3F0314-06, 2013 Annual Radioactive Effluent Release Report

From kanterella
Jump to navigation Jump to search
2013 Annual Radioactive Effluent Release Report
ML14098A038
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 03/27/2014
From: Wunderly B
Duke Energy Florida
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
3F0314-06
Download: ML14098A038 (28)
v • d • e


Text

DUKE

ENERGY, Crystal River Nuclear Plant 15760 W. Power Line Street Crystal River, FL 34428 Docket 50-302 Operating License No. DPR-72 10 CFR 50.36a(a)(2)

ITS 5.7.1.1(c)

March 27, 2014 3F0314-06 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Crystal River Unit 3 - 2013 Annual Radioactive Effluent Release Report

Dear Sir:

Duke Energy Florida, Inc., hereby provides the 2013 Radioactive Effluent Release Report for Crystal River Unit 3 (CR-3) in accordance with 10 CFR 50.36a(a)(2) and the CR-3 Improved Technical Specifications (ITS), Section 5.7.1.1(c). The attached report includes a summary of the quantities of radioactive liquid and gaseous effluents, and solid waste released from the CR-3 site during 2013. The material provided is consistent with the objectives outlined in the Off-Site Dose Calculation Manual (ODCM) and the Process Control Program (PCP), and is in conformance with 10 CFR 50, Appendix I, Section IV.B.1.

The CR-3 ITS, Section 5.6.2.3, requires submittal of licensee initiated changes to the ODCM as part of the Radioactive Effluent Release Report for the period of the report in which any changes were made. The ODCM and the PCP were not revised in 2013.

No new regulatory commitments are made in this letter If you have any questions regarding this submittal, please contact Mr. Dan Westcott, Manager, Nuclear Regulatory Affairs, at (352) 563-4796.

Blair P. Wunderly Plant Manager Crystal River Nuclear Plant BPW/ff

Attachment:

2013 Annual Radioactive Effluent Release Report xc:

NRR Project Manager Regional Administrator, Region I 6-ý (A~

It ZAý U-'

DUKE ENERGY FLORIDA, INC.

DOCKET NUMBER 50 - 302 / LICENSE NUMBER DPR - 72 ATTACHMENT 2013 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2013

,* DUKE ENERGY.

DUKE ENERGY FLORIDA, INC CRYSTAL RIVER UNIT 3 Facility Operating License No. DPR-72 Docket No. 50-302 4k elemmu Prepared By:

Rudv Pinner

- -TT -I*" El.

1111 Sr. Scientist

/

Aauýý Approved By:

Brvant Akins

-- w r J*-

Manager Radiation Protection 8fChemistry Date: 03-24-2014

CONTENTS In tro d u c tio 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 Abnorm al Release Sum m ary.....................................................................................

12 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 M onitor Instrum ent O perability.....................................................................

19 M eterology Instrum entation Evaluation.....................................................................

20 O DCM Changes.........................................................................................................

20 Process Control Program Changes...........................................................................

21 Em ergency Feed Pum p 2.........................................................................................

21 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.

I

EFFLUENT and WASTE DISPOSAL REPORT-2013 Table 1A - Regulatory Guide 1.21 Gaseous Effluents - Summation of All Releases Unit: 3 Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Est. Total

% Error A. Fission & Activation Gases

1. Total Release Curies O.OOE+oo O.OOE+O0 O.OOE+O0 O.OOE+O0 3.00E+011I
2. Average Release Rate for Period uCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 B. Iodines
1. Total Iodine-131 Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.00E+01 I
2. Average Release Rate for Period uCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 C. Particulates
1. Particulates with half-lives > 8 days Curies O.OOE+00 2.36E-07 O.OOE+00 6.98E-07 3.OOE+01 I
2. Average Release Rate for Period uCi/sec O.OOE+00 3.01E-08 O.OOE+00 8.78E-08
3. Gross Alpha Radioactivity Curies 3.73E-08 O.OOE+00 4.02E-08 2.36E-09 D. Tritium
1. Total Release Curies 7.80E-01 1.14E+00 9.77E-01 7.25E-01 3.OOE+01 I
2. Average Release Rate for Period uCi/sec 1.00E-01 1.44E-01 1.23E-01 9.12E-01 I 2

EFFLUENT and WASTE DISPOSAL REPORT-2013 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 Iodines 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-2013 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 Iodines

