ML13134A469

2012 Annual Radioactive Effluent Release Report

ML13134A469
Person / Time
Site:	Catawba
Issue date:	04/30/2013
From:	Henderson K Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13134A469 (57)

Text

Kelvin Henderson Vice President Catawba Nuclear Station

~ENERGY. 803-701-4251 Duke Energy CNOIVP 1 4800 Concord Rd.

York, SC 29745 April 30, 2013 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 2012 Annual Radioactive Effluent Release Report Pursuant to Catawba Nuclear Station Technical Specification (TS) 5.6.3 and Selected Licensee Commitment 16.11-16, please find attached the Annual Radioactive Effluent Release Report for the period of January 1, 2012, through December 31, 2012. In accordance with Catawba TS 5.5.1, the Offsite Dose Calculation Manual (ODCM) is included in this submittal.

Attachment 1 Summary of Gaseous and Liquid Effluents Report Attachment 2 Supplemental Information Attachment 3 Solid Waste Disposal Report Attachment 4 Meteorological. Data Attachment 5 Unplanned Offsite Releases Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (includes fuel cycle dose calculation results)

Attachment 7 Revisions to UFSAR Section 16.11, Radiological Effluent Controls Attachment 8 Revisions to the Radioactive Waste Process Control Program Manual (Compact Disc)* if changes to program Attachment 9 Information to Support the NEI Groundwater Protection Initiative Attachment 10 Inoperable Equipment Attachment 11 Radioactive Waste Systems Changes Enclosure 2012 Offsite Dose Calculation Manual (Compact Disc) fOr ct www.duke-energy.coml

U.S. Nuclear Regulatory Commission 2012 Annual Radioactive Effluent Release Report April 30, 2013 Page 2 Any questions concerning this report should be directed to Randy Hart at (803) 701-3622.

Kelvin Henderson Attachments and Enclosures (Process Control Program [PCP] Revision Compact Disc [CD]* if changes to program and Offsite Dose Calculation Manual [ODCM] Compact Disc [CD]* ifrevised from previous submittal) xc (with attachments and enclosures):

V. M. McCree Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 J. S. Kim NRC Project Manager U.S. Nuclear Regulatory Commission Mail Stop 8 C2 11555 Rockville Pike Rockville, MD 20852-2738 xc (with PCP CD only)

G. A. Hutto, III NRC Senior Resident Inspector

ATTACHMENT 1 Summary of Gaseous and Liquid Effluents Report This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents as outlined in Regulatory Guide 1.21, Revision 1, Appendix B.

TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Catawba Nuclear Station Units 1 & 2 REPORT FOR 2012 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

---

.-.-------.-.------

A. Fission and Activation Gases

1. Total Release Ci 8.19E-01 6.58E1-01 9.48E-01 8.10E-01 3.23E+00

2. Avg. Release Rate. pCi/sec 1.04E-01 8.37E-02 1.19E-01 1.02E-01 1.02E-01 B. Iodine-131

1. Total Release Ci O.OOE+00 O.OOE+OO O.OOE+0O O.OOE+O0O0.OOE+OO

2. Avg. Release Rate )ICi/sec O.OOE+00 O.OOE+00O0.OOE+0O O.OOE+0O O.OOE+OO C. Particulates Half Life >= 8 days

1. Total Release Ci O.OOE+00 O.OOE+O0O0.OOE+OO O.OOE+OO O.OOE+O0

2. Avg. Release Rate pCi/sec O.OOE+00 O.OOE+0O O.OOE+OO O.OOE+O0 O.OOE+0O D. Tritium

1. Total Release Ci 5.53E+01 5.60E+01 5.11E+01 5.67E+01 2.19E+02

2. Avg. Release Rate pCi/sec 7.03E+00 7.12E+00 6.43E+00 7.13E+00 6.93E+00 E. Carbon-14

1. Total Release Ci 4.79E+00 4.47E+00 5.44E+00 4.43E+00 1.91E+01

2. Avg. Release Rate pCi/sec 6.10E-01 5.69E-01 6.84E-01 5.57E-01 6.05E-01 F. Gross Alpha Radioactivity

1. Total Release Ci 0.OOE+00 O.OOE+OO O.OOE+O0O0.OOE+O0 0.OOE+OO

2. Avg. Release Rate pCi/sec 0.00E+00 O.OOE+0O O.OOE+OO O.OOE+O0O .001+00

TABLE IB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 GASEOUS EFFLUENTS - ELEVATED RELEASES - CONTINUOUS MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2012 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases

• • No Nuclide Activities **

2. lodines

• • No Nuclide Activities **

3. Particulates Half Life >= 8 days

• • No Nuclide Activities **........ ........ ........ ........ ........

4. Tritium

• • No Nuclide Activities **........ ........ ........ ........ ........

5. Carbon-14

• • No Nuclide Activities **........ ........ ........ ........ ........

6. Gross Alpha Radioactivity

• • No Nuclide Activities **

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 GASEOUS EFFLUENTS - ELEVATED RELEASES - BATCH MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2012 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases

• • No Nuclide Activities **

2. Iodines

• • No Nuclide Activities **

3. Particulates Half Life >= 8 days

• • No Nuclide Activities **

4. Tritium

• • No Nuclide Activities . .

5. Carbon-14

• • No Nuclide Activities **

6. Gross Alpha Radioactivity

• • No Nuclide Activities ** ........

TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2012 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases AR-41 Ci O.OOE+00 O.OOE+O0 0. OOE+O0 4.76E-05 4.76E-05 XE-133 Ci O.OOE+00 O . 0E+00 0. OOE+00 9.48E-05 9.48E-05 XE-135 Ci 0.0OE+0O 0.OOE+00 0.OOE+O0 9. 62E-06 9.62E-06 Totals for Period... Ci 0.0OE+00 0. OOE+O0 0. OOE+00 1. 52E-04 1. 52E-04

2. lodines

• • No Nuclide Activities **

3. Particulates Half Life >= 8 days

• • No Nuclide Activities ** ........

4. Tritium H-3 Ci 5.51E+01 5.59E+01 5.10E+01 5.65E+01 2.18E+02

5. Carbon-14 C-14 Ci 1.44E+00 1.34E+00 1.63E+00 1.33E+00 5.74E+00

6. Gross Alpha Radioactivity

• • No Nuclide Activities **

TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2012 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases AR-41 Ci 7.06E-01 5.07E-01 7.07E-01 6.17E-01 2.54E+00 KR-85 Ci 9.38E-04 O.0OE+00 0..QOE+00 0. OOE+0O 9.38E-04 XE-133 Ci 1.06E-01 1.42E-01 2. 30E-01. 1. 79E-01 6.57E-01 XE-135 Ci 5.26E-03 8.54E-03 1.13E-02 1.41B-02 3.92E-02 Totals for Period... Ci 8.19E-01 6.58E-01 9.48E-01 8. lOE-01 3.23E+00

2. lodines

• • No Nuclide Activities **

3. Particulates Half Life >= 8 days

• • No Nuclide Activities **........ ........ ........ ........ ........

