ML13128A061

Attachment a, 2012 Annual Radioactive Effluent Release Report

ML13128A061
Person / Time
Site:	Crystal River
Issue date:	03/20/2013
From:	Pinner R Progress Energy Florida
To:	Office of Nuclear Reactor Regulation
References
3F0413-03
Download: ML13128A061 (27)

Text

FLORIDA POWER CORPORATION DOCKET NUMBER 50 - 302 / LICENSE NUMBER DPR - 72 ATTACHMENT A 2012 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2012 PROGRESS ENERGY FLORIDA, INC CRYSTAL RIVER UNIT 3 Facility Operating License No. DPR-72 Docket No. 50-302 Prepared By: Rudy Pinner Sr. Nuclear Plant Chemistry Specialist Approved By: Gordon Caldwell Superintendent Environmental & Chemistry Date: 03-20-2013 I

CONTENTS Intro d u ctio n .................................................................................................................... 1 Tabular Data Summaries G aseous Effluents - Q uarters 1 to 4 ............................................................. 2 Liquid Effl uents - Q uarters 1 to 4 .................................................................. 7 Batch Release Sum m ary ............................................................................................ 10 Dose Evaluation .......................................................................................................... 14 Appendix I Dose Sum m ary ......................................................................................... 16 Radwaste Shipm ents ................................................................................................. 18 Unplanned Releases ................................................................................................... 19 Radioactive W aste Treatm ent System s ....................................................................... 19 Annual Land Use Census ............................................................................................ 19 Effl uent Monitor Instrum ent O perability ..................................................................... 19 Meterology Instrum entation Evaluation ..................................................................... 19 O DCM Changes ........................................................................................................ 19 Process Control Program Changes .......................................................................... 20 Em ergency Feed Pum p 2 ......................................................................................... 20 Carbon-14 Evaluation ................................................................................................ 21 NEI 07-07 Required Data ............................................................................................ 22

INTRODUCTION This report is submitted as required by the Offsite Dose Calculation Manual, section 6.5, and Technical Specfications 5.6.2.3.3 and 5.7.1.1.c.

The scope of this report includes:

" A summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the plant.

" Quarterly and annual dose summaries.

• A list and description of unplanned releases to unrestricted areas.

" A description of any changes to the:

Process Control Program (PCP), and Offsite Dose Calculation Manual (ODCM).

• Significant changes to any radioactive waste treatment system.

• A list of new dose calculation location changes identified by the annual land-use census.

• Information relating to effluent monitors or required supporting instrumentation being inoperable for 30 or more days.

• Information required to be included in this report per NEI 07-07 Industry Ground Water Protection Initiative-Final Guidance Document issued in August 2007.

Note for reporting purposes, N/D = Not Detected.

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EFFLUENT and WASTE DISPOSAL REPORT-2012 Table 1A - Regulatory Guide 1.21 Gaseous Effluents - Summation of All Releases Unit: 3 Units Ist Qtr 2nd Qtr 3rd Qtr 4th Qtr Est. Total

% Error A. Fission & Activation Gases

1. Total Release Curies O.OOE+00 O.OOE+O0 O.OOE+O0 O.OOE+00 3.00E+01 I

2. Average Release Rate for Period uCi/sec O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 B. lodines

1. Total Iodine-131 Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.00E+01

2. Average Release Rate for Period uCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 I C. Particulates

1. Particulates with half-lives > 8 days Curies O.OOE+00 7.91E-08 6.94E-07 2.94E-07 3.00E+O1 I

2. Average Release Rate for Period uCi/sec O.OOE+00 1.01E-08 8.73E-08 3.70E-08

3. Gross Alpha Radioactivity Curies 5.52E-08 O.OOE+00 4.35E-07 3.80E-07 D. Tritium

1. Total Release Curies 1.09E+00 1.57E+00 1.65E+00 9.55E-01 3.00E+01

2. Average Release Rate for Period uCi/sec 1.39E-01 2.OOE-01 2.07E-01 1.20E-01 I 2

EFFLUENT and WASTE DISPOSAL REPORT-2012 Table 1B - Regulatory Guide 1.21 Gaseous Effluents - Elevated Batch Mode Unit: 3 (This Table Does Not Apply to Crystal River Unit 3)

Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Fission & Activation Gases Total Curies N/D N/D N/D N/D lodines Total Curies N/D N/D N/D N/D Particulates Total Curies N/D N/D N/D N/D H-3 Curies N/D N/D N/D N/D Gross Alpha Curies N/D N/D N/D N/D 3

EFFLUENT and WASTE DISPOSAL REPORT-2012 Table 1B - (Continued) Regulatory Guide 1.21 Gaseous Effluents - Elevated Continuous Mode Unit: 3 (This Table Does Not Apply to Crystal River Unit 3)

Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Fission & Activation Gases Total Curies N/D N/D N/D N/D lodines Total Curies N/D N/D N/D N/D Particulates Total Curies N/D N/D N/D N/D H-3 Curies N/D N/D N/D N/D Gross Alpha Curies N/D N/D N/D N/D 4

EFFLUENT and WASTE DISPOSAL REPORT-2012 Table 1C - Regulatory Guide 1.21 Gaseous Effluents - Ground Batch Mode Unit: 3 Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Fission & Activation Gases fTotal Curies N/D N/D N/D N/

Iodines

ýotal Curies N/D N/D N/D NI Particulates f otal Curies N/D N/D N/D N/

FH-3 Curies N/D N/D N/D N/

JGross Alpha Curies N/D N/D N/D N 5

EFFLUENT and WASTE DISPOSAL REPORT-2012 Table 1C - (Continued) Regulatory Guide 1.21 Gaseous Effluents - Ground Continuous Mode Unit: 3 Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Fission & Activation Gases Total Curies N/D N/D N/D N/D lodines Total Curies N/D N/D N/D N/D Particulates Cs-137 Curies N/D 7.91E-08 6.94E-07 2.94E-077]

Total Curies N/D 7.91E-08 6.94E-07 2.94E-07 H-3 Curies 1.09E+00 1.57E+00 1.65E+00 9.55E-01 Gross Alpha Curies 5.52E-08 N/D 4.35E-07 3.80E-07 6

EFFLUENT and WASTE DISPOSAL REPORT-2012 Table 2A - Regulatory Guide 1.21 Liquid Effluents - Summation of All Releases Unit: 3 Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Est. Total

% Error A. Fission & Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 7.34E-05 6.01E-05 1.57E-04 2.80E-05 2.50E+01

2. Average diluted concentration during period uCi/ml 4.18E-13 2.33E-13 6.12E-13 1.35E-13

3. Percent of Applicable Limit  % 9.95E-07 1.39E-06 3.47E-06 1.14E-06 B. Tritium

1. Total Release Curies 1.06E-01 1.23E-01 2.77E-01 1.28E-01 3.00E+01

2. Average diluted concentration during period uCi/ml 6.03E-10 4.76E-10 1.08E-09 6.14E-10

3. Percent of Applicable Limit  % 6.03E-06 4.76E-06 1.08E-05 6.14E-06 C. Dissolved and Entrained Gases

1. Total Release Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.50E+01

2. Average diluted concentration during period uCi/ml O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

3. Percent of Applicable Limit  % O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 D. Gross Alpha Radioactivity

1. Total Release Curies O.OOE+00 2.79E-05 O.OOE+00 O.OOE+00 3.00E+701 E. Waste Volume Released (Pre-Dilution) Liters 2.08E+06 3.66E+06 2.18E+06 1.90E+06 1.00E+01 F. Dilution Water Volume During Period Liters 1.76E+11 2.58E+11 2.57E+11 2.08E+11 1.OOE+01 7

