ML081230612

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2007 Radioactive Effluent Release Report
ML081230612
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 04/21/2008
From:
Progress Energy Florida
To:
Office of Nuclear Reactor Regulation
References
Download: ML081230612 (18)
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Text

PROGRESS ENERGY FLORIDA, INC.

CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 ATTACHMENT A RADIOACTIVE EFFLUENT RELEASE REPORT 2007

RADIOACTIVE EFFLUENT RELEASE REPORT 2007 PROGRESS ENERGY FLORIDA, INC, CRYSTAL RIVER UNIT 3 Facility Operating License No. DPR-72 Docket No. 50-302 Prepared By: e4d,,

Sr. Scien~e and Lab Services Specialist Approved By:_ _ _ _ _ _ _ _

Superintendent V{vironmentai and Chemistry Date: /4 , /0 RO

CONTENTS Intou t r o d i uc...............................

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.

1

TABLE 1 EFFLUENT AND WASTE DISPOSAL REPORT - 2007 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 1 2 Error %

A. Fission and activation gases

1. Total release
2. Average release rate for period
3. Percent of technical specification limit B. Iodines
1. Total Iodine-131
2. Average release rate for period
3. Percent of technical specification limit C. Particulates*
1. Particulates with half-lives > 8 days Ci [ 0.OOE+00 O.OOE+00 I 3
2. Average release rate for period *tCi/sec O.OOE+00 0.OOE+00
3. Percent of technical specification limit  % 0.OOE+00 0.OOE+00
4. Gross alpha radioactivity Ci 2.24E-08 2.14E-08 D. Tritium
1. Total release Ci 2.01E+00
2. Average release rate for period tiCi/sec 2.58E-01
3. Percent of technical specification limit  % 6.43E-03
  • 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

TABLE2 EFFLUENT AND WASTE DISPOSAL REPORT - 2007 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES A. Fission gases Argon-41 Ci __________

Krypton-85 Ci __________

Krypton-85m Ci ______________________________

Krypton-87 Ci ____________________

Krypton-88 Ci _________

Xenon-131m Ci __________

Xenon-133 Ci ___________3.37E-02 2.02E-01 Xenon-133m Ci __________

Xenon-135 Ci _________ 1 .06E-02 Xenon-135m Ci __________

Xenon-138 Ci __________

Total for period Ci O.OOE+OO O.OOE+OO 3.37E-02 2.1213-01 B. lodines lodine-131 Ci ___________ ___________ _________

Iodine-132 Ci __________ ___________ __________ __________

Iodine-133 Ci ___________ ___________ _________

Iodine-135 Ci ___________ ____________ ___________ ___________

Total for period Ci O.OOE+OO O.OO13+00 O.OOE+OO O.OOE+OO C. Particulates Zinc-72 Ci __________ __________

Cobalt-58* Ci ___________ ___________

Cobalt-6O* Ci1,________ __________

Strontium-89* Ci Strontium-9O* Ci __________

Niobium-95m Ci ______________________ 2.50E-08 Technicium-99m Ci __________ __________

Tellurium-132 C1, ___________ ____________ __________

Cesium-134* Ci ___________ ___________

Cesium-137* Ci Cesium-138 Ci1, _________ ____________ __________

Barium-139 Ci Lanthanum-142 Ci Cerium-141* Ci _________

Cerium-143* Ci 1 .3213-07 _________ _________

Rhenium-188 Ci _________

Total for period Ci O.OOE+OO 1.3213-07 2.50E-08 O.OOE+OO

  • > 8 day half-life 3

TABLE3 EFFLUENT AND WASTE DISPOSAL REPORT - 2007 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 3 4 Error%

A. Fission and activation gases

1. Total release Ci 1.71E-01 4.03E+00 30II
2. Average release rate for period [LCi/sec 2.15E-02 5.07E-01
3. Percent of technical specification limit  % 2.41E-04 4.55E-03 B. lodines
1. Total Iodine-131 Ci O.OOE+00 1.89E-06 30ZZ
2. Average release rate for period tiCi/sec O.OOE+00 2.37E-07
3. Percent of technical specification limit  % O.OOE+00 3.66E-02 C. Particulates*
1. Particulates with half-lives > 8 days Ci O.OOE+00 3.49E-07 30
2. Average release rate for period MuCi/sec O.OOE+00 4.39E-08
3. Percent of technical specification limit  % O.OOE+00 3.66E-02
4. Gross alpha radioactivity Ci 1.08E-08 1.82E-08 D. Tritium
1. Total release Ci 1.67E+00 6.44E+00 30I[
2. Average release rate for period I tCi/sec I2.10E-01 1 8.1 IE-01
3. Percent of technical specification limit T  % 5.35E-03 3.66E-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

