ML101250164

Annual Radioactive Effluent Release Report 2009

ML101250164
Person / Time
Site:	Crystal River
Issue date:	04/29/2010
From:	Pinner R Progress Energy Co, Progress Energy Florida
To:	Office of Nuclear Reactor Regulation
References
3F0410-05
Download: ML101250164 (20)

Text

PROGRESS ENERGY FLORIDA, INC.

CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 ATTACHMENT A RADIOACTIVE EFFLUENT RELEASE REPORT 2009

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2009

&2 Progma EIP PROGRESS ENERGY FLORIDA, INC CRYSTAL RIVER UNIT 3 Facility Operating License No. DPR-72 Docket No. 50-302 Pinner, Rudolph W.

I am the author of this document.

Prepared By: 2010.02.11 11:25:50 -05'00' Sr. Science and Lab Services Specialist Hughes, Lee I am approving this document.

Approved By 2010.02.12 12:53:55-05'00' Superintendent Environmental and Chemistry Date: 02/11/2010

CONTENTS Introduction ................................................................................................................................. 1 Tabular Data Summaries G aseous Effluents - Q uarters 1 & 2 ............................................................................ 2 G aseous Effl uents - Q uarters 3 & 4 ............................................................................ 4 Liquid Effl uents - Q uarters 1 & 2 ............................................................................... 6 Liquid Effl uents - Q uarters 3 & 4 ................................................................................ 9 Radw aste Shipm ents ................................................................................................................. 12 Unplanned Releases .................................................................................................................... 13 Radioactive Waste Treatm ent System s ...................................................................................... 13 Annual Land U se Census .......................................................................................................... 13 Effl uent M onitor Instrum ent Operability ................................................................................. 13 ODCM & PCP Changes ............................................................................................................. 13 Em ergency Feed Pum p 2 ......................................................................................................... 14 Appendix I D ose Sum m ary ....................................................................................................... 15 NEI 07-07 Required Data ........................................................................................................ 16

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 - 2009 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total I I1 2 1Error%

A. Fission and activation gases

1. Total release Ci 7.54E-03 O.OOE+00 30

2. Average release rate for period p.Ci/sec 9.70E-04 O.OOE+00

3. Percent of technical specification limit  % 6.27E-06 O.OOE+00 B. lodines

1. Total Iodine-131 Ci 3.33E-06 4.50E-06 30

2. Average release rate for period liCi/sec 4.28E-07 5.73E-07

3. Percent of technical specification limit  % 3.82E-02 4.52E-02 C. Particulates*

I. Particulates with half-lives > 8 days Ci 5.22E-07 1.14E-06 30

2. Average release rate for period piCi/sec 6.70E-08 1.45E-07

3. Percent of technical specification limit  % 3.82E-02 4.52E-02

4. Gross alpha radioactivity Ci 1.57E-08 1.73E-08 D. Tritium

1. Total release Ci 3.13E+00 2.17E+00 30

2. Average release rate for period ItCi/sec I 4.03E-01 2.77E-01

3. Percent of technical specification limit  % 3.82E-02 4.52E-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

TABLE2 EFFLUENT AND WASTE DISPOSAL REPORT - 2009 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES A. Fission gases Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon- 131 m Ci Xenon-133 Ci 7.54E-03 Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Xenon-138 Ci Total for period Ci O.OOE+00 O.OOE+00 7.54E-03 O.OOE+00 B. lodines Iodine-131 Ci 3.33E-06 4.50E-06 Iodine-132 Ci Iodine- 133 Ci Iodine- 135 Ci Total for period Ci 3.33E-06 4.50E-06 O.OOE+00 O.OOE+00 C. Particulates Manganese-54* Ci 1.27E-07 3.34E-07 Zinc-72 Ci Cobalt-58* Ci 1.49E-07 2.76E-07 Cobalt-60* Ci Strontium-89* Ci Strontium-90* Ci Niobium-95m Ci Technicium-99m Ci Tellurium- 132 Ci Cesium-134* Ci Cesium-137* Ci 1.24E-07 5.27E-07 Cesium-138 Ci Barium-139 Ci Lanthanum- 142 Ci Cerium- 141