EFFLUENT and WASTE DISPOSAL REPORT-2012 Table 2B - Regulatory Guide 1.21 Liquid Effluents - Batch Mode Unit: 3 IUnits 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Fission & Activation Products Co-60 Curies N/D 2.04E-06 7.53E-05 6.64E-06 Ni-63 Curies 1.25E-05 N/D N/D N/D Sb-125 Curies 4.51E-05 2.38E-05 1.87E-05 N/D Cs-137 Curies 1.59E-05 3.43E-05 6.35E-05 2.14E-05 Total Curies 7.34E-05 6.01E-05 1.57E-04 2.80E-05 Dissolved and Entrained Gases Total Curies N/D N/D N/D N/D H-3 Curies 1.06E-01 1.23E-01 2.77E-01 1.28E-01 Gross Alpha Curies N/D 2.79E-05 N/D N/D 8

EFFLUENT and WASTE DISPOSAL REPORT-2012 Table 2B - (Continued) Regulatory Guide 1.21 Liquid Effluents - Continuous Mode Unit: 3 I Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Fission & Activation Products Total Curies N/D N/D N/D N/D Dissolved and Entrained Gases Total Curies N/D N/D N/D N/D H-3 Curies N/D N/D N/D N/D 7 Gross Alpha Curies N/D N/D N/D N/D 9

EFFLUENT and WASTE DISPOSAL REPORT-2012 Regulatory Guide 1.21 Gaseous Batch Release Summary Unit: 3 Jan - Jun Jul - Dec Number of Batch Releases 0 0 Total Time Period for Batch Releases 0.OOE+00 min O.OOE+00 min Maximum Time Period for a Batch Release 0.OOE+00 min O.OOE+00 min Average Time Period for a Batch Release 0.OOE+00 min O.OOE+00 min Minimum Time Period for a Batch Release O.OOE+00 min O.OOE+00 min 10

EFFLUENT and WASTE DISPOSAL REPORT-2012 Regulatory Guide 1.21 Liquid Batch Release Summary Unit: 3 Jan - Jun Jul - Dec Number of Batch Releases 32 27 Total Time Period for Batch Releases 8.53E+03 min 6.25E+03 min Maximum Time Period for a Batch Release 4.22E+02 min 4.20E+02 min Average Time Period for a Batch Release 2.67E+02 min 2.32E+02 min Minimum Time Period for a Batch Release 4.80E+01 min 5.40E+01 min Average Stream Flow During Release Periods 1.91 E+05 gpm 2.46E+05 gpm II

EFFLUENT and WASTE DISPOSAL REPORT-2012 Regulatory Guide 1.21 Gaseous Abnormal Release Summary Unit: 3 Jan - Jun Jul - Dec Number of Abnormal Releases 0 0 Total Time Period for Abnormal Releases 0.OOE+00 min 0.OOE+00 min Maximum Time Period for an Abnormal Release 0.OOE+00 min 0.OOE+00 min Average Time Period for an Abnormal Release 0.OOE+00 min 0.OOE+00 min Minimum Time Period for an Abnormal Release O.OOE+00 min 0.OOE+00 min Total Activity for Abnormal Releases O.OOE+00 Ci 0.OOE+00 Ci 12

EFFLUENT and WASTE DISPOSAL REPORT-2012 Regulatory Guide 1.21 Liquid Abnormal Release Summary Unit: 3 Jan - Jun Jul - Dec Number of Abnormal Releases 0 0 Total Time Period for Abnormal Releases O.OOE+00 min 0.OOE+00 min Maximum Time Period for an Abnormal Release O.OOE+00 min 0.OOE+00 min Average Time Period for an Abnormal Release O.OOE+00 min 0.OOE+00 min Minimum Time Period for an Abnormal Release O.OOE+00 min 0.OOE+00 min Total Activity for Abnormal Releases 0.OOE+00 Ci 0.OOE+00 Ci 13

EFFLUENT and WASTE DISPOSAL REPORT-2012 Regulatory Guide 1.21 Gaseous NNG Organ Dose Unit: 3 Receptor Name: Infant Max Ind NW at 1.34 km 1 Quarter 2 nd Quarter 3r Quarter 4 th Quarter Calendar Year 0 0

