUNDARY FOR RADIOACTIVE RELEASE CALCULATION (Exclusion Areas)

UNIT 2 UNIT 1 N EVACUATION ROUTE 1 EVACUATION ROUTE 3 EVACUATION ROUTE 2 COOLING TOWER EMERGENCY RESPONSE FACILITY 0.65 MILE RADIUS POINT A SWITCHYARD HWY. 333 GASES - 1046 METER RADIUS LIQUIDS - END OF DISCHARGE CANAL (POINT A)

ARKANSAS NUCLEAR ONE ODCM Revision 20 34 TABLE 4-1 Environmental Sampling Stations - Radiological Sample Station # Approximate Direction and Distance from Plant Sample Types Sample Station Location 1 88° - 0.5 miles Airborne radioiodines Airborne particulates Direct radiation The thermoluminescent dosimeter (TLD) is on a pole near the meteorology tower

approx. 0.6 miles east of ANO. 2 243° - 0.5 miles Airborne radioiodines Airborne particulates Direct radiation Traveling from ANO, go approx. 0.2 miles west toward Gate 4. Turn left (at the east

end of the sewage treatment plant) and go

approx. 0.1 miles. Turn right and go

approx. 0.1 miles. The sample station is

on the right. 3 5° - 0.7 miles Direct radiation If traveling west on Highway (Hwy) 333, go approx. 0.35 miles from Gate 2 at ANO.

TLD is located on utility pole on south side

of Hwy 333 S.

If traveling east on Highway 333, go approx. 0.9 miles from junction of Hwy 333

and Flatwood Road. TLD is located on

utility pole on south side of Hwy 333 S. 4 181° - 0.5 miles Direct radiation Go approx. 0.25 miles south from bridge over intake canal. Turn right onto May

Road. Proceed approx. 0.1 miles west of

May Cemetery entrance. The TLD is

located on a utility pole on the south side

of May Road. 6 111° - 6.8 miles Airborne radioiodines Airborne particulates Direct radiation Go to the Entergy local office which is located off Hwy 7T in Russellville, Arkansas (AR) (305 South Knoxville

Avenue). The sample station is against

the east wall of the back lot.

7 210° - 19.0 miles Airborne radioiodines Airborne particulates Direct radiation Turn west at junction of Hwy 7 and Hwy 27 in Dardanelle, AR. Proceed to junction of

Hwy 27 and Hwy 10 in Danville, AR. Turn

right onto Hwy 10 and proceed a short

distance to the Entergy supply yard, which

is on the right adjacent to an Entergy

substation. The sample station is in the

southwest corner of the supply yard.

8 166° - 0.2 miles 243° - 0.9 miles

212° - 0.5 miles Surface water (composite)Shoreline sediment Fish Plant discharge canal

ARKANSAS NUCLEAR ONE ODCM Revision 20 35 TABLE 4-1 Environmental Sampling Stations - Radiological (continued)

Sample Station # Approximate Direction and Distance from Plant Sample Types Sample Station Location 10 95° - 0.5 miles (intake canal)

Surface water (grab)

Surface water (grab) is collected at plant intake canal. 13 273° - 0.5 miles Broad leaf vegetation Traveling from Hwy 333, turn south onto Flatwood Road. Go approx. 1.0 miles.

The sample may be collected from either

side of Flatwood Road. 14 70° - 5.1 miles Drinking water From junction of Hwy 7 and Water Works Road, go approx. 0.8 miles west on Water

Works Road. The sample station is on the

left at the intake to the Russellville city

water system from the Illinois Bayou. 16 287° - 5.5 miles Shoreline sediment Fish Panther Bay, located on the south side of the AR River across from the mouth of

Piney Creek.

36 153° - 0.02 miles Pond water Pond sediment The sample station is at the Wastewater Holding Pond on the ANO site east of the

discharge canal.

55 208° - 16.5 miles Broad leaf vegetation From Dardanelle, travel south on Hwy 27.

Go approx. 15.5 miles to the intersection of

Hwys 27 and 154. The sample station is

located at this intersection. 56 264° - 0.4 miles Airborne radioiodines Airborne particulates Direct radiation Traveling west from ANO, the sample station is located at the west end of the

sewage treatment plant near the facility

blower building.

57 208° - 19.5 miles Drinking water Go to Danville and turn left on Fifth Street.

Go approx. three blocks. The Danville

public water supply treatment facility is

located on the left. 58 22° - 0.3 miles Groundwater GWM - 1; North of Protected Area on owner controlled area (OCA), west of north Security Check Point, east side of access road. 62 34° - 0.5 miles Groundwater GWM - 101; North of Protected Area on OCA, east of outside receiving building.

ARKANSAS NUCLEAR ONE ODCM Revision 20 36 TABLE 4-1 Environmental Sampling Stations - Radiological (continued)

Sample Station # Approximate Direction and Distance from Plant Sample Types Sample Station Location 63 206° - 0.1 miles Groundwater GWM - 103; South of Protected Area on OCA, northeast of Stator Rewind Building near woodline.

64 112° - 0.1 miles Groundwater GWM - 13; South of Oily Water Separator, northwest corner of ANO-2 Intake Structure, inside the Protected Area.

108 306° - 0.9 miles Direct radiation If traveling from Hwy 333, turn south onto Flatwood Road and go approx. 0.4 miles.

The TLD is on a utility pole on the right.

If traveling north on Flatwood Road, go approx. 0.4 miles from sample station 109.

The TLD is on a utility pole on the left. 109 291° - 0.6 miles Direct radiation Traveling from Hwy 333, turn south onto Flatwood Road. Go approx. 0.8 miles. The

TLD is on a utility pole on the left across

from the junction of Flatwood Road and

Round Mountain Road. 110 138° - 0.8 miles Direct radiation From bridge over intake canal, go south approx. 0.25 miles. Turn left and go

approx. 0.25 miles. Turn right on Bunker

Hill Lane. The TLD is on the first utility

pole on the left. 111 120° - 2.0 miles Direct radiation From junction of Hwy 64 and Hwy 326 (Marina Road), go approx. 2.1 miles on

Marina Road. The TLD is on a utility pole

on the left just prior to curve. 116 318° - 1.8 miles Direct radiation Go one block south of the west junction of Hwy 333 and Hwy 64 in London, AR. The

TLD is on a utility pole north of the railroad

tracks. 125 46° - 8.7 miles Direct radiation Traveling north on Hwy 7, turn left onto Water Street in Dover, AR. Go one block

and turn left onto South Elizabeth Street.

Go one block and turn right onto College

Street. The TLD is on a utility pole at the

southeast corner of the red brick school

building, which is located on top of hill.

ARKANSAS NUCLEAR ONE ODCM Revision 20 37 TABLE 4-1 Environmental Sampling Stations - Radiological (continued)

Sample Station # Approximate Direction and Distance from Plant Sample Types Sample Station Location 127 100° - 5.2 miles Direct radiation The TLD is located on Arkansas Tech Campus on N. Glenwood Street. If

traveling south on Hwy 7 from I- 40, turn

right on N. Glenwood. Follow N. Glenwood

for approx. 0.6 miles. The TLD is located

on a utility pole (with a No Parking sign on

it) across from the northeast corner of

Paine Hall. 137 151° - 8.2 miles Direct radiation At junction of Hwy 7 and Hwy 28 in Dardanelle, AR, go approx. 0.2 miles on

Hwy 28. The TLD is on a speed limit sign

on the right in front of the Morris R. Moore

Arkansas National Guard Armory. 145 28° - 0.6 miles Direct radiation The TLD is located near the west entrance to the Reeves E. Ritchie Training Center (RERTC) on a utility pole on the north side

of Hwy 333. 146 45° - 0.6 miles Direct radiation The TLD is located on the south end of the east parking lot at the RERTC. The TLD is

located on a utility pole. 147 61° - 0.6 miles Direct radiation The TLD is located on the west side of Bunker Hill Road, approx. 100 yards from

the intersection with Hwy 333. 148 122° - 0.6 miles Direct radiation Traveling east from ANO, turn right on Bunker Hill Road. Travel south for approx.

0.25 miles to the intersection with Scott

Lane. The TLD is located on the county

road sign post. 149 156° - 0.5 miles Direct radiation Traveling south on Bunker Hill Road, turn right on May Road. Travel approx.

0.4 miles. The TLD is located on a "Notice"

sign on the north side of May Road. 150 205° - 0.6 miles Direct radiation Traveling south on Bunker Hill Road, turn right on May Road. Travel approx.

0.8 miles. The TLD is located just past the

McCurley Place turn off on the north side

of May Road on a utility pole.

ARKANSAS NUCLEAR ONE ODCM Revision 20 38 TABLE 4-1 Environmental Sampling Stations - Radiological (continued)

Sample Station # Approximate Direction and Distance from Plant Sample Types Sample Station Location 151 225° - 0.4 miles Direct radiation Traveling west from ANO, turn south on plant road along the east side of the

sewage treatment plant. The TLD is

located at the end of this road, near the

lake on a metal post. 152 338° - 0.8 miles Direct radiation Traveling west on Hwy 333 from the RERTC, travel approx. 0.7 miles. The TLD

is located on the south side of Hwy 333 on

a utility pole. 153 304° - 9.2 miles Direct radiation Travel Hwy 64 west to Knoxville Elementary School. The TLD is located

near the school entrance gate on a utility

pole. STR - 1 120° - 0.33 miles Storm water runoff East side of GSB drainage ditch near lift station. STR - 2 351° - < 0.10 miles Storm water runoff Inside protected area near Sally Port from drainage ditch along fence. STR - 3 0.2° - 0.13 miles Storm water runoff Outside Protected Area near Sally Port from drainage ditch along fence.