• Ci Cerium- 143* Ci 1.22E-07 Rhenium-188 Ci Total for period Ci 5.22E-07 I.14E-06 O.OOE+O0 0.00E+00

• > 8 day half-life 3

TABLE3 EFFLUENT AND WASTE DISPOSAL REPORT - 2009 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 3 4 Error %

A. Fission and activation gases 1I. Total release

2. Average release rate for period

13. Percent of techmical specification limit B. lodines

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

2. Average release rate for period gCi/sec O.OOE+00 O.OOE+00

3. Percent of technical specification limit  % O.OOE+00 O.OOE+00 C. Particulates*

I. Particulates with half-lives > 8 days Ci 1.1 OE-06 1.07E-05 30

2. Average release rate for period liCi/sec 1.38E-07 1.34E-06

3. Percent of technical specification limit  % 8.40E-03 1.15E-02

4. Gross alpha radioactivity Ci 2.3 1E-09 1.48E-07 D. Tritium

[I. Total release Ci 2.48E+00 3.25E+00

2. Average release rate for period I[~ise I3.13E-01 4.09E-0 I

3. Percent of technical specification limit  % 8.40E-03 1.15E-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 - 2009 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES A. Fission gases Argon-41 Ci _________

Krypton-85 Ci ______________________________

Krypton-85m Ci ________

Krypton-87 Ci ________

Krypton-88 Ci _________

Xenon-l13l1m Ci ________

Xenon-133 Ci 8.38E-02 Xenon-133m Ci _________ __________

Xenon-135 - Ci __________ ___________ _________ ____ _____

Xenon-135m Ci ________

Xenon-138 Ci __________________

Total for period Ci 0.OOE+00 0.OOE+00 8.3 8E-02 0.OOE+00 B. lodines Iodine-13l Ci _________ __________ _________I___ ______

lodine-l32 Ci lodine-133 Ci __________ ___________ ___ ______

Iodine-l35 Ci __________ ___________ ____ _____t Total for period Ci 0.OOE+00 0.OOE+00 0.OOE+00 j .OOE+O0 C. Particulates Manganese-54* Ci ___________ 8.01lE-07 Zinc-72 Ci __________

Cobalt-58* Ci 05OE-07 4.18E-06 Cobalt-60* . Ci ___________ 2.73E-06 Chromium-51* Ci __________

Strontium-89* Ci ___________

Strontium-90* Ci __________

Niobium-95* Ci 1OE-06 1._________

Tin-ll13* Ci ____ _____

Zirconium-95* Ci 5.50E-07 Barium-133m Ci _______ _______

Cesium-137* Ci 7.94E-07 1.06E-06 Barium-l39 Ci __________

Cerium-141 Ci __________

Cerium-143 Ci ___________ 4.21E-07 Cerium-l44* Ci __________

Ruthenium-103 Ci ___________ 2.20E-07 _________ _________

Total for period Ci 1.I1OE-06 1.11IE-05 0 OOE-00 0OE0

• > 8 day half-life 5

TABLE5 EFFLUENT AND WASTE DISPOSAL REPORT - 2009 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 1 2 Error %

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 8.81 E-03 3.73E-04 25

2. Average diluted concentration during period pCi/ml 1.66E-12 6.54E- 13

3. Percent of applicable limit  % 9.98E-04 4.66E-04 B. Tritium I. Total release Ci 1.87E+02 1.91E+02 30

2. Average diluted concentration during period gtCi/ml 3.52E-07 3.35E-07

3. Percent of applicable limit  % 2.99E-01 3.35E-01 C. Dissolved and entrained gases I. Total release Ci 2.83E-03 2.19E-03 25

2. Average diluted concentration during period piCi/ml 5.33E-12 3.84E-12

3. Percent of applicable limit  % 2.26E-04 1.92E-04 D. Gross alpha radioactivity I. Total release Ci O.OOE+OO O.OOE+O E. Volume of waste released (prior to dilution)

I1. Batch and continuous modes Liters 9.58E+06 1.00E+07 10 F. Volume of dilution water used during period I1. Batch and continuous modes Liters 5.3 IE+l I 5.70E+l I 10 6