% of 0/0 of  % of /0 of /%of Organ Dose ODCM Dose ODCM Dose ODCM Dose ODCM Dose ODCM Limit Limit Limit Limit Limit Bone 2.63E-04 3.50E-03 3.80E-04 5.07E-03 4.21E-04 5.62E-03 2.40E-04 3.20E-03 1.30E-03 8.69E-03 Liver 2.63E-04 3.50E-03 3.80E-04 5.07E-03 4.25E-04 5.66E-03 2.42E-04 3.22E-03 1.31E-03 8.73E-03 Total Body 2.63E-04 3.50E-03 3.78E-04 5.04E-03 4.01E-04 5.35E-03 2.32E-04 3.09E-03 1.27E-03 8.49E-03 Thyroid 2.63E-04 3.50E-03 3.77E-04 5.03E-03 4.OOE-04 5.33E-03 2.31E-04 3.08E-03 1.27E-03 8.47E-03 Kidney 2.63E-04 3.50E-03 3.78E-04 5.04E-03 4.06E-04 5.42E-03 2.34E-04 3.12E-03 1.28E-03 8.54E-03 Lung 2.63E-04 3.50E-03 3.78E-04 5.04E-03 4.02E-04 5.36E-03 2.32E-04 3.1OE-03 1.28E-03 8.50E-03 GI-Lli 2.63E-04 3.50E-03 3.77E-04 5.03E-03 4.OOE-04 5.33E-03 2.31E-04 3.08E-03 1.27E-03 8.47E-03 Maximum Organ was LIVER.

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EFFLUENT and WASTE DISPOSAL REPORT-2012 Regulatory Guide 1.21 Liquid Organ & Whole Body Dose Unit: 3 Receptor Name: Adult NW at 1.34 km 1st Quarter 2 nd Quarter 3rd Quarter 4th Quarter Calendar Year

% of 0/0 of  % of 0/0 of 0/0 of Organ Dose ODCM Dose ODCM Dose ODCM Dose ODCM Dose ODCM Limit Limit Limit Limit Limit Bone 1.91E-07 3.82E-06 4.33E-07 8.65E-06 1.08E-06 2.15E-05 1.61E-07 3.23E-06 1.86E-06 1.86E-05 Liver 2.21E-07 4.41E-06 5.90E-07 1.18E-05 1.48E-06 2.95E-05 2.20E-07 4.41E-06 2.51E-06 2.51E-05 Total Body 1.46E-07 9.70E-06 3.88E-07 2.59E-05 9.81E-07 6.54E-05 1.46E-07 9.73E-06 1.66E-06 5.53E-05 Thyroid 3.67E-09 7.34E-08 2.79E-09 5.59E-08 1. 13E-08 2.25E-07 2.49E-09 4.98E-08 2.02E-08 2.02E-07 Kidney 7.66E-08 1.53E-06 2.02E-07 4.04E-06 5.06E-07 1.01E-05 7.63E-08 1.53E-06 8.61E-07 8.61E-06 Lung 2.82E-08 5.64E-07 6.92E-08 1.38E-06 1.76E-07 3.52E-06 2.70E-08 5.40E-07 3.OOE-07 3.OOE-06 GI-Lli 1.27E-08 2.53E-07 1.82E-08 3.64E-07 1.68E-07 3.36E-06 1.55E-08 3.10E-07 2.14E-07 2.14E-06 Liquid Effluent Dose Limits Total Body: 1.5 mrem/quarter, 3 mrem/year Any Organ: 5 mrem/quarter, 10 mrem/year 15

EFFLUENT and WASTE DISPOSAL REPORT-2012 Regulatory Guide 1.21 Liquid App I Dose Assessment Unit: 3 Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual 4

Maximum Organ Dose mRem 2.21 E-07 5.90E-07 1.48E-06 2.20E-07 2.51 E-06 ODCM Limit mRem 5.00 5.00 5.00 5.00 10.00

