ML091140598

Annual Radioactive Effluent Release Report 2008

ML091140598
Person / Time
Site:	Crystal River
Issue date:	03/09/2009
From:	Pinner R Progress Energy Co, Progress Energy Florida
To:	Office of Nuclear Reactor Regulation
References
Download: ML091140598 (18)

Text

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2008 Progress, Energy PROGRESS ENERGY FLORIDA, INC CRYSTAL RIVER UNIT 3 Facility Operating License No. DPR-72 Docket No. 50-302 Prepared By: &LCL 1 M'M2A Sr. Scienc4 and Lab Services Specialist Approved By: _ _ _ _ _ _ _

Superintendent En\i'ronmental and Chemistry Date: 3/2/0

CONTENTS In r d ctntr.................du.............t.........on.......................1...

Tabular Data Summaries Gaseous Effluents - Quarters 1 & 2......................................................... 2 Gaseous Effluents - Quarters 3 & 4......................................................... 4 Liquid Effluents - Quarters 1 & 2........................................................... 6 Liquid Effluents - Quarters 3 & 4........................................................... 9 Radwaste Shipments.................................................................................... 12 Unplanned Releases..................................................................................... 13 Radioactive Waste Treatment Systems............................................................... 13 Annual Land Use Census.............................................................................. 13 Effluent Monitor Instrument Operability............................................................. 13 ODCM & PCP Changes................................................................................ 13 Emergency Feed Pump 2 ............................................................................... 13 Appendix I Dose Summary............................................................................ 14 NEI 07-07 Required Data.............................................................................. 15

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.

TABLE I EFFLUENT AND WASTE DISPOSAL REPORT - 2008 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 11 2 Error %

A. Fission and activation gases I. Total release Ci 3.09E+00 O.OOE+00 30

2. Average release rate for period ACi/sec 3.93E-01 0.OOE+00

3. Percent of technical specification limit  % 3.OOE-03 0.OOE+00 B. lodines

1. Total Iodine-131 Ci 1.02E-06 0.OOE+00 30 ]

2. Average release rate for period ACi/sec 1.30E-07 0.OOE+00

3. Percent of technical specification limit  % 2.34E-02 0.OOE+00 C. Particulates*

1. Particulates with half-lives > 8 days Ci 1.08E-06 0.OOE+00 30

2. Average release rate for period gCi/sec 1.38E-07 0.00E+00

3. Percent of technical specification limit  % 2.34E-02 O.00E+00

4. Gross alpha radioactivity Ci 5.47E-08 7.91E-09 D. Tritium I. Total release Ci 4.77E+00 4.49E+00 30

2. Average release rate for period pCi/sec 5.93E-01 5.71E-01

3. Percent of technical specification limit  % I 2.34E-02 J 1.37E-02

• The sum of the particulates reported on this page may be less than the sum from Table 2, as Table 2 includes all particulates, while this table includes only those with half-lives greater than 8 days.

2

TABLE 2 EFFLUENT AND WASTE DISPOSAL REPORT - 2008 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES A. Fission gases Argon-41 Ci __________

Krypton-85 Ci __________ __________ 4. 1OE-01 __________

Krygton-85m Ci __________

Krypton-87 Ci __________

Krygton-88 Ci ___________ _________

Xenon-131m Ci _________ __ ______

Xenon-l33 Ci 2.34E1-00 2.19E-01 Xenon-l33m Ci _________ _________

Xenon-l35 Ci 1. 14E-0lI__________ 6.OOE-03 __________

Xenon-135m Ci _________ _________

Xenon-13 8 Ci _________ _________

Total for period Ci 2.46E+00 O.OOE+OO 6.35E-01 O.OOE+00 B. lodines Iodinie-l31 Ci 1.02E-06 ___________ __________ __________

Iodine-132 Ci ___________ ___________ _________ __________

Iodirie-133 J Ci ___________ ___________ _________ __________

Iodine-135 Ci J

C ___________ ___________ _________ _________

Total for period Ci 1.02E-06 O.OOE+OO O.OOE+OO O.OOE+OO C. Particulates Zinc-72 Ci ___________ ___________ _________