STR - 4 102° - 0.10 miles Storm water runoff East side of Oily Water Separator from storm drain.

STR - 5 170° - < 0.10 miles Storm water runoff West side of discharge canal from storm drain. STR - 6 90° - < 0.10 miles Storm water runoff East side of chemistry chemical storage area storm drain.

ARKANSAS NUCLEAR ONE ODCM Revision 20 39

APPENDIX 1 RADIOLOGICAL EFFLUENT CONTROLS

ARKANSAS NUCLEAR ONE ODCM Revision 20 40 1.0 DEFINITIONS

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

The defined terms of this section appear in capitalized type and are applicable throughout these

Limitations and Bases.

Term Definition

ACTION(S) ACTIONS shall be that part of a Limitation that prescribes Required Actions to be taken under designated Conditions

within specified Completion Times.

BATCH RELEASE A BATCH RELEASE is the discharge of liquid or gaseous wastes of a discrete volume.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds

within the necessary range and accuracy to known values

of the parameter that the channel monitors. The CHANNEL

CALIBRATION shall encompass all devices in the channel

required for channel FUNCTIONALITY and the CHANNEL

TEST. The CHANNEL CALIBRATION may be performed

by means of any series of sequential, overlapping, or total

channel steps.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This

determination shall include, where possible, comparison of

the channel indication and status to other indications or

status derived from independent instrument channels

measuring the same parameter.

CHANNEL TEST A CHANNEL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as

practicable to verify FUNCTIONALITY of all devices in the

channel required for channel FUNCTIONALITY. The

CHANNEL TEST may be performed by means of any series

of sequential, overlapping, or total steps.

CONTINUOUS RELEASE A CONTINUOUS RELEASE is the discharge of liquid waste of a non-discrete volume, e.g. from a volume of a system

that has an input flow during the continuous release.

EXCLUSION AREA The EXCLUSION AREA is that area surrounding ANO within a minimum radius of 0.65 miles of the Reactor (Containment) Buildings and controlled to the extent

necessary by the licensee for purposes of protection of

individuals from exposure to radiation and radioactive materials.

ARKANSAS NUCLEAR ONE ODCM Revision 20 41 1.0 DEFINITIONS (continued)

Term Definition

FUNCTIONAL-FUNCTIONALITY A system, subsys tem, train, component, or device shall be FUNCTIONAL or have FUNCTIONALITY when it is capable

of performing its specified function(s), as set forth in the

current license basis (CLB) and when all necessary

attendant instrumentation, controls, normal or emergency

electrical power, cooling and seal water, lubrication, and

other auxiliary equipment that are required for the system,

subsystem, train, component, or device to perform its

specified function(s) are also capable of performing their

related support function(s).

GASEOUS RADWASTE A GASEOUS RADWASTE TREATMENT SYSTEM is TREATMENT SYSTEM any system designed and installed to reduce radioactive gaseous effluents by collecting gases from radioactive

systems and providing for decay or holdup for the purpose

of reducing the total radioactivity prior to release to the

environment.

LIQUID RADWASTE A LIQUID RADWASTE TREATMENT SYSTEM is a TREATMENT SYSTEM system designed and used for holdup, filtration, and/or demineralization of radioactive liquid effluents prior to their

release to the environment.

MEMBER(S) OF THE PUBLIC MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This

category does not include employees of the utility, its

contractors or vendors. Also excluded from the category

are persons who enter the site to service equipment or to

make deliveries. This category does include persons who

use portions of the site for recreational, occupational or

other purposes not associated with the plant.

MODE(S) Refer to Definitions section of ANO-1 and ANO-2 TSs.

PURGE - PURGING PURGE or PURGING is the controlled process of discharging air or gas from a confinement to reduce the

airborne radioactivity concentration in such a manner that

replacement air or gas is required to purify the confinement.

SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a

radioactive source.

ARKANSAS NUCLEAR ONE ODCM Revision 20 42 1.0 DEFINITIONS (continued)

Term Definition VENTILATION EXHAUST A VENTILATION EXHAUST TREATMENT SYSTEM is any TREATMENT SYSTEM system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in

effluents by passing ventilation or vent exhaust gases

through charcoal adsorbers and/or HEPA filters for the

purpose of removing iodines or particulates from the

gaseous exhaust stream prior to the release to the

environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEMS.

UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area beyond the EXCLUSION AREA boundary.

ARKANSAS NUCLEAR ONE ODCM Revision 20 43 2.0 LIMITITATION (L) APPLICABILITY L 2.0.1 Limitations shall be met during the specified conditions in the Applicability, except as provided in L 2.0.2.

L 2.0.2 Upon discovery of a failure to meet a Limitation, the applicable ACTIONS of the associated Limitation shall be met, except as provided in L 3.0.5. If the Limitation is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the ACTIONS is not required, unless otherwise stated.

L 2.0.3 When a Limitation is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, immediately initiate a condition report to document the condition and determine any

limitations for continued operation of the plant.

Exceptions to this Limitation are stated in the individual Limitations.

L 2.0.4 When a Limitation is not met, entry into a MODE or other specified condition in the Applicability shall only be made when the associated ACTIONS to be entered permit

continued operation in the MODE or other specified condition in the Applicability for

an unlimited period of time.

L 2.0.5 Equipment removed from service or declared non-functional to comply with ACTIONS may be returned to service under adm inistrative control solely to perform testing required to demonstrate its FUNCTIONALITY or the FUNCTIONALITY of

other equipment. This is an exception to L 2.0.2 for the system returned to service

under administrative control to perform the testing required to demonstrate

FUNCTIONALITY.

ARKANSAS NUCLEAR ONE ODCM Revision 20 44 2.0 SURVEILLANCE (S) APPLICABILITY S 2.0.1 Surveillances shall be met during the specified conditions in the Applicability for individual Limitations, unless otherwise stated in the Surveillance. Failure to

meet a Surveillance, whether such failure is experienced during the performance

of the Surveillance or between performances of the Surveillance, shall be failure

to meet the Limitation. Failure to perform a Surveillance within the specified

Frequency shall be failure to meet the Limitation except as provided in S 2.0.3.

Surveillances are not required to be performed on non-functional equipment or

variables outside specified limits.

S 2.0.2 The specified Frequency for each Surveillance is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured

from the previous performance or as measured from the time a specified condition of the Frequency is met. For Frequencies specified as "once," the

above interval extension does not apply. If an Action completion time requires

periodic performance on a "once per . . ." basis, the above Frequency extension

applies to each performance after the initial performance.

S 2.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the Limitation not

met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit

of the specified Frequency, whichever is greater. This delay period is permitted

to allow performance of the Surveillance.

If the Surveillance is not performed within the delay period, the Limitation must immediately be declared not met, and the applicable ACTIONS must be entered.

When the Surveillance is performed within the delay period and the Surveillance is not met, the Limitation must immediately be declared not met, and the applicable

ACTIONS must be entered.

S 2.0.4 Entry into a specified condition in the Applicability of a Limitation shall only be made when the Limitation's Surveillances have been met within their specified

Frequency, except as provided by S 2.0.3. When a Limitation is not met due to

Surveillances not having been met, entry into a specified condition in the

Applicability shall only be made in accordance with L 2.0.4.

ARKANSAS NUCLEAR ONE ODCM Revision 20 45 L 2.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

L 2.1.1 The following Radioactive Liquid Effluent Monitoring Instrumentation shall be FUNCTIONAL:

a. Liquid Radwaste Effluent Radiation Monitor with alarm/trip function

b. Liquid Radwaste Effluent Flow Monitor

c. One Main Steam Line Radiation Moni tor per Steam Generator (ANO-1 only)

APPLICABILITY: Liquid Radwaste Effluent Monitor - during releases via the associated pathway Main Steam Line Radiation Monitors - MODES 1, 2, 3, and 4

ACTIONS

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

Separate Condition entry is allowed for each instrument.

-- CONDITION REQUIRED ACTION COMPLETION TIME A. Required Liquid Radwaste Effluent Radiation Monitor

non-functional.

A.1 Suspend the release of radioactive effluents

monitored by the affected

channel.

AND A.2.1 Restore the monitor to a FUNCTIONAL status.

OR A.2.2.1 Analyze two independent samples of the associated

tank contents.

AND A.2.2.2 Computer input data verified by two qualified

individuals.

AND Immediately

Prior to release of

radioactive effluents

monitored by the

affected channel

Prior to release of

radioactive effluents

monitored by the

affected channel

Prior to release of

radioactive effluents

monitored by the

affected channel

ARKANSAS NUCLEAR ONE ODCM Revision 20 46 L 2.1.1 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)

A.2.2.3 Correct discharge valve lineup independently

verified by two qualified

individuals.

Prior to release of

radioactive effluents

monitored by the

affected channel

B. Required Liquid Radwaste Effluent Flow Monitor non-

functional.

B.1 Estimate flow.

OR B.2 Suspend the release of radioactive effluents monitored

by the affected channel.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

Immediately

C. One or more required Main Steam Line Radiation

Monitor non-functional.

C.1 Establish pre-planned alternate monitoring method

of monitoring.

AND C.2 Restore the affected Main Steam Line Radiation

Monitor(s) to a FUNCTIONAL

status. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

7 days

D. Required Action(s) and/or Completion Time(s) of

Conditions A, B, and/or C

not met. D.1 Initiate a condition report to document the condition and

determine any limitations for

the continued effluent release

operations.