% of ODCM Limit  % 4.41 E-06 1.18E-05 2.95E-05 4.41 E-06 2.51 E-05 Maximum Organ was LIVER 16

EFFLUENT and WASTE DISPOSAL REPORT-2012 Regulatory Guide 1.21 App I Dose Assessment Unit: 3 Airborne Noble Gas Doses Child Site Boundary NW at 1.34 km Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual 1Beta Air mRad 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00F+0 JODCM Limit mRad 10.00 10.00 10.00 10.00 20.001 0% of ODCM Limit  % 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+0 Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual Oamma Air mRad 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.00E+0 ODCM Limit mRad 5.00 5.00 5.00 5.00 10.0

%/oof ODCM Limit  % 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+01 Gaseous Release Dose Summary Note: There were no noble gases released in 2012 due to the extended plant shutdown from refueling outage 16 that began in September 2009. The plant is still shutdown in mode 7 (defueled) for all of 2010, 2011, and 2012 due to reactor building containment concrete wall delamination issues.

Gaseous Effluent Dose Limits Gamma Air Dose: 5 mrad/quarter, 10 mrad/year Beta Air Dose: 10 mrad/quarter, 20 mrad/year Any Organ: 7.5 mrem/quarter, 15 mrem/year 17

TABLE 3 EFFLUENT and WASTE DISPOSAL REPORT-2012 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR PROCESSING OR BURIAL (Non-irradiated fuel)

Type of waste Unit 12 month period Est. Total Error %

m3 3.21 E+01 25

a. Spent resins, filter sludges, evaporator bottoms, etc. m3 1.1E+01 Ci 1.12E+02 m3 2.92E+02 25 25

b. Dry compressible waste, contaminated equipment, etc. m3 2.92E02 Ci 4.46E-02

c. Irradiated components, control rods, etc. m3 Ci 0.OOE+00 0.00E+00 25 m3 0.00E+00 25 25

d. Other (describe): Combined DAW package Ci 0.OOE+00

2. Estimate of major nuclide composition (by type of waste in %)*

Fe-55 17.32 Co-60 18.57 Cs-137 15.72

a. Sb-125 0.53 Ni-63 40.89 Ag-110m 0.11 Mn-54 0.89 Ni-59 0.18 C-14 4.19 Cs-134 1.37 C-14 5.85 Ni-63 25.11 Co-58 6.15

b. Fe-55 11.2 Mn-54 4.13 Zn-65 0.31 Co-60 37.66 Cs-1 37 3.54 Zr-95 1.25 Nb-95 2.61 Cs-134 0.38 Ag-110m 0.31 Sb-1 25 0.94 Co-57 0.15 Ce-144 0.37

c. N/A N/A N/A

d. N/A N/A N/A

• Curie values and principle radionuclides are estimates based on a combination of direct and indirect methods.

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 01 Truck Shipments Energy Solutions 07 Truck Shipments Energy Solutions-Bear Creek 04 Truck Shipments Energy Solutions, LLC 03 Truck Shipments Studsvik Processing Facility, LLC B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination 0 N/A N/A 18

Unplanned Releases There were no unplanned releases in 2012.

Radioactive Waste Treatment Systems There were no significant changes to the radioactive waste treatment systems in 2012. In November of 2011, a demineralized water valve that was found with significant seat leakage, providing input into the liquid radwaste system, was successfully repaired. This repair has significantly reduced the liquid waste processing routine from approximately every 10 to 14 days to approximately 50 to 55 days between processing runs. Due to the lengthy shutdown of Crystal River Unit 3, liquid waste volume and radioactivity concentration has continued to decrease.

Annual Land Use Census The 2012 land-use census did not identify any new dose calculation locations.