Cobalt-58* Ci 6.38E-07 ____________ 6.08E-08 ___________

Cobaslt.6O* Ci Stroiltium-89* Ci ___________ __________

Strofitium-9O* Ci ___________ ____________ ___________ ____ _______

Niobium-95m Ci Technicium-99m Ci ___________ ________

Tellurium-132 Ci Cesium-l34* Ci-Cesium-I37* Ci 3.65E-07 1.73E-08 Cesium-138 Ci Barium-139 Ci ___________ ___________

Lanthanum-l42 Ci Cerium-l4l* Ci Cerium-I43* Ci Rheriium-188 Ci __________ __________ _________ __________

Total for period Ci 1.00,E-06 O.OO13+00 7.80E-08 O.OOEi-OO

• > 8 day half-life 3

TABLE 3 EFFLUENT AND WASTE DISPOSAL REPORT - 2008 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 3 4 Error %

A. Fission and activation gases I. Total release Ci 1.78E-01 O.OOE+00 30

2. Average release rate for period jiCi/sec 2.24E-02 0.OOE+00

3. Percent of technical specification limit  % 2.63E-04 0.OOE+00 B. lodines

1. Total Iodine-131 Ci 0.OOE+00 0.00E+00 30

2. Average release rate for period ltCi/sec 0.00E+00 0.00E+00

3. Percent of technical specification limit  % 0.00E1+00 0.00E+00 C. Particulates*

I. Particulates with half-lives > 8 days Ci 0.00E+00 00.0E00 30

2. Average release rate for period piCi/sec 0.00E+00 0.00E+00

3. Percent of technical specification limit  % 0.00E+00 0.00E+00

4. Gross alpha radioactivity Ci 5.60E-09 5.37E-09 D. Tritium I. Total release Ci 2.96E+00 3.34E+00

2. Average release rate for period pCi/sec I 3.72E-01 4.21E-01

3. Percent of technical specification limit  % 9.47E-03 I 1.07E-02

• The sum of the particulates reported on this page may be less than the sum from Table 4, as Table 4 includes all particulates, while this table includes only those with half-lives greater than 8 days.

4

TABLE 4 EFFLUENT AND WASTE DISPOSAL REPORT - 2008 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES A. Fission gases Argon-41 Ci Krypton-85 Ci 1.61E-01 Krypton-85m Ci Kyton-87 Ci _________

Krypton-88 Ci _________

Xenon-131m Ci ________

Xenon-133 Ci 1.65E-02 Xenon-133m Ci _________

Xenon- 13 5 Ci ________

Xenon-135m Ci _________

Xenon-138 Ci Total for period Ci O.OOE--OO O.OOE+OO 1.78E-01 0.OEO B. Jodines Iodine-131 Ci ___________I_____________________I__________

lodine-132 Ci __________I lodirie-133 Ci __________

Iodioie-135 Ci Total for period Ci O.OOE+OO O.OOE+/-OO O.OOE-i-O O.OOE+OO0 C. Particulates Zinc-72 Ci _________

Cobalt-58* Ci

-Chromium-5lI Ci ________

Strontium-89* Ci Strovitium-9O* Ci ________

Niobium-95* Ci _________

Tin-1ll3* Ci ________

Indium- I 13m Ci _________

Barium-133m Ci _______

Cesium-l37* Ci __________

Cesium-138 Ci __________

Barium-139 Ci ________

Lanthanum-142 Ci ________

Cerium-141 Ci Cerium-143 Ci Cerium-144* Ci _________ ___________________ _________

Rhenium-188 Ci _____________________________________________

Total for period Ci O.OOE+/-OO O.OOE--OO O.OOE-+0O O.OOE+/-OO

• > 8 day half-life 5

TABLE 5 EFFLUENT AND WASTE DISPOSAL REPORT - 2008 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 1 2 Errorr %

