Text

Submittal of Radiological Effluent Operating Environmental Release Report for Year 2012
	ML13135A311
Person / Time
Site:	Fort Calhoun
Issue date:	04/23/2013
From:	Simpkin T; Omaha Public Power District
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	LIC-13-0043
	Download: ML13135A311 (172)
	v • d • e

444 South 16e Street Mall Omaha, NE 68102-2247 April 23, 2013 LIC-13-0043 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20655

Reference:

Docket No. 50-285

SUBJECT:

Fort ChUmm nStaon (FCS) Radiloogl Effluent Release Report and Pursuant to Fort Calhoun Station (FCS), Unit No. 1, Technical Specifications (TS) 5.9.4a and 5.9.4b, the Omaha Public Power District (OPPD) provides the Annual Radiological Effluent Release Report and the Annual Radiological Environmental Operating Report.

The Annual Radiological Effluent Release Report encompasses the period of January 1, 2012 through December 31, 2012 and is submittd In accordance with TS 5.9.4a. The report is presented in the format outlined in Regulatory Guide 1.21, Revsion 1. In addition, the report provides the results of quarterty dose calculations performed In accordance with the Offeite Dose Calculation Manual (OOCM).

In accordance with TS 5.17d and 5.18d,Section VII of the Annual Radiological Effluent Release Report includes the latest revisions to the OCM and Process Control Program.

The Annual Radiological Environmental Operating Report encompasses the period of January 1, 2012 through December 31, 2012 and is submitted In accordance with TS Section 5.9.4b. The date provided is consistent with the objectives specified in Section 5.2.2 of the O0CM.

No commitments to the NRC are made In this letter.

Employment with Equal Opportunity

U. S. Nuclear Regulatory Commission LIC-13-0043 Page 2 Please contact the Supervisor of Chemical Operations, Mr. James Shipman at (402) 533-7127 if you have any questions.

Sincerely, Manager - Site Regulatory Assurance TWS/imm

Enclosures:

1. Annual Radiological Effluent Release Report

2. Annual Radiological Environmental Operating Report c: A. T. Howell, NRC Regional Administrator, Region IV L. E. Wilkins, NRC Project Manager J. M. Sebrosky, NRC Project Manager J. C. Kirkland, NRC Senior Resident Inspector

OMAHA PUBLIC POWER DISTRICT FORT CALHOUN NUCLEAR STATION 2012 RADIOLOGICAL OPERATING ENVIRONMENTAL REPORT

. ' m

0 0

OMH ULCPWRDSRC 0

OTCLOU TTO 0

0 0

0

aur 01,H2012-OWEDecembRI3,C01 0

0 OTCLOU TTO 0

0AILGCLEVRNETLOEAIGRPR 0EHIA PCFCTO ...

0 0

0 0aur 1 02- eebr3,21 0

0 0

Annual Radiological Environmental Operating Report

This report is submitted in accordance with Section 5.9.4.b of the Technical

Specifications of Fort Calhoun Station Unit No. 1, Facility Operating License DPR-40 for the period January 01, 2012 through December 31, 2012.

In addition, this report provides any observations and anomalies that occurred during

the monitoring period.

Reviewed by: Approved by:

isor-System Chemistry F- Manager-Chemistry

Plant Manger 0

0

teP and CNO 0 .,,/

0 0

0 9

0 0

0

Annual Radiological Environmental Operating Report S

In accordance with Technical Specification 5.9.4.b, herein is the Fort Calhoun

Station (FCS) Annual Radiological Environmental Operating Report for year 2012.

The data provided is consistent with the objectives as specified in Section 5.2.2 of the

Offsite Dose Calculation Manual (ODCM), "Annual Radiological Environmental

'0 Operating Report." The report is presented as follows:

0

1) An introductory discussion of the implementation of the Radiological Environmental Monitoring Program (REMP), including program observations

and environmental impact relevant to the operation of FCS.

0

2) The sample class, sample collection frequency, number of sample locations, and the number of samples collected this reporting period for each parameter is delineated in Table 1.0.

0

3) A statistical evaluation of REMP data is summarized in Table 2.0, in accordance with Regulatory Guide 4.8, Table 1. For each type of sample media and analysis, Table 2.0 presents data separately for all indicator

locations, all control (background) locations, and the location having the

highest annual mean result. For each of these classes, Table 2.0 specifies the

following:

a. The total number of analyses

b. The fraction of analyses yielding detectable results (i.e., results above

the highest Lower Limit of Detection (LLD) for this period)

c. The maximum, minimum, and average results

d. Locations with the highest annual mean are specified by code, name,

and by distance and direction from the center of plant reactor

containment building.

0

4) Table 3.0 is a listing of missed samples and explanations

5) FC-801, 2012 Environmental Land Use Survey Report 0

6) Review of Environmental Inc. Quality Assurance Program

7) Appendix A describes the Interlaboratory Comparison Program 0

8) Appendix B describes the vendor Data Reporting Conventions utilized

9) Appendix C reports the information required when primary coolant specific

activity has exceeded the limits of Technical Specification 2.1.3

10) Appendix D is the Sample Locations/Map P

0

Page 1 of 14 S

0 0

INTRODUCTION

Radiological Environmental Monitoring Program (REMP) - 2012 0

This report gives the results of the Radiological Environmental Monitoring Program (REMP) for the year 2012. The REMP is a requirement of the Fort Calhoun Station (FCS) operating license. It was 0* initiated prior to plant operation in 1973.

The main purpose of the REMP is to ensure public safety by monitoring plant discharges and assessing the effect, if any, of plant operations, on the environment. Samples are collected that would account for various exposure pathways such as ingestion, inhalation, adsorption and direct

exposure. Samples collected on a regular basis include: air, surface water, ground water, milk,

vegetation, fish, sediment, and food crops. Direct radiation is measured by thermoluminescent

dosimeters (TLDs). These samples and TLDs are sent to an independent vendor laboratory for analysis. The vendor uses analytical methods that are sensitive enough to detect a level of activity

far below that which would be considered harmful. Locations for sample collection are based on

radiological and meteorological data from the Annual Effluent Release Report and information

obtained from the Environmental Land Use Survey.

Most samples, particularly indicator samples, are collected in a circular area within a five-mile radius

of plant containment while control locations are usually outside of five miles. This circle is divided into

sixteen equal sectors, each assigned an identification letter "A" through "R" (note: letters "I"and "0" are not used, as they may be mistaken for the numbers "1" and "0"). Sector "A" is centered on North or zero degrees. Sectors are also given directional labels such as "West-Southwest" ("WSW").

Sample locations are listed by number along with their respective distances and direction from plant containment, in the Offsite Dose Calculation Manual (ODCM).

When assessing sample results, data from indicator locations most likely to be effected by plant operations are compared to control locations least or not likely to be effected. Results from an indicator location which were significantly higher than those from a control location, could indicate a plant-attributable effect, and could require additional investigation.

The results of the sample analyses, as required by the FCS Offsite Dose Calculation Manual (ODCM), are presented in the attached statistical tables in accordance with Table 1 of Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants." Sample collection was conducted by plant chemistry/environmental staff. A contract vendor (Environmental Inc.,

Northbrook, Illinois) performed sample analyses, preparation of monthly reports and the statistical evaluation of sample results. All vendor analysis techniques met the sensitivity requirements as stated in the ODCM.

Results for 2012 were within expected ranges and compared closely with historical results, with the following exceptions.

0 0

Page 2 of 14 0

0

0 0 1) Ambient Gamma Radiation 0

0 Ambient gamma radiation is measured by thermoluminescent dosimeters (TLDs) provided by 0 the vendor laboratory. These dosimeters contain calcium sulfate phosphors and are processed quarterly. Thirty-two new thermoluminescent dosimeters were added to the 0 program during the fourth quarter of 2010.