Effluent Monitor Instrument Operability In June 2012 gaseous effluent radiation monitors RM-A1 and RM-A2, along with the associated post accident range monitors for these release pathways were taken out of service for planned replacement of these monitors with new monitor modules built by Mirion Technologies. The monitors were installed, functionally tested, and the normal range monitors returned to service in December 2012 for RM-A2 and in January 2013 for RM-A1. RM-A1 is the effluent monitor for the reactor building purge exhaust ventilation system and RM-A2 is the effluent monitor for the auxiliary building ventilation exhaust system. The design, procurement, factory acceptance testing, installation, procedural development, functional testing, and return to service instructions were performed under Engineering Change # 76363. During the time when RM-A2 was out of service, compensatory sampling was performed using alternate gaseous monitors RM-A4 and RM-A8. During the time that RM-A1 was out of service, there were no reactor building ventilation purges performed, so there was no alternate monitoring required for the reactor building ventilation exhaust pathway.

Meterology Instrumentation Evaluation During 2012 the yearly instrumentation data recovery for all meterology tower instruments has remained in the range of 98.5% to 99.7%. Actual meterological data is available and is maintained at the Crystal River site. The actual met. data is not provided in this report as is allowed by the ODCM.

Offsite Dose Calculation Manual (ODCM) Changes

• The ODCM was revised two times in 2012. The first revision, #33, incorporated the following changes:

1. Table 2-3, page 13, 14, of action 28; guidance was added regarding actions needed if the auxiliary building ventilation system is secured. Also compensatory actions for sampling requirements if RM-A2 is out of service was updated to allow trending radiation monitors RM-A4 and RM-A8 instead of collecting grab samples. An update was needed to allow use of other in service radiation monitors for real time data gathering instead of periodic momentary grab sampling. This improves the efficiency of tracking effluent data.

2. Pages 52 and 134-137 corrected typos.

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3. Page 92, on the flow diagram for liquid waste processing, removed the waste evaporators as a source of liquid waste and inserted the miscellaneous waste storage tank to update the diagram to current plant configuration.

4. Pages 138-143, added methodology for accounting for C-14 in radiological effluents.

5. Page 145 updated the location descriptor for vegetation sampling station C48A as the previous location was removed due to site construction.

6. Page 161, guidance was added to also contact American Nuclear Insurers (ANI) if an event occurs where a radiological spill or leak occurs and the water could reach groundwater.

e The second revision, #34, incorporated the following changes:

1. This revision was made entirely to support replacing the ventilation effluent radiation monitors, RM-A1 and RM-A2 and their associated post accident sampling monitors. RM-A1 monitors the reactor ventilation exhaust system and RM-A2 monitors the auxiliary building ventilation exhaust system.

2. Page 2 added the "A"frequency for annual to support yearly calibration of the new gaseous effluent monitors per manufacturer's recommendations.

3. Page 11, table 2-3 changed operating range to normal range and changed mid range monitor to accident range monitor. Also removed the high range monitor for items number 2 and 3.

4. Page 15, table 2-4 same changes as table 2-3, plus changed the frequency of surveillance requirements to match the manufacturer's recommendations and plant PM programs for items number 2 and 3.

5. Page 16 item "#" changed RM-A1 operating range to normal range.

6. Page 27 table 2-6 table notation item "d" rewritten to agree with NUREG 1301 verbiage as we no longer have "live" iodine channels for RM-A1 and RM-A2 with the new monitors.

7. Page 40, section 2.14 item "H" changed mid and high range to accident range.

8. Page 57, table I, deleted RM-A1 and RM-A2 iodine channel setpoint references as there are no live iodine channels associated with the new monitors.

9. Page 60, Gaseous Effluent Setpoint Specification 1.1-3 Iodine channels for RM-A1 and RM-A2, deleted verbiage relating to iodine channel setpoints.

10. Page 70, Pre-Release Calculation 1.3-3 for Gaseous Effluent Iodine Monitors, changed title to Pre-Release Calculation for Iodine Evaluation; changed the introduction to discuss iodine loading on the sample cartridge, item I.D. changed the flow rate from 1 to 2 scfm and corresponding cc/sec value to match the new monitor design flow of 2 scfm, also changed the corresponding total flow through the cartridge.