TABLE 6 EFFLUENT AND WASTE DISPOSAL REPORT - 2009 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Fission and activation products Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Sodium-24 Ci __________

Chromium-5 ICi __________

Manganese-54 Ci __ _______

Manganese-56 Ci Iron-55 Ci ___________ ___________ 2.33E-04 Iron-59 Ci __________

Cobalt-57 Ci __________ ___________ ____ _____

Cobalt-58 Ci ___________ ___________ 9.47E-07 7.2212-07 Cobalt-60 Ci ___________ _________ _ 1.05E-05 2.I1OE-05 Zinc-69 Ci __________ ___________ _____ ____

Strontium-85 Ci __________

Strontium-89 Ci __________ ___________ __ _______

Strontium-90 Ci __________ ___________ __ _______

Yttrium-91m Ci Yttrium-92 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Yttrium-93 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Niobium-95 Ci __________ __________ ________

Niobium-95m Ci __________ __________ ________

Niobium-97 Ci __________ __________ ________

Zirconiurn-95 Ci __________ ___________ _________ __ _______

Zirconiurm-97 Ci __________ ___________ __ _______

Molybdinum-99 Ci __________ __________ ________

Technetium-99m Ci __________ ___________ _ ________

Technetium-l01 Ci __________ ___________ _ ________

Ruthenium-103 Ci __________ ___________ __ _______

Ruthenium- 106 Ci __________ ___________ _ ________

r Silver-W10m________ CI ___________ ________

Tin-113 Ci __________ __________ ________

Indium- I 13m Ci __________ ___________ __ _______

Antimony-122 Ci __________ ___________ __ _______

Antimony-124 Ci __________ __________ ________

Antimony- 125 Ci ___________ ___________ 7.04E-06 3.I11E-04 Tellurium-129 Ci __________ ___________ ___ _______

Tellurium-132 Ci __________ ___________ __ _______

Iodine-131 Ci __________ ___________ ___ ______

Iodine-133 Ci __________ ___________ ___ ______

Iodine-135 Ci __________ ___________ ___ ______

Cesium-134 Ci __________ ___________ ___ ______

Cesiuni-137 Ci 4.49E-05 _ __________ 6.79E-05 3.47E-05 Cesium-138 Ci ___________ ___________ __________

Barium-133m Ci ___________I.67E-06 1__________

Barium-140 Ci _________ _____________ ______

Lanthanum- 140 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _

Cerium-141 - Ci __________ __________ ________

Cerium-143 Ci __________ __________ _________

Neodymium-147 Ci _________ ____________ _______

Tungsten- 187 Ci __________ ___________ _________ __ _______

Neptunium--239 Ci __________ ___________ _________ _ ________

Nickle-63 Ci __________ __________ 5.17E-04 4.42E-06 Total for period Ci 4.49E-05 0.OOE-I-0 8.8 1IE-04 3.73E-04 7

TABLE 6 (CONTINUED)

EFFLUENT AND WASTE DISPOSAL REPORT - 2009 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 2.53E-04 Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-13 1m Ci 1.94E-04 Xenon-133 Ci 2.77E-03 1.69E-03 Xenon-133m Ci Xenon-135 Ci 5.84E-05 5.03E-05 Xenon-135m Ci Total for period Ci O.OOE+00 0.00E+00 2.83E-03 2.19E-03 Tritium Ci 1.51E-01 O.OOE+00 1.87E+02 1.91E+02 8

TABLE 7 EFFLUENT AND WASTE DISPOSAL REPORT - 2009 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 2.24E-02 6.84E-03 25I

2. Average diluted concentration during period ACi/ml 3.98E-1 1 2.96E- 11

3. Percent of applicable limit  % 1.15E-03 1.07E-03 B. Tritium I. Total release Ci 2.81E+02 5.64E+01 30

2. Average diluted concentration during period j.Ci/ml 5.OOE-07 2.44E-07

3. Percent of applicable limit  % 3.61E-01 8.33E-02 C. Dissolved and entrained gases I. Total release Ci 1.64E-02 2.59E-03 25