0 All sample results are within the range of historical data and displayed less than 10%

difference when compared to historical averages. Vendor analytical results displayed a high 0 bias for the 2 nd half of the year. A vendor investigation determined a math error at calibration, and results were corrected by the vendor. One TLD could not be retrieved. The power pole that the TLD was attached to was removed during flood reconstruction efforts. No discrepancy 0 between released effluents and resultant radiation dose measured was observed. No changes in plant operation/procedures are required based upon observed impacts to the environment to date.

0 0 10-Year Trend Comparison of TLD Locations 0 Location Avg. Dose (mr/week) 2012 Avg. Dose (mr/week) 0 A 1.36 1.35 B 1.45 1.48 0 C 1.48 1.60 0 D 1.27 1.35 0 F 1.44 1.53 0 G 1.34 1.48 H 1.48 1.55 S 1 1.54 1.68 6 J 1.59 1.60 K 1.51 1.60 S N 1.40 1.50 0 0 1.40 1.50 P* 1.44 1.60 0

0 S* 1.45 1.58 L (Control) 1.29 1.35 0

At least 8-Year comparison due to data availability 0

0

2) Milk/Pasture 0

Milk samples or pasture grasses, if milk is temporarily unavailable, are collected every two 0 weeks during the pasture season from the beginning of May through September, and monthly 0 the rest of the calendar year. Indicator samples are collected from a herd of milk goats at a family farm located approximately 0.7 miles from the plant in Sector K (South-Southwest). The 0 control samples are collected from a commercial dairy cow herd located approximately 9.9 miles from the plant in Sector J (South). These locations are unchanged from last year.

All sample results for Cesium-1 34, Cesium-1 37 and other gammas were at the LLD for both indicator and control locations. No plant-related effects were observed.

Page 3 of 14

0 0

3) Fish Fish are collected on an annual basis. Control samples are collected at a location 0 approximately twenty miles upstream of the plant (river miles 665 - 667). Indicator samples I are collected in the immediate vicinity of the power plant (river miles 644 - 646). Several

species of fish, important to commercial and recreational interest, representing all levels of the

aquatic food chain are collected at both locations.

All sample results are within the range of historical data. Results from both control and

indicator locations were less than LLD for all gamma emitters, indicating no plant-related O effects.

4) Food Crop O Based on the results of the biennial Land Use Survey, the nearest high deposition pathway for food crops is the Alvin Pechnik Farm in Sector H (0.94 miles, 1630). Accordingly, vegetable samples were collected at Alvin Pechnik Farm for the purposes of the 2012 REMP.

Samples were comparable with historical results and within the range of results reported from

the control location garden at Mohr Dairy.

All results were at the LLD for all non-naturally occurring radionuclides. No plant-related

effects were observed.

0 0 5) Sediment O River sediment samples are collected twice a year at an upstream control location (0.09 miles,

40 N) and a downstream indicator location (0.45 miles, 1080 ESE).

All results were at the LLD for all non-naturally occurring radionuclides. No plant-related

effects were observed.

0

6) Air Monitoring Air sample results for 2012 were well within historical limits for all locations. Additionally, all

indicator locations showed results very similar to the control locations.

0 O All sample results are within the range of historical data. All indicator locations displayed less than 17% difference when compared to historical average. All 2012 results when compared to

historical averages are within the stated vendor error acceptance tolerance.

0

Results from both control and indicator locations were less than LLD for gamma emitters and iodine. No changes in plant operation/procedures are required based upon observed impacts to the environment to date.

0 0

0

Page 4 of 14 0

0

0 0

10-Year Trend Comparison of Air Sampling Locations Location Avg. Beta (pCi/m 3) 2012 Avg. Beta (pCi/m 3) 0 Sector B 0.030 .034 Sector D 0.030 .035 Sector I 0.030 .033 Sector J 0.026 .031 0 Sector K* 0.028 .029 Sector F (Control) 0.029 .032 0

At least a 5-Year comparison due to data availability 0 7) Surface Water Water samples are collected upstream of the plant (control location) as well as half-mile 0 downstream and at a municipal water treatment plant on the north edge of Omaha.

0 Results for Cs-1 34, Cs-1 37, and other gammas were all less than LLD. Tritium results were also less than LLD. No plant-related effects were detected.

0

8) Ground Water 0

0 Quarterly residential well water samples are collected at the following locations: Station No.

15, Smith Farm, Station No. 20, Mohr Dairy, Station No. 33, Bansen Farm and Station No. 40, Herber Acreage. All sample results to date have been at the LLD except gross beta due to 0 naturally occurring radionuclides. Gross beta results have ranged from a low of 4.2 pCi/liter to a high of 81.7 pCi/liter, with an average gross beta for the year of 24.2 pCi/liter. Strontium-90 0 analysis is being conducted on wells as part of the station's groundwater protection program.

No plant-related effects were detected.

0 0

0 Page 5 of 14

0 0

Table 1.0 0

0 Sample Collection Program 0

0 Collection Number of Samples Sample Class Frequency Sample Collected this Locations Period.

0 0 Background Radiation (TLDs) Quarterly 47 1871 0

0 Air Particulates Weekly 6 3182 Airborne Iodine Weekly 6 3182 0

0 Biweekly 0 Milk May thru Sept 2 22' 0 Surface Water Monthly 3 36 0

0 Ground Water Quarterly 4 16 0

0 Fish Annually 2 54 0

Sediment Semi-annually 2 4 0

0 Food Crops Annually 3 85 0

0 TOTAL 914 0

0 Note 1: One sample collection was missed due to missing TLD (CR 2012-06762).

0 Note 2: Weekly sampling periods overlapped 2013 resulting in extra samples being 0 collected.

0 Note 3: Milk sample collection totals include vegetation when milk is unavailability.

Note 4: Includes one background sample.

0 Note 5: Variety of samples collected during period.

0 0

0 Page 6 of 14

0 S

0 Table 2.0 Radiological Environmental Monitoring Program Summary Reporting Period January-December, 2012 0 Name of Facility Location of Facility Fort Calhoun Nuclear Power Station - Unit 1 Washinaton. Nebraska Docket No. 50-285 (County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)0 Routine (Units) Analysesa Range' Locationd Rangec Range' Resultse Background Gamma 183 0.5 1.6 (183/183) OTD-2K-(I), 1.9 (4/4) 1.4 (4/4) 0 Radiation (1.2-2.1) 2.52 mi. @ 205° (1.7-2.1) (1.3-1.4)

(TLD)

(mR/week)

Airborne GB 318 0.005 0.032 (265/265) OAP-D-(I) 0.035 (53/53) 0.032 (52/52) 0 Particulates (0.007-0.096) 19.5 miles SW. (0.012-0.064) (0.019-0.076)

(pCi/m 3) GS 24 Cs-1 34 0.001 < LLD -< LLD 0 Cs-137 0.001 < LLD -< LLD 0 Other Gammas 0.001 < LLD -< LLD 0 Airborne 1-131 318 0.070 < LLD -< LLD 0 Iodine (pCi/m3) 0 Milk (pCi/L) 1-131 11 0.5 < LLD -< LLD 0 GS 11 0 K-40 150 1284 (11/11) OFM-D-(C), Mohr 1284 (11/11) 1284 (11/11) 0 (1200-1351) Dairy, 9.8 mi@187° (1200-1351) (1200-1351)

Cs-134 15 < LLD -< LLD 0 0 Cs-137 15 < LLD < LLD 0 Other Gammas 15 < LLD < LLD 0 0