Immediately

E. Required Radioactive Liquid Effluent Monitoring

Instrument non-functional

for > 30 days.

E.1 Initiate a condition report to document and track the

condition for inclusion in the

Radioactive Effluent Release

Report pursuant to TS 5.6.3 (ANO-1) / TS 6.6.3 (ANO-2).

Immediately

ARKANSAS NUCLEAR ONE ODCM Revision 20 47 L 2.1.1 SURVEILLANCES SURVEILLANCE FREQUENCY S 2.1.1.1 Perform a CHANNEL CHECK of required instrumentation.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

S 2.1.1.2 -----------------------------------NOTE------------------------------------

Not applicable to Liquid Radwaste Effluent Flow Monitor.

Perform a CHANNEL TEST of the required instrumentation.

92 days

S 2.1.1.3 Perform a CHANNEL CALIBRATION on the required instrumentation.

18 months

S 2.1.1.4 -----------------------------------NOTES----------------------------------- 1. SOURCE CHECK not required when background radioactivity is greater than the check source. 2. Not applicable to Liquid Radwaste Effluent Flow Monitor or Main Steam Line Radiation Monitors.

Perform a SOURCE CHECK on the required

instrumentation.

Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior

to release of

radioactive effluents

monitored by the

channel

ARKANSAS NUCLEAR ONE ODCM Revision 20 48 L 2.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

L 2.2.1 The following Radioactive Gaseous Effluent Monitoring Instrumentation shall be FUNCTIONAL:

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

Refer to ANO-2 Technical Specification (TS) 3.3.3.1 for ANO-2 Containment Building

Purge System Process Monitor operability requirements and associated ACTIONS.

a. Waste Gas Holdup Systems

1. Gas Activity Process Monitor with alarm/trip function 2. Effluent Flow Process Monitor

b. Reactor (Containment) Building Purge and Ventilation, Auxiliary Building Ventilation, Spent Fuel Pool Area Ventilation, Emergency Penetration Room

Ventilation, Low Level Radwaste Build ing Ventilation, and ANO-2 Auxiliary Building Extension Ventilation SPING Monitors

1. Noble Gas Activity Monitor 2. Iodine Sampler

3. Particulate Sampler

4. Effluent Flow Monitor

5. Sampler Flow Monitor

APPLICABILITY: During releases via the associated pathway

ARKANSAS NUCLEAR ONE ODCM Revision 20 49 ACTIONS

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

Separate Condition entry is allowed for each instrument.

-- CONDITION REQUIRED ACTION COMPLETION TIME A. -------------NOTE--------------

Applicable to releases

associated with Waste Gas

Holdup Systems and

PURGE of the ANO-1

Reactor Building.

Required Waste Gas

Holdup and/or Reactor

Building Purge System

Gas Activity Process

and/or Noble Gas Activity

Monitor non-functional.

A.1 Suspend the release of radioactive effluents

monitored by the affected

channel.

AND A.2.1 Restore the monitor to a FUNCTIONAL status.

OR A.2.2.1 Analyze two independent samples of the Waste Gas

Holdup Tank and/or

Reactor Building contents.

AND A.2.2.2 Computer input data verified by two qualified

individuals.

AND A.2.2.3 -------------NOTE-------------

Not applicable to Reactor

Building Purge System.

Correct discharge valve

lineup independently

verified by two qualified

individuals.

Immediately

Prior to release of

radioactive effluents

monitored by the

affected channel

Prior to release of

radioactive effluents

monitored by the

affected channel

Prior to release of

radioactive effluents

monitored by the

affected channel

Prior to release of

radioactive effluents

monitored by the

affected channel

ARKANSAS NUCLEAR ONE ODCM Revision 20 50 L 2.2.1 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. Required Effluent or Sampler Flow Monitor non-

functional.

B.1 Estimate flow.

OR B.2 Suspend the release of radioactive effluents monitored

by the affected channel.

Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

Immediately

C. --------------NOTE--------------

Applicable to releases other

than those described in

Condition A above.

Required Noble Gas Activity

Monitor non-functional.

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

If ANO-1 Reactor Building Purge

and Ventilation required Noble Gas

Activity Monitor inoperable and

moving irradiated fuel within the

ANO-1 Reactor Building, refer to

ANO-1 TS 3.9.3.

C.1 Obtain sample of effluent.

AND C.2 Analyze sample of effluent.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

following completion of

Required Action C.1

D. Required Iodine and/or Particulate Sampler non-

functional.

D.1 Verify effluent samples are continuously collected by

auxiliary sampling equipment.

AND D.2 Replace Iodine and/or Particulate cartridges (as

applicable).

AND D.3 Analyze Iodine and/or Particulate cartridges (as

applicable).

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

7 days

Within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months

following replacement ARKANSAS NUCLEAR ONE ODCM Revision 20 51 L 2.2.1 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action(s) and/or Completion Time(s) of

Condition C and/or

Condition D not met.

E.1 Suspend the release of radioactive effluents monitored

by the affected channel.

Immediately

F. Required Action(s) and/or Completion Time(s)

Condition A, B, and/or E

not met. F.1 Initiate a condition report to document the condition and

determine any limitations for

the continued effluent release

operations.

Immediately

G. Required Radioactive Gaseous Effluent

Monitoring Instrument

non-functional for

> 30 days.

G.1 Initiate a condition report to document and track the

condition for inclusion in the

Radioactive Effluent Release

Report pursuant to TS 5.6.3 (ANO-1) / TS 6.6.3 (ANO-2).

Immediately

SURVEILLANCES SURVEILLANCE FREQUENCY S 2.2.1.1 -----------------------------------NOTE------------------------------------

Not applicable to Iodine and Particulate Samplers

Perform a CHANNEL CHECK of required instrumentation.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

S 2.2.1.2 Verify presence of required Iodine Sampler Cartridge and required Particulate Sample Filter.

7 days

S 2.2.1.3 Perform a CHANNEL TEST of the required Reactor Building Purge and Ventilation System Gas Activity Process and

Noble Gas Activity Monitors.

31 days prior to

initiating Reactor

Building Purge

and/or Ventilation

activities

ARKANSAS NUCLEAR ONE ODCM Revision 20 52 L 2.2.1 SURVEILLANCES (continued)

SURVEILLANCE FREQUENCY S 2.2.1.4 -----------------------------------NOTES-----------------------------------

SOURCE CHECK not required when background

radioactivity is greater than the check source.

Perform a SOURCE CHECK on the required Noble Gas

Activity Monitors.

31 days

S 2.2.1.5 -----------------------------------NOTES----------------------------------- 1. SOURCE CHECK not required when background radioactivity is greater than the check source.

2. Only applicable to Waste Gas Holdup and Reactor Building Purge Systems.

Perform a SOURCE CHECK on the required Gas Activity

Process and Noble Gas Activity Monitors.

Within 14 days prior

to release of

radioactive effluents

monitored by the

channel

S 2.2.1.6 Perform a CHANNEL TEST of the required Noble Gas Activity Monitors.

92 days

S 2.2.1.7 -----------------------------------NOTE------------------------------------

Not applicable to Iodine and Particulate Samplers

Perform a CHANNEL CALIBRATION on the required

instrumentation.

18 months

ARKANSAS NUCLEAR ONE ODCM Revision 20 53 L 2.3 RADIOACTIVE LIQUID EFFLUENTS

L 2.3.1 Radioactive material released to the discharge canal shall:

a. For dissolved or entrained noble gases, be limited to a total concentration of 2 x 10-4 µCi/ml. b. For radioactive nuclides other than dissolved or entrained noble gases, be limited to the concentration specified in 10 CFR 20, Appendix B, Table II, Column 2.

c. During any calendar quarter, result in a dose commitment to a MEMBER OF THE PUBLIC of 1.5 mrem to the total body and 5 mrem to any organ.

d. During any calendar year, result in a dose commitment to a MEMBER OF THE PUBLIC of 3 mrem to the total body and 10 mrem to any organ.

e. Be processed by a LIQUID RADWASTE TREATMENT SYSTEM when accumulative dose during a calendar quarter is projected to exceed 0.18 mrem

to the total body and/or 0.625 mrem to any organ.

APPLICABILITY: At all times.

ACTIONS

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

Separate Condition entry is allowed for each Limitation L 2.3.1.a through L 2.3.1.e above and for each BATCH RELEASE and CONTINUOUS RELEASE Surveillance requirement not met.

-- CONDITION REQUIRED ACTION COMPLETION TIME A. Any limit listed in L 2.3.1.a through L 2.3.1.e not met.

A.1 Initiate action to restore to within limit.

AND A.2 Initiate a condition report to document the condition, determine any limitations for

the continued effluent release

operations, and track the

condition for inclusion in the

Radioactive Effluent Release

Report pursuant to TS 5.6.3 (ANO-1) / TS 6.6.3 (ANO-2).

Immediately

ARKANSAS NUCLEAR ONE ODCM Revision 20 54 L 2.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. --------------NOTE--------------

Only applicable to BATCH

RELEASE.

Sampling and/or analysis

requirements not met.

B.1 Verify associated effluent release suspended.

AND B.2 Initiate a condition report to document the condition and

determine any limitations for

the continued effluent release

operations.

Immediately

C. --------------NOTE--------------

Only applicable to

CONTINUOUS RELEASE

of secondary coolant.

Secondary coolant dose

equivalent I-131 (DEI)

> 0.01 µCi/ml.

C.1 Obtain a grab sample of the associated secondary

coolant.