4. Tritium H-3 Ci 1.22E-01 9.44E-02 1.57E-01 2.08E-01 5.B1E-01

5. Carbon-14 C-14 Ci 3.36E+00 3.13E+00 3.81E+00 3.10E+00 1.34E+01

6. Gross Alpha Radioactivity

• • No Nuclide Activities **

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Catawba Nuclear Station Units 1 & 2 REPORT FOR 2012 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

---

.-.-------.-.------ ---------.-.-------.-.------

A. Fission and Activation Products

1. Total Release Ci 1.32E-02 3.86E-03 5.17E-03 5.63E-03 2.79E-02

2. Average Diluted Concentration

a. Continuous Releases pCi/ml O.00E+00 0.00E+00 0.00E+00 0.OOE+00 0. 00E+00

b. Batch Releases pCi/ml 4.75E-10 1.30E-10 1.41E-10 1.97E-10 2.27E-10 B. Tritium

1. Total Release Ci 2.88E+02 1.27E+02 1.46E+02 2.00E+02 7. 62E+02

2. Average Diluted Concentration

a. Continuous Releases pCi/ml 1.24E-07 0.00E+00 0.OOE+00 0.00E+00 2.85E-08

b. Batch Releases pCi/ml 1.04E-05 4.27E-06 4.OOE-06 7.OOE-06 6.21E-06 C. Dissolved and Entrained Gases

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

2. Average Diluted Concentration

a. Continuous Releases lxCi/ml O.OOE+00 0.00E+00 O.00E+00 0.00E+00 0.00E+00

b. Batch Releases pCi/ml 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0. 00E+00 D. Gross Alpha Radioactivity

1. Total Release Ci 0.OOE+00 0. 00E÷00 0.00E+00 0.00E+00 0. OOE+00

2. Average Diluted Concentration

a. Continuous Releases pCi/ml O.00E+00 0.00E+00 0.OOE+00 0.00E+00 0. 00E+00

b. Batch Releases pCi/ml 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E. Volume of Liquid Waste

1. Continuous Releases liters 5.83E+07 0.00E+00 0.00E+00 0.OOE+00 5.83E+07

2. Batch Releases liters 1.03E+06 7.16E+05 1.08E+06 9.84E+05 3.81E+06 F. Volume of Dilution Water

1. Continuous Releases liters 2.78E+09 2.97E+09 3.66E+09 2.86E+09 1.23E+10

2. Batch Releases liters 2.78E+10 2.97E+10 3.66E+10 2.86E+10 1.23E+11

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 LIQUID EFFLUENTS - CONTINUOUS MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2012 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Products

• • No Nuclide Activities **

2. Tritium H-3 Ci 3.51E-01 O.OOE+00 O.OOE+00 0.OOE+00 3.51E-01

3. Dissolved and Entrained Gases

• • No Nuclide Activities **

4. Gross Alpha Radioactivity

• • No Nuclide Activities **

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 LIQUID EFFLUENTS - BATCH MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2012 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Products AG-I10M Ci 5.86E-06 0. OOE+00 7.09E-06 1.86E-04 1. 98E-04 BE-7 Ci 4. 39E-04 0. OOE+00 O.OOE+00 0.OOE+00 4. 39E-04 BI-214 Ci 1. 69E-06 0. OOE+00 4.56E-06 5.57E-06 1. 1BE-05 CO-57 Ci 8. 63E-06 0.009+00 3.08E-06 0.OOE+00 1. 17E-05 CO-58 Ci 2.17E-03 2.33E-03 2.65E-03 4.41E-04 7.59E-03 CO-60 Ci 8.53E-03 1. 08E-03 2.18E-03 2.OOE-03 1. 38E-02 CR-51 Ci 4. 99E-04 1. 47E-04 2.92E-05 8.63E-04 1. 54E-03 CS-136 Ci 3.96E-06 0. OOE+00 0.OOE+00 0.OOE+00 3. 96E-06 CS-137 Ci 4. 41E-05 0. O0E+00 1.13E-06 1.91E-05 6.49E-05 FE-59 Ci 1. 14E-04 1.28E-05 0.OOE+00 0.OOE+00 1.27E-04 K-40 Ci 0.Q0OE+0o 0. OOE+00 0.OOE+00 3.26E-06 3.26E-06 MN-54 Ci 3.03E-04 2. OOE-05 4.04E-05 3.22E-05 3.96E-04 NB-95 Ci 0.00OE+0Q 0 .OOE+00 2.1.3E-05 2.80E-07 2.16E-05 NB-97 Ci 3.03E-05 0. OOE+00 O.OOE+00 0.OOE+00 3.03E-05 PB-214 Ci 1. 31E-05 1.28E-06 3.79E-06 1.16E-05 2. 97E-05 SB-124 Ci 1. 21E-05 9.57E-06 0.OOE+00 2.33E-04 2. 54E-04 SB-125 Ci 8.7 6E-04 2. 39E-04 2.08E-04 1.84E-03 3.16E-03 SE-126 Ci 0.OOE+00 0. OOE+00 0.00E+00 2.55E-06 2. 55E-06 SE-75 ci 7. 84E-06 0.00E+00 0.OOE+00 0.OOE+00 7. 84E-06 ZN-65 Ci 1. 38E-04 3.04E-05 4.89E-06 6.89E-07 1. 74E-04 ZR-95 Ci 0.OOE+00 0. OOE+00 1.OOE-05 0.OOE+00 1. OOE-05 Totals for Period... Ci 1.32E-02 3.86E-03 5.17E-03 5.63E-03 2.79E-02

2. Tritium H-3 Ci 2.88E+02 1.27E+02 1.46E+02 2.OOE+02 7.61E+02

3. Dissolved and Entrained Gases

• • No Nuclide Activities **

4. Gross Alpha Radioactivity

• • No Nuclide Activities **

ATTACHMENT 2 Supplemental Information to the Gaseous and Liquid Effluents Report

Page 1 of 2 Catawba 2012 ARERR - Carbon-14 Supplemental Information Carbon-14 (C-14), with a half-life of 5730 years, is a naturally occurring isotope of carbon produced by cosmic ray interactions in the atmosphere. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. C-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing.

In Regulatory Guide 1.21, Revision 2, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste", the NRC recomnends U.S. nuclear power plants evaluate whether C-14 is a "principal radionuclide", and. if so, report the amount of C- 14 released. At Catawba, improvements over the years in effluent management practices and fuel perfornance have resulted in a decrease in gaseous radionuclide (non-C-14) concentrations, and a change in the distribution of gaseous radionuclides released to the environment. As a result, C-14 has become a "principal radionuclide" for the gaseous effluent pathway at Catawba, as defined in Regulatory Guide 1.21, Rev. 2. Catawba's 2012 Annual Radioactive Effluent Release Report (ARERR) contains estimates of C-14 radioactivity released in 2012, and estimates of public dose resulting from the C: 14 effluent.

Because the dose contribution of C- 14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid radioactive waste at Catawba is not required (Ref. Reg. Guide 1.21, Rev. 2). The quantity of gaseous C-14 released to the environment can be estimated by use of a C- 14 source term scaling factor based on power generation (Ref. Reg. Guide 1.21, Rev. 2). Many documents provide infornation related to the magnitude of C- 14 in typical effluents from commercial nuclear power plants. Those documents suggest that nominal annual releases of C- 14 in gaseous effluents are approximately 5 to 7.3 curies from PWRs (Ref. Reg. Guide 1.21, Rev. 2). A more recent study recormnends a higher C-14 gaseous source term scaling factor of approximately 9.0 to 9.8 Ci/GWe-yr for a PWR (Westinghouse) (Ref. EPRI 1021106). For the 2012 Catawba ARERR a source term scaling factor of 9.4 Ci/GWe-yr is assumed. Using a source term scaling factor of 9.4 Ci/GWe-yr and actual electric generation (MWe-hrs) from Catawba in 2012 results in a site total C-14 gaseous release estimate to the environment of -20 Curies. 70% of the C-14 gaseous effluent is assumed to be from batch releases (e.g. WGDTs), and 30% of C-14 gaseous effluent is assumed to be from continuous releases through the unit vents (ref. IAEA Technical Reports Series no. 421, "Management of Waste Containing Tritium and Carbon-14", 2004).

C- 14 releases in PWRs occur primarily as a mix of organic carbon and carbon dioxide released from the waste gas system. Since the PWR operates with a reducing chemistry, most, if not all, of the C-14 species initially produced are organic (e.g., methane). As a general rule, C-14 in the primary coolant is essentially all organic with a large fraction as a gaseous species. Any time the RCS liquid or gas is exposed to an oxidizing environment (e.g. during shutdown or refueling), a slow transformation from an organic to an inorganic chemical form can occur. Various studies documenting measured C-14 releases from PWRs suggest a range of 70% to 95% organic with an average of 80% organic with the remainder being CO 2 (Ref. EPRI TR-105715). For the Catawba 2012 ARERR a value of 80% organic C-14 is assumed.