11. Page 71, sub item "r'changed the flows as described in #10 above, changed the calculated uCi in the building vents based on the new flow information, and deleted the last sentence as there is no longer a live iodine channel on RM-A1 and RM-A2.

12. Pages 72 through 79 changes setpoint methodology for gaseous releases to a fixed method based on conservative isotopic mix and vendor information for the calibration slope response of the respective monitor.

Process Control Program (PCP) Changes The PCP was not revised in 2012.

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Emergency Feed Pump 2 & Steam Releases Emergency Feed Pump 2 (EFP-2) over-speed testing is performed quarterly using steam from CR-3s steam generators. Due to a historical small primary to secondary leak, an evaluation is normally performed to estimate the quantity of radioactive material which would be released during 2012 due to operation of this pump. In addition, radioactive releases due to other steam releases are normally estimated and included. These values normally include any plant trips with associated secondary plant atmosphere steam relief valve initiation. The results are given below in units of Curies/year.

Due to the extended plant shutdown for refueling outage 16, which began in September of 2009, the plant is still shutdown for the containment building wall repair. The emergency feed pump 2 has not operated and there were no secondary plant steam releases during 2010, or 2011, or 2012.

Xe-133 0.OOE+00 1-131 0.OOE+0 Cs-137 0.OOE+00 Xe-135 0.OOE+00 1-133 0.OOE+0 H-3 0.OOE+00 These values are not included in Tables 1 through 4 of this report.

Carbon-14 Evaluation During the entire year of 2012, Crystal River Unit 3 has been in a cold shutdown mode. The plant was taken off line in September of 2009 for refueling outage 16. In 2009, the plant was degassed, the reactor building was purged of radioactivity, waste gas decay tanks were released, a construction opening was made in the side of the reactor building containment wall, and both once through steam generators were replaced. Since the plant has been in cold shutdown for the entire years of 2010, 2011, and 2012 due to reactor building containment wall delamination issues, there is no source term generation for carbon-14 production in 2010, 2011, or 2012. Once the plant restarts, C-14 source term and resultant dose will be estimated and reported utilizing the methodology discussed in NUREG-0017, Rev 1 "Calculation of Releases of Radioactive Materials in Gaseous and Liquid effluents From Pressurized Reactors, and in Regulatory Guide 1.109, "Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance With 10 CFR Part 50, Appendix I".

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Nuclear Electric Institute (NEI) Required Information The following environmental data is being included in this report per objective 2.4.b.i and 2.4.b.ii of NEI 07-07 Industry Ground Water Protection Initiative, as this groundwater well data is used to evaluate groundwater at the site, but is not officially included in the Radiological Environmental Monitoring Program (REMP) or the Offsite Dose Calculation Manual (ODCM). These 2 graphs are of tritium measurements in units of pCi/I, taken from groundwater monitoring wells located west of CR-3 on either side (north and south) of the site settling ponds. There are many other groundwater monitoring wells included in the REMP that are used for evaluating the groundwater in the vicinity of the CR-3 site. These 2 wells are providing supplemental information. The LLD for tritium measurement of these environmental well samples is -150 pCi/I.

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Tritium Measurements GW Well # MWC-4F2 600 500 400 200 I 100 0-1/1*0I0 02/22/08 07/06/09 11/18/10 04/01/12 08/14/13 Tritium Measurements GW Well # MWC-27 1400 1200 1000 800 600-400 200 0

10/10/06 02/22/08 07/06/09 11/18/10 04/01/12 08/14113 23

Additional Information On February 5, 2013, Duke Energy announced that a decision has been made to permanently retire Crystal River Unit 3. The decision was made due to the high cost of repair and risk associated with repairing the containment building's concrete wall. The company is working to develop a comprehensive decommissioning plan and intends to place the facility in SAFSTOR for the immediate future and eventual dismantling.

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