AND C.2 Perform gamma isotopic and I-131 analysis of sample.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months following

sample acquisition

D. Annual dose limits of L 2.3.1.d projected to

exceed 40 CFR 190 limits.

D.1 Apply for a variance from the NRC to permit releases in

excess of 40 CFR 190 limits.

Prior to exceed

40 CFR 190 limits

Immediately

E. Required Action(s) and/or Completion Time(s) of

Conditions C and/or D not

met.

OR Sampling and/or analysis

requirements not met.

E.1 Initiate a condition report to document the condition and

determine any limitations for

the continued effluent release

operations.

Immediately

ARKANSAS NUCLEAR ONE ODCM Revision 20 55 L 2.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Lower Limit(s) of Detection (LLD) not met.

F.1 Initiate a condition report to document and track the

condition for inclusion in the

Radioactive Effluent Release

Report pursuant to TS 5.6.3 (ANO-1) / TS 6.6.3 (ANO-2).

Immediately SURVEILLANCES SURVEILLANCE FREQUENCY S 2.3.1.1 -----------------------------------NOTE------------------------------------

Only applicable to BATCH RELEASE.

Obtain representative sample of each batch.

AND Perform gamma isotopic and I-131 analysis of sample.

AND Perform dissolved and entrained gas analysis of sample.

AND Perform gross alpha composite and H-3 analysis of sample.

AND Perform Sr-89, Sr-90, and Fe-55 composite analysis of sample.

Prior to release Prior to release 31 days following

sample acquisition 31 days following sample acquisition 92 days following sample acquisition

ARKANSAS NUCLEAR ONE ODCM Revision 20 56 L 2.3.1 SURVEILLANCES (continued) SURVEILLANCE FREQUENCY S 2.3.1.2 -----------------------------------NOTE------------------------------------

Only applicable to CONTINUOUS RELEASE.

Obtain representative sample of effluent.

AND Perform gamma isotopic and I-131 analysis.

AND Perform dissolved and entrained gas analysis.

AND Perform gross alpha composite and H-3 analysis.

AND Perform Sr-89, Sr-90, and Fe-55 composite analysis.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following

sample acquisition 31 days following sample acquisition 31 days following sample acquisition 92 days following sample acquisition

S 2.3.1.3 Using data acquired by performance of S 2.3.1.1 and S.2.3.1.2, verify Limitations L 2.3.1.a through L 2.3.1.e

continue to be met.

Within 7 days

following completion

of each required

analysis

S 2.3.1.4 Using data acquired by performance of S 2.3.1.1 and S.2.3.1.2, verify the limits of 40 CFR 190 are not projected to

be exceeded.

31 days

S 2.3.1.5 Verify the following LLDs are met:

Gamma isotopic 5 x 10

-7 µCi/ml I-131 and Fe-55 1 x 10

-6 µCi/ml Dissolved/entrained gases (gamma emitters) 1 x 10

-5 µCi/ml H-3 1 x 10

-5 µCi/ml Gross alpha 1 x 10

-7 µCi/ml Sr-89 and Sr-90 5 x 10

-8 µCi/ml 12 months

ARKANSAS NUCLEAR ONE ODCM Revision 20 57 L 2.4 RADIOACTIVE GASEOUS EFFLUENTS

L 2.4.1 Radioactive Gaseous Effluent releases to unrestricted areas shall:

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

Dose rates associated with Reactor (Containment) Building Purge operations may

be averaged over a one hour interval.

a. For noble gases, be limited to:

1. A total body dose rate of 500 mrem/yr.

2. A skin dose rate of 3000 mrem/yr.

3. A dose commitment to a MEMBER OF THE PUBLIC in any calendar quarter of 5 mrads gamma and 10 mrads beta radiation.

4. A dose commitment to a MEMBER OF THE PUBLIC in any calendar year of 10 mrads gamma and 20 mrads beta radiation.

b. For I-131, H-3, and for all radionuclides in particulate form having a half life of

> 8 days, be limited to:

1. An organ dose rate of 1500 mrem/yr.

2. A dose commitment to a MEMBER OF THE PUBLIC in any calendar quarter of 7.5 mrem to any organ.

3. A dose commitment to a MEMBER OF THE PUBLIC in any calendar year of 15 mrem to any organ.

c. Be processed by a VENTILATION EXHAUST TREATMENT SYSTEM when:

1. For noble gases, the dose over a calendar quarter is project to exceed 0.625 mrads gamma and/or 1.25 mrads beta radiation.

2. For I-131, H-3, and for all radionuclides in particulate form having a half life of > 8 days, the dose over a calendar quarter is project to exceed 1.0 mrem

to any organ.

d. Be processed by the GASEOUS RADWASTE TREATMENT SYSTEM when degasifying the Reactor Coolant System (RCS), if projected dose would exceed

0.625 mrads gamma and/or 1.25 mrads beta radiation over a calendar quarter.

APPLICABILITY: At all times.

ARKANSAS NUCLEAR ONE ODCM Revision 20 58 L 2.4.1 ACTIONS

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

Separate Condition entry is allowed for each Limitation L 2.4.1.a through L 2.4.1.d above and for each Surveillance requirement not met.

-- CONDITION REQUIRED ACTION COMPLETION TIME A. Any limit listed in L 2.4.1.a through L 2.4.1.d not met.

A.1 Initiate action to restore to within limit.

AND A.2 Initiate a condition report to document the condition, determine any limitations for

the continued effluent release

operations, and track the

condition for inclusion in the

Radioactive Effluent Release

Report pursuant to TS 5.6.3 (ANO-1) / TS 6.6.3 (ANO-2).

Immediately

B. Sampling and/or analysis requirements of S 2.4.1.1

not met.

B.1 Verify associated effluent release suspended.

AND B.2 Initiate a condition report to document the condition and

determine any limitations for

the continued effluent release

operations.

Immediately

C. Annual dose limits of L 2.4.1.a.4 and/or

L 2.4.1.b.4 projected to

exceed 40 CFR 190 limits.

C.1 Apply for a variance from the NRC to permit releases in

excess of 40 CFR 190 limits.

Prior to exceed

40 CFR 190 limits

Immediately

ARKANSAS NUCLEAR ONE ODCM Revision 20 59 L 2.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action(s) and/or Completion Time(s) of

Condition C not met.

OR Sampling and/or analysis

requirements of S 2.4.1.2

not met. D.1 Initiate a condition report to document the condition and

determine any limitations for

the continued effluent release

operations.

Immediately

E. Lower Limit(s) of Detection (LLD) not met.

E.1 Initiate a condition report to document and track the

condition for inclusion in the

Radioactive Effluent Release

Report pursuant to TS 5.6.3 (ANO-1) / TS 6.6.3 (ANO-2).

Immediately SURVEILLANCES SURVEILLANCE FREQUENCY S 2.4.1.1 -----------------------------------NOTE------------------------------------

Only applicable to Waste Gas Storage Tank and Reactor

Building Purge release.

Obtain representative sample of gas to be released.

AND Analyze sample for principal gamma emitters.

AND

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

Only applicable to Reactor Building Purge release.

Perform H-3 analysis of sample.

Prior to release

ARKANSAS NUCLEAR ONE ODCM Revision 20 60 L 2.4.1 SURVEILLANCES (continued) SURVEILLANCE FREQUENCY S 2.4.1.2 -----------------------------------NOTE------------------------------------

Only applicable to Auxiliary Building, Spent Fuel Pool Area, Auxiliary Building Extension Area (ANO-2), Low Level

Radwaste Building, Emergency Penetration Room, and

Reactor (Containment) Building Ventilation systems.

The following effluent samples shall be obtained to support

the radioactive analysis specified:

a. ------------------------------------NOTE-------------------------------

Only applicable to Reactor Building Ventilation when

Reactor Vessel Head is removed.

Representative sample for H-3 analysis.

b. ------------------------------------NOTE-------------------------------

Only applicable to Spent Fuel Pool Area Ventilation.

Representative sample for H-3 analysis.

c. Charcoal sample for I-131 analysis.

d. Particulate sample for principal gamma emmiters analysis.

e. Particulate sample for composite gross alpha analysis.

f. Representative sample for principal gamma emmiters analysis.

g. Representative sample for H-3 analysis.

h. Particulate sample of for Sr-89 and Sr-90 composite analysis.

AND (continued)

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

7 days

31 days

92 days

(continued)

ARKANSAS NUCLEAR ONE ODCM Revision 20 61 S 2.4.1.2 (continued)

Complete analysis of above samples:

i. Samples a, b, c, and d

j. Samples e, f, and g

k. Sample h

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months following

sample acquisition

31 days following

sample acquisition

60 days following

sample acquisition

S 2.4.1.3 Record SPING Noble Gas activity.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

S 2.4.1.4 Using data acquired by performance of S 2.4.1.1 and S.2.4.1.2, verify Limitations L 2.4.1.a through L 2.4.1.d

continue to be met.

31 days

S 2.4.1.5 Using data acquired by performance of S 2.4.1.1 and S.2.4.1.2, verify the limits of 40 CFR 190 are not projected to

be exceeded.

31 days

S 2.4.1.6 Verify the following LLDs are met:

Principal gamma emitters (gaseous) 1 x 10

-4 µCi/ml Principal gamma emitters (particulate) 1 x 10

-11 µCi/ml I-131 1 x 10

-12 µCi/ml H-3 1 x 10

-6 µCi/ml Gross alpha 1 x 10

-11 µCi/ml Sr-89 and Sr-90 1 x 10

-11 µCi/ml Noble gas (dose equivalent Xe-133) 1 x 10

-6 µCi/ml 12 months

ARKANSAS NUCLEAR ONE ODCM Revision 20 62 L 2.5 RADIOLOGICAL ENVIRONMENTAL MONITORING

L 2.5.1 The following environmental sample locations shall be designated and maintained:

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

Other instruments may be used in place of, or in addition to, integrating dosimeters.