Page 2 of 2 Public dose estimates from airborne C-14 are performed using dose models in NUREG-0133 and Regulatory Guide 1.109. The dose models and assumptions used are documented in the Catawba ODCM. The estimated C-14 dose impact on the maximum organ dose from airborne effluents released from Catawba in 2012 is well below the 1OCFR50, Appendix I, ALARA design objective (i.e., 15 mrem/yr per unit).

CATAWBA NUCLEAR STATION 2012 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION I. REGULATORY LIMITS - PER UNIT A. NOBLE GASES - AIR DOSE B. LIQUID EFFLUENTS - DOSE

1. CALENDAR QUARTER - GAMMA DOSE = 5 MRAD 1. CALENDAR QUARTER - TOTAL BODY DOSE = 1.5 MHEM

2. CALENDAR QUARTER - BETA DOSE = 10 MRAD 2. CALENDAR QUARTER - ORGAN DOSE = 5 MREM

3. CALENDAR YEAR - GAMMA DOSE = 10 MRAD 3. CALENDAR YEAR - TOTAL BODY DOSE = 3 MREM

4. CALENDAR YEAR - BETA DOSE = 20 MRAD 4. CALENDAR YEAR - ORGAN DOSE = 10 MREM C. GASEOUS EFFLUENTS - IODINE - 131 AND 133, TRITIUM, PARTICULATES WITH HALF-LIVES > 8 DAYS - ORGAN DOSE

1. CALENDAR QUARTER = 7.5 MREM

2. CALENDAR YEAR = 15 MREM II. MAXIMUM PERMISSIBLE EFFLUENT CONCENTRATIONS A. GASEOUS EFFLUENTS - INFORMATION FOUND IN OFFSITE DOSE CALCULATION MANUAL B. LIQUID EFFLUENTS - INFORMATION FOUND IN 1OCFR20, APPENDIX B, TABLE 2, COLUMN 2 III. AVERAGE ENERGY - NOT APPLICABLE IV. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY ANALYSES OF SPECIFIC RADIONUCLIDES IN SELECTED OR COMPOSITED SAMPLES AS DESCRIBED IN THE SELECTED LICENSEE COMMITMENTS ARE USED TO DETERMINE THE RADIONUCLIDE COMPOSITION OF THE EFFLUENT. A

SUMMARY

DESCRIPTION OF THE METHOD USED FOR ESTIMATING OVERALL ERRORS ASSOCIATED WITH RADIOACTIVITY MEASUREMENTS IS PROVIDED AS PART OF THE "SUPPLEMENTAL INFORMATION" ATTACHMENT.

V. BATCH RELEASES A. LIQUID EFFLUENT

1. 9.20E+01 = TOTAL NUMBER OF BATCH RELEASES

2. 5.51E+03 = TOTAL TIME (MIN.) FOR BATCH RELEASES.

3. 1.22E+02 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.

4. 5.99E+01 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.

5. 2.OOE+00 = MINIMUM TIME (MIN.) FOR A BATCH RELEASE.

6. 6.17E+04 = AVERAGE DILUTION WATER FLOW DURING RELEASES (GPM).

B. GASEOUS EFFLUENT

1. 6.60E+01 = TOTAL NUMBER OF BATCH RELEASES.

2. 1.02E+06 = TOTAL TIME (MIN.) FOR BATCH RELEASES.

3. 5.OOE+04 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.

4. 1.54E+04 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.

5. 1.03E+02 = MINIMUM TIME (MIN.) FOR A BATCH RELEASE.

VI. ABNORMAL RELEASES (SEE "UNPLANNED OFFSITE RELEASES" ATTACHMENT)

CATAWBA NUCLEAR STATION Overall Estimate of Error for Effluent Radioactivity Release Reported The estimated percentage of overall error for both Liquid and Gaseous effluent release data at Catawba Nuclear Station has been determined to be + 30.3%. This value was derived by taking the square root of the sum of the squares of the following discrete individual estimates of error:

(1) Flow Rate Determining Devices = +20%

(2) Counting Statistical Error = +20%

(3) Calibration Error = -10%

(4) Calibration Source Error = +2.5%

(5) Sample Preparation Error = +/-3%

ATTACHMENT 3 Solid Radioactive Waste Disposal Report

CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE SHIPPED TO A DISPOSAL FACILITY REPORT PERIOD 1/1/2012 TO 12/31/2012 Total Number of Number of Waste Container Burial Volume Activity Type of Waste Shipped Shipments Containers Class Type (ft') (me) (Curies)

1. Waste from Liquid Systems (A) Dewatered Secondary Resins 2 11 2AU 11 B-25 1512.9 42.85 2.780E-05 1 AS (B) Dewatered Primary Resins 4 4 3B 4 HIC 566.7 16.05 291.404 (C) Evaporator Concentrates 0 0 NA NA 0.0 0.00 0.000 (D) Dewatered Mechanical Filters 0 0 NA NA 0.0 0.00 0.000 (E) Dewatered Demineralizers 0 0 NA NA 0.0 0.00 0.000 (F) Solidified (Cement) Acids, Oils, Sludges 0 0 NA NA 0.0 0.00 0.000

2. Dry Solid Waste (A) Dry Active Waste (compacted) 0 0 NA NA 0.0 0.00 0.000 (B) Dry Active Waste (non-compacted) 0 0 NA NA 0.0 0.00 0.000 (C) Dry Active Waste (brokered) NA NA NA NA 12,878.9 364.73 1.294 (D) Irradiated Components 0 0 NA NA 0.0 0.00 0.000

3. All Solid Waste 6 15 NA NA 14,958.6 423.63 292.698

• Does not included brokered Dry Active Waste totals.

CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE

SUMMARY

OF PRINCIPAL RADIONUCLIDE COMPOSITION REPORT PERIOD 1/1/2012 TO 12/31/2012 Type of Waste Shipped Radionuclide % Abundance*

1. Waste from Liquid Systems (A) Dewatered Secondary Resins H-3 72.70%

Cr-51 0.00%

Mn-54 0.00%

Co-57 0.00%

Co-58 0.00%

Fe-59 0.00%

Co-60 0.00%

Zn-65 0.00%

Nb-94 0.00%

Nb-95 0.00%

Zr-95 0.00%

Ag-1 08m 0.00%

Ag-110m 0.00%

Sn-113 0.00%

Sb-122 0.00%

Sb-124 0.00%

Sb-125 0.00%

Te-125m 0.00%

1-131 0.00%

Ba-1 33 0.00%

Cs-1 34 0.00%

Cs-1 37 0.01%

W-187 0.00%

Ba/La-140 0.00%

Ce-141 0.00%

Ce-144 0.00%

Pu-238 0.00%

Pu-239 0.00%

C-14 6.32%

Fe-55 0.00%

Ni-59 0.00%

Ni-63 0.00%

Sr-89 0.00%

Sr-90 0.00%

Tc-99 20.00%

1-129 0.96%

Am-241 0.00%

Pu-241 0.00%

Cm-242 0.00%

Cm-243 0.00%

(B) Dewatered Primary Resins H-3 0.0%

Cr-51 0.0%

Mn-54 0.4%

Co-57 0.1%

Co-58 0.4%

Fe-59 0.0%

Co-60 6.2%

Zn-65 0.1%

• Average percent abundance for all shipments during period. Page 1 of 4

CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE

SUMMARY

OF PRINCIPAL RADIONUCLIDE COMPOSITION REPORT PERIOD 1/1/2012 TO 12/31/2012 Type of W aste Shipped Radionuclide  % Abundance

