ML071220460

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Radioactive Effluent Release Report
ML071220460
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 04/12/2007
From: Pinner R
Progress Energy Florida
To:
Office of Nuclear Reactor Regulation
References
3F0407-05
Download: ML071220460 (16)
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Text

RADIOACTIVE EFFLUENT RELEASE REPORT 2006 PROGRESS ENERGY FLORIDA, INC.

CRYSTAL RIVER UNIT 3 Facility Operating License No. DPR-72 Docket No. 50-302 Prepared By:

Sr. cien and Lab Services Specialist Approved By: S __ n- ___ v_____ __

Superintendent E ronmental and Chemistry Date: If/ 2-./0 )

CONTENTS Intou troo.............................................n...... 1 Tabular Data Summaries Gaseous Effluents -Quarters I& 2 ............................. 2 Gaseous Effluents -Quarters 3 &4 ............................. 4 Liquid Effluents -Quarters I& 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 Ptump 2 ............................................................. 13 Appendix I Dose Summary............................................................ 14

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.

I

TABLE 1 EFFLUENT AND WASTE DISPOSAL REPORT - 2006 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter 1 1 Quarter 2 1 Est.

Error Total

%

A. Fission and activation gases

11. Total release
2. Average release rate for period
3. Percent of technical specification limit B. Iodines
1. Total Iodine-131 Ci O.OOE+00 4.55E-07 30iI
2. Average release rate for period } Ci/sec O.OOE+00 5.79E-08
3. Percent of technical specification limit  % O.OOE+00 1.09E-02 C. Particulates*
1. Particulates with half-lives > 8 days Ci 0.00E+00 8.50E-07 30 ]
2. Average release rate for period pzCi/sec O.OOE+00 1.08E-07
3. Percent of technical specification limit  % 0.00E+00 1.09E-02
4. Gross alpha radioactivity Ci 2.21E-08 2.99E-08 D. Tritium
1. Total release Ci 2.01E+00 1.92E+00 30j]
2. Average release rate for period  ;&Ci/sec I 2.59E-01 I 2.44E-01
3. Percent of technical specification limit  % I 6.44E-03 1.09E-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 - 2006 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES A. Fission gases Argon-41 Ci ________ _______ 1.22E-01 Krypton-85 Ci __ _____ 2.62E+00 6.11E-01 Krypton-85m Ci _ _ _ _ _ _ __ _ _ _ _ _

Krypton-87 Ci _ _ _ _ _ _ __ _ _ _ _ _

Krypton-88 Ci _ _ _ _ _ _ __ _ _ _ _ _

Xenon-l3lm Ci _ _ _ _ _ _ __ _ _ _ _ _

Xenon-l33 Ci __ _____ 7.65E-03 5.1213-02 Xenon-133m Ci ___________ ______

Xenon-135 Ci ____________ _____

Xenion-135m Ci _ _ _ _ _ _ _ _ _ _ _ _ _

Xenon-138 Ci _ _ _ _ _ _ __ _ _ _ _ _

Total for period Ci O.OOE+OO O.OOE+OO 2.6213+00 7.85E-01 B. lodines Iodine-l3l Ci ____ _____ 4.5513-07_________[

Iodine-132 Ci _________ _____ ____jj lodine-133 Ci 1.07E-05 j I

____ _____

Iodine-135 Ci Total for period Ci O.OOE+OO 1.1213-05 J O.OOE+OO O.OOE+OO C. Particulates Zinc-72 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Cobalt-58* Ci _________ __ ______

Cobalt-60* Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Strontium-89* Ci __________ _______

Stromtium-9O* Ci _______________

Niobium-95m Ci _ _ _ _ _ _ __ _ _ _ _ _

Techniciun-99m Ci _ _ _ _ _ _ __ _ _ _ _ _

Tellurium-132 Ci _________ _ _______

Cesium-l34* Ci _________ __ ______

Cesium-137* Ci 50E-07 8.________ ________

Cesium-138 Ci _________ __ ______

Barium-139 Ci _ _ _ _ _ _ _ ________ _ _ _ _ _ _ _

Lanthanum-142 Ci _ _ _ _ _ _ __ _ _ _ _ _

Cerium-141* Ci ________________

Cerium-143* Ci ___________ ______

Rhenium-188 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Total for period Ci O.OOE+OO 8.5013-07 O.OOE+OO O.OO13+00

  • > 8 day half-life 3

TABLE 3 EFFLUENT AND WASTE DISPOSAL REPORT - 2006 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter I Quarter Est. Total 11 3 4 Error%

A. Fission and activation gases I.

2.