Pathway / Sample Type # Location 2 Samples close to site boundary in or near different sectors having the highes t calculated annual average ground-level D/Q 1 Sample from the vicinity of a community having the highest calculated annual average ground-level D/Q Airborne Radionuclide and Particulate 1 Background information sample from a control location 10-20 miles from one reactor building 16 Inner ring stations with 2 or more dosimeters in each meteorological sector in the general area of the site

boundary Direct Radiation 8 Stations with 2 or more dosimeters in special interest areas such as population centers, nearby residences, schools, and in 1-2 areas to serve as control locations. 1 Indicator location influenced by plant discharge Surface Water 1 Control location uninfluenced by plant discharge 1 Indicator location influenced by plant discharge Drinking Water 1 Control location uninfluenced by plant discharge 1 Indicator location influenced by plant discharge Shoreline Sediment 1 Control location uninfluenced by plant discharge 1 Indicator location influenced by plant discharge Waterborne Ground Water 1 Control location uninfluenced by plant discharge 1 Indicator location within 5 miles of one reactor, if commercially available Milk 1 Control location > 5 miles from one reactor when an indicator exists 1 Sample of commercially and/or recreationally important species in vicinity of plant discharge Fish 1 Sample of same species in area not influenced by plant discharge 1 Sample of broadleaf (edible or inedible) near the site boundary from one of the highest anticipated annual

average ground-level D/Q sectors Ingestion Food Products 1 Sample location of broadleaf vegetation (edible or inedible) from a control location 10-20 miles from one

reactor ARKANSAS NUCLEAR ONE ODCM Revision 20 63 L 2.5.1 APPLICABILITY: At all times.

ACTIONS

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

Separate Condition entry is allowed for each sample location and Surveillance requirement.

-- CONDITION REQUIRED ACTION COMPLETION TIME A. Sample location requirement not met.

OR Required sample

equipment non-functional.

OR Sample Frequency not met.

OR Sample analysis

Frequency not met.

OR One or more Lower Limit(s)

of Detection (LLD) listed in

Table 2.5-1 not met.

OR One or more limits listed in

Table 2.5-2 not met.

OR Dose to a MEMBER OF

THE PUBLIC from

radionuclides other than

those listed in Table 2.5-2

projected to exceed

calendar year limits of

L 2.3.1 and/or L 2.4.1.

A.1 Initiate action to restore to within limits.

AND A.2 Initiate a condition report to document and track the

condition for inclusion in the

Annual Radiological

Environmental Operating

Report pursuant to TS 5.6.2 (ANO-1) / TS 6.6.2 (ANO-2).

Immediately

ARKANSAS NUCLEAR ONE ODCM Revision 20 64 L 2.5.1 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. Sample(s) from required sample location(s)

unavailable.

B.1 Identify and add to the Radiological Environment

Monitoring Program, locations for obtaining

replacement samples.

30 days SURVEILLANCES SURVEILLANCE FREQUENCY S 2.5.1.1 -----------------------------------NOTE------------------------------------

Only applicable to Airborne Radionuclide and Particulate.

Collect sample from continuous sampler.

AND Perform I-131 analysis of radioiodine canister.

AND Perform gross beta analysis of particulate sampler.

14 days

14 days following

sample acquisition

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and 14 days following filter change

S 2.5.1.2 -----------------------------------NOTE------------------------------------

Only applicable to Direct Radiation locations.

Collect sample from required location.

AND Perform gamma dose analysis of sample.

92 days

60 days following

sample acquisition

ARKANSAS NUCLEAR ONE ODCM Revision 20 65 L 2.5.1 SURVEILLANCES (continued) SURVEILLANCE FREQUENCY S 2.5.1.3 -----------------------------------NOTE------------------------------------

Only applicable to Surface Water samples.

Collect sample from required location.

AND Perform gamma isotopic analysis of sample.

AND Perform H-3 analysis of sample.

92 days

21 days following

sample acquisition

31 days following

sample acquisition

S 2.5.1.4 -----------------------------------NOTE------------------------------------

Only applicable to Drinking and Ground Water samples.

Collect sample from required location.

AND Perform gamma isotopic analysis of sample.

AND Perform H-3 analysis of sample.

AND Perform I-131 analysis of sample.

AND Perform gross beta analysis of sample.

92 days

21 days following

sample acquisition

31 days following

sample acquisition

21 days following

sample acquisition

31 days following

sample acquisition

ARKANSAS NUCLEAR ONE ODCM Revision 20 66 L 2.5.1 SURVEILLANCES (continued) SURVEILLANCE FREQUENCY S 2.5.1.5 -----------------------------------NOTE------------------------------------

Only applicable to Waterborne Shoreline Sediment samples.

Collect sample from required location.

AND Perform gamma isotopic analysis of sample.

12 months

60 days following

sample acquisition

S 2.5.1.6 -----------------------------------NOTE------------------------------------

Only applicable to Milk samples.

Collect sample from required location.

AND Perform gamma isotopic analysis of sample.

AND Perform I-131 analysis of sample.

92 days

21 days following

sample acquisition

21 days following

sample acquisition

S 2.5.1.7 -----------------------------------NOTE------------------------------------

Only applicable to edible portions of Fish samples.

Collect sample from required location.

AND Perform gamma isotopic analysis of sample.

12 months

60 days following

sample acquisition

ARKANSAS NUCLEAR ONE ODCM Revision 20 67 L 2.5.1 SURVEILLANCES (continued) SURVEILLANCE FREQUENCY S 2.5.1.8 ----------------------------------NOTES----------------------------------- 1. Only applicable to Food Product samples.

2. Only applicable if Milk sampling not performed.

Collect sample from required location.

AND Perform gamma isotopic analysis of sample.

AND Perform I-131 analysis of sample.

12 months

21 days following

sample acquisition

21 days following

sample acquisition

S 2.5.1.9 Verify the LLDs listed in Table 2.5-1 are met.

12 months

S 2.5.1.10 Verify radioactivity concentrations are less than or equal to the limits listed in Table 2.5-2, when averaged over a

calendar quarter.

92 days

ARKANSAS NUCLEAR ONE ODCM Revision 20 68 L 2.5.1 TABLE 2.5-1 MAXIMUM VALUES OF THE LOWER LIMITS OF DETECTION (LLD)

Analyses Water (pCi/l) Airborne Particulate or Gas (pCi/m 3) Fish (pCi/kg, wet)

Milk (pCi/l)

Food Products (pCi/kg, wet)

Sediment (pCi/kg, dry) Gross Beta 4 (a) 1 x 10-2(b) H-3 2000 (c) Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15

I-131 1 (d) 7 x 10-2(e) 1 60 Cs-134 15 5 x 10

-2(f) 130 15 60 150 Cs-137 18 6 x 10

-2(f) 150 18 80 180 Ba-140 60 60 La-140 15 15 (a) LLD for drinking water. (b) Only applicable to particulate. (c) LLD for drinking water. When no drinking water pathway exists, a value of 3000 pCi/l may be used. (d) LLD for drinking water. When no drinking water pathway exists, a gamma isotopic analysis LLD value of 15 pCi/l may be used. (e) Only applicable to gas. (f) Only applicable to particulate gamma isotopic analysis.

ARKANSAS NUCLEAR ONE ODCM Revision 20 69 L 2.5.1 TABLE 2.5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Analyses Water (pCi/l)

Airborne Particulate or Gas (pCi/m 3) Fish (pCi/kg, wet) Milk (pCi/l) Food Products (pCi/kg, wet) H-3 2 x 10 4(a) Mn-54 1 x 10 3 3 x 10 4 Fe-59 4 x 10 2 1 x 10 4 Co-58 1 x 10 3 3 x 10 4 Co-60 3 x 10 2 1 x 10 4 Zn-65 3 x 10 2 2 x 10 4 Zr-95, Nb-95 4 x 10 2(b) I-131 2 (c) 0.9 3 1 x 10 2 Cs-134 30 10 1 x 10 3 60 1 x 10 3 Cs-137 50 20 2 x 10 3 70 2 x 10 3 Ba-140, La-140 2 x 10 2(b) 3 x 10 2(b) (a) Drinking water samples. (b) Total for parent and daughter. (c) LLD for drinking water. When no drinking water pathway exists, a value of 20 pCi/l may be used.

ARKANSAS NUCLEAR ONE ODCM Revision 20 70 L 2.5 RADIOLOGICAL ENVIRONMENTAL MONITORING

L 2.5.2 -----------------------------------------------------NOTE---------------------------------------------------

Broad leaf vegetation sampling may be performed at the site boundary in the directional sector with the highest D/Q in lieu of the garden census.

The location of the nearest milk animal, the nearest residence, and the nearest

garden of greater than 500 ft 2 producing fresh leafy vegetables in each of the 16 meteorological sectors within a 5 mile distance from one reactor (containment)

building shall be identified.

APPLICABILITY: At all times.

ACTIONS

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

Separate Condition entry is allowed for each sample location.

-- CONDITION REQUIRED ACTION COMPLETION TIME A. New sample location identified which yields a

calculated dose due to

I-131, H-3, and/or

particulates projected to

exceed 40 CFR 190 limits.

OR New sample location

identified which yields a

calculated dose via the

same exposure pathway in

excess of values calculated

at sample locations of

Limitation L 2.51.