• Nb-94 0.0%

Nb-95 0.0%

Zr-95 0.0%

Ag-108m 0.0%

Ag-110m 0.0%

Sn-113 0.0%

Sb-122 0.0%

Sb-124 0.0%

Sb-1 25 0.3%

Te-125m 0.0%

1-131 0.0%

Ba-1 33 0.0%

Cs-1 34 0.0%

Cs-137 0.2%

W-187 0.0%

Ba/La-140 0.0%

Ce-141 0.0%

Ce-144 0.0%

Pu-238 0.0%

Pu-239 0.0%

C-14 0.1%

Fe-55 12.3%

Ni-59 0.5%

Ni-63 79.2%

Sr-89 0.0%

Sr-90 0.0%

Tc-99 0.0%

1-129 0.0%

Am-241 0.0%

Pu-241 0.0%

Cm-242 0.0%

Cm-243 0.0%

(C) Evaporator Con centrates (None shipped to a 10CFR61 facility this period)

(D) Dewatered Mec hanical Filters (None shipped to a 10CFR61 facility this period)

(E) Dewatered Demiineralizers (None shipped to a 10CFR61 facility this period)

(F) Solidified (Ceme nt) Acids, Oils, Sludges (None shipped to a 10CFR61 facility this period)

2. Dry Solid Waste (A) Dry Active Waste (compacted) (None shipped to a 10CFR61 facility this period)

(B) Dry Active Waste (non-compacted) (None shipped to a 10CFR61 facility this period)

(C) Dry Active Waste (brokered) H-3 2.4%

Cr-51 0.0%

Mn-54 0.8%

Co-57 0.1%

• Average percent abundance for all shipments during period. Page 2 of 4

CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE

SUMMARY

OF PRINCIPAL RADIONUCLIDE COMPOSITION REPORT PERIOD 1/11/2012 TO 12/31/2012 Type of Waste Shipped Radionuclide  % Abundance

• Co-58 7.9%

Fe-59 0.0%

Co-60 24.1%

Zn-65 0.0%

Nb-94 0.0%

Nb-95 0.0%

Zr-95 0.0%

Ag-1 08m 0.0%

Ag-110m 0.0%

Sn-113 0.0%

Sb-1 22 0.0%

Sb-1 24 0.0%

Sb-125 2.1%

Te-125m 0.0%

1-131 0.0%

Ba-133 0.0%

Cs-134 0.0%

Cs-137 1.1%

W-187 0.0%

Ba/La-140 0.0%

Ce-141 0.0%

Ce-144 0.5%

Pu-238 0.0%

Pu-239 0.0%

C-14 0.9%

Fe-55 37.3%

Ni-59 0.0%

Ni-63 22.8%

Sr-89 0.0%

Sr-90 0.0%

Tc-99 0.0%

1-129 0.0%

Am-241 0.0%

Pu-241 0.0%

Cm-242 0.0%

Cm-243 0.0%

(D) Irradiated Components (None shipped to a 10CFR61 facility this period)

3. All Solid Waste H-3 0.0%

Cr-51 0.0%

Mn-54 0.4%

Co-57 0.1%

Co-58 0.4%

Fe-59 0.0%

Co-60 6.3%

Zn-65 0.1%

Nb-94 0.0%

Nb-95 0.0%

Zr-95 0.0%

Ag-108m 0.0%

• Average percent abundance for all shipments during period. Page 3 of 4

CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE

SUMMARY

OF PRINCIPAL RADIONUCLIDE COMPOSITION REPORT PERIOD 1/1/2012 TO 12/31/2012 Type of Waste Shipped Radionuclide % Abundance

• Ag-110m 0.0%

Sn-113 0.0%

Sb-1 22 0.0%

Sb-1i24 0.0%

Sb-125 0.3%

Te-125m 0.0%

1-131 0.0%

Ba-133 0.0%

Cs-1 34 0.0%

Cs-1 37 0.2%

W-187 0.0%

Ba/La-140 0.0%

Ce-141 0.0%

Ce-144 0.0%

Pu-238 0.0%

Pu-239 0.0%

C-14 0.1%

Fe-55 12.4%

Ni-59 0.5%

Ni-63 79.0%

Sr-89 0.0%

Sr-90 0.0%

Tc-99 0.0%

1-129 0.0%

Am-241 0.0%

Pu-241 0.0%

Cm-242 0.0%

Cm-243 0.0%

• Average percent abundance for all shipments during period. Page 4 of 4

ATTACHMENT 4 Meteorological Data Meteorological Joint Frequency Distributions of Wind Speed, Wind Direction and Atmospheric Stability using winds at the 10 M Level (Hours of Occurrence)

JFD CNS 2012 SECTOR N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW No. No. No. No. No. No. No. No. No. No. No. No. No. No. No. No.

STAB WSCLS( 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 m/s A 0.46-0.76 0.76- 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.00 1.01- 0 0 0 0 0 '0 0 0 0 0 0 0 0 0 0 0 1.25 1.26- 0 0 0 0 0 0 0 0 1 1 0 0 0 0 0 1 1.60 1 1___1 1_1_1 1.61- 0 1 0 1 0 3 2 7 3 7 4 4 1 2 1 2.00 2.01- 3 4 2 1 3 1 5 33 24 78 112 57 29 10 2 4 3.00 1 3.01- 8 10 5 2 1 0 0 7 12 57 47 18 11 9 8 8 4.00 4.01- 33 33 7 2 1 0 0 1 1 9 41 2 2 15 7 7 6.00 6.01- 5 16 2 0 0 0 0 0 0 2 0 1 0 4 3 4 6.00 6.01- 0 1 0 0 0 0 0 0 0 0 0 0 0 4 6 1 8.00 1 8.01- 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 10.00 1 B 0.46- 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76 0.76- 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.00 1.01- 1 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 1.26 1 1 1 1 1 1.26- 0 0 0 0 0 0 1 0 1 0 2 2 2 2 0 0 1.60 1 1 1.61- 0 0 0 1 0 4 8 4 9 14 7 13 4 0 1 1 2.00 1 2.01- 2 6 2 2 1 2 7 39 271 68 46 13 16 9 0 3 3.00 1 3.01- 28 13 2 0 1 0 1 2 5 15 9 03 3 9 11 4.00 4.01- 12 9 5 2 1 0 0 0 0 1 2 1 1 2 6 4 6.00 1 1 6.01- 7 8 3 0 0 0 0 0 0 0 0 0 0 1 5 2 6.00 6.01- 0 1 0 0 0 0 0 0 0 00 0 0 1 0 2 8.00 8.01- 0 0 0 0 0 0 0 0 0 0 0 00 00 0 10.00 1 1 1 0 1 0 0 C 0.46- 0 "0 0 010 11 0 0 0 0 0 0 0 (

01 0 0.75 0.76-1.00 1 01 01 01 01 01 01 01 01 01 01 01 01 01 01

1.01- 0 0 0 0 0 0 0 1 1 1 0 0 10 1.26 01 0 __

1.26- 0 0 0 1 0 1 3 3 1 2 8 2 1 1 0 1 1.60 1.61- 8 1 1 2 1 4 6 13 17 25 15 15 13 5 1 1 2.00 1 1 1_1__

2.01- 30 8 5 1 3 3 6 19 24 40 40 7 10 3 4 9 3.00 3.01- 48 33 10 3 1 0 1 3 5 7 6 3 3 4 4 7 4.00 4.01- 21 38 11 1 0 0 0 0 0 1 1 0 0 5 5 5 6.00 5.01- 10 8 1 0 0 0 0 0 0 2 0 0 0 1 1 0 6.00 6.01- 0 0 0 0 0 0 O0 0 0 0 0 0 0 2 1 0 8.00 8.01- 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 10.00 D 0.46- 0 I1 01 01 0 0 0 21 3 01 1 1 1 2 0 1 0.76 0.76- 3 0 1 1 1 2 9 8 13 6 14 6 15 5 1 1 1.00 1.01- 4 2 0 0 3 1 7 10 23 28 27 24 9 21 12 10 1.26 5I 1.26- 4 6 3 5 0 9 14 30 54 48 53 29 28 10 11 11 1.60 1 1 1.61- 35 15 5 7 9 8 31 59 102 137 70 27 21 21 27 47 2.00 2.01- 146 66 36 18 5 3 21 73 126 118 70 17 16 24 21 69 3.00 3.01- 155 133 69 7 5 0 8 28 32 31 24 8 6 29 22 27 4.00 . I II I1 4.01- 55 98 52 11 1 1 1 1 7 18 5 5 1 7 8 15 6.00 6.01- 47 29 8 3 0 2 1 0 3 5 2 1 0 3 12 9 6.00 6.01- 4 4 0 0 0 0 0 0 0 0 0 0 0 1 7 3 8.00 1 1 1 8.01- 0 01 0 01 0 01 0 0 0 01 0 0 0 01 0 0 1000 4 - --- +-4.-4-4-4-4-4-4-4-a-4. 4-4 4-4 E 0.46- 0 01 0 01 1 01 0 41 3 11 5 4 1 5 2 1 0.76 0.76- 1 1 0 0 1 3 5 10 23 34 33 25 21 10 4 3 1.00 1.01- 4 0 0 0 0 2 7 15 46 70 65 23 40 15 22 4 1.25 1.26- 2 1 0 0 0 2 8 23 74 114 58 33 22 15 19 12 1.60 1 1____