Total release Average release rate for period

3. Percent of technical specification limit B. lodines
1. Total Iodine-131 Ci 3.77E-07 O.OOE+00 30
2. Average release rate for period pCiUsec 4.74E-08 0.003E+00
3. Percent of technical specification limit  % 7.23E-03 O.OOE+00 C. Particulates*
1. Particulates with half-lives > 8 days Ci O.OOE+00 3.41E-07 30
2. Average release rate for period p&Ci/sec O.OOE+00 4.29E-08
3. Percent of technical specification limit  % 0.00E+00 8.56E-03
4. Gross alpha radioactivity Ci 4.25E-08 5.43E-08 D. Tritium
1. Total release Ci 1.26E+00 1 2.65E1+00 30
2. Average release rate for period I jCi/sec I1-59E-01I 3.3413-01 1
3. Percent of technical specification limit I _% I 7.23E-03 I 8.56E-03
  • 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 - 2006 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES A. Fission gases Argon-41 Ci .22E-02 1_______

Krypton-85 Ci ________ 4.40E-01 2.99E-02 Krypton-85m Ci _______

Krypton-87 Ci _________

Krypton-88 Ci _______

Xenon-l3lin Ci Xenon-133 Ci 1.39E-01 1.80E-03 Xenon-133m Ci _______

Xenon-135 Ci 1.37E-03 7.14E-05 Xenon-135m Ci Xenon-138 Ci__________

Total for period Ci O.OOE+OO O.OO13+00 5.29E-01 3.17E-02 B. lodines lodine-131 Ci 37E-07 _________

lodine-132 Ci jj Iodine-133 Ci j__________ ___________ ___

i

______

Iodine-135 Ci Total for period Ci 3.77E-97 O.OOE+OO O.OO13+00 O.OO13+00 C. Particulates Zinc-72 Ci _______

Cobalt-58* Ci _________

Ch~romum51* Ci _ _____

Strontium-89* Ci ________

Strontium-90* Ci ________

Niobium-95* Ci _________

Tin-113* Ci _____ ____

Indium-113m Ci _______

Barium-133m Ci Cesium-137* Ci 1.14E-07_________

Cesium-138 Ci ________

Barium-139 Ci _______

Lanthanum-142 Ci ________

Ceritum-141 Ci 2.27E-07 _______

Cerium-143 Ci _______

Cerium-l44* Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Rbenium-188 Ci _________ __________ _________ ___ ______

Total for period Ci O.OO13+00 3.41E-07 O.OOE+OO O.OOE+OO

  • > 8 day half-life 5

TABLE5 EFFLUENT AND WASTE DISPOSAL REPORT - 2006 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 1 2 trError A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 4.07E-03 5.21E-03 25I.
2. Average diluted concentration during period uCi/ml 7.15E-12 9.13E-12
3. Percent of applicable limit  % 9.60E-04 9.89E-05 B. Tritium
1. Total release Ci 5.21E+01 1.75E+01 30i]
2. Average diluted concentration during period jCi/ml 9.63E-08 3.07E-08
3. Percent of applicable limit  % 8.47E-02 3.18E-02 C. Dissolved and entrained gases
1. Total release Ci 8.59E-03 2.94E-03
2. Average diluted concentration during period pCi/ml 1.59E-11 5.15E-12
3. Percent of applicable limit  % 8.97E-04 2.67E-04 D. Gross alpha radioactivity
1. Total release Ci I.23E-04 5.69E-05 30 E. Volume of waste released (prior to dilution)
1. Batch and continuous modes Liters i.30 1+07 6.OOE+06 1 F. Volume of dilution water used during period
1. Batch and continuous modes Liters 5.42E+ II 5.71E+ll 10 6

TABLE 6 EFFLUENT AND WASTE DISPOSAL REPORT - 2006 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 3.46E-05 3.24E-04 Manganese-54 Ci 2.00E-07 Manganese-56 Ci Iron-55 Ci 4.96E-04 7.84E-04 2.49E-04 Iron-59 Ci Cobalt-57 Ci Cobalt-58 Ci 9.72E-05 7.15E-05 Cobalt-60 Ci 6.34E-05 3.83E-05 Zinc-69 Ci Strontium-85 Ci Strontium-89 Ci Strontium-90 Ci 1.49E-04 Yttrium-91m Ci Yttrium-92 Ci Yttrium-93 Ci Niobium-95 Ci Niobium-95m Ci Niobium-97 Ci Zirconium-95 Ci Zirconium-97 Ci Molybdinum-99 Ci Technetium-99m Ci Technetium-101 Ci Ruthenium-103 Ci Ruthenium-106 CQ Silver-110m Ci 1.27E-04 6.68E-05 Tin-113 Ci Indium-113m Ci Antimony-122 Ci Antimony-124 Ci Antimony-125 Ci 2.32E-03 4.53E-03 Tellurium-129 Ci Tellurium-132 Ci Iodine-131 Ci Iodine-133 Ci Iodine-135 Ci Cesium-134 Ci 1.77E-06 2.75E-07 Cesium-137 Ci 1.46E-05 3.91E-05 Cesium-138 Ci Barium-133m Ci Barium-140 Ci Lanthanum- 140 Ci Cerium-141 Ci Cerium-143 Ci 1.OOE-05 Neodymium-147 Ci Tungsten-187 Ci Neptunium--239 Ci Total for period Ci 4.96E-04 0.00E+00 3.60E-03 5.21E-03 7