A.1 Initiate a condition report to document and track the

condition for inclusion in the

Annual Radiological

Environmental Operating

Report pursuant to TS 5.6.2 (ANO-1) / TS 6.6.2 (ANO-2).

AND A.2.1 Identify and add the new sample location to the

Radiological Environment

Monitoring Program.

AND A.2.2 Delete the previous sample location via the

associated exposure

pathway from the

Radiological Environment

Monitoring Program.

Immediately

30 days

Within 90 days

following October 31

of the year in which

the new sample

location was

identified.

ARKANSAS NUCLEAR ONE ODCM Revision 20 71 L 2.5.2 SURVEILLANCES

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

S 2.0.2 is not applicable to the Surveillances of this Limitation.

SURVEILLANCE FREQUENCY S 2.5.2.1 A land use census to identify the locations described in Limitation L 2.5.2 shall be performed by door-to-door survey, aerial survey, or by consulting local agricultural authorities.

24 months between

June 1 and

October 1

S 2.5.2.2 Include the results of S 2.5.2.1 in the Annual Radiological Environmental Operating Report pursuant to TS 5.6.2 (ANO-1) / TS 6.6.2 (ANO-2).

12 months

ARKANSAS NUCLEAR ONE ODCM Revision 20 72 L 2.5 RADIOLOGICAL ENVIRONMENTAL MONITORING

L 2.5.3 Radioactive materials supplied as part of the Interlaboratory Comparison Program shall be analyzed.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Limitation not met.

A.1 Initiate a condition report to document and track the

condition for inclusion in the

Annual Radiological

Environmental Operating

Report pursuant to TS 5.6.2 (ANO-1) / TS 6.6.2 (ANO-2).

Immediately

SURVEILLANCES

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

S 2.0.2 is not applicable to the Surveillances of this Limitation.

SURVEILLANCE FREQUENCY S 2.5.3.1 Include the results of analyses performed as part of the Interlaboratory Comparison Program in the next Annual

Radiological Environmental Operating Report pursuant to TS 5.6.2 (ANO-1) / TS 6.6.2 (ANO-2).

12 months

ARKANSAS NUCLEAR ONE ODCM Revision 20 73 B 2.0 LIMITITATION (L) APPLICABILITY BASES Limitations L 2.0.1 through L 2.0.5 establish the general requirements applicable to all Limitations and apply at all times, unless otherwise stated.

B 2.0.1 L 2.0.1 establishes the Applicability statement within each individual Limitation as the requirement for when the Limitation is required to be met (i.e., when the

unit is in the MODES or other specified conditions of the Applicability statement

of each Limitation).

B 2.0.2 L 2.0.2 establishes that upon discovery of a failure to meet a Limitation, the associated ACTIONS shall be met. The Completion Time of each Required

Action for an ACTIONS Condition is applicable from the point in time that an

ACTIONS Condition is entered. The Required Actions establish those remedial

measures that must be taken within specified Completion Times when the

requirements of a Limitation are not met. This Limitation establishes that:

a. Completion of the Required Actions within the specified Completion Times constitutes compliance with a Limitation; and

b. Completion of the Required Actions is not required when a Limitation is met within the specified Completion Time, unless otherwise specified.

Completing the Required Actions is not required when a Limitation is no longer

applicable, unless otherwise stated in the individual Specification.

B 2.0.3 L 2.0.3 establishes the Required Actions that must be implemented when a Limitation is not met and the condition is not specifically addressed by the

associated Conditions. It is not intended to be used as an operational

convenience that permits routine voluntary removal of redundant systems or

components from service in lieu of other al ternatives that would not result in redundant systems or components being inoperable. This requirement is

intended to provide assurance that plant management is aware of the condition

and to ensure that the condition is evaluated for its affect on continued

operation of the plant.

B 2.0.4 L 2.0.4 establishes Limitations on changes in MODES or other specified conditions in the Applicability when a Limitation is not met. It allows placing the

unit in a MODE or other specified condition stated in that Applicability (e.g., the

Applicability desired to be entered) when unit conditions are such that the

requirements of the Limitation would not be met, in accordance with Limitation

L 2.0.4.a, L 2.0.4.b, or L 2.0.4.c.

ARKANSAS NUCLEAR ONE ODCM Revision 20 74 BASES LIMITATION APPLICABILITY (continued)

B 2.0.4 L 2.0.4 allows entry into a MODE or other specified condition in the (continued) Applicability with the Limitation not met when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in

the Applicability for an unlimited period of time. Compliance with Required

Actions that permit continued operation of the unit for an unlimited period of

time in a MODE or other specified condition provides an acceptable level of

safety for continued operation. This is without regard to the status of the unit

before or after the MODE change. Therefore, in such cases, entry into a MODE

or other specified condition in the Applicability may be made in accordance with

the provisions of the Required Actions. The provisions of this Limitation should

not be interpreted as endorsing the failure to exercise the good practice of

restoring systems or components to FUNCTIONAL status before entering an

associated MODE or other specified condition in the Applicability.

Upon entry into a MODE or other specified condition in the Applicability with the

Limitation not met, L 2.0.1 and L 2.0.2 require entry into the applicable

Conditions and Required Actions until the Condition is resolved, until the

Limitation is met, or until the unit is not within the Applicability of the Limitation.

Surveillances do not have to be performed on the associated inoperable

equipment (or on variables outside the specified limits), as permitted by S 2.0.1.

Therefore, utilizing L 2.0.4 is not a violation of S 2.0.1 or S 2.0.4 for any

Surveillances that have not been performed on equipment. However, Surveillances must be met to ensure FUNCTIONALITY prior to declaring the

associated equipment FUNCTIONAL (or variable within limits) and restoring

compliance with the affected Limitation.

B 2.0.5 L 2.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared non-functional to comply with ACTIONS. The sole purpose of this Limitation is to

provide an exception to L 2.0.2 (e.g., to not comply with the applicable Required

Actions) to allow the performance of required testing to demonstrate:

a. The FUNCTIONALITY of the equipment being returned to service; or

b. The FUNCTIONALITY of other equipment.

The administrative controls ensure the time the equipment is returned to service

in conflict with the requirements of the ACTIONS is limited to the time absolutely

necessary to perform the required testing to demonstrate FUNCTIONALITY.

This Limitation does not provide time to perform any other preventive or

corrective maintenance.

An example of demonstrating the FUNCTIONALITY of the equipment being

returned to service is restarting a ventilation system that has been secured to

comply with Required Actions and must be restarted to perform the required

testing.

ARKANSAS NUCLEAR ONE ODCM Revision 20 75 B 2.0 SURVEILLANCE (S) APPLICABILITY BASES S 2.0.1 SRs shall be met during the MODES or other specified conditions in the Applicability for individual Limitations, unless otherwise stated in the individual

Surveillance. Failure to meet a Surveillance, whether such failure is

experienced during the performance of the Surveillance or between

performances of the Surveillance, shall be failure to meet the Limitation. Failure

to perform a Surveillance within the specified Frequency shall be failure to meet

the Limitation except as provided in S 2.0.3. Surveillances are not required to

be performed on non-functional equipment or variables outside specified limits.

S 2.0.2 The specified Frequency for each Surveillance is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as

measured from the previous performanc e or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as "once," the above interval extension does not

apply. If a Completion Time requires periodic performance on a "once per . . ." basis, the above Frequency extension applies to each performance after the initial

performance.

Exceptions to this Limitation are stated in the individual Limitations.

S 2.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the Limitation not

met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit

of the specified Frequency, whichever is greater. This delay period is permitted

to allow performance of the Surveillance.

If the Surveillance is not performed within the delay period, the Limitation must

immediately be declared not met, and the applicable Condition(s) must be

entered. When the Surveillance is performed within the delay period and the Surveillance

is not met, the Limitation must immediately be declared not met, and the

applicable Condition(s) must be entered.

S 2.0.4 Entry into a MODE or other specified condition in the Applicability of a Limitation shall only be made when the Limitation's Surveillances have been met within

their specified Frequency, except as provided by S 2.0.3. When a Limitation is

not met due to Surveillances not having been met, entry into a MODE or other

specified condition in the Applicability shall only be made in accordance with

L 2.0.4.

ARKANSAS NUCLEAR ONE ODCM Revision 20 76 B 2.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

BASES BACKGROUND The Radioactive Liquid Effluent Monitoring Instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential

releases.

LIMITATION

The following Radioactive Liquid Effluent Monitoring Instrumentation is required to be

FUNCTIONAL:

ANO-1: RE-4642 - Liquid Radwaste Monitor RE-2682 - "A" Main Steam Line Radiation Monitor RE-2681 - "B" Main Steam Line Radiation Monitor ANO-2: 2RE-2330 - Liquid Radwaste Monitor 2RE-4423 - Liquid Radwaste Monitor Both radiation monitoring and flow monitoring capability are required to be FUNCTIONAL for

each Liquid Radwaste Monitor. With regard to Liquid Radwaste radiation monitoring, the

alarm/trip function must also be FUNCTIONAL. The alarm/trip setpoints for these instruments

are calculated in accordance with the methods contained in ODCM Section 2.1 to ensure that

the alarm/trip will occur prior to potentially exceeding the limits of 10 CFR Part 20.

With regard to the Main Steam Line Radiation Monitors, these monitors must have a

measurement range capability from 10

-1 mR/hr to 10 4 mR/hr.

APPLICABILITY

The Liquid Radwaste Monitors are required to be FUNCTIONAL during any release via the

pathway in which the monitor is installed. The Main Steam Line Radiation Monitors are

required to be FUNCTIONAL in MODES 1, 2, 3, and 4.