2. Average diluted concentration during period pCi/ml 2.92E-1I 1.12E- I1

3. Percent of applicable limit  % 1.05E-03 1.91E-04 D. Gross alpha radioactivity I. Total release Ci I000E+00 1.69E-04 30 E. Volume of waste released (prior to dilution)

1. Batch and continuous modes Liters 1.18E+07 6.39E+06 10 F. Volume of dilution water used during period I. Batch and continuous modes Liters 5.62E+1 1 2.31E+1,1 10 9

TABLE 8 EFFLUENT AND WASTE DISPOSAL REPORT - 2009 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Fission and activation products Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Sod ium-24 Ci ______________________________

Chromium-SI Ci __________ __________ 8.95E-04 6.30E-05 Manganese-54 Ci ___________ 6.20E-06 3.93E-06 Manganese-56 Ci __________

Iron-55 Ci __________

9 Iron-5 Ci __________ ___________ _____ ____

Cobalt-57 Ci _________

Cobalt-58 Ci .37E-04 1__________ 2.46E-04 Cobalt-60 Ci ______________________ 2.26E-04 3.84E-05 Zinc-69 Ci _________

Zinc-72 Ci 9.26E-06 Strontium-85 Ci _________

Strontium-89 Ci _________

Strontium-90 Ci _________

Strontium-92 Ci __________

Yttrjum-9 1 Ci _ _ _ _ _ _ _ __ _ _ _ _ _ _

Yttri~un-92 Ci _______________

Yttriumn-93 - Ci _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _

Rubidium-88 Ci __________ _________

Niobium-95 Ci ___________3.52E-05 2.55E-05 Niobium-95m Ci ___________________

Zirconium-95 Ci ___________2.60E-05 1.50E-05 Molybdinum-99 Ci ___________________

Techrietium-99m Ci ___________________

Technietium-10I Ci ________

Ruthenium- 106 Ci ___________________

Silver- I IOm Ci 3.72E-05 9.6 1E-06 Tin-l 13 Ci ____ ____

Indium- I 13m Ci Antimiony- 122 Ci Antimony- 124 Ci Antiniony-125 Ci ___________2.09E-02 6.16E-03 Tellurium-129 Ci Tellurium-132 Ci __________

Iodine-131 Ci _________

Iodine-133 Ci _________

Iodine-135 - Ci ____ ______

Cesium-134 Ci 2.12E-07 Cesium-137 Ci 1.12E-04 1.26E-04 Barium-133m Ci Barium-139 Ci Barium-140 Ci __________

Lanthanumn-140 Ci _ _____

Cerium-141 Ci 1.57E-05 Cerium-143 Ci 7.54E-05 Praseodymium- 144 Ci _________

Neodymium-147 Ci _____________________________________

Neptunium-239 Ci ____________________ ________ 3.73E-06 Nickel-63 Ci __________ __________ 7.11E-05 4.11 E-05 Rhenium-188 Ci ____________________ ___________________

Total for period Ci O.OOE+OO O.OOE+0O 2.24E-02 6.84E-03 10

TABLE 8 (CONTINUED)

EFFLUENT AND WASTE DISPOSAL REPORT - 2009 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 5.21E-04 Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-131m Ci Xenon-133 Ci 1.54E-02 2.59E-03 Xenon-133m Ci Xenon-135 Ci 4.68E-04 Xenon-135m Ci Total for period Ci O.OOE+00 O.OOE+00 1.64E-02 2.59E-03 Tritium Ci 8.95E-02 O.OOE+00 2.81E+02 5.64E+O1 11

TABLE 9 EFFLUENT AND WASTE DISPOSAL REPORT - 2009 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 2.55E+00 25

a. Spent resins, filter sludges, evaporator bottoms, etc. Ci 3.38E-07 m3 8.18E+02 25 25

b. Dry compressible waste, contaminated equipment, etc. Ci 8.14E+00 m3 0.00E+00 25

c. Irradiated components, control rods, etc. Ci 0.00E+00 25 m3 3.66E+01 25

d. Other (describe): Combined DAW package Ci 2.0 1E+00

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

Ce-144 16.22 Co-60 44.51 Cs-137 39.27 a.