0 Ground Water GB 16 24.2 (12/12) OGW-A-(I), Smith 60.3 (4/4) 5./8 (4/4) 0 (pCi/L) (4.2-81.7) Farm, 1.9 mi @ 1330 (39.9-81.7) 0 H-3 16 300 < LLD -<

(5.3-6.4)

LLD 0 Sr-90 16 0.71 < LLD LLD 0 0 -<

0 (pCi/L)

GS Cs-134 16 15 < LLD -< LLD 0 Cs-137 18 < LLD -< LLD 0 0 Other Gammas 15 < LLD -< LLD 0 Surface Water GS 36 0 (pCi/L) Cs-134 Cs-137 15 18

< LLD

< LLD LLD LLD 0

0 Other Gammas 15 < LLD -< LLD 0 0

H-3 12 300 < LLD < LLD Page 7 of 14

0 0

0 0 Name of Facility Location of Facility Fort Calhoun Nuclear Power Station - Unit 1 Washington, Nebraska Docket No. 50-285

( County, State)

Sample Type and Indicator Location with Highest Control Number 0 Type Number of LLDb Locations0 Annual Mean Locations Non-(Units) Analysesa Mean (F) d Mean (F)c Mean (F)c Routine Range' Location Rangec Range ' Resultse Fish GS 5 (pCi/g wet) Mn-54 0.021 < LLD - < LLD 0 Co-58 0.023 < LLD - < LLD 0 Co-60 0.016 < LLD - < LLD 0 Fe-59 0.071 < LLD - < LLD 0 Zn-65 0.040 < LLD - < LLD 0 Ru-1 03 0.031 < LLD - < LLD 0 Cs-1 34 0.022 < LLD - < LLD 0 Cs-137 0.019 < LLD -< LLD 0 Sediment GS 4 pCi/g dry Mn-54 0.023 < LLD -< LLD 0 Co-58 0.023 < LLD -< LLD 0 Co-60 0.016 < LLD -< LLD 0 Fe-59 0.066 < LLD -< LLD 0 Zn-65 0.051 < LLD -< LLD 0 Cs-134 0.015 < LLD -< LLD 0 Cs-1 37 0.020 < LLD -< LLD 0 Food Crops GS 6 0 (pCi/g wet) Mn-54 0.021 < LLD -< LLD 0 Co-58 0.020 < LLD -< LLD 0 Co-60 0.014 < LLD -< LLD 0 0 Fe-59 0.045 < LLD -< LLD 0 Zn-65 0.043 < LLD LLD 0 0 Zr-Nb-95 0.023 < LLD

-< LLD 0 Cs-134 0.017 < LLD -< LLD 0 Cs-1 37 0.016 < LLD 0 Ba-La-140 0.015 < LLD LLD LLD 0

0 0 Vegetation (MI) GS i1 (pCi/g wet) Mn-54 0.033 < LLD -< LLD 0 0 Co-58 Co-60 0.029 0.026 LLD LLD LLD LLD 0

0 Fe-59 0.050 < LLD -< LLD 0 0 Zn-65 Zr-Nb-95 0.052 0.035 LLD LLD LLD LLD 0

0 S 1-131 Cs-134 0.046 0.026 LLD LLD

< LLD

<- LLD 0

0 0 Cs-137 Ba-La-140 0.029 0.027 LLD LLD LLD LLD 0

0 0

a GB = gross beta, GS = gamma scan.

LLD = nominal lower limit of detection based on a 95% confidence level.

c Mean and range are based on detectable measurements only (i.e., >LLD) Fraction of detectable measurements at specified locations is indicated in parentheses (F).

d Locations are specified: (1) by code, (2) by name, and (3) by distance and direction relative to the Reactor Containment Building.

Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result is considered non-routine if it exceeds the typical pre-operational value for the medium or location.

Page 8 of 14

Table 3.0 Listing of Missed Samples (samples scheduled but not collected)

Sample Date Location Reason 0 Type S TLD 7/2/2012 OTD-2A-(I) The pole on which the TLD had been placed had been 0 removed during flood cleanup activities at the cottonwood marina campground. The TLD could not be located.

0 (CR 2012-06762).

0 0

S 0

0 0

0 S

0 0

0 S

0 0

0 S

Page 9 of 14

CHEMISTRY FORM REV 1 Environmental Land Use Survey Report Page 1 of 3 Sector Dir Land Use Owner Miles Meters Deg Technique -

Survey _Age Group XOQ DOQ Remarks A N RESIDENCE WRIGHT 4.36 7016.74 351 INTERVIEW X X MILK ANIMAL MEAT ANIMAL VEGETATION GROUNDWATER WRIGHT 4.36 7016.74 351 INTERVIEW X X B NNE RESIDENCE RAND,J 1.93 3106.03 12 INTERVIEW X MILK ANIMAL MEAT ANIMAL VEGETATION GROUNDWATER RAND,J 1.93 3106.03 12 INTERVIEW X C I RESIDENCE HANSEN,S 1.52 2446.20 42 INTERVIEW X X MILK ANIMAL MEAT ANIMAL VEGETATION THIELE 1.59 2558.86 52 MAIL SURVEY X GROUNDWATER HANSEN,S 1.52 2446.20 42 MAIL SURVEY X X D I ENE RESIDENCE MEADE,G 4.79 7708.76 63 INTERVIEW X MILK ANIMAL MEAT ANIMAL VEGETATION MEADE,G 4.79 7708.76 63 INTERVIEW X GROUNDWATER MEADE,G 4.79 7708.76 63 INTERVIEW X E IPE RESIDENCE DOTY,J 4.67 7515.64 89 MAIL SURVEY X MILK ANIMAL MEATANIMAL BROTHERS,D 4.91 7901.88 90 INTERVIEW X VEGETATION GROUNDWATER DOTY,J 4.67 7515.64 89 INTERVIEW X F I ESE RESIDENCE WILSON ISLAND 4.22 6791.43 121 INTERVIEW X MILK ANIMAL MEAT ANIMAL VEGETATION GROUNDWATER WILSON ISLAND 4.22 6791.43 121 INTERVIEW X G I SE RESIDENCE CARTER,T 1.67 2687.60 145 INTERVIEW X MILK ANIMAL MEAT ANIMAL VEGETATION KALIN,W 1.74 2800.26 145 INTERVIEW X GROUNDWATER SMITH 1.99 3202.59 134 INTERVIEW X Page 10 of 14

CHEMISTRY FORM 2012 REV 1 Environmental Land Use Survey Report Page 2 of 3 Sector Dir Land Use Owner Miles Meters Deg Survey A e Grou XOQ DOQ Remarks Technique <