[

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-2013 Table 1C - Regulatory Guide 1.21 Gaseous Effluents - Ground Unit: 3 Batch Mode 2nd Qtr Units 1st Qtr 3rd Qtr 4th Qtr Fission & Activation Gases

ýotal Curies N/D N/D N/D N

Iodines

ýotal Curies N/D N/D N/D NI Particulates

ýotal Curies N/D N/D N/D NI 1H-3 Curies N/D N/D N/D NI/D

ýGross Alpha Curies N/D N/D N/D N

5

EFFLUENT and WASTE DISPOSAL REPORT-2013 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 Iodines Total Curies N/D N/D N/D N/D Particulates Cs-137 Curies N/D 2.36E-07 N/D 6.98E-07 Total Curies N/D 2.36E-07 N/D 6.98E-07 H-3 Curies 7.80E-01 1.14E+00 9.77E-01 7.25E-01 Gross Alpha Curies 3.73E-08 N/D 4.08E-08 2.36E-09 6

EFFLUENT and WASTE DISPOSAL REPORT-2013 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 1.60E-05 1.57E-04 6.10E-03 5.01E-04 2.50E+01

2. Average diluted concentration during period uCi/ml 8.64E-14 6.20E-13 2.23E-11 2.52E-12
3. Percent of Applicable Limit 3.09E-07 2.32E-06 3.59E-05 7.98E-06 B.

Tritium

1. Total Release Curies 1.42E-01 5.69E+00 6.56E+00 6.70E+00 3.OOE+01
2. Average diluted concentration during period uCi/ml 7.68E-10 2.24E-08 2.39E-08 3.37E-08
3. Percent of Applicable Limit 7.68E-06 2.24E-04 2.39E-04 3.37E-04 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 O.OOE+00 O.OOE+00 O.OOE+00 3.00E+O01 E.

Waste Volume Released (Pre-Dilution)

Liters 2.13E+06 2.73E+06 4.01E+06 2.79E+06 1.00E+01 F.

Dilution Water Volume During Period Liters 1.85E+11 2.54E+11 2.74E+11 1.99E+11 1.00E+01 7

EFFLUENT and WASTE DISPOSAL REPORT-2013 Table 2B - Regulatory Guide 1.21 Liquid Effluents - Batch Mode Unit: 3 I Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Fission & Activation Products Mn-54 Curies N/D N/D 8.71E-06 2.79E-06 Fe-55 Curies N/D N/D 2.73E-03 7.14E-05 Co-60 Curies 1.54E-05 1.04E-04 2.56E-03 1.64E-04 Ni-63 Curies N/D N/D 7.02E-04 1.56E-04 Ag-l10m Curies N/D 3.39E-06 N/D N/D Sb-125 Curies N/D 2.72E-05 N/D 5.48E-06 Cs-134 Curies N/D N/D 1.84E-06 1.90E-06 Cs-137 Curies 5.82E-07 2.26E-05 9.54E-05 9.92E-05 Total Curies 1.60E-05 1.57E-04 6.10E-03 5.01E-04 Dissolved and Entrained Gases Total Curies N/D N/D N/D N/D H-3 Curies 1.42E-01 5.69E+00 6.56E+00 6.70E+0O Gross Alpha Curies N/D N/D N/D N/D 8

EFFLUENT and WASTE DISPOSAL REPORT-2013 Table 2B - (Continued) Regulatory Guide 1.21 Liquid Effluents - Continuous Mode Unit: 3 I Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr I 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 1.48E-04 Gross Alpha Curies N/D N/D N/D N/D 9

EFFLUENT and WASTE DISPOSAL REPORT-2013 Regulatory Guide 1.21 Gaseous Batch Release Summary Unit: 3 Jan - Jun Number of Batch Releases Total Time Period for Batch Releases Maximum Time Period for a Batch Release Average Time Period for a Batch Release Minimum Time Period for a Batch Release 6

3.63E+03 min 1.04E+03 min 6.06E+02 min 3.09E+02 min Jul - Dec 0

O.OOE+00 min O.OOE+00 min O.OOE+0O min O.OOE+00 min I0

EFFLUENT and WASTE DISPOSAL REPORT-2013 Regulatory Guide 1.21 Liquid Batch Release Summary Unit: 3 Number of Batch Releases Total Time Period for Batch Releases Maximum Time Period for a Batch Release Average Time Period for a Batch Release Minimum Time Period for a Batch Release Average Stream Flow During Release Periods Jan - Jun 36 7.65E+03 min 4.15E+02 min 2.13E+02 min 2.20E+01 min 2.62E+05 gpm Jul - Dec 74 1.18E+04 min 4.20E+02 min 1.60E+02 min 5.OOE+01 min 3.76E+05 gpm I1