TABLE4 EFFLUENT AND WASTE DISPOSAL REPORT - 2007 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES A. Fission gases Argon-41 Ci Krypton-85 Ci 1.39E-01 1.18E+00 Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-131m Ci Xenon-133 Ci 2.83E-01 3.19E-02 2.33E+00 Xenon-133m Ci Xenon-135 Ci 2.34E-01 Xenon-135m Ci Xenon-138 Ci Total for period Ci O.OOE+00 2.83E-01 1.71E-01 3.74E+00 B. Iodines Iodine-131 Ci 1.89E-06 Iodine-132 Ci Iodine-133 Ci Iodine-135 Ci Total for period Ci 0.001E+00 1.89E-06 O.OOE+00 O.OOE+00 C. Particulates Zinc-72 Ci Cobalt-58* Ci 1.95E-07 Chromium-51* Ci Strontium-89* Ci Strontium-90* Ci Niobium-95* Ci Tin-113* Ci Indium-113m Ci Barium-133m Ci Cesium-137* Ci 6.89E-08 8.56E-08 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+00 2.64E-07 O.OOE+00 8.56E-08

  • > 8 day half-life 5

TABLE 5 EFFLUENT AND WASTE DISPOSAL REPORT - 2007 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total I 1 2 Error %

A. Fission and activation products

1. Total release (not including tritium, gases, alpha)
2. Average diluted concentration during period
3. Percent of applicable limit B. Tritium
1. Total release
2. Average diluted concentration during period
3. Percent of applicable limit C. Dissolved and entrained gases
1. Total release
2. Average diluted concentration during period
3. Percent of applicable limit D. Gross alpha radioactivity

[1 Total release Ci 1.97E-05 1.86E-04 30 E. Volume of waste released (prior to dilution)

I1. Batch and continuous modes T Liters 5.81E1+06 6.72E +06 10 F. Volume of dilution water used during period

1. Batch and continuous modes I Liters 4.85E+11 4.99E + 11 10 6

TABLE 6 EFFLUENT AND WASTE DISPOSAL REPORT - 2007 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Fission and activation products Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Sod ium-24 Ci Chromium-51 Ci _________________ __ ______

Manganese-54 Ci __________ __________

Manganese-56 Ci 4.03E-06 Iron-55 Ci ___________ ___________ 2.9113-0 Iron-59 Ci __________ ___________ _________ _____ ____

Cobalt-57 Ci __________ ___________ ____ _____

Cobalt-58 Ci __________ __________ 1.2213-04 7.3 6E-05 Cobalt-60 Ci, _________ .63E-04 1_________ 2.07E-04 Zinc-69 Ci __________ __________

Strontium-85 Ci Strontium-89 Ci ___________ _________ _ 5 .64E-06 Strontium-90 Ci __________ __________

Yttrium-91m Ci Yttrium-92 Ci __________ __________

Yttrium-93 Ci ____ ______

Niobium-95 Ci __________

Niobium-95m Ci __________ __________

Niobium-97 Ci __________

Zirconium-95 Ci ___________2.39E-06 Zirconium-97 Ci __________

Molybdinum-99 Ci __________

Technetium-99m Ci __________

Technetium-101 Ci __________

Ruthenium-103 Ci ___________

Ruthenium-106 Ci Silver-11rn Ci _________ __________ 7.52E-05 2.26E-05 Tin-113 Ci Indiurn-113rn Ci __________ __________

Antimony-122 Ci __________

Antimony-124 Ci Antimony-125 Ci ______________________ 2.66E-05 5.49E-06 Tellurium-129 Ci Tellurium-132 Ci ____ _______

Iodine-131 C0___________ _______ _ 1 .0613-06 Iodine-133 01____________ __________