H SSE RESIDENCE LOMP .65 1046.07 163 INTERVIEW X MILK ANIMAL MEAT ANIMAL HINELINE,R 1.82 2929.01 148 INTERVIEW X VEGETATION PECHNIK,A .94 1512.78 163 INTERVIEW X GROUNDWATER LOMP .65 1046.07 163 INTERVIEW X J SIS RESIDENCE DOWLER .73 1174.82 175 INTERVIEW X I MILK ANIMAL MEAT ANIMAL DICKES,L 2.60 4184.29 170 INTERVIEW X VEGETATION DOWLER .73 1174.82 175 INTERVIEW X GROUNDWATER DOWLER .73 1174.82 175 INTERVIEW X KISSW RESIDENCE D.MILLER .65 1046.07 203 INTERVIEW X MILKANIMAL MEAT ANIMAL T. DEIN 2.00 3218.69 189 INTERVIEW X VEGETATION T.DEIN 2.00 3218.69 189 INTERVIEW X GROUNDWATER D.MILLER .65 1046.07 203 INTERVIEW X L SW RESIDENCE ROBERTSON,D .73 1174.82 224 INTERVIEW X MILK ANIMAL MEAT ANIMAL ROBERTSON,D .73 1174.82 224 INTERVIEW X VEGETATION ROBERTSON,D .73 1174.82 224 INTERVIEW X GROUNDWATER ROBERTSON,D .73 1174.82 224 INTERVIEW X M JWSW RESIDENCE BENSEN,M 1.06 1705.90 257 MAIL SURVEY X MILK ANIMAL MEAT ANIMAL WRICHB 2.42 3894.61 250 MAIL SURVEY X VEGETATION RUSSELL,D 1.21 1947.31 246 MAIL SURVEY X GROUNDWATER BENSEN,M 1.06 1705.90 257 MAIL SURVEY X N I W RESIDENCE NIELSEN,D 1.20 1931.21 263 INTERVIEW X MILK ANIMAL MEAT ANIMAL ANDERSON,J 3.25 5230.37 281 INTERVIEW X VEGETATION ASMUSSEN,G 1.30 2092.15 270 MAIL SURVEY X GROUNDWATER ANDERSON,J 3.25 5230.37 281 INTERVIEW X P JWNW RESIDENCE WACHTER,G 2.27 3653.21 302 INTERVIEW X MILK ANIMAL MEAT ANIMAL WACHTER,G 2.27 3653.21 302 INTERVIEW X VEGETATION WACHTER,G 2.27 3653.21 302 INTERVIEW X GROUNDWATER WACHTER,G 2.27 3653.21 302 INTERVIEW X Page 11 of 14

CHEMISTRY FORM REV I Environmental Land Use Survey Report Page 3 of 3 Sector Dir Land Use Owner Miles Meters Deg Survey Age Grou XOQ DOQ Remarks Technique .

Q NW RESIDENCE HANSEN,R 2.40 3862.43 318 INTERVIEW X MILK ANIMAL MEAT ANIMAL VEGETATION HANSEN,R 2.40 3862.43 318 INTERVIEW X GROUNDWATER HANSEN,R 2.40 3862.43 318 INTERVIEW X R JNNW RESIDENCE SHUBERT,B 2.08 3347.44 330 INTERVIEW X MILK ANIMAL MEAT ANIMAL SONDERUP 3.73 6002.85 328 INTERVIEW X VEGETATION SONDERUP 3.73 6002.85 328 INTERVIEW X GROUNDWATER SONDERUP 3.73 6002.85 328 INTERVIEW X Performed by 6 1i, Reviewed by Page 1 . of 14

0 0

Review of Environmental Inc., Quality Assurance Program

Fort Calhoun Station contracts with Environmental Inc., Midwest Laboratory (vendor

lab) to perform radioanalysis of environmental samples. Environmental Inc.

participates in interlaboratory comparison (cross-check) programs as part of its quality control program. These programs are operated by such agencies as the

Department of Energy, which supply blind-spike samples such as milk or water

containing concentrations of radionuclides unknown to the testing laboratory. This

type of program provides an independent check of the analytical laboratory's procedures and processes, and provides indication of possible weaknesses. In

addition, Environmental Inc. has its own in-house QA program of blind-spike and

duplicate analyses.

0 Vendor in-house spike sampling was performed without a failure and in-house blank analyses were performed within acceptable ranges.

0

Three failures were observed from QA samples performed as part of the Environmental Resource Associates Inter-laboratory Comparison Cross-check

Program. Drinking water sample ERW-1789, experienced high results for a Gross

Beta. Gross beta was measured at 76.2 +/- 1.8 pCi/L with an acceptable band of

29.6-51.5 pCi/I. The stated error was a sample dilution problem. A new sample dilution was prepared; the analysis was re-performed, and produced acceptable results. The stated error was a sample dilution problem. Gross Beta performed for

Department of Energy's MAPEP was performed successfully for 2012. Gross Beta

sampling at FCS indicator stations displayed normal trends. One location had its well

replaced after flooding from last year damaged it. This locale did show an increase over previous trending; however connecting of these results to this sample dilution

issue seems unwarranted. Water sample ERW-1257 was performed to determine

isotopes of Radium. Determinations for Ra-226 and Ra-228 displayed a high bias.

Reanalysis of both samples produced acceptable results. No reason was given for the failures. A new test was ordered from ERA to be performed in the first quarter of 2013 and will be evaluated then. Radium analysis is not part of the FCS REMP

program. OPPD results were not negatively impacted by these vendor identified

issues.

Five DOE mixed analytic failures occurred during the calendar year. Soil sample

STSO-1 766 failed low on Am-241. Sample result was 88.50 +/- 8.30 Bq/kg for a

range of 111-207 Bq/kg. Investigation of anomalous result was inconclusive, and

insufficient sample was available to perform reanalysis. ERA soil analysis for AM-241 produced acceptable results. All isotopes analyzed as part of the FCS REMP program produced acceptable results. Water sample STW-5445, failed low on Am-

241. Sample result was 0.64 +/- 0.04 Bq/L for a range of 0.74-1.38 Bq/L. An issue

with sample recovery for the matrix was identified as the cause of the failure. A correction using the blank to determine recovery and reanalysis produced acceptable results. Air particulate filter, STAP-5401 failed high for Am-241 and low

for uranium 233/234 analyses. Eleven other analyses performed on the filter were

completed satisfactorily. All three failed analyses were successfully re-performed.

0

Page 13 of 14 0

0

0 0

Performing the testing on a larger sample size resulted in the reduction in counting 0 error. Gamma scans for the FCS REMP programs had no positive detections at 0 control or indicator stations, and Uranium analyses are not part of the station's 0 program. Vegetation sample, STVE-5395, failed high on cobalt 57 activity. The original sample result was 7.44 +/- 0.04 Bq/total sample, for an acceptable range of 0 3.96-7.36 Bq/total sample. The gamma counting for five nuclides show a high bias, 0 however 4 out of the 5 five test results were in the acceptable range. Four acceptable test results included isotopes that are in FCS REMP program. No gamma counts from control or indicator spectrums had plant related nuclides S present. A sample geometry adjustment was made and the sample recounted. The 0 re-performed analysis was within acceptable limits (6.74).

0 0 No test results failed both the ERA and DOE methodologies for a given sample type.

Reanalysis produced acceptable results. Documentation of bias being present, 0 despite falling within acceptable performance, visibly demonstrates the vendor's 0 commitment to reporting and resolving deficiencies.

0 These results indicate the vendor's ability to self-identify and correct any deviations 0 from acceptable or expected results. The test results had no impact on Fort Calhoun samples and were documented as such by the vendor.

S 0

0 0

S 0

0 S

Page 14 of 14

0 0

S S

0 S

ATI dw a~try r 700 Landwehr Road - NorthJbrook. IL60062-23 10 phone (847) 564-0700 - la (847) 564-4517 0

0 S

S 0

0 S

0 0

S 0 APPENDIX A S INTERLABORATORY COMPARISON PROGRAM RESULTS 0

0 0

0 NOTE: Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by 0 Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are 0 reported inAppendix A.TLD Intercomparison results, in-house spikes, blanks, duplicates and 0 mixed analyte performance evaluation program results are also reported. Appendix A is updated S four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January, 2012 through December, 2012

0 0

1 ~AppendixA Interlaboratory Comparison Program Results 5 Environmental, Inc., Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possible problems.

5 Participant laboratories measure the concentration of specified radionuclides and report them to the issuing 0! agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control 0 limits indicate a need to check the instruments or procedures used.

5Results in Table A-1 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted 0 previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.

Table A-2 lists results for thermoluminescent dosimeters (TLDs), via International 5I Intercomparison of Environmental Dosimeters, when available, and internal laboratory testing.