EFFLUENT and WASTE DISPOSAL REPORT-2013 Regulatory Guide 1.21 Gaseous Abnormal Release Summary Unit: 3 Jan - Jun Number of Abnormal Releases Total Time Period for Abnormal Releases Maximum Time Period for an Abnormal Release Average Time Period for an Abnormal Release Minimum Time Period for an Abnormal Release Total Activity for Abnormal Releases 0

O.OOE+00 min O.OOE+00 min O.OOE+00 min 0.OOE+00 min 0.OOE+00 Ci Jul - Dec 0

O.OOE+00 min O.OOE+00 min O.OOE+00 min 0.OOE+00 min 0.00E+00 Ci 12

EFFLUENT and WASTE DISPOSAL REPORT-2013 Regulatory Guide 1.21 Liquid Abnormal Release Summary Unit: 3 Jan - Jun Number of Abnormal Releases Total Time Period for Abnormal Releases Maximum Time Period for an Abnormal Release Average Time Period for an Abnormal Release Minimum Time Period for an Abnormal Release Total Activity for Abnormal Releases 0

0.OOE+00 min 0.OOE+00 min 0.OOE+00 min 0.OOE+00 min 0.OOE+00 Ci Jul - Dec 0

O.OOE+00 min O.OOE+00 min O.OOE+00 min O.OOE+00 min O.OOE+00 Ci 13

EFFLUENT and WASTE DISPOSAL REPORT-2013 Regulatory Guide 1.21 Gaseous NNG Organ Dose Unit: 3 Receptor Name: Infant Max Ind NW at 1.34 km 1s Quarter 2 nd Quarter 3 rd Quarter I4t Quarter Calendar Year 0/ of

%/ of

%/ of

%/ of

%/ of Organ Dose ODCM Dose ODCM Dose ODCM Dose ODCM Dose ODCM Limit Limit Limit Limit Limit Bone 1.87E-04 2.50E-03 2.81E-04 3.75E-03 2.35E-04 3.13E-03 2.OOE-04 2.67E-03 9.03E-04 6.02E-03 Liver 1.87E-04 2.50E-03 2.83E-04 3.77E-03 2.35E-04 3.13E-03 2.04E-04 2.72E-03 9.08E-04 6.05E-03 Total Body 1.87E-04 2.50E-03 2.75E-04 3.66E-03 2.35E-04 3.13E-03 1.80E-04 2.40E-03 8.77E-04 5.84E-03 Thyroid 1.87E-04 2.50E-03 2.74E-04 3.65E-03 2.35E-04 3.13E-03 1.78E-04 2.38E-03 8.74E-04 5.83E-03 Kidney 1.87E-04 2.50E-03 2.76E-04 3.69E-03 2.35E-04 3.13E-03 1.85E-04 2.47E-03 8.83E-04 5.89E-03 Lung 1.87E-04 2.50E-03 2.75E-04 3.67E-03 2.35E-04 3.13E-03 1.81E-04 2.41E-03 8.78E-04 5.85E-03 GI-Lli 1.87E-04 2.50E-03 2.74E-04 3.65E-03 2.35E-04 3.13E-03 1.78E-04 2.38E-03 8.74E-04 5.83E-03 Maximum Organ was LIVER.

14

EFFLUENT and WASTE DISPOSAL REPORT-2013 Regulatory Guide 1.21 Liquid Organ & Whole Body Dose Unit: 3 Receptor Name: Adult W at 1.34 km 1s Quarter 2 nd Quarter 3 rd Quarter 4th Quarter Calendar Year