Iodine-135 Ci Cesium-134 Ci __________ __________ 5.77E-07 7.0413-07 Cesiurn-137 Ci 6.03E-06 7.32E-05 2.4713-05 Cesium-138 Ci Barium-133m Ci ___________

Bariurn-140 Ci __________

Lanthanum-140 Ci Ceriurn-141 Ci Cerium-143 Ci Neodymium-l47 Ci Tungsten-187 Ci ___________ ___________

Neptuniurn--239 Ci Total for period Ci 6.0313-06 O.OOE+OO 4.98E-04 2.91 E-04 7

TABLE 6 (CONTINUED)

EFFLUENT AND WASTE DISPOSAL REPORT - 2007 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Dissolved and entrained gases Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Argon-41 Ci Krypton-85 Ci 2.24E-03 Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-131m Ci 4.31E-05 Xenon-133 Ci 2.98E-03 1.76E-03 Xenon-133m Ci Xenon-135 Ci 1.09E-04 6.89E-05 Xenon-135m Ci Total for period Ci O.OOE+00 O.OOE+00 3.13E-03 4.07E-03 Tritium Ci 5.59E-02 I 0.003+00 2.47E+02 1.11IE+02 8

TABLE 7 EFFLUENT AND WASTE DISPOSAL REPORT - 2007 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 3 4 Error%

A. Fission and activation products 1'. Total release (not including tritium, gases, alpha) Ci 7.23E-04 8.54E-03 25

2. Average diluted concentration during period p Ci/jl 1.23E-12 1.58E-11
3. Percent of applicable limit  % 6.57E-04 3.14E-03 B. Tritium
1. Total release Ci 2.10E+02 1.45E+02 30
2. Average diluted concentration during period pCijml 3.57E-07 2.68E-07
3. Percent of applicable limit  % 3.76E-01 2.06E-01 C. Dissolved and entrained gases
1. Total release Ci 6.15E-03 2.24E-02 25
2. Average diluted concentration during period pLCi/ml 1.04E-11 4.14E-11
3. Percent of applicable limit  % 5.50E-04 1.59E-03 D. Gross alpha radioactivity
1. Total release Ci 2.80E-04 2.61E-05 30 E. Volume of waste released (prior to dilution)
1. Batch and continuous modes Liters 6.09E+06 1.05E+07 10 F. Volume of dilution water used during period
1. Batch and continuous modes Liters 5.89E+11 5.41E+11 10 9

TABLE 8 EFFLUENT AND WASTE DISPOSAL REPORT - 2007 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 1.27E-05 2.60E-04 Manganese-56 Ci Iron-55 Ci 5.95E-05 Iron-59 Ci Cobalt-57 Ci Cobalt-58 Ci 7.72E-06 4.12E-04 Cobalt-60 Ci 6.80E-04 5.99E-03 Zinc-69 Ci Zinc-72 Ci Strontium-85 Ci Strontium-89 Ci Strontium-90 Ci Strontium-92 Ci Yttrium-91 Ci Yttrium-92 Ci Yttrium-93 Ci Rubidium-88 Ci Niobium-95 Ci 1.56E-05 Niobium-95m Ci Zirconium-95 Ci Molybdinum-99 Ci, Technetium-99m Ci Technetium-101 Ci Ruthenium-106 Ci Silver-110m Ci 4.63E-05 1.60E-03 Tin-113 Ci Indium-113m Ci Antimony-122 Ci Antimony-124 Ci Antimony-125 Ci 2.36E-05 2.60E-04 Tellurium-129 Ci Tellurium-132 Ci Iodine-131 Ci Iodine-132 Ci Iodine-133 Ci Iodine-135 Ci1 Cesium-134 Ci 2.70E-07 1.19E-07 Cesium-136 Ci Cesium-137 Ci 2.83E-05 8.63E-06 Barium-133m Ci Barium-139 Ci Barium-140 Ci Lanthanum-140 Ci Cerium-144 Ci Cerium-143 Ci*

Praseodymium-144 Ci Neodymium-147 Ci Rhenium-188 Ci Total for period Ci O.OOE+00 O.OOE+00 7.23E-04 8.54E-03 10

TABLE 8 (CONTINUED)