1.61- 6 3 1 2 2 2 11 54 110 112 47 24 37 39 39 48 2.00 2.01- 74 9 1 4 2 6 16 58 76 49 20 2 12 29 49 115 3.00 1 1 1 3.01- 42 6 7 12 5 1 914 9 8 2 0 415 32 4.00 . I

4.01- 2 5 8 1 0 0 1 0 2 8 2 0 0 2 3 5 5.00 6.01- 1 0 5 1 1 2 0 0 0 0 0 0 0 0 0 1 6.00 6.01- 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8.00 1 1 1_1 1_ _

8.01- 0 0 0 0 0 01 0 0 0 0 0 01 0 0 0 0 10.00 - 0a~.

F 0.46- 0 01 0 01

4. 0 01 0 4-4-I

& 4.-4-4 0 5I.-01 0 5 2 5 21 3 0 0.75 0.76- 2 0 0 0 0 0 0 2 12 19 27 161 9 10 2 1.00 _

1.01- 0 0 0 1 0 0 0 6 38 36 26 17 17 8 8 5 1.25 1.26- 0 0 0 0 0 1 1 9 36 36 31 10 10 11 11 18 1.60 1II 1.51- 9 0 0 0 0 0 3 13 22 7 12 8 18 12 15 21 2.00 2.01- 27 1 1 1 0 1 3 4 2 2 0 0 8 18 9 54 3.00 3.01- 7 0 0 0 0 0 2 1 0 0 0 0 0 0 0 4 4.00 111 4.01- 0 1 0 0 0 0 0 1 0 0 0 0 0 0 0 0 6.00 1_1 5.01- 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6.00 6.01- 0 0 0 0 0 0 0 0 0 0 0 0 0 00 0 8.00 8.01- 0 01 0 01 0 0 0 01 0 01 0 01 0 01 01 0 4

10.00 119t 1-t-t-4 I-I f-I G 0.46- 0 01 0 0 1 0 11 11 231 18 81 10 81 8 0 0.75 0.76- 0 2 0 0 0 0 0 4 17 34 37 19 18 20 15 13 1.00 1.01- 0 0 0 0 0 0 0 7 37 24 28 26 9 16 16 11 1.26 1.26- 1 0 0 0 0 0 0 6 27 23 23 15 13 7 10 23 1.50 1.61- 5 0 0 0 0 0 0 5 16 13 11 8 6 5 4 21 2.00 2.01- 14 0 0 0 0 0 1 1 0 0 0 1 2 11 3 10 3.00 3.01- 3 0 0 0 0 0 0 0 0 0 0 0 1 1 0 0 4.00 _ I 4.01- 1 0000000000 00 00 0 6.00 01 01000 6.01- 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6.00 1 11 6.01- 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8.00 8.01- 0 0 0 01 0 0 0 0 0 0 0 01 0 01 0 0 10.00

- i a i - - .- . - S- S- - S- S- *- * - S- * - - S- i -

ATTACHMENT 5 Unplanned Offsite Releases

Unplanned Offsite Releases for 2012 Based on review of the following data sources; there were no known, unplanned releases of radioactivity (material, liquid, or airborne) from Catawba Nuclear Station in 2012.

" Completed Investigation of Unusual Radiological Occurrences (SIPMP 8-2) for 2012.

" CNS Problem Investigation Process - PIPs from 1/1/12 to 3/21/13 with the following filters.

o PIP SITE='C' o ENTERED DATE = From: 1/1/2012 To: 3/21/2013 o EVENT CODE=

• El - Leak/Spill/Releases or S E Ih - Sewage or S Eli - Other or

• M 12c - Shipment Involved in Shipment Involved in Accident or

• M5 - Radioactive Material/Waste or

• M5b - Radioactive material in clean area or

• M5c - Liquid spill Liquid spill or

• M5f- Unexpected Radiation Alarm or

• M5g - Rad Material Outside Protected Area or

• M5h - Rad Material Outside Owner Controlled or

• M5i - Rad Material Outside the RCA (>SAM) or

• Y4 - Radiation Protection

• CNS Problem Investigation Process - PIPs from 1/1/12 to 3/21/13 with the following filters.

o PIP SITE='C' o ENTERED DATE = From: 1/1/2012 To: 3/21/13 o EVENT DESCRIPTION = 'Release' and 'Unplanned'.

ATTACHMENT 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (includes fuel cycle dose calculation results)

This attachment includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of the report as well as the total dose for the calendar year.

This attachment also includes an assessment of radiation doses to the maximum exposed member of the public from all uranium fuel cycle sources within 8 km of the site for the calendar year of this report to show conformance with 40 CFR 190.

Methods for calculating the dose contribution from liquid and gaseous effluents are given in the Offsite Dose Calculation Manual (ODCM).

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 1 st Quarter 2012 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 1 2012 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q1 - Maximum Organ Dose CHILD BONE 1.13E+00 1.50E+01 7.50E+00 Maximum Organ Dose Receptor Location: 0.5 Mile NE Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage C-14 1.00E+02

=== NOBLE GAS DOSE LIMIT ANALYSIS: Quarter 1 2012 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Ql - Maximum Gamma Air Dose 7.36E-03 1.OOE+01 7.36E-02 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.93E+01 Ql - Maximum Beta Air Dose 2.72E-03 2.00E+01 1.36E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.48E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 2 nd Quarter 2012 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 2 2012 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose CHILD BONE 1.05E+00 1.50E+01 6.99E+00 Maximum Organ Dose Receptor Location: 0.5 Mile NE Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage C-14 1.00E+02 NOBLE GAS DOSE LIMIT ANALYSIS:==- - Quarter 2 2012 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Q2 - Maximum Gamma Air Dose 5.32E-03 1.00E+01 5.32E-02 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.86E+01 Q2 - Maximum Beta Air Dose 2.04E-03 2.OOE+01 1.02E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.07E+01 XE-133 8.16E+00

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 3 rd Quarter 2012 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 3 2012 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose CHILD BONE 1.28E+00 1.50E+01 8.51E+00 Maximum Organ Dose Receptor Location: 0.5 Mile NE Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage C-14 1.00E+02 NOBLE GAS DOSE LIMIT ANALYSIS ==-- ----------------Quarter 3 2012 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Q3 - Maximum Gamma Air Dose 7.43E-03 1.OOE+01 7.43E-02 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.85E+01 Q3 - Maximum Beta Air Dose 2.88E-03 2.OOE+01 1.44E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 8.96E+01 XE-133 9.32E+00

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 4 th Quarter 2012 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 4 2012 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose CHILD BONE 1.04E+00 1.50E+01 6.93E+00 Maximum Organ Dose Receptor Location: 0.5 Mile NE Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage C-14 1.00E+02 NOBLE GAS DOSE LIMIT ANALYSIS------------------------- Quarter 4 2012 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Q4 - Maximum Gamma Air Dose 6.49E-03 1.OOE+01 6.49E-02 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.85E+01 Q4 - Maximum Beta Air Dose 2.50E-03 2.OOE+01 1.25E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.01E+01 XE-133 8.36E+00

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 ANNUAL 2012 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Annual 2012 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose CHILD BONE 4.49E+00 3.OOE+01 1.50E+01 Maximum Organ Dose Receptor Location: 0.5 Mile NE Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage C-14 1.00+E02 NOBLE GAS DOSE LIMIT ANALYSIS:===------------ - Annual 2012 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Yr - Maximum Gamma Air Dose 2.66E-02 2.00E+01 1.33E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.87E+01 Yr - Maximum Beta Air Dose 1.01E-02 4.00E+01 2.53E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.13E+01 XE-133 7.58E+00

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 LIQUID ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 Ist Quarter 2012

BATCH LIQUID RELEASES Quarter 1 2012 ===

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q1 - Maximum Organ Dose CHILD LIVER 3.35E-02 1.00E+01 3.35E-01 Q1 - Total Body Dose CHILD 3.21E-02 3.00E+00 1.07E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 8.93E+01 CS-137 5.18E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.34E+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 1 2012 ...-.