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 2.77E-03 2.60E-03

2. Average diluted concentration during period PCi/ml 5.38E-12 4.39E-12

3. Percent of applicable limit  % 6.81E-04 4.00E-04 B3. Tritium

1. Total release Ci 1.27E+02 6.95E+01 30

2. Average diluted concentration during period ACi/ml 2.47E-07 1.17E-07

3. Percent of applicable limit  % 1.89E-01 1.21E-01 C. Dissolved and entrained gases

1. Total release Ci 7.12E-03 8.11E-04 25

2. Average diluted concentration during period ACi/ml 1.38E-11 1.37E-12

3. Percent of applicable limit  % 5.30E-04 7.07E-05 D. Gross alpha radioactivity I. Total release Ci 2.44E-05 5.56E-05 30 E. Volume of waste released (prior to dilution)

I1. Batch and continuous modes Liters 1.21E+07 7.81E+06 1o F. Volume of dilution water used during period I. Batch and continuous modes Liters 5.14E+11 5.92E+1 10I 6

TABLE 6 EFFLUENT AND WASTE DISPOSAL REPORT - 2008 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Fission and activation products Unit Quarter I Quarter 2 Quarter 1 Quarter 2 Sodium-24 Ci Chromium-51 Ci Manganese-54 Ci 4.09E-05 6.18E-05 Manganese-56 Ci Iron-55 Ci 2.41 E-04 1.74E-04 Iron-59 Ci Cobalt-57 Ci Cobalt-58 Ci 5.71E-04 8.35E-04 Cobalt-60 Ci 1.41E-03 1.28E-03 Zinc-69 Ci Strontium-85 Ci Strontium-89 Ci Strontium-90 Ci Yttrium-91m Ci Yttrium-92 Ci Yttrium-93 Ci Niobium-95 Ci 4.42E-06 9.23E-05 Niobium-95m Ci Niobium-97 Ci Zirconium-95 Ci 1.56E-05 Zirconium-97 Ci Molybdinum-99 Ci Technetium-99m Ci Technetium-101 Ci Ruthenium-103 Ci Ruthenium-106 Ci Silver-I lO1m Ci 1.49E-04 5.64E-05 Tin-113 Ci Indium-1 13m Ci Antimony-122 Ci Antimony-124 Ci, Antimony-125 Ci 2.59E-04 5.96E-05 Tellurium-129 Ci Tellurium-132 Ci Iodine-131 Ci Iodine-133 Ci Iodine-135 Ci Cesium-134 Ci Cesium-137 Ci 7.02E-05 2.39E-05 Cesium-138 Ci Barium-133m Ci 2.61E-05 Barium-140 Ci Lanthanum-140 Ci Cerium-141 Ci Cerium-143 Ci Neodymium-147 Ci Tungsten-187 Ci Neptunium--239 Ci Nickle-63 Ci Total for period Ci O.OOE+00 O.OOE+00 2,77E-03 2160E-03 7

TABLE 6 (CONTINUED)

EFFLUENT AND WASTE DISPOSAL REPORT - 2008 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Dissolved and entrained gases Unit Quarter 1 Quarter 2 Quarter I Quarter 2 Argon-41 Ci Krypton-85 Ci 7.00E-04 Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon- 131 m Ci Xenon-133 Ci 6.12E-03 8.OOE-04 Xenon-133m Ci 2.78E-05 Xenon-135 Ci 2.71E-04 1.1OE-05 Xenon-135m Ci Total for period Ci O.OOE+00 O.OOE+00 7.12E-03 8.11E-04 Tritium Ci 1.82E-01 O.OOE+00 1.27E+02 6.95E+01 8

TABLE 7 EFFLUENT AND WASTE DISPOSAL REPORT - 2008 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 11 3 1 4 Error%

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 1.07E-03 9.28E-04 25

2. Average diluted concentration during period PsCi/ml 1.99E-12 1.75E-12

3. Percent of applicable limit  % 3.59E-04 1.59E-04 B. Tritium

1. Total release Ci 5.81E+01 9.29E+01 30

2. Average diluted concentration during period ACi/ml 1.08E-07 1.75E-07

3. Percent of applicable limit  % 9.98E-02 1.52E-01 C. Dissolved and entrained gases

1. Total release Ci 9.19E-04 1.18E-03 25: ]

2. Average diluted concentration during period lCi/ml 1.71E-12 2.22E-12

3. Percent of applicable limit  % 7.89E-05 9.64E-05 D. Gross alpha radioactivity I. Total release Ci 0.o1oo00 o .OOE+00 30 E. Volume of waste released (prior to dilution)