SI Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples 0I are prepared using NIST traceable sources. Data for previous years available upon request.

Table A-4 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for

previous years available upon request.

Table A-5 lists REMP specific analytical results from the in-house "duplicate" program for the past twelve 0 months. Acceptance is based on the difference of the results being less than the sum of the errors.

5t Complete analytical data for duplicate analyses is available upon request.

5) The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation

I Program.

et Results in Table A-7 were obtained through participation in the environmental sample crosscheck program 5I administered by Environmental Resources Associates, serving as a replacement for studies conducted

previously by the Environmental Measurement Laboratory Quality Assessment Program (EML).

5Attachment A lists the laboratory precision at the I sigma level for various analyses. The acceptance criteria

in Table A-3 is set at +/-:2 sigma.

I Out-of-limit results are explained directly below the result.

A S

S S

S

I Al S

0 S

0 0

0 TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.

0 Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result b Result' Limits Acceptance 0

ERW-1783 04/09/12 Sr-89 62.2 +/- 6.0 58.5 46.9 - 66.3 Pass ERW-1783 04/09/12 Sr-90 33.7 +/- 2.1 37.4 27.4 - 43.1 Pass 0 ERW-1786 04/09/12 Ba- 133 75.7 +/- 4.1 82.3 69.1 -90.5 Pass ERW-1786 04/09/12 Co-60 71.9 +/- 4.0 72.9 65.6 82.6 Pass 0 ERW-1786 04/09/12 Cs-134 70.0 +/- 4.3 74.2 60.6 -81.6 Pass S ERW-1786 04/09/12 Cs-137 151.5 +/- 6.1 155.0 140.0 - 172.0 Pass ERW-1786 04/09/12 Zn-65 108.3 +/- 89.0 105.0 94.5 - 125.0 Pass 0

0 ERW-1789 ERW-1789 04/09/12 04/09/12 Gr. Alpha Gr. Beta 55.0 +/- 2.4 38.3 +/- 1.3 62.9 44.2 33.0 - 78.0 29.6 -51.5 Pass d Pass 0 ERW-1795 04/09/12 Ra-226 6.4 +/- 0.4 5.7 4.3 - 6.9 Pass 0 ERW-1795 04/09/12 Ra-228 5.4 +/- 1.2 4.6 2.7 - 6.3 Pass ERW-1795 04/09/12 Uranium 56.2 +/- 2.6 61.5 50.0 - 68.2 Pass S

0 ERW-1798 04/09/12 H-3 16023 +/-355 15800 13800-17400 Pass ERW-6283 10/05/12 Sr-89 41.5 +/- 4.1 39.1 29.7 - 46.1 Pass ERW-6283 10/05/12 Sr-90 19.7 +/- 1.6 20.1 14.4 - 23.8 Pass 0

S ERW-6286 ERW-6286 10/05/12 10/05/12 Ba-133 Co-60 82.7 77.2

+/- 4.4

+/- 3.7 84.8 78.3 71.3 70.5

-93.3

- 88.5 Pass Pass 0 ERW-6286 10/05/12 Cs-1 34 74.4 +/- 1.5 76.6 62.6 - 84.3 Pass 0 ERW-6286 ERW-6286 10/05/12 10/05/12 Cs-137 Zn-65 183.0 211.0

+/- 6.2

+/- 9.9 183.0 204.0 165.0 184.0

- 203.0

- 240.0 Pass Pass 0

ERW-6288 10/05/12 Gr. Alpha 47.0 +/- 2.3 58.6 30.6 - 72.9 Pass 0 ERW-6288 10/05/12 Gr. Beta 33.4 +/- 1.2 39.2 26.0 - 46.7 Pass 0 ERW-6290 10/05/12 1-131 23.3 +/- 1.0 24.8 20.6 - 29.4 Pass 0 ERW-6295e 16.5 +/- 0.7 10/05/12 Ra-226 15.0 11.2-17.2 Pass ERW-6295 10/05/12 Ra-228 4.9 +/- 1.1 4.6 2.7 -6.2 Pass 0 ERW-6295 10/05/12 Uranium 61.2 +/- 1.8 62.5 50.8 - 69.3 Pass 0

0 0 a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency 0 b testing in drinking water conducted by Environmental Resources Associates (ERA).

Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.

c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.

d Result of reanalysis. Sample dilution problem suspected. A new dilution was prepared and the sample reanalyzed.

Original analysis results, 76.2 +/- 1.8 pCi/L.

e Results of reanalyses, original submission (pCi/L): Ra-226, 17.52 +/- 0.69 Ra-228, 7.44 +/- 1.1.49.

A new test was ordered from Environmental Resources Associates, results will be updated for first quarter, 2013.

Al-1

0 0

0 0 el Attachment A

ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES

LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES' One standard deviation

Analysis Level for single determination Gamma Emitters 5 to 100 pCi/liter or kg 5.0 pCi/liter

> 100 pCi/liter or kg 5% of known value Strontium-89b 5 to 50 pCilliter or kg 5.0 pCi/liter

> 50 pCi/liter or kg 10% of known value Strontium-90b 2 to 30 pCi/liter or kg 5.0 pCi/liter

> 30 pCi/liter or kg 10% of known value 0

Potassium-40 - 0.1 g/liter or kg 5% of known value

Gross alpha 5 20 pCi/liter 5.0 pCi/liter

> 20 pCi/liter 25% of known value

Gross beta :S100 pCi/liter 5.0 pCi/liter

> 100 pCi/liter 5% of known value

Tritium 5 4,000 pCilliter + lc =

169.85 x (known)°0 933

> 4,000 pCi/liter 10% of known value S

Radium-226,-228 > 0.1 pCi/liter 15% of known value

Plutonium > 0.1 pCi/liter, gram, or sample 10% of known value

Iodine-131, <55 pCi/liter 6 pCi/liter

Iodine-129b > 55 pCi/liter 10% of known value

Uranium-238, -<35 pCi/liter 6 pCi/liter Nickel-63b > 35 pCi/liter 15% of known value

Technetium-99b Iron-55b 50 to 100 pCi/liter 10 pCi/liter

> 100 pCi/liter 10% of known value 0

Other Analyses b 20% of known value 0

0 From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies 0 Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.

b Laboratory limit.

A2 0

0 0

O TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaSO4 : Dy Cards).

0 0 mR 0 Lab Code Date Known Lab Result Control Description Value +/-2 sigma Limits Acceptance 0

0 Environmental, Inc.

0 2012-1 2/7/2012 30 cm. 74.87 87.22 +/- 2.86 52.41 - 97.33 Pass 2012-1 2/7/2012 40 cm. 42.12 53.70 +/- 4.53 29.48 - 54.76 Pass 0 2012-1 2012-1 2/7/2012 2/7/2012 50 cm.

70 cm.

26.95 13.75 33.04 13.26

+/- 1.96

+/- 1.15 18.87 - 35.04 Pass 9.63-17.88 Pass 0 2012-1 2/7/2012 75 cm. 11.98 13.38 +/- 1.68 8.39 -15.57 Pass 0 2012-1 2012-1 2/7/2012 2/7/2012 80 cm.

90 cm.

10.53 8.32 11.27 7.79

+/- 0.95

+/- 0.83 7.37 -13.69 5.82 - 10.82 Pass Pass 2012-1 2/7/2012 100 cm. 6.74 5.91 +/- 0.25 4.72 -8.76 Pass 0 2012-1 2/7/2012 110 cm. 5.57 4.63 +/- 0.83 3.90 - 7.24 Pass 2012-1 2/7/2012 120 cm. 4.68 3.96 +/- 1.68 3.28 -6.08 Pass 2012-1 2/7/2012 150 cm. 2.99 2.41 +/- 0.08 2.09 -3.89 Pass 2012-1 2/7/2012 180 cm. 2.08 2.02 +/- 0.25 1.46 -2.70 Pass S

0 Environmental, Inc.

0 2012-2 9111/2012 40 cm. 33.75 43.74 +/- 1.31 23.63 - 43.88 Pass 2012-2 9/11/2012 50 cm. +/- 0.82 0 2012-2 9/11/2012 60 cm.