TABLE 6 (CONTINUED)

EFFLUENT AND WASTE DISPOSAL REPORT - 2006 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 _________ ________ 7.6313-03 1.O113-03 Krypton-85m Ci _ _____

Krvoton-87 Ci _ _____

Krypton-88 Ci _____________

Xenon-13lm Ci _ _____

Xenon-133 Ci _______ 8.30E-04 1.81E-03 Xenon-133m Ci ________ ______

Xenon-135 Ci ________ ________ 1.3313-04 1.2313-04 Xenon-135m Ci Total for period Ci O.OO13+00 O.O13+00 8.5913-03 2.974E-037 Tritiumi Ci 2.50E-01 O.OO13+00 5.1913+01 1.75E+01 8

TABLE7 EFFLUENT AND WASTE DISPOSAL REPORT - 2006 LIQUI) EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 11 3 1 4 1Error %

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 7.19E-03 {4.6513-04 25
2. Average diluted concentration during period AsCi/ml 1.24E-11 8.51E-13
3. Percent of applicable limit 8.39E-04 I1.48E.0 B. Tritium
1. Total release
2. Average diluted concentration during period
3. Percent of applicable limit C. Dissolved and entrained gases
1. Total release Ci 1.33E-03 1.04E-03 25
2. Average diluted concentration during period giCi/mil 2.29E-12 1.90E-12
3. Percent of applicable limit  % 1.11E-04 9.80E-05 D. Gross alpha radioactivity
1. Total release Ci 4.92E-05 1.17E-04 30 E. Volume of waste released (prior to dilution)
1. Batch and continuous modes Liters 7.08E+06 4.16E+06 10 F. Volume of dilution water used during period
1. Batch and continuous modes Liters 5.811+11 5.46E+I1 10 9

TABLE 8 EFFLUENT AND WASTE DISPOSAL REPORT - 2006 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 6.29E-05 Manganese-54 Ci Manganese-56 Ci I Iron-55 Ci 1.50E-04 3.96E-05 Iron-59 Ci Cobalt-57 Ci Cobalt-58 Ci 1.10E-03 2.70E-05 Cobalt-60 Ci 7.30E-05 1.86E-05 Zinc-69 Ci Zinc-72 Ci Strontium-85 Ci Strontium-89 Ci 7.67E-06 Strontium-90 Ci Strontium-92 Ci Yurium-91 Ci Yttrium-92 Ci Yttrium-93 Ci Rubidium-88 Ci Niobium-95 Ci Niobium-95m Ci Zirconium-95 Ci Molybdinum-99 Ci Technetium-99m Ci Technetium-101 Ci Ruthenium-106 Ci Silver-1 10m Ci 4.33E-06 Tin-113 Ci Indium-113m Ci Antimony-122 Ci 1.18E-06 Antimony-124 Ci Antimony-125 Ci 5.67E-03 3.33E-04 Tellurium-129 Ci Tellurium-132 Ci Iodine-131 Ci Iodine-132 Ci Iodine-133 Ci Iodine-135 Ci Cesium-134 Ci 4. 1OE-07 Cesium-136 Ci Cesium-137 Ci 5.31E-05 3.91E-05 Barium-133m Ci Barium-139 Ci Barium-140 Ci Lanthanum-140 Ci Cerium-144 Ci 7.18E-05 Cerium-143 Ci Praseodymium-144 Ci Neodymium-147 Ci Rhienium-188 Ci Total for period Ci O.OOE+00 O.OOE+00 7.19E-03 4.65E-04 10

TABLE 8 (CONTINUED)

EFFLUENT AND WASTE DISPOSAL REPORT - 2006 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-131m Ci Xenon-133 Ci 1. 19E-03 1.001E-03 Xenon-133m Ci Xenon-135 Ci 1.34E-04 3.86E-05 Xenon-135m Ci Total for period Ci O.OOE+00 O.OOE+00 1.33E-03 1.04E-03 Tritium Ci O.OOE+00 O.OOE+00 5.48E+01 1.86E+02 11