1. Batch and continuous modes Liters 1.07E+07 8.14E+06 10 F. Volume of dilution water used during period

1. Batch and continuous modes Liters 5.37E+1 5.31E+ll 10 9

TABLE 8 EFFLUENT AND WASTE DISPOSAL REPORT - 2008 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Fission and activation products Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Sodium-24 Ci Chromium-51 Ci Manganese-54 Ci 1.82E-05 9.93E-07 Manganese-56 Ci Iron-55 Ci 1.56E-04 2.68E-04 lron-59 Ci Cobalt-57 Ci Cobalt-58 Ci 9.3 1E-05 2.98E-06 Cobalt-60 Ci 3.56E-04 4.13E-05 Zinc-69 Ci Zinc-72 Ci Strontium-85 Ci Strontium-89 Ci Strontium-90 Ci Strontium-92 Ci Yttrium-91 Ci Yttrium-92 Cim Yttrium-93 Ci Rubidium-88 Ci Niobium-95 Ci 2.63E-05 Niobium-95m Ci Zirconium-95 Ci Molybdinum-99 Ci Technetium-99m Ci Technetium-101 Ci Ruthenium-106 Ci Silver-I lOmn Ci 1.99E-05 Tin-1 13 Ci Indium- 113m Ci Antimony-122 Ci Antimony-124 Ci Antimony-125 Ci 1.11E-05 5.34E-06 Tellurium-129 Ci Tellurium-132 Ci Iodine-131 Ci Iodine-133 Ci Iodine-135 Ci Cesium-134 Ci Cesium-137 Ci 4.15E-05 1.38E-05 Barium-133m Ci Barium-139 Ci Barium-140 Ci Lanthanum-140 Ci Cerium-141 Ci Cerium-143 Ci Praseodymium-144 Ci Neodymium-147 Ci Neptunium-239 Ci Nickel-63 Ci 3.46E-04 5.95E-04 Rhenium-188 Ci Total for period Ci O.OOE+00 O.OOE+00 1.07E-03 9.28E-04 10

TABLE 8 (CONTINUED)

EFFLUENT AND WASTE DISPOSAL REPORT - 2008 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE, Dissolved and entrained gases Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon- 131 m Ci Xenon-133 Ci 8.96E-04 1.16E-03 Xenon-133m Ci Xenon-135 Ci 2.31E-05 2.83E-05 Xenon-135m Ci Total for period Ci O.OOE+00 O.OOE+00 9.19E-04 1.19E-03 Tritium Ci 1.68E-01 O.OOE+00 5.79E+O1 9.29E+01 11

TABLE 9 EFFLUENT AND WASTE DISPOSAL REPORT - 2008 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 6.04E+01 25

a. Spent resins, filter sludges, evaporator bottoms, etc. Ci 3.43E+02125 m3 2.00E+02 25 Dry compressible waste, contaminated equipment, etc. m3 3.60E-02 25

b. Ci 3.60E-01 m3 0.00E+00 25 25

c. Irradiated components, control rods, etc. m3 0.00E+00 Ci 0.00E+00 m3 3.63E+01 25 25

d. Other (describe): Combined DAW package Ci 8.86E+00

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

Mn-54 1.1 Co-60 7.4. Cs-134 14.5

a. Fe-55 11.5 Ni-63 31.2 Cs- 137 34.0 Ce-144 0.25 Ni-63 45.4 Co-58 2.8

b. Fe-55 32.0 Mn-54 0.34 C-14 4.8 Co-60 11.9 Cs-137 1.4 Pu-241 0.82

c. N/A N/A N/A Fe-55 6.3 Ce-144 0.6 Zr-95 1.2

d. Co-58 18.1 Cs-134 22.6 H-3 1.8 Co-60 3.6 Cs-137 24.5 C-14 1.0 Ni-63 4.5 Nb-95 15.1

• 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 5 Hittman Transport Services Clive Disposal Facility 1 Hittman Transport Services DURATEK 5 Hittman Transport Services. DURATEK - Bear Creek 6 Hittman Transportation Studsvik Processing Facility, LLC B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination 0 N/A N/A 12

Unplanned Releases There were no unplanned releases in 2008.