21.6 15 25.37 16.63 +/- 0.45 15.12 - 28.08 10.50 - 19.50 Pass Pass 2012-2 9/11/2012 70 cm. 11.02 10.58 +/- 0.20 7.71 -14.33 Pass 0 2012-2 9/11/2012 80 cm. 8.44 8.55 +/- 1.18 5.91 - 10.97 Pass 2012-2 9/11/2012 90 cm. 6.67 5.75 +/- 0.33 4.67 -8.67 Pass 2012-2 9/11/2012 100 cm. 5.4 4.44 +/- 0.22 3.78 -7.02 Pass 0 2012-2 9/11/2012 110 cm. 4.46 3.85 +/- 0.05 3.12 -5.80 Pass 2012-2 9/11/2012 120 cm. 3.75 3.03 +/- 0.71 2.63 -4.88 Pass 2012-2 9/11/2012 150 cm. 2.4 1.82 +/- 0.10 1.68-3.12 Pass 0 2012-2 9/11/2012 180 cm. 1.67 1.19 +/- 0.34 1.17 -2.17 Pass 0

0 0

A2-1

0 0

S 0

0 TABLE A-3. In-House "Spiked" Samples 0

0 Concentration (pCi/L)8 Lab Code b Date Analysis Laboratory results Known Control 0 2s, n=1 c Activity Limits d Acceptance 0

SPW-41824 2/15/2012 Ra-228 24.85 +/- 2.14 28.75 0 W-22712 2/27/2012 Gr. Alpha 14.59 +/- 0.34 20.00 20.13 - 37.38 10.00 - 30.00 Pass Pass 0 W-22712 SPAP-1032 2/27/2012 3/5/2012 Gr. Alpha 43.57 +/- 0.40 41.70 20.85 - 62.55 Pass Cs-1 34 7.06 +/- 1.71 5.26 0.00 - 15.26 Pass 0 SPAP-1032 3/5/2012 Cs-137 102.63 +/- 3.13 104.24 93.82 -114.66 Pass 0 SPAP-1034 SPW-1036 3/5/2012 3/5/2012 Gr. Beta Cs-134 44.30 43.23

+/- 0.11

+/- 3.84 46.88 39.42 28.13 - 65.63 29.42 - 49.42 Pass Pass 0 SPW-1036 3/5/2012 Cs-1 37 57.44 +/- 4.60 52.12 42.12 - 62.12 Pass SPW-1036 3/5/2012 Sr-90 60.51 +/- 1.93 61.52 49.22 - 73.82 Pass 0 SPM1-1038 SPMI-1038 3/5/2012 3/5/2012 Cs-1 34 Cs-137 37.79 +/- 4.06 54.75 +/- 5.09 39.42 52.12 29.42 - 49.42 Pass 42.12 - 62.12 Pass 0 SPW-1045 3/5/2012 H-3 68022 +/- 746 69048 55238 - 82858 Pass SPW-1047 3/5/2012 Ni-63 0 SPW-1049 3/5/2012 C-14 217.10 3858.90

+/- 3.64

+/- 12.79 206.64 4738.80 144.65 - 268.63 2843.28 - 6634.32 Pass Pass S W-31412 3/14/2012 Ra-226 13.13 +/- 0.36 16.70 11.69 - 21.71 Pass SPW-1520 3/23/2012 U-238 45.67 +/- 2.02 41.70 29.19 - 54.21 Pass SPW-41825 4/10/2012 0 WW-1547 4/16/2012 Ra-228 Ba-133 28.48 18.99

+/- 2.51

+/- 4.67 28.35 26.70 19.85 - 36.86 16.70 - 36.70 Pass Pass 0 WW-1547 4/16/2012 Cs-134 9.28 +/- 2.82 8.68 0.00 - 18.68 Pass WW-1547 4/16/2012 Cs-137 27.77 +/- 4.49 29.70 19.70 - 39.70 Pass W-51712 5/17/2012 Ra-226 17.29 +/- 0.43 16.70 11.69 - 21.71 Pass W-61112 6/11/2012 Gr. Alpha 22.16 +/- 0.45 20.00 10.00 - 30.00 Pass W-61112 6/11/2012 Gr. Beta 43.57 +/- 0.40 45.20 35.20 - 55.20 Pass SPAP-4418 7/25/2012 Gr. Beta 43.74 +/- 0.11 46.50 27.90 - 65.10 Pass SPAP-4420 7/25/2012 Cs-134 4.54 +/- 0.73 4.60 2.76 - 6.44 Pass SPAP-4420 7/25/2012 Cs-137 104.70 +/- 2.77 103.30 92.97 -113.63 Pass SPMI-4422 7/25/2012 Co-60 31.43 +/- 2.12 31.62 21.62 - 41.62 Pass SPMI-4422 7/25/2012 Cs-134 16.50 +/- 1.17 16.15 6.15 -26.15 Pass SPMI-4422 7/25/2012 Cs-137 29.60 +/- 2.61 26.64 16.64 - 36.64 Pass SPMI-4422 7/25/2012 Sr-90 31.60 +/- 1.35 30.47 24.38 - 36.56 Pass SPW-4424 7/25/2012 Co-60 38.52 +/- 1.76 37.95 27.95 - 47.95 Pass SPW-4424 7/25/2012 Cs-137 33.23 +/- 2.27 32.01 22.01 - 42.01 Pass SPW-4424 7/25/2012 Sr-90 36.56 +/- 1.58 40.60 32.48 - 48.72 Pass SPF-4426 7/25/2012 Cs-1 34 947.50 +/- 42.50 1025.00 922.50 - 1127.50 Pass SPF-4426 7/25/2012 Cs-137 2692.00 +/- 62.40 2480.00 2232.00 - 2728.00 Pass SPW-4428 7/25/2012 C-14 4325.70 +/- 15.80 4738.80 2843.28 - 6634.32 Pass SPW-4430 7/25/2012 H-3 70119.40 +/- 773.40 67570.00 54056.00 - 81084.00 Pass SPW-4432 7/25/2012 Ni-63 187.20 +/- 3.85 206.80 144.76 - 268.84 Pass W-81712 8/17/2012 Ra-226 14.94 +/- 0.40 16.70 11.69 - 21.71 Pass SPW-5407 8/29/2012 U-238 42.95 +/- 0.11 41.70 29.19 - 54.21 Pass SPW-18022 9/10/2012 Ra-228 29.03 +/- 2.80 28.21 19.75 - 36.67 Pass A3-1

0 0

0 TABLE A-3. In-House "Spiked" Samples 0

Concentration (pCi/L)a 0

Lab Code b Date Analysis Laboratory results Known Control 0 2s, n=l c Activity Limitsd Acceptance 0

W-91012 9/10/2012 Gr. Alpha 19.95 +/- 0.42 20.00 Pass 0 W-91012 9/10/2012 Gr. Beta 43.47 +/- 0.40 45.20 10.00 - 30.00 35.20 - 55.20 Pass 0

0 W-100312 10/3/2012 Gr. Alpha 19.95 +/- 0.41 20.00 10.00 - 30.00 Pass W-100312 10/3/2012 Gr. Beta 44.21 +/- 0.40 45.20 35.20 - 55.20 Pass 0 W-101812 10/18/2012 Ra-226 18.80 +/- 0.43 16.70 11.69 -21.71 Pass ESO-7235 12/6/2012 Sr-90 138.79 +/- 2.67 161.05 128.84 - 193.26 Pass SPW-7753 12/6/2012 U-238 45.55 +/- 5.05 41.70 29.19 - 54.21 Pass 0 SPW-18023 12118/2012 Ra-228 31.59 +/- 2.99 25.98 18.19 - 33.77 Pass 0

0 0

S S

0 0

0 9 Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/m 3), and solid samples (pCi/g).