ACTIONS The following ACTIONS are generally applicable to the pathway in which a radioactive liquid

release is in progress. Because more than one release could occur simultaneously, the

ACTIONS are modified by a Note that permits separate Condition entry for each non-functional

Radioactive Liquid Effluent Monitoring Instrument.

ARKANSAS NUCLEAR ONE ODCM Revision 20 77 B 2.1 ACTIONS (continued)

A.1 If the radiation monitoring feature of the Radioactive Liquid Effluent Monitoring Instrument is

non-functional, any release via the associated pathway must be suspended immediately. This

prevents the release of unmonitored effluents to the environment.

A.2.1 In addition to Required Action A.1, a non-functional radiation monitoring feature of a

Radioactive Liquid Effluent Monitoring Instrument must be returned to a FUNCTIONAL status

prior to the restart or subsequent release of effluents via the associated pathway. This

prevents the release of unmonitored effluents to the environment. Exceptions to this requirement are included in Required Actions A.2.2.1 through A.2.2.3 below.

A.2.2.1 through A.2.2.3 In lieu of performing Required Action A.2.1 above, grab samples may be obtained and

analyzed to provide a backup monitoring method for the effluent release. Because of the

importance of monitoring radioactive liquid releases, two independent samples of the effluent

must be obtained and analyzed. The independency required is with regard to obtaining and

analyzing each sample separately. Two independent personnel are not required to obtain and

analyze the two samples.

Notwithstanding the above, computer input data and the discharge valve lineup associated

with the effluent release path must be verified by two independent, qualified individuals.

Integrity of independence is maintained by preventing interaction between personnel during

the verification process. With regard to valve lineups, independent verification is conducted

such that each check constitutes actual identification of the valve and a determination of both

"required" and "actual" valve position.

B.1 and B.2 If the flow monitoring feature of the Radioactive Liquid Effluent Monitoring Instrument is non-

functional, the flow rate may be estimated within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of initial loss of the instrument and

every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter, for the duration of the effluent release. Flow rate data is necessary to

calculate the amount of radioactive released via the effluent discharge. The 4-hour

Completion Time is reasonable because a significant change in flow rate over the course of an

effluent release is unlikely.

S 2.0.2 is not applicable to the initial flow estimation, but may be applied to the flow

estimations thereafter. Pump curves may be used to estimate flow.

ARKANSAS NUCLEAR ONE ODCM Revision 20 78 B 2.1 ACTIONS (continued)

C.1 If one or more Main Steam Line Radiation Monitors is non-functional, the pre-planned alternate

monitoring method of monitoring must be established within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . The alternate method

chosen should ensure continued monitoring of the Main Steam system for radiation while

operating in MODES 1, 2, 3, or 4. In addition, the affected monitor(s) must be restored to a

FUNCTIONAL status within 7 days.

D.1 If the Required Actions and associated Completion Times of Conditions A, B, and/or C cannot

be met, then additional measures may be necessary to ensure continued safe operation or to

reduce overall station risk. Therefore, a condition report must be initiated immediately to

assess the impact on continued effluent release operations given the degraded condition.

E.1 Instrumentation installed to ensure radiological monitoring of effluent releases is expected to

be normally available in accordance with the design function or purpose of the equipment.

Instrumentation that remains non-functional for greater than 30 days may indicate

inappropriate importance placed on the equipment or over-reliance on the backup sampling

method for effluent release monitoring. As an incentive to avoid either of these conditions, Radioactive Liquid Effluent Monitoring Instrumentation that remains non-functional for more

than 30 days must be included in the Radioactive Effluent Release Report submitted pursuant

to TS 5.6.3 (ANO-1) or TS 6.6.3 (ANO-2). In order to ensure inclusion, Required Action E.1

requires the condition to be tracked via a condition report.

Information to be provided in the respective Radioactive Effluent Release Report should

include 1) the component number and noun name, 2) the failure mode, 3) the reason for

continued inoperability, and 4) the expected return to service date.

SURVEILLANCES

S 2.1.1.1 Performance of the CHANNEL CHECK every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months provides reasonable assurance for

prompt identification of a gross failure of instrumentation. A CHANNEL CHECK is normally a

comparison of the parameter indicated on one channel to a similar parameter on other

channels. Where parameter comparison is not possible, the CHANNEL CHECK will continue

to identify gross instrument failure such as loss of power, unexpected upscale readings, failed-

low indications, etc. The CHANNEL CHECK is key in verifying that the instrumentation

continues to operate properly between CHANNEL CALIBRATIONs. The Frequency is based

on unit operating experience that demonstrates channel failure is rare.

ARKANSAS NUCLEAR ONE ODCM Revision 20 79 B 2.1 SURVEILLANCES (continued)

S 2.1.1.2 A CHANNEL TEST is performed on the radiation monitoring portion of each required

instrument channel to ensure the entire channel will perform the intended functions. The

CHANNEL TEST demonstrates that automatic isolation of the associated pathway and Control

Room alarm occur should the instrument indicate measured levels above the trip setpoint.

The channel test also demonstrates that alarm occurs when any of the following conditions

exist: A. Power to the detector is lost.

B. The instrument indicates a downscale failure.

C. Instrument controls are not set in the operate mode.

Any setpoint adjustment shall be consistent with Section 2.1 of the ODCM.

The Surveillance is modified by a Note clarifying that the CHANNEL TEST is applicable only to

the radiation detection portion of the monitor function and is not applicable to the flow

monitoring function. The Frequency of 92 days is based on unit operating experience, with

regard to channel FUNCTIONALITY and drift, which demonstrates that failure of a channel in

any 92-day interval is a rare event, especially in light of the infrequency of radioactive liquid

releases.

S 2.1.1.3 CHANNEL CALIBRATION is a complete check of the instrument channel, including the

sensor. The test verifies that the channel responds to a measured parameter within the

necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to

account for instrument drift (as required) to ensure that the instrument channel remains

FUNCTIONAL between successive tests. CHANNEL CALIBRATION shall find that

measurement errors and setpoint errors are within the assumptions of the setpoint

calculations. CHANNEL CALIBRATIONS must be performed consistent with the assumptions

of the setpoint calculations. This Frequency is justified by the assumption of at least an

18 month calibration interval to determine the m agnitude of equipment drift or deviation in the setpoint calculations.

Initial CHANNEL CALIBRATION is performed using one or more of the reference standards

certified by the National Institute of Standards and Technology (NIST) or using standards that

have been obtained from suppliers that participate in measurement assurance activities with

NIST. These standards permit calibrating the system over its intended range of energy and

measurement range. For subsequent CHANNEL CALIBRATION, sources that have been

related to the initial calibration are used.

ARKANSAS NUCLEAR ONE ODCM Revision 20 80 B 2.1 SURVEILLANCES (continued)

S 2.1.1.4 A SOURCE CHECK provides a qualitative assessment of channel response when the channel

sensor is exposed to the radioactive source. This check is performed within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to

release of effluent via the associated flow path. When a SOURCE CHECK can be performed, it provides verification that the sensor will respond to an increase in radiation level. Note 1, however, does not require a SOURCE CHECK when the background radiation at the sensor is

greater than the check source. This is acceptable because of the other required tests above (CHANNEL CHECK, CHANNEL TEST, CHANNEL CALIBRATION). The 8-hour restriction is

reasonable because it is unlikely that the sensor will unexpectedly fail in any 8-hour period.

Note 2 provides clarification that the SOURCE CHECK applies only to the radiation detection

portion of the Liquid Radwaste Monitor and is not applicable to the flow monitor portion or to

the Main Steam Line Radiation Monitors.

ARKANSAS NUCLEAR ONE ODCM Revision 20 81 B 2.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

BASES BACKGROUND The Radioactive Gaseous Effluent Monitoring Instrumentation is provided to monitor and

control, as applicable, the releases of radioactive materials in gaseous effluents during actual

or potential releases.

LIMITATION The following Radioactive Gaseous Effluent Monitoring Instrumentation is required to be

FUNCTIONAL:

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

Refer to ANO-2 Technical Specification (TS) 3.3.3.1 for ANO-2 Containment Building Purge

System Process Monitor (2RE-8233) operab ility requirements and associated ACTIONS.

ANO-1: RE-4830 - Waste Gas Holdup System Process Monitor* RX-9820 - Reactor Building Purge and Ventilation SPING RX-9825 - Auxiliary Building Ventilation SPING RX-9830 - Spent Fuel Pool Area Ventilation SPING RX-9835 - Emergency Penetration Room Ventilation SPING ANO-2: 2RE-2429 - Waste Gas Holdup System Process Monitor* 2RX-9820 - Containment Building Purge and Ventilation SPING 2RX-9825 - Auxiliary Building Ventilation SPING 2RX-9830 - Spent Fuel Pool Area Ventilation SPING 2RX-9835 - Emergency Penetration Room Ventilation SPING 2RX-9845 - Auxiliary Building Extension Ventilation SPING 2RX-9850 - Radwaste Storage Building Ventilation SPING

These monitors provide automatic isolation.

The radiation monitoring (process gas and SPING noble gas) and effluent flow monitoring

capability are required to be FUNCTIONAL for each monitor. For SPING monitors the

sample flow monitoring, the iodine sample, and the particulate sampler must also be

FUNCTIONAL. With regard to Waste Gas Holdup System radiation monitoring, the alarm/trip

function must also be FUNCTIONAL. The alarm/trip setpoints for specified instruments are

calculated in accordance with the methods contained in ODCM Section 3.1 to ensure that the

alarm/trip will occur prior to potentially exceeding the limits of 10 CFR Part 20.105. Note that

the PURGE function of the ANO-1 and ANO-2 Reactor (Containment) Building is treated

separately from the ventilation function.