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Ql - Maximum Organ Dose CHILD LIVER 3.58E-04 1.00E+01 3.581E-03 Ql - Total Body Dose CHILD 3.58E-04 3.00E+00 1.19E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.001E+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage 02

---

---

H- 3---00 H-3 1.00OE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 LIQUID ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 2 nd Quarter 2012

=== BATCH LIQUID RELEASES Quarter 2 2012 ---

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose CHILD GI-LLI 1. 27E-02 1.OOE+01 1. 27E-01 Q2 - Total Body Dose CHILD 1. 26E-02 3.00E+00 4.21E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.74E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.77E+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 2 2012 ..-

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose NA NA 0.OOE+00 1.OOE+01 0.OOE+00 Q2 - Total Body Dose NA 0.OOE+00 3.OOE+00 0.OOE+00 Maximum Organ Critical Pathway: NA Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage NA NA Total Body Critical Pathway: NA Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage NA NA

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 LIQUID ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 3 rd Quarter 2012

= BATCH LIQUID RELEASES Quarter 3 2012 ....

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose ADULT GI-LLI 1.28E-02 1.00E+01 1.28E-01 Q3 - Total Body Dose CHILD 1.20E-02 3.00E+00 4.01E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 7.59E+01 NB-95 1.49E+01 CO-60 6.47E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9. 72E+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 3 2012 -==

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (orem) Limit Q3 - Maximum Organ Dose NA NA 0.OOE+00 1.00E+01 0.OOE+00 Q3 - Total Body Dose NA 0.00E+00 3.OOE+00 0.OOE+00 Maximum Organ Critical Pathway: NA Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage NA NA Total Body Critical Pathway: NA Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage NA NA

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 LIQUID ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 4 th Quarter 2012 BATCH LIQUID RELEASES Quarter 4 2012 ======

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (trem) Limit Q4 - Maximum Organ Dose CHILD LIVER 2.14E-02 1.00E+01 2.14E-01 Q4 - Total Body Dose CHILD 2.09E-02 3.OOE+00 6.96E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.54E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.79E+01

=== CONTINUOUS LIQUID RELEASES (WC) Quarter 4 2012 --...

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Or gan Dose NA NA 0.00E+00 1.00E+01 O.OOE+00 Q4 - Total Body Dose NA 0.OOE+00 3.OOE+00 O.OOE+00 Maximum Organ Critical Pathway: NA Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage NA NA Total Body Critical Pathway: NA Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage NA NA

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 LIQUID ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 ANNUAL 2012

=== BATCH LIQUID RELEASES Annual 2012 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (trem) Limit Yr - Maximum Organ Dose CHILD LIVER 7.70E-02 2.OOE+01 3.85E-01 Yr - Total Body Dose CHILD 7.52E-02 6.00E+00 1.25E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or g reater to total)

Nuclide Percentage H-3 9.38E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or g reater to total)

Nuclide Percentage H-3 9ý60E+01

=ý CONTINUOUS LIQUID RELEASES (WC) Annual 2012 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit

-gan Dose CHILD LIVER 3.31--04 Yr - Maximum Or

• Dose CHILD 3.31E-04 2.00E+01 1.66E-03 Yr - Total Body 6.00E+00 5.52E-03 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

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

Nuclide Percentage

- -. - - - - - --

-- - - -

H-3 1.00OE+02

Catawba Nuclear Station 2012 Radioactive Effluent and ISFSI 40CFR190 Uranium Fuel Cycle Dose Calculation Results In accordance with the requirements of 40CFR 190, the annual dose commitment to any member of the general public shall be calculated to assure that doses are limited to 25 millirems to the total body or any organ with the exception of the thyroid which is limited to 75 millirems. The fuel cycle dose assessment for Catawba Nuclear Station only includes liquid and gaseous effluent dose contributions from Catawba and direct and air-scatter dose from Catawba's onsite Independent Spent Fuel Storage Installation (ISFSI) since no other uranium fuel cycle facility contributes significantly to Catawba's maximum exposed individual. Included in the gaseous effluent dose calculations is an estimate of the dose contributed by Carbon-14 (Ref. "Carbon-14 Supplemental Information", contained in the ARERR for further information). The combined dose to a maximum exposed individual from Catawba's effluent releases and direct and air-scatter dose from Catawba's ISFSI is below 40CFR190 limits as shown by the following summary:

1. 2012 Catawba 40CFR190 Effluent Dose Summary The 40CFR 190 effluent dose analysis to the maximum exposed individual from liquid and gas releases includes the dose from noble gases (i.e., total body and skin).

Maximum Total Body Dose = 2.03E+00 mrem Maximum Location: 0.5 Mile, Northeast Sector Critical Age: Child Gas non-NG Contribution: 95.3%

Gas NG Contribution: 1.0%

Liquid Contribution: 3.7%

Maximum Organ (other than TB) Dose = 4.49E+00 mrem Maximum Location: 0.5 Mile, Northeast Sector Critical Age: Child Critical Organ: Bone Gas Contribution: 99.9%

Liquid Contribution: 0.1%

II. 2012 Catawba 40CFR190 ISFSI Dose Summary Direct and air-scatter radiation dose contributions from the onsite Independent Spent Fuel Storage Installation (ISFSI) at Catawba have been calculated and documented in the "Catawba Nuclear Station, ISFSI, 1OCFR72.212 Evaluation" report. The maximum dose rate to the nearest resident from the Catawba ISFSI is conservatively calculated to be 16.6 mremlyear.

The attached excerpt from the "Catawba Nuclear Station, ISFSI, IOCFR72.212 Evaluation" report is provided to document the method used to calculate the Catawba ISFSI 16.6 mrem/year dose estimate.

The following three pages are excerpted from the "Catawba Nuclear Station, Independent Spent Fuel Storage Installation, 1OCFR72.212 Evaluation, NAC-UMS Universal Storage System" report.

CNS 10CFR72.212 Evaluation NAC-UMS Universal Storage System Page 31 of 56 7.3 10CFR72.212(b)(2)(i)(C) - Requirements of §72.104

"(C) the requirementsof§72.104 have been met. A copy of this recordmust be retaineduntil spentfuel is no longer stored under the general license issued under §72.210."

The requirements of §72.104 are as follows:

(a) During normal operations and anticipated occurrences, the annual dose equivalent to any real individual who is located beyond the controlled area must not exceed 0.25 mSv (25 mrem) to the whole body, 0.75 mSv (75 mrem) to the thyroid and 0.25 mSv (25 mrem) to any other critical organ as a result of exposure to:

(1) Planned discharges of radioactive materials, radon and its decay products excepted, to the general environment, (2) Direct radiation from ISFSI or MRS operations, and (3) Any other radiation from uranium fuel cycle operations within the region.

Doses from 24 loaded storage casks located at the ISFSI have been calculated. This represents the placement of a loaded canister at all available locations on the current ISFSI storage pad, completing the projected loading for Phase I.