0 b Laboratory codes : W (Water), MI (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister). F (fish), U (urine).

'Results are based on single determinations.

d Control limits are established from the precision values listed in Attachment A of this report, adjusted to +/- 2U.

0 NOTE: For fish, Jello is used for the Spike matrix. For Vegetation, cabbage is used for the Spike matrix.

A3-2

TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysisb Laboratory results ( 4 .6 6C) Acceptance Type LLD Activityc Criteria (4.66 CT) 0 SPW-41814 Water 2/15/2012 Ra-228 0.65 0.49 +/- 0.36 2 0 W-22712 W-22712 Water Water 2/27/2012 Gr. Alpha 0.42 -0.04 +/- 0.29 1 2/27/2012 Gr. Beta 0.74 -0.54 +/- 0.50 3.2 SPAP-1031 Air Filter 3/5/2012 Cs-134 1.89 100 0 SPAP-1031 SPAP-1033 Air Filter Air Filter 315/2012 3/5/2012 Cs-137 Gr. Beta 1.16 0.003 0.013 +/- 0.003 100 0.01 SPW-1035 Water 3/512012 Cs-134 2.40 10 SPW-1035 Water 31512012 Cs-137 2.88 10 0 SPW-1035 Water 3/5/2012 1-131(G) 2.35 20 SPW-1035 Water 3/5/2012 Sr-90 0.60 -0.11 +/- 0.26 1 S SPMI-1037 Milk 3/5/2012 Cs-134 2.85 10 SPMI-1037 Milk 3/5/2012 0 SPMI-1037 Milk 3/5/2012 Cs-137 1-131(G) 3.73 3.24 10 20 0 SPW-1044 Water 3/512012 H-3 146.10 37.10 +/- 74.40 200 SPW-1046 Water 3/5/2012 Ni-63 19.07 8.30 +/- 11.79 20 SPW-1048 Water 3/5/2012 0 SPW-1 166 water 3/912012 C-14 C-14 5.70 6.79 2.99 +/- 3.04 1.11 200 200 W-31412 Water 3/14/2012 Ra-226 0.034 0.043 +/- 0.027 1 SPW-1521 Water 3/23/2012 U-238 0.10 0.09 +/- 0.11 1 S W-51712 Water 4/24/2012 Ra-226 0.04 0.04 +/- 0.03 1 0 W-61112 Water 6/1112012 Gr. Alpha 0.47 -0.14 +/- 0.32 1 3.2 W-61112 Water 6/1112012 Gr. Beta 0.71 0.29 +/- 0.51 0

SPW-41815 Water 7/7/2011 Ra-228 0.77 0.52 +/- 0.42 2 0 SPAP-4417 Air Filter 7/25/2012 Gr. Beta 0.001 0.021 +/- 0.003 0.01 SPMI-4421 Milk 7/25/2012 Co-60 4.29 10 0 SPMI-4421 SPMI-4421 Milk Milk 7/25/2012 7/25/2012 Cs-134 Cs-1 37 3.58 4.60 10 10 SPMI-4421 Milk 7/25/2012 Sr-90 0.45 0.53 +/- 0.27 1 0 SPW-4423 Water 7/25/2012 Co-60 1.88 10 SPW-4423 Water 7/25/2012 Cs-1 34 2.38 10 0 SPW-4423 Water 7125/2012 Cs-137 2.80 10 I

SPW-4423 water 7/25/2012 Sr-90 0.45 0.08 +/- 0.22 Fish 7/25/2012 100 0 SPF-4425 SPF-4425 Fish 7/25/2012 Co-60 Cs-134 6.74 7.47 100 SPF-4425 Fish 7/25/2012 Cs-137 9.62 100 SPW-4427 Water 7/25/2012 C-14 10.93 3.54 +/- 5.84 200 0 SPW-4431 Water 7/25/2012 Ni-63 19.00 5.50 +/- 11.70 20 W-81712 Water 8/17/2012 Ra-226 0.038 0.035 +/- 0.030 1 0 SPW-5408 Water 812912012 U-238 0.039 0.015 +/- 0.057 1 A4-1

0 0

0 TABLE A-4. In-House "Blank" Samples 0

0 Lab Code Sample Date Concentration (pCi/L)a Analysis' Laboratory results (4.66a) Acceptance 0 Type LLD Activityc Criteria (4.66 a)

SPW-18032 Water 9/10/2012 Ra-228 0.78 0.85 + 0.46 2 S W-91012 Water 9/10/2012 Gr. Alpha 0.42 0.027 +/- 0.29 1 W-91012 Water 9/10/2012 Gr. Beta 0.75 -0.13 + 0.52 3.2 W-100312 Water 10/3/2012 Gr. Beta 0.77 -0.32 _ 0.53 3.2 W-100312 Water 10/3/2012 Gr. Beta 0.43 0.06 + 0.30 3.2 0 W-101812 Water 10/18/2012 Ra-226 0.04 0.04 +/- 0.03 1 0 SPW-7754 Water 12/6/2012 U-238 0.10 0.02 +/- 0.08 2

SPW-18033 Water 12/18/2012 Ra-228 0.98 0.43 +/- 0.50 0

0 0

0 a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).

0 b 1-131(G); iodine-131 as analyzed by gamma spectroscopy.

Activity reported is a net activity result. For gamma spectroscopic analysis, activity detected below the LLD value is not reported.

0 S

A4-2

0 0

0 0 TABLE A-5. In-House "Duplicate" Samples 0

0 Concentration (pCi/L)a 0 Averaged Lab Code Date Analysis First Result Second Result Result 0 Acceptance 0 CF-20, 21 1/3/2012 Gr. Beta 14.50 +/- 0.29 15.02 +/- 0.30 14.76 +/- 0.21 Pass CF-20, 21 113/2012 K-40 12.88 +/- 0.55 12.40 +/- 0.53 12.64 +/- 0.38 Pass CF-20, 21 1/3/2012 Sr-90 0.01 +/- 0.01 0.01 +/- 0.01 0.01 +/- 0.00 Pass 0 P-9133, 9134 1/3/2012 H-3 108.86 +/- 83.03 206.60 +/- 86.38 157.73 +/- 59.91 Pass U-302, 303 1/17/2012 Beta (-K40) 6.84 +/- 2.91 5.24 +/- 2.56 6.04 +/- 1.94 Pass S-386,387 1/23/2012 Ac-228 0.77 +/- 0.11 0.79 +/- 0.14 0.78 +/- 0.09 Pass 0 S-386,387 1/23/2012 Bi-214 0.80 +/- 0.07 0.73 +/- 0.11 0.77 +/- 0.07 Pass S-386,387 1/23/2012 Pb-214 0.74 0.75 +/- 0.11 0 S-386,387 1/23/2012 TI-208 0.21

+/- 0.06

+/- 0.02 0.21 +/- 0.04 0.75 0.21

+/- 0.06

+/- 0.02 Pass Pass 0 S-386,387 1/23/2012 U-235 0.05 +/- 0.02 0.12 +/- 0.05 0.09 +/- 0.03 Pass WW-619, 620 1/31/2012 H-3 257.20 +/- 86.00 305.80 +/- 88.30 281.50 0 MI-702,703 2/6/2012 K-40 1337.00 +/- 123.00 1460.40 +/- 102.00 1398.70