% of

% of

% of

% of

/of Organ Dose ODCM Dose ODCM Dose ODCM Dose ODCM Dose ODCM Limit Limit Limit Limit Limit Bone 7.27E-09 1.45E-07 5.65E-07 1.13E-05 1.45E-03 2.91E-02 5.21E-05 1.04E-03 1.51E-03 1.51E-02 Liver 8.54E-09 1.71E-07 7.29E-07 1.46E-05 8.27E-04 1.65E-02 1.57E-05 3.15E-04 8.44E-04 8.44E-03 Total Body 9.94E-09 6.63E-07 5.61E-07 3.74E-05 2.01E-04 1.34E-02 5.35E-06 3.57E-04 2.07E-04 6.91E-03 Thyroid 7.14E-09 1.43E-07 1.63E-07 3.25E-06 3.88E-07 7.76E-06 2.81E-07 5.62E-06 8.39E-07 8.39E-06 Kidney 7.20E-09 1.44E-07 3.50E-07 6.99E-06 1.63E-06 3.26E-05 9.18E-07 1.84E-05 2.90E-06 2.90E-05 Lung 7.16E-09 1.43E-07 2.25E-07 4.50E-06 4.48E-04 8.97E-03 6.73E-06 1.35E-04 4.55E-04 4.55E-03 GI-Lli 3.OOE-08 6.OOE-07 6.88E-07 1.38E-05 4.81E-04 9.63E-03 8.OOE-06 1.60E-04 4.90E-04 4.90E-03 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-2013 Regulatory Guide 1.21 Liquid App I Dose Assessment Unit: 3 Adult W at 1.34km Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual Maximum Organ Dose mRem 7.27E-09 5.65E-07 1.45E-03 5.21 E-05 1.51E-03 ODCM Limit mRem 5.00 5.00 5.00 5.00 10.00

% of ODCM Limit 1.45E-07 1.13E-05 2.91E-02 1.04E-03 1.51E-02 Maximum Organ was Bone Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual Total Body mRem 9.94E-09 5.61 E-07 2.01 E-04 5.35E-06 2.07E-04 ODCM Limit mRem 1.50 1.50 1.50 1.50 3.00

% of ODCM Limit 6.63E-07 3.74E-05 1.34E-02 3.57E-04 6.91 E-03 16

EFFLUENT and WASTE DISPOSAL REPORT-2013 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

[Beta Air mRad 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+0 ODCM Limit mRad 10.00 10.00 10.00 10.00 20.00 0% of ODCM Limit 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0(

Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual Oamma Air mRad O.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+0::

ODCM Limit mRad 5.00 5.00 5.00 5.00 10.0-1% of ODCM Limit 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+0 Gaseous Release Dose Summary Note: There were no noble gases released in 2013 due to the extended plant shutdown from refueling outage 16 that began in September 2009. The plant remains shutdown in mode 7 (defueled) for all of 2010, 2011, 2012, and 2013 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-2013 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.

SOLID WASTE SHIPPED OFFSITE FOR PROCESSING OR BURIAL (Non-irradiated fuel)

1.

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

m3 1.01E+01 25

a.

Spent resins, filter sludges, evaporator bottoms, etc.

m3 1.0E+01 Ci 7.80E+01 m3 3.71E+02 25

b.

Dry compressible waste, contaminated equipment, etc.

m3 1E.02E25 Ci 1.02E-01 m3 0.00E+00 25

c.

Irradiated components, control rods, etc.

Ci 0.OOE+00 25 m3 5.81 E-01 25

d.

Other (describe): Combined DAW package Ci 3.98E+00 25

2.

Estimate of major nuclide composition (by type of waste In %)*

Fe-55 4.01 Co-60 5.69 Cs-137 42.51

a.

Sb-125 0.14 Ni-63 45.20 Sr-90 0.27 Mn-54 0.04 Ni-59 0.33 Ce-144 0.02 C-14 0.17 Cs-134 1.60 C-14 8.80 Ni-63 34.70 Zn-65 0.07

b.

Fe-55 7.25 Mn-54 1.24 Ag-110m 0.07 Co-60 42.43 Cs-137 4.23 Ce-144 0.03 Sb-1 25 0.90 Cs-1 34 0.24 Co-57 0.04

c.

N/A N/A N/A Mn-54 4.24 Ni-63 10.57 Cs-137 20.03

d.

Fe-55 0.24 Zr-95 1.49 Ce-144 4.66 Co-57 0.05 Ag-110m 4.19 Co-58 18.61 Cs-134 10.70 Co-60 25.21

  • 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 09 11 04 Truck Shipments Truck Shipments Truck Shipments Energy Solutions Energy Solutions-Bear Creek Studsvik Processing Facility, LLC Destination N/A B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation 0

N/A 18

Unplanned Releases There were no unplanned releases in 2013.