The methodology and results of the dose calculations are discussed in detail in References 7.3-3 and 7.3-4. A summary of the methodology and results is presented below.

There are two calculations used to estimate the impact of the ISFSI direct radiation doses. The first calculation (Reference 7.3-3) determines a fuel assembly source term to be used in the subsequent shielding model. In order to bound fuel assemblies loaded into canisters in the past and projected to be loaded in the future, the same, bounding fuel assembly is modeled for all 24 spaces in each of the 24 casks. The source term was developed to bound ll types of LEU fuel at Catawba (Westinghouse OFA, RFA, and-Mk-BW). Axial flux profiles, fuel hardware activation, component activation, and the potential impacts from burnable poisons were modeled. Both gamma and neutron source spectrums were produced. In order to ensure that the gamma flux was conservative, the model includes the impact from activation of components, fuel hardware, and light elements. Thus, each spent fuel location models a bounding fuel assembly with a bounding activated component (thimble plug).

CNS 1OCFR72.212 Evaluation NAC-UMS Universal Storage System Page 32 of 56 The source term was modeled using the SAS2H coupled shielding and depletion analysis module of the SCALE code suite. This module utilizes the ORIGEN-S point depletion code to compute the source spectra. An appropriate 44 group library was employed. Use of this code is a standard industry application for source term depletion and decay calculations. It is utilized in a manner consistent with its development.

The results from the source term calculation (Reference 7.3-3) are used as the source term spectra input to the shielding model (Reference 7.3-4).

MCNP, a Monte-Carlo code for neutron and photon transport, was utilized for the shielding computations. This code is an industry standard and is typically applied to problems of this type. The fuel related source term was normalized to the 20 kW administrative decay heat limit and the component source term was normalized to an eight-year decay duration.

The MCNP models were set up using the source terms developed for the four source regions in Reference 7.3-3: fuel (neutron and gamma), fuel hardware, upper plenum, and upper nozzle. These source regions include contributions from both the fuel assembly and the component, as physically appropriate.

The same mesh tally scheme was applied to each source case so the results for each source term could then be summed to produce the final result. A detailed cask model was developed (the work was performed by the cask vendor) and replicated ina 2 by 12 array mimicking the planned arrangement of the loaded canisters on the Catawba ISFSI pad. This represents a full pad of loaded canisters.

Detector locations were laid out on a grid in three dimensions and plots for both near and far field doses were obtained. However, because the coordinate axes align with the cask array orientation, the highest doses are seen along the axes. Thus, for a given distance the highest dose will be found along the x axis, as the long part of the array defines the y axis. The results are as expected for the near and far field doses. Conservatively, the coordinate system was eschewed in the evaluation of the results for 72.104 purposes in favor or the straight line distance to the limiting receptor location (nearest real individual). The nearest real individual is over 450 meters from the ISFSI, but a conservative evaluation distance of 405 meters is adopted. This distance from the ISFSI is within the site boundary. No real individual can live within the (site controlled) boundary, so this distance (location) bounds any real individual (living off-site). As shown in Table 6.7-5 of Reference 7.3-4, the annual dose to the nearest real individual from a full 2 by 12 array of loaded canisters with limiting 20 kW fuel sources and inserts decayed for eight years is 16.6 mrem/yr. The maximum dose at this distance is found, as expected, along

CNS 1 OCFR72.212 Evaluation NAC-UMS Universal Storage System Page 33 of 56 the x axis. This is a conservative application of the shielding analysis results.

The shielding analysis contains many receptor locations, and the results from these cases could be used with a plot of the location of the nearest individual on the shielding model XY coordinates system. This would produce a more precise and lower result.

The computed direct shine dose from the ISFSI to the nearest individual will be added to the plant generated dose to show compliance with 72.104.

General Office Radiation Protection has responsibility for this function.

This information is submitted to the NRC as part of the Annual Radioactive Effluent Release Report for Catawba.

(b) Operational restrictions must be established to meet as low as is reasonably achievable objectives for radioactive materials in effluents and direct radiation levels associated with ISFSI or MRS operations.

(c) Operational limits must be established for radioactive materials in effluents and direct radiation levels associated with ISFSI or MRS operations to meet the limits given in paragraph (a) of this section.

The requirements are met through implementation of the CNS Radiation Protection Program (References 7.3-1 and 7.3-2).

ATTACHMENT 7 Revisions to the Updated Final Safety Analysis Report Radiological Effluent Controls Section 16.11

There were no revisions to the Catawba Nuclear Station Updated Final Safety Analysis Report, Section 16.11, Radiological Controls, in 2012.

ATTACHMENT 9 Information to Support the Nuclear Energy Institute (NEI)

Groundwater Protection Initiative

2012 Catawba ARERR Groundwater Well Data Section Duke Energy implemented a Ground Water Protection program in 2007. This initiative was developed to ensure timely and effective management of situations involving inadvertent releases of licensed material to ground water. As part of this program, Catawba Nuclear Station monitored forty-six wells in 2012.

Wells are typically sampled quarterly or semi-annually. Ground water samples are regularly analyzed for tritium and gamma emitters, select wells being analyzed for difficult to detect radionuclides. No gamma or difficult to detect radionuclides (other than naturally occurring radionuclides) were identified in well samples during 2012. Results from sampling during 2012 confirmed existing knowledge of tritium concentrations in site ground water.

Results from sampling during 2012 are shown in the table below.

Well Location Tritium Concentration (pCi/1) of Name 3/20/12 6/26//12 9/25/12 12/11/12 Samples C1OOR U-1 SFP NS NS NS NS 0 C100DR U-1 SFP <MDA <MDA <MDA NS 3 ClOIR U-1 SFP 877 757 842 705 4 C1OIDR U-1 SFP 552 428 484 535 4 C102 E of U1 SFP O/S protected area 687 676 657 545 4 C103 E of U1 SFP @

Cooling Towers 698 550 669 682 4 C104 U-1 RMWST 647 428 498 468 4 C105 Engr. Bldg. 232 <MDA <MDA NS 3 C105R Engr. Bldg. 781 638 686 684 4 C106 W Parking Lot <MDA <MDA <MDA <MDA 4 C106R W Parking Lot <MDA <MDA <MDA <MDA 4 C107 MET Tower Hill 498 549 599 619 4 C200R U-2 SFP NS 823 802 790 3 C200DR U-2 SFP NS 541 447 492 3 C201R U-2 SFP 1,730 2,820 4,350 3,420 4 C201DR U-2 SFP 512 530 458 606 4 C202 S of RMC Tent 570 668 621 615 4 C203 East of RMC tent

@ Cooling Towers 363 592 490 459 4 C204 S of RMC Tent <MDA <MDA <MDA <MDA 4 C205 Adm. Parking <MDA <MDA <MDA <MDA 4 C205R Adm Parking <MDA <MDA <MDA <MDA 4 C206 W Parking Lot <MDA <MDA <MDA <MDA 4 C207 Mon. Tank B 593 659 782 508 4 C207R Mon. Tank B 350 206 253 195 4 C208 N of MTB 240 270 375 198 4