TABLE 9 EFFLUENT AND WASTE DISPOSAL REPORT - 2006 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 4.35E+01 25 25

a. Spent resins, filter sludges, evaporator bottoms, etc. Ci 2.11E-02 m3 1.IIE+02 25
b. Dry compressible waste, contaminated equipment, etc. Ci 1.14E-_0125 m3 0.00E+00 25 25
c. Irradiated components, control rods, etc. mi O.OOE+0O Ci 0.00E+00 m3 5.83E+00 25 25
d. Other (describe): Combined DAW package Ci 4.18E+00
2. Estimate of major nuclide composition (by type of waste in %)*

H-3 1.2 Co-60 17.0 Cs-134 5.0

a. C-14 14.3 Ni-63 23.4 Cs-137 9.4 Fe-55 26.9 Ag-110m 1.2 H-3 1.5 Ni-63 32.5
b. Fe-55 2.8 Cs-134 23.2 Co-60 4.6 Cs-137 33.6 C.

Fe-55 2.8 Cs-134 23.2

d. Co-60 4.6 Cs-137 33.6 Ni-63 32.6

- Curie values and principle radionuclides are estimates based on a combination of direct and indirect methoas.

3. Solid Waste Disposition Number of Shipments Mode of Transportation
  • Destination 2 Hittman Duratek (TN) 1 Hituman Studsvik Processing Facility, LLC 2 Hittman Energy Solutions, LLC (Bulk)

All exclusive use trucks 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 2006.

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

Annual Land Use Census The 2006 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 2006.

ODCM & PCP Changes The ODCM was revised 2 times in 2006. Revision 28 added a clarifying note to table 2-3, Action 30, page 14, which pertains to operability of RM-A12 if a valid counts per minute (cpm) to gallons per day (gpd) conversion factor is not available. The note explains that RM-A12 can still be used as an indicator of the changes in the noble gas concentrations in the condenser offgas, and the monitor should not be declared inoperable in the absence of this conversion factor. In Revision 29, section 2.2, Table 2-3, Action 29, page 14, removed reference of use of the Post Accident Sample System (PASS) Reactor And Noble Gas Effluent Automated Isotopic Monitoring System (RANGE AIMS) as use for a back up alternative method of monitoring if either RM-A1 or RM-A2 mid and/or high range monitors are out of service. The RANGE AIMS system is being abandoned by Engineering Change (EC) 49486. Appropriate manual sampling methods are in place if needed to evaluate elevated effluent releases.

The PCP was not revised in 2006.

Emergency Feed Pump 2 & Steam Releases Emergency Feed Pump 2 (EFP-2) overspeed 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 2006 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 9.60E-08 1-131 2.40E-09 Cs-134 4.80E-08 Xe-135 9.00E-08 1-133 2.40E-08 Cs-137 5.40E-08 H-3 5.16E-06 These values are not included in Tables I through 4.

Correction to 2005 Radioactive Effluent Release Report Table 6 liquid effluent batch mode releases for quarter 1 and quarter 2 incorrectly identified Technicium-101 as being present.

This radionuclide should have been removed from the report during the nuclide verification process as TC-101 peak criteria was statistically invalid. The reported concentrations of TC-101 were insignificant regarding curies released and dose consequences.

13

2006 Appendix I Dose Summary Maximum Hypothetical Individual Liquid Effluent Dose Limits Total Body: 1.5 rnrem/quarter, 3 mrem/year Any Organ: 5 mrero/quarter, 10 mrem/year Liquid Effluent Dose Summary Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Total Total Body Dose (mrem) 1.44E-05 1.4813-06 5.3313-06 8.48E-06 2.9711-05 Maximum Organ Dose (mrem) 3.78E-05 5.64E-06 4.20E-05 7.41E-06 9.2913-05 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 orem/quarter, 15 mrem/year Gaseous Release Dose Summary Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Total Gamma Air Dose (mrad) 3.8613-06 2.27E-06 4.7013-06 1.0213-07 1.0913-05 Beta Air Dose (mrad) 4.0613-04 9.9013-05 7.98E-05 4.7813-06 5.8913-04 Total Body Dose (mrem) 4.83E-04 4.6913-04 3.0313-04 6.38E-04 1.8913-03 Maximum Organ Dose (mrem) 4.83E-04 8.2013-04 5.4211-04 6.38E-04 2.4813-03 Maximum Organ was Thyroid 14

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