Ce- 144 2.91 Ni-63 18.97 Co-58 10.67

b. Fe-55 38.3 Mn-54 3.95 Nb-95 2.1 Co-60 19.98 Cs-137 2.96 Cs-134 0.31

c. N/A N/A N/A Fe-55 32.5 Sb-125 1.76 Mn-54 0.958

d. Co-60 21.17 Cs-134 3.04 H-3 1.08 Ni-63 30.56 Cs-137 8.01 C-14 0.196 Pu-241 0.518

• 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 Destinati on 2 Hittman Transport Services EnergySolutions 21 Hittman Transport Services EnergySolutions-Bear Creek 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 2009.

Radioactive Waste Treatment Systems There were no significant changes to the radioactive waste treatment systems in 2009. A new macroporous anion ion-specific speciality resin was added to one waste processing demineralizer to target removal of Sb-125. Data is still being collected on this project.

Annual Land Use Census The 2009 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 2009.

ODCM & PCP Changes The ODCM was revised once in 2009. Revision 32 incorporated the following changes:

1. The replacement of the CR-3 steam generators in refuel 16 outage require cutting a sizeable hole in the reactor building wall to facilitate removal and installation of these large components. Verbiage was added to page 97 under the section for representative sampling method 3.1-5 dealing with the reactor building equipment hatch and personnel hatch being in the open position to also include the steam generator replacement access hole.

Under certain wind flow conditions outside air might flow into the reactor building through one open hatch and out the otheropen hatch. ODCM sampling specification 3.1-5 was established to provide guidance for controlling these hatches (personal and equipment hatches) to minimize the chances of releasing airborne radioactive material. This guidance is not a commitment and is not a required part of the ODCM.

The SG replacement project requires an opening in the Reactor Building that is equivalent to having another hatch opening. This new opening is not practical to control in the same way the personnel and equipment hatches have been controlled in the past. Consequently, the sampling specification is being revised to recognize this new opening and to provide for flexibility in theapplication of the guideline.

2. Also on page 97 under the section for representative sampling method 3.1-6 dealing with sampling to support the reactor building integrated leak rate test, verbiage was added that describes use of RM-A6 samples prior to pressurizing the RB or use of RM-A1 samples from the previous RB purge permit as long as the source term has not changed.

3. On page l Ithe footnote of table 2-3 for requirements of when the RM-A1 automatic isolation function is required was updated to state that this function is not required during periods of"no mode" due to no gas source term being located in the RB during the "no mode" plant condition.

4. On page 140, the direction for station C14H was changed from NW to N as we moved the collection of surface water slightly east to eliminate dilution effects of units CR 1&2. Also footnote 1 was added to the vegetation collection areas to provide an alternate means of collecting required media if adequate vegetation is not available.

The PCP was not revised in 2009.

13

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 2009 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 3.77E-07 1-131 8.80E-09 Cs-137 3.77E-10 Xe-135 4.28E-07 1-133 7.55E-08 H-3 1.51E-05 These values are not included in Tables 1 through 4.

14

2009 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) 1.50E-05 6.99E-06 1.73E-05 1.61E-05 5.53E-05 Maximum Organ Dose (mrem) 6.70E-06 6.03E-06 5.86E-05 4.23E-05 1.14E-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) 2.11E-07 0.OOE+00 2.34E-06 0.OOE+00 2.56E-06 Beta Air Dose (mrad) 6.27E-07 0.OOE+00 6.97E-06 0.OOE+00 7.60E-06 Total Body Dose (mrem) 7.56E-04 5.3 1E-04 6.04E-04 8.26E-04 2.72E-03 Maximum Organ Dose (mrem) 2.86E-03 3.39E-03 6.01E-04 8.24E-04 7.68E-03 Maximum Organ was Thyroid 15

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/1, 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.

16

Tritium Measurements GW Well # MWC-4F2 600 500 400 100 0

10110106 04/28/07 11/14107 06101/08 12/18/08 07106109 01/22/10 Tritium Measurements GW Well # MWC-27 1400 -

1200 1000 800 600 -

400- L 0 t 10110/06 04/28107 11114/07 06/01/08 12/18100 07106/09 01/22/10 17