EFFLUENT AND WASTE DISPOSAL REPORT - 2007 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 8.93E-04 5.44E-03 Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon- 131 m Ci 3.32E-04 Xenon-133 Ci 5.06E-03 1.63E-02 Xenon-133m Ci 2.29E-05 Xenon-135 Ci 1.95E-04 2.78E-04 Xenon-135m Ci Total for period Ci O.OOE+00 O.OOE+00 6.15E-03 2.24E-02 Tritium Ci O.OOE+oo 1.82E-01 2.10E+02 1.45E+02 11

TABLE 9 EFFLUENT AND WASTE DISPOSAL REPORT - 2007 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 8.65E+00 25

a. Spent resins, filter sludges, evaporator bottoms, etc. m3 8.6E+00 Ci 4.76E+02 m3 3.40E+02 1.38E+00 25
b. Dry compressible waste, contaminated equipment, etc. Ci m3 0.38E+00 25
c. Irradiated components, control rods, etc. m3 0.00E+00 Ci 0.00E+00 m3 1.71E+01 25 25
d. Other (describe): Combined DAW package Ci 2.65E+00
2. Estimate of major nuclide composition (by type of waste in %)*

H-3 0.5 Co-60 15.1 Cs-134 8.4

a. C-14 7.2 Ni-63 30.0 Cs-137 16.2 Fe-55 19.0 Ag-110m 1.1 CO-58 0.6 Ce-144 0.5 Ni-63 19.6
b. Fe-55 11.4 Cs-134 19.9 Co-60 6.8 Cs-137 41.6
c. N/A N/A Fe-55 11.5 Cs-134 19.8
d. Co-60 6.9 Cs-137 41.4 Ni-63 19.6
  • 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 2 Hittman Transport Services DURATEK 7 Hittman Transport Services DURATEK - Bear Creek 1 Tri-State Motor Transit Co. DURATEK - Bear Creek 4 Hittman Transport Services Studsvik Processing Facility, LLC 1 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 2007.

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

Annual Land Use Census The 2007 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 2007.

ODCM & PCP Changes The ODCM was revised once in 2007. Revision 30 added new groundwater monitoring well locations to table 5.1-2, a map of the well locations in figure 5.4, a statement in section 6.6 for the annual radiological environmental operating report (AREOR) that discusses results of any leak or spill of radioactive material that could have the potential to contaminate the groundwater shall be included in the AREOR, and section 6.7 was added to provide guidance for reporting protocol in the event that unplanned or uncontrolled release of radioactive material occurred. All of these items were added to the ODCM as a result of the NEI 07-07 Groundwater Protection Initiative Guidance Document.

The PCP was not revised in 2007.

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 2007 due to operation of this pump. In addition, radioactive releases due to other steam releases have been estimated and included. The results are given below in units of Curies/year.

Xe-133 1.56E-07 1-131 3.00E-09 Cs-134 1.80E-10 Xe-135 1.41E-07 1-133 4.80E-08 Cs-137 3.OOE-10 H-3 5.40E-06 These values are not included in Tables 1 through 4.

13

2007 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) 5.68E-06 3.93E-06 9.86E-06 9.64E-06 2.91E-05 Maximum Organ Dose (mrem) 6.87E-06 5.13E-06 1.57E-05 1.57E-05 1.85E-04 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) 9.43E-07 7.26E-06 1.08E-06 1.10E-04 1 20E-04 Beta Air Dose (mrad) 2.80E-06 1.89E-05 2.41E-05 4.45E-04 4.91E-04 Total Body Dose (mrem) 4.82E-04 4.36E-04 4.01E-04 1.55E-03 2.87E-03 Maximum Organ Dose (mrem) 4.82E-04 4.36E-04 4.01E-04 2.75E-03 4.07E-03 Maximum Organ was Thyroid 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 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/1.

14

GW Well # MWC-IF2 600 1 500 400 -400,\

E 300 \

200 100 + -4 + f 0 p 1/18/07 3M9/07 4/28/07 6/17/07 816/07 9/25/07 11114/07 113/08 GW Well # MWC-27 1400 1200 1000 800 600 400 200 0

1118107 319/07 4/28/07 6;17107 8/6107 9"25/07 11/14/07 1/3/08 15

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