Radioactive Waste Treatment Systems There were no significant changes to the radioactive waste treatment systems in 2013. Due to the lengthy shutdown of Crystal River Unit 3, liquid waste volume and radioactivity concentration had continued to decrease until the decision to retire CR3 and begin decommissioning was made in February of 2013. As part of the preparation to place the unit in SAFSTOR, liquid waste inventory of all systems no longer required to support spent fuel cooling are being processed for discharge as liquid wastes, where possible. The liquid waste demineralizers were recharged with new condensate resin that was previously loaded into the condensate demineralizers to support the plant restart from the refuel 16 outage. This resin is a 2:1 cation to anion macroporous gel mixture of Ambersep 200H cation resin and IRN78 anion resin. This resin has performed extremely well while processing higher activity waste tanks including reactor coolant and borated water refueling water.

Annual Land Use Census The 2013 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. There continued to be no reactor building purge evolutions performed in 2013.

The 3 waste gas decay tanks (WGDTs), which had previously been emptied of radioactive gases, were purged with nitrogen gas, isolated, and permanently taken out of service to support decommissioning.

During the time period these releases were to occur, the flow instrument used to measure release rate (WD-19-FQI) became inoperable on 4-24-13. The ODCM (section 2.2, table 2-3, item 1.b, action 26) allows WGDT releases to be made with this instrumentation out of service as long as flow estimates are made once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. This action was performed when needed. The flow instrument was inoperable for more than 30 days. Since the WGDTs have been abandoned, this instrumentation will not be repaired. Condition report 605656 documents this evolution.

Additionally, the WGDT radioactive gaseous release monitor, RM-A11,which is utilized for monitoring WGDT permitted discharges, is being abandoned to support decommissioning activities described above.

Once all of the WGDTs were purged with nitrogen and permanently removed from service, surveillance activities on RM-A1 1 have been permanently suspended. Condition report 622740 documents this evolution.

19

Meterology Instrumentation Evaluation During 2013 the yearly instrumentation data recovery for all meterology tower instruments has remained in the range of > or = 99.64%. Actual meterological tower data is available and is maintained at the Crystal River site. The actual meterological data is not provided in this report as is allowed by the ODCM.

Offsite Dose Calculation Manual (ODCM) Changes The ODCM was not revised in 2013.

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.
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.

0 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 20

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 "f" 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 2013.

Emergency Feed Pump 2 & Steam Releases Emergency Feed Pump 2 (EFP-2) over-speed testing is performed quarterly using steam from CR-3's 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 2013 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 was still shutdown for the containment building wall repair in 2013. The emergency feed pump 2 has not operated and there were no secondary plant steam releases during 2010, 2011, 2012, or 2013. Based on the decision to retire and decommission CR-3, the emergency feed pump 2 will never operate again and there will be no steam releases.

Xe-133 0.00E+00 1-131 0.OOE+0 Cs-137 0.00E+00 Xe-135 0.OOE+00 1-133 0.OOE+0 H-3 0.OOE+00 Carbon-14 Evaluation During the entire year of 2013, Crystal River Unit 3 has been in a cold shutdown, defueled mode. The plant was taken off line in September of 2009 for refueling outage 16. In 2009, the primary 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, 2012, and 2013 due to reactor building containment wall delamination issues, there is no source term generation for carbon-14 production in 2010, 2011, 2012, or 2013. Since the decision to retire the facility has been announced, there will be no C-14 source term generated ever again at CR-3.

21

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 assist in evaluation of 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/l.

22

Tfldum NWessmuntW GW Wel 0 MWCF2 600s S00 400 i¶ A4A A__

w.lI 12271 200 100 Lýý LU18110 0411/2 6

D1/

0 --

10/01W0 0222f0" 07/06109 11/18110 04/01112 0O/14/3 12/27/14 Thilum Mmourement. Gw WON 0 LWC47 1400 1200 1000 600 600 400 200 lN 12,27/1 ILr N

11/18/10 04101/12 t

¶Z~

06/14/13 o

4W~W 02/22106 07/06109 t0/10/06 02r 22108 07/06(09 11 !18/1 04/01112 06114/13 12M2"11 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 delaminated 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.

The plant staff (called decommissioning transition organization) is working to shutdown and abandon as many systems as possible, by removing energy sources, lubrications, greases, electrical, and system fluids to prepare the unit for SAFSTOR and eventual dismantlement.

24

Retrieved from "https://kanterella.com/w/index.php?title=3F0314-06,_2013_Annual_Radioactive_Effluent_Release_Report&oldid=5212511"