Radioactive Waste Treatment Systems There were no significant changes to the radioactive waste treatment systems.

Annual Land Use Census The 2008 land-use census did not identify any new dose calculation locations.

Effluent Monitor Instrument Operability Required effluent monitor instrumentation was not out of service for more than 30 days during 2008.

ODCM & PCP Changes The ODCM was revised once in 2008. Revision 31 incorporated an updated protocol for voluntary communication regarding leaks or spills of radioactive material that could potentially reach groundwater, per the guidance in the final version of NEI 07-07, Industry Groundwater Protection Initiative Guidance Document. The remainder of changes are enhancements that include:

labeling of dose table names at the top of each table, correction of an equation that was missing a division sign on page 110, added Appendix I dose calculation exemption criteria associated with settling pond releases to document that liquid releases to the settling ponds are insignificant in relationship to the other liquid effluent pathways, added a summary table of unrestricted and controlled area dose limits for members of the public to provide a composite collection of the various limits into one discussion for ease of understanding. On pages 11 and 16, added guidance for RM-A I (RB Purge Exhaust monitor) trip function requirements when moving fuel (from ITS 3.3.15) for clarity. On page 140, modified the location descriptor for environmental air sample station C40, as this station was relocated from underneath the dense tree canopy area just north of the plant access road, to along the power line corridor, adjacent to the plant access road, keeping within the same sector locale.

The PCP was not revised in 2008.

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 small primary to secondary leak, an evaluation was performed to estimate the quantity of radioactive material which was released during 2008 due to operation of this pump. In addition, radioactive releases due to other steam releases have been estimated and included. These values include any plant trips with associated secondary plant atmosphere steam relief valve initiation. The results are given below in units of Curies/year.

Xe-133 1.80E-07 1-131 4.50E-09 Cs-134 7.50E-11 Xe-135 1.95E-07 1-133 5.25E-08 Cs-137 2.25E-10 H-3 1.35E-05 These values are not included in Tables 1 through 4.

13

2008 Appendix I Dose Summary Maximum Hypothetical Individual Liquid Effluent Dose Limits Total Body: 1.5 mrem/quarter, 3 mrem/year Any Organ: 5 mrem/quarter, 10 mrem/year Liquid Effluent Dose Summary Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Total Total Body Dose (mrem) 1.02E-05 2.86E-06 5.38E-06 2.38E-06 2.08E-05 Maximum Organ Dose (mrem) 3.1 OE-05 2.OOE-05 9.05E-06 7.56E-06 6.76E-05 Maximum Organ was GI 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 Gaseous Release Dose Summary Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Total Gamma Air Dose (mrad) 9.04E-05 0.OOE+00 6.81E-07 0.OOE+00 9.11E-05 Beta Air Dose (mrad) 2.99E-05 0.OOE+00 2.63E-04 0.OOE+00 3.26E-04 Total Body Dose (mrem) 1.11E-03 1.03E-03 7.1OE-04 8.02E-04 3.65E-03 Maximum Organ Dose (mrem) 1.76E-04 1.03E-04 7.09E-04 8.03E-04 1.79E-03 Maximum Organ was Thyroid 14

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/l, taken from groundwater monitoring wells located west of CR-3 on either side of the 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.

15

Tritium Measurements GW Well # MWC4F2 600 500 400 2300 200 F W 100

<LW 0 i I 4 01/18/07 04/28/07 08/06/07 11/14107 02/22/08 06/01108 09/09108 12118/08 03128/09 Tritium Measurements GW Well # MWC-27 1400 1200 1000 8oo 600 400 200 01/18/07 04/28/07 08106/07 11/14/07 02122/08 06/01/08 09/09108 12/18108 03128109 16