Performance of a SOURCE CHECK on a given radiation monitor does not require the monitor

to be declared non-functional due to the short period of time required to perform this test.

ARKANSAS NUCLEAR ONE ODCM Revision 20 82 B 2.2 APPLICABILITY The above monitors are required to be FUNCTIONA L during any release via the pathway in which the monitor is installed.

ACTIONS The following ACTIONS are applicable to the pathway in which a radioactive gaseous release

is in progress. Because more than one release could occur simultaneously, the ACTIONS are

modified by a Note that permits separate Condition entry for each non-functional Radioactive

Gaseous Effluent Monitoring Instrument.

A.1 If the radiation monitoring feature, including the alarm/trip function for monitors having an

automatic isolation feature, of the Waste Gas Holdup or ANO-1 Reactor Building Purge and

Ventilation System Gas Activity Process or Nobl e Gas Activity Monitor(s) is non-functional, any release via the associated pathway must be suspended immediately. This prevents the

release of unmonitored effluents to the environment.

A.2.1 In addition to Required Action A.1, a non-functional Waste Gas Holdup or Reactor Building

Purge and Ventilation System Gas Activity Proce ss or Noble Gas Activity Monitor, including the alarm/trip function for monitors having an automatic isolation feature, must be returned to a

FUNCTIONAL status prior to the restart or subsequent release of effluents via the associated

pathway. This prevents the release of unmonito red effluents to the environment. Exceptions to this requirement are included in Required Actions A.2.2.1 through A.2.2.3 below.

A.2.2.1 through A.2.2.3 In lieu of performing Required Action A.2.1 above, grab samples may be obtained and

analyzed to provide a backup monitoring method for the effluent release. Because of the

importance of monitoring radioactive gaseous releases, two independent samples of the

effluent must be obtained and analyzed. The independency required is with regard to

obtaining and analyzing each sample separately. Two independent personnel are not required

to obtain and analyze the two samples.

ARKANSAS NUCLEAR ONE ODCM Revision 20 83 B 2.2 ACTIONS (continued)

A.2.2.1 through A.2.2.3 (continued)

Notwithstanding the above, computer input data and the discharge valve lineup associated

with the effluent release path must be verified by two independent, qualified individuals.

Integrity of independence is maintained by preventing interaction between personnel during

the verification process. With regard to valve lineups, independent verification is conducted

such that each check constitutes actual identification of the valve and a determination of both

"required" and "actual" valve position. Required Action A.2.2.3 is modified by a Note that

excepts the valve lineup requirement from the Reactor Building Purge and Ventilation System since no manual valves are manipulated for this release path.

B.1 and B.2 If the flow monitoring features of the Radioactive Gaseous Effluent Monitoring Instrumentation is non-functional, the flow rate may be estimated within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of initial loss of the instrument

and every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter, for the duration of the effluent release. Flow rate data is

necessary to calculate the amount of radioactive released via the effluent discharge.

Therefore, if flow cannot be estimated, it is necessary to suspend the release of radioactive

effluents monitored by the affected channel. The 4-hour Completion Time is reasonable

because a significant change in flow rate over the course of an effluent release is unlikely.

S 2.0.2 is not applicable to the initial flow estimation, but may be applied to the flow

estimations thereafter. Pump curves may be used to estimate flow.

C.1 and C.2 With the exception of Waste Gas Holdup System releases or during a PURGE of the ANO-1 Reactor Building, releases may continue via an associated pathway when the Noble Gas

Activity Monitor(s) is non-functional, provided a sample of the effluent is obtained once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and analyzed within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . This prevents the release of

unmonitored effluents to the environment. AC TIONS C.1 and C.2 are modified by a note, referring to ANO-1 TS 3.9.3 for additional ACTIONS that may be necessary if the required

ANO-1 Reactor Building Purge and Ventilation System Noble Gas Activity Monitor is inoperable.

S 2.0.2 is not applicable to the initial sample and analysis, but may be applied to the sample

and analysis thereafter.

D.1, D.2, and D.2 If one or more required Iodine and/or Particulate Samplers are non-functional, auxiliary sampling equipment must be established within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The backup Iodine and Particulate

cartridges must be replaced every 7 days. Following replacement, the respective cartridge

must be analyzed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . This prevents the release of unmonitored effluents to the

environment.

ARKANSAS NUCLEAR ONE ODCM Revision 20 84 B 2.2 ACTIONS (continued)

E.1 If the Required Actions and associated Completion Times of Condition C and/or D cannot be

met, then releases via the associated pathway must be suspended. This prevents the release

of unmonitored effluents to the environment.

F.1 If the Required Actions and associated Completion Times of Condition A, B, and/or E cannot

be met, then additional measures may be necessary to ensure continued safe operation or to

reduce overall station risk. Therefore, a condition report must be initiated immediately to

assess the impact on continued effluent release operations given the degraded condition.

G.1 Instrumentation installed to ensure radiological monitoring of effluent releases is expected to

be normally available in accordance with the design function or purpose of the equipment.

Instrumentation that remains non-functional for greater than 30 days may indicate

inappropriate importance placed on the equipment or over-reliance on the backup sampling

method for effluent release monitoring. As an incentive to avoid either of these conditions, Radioactive Gaseous Effluent Monitoring Instrumentation that remains non-functional for more

than 30 days must be included in the Radioactive Effluent Release Report submitted pursuant

to TS 5.6.3 (ANO-1) or TS 6.6.3 (ANO-2). In order to ensure inclusion, Required Action G.1

requires the condition to be tracked via a condition report.

Information to be provided in the respective Radioactive Effluent Release Report should

include 1) the component number and noun name, 2) the failure mode, 3) the reason for

continued inoperability, and 4) the expected return to service date.

SURVEILLANCES

S 2.2.1.1 Performance of the CHANNEL CHECK every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months provides reasonable assurance for

prompt identification of a gross failure of instrumentation. A CHANNEL CHECK is normally a

comparison of the parameter indicated on one channel to a similar parameter on other

channels. Where parameter comparison is not possible, the CHANNEL CHECK will continue

to identify gross instrument failure such as loss of power, unexpected upscale readings, failed-

low indications, etc. The CHANNEL CHECK is key in verifying that the instrumentation

continues to operate properly between CHANNEL CALIBRATIONs. The Frequency is based

on unit operating experience that demonstrates channel failure is rare.

This Surveillance is modified by a Note the ex empts the Iodine and Particulate Samplers from a CHANNEL CHECK since these components do not have electronic features or indications.

ARKANSAS NUCLEAR ONE ODCM Revision 20 85 B 2.2 SURVEILLANCES (continued)

S 2.2.1.2 A local check must be made every 7 days to verify that required Iodine Sampler cartridges and

Particulate Sample filters are in place. The 7-day Frequency is reasonable because it is

unlikely a cartridge or filter could be i nadvertently removed from the system.

S 2.2.1.3 and S 2.2.1.6

A CHANNEL TEST is performed on required Gas Activity Process and Noble Gas Activity

Monitors to ensure the entire channel will perform the intended functions. For the Waste Gas

Holdup and ANO-2 Containment Building Purge Systems, the CHANNEL TEST demonstrates

that automatic isolation of the associated pathway and Control Room alarm occur should the

instrument indicate measured levels above the trip setpoint. The channel test also

demonstrates that alarm occurs when any of the following conditions exist: A. Power to the detector is lost.

B. The instrument indicates a downscale failure.

C. Instrument controls are not set in the operate mode.

Any setpoint adjustment shall be consistent with Section 3.1 of the ODCM.

Because the alarm/trip function and/or the importance of the release path, a CHANNEL TEST

of the associated Gas Activity Process and Noble Gas Activity Monitors is required within

31 days prior to release via the Waste Gas Holdup or ANO-1 Reactor Building Purge and

Ventilation Systems. This ensures the monitors are FUNCTIONAL within a reasonable period

of time before such a release is commenced. All active pathway Gas Activity Process and

Noble Gas Activity Monitors undergo a CHANNEL TEST once every 92 days. This Frequency

is reasonable because each has a Control Room alarm function.

S 2.2.1.4 and S 2.2.1.5

A SOURCE CHECK provides a qualitative assessment of channel response when the channel

sensor is exposed to the radioactive source. This check is performed within 14 days prior to

release of effluent via the Waste Gas Holdup or ANO-1 Reactor Building Purge Systems. The

14-day restriction is reasonable because it is unlikely that the sensor will unexpectedly fail in

any 14-day period. All active pathway Gas Acti vity Process and Noble Gas Activity Monitors must undergo a SOURCE CHECK every 31 days. This Frequency is reasonable because

each has a Control Room alarm function.

ARKANSAS NUCLEAR ONE ODCM Revision 20 86 B 2.2 SURVEILLANCES (continued)

S 2.2.1.4 and S 2.2.1.5 (continued)

When a SOURCE CHECK can be performed, it provides verification that the sensor will

respond to an increase in radiation level. Note 1 of S 2.2.1.5 and the Note associated with

S 2.2.1.4 does not require a SOURCE CHECK when the background radiation at the sensor is

greater than the check source. This is acceptable because of the other required tests above (CHANNEL CHECK, CHANNEL TEST, and CHANNEL CALIBRATION).

S 2.2.1.7 CHANNEL CALIBRATION is a complete check of the instrument channel, including the