2012 Catawba ARERR Groundwater Well Data Section Well Location Tritium Concentration (pCi/1) # of Namne 3/20/12 6/26//12 9/25/12 12/11/12 Samples C209 MTUville S of light pole 23A <MDA <MDA 229 <MDA 4 C210 N of U2 Mech Equip Bldg <MDA 263 279 <MDA 4 C211 West of RL intake O/S protected area 774 764 1270 630 4 C212 Behind Aquatic Center <MDA <MDA <MDA <MDA 4 C213R Mon. Tank B <MDA <MDA 184 169 4 C214 Mon. Tank B 723 682 619 887 4 C215 N of U2 TB 662 629 680 821 4 C217 N of U2 TB 828 800 962 917 4 C218 N of U2 TB 2,910 4,440 1,090 1,350 4 C220 N of U2 TB 5,680 5,880 7,360 10,500 4 C221 N of U2 TB 336 357 491 492 4 WCMW-2 N of U2 TB 2,680 2,320 2,930 3,170 4 WCMW-3 WC Ponds 935 634 1,030 1,220 4 WCMW-4 WC Ponds 450 221 508 428 4 WCMW-5 WC Ponds 258 <MDA 246 176 4 Well Location Tritium Concentration (pCi/1) # of Name 4/25/12 10/29//12 Samples LMW 2A Landfill <MDA <MDA 2 LMW 3A Landfill <MDA <MDA 2 LMW 4 Landfill <MDA <MDA 2 LMW 5S Landfill <MDA <MDA 2 LMW 5D Landfill <MDA <MDA 2 Well Location Tritium Concentration (pCi/l) # of Name 3/20/12 8/28//12 9/18/12 10/16/12 11/13/12 12/11/12 Samples C213 Mon. Tank B 11,300 9,120 6,040 6,150 5,740 5,440 6 NS - Not sampled due to insufficient volume in well or well inaccessible during outage.

pCi/I - pico curies per liter

< - less than minimum detectable activity, typically 250 pCi/liter 20,000 pCi/l - the Environmental Protection Agency drinking water standard for tritium. This standard applies only to water that is used for drinking.

1,000,000 pCi/l - the 1OCFR20, Appendix B, Table 2, Column 2, Effluent Concentration limit for tritium.

ATTACHMENT 8 Revisions to the Radioactive Waste Process Control Program Manual

The following letter dated March 27, 2013, from David L. Vaught, Senior Engineer, Nuclear Chemistry, summarizes how the Process Control Program (PCP) manual has been revised. The updated version of the manual contains all the changes implemented during 2012 and is designated as the "2012 Report Year" on the enclosed Compact Disc.

March 27, 2013 RD Hart Regulatory Affairs Catawba Nuclear Safety Assurance ATTENTION: TK Pasour

SUBJECT:

Catawba Nuclear Station 2012 Annual Radioactive Effluent Release Report Process Control Program Changes File: GS-764.25, CN-215.06 Enclosed are CD copies of the PDF file of the Radioactive Waste Process Control Program Manual to be included in the NRC distribution of the Annual Radioactive Effluent Release Report for Catawba Nuclear Station for the period of January 1, 2012 through December 31, 2012. This version of the Manual contains all the changes implemented during 2012 and is designated on the CD cover as the "2012 Report Year".

The PCP Manual is revised using the review and approval process in APPENDIX F of the PCP Manual, "Administration of the PCP and Support Documents" prior to publication on the NEDL Portal.

The attachment summarizes the scope of the changes during 2012.A more detailed summary of changes and basis are in the Appendix H of the PCP Manual.

The PDF file "DukeEnergy-2013-PCP-Manual.pdf' on the CDs was reviewed and verified against the control copies of the PCP Manual published on the NEDL Portal.

Two CD copies are for internal distribution and one for DHEC and four CDs are for the NRC as follows:

DUKE

i. ELL

2. Master File SC STATE

3. DHEC primary contact Russell Keown NRC

4. NRC Document Control Desk

5. Catawba NRC Project Manager

6. Catawba Senior Resident Inspector

7. NRC Regional Administrator If you have any questions, please call David Vaught @ 980-373-5302.

Larry A Wilson Supervising Scientist Nuclear Chemistry by: David L Vaught Senior Engineer Nuclear Chemistry - Radwaste ATTACHMENT

Appendix L - ARERR ATTACHMENT 8 Revisions to the Radioactive Waste Process Control Program Manual A brief summary of the 2012 changes to the Duke Energy Radioactive Waste PCP Manual is found below. These are described in more detail in APPENDIX H "Revision Summary -

Licensee Initiated Changes" PCP MANUAL SECTIONS CHANGED APPENDIX A: "ONS PCP" Rev 15 Minor Change APPENDIX D: "Approved Suppliers of PCP Services" Rev 3 APPENDIX E: "PCP Manual Review and Approval Requirements" Rev 2 DESCRIPTION OF CHANGES BY SECTION APPENDIX A: "ONS PCP" Rev 15 Minor Change A Minor Change was published to address a NOS Audit Deficiency identified during the 2012 ONS Radiological Effluent Controls Audit.

1. Two procedures listed in the manual have been revised from "B" to "A" procedures.

2. The procedure CP/0/B/5200/054, "Radwaste Liquid Waste Processing" was removed from the implementing procedure list after it was determined that it does not implement or impact any part of the PCP.

3. Two editorial changes were included to correct procedure title wording APPENDIX D: "Approved Suppliers of PCP Services" Rev 3 CHANGES:

1. Added Waste Management Group (WMG) to the Approved Suppliers of PCP Services table.

2. Edited details of the DOCUMENTATION section to clarify applicability.

3. Added the PIP reference G-04-00113 that documents the review and approval of the Studsvik Processing Facility, LLC previously added to the table.

4. Deleted section 2.2 due to changes in internal Duke administrative processes outside the PCP Manual purview.

APPENDIX E: "PCP Manual Review and Approval Requirements" Rev 2 CHANGES:

1. Changed titles to reflect post merger.

2. Changed the approval protocol for the PCP Manual sections to simplify the approval process by lowering the management approval level required based on significance of the section being changed and whether it is a revision or a minor change.

ATTACHMENT 10 Inoperable Equipment

Inoperable Monitoring Equipment Report from 1/01/2012 to 12/31/2012 per SLC 16.11-2 and 16.11-7 SLC # from Title Completion Determination and Data Reviewed Table 16.11- Time 2-1 1.a EMF 49 14 Days For OEMF49, out of service time was 14.95 1 _days (TSAIL C0-12-03408).

0EMF49 was entered into TSAIL on 12/04/12 and was restored on 12/19/2012. On 12/04/12, Work Request 1075545 was written to investigate why 0EMF49 did not correlate within the procedural acceptance range for the release. It was found that OEMF49 was out of tolerance low. OEMF49 was recalibrated and restored to service on 12/19/12.

• Work Order 01075545 SLC # from Title Completion Determination and Data Reviewed Table 16.11- Time 7-1 1.a EMF 50 (L) 14 Days 0EMF50(L), out of service time for year 2012 is 137.59 days (1/01/12 to 5/17/12 TSAIL CO-11-01041).

For year 2012, OEMF50 was non-functional from 1/01/2012 to 5/17/12 due to issues associated with correlation of OEMF50 actual reading to expected reading based on sample activity. The start date of the non-functional period extends back to the previous year on 4/07/2011. This was due to C-14 interference in the monitors count rate.

This monitor was restored to functional status after implementation of the new calibration methodologies provided by the vendor General Atomics via a new primary calibration.

• PIP C-12-02678

• PIP C-12-00507

• WO 02002300 - OEMF50: TEST EMF50 FOR DIFFERENT HV AND DISC VALUES Page 1 of 1

ATTACHMENT 11 Radioactive Waste Systems Changes

ATTACHMENT 11 Radioactive Waste Systems Changes There were no significant modifications to the Liquid Waste system performed during the calendar year 2012. The only modifications performed were associated with parts obsolescence issues.

The Gaseous Waste System had no significant modifications performed during the calendar year 2012.

The only modifications performed were associated with parts obsolescence issues.

There were no modifications to the Solid Waste Disposal system performed during the calendar year 2012.

All Open Mods by window for 2012 were reviewed. From that list, the following modifications were reviewed for impact based on the description of change:

EC0000107896 RRT REPLACE OBSOLETE MTB TRUCK BAY SUMP PUMP OWLPUTB (ERRT)

EC0000100576 DELETION OF OWGCR5100 (WG DECAY TANKS PRESSURE)

EC0000090468 CD500785 - RRT SPENT RESIN STORAGE TANK B EC0000106637 REVISE IMPELLER SIZE FOR 'A' AND 'B' NB CONCENTRATE PUMPS EC0000105868 REPLACE SSF D/G JACKET WATER OUTLET TEMPERATURE GAUGE AND SENDER