+/- 61.63

+/- 79.90 Pass Pass 0 WW-892, 893 2/17/2012 Gr. Beta 3.46 +/- 0.56 3.77 +/- 0.59 3.61 +/- 0.41 Pass S-850,851 2/22/2012 Cs-1 34 0.14 +/- 0.02 0.13 +/- 0.02 0.14 +/- 0.01 Pass S-850,851 2/22/2012 Cs-137 0.21 +/- 0.03 0.22 +/- 0.03 0.22 +/- 0.02 Pass 0 W-1251,1252 3/6/2012 Gr. Alpha 1.20 +/- 0.62 1.27 +/- 0.92 1.24 +/- 0.55 Pass W-1251,1252 3/6/2012 Gr. Beta 0 W-1251,1252 3/6/2012 H-3 16.86 5235.52

+/- 1.43

+/- 230.91 15.14 4893.24

+/- 1.34

+/- 224.55 16.00 5064.38

+/- 0.98

+/- 161.05 Pass Pass S W-1251,1252 3/6/2012 Tc-99 19.67 +/- 3.60 14.46 +/- 3.51 17.07 +/- 2.51 Pass AP-1209,1210 3/8/2012 Be-7 0.24 +/- 0.12 0.20 +/- 0.11 0.22 +/- 0.08 Pass 0 XWW-1 564,1565 3/14/2012 H-3 308.00 +/- 88.00 293.00 +/- 87.00 300.50 +/- 61.87 Pass SG-1438, 1439 3/19/2012 Ac-228 6.01 +/- 0.30 6.23 +/- 0.31 6.12 +/- 0.22 Pass 3/19/2012 S SG-1438,1439 WW-1585,1586 3/19/2012 Pb-214 H-3 4.69 3124.50

+/- 0.49

+/- 176.96 5.20 2982.38

+/- 0.54

+/- 173.62 4.95 3053.44

+/- 0.36

+/- 123.96 Pass Pass AP-2103, 2104 3/28/2012 Be-7 0.080 +/- 0.016 0.076 +/- 0.013 0.078 +/- 0.010 Pass 0 AP-2166, 2167 3/28/2012 Be-7 0.061 +/- 0.020 0.071 +/- 0.016 0.066 +/- 0.013 Pass AP-1632,1633 3/29/2012 Be-7 0.26 +/- 0.12 0.24 +/- 0.12 0.25 +/- 0.08 Pass 0

E-1 653, 1654 4/2/2012 Gr. Beta 1.53 +/- 0.05 1.55 +/- 0.04 1.54 +/- 0.03 Pass 0 E-1653,1654 4/2/2012 K-40 1.34 +/- 0.13 1.36 +/- 0.14 1.35 +/- 0.10 Pass SG-1677,1678 4/2/2012 Ac-228 6.63 +/- 0.37 6.49 +/- 0.33 6.56 +/- 0.25 Pass 0 SG-1677,1678 4/2/2012 Pb-214 4.77 +/- 0.16 5.07 +/- 0.14 4.92 +/- 0.11 Pass 0 SWU-1719,1720 4/3/2012 Gr. Beta 1.16 +/- 0.41 1.53 +/- 0.44 1.35 +/- 0.30 Pass W-1698,1699 4/5/2012 Gr. Beta 10.86 +/- 1.49 9.42 +/- 1.32 10.14 +/- 1.00 Pass 0 W-1698,1699 W-1698,1699 4/5/2012 4/5/2012 Ra-226 Ra-228 0.41 +/- 0.15 1.46 +/- 0.76 0.67 1.48

+/- 0.18

+/- 0.74 0.54 +/- 0.12 Pass 1.47 +/- 0.53 Pass 0 SG-1761, 1762 4/10/2012 Ac-228 16.26 +/- 0.53 16.55 +/- 0.44 16.41 +/- 0.34 Pass 4/10/2012 0 SG-1761, 1762 AP-2019, 2020 4/12/2012 Pb-214 Be-7 14.16 +/- 1.44 0.17 +/- 0.10 15.40 0.17

+/- 1.56

+/- 0.08 14.78 +/- 1.06 Pass 0.17 +/- 0.07 Pass 0 DW-2272, 2273 4/20/2012 1-131 0.52 +/- 0.24 0.49 +/- 0.27 0.51 +/-0.18 Pass 0 DW-2356,2357 4/24/2012 Gr. Beta 12.82 +/- 2.01 9.47 +/- 1.74 11.14 +/- 1.33 Pass S

A5-1

0 0

0 0 TABLE A-5. In-House "Duplicate" Samples 0

0 Concentration (pCi/L)a 0 Averaged Lab Code Date Analysis First Result Second Result Result Acceptance 0 G-2403, 2404 5/1/2012 Be-7 1.77 +/- 0.21 1.55 +/- 0.33 1.66 +/- 0.20 Pass G-2403, 2404 5/1/2012 K-40 6.38 t 0.50 6.93 +/- 0.72 6.66 +/- 0.44 Pass 0 BS-2445, 2446 5/1/2012 Gr. Beta 8.92 +/- 1.52 9.29 +/- 1.63 9.11 +/- 1.11 Pass BS-2445, 2446 5/1/2012 K-40 5.86 +/- 0.38 6.22 +/- 0.48 6.04 +/- 0.31 Pass 0 SWU-2550, 2551 5/1/2012 Gr. Beta 2.07 +/- 0.65 1.59 +/- 0.62 1.83 +/- 0.45 Pass WW-2614, 2615 5/1/2012 Gr. Beta 2.03 +/- 1.04 2.36 +/- 1.14 2.20 +/- 0.77 Pass WW-2614, 2615 5/11/2012 H-3 750.60 +/- 106.20 653.20 +/- 102.30 701.90 +/- 73.73 Pass 0 BS-2656, 2657 5/2/2012 Cs-137 0.13 t 0.07 0.07 +/- 0.04 0.10 +/- 0.04 Pass 0 BS-2656, 2657 SO-2635, 2636 5/2/2012 5/3/2012 K-40 Cs-137 10.15 +/- 0.97 0.046 +/- 0.024 11.13 +/- 0.90 0.050 +/- 0.027 10.64 0.048

+/- 0.66

+/- 0.018 Pass Pass 0 SO-2635, 2636 5/3/2012 K-40 13.20 +/- 0.74 14.01 +/- 0.67 13.61 +/- 0.50 Pass 0 MI-2677, 2678 VE-2719, 2720 5/7/2012 5/7/2012 K-40 K-40 1415.30 +/- 131.40 4.15 +/- 0.36 1348.10 +/- 109.00 4.19 +/- 0.38 1381.70 4.17

+/- 85.36

+/- 0.26 Pass Pass SWU-3221, 3222 5/8/2012 Gr. Beta 1.67 +/- 0.47 1.39 +/- 0.45 1.53 +/- 0.33 Pass 0 SWU-3221, 3222 WW-3073, 3074 5/8/2012 5/14/2012 H-3 H-3 236.90 +/- 101.90 339.12 +/- 145.45 281.90 +/- 103.70 337.23 +/- 98.19 259.40 338.18

+/- 72.69

+/- 87.74 Pass Pass 0 AP-2968, 2969 5/17/2012 Be-7 0.25 +/- 0.12 0.21 +/- 0.09 0.23 +/- 0.07 Pass S F-3031, 3032 F-3031, 3032 5/22/2012 5/22/2012 H-3 K-40 11291.00 +/- 372.80 11167.00 ;k 315.00 3528.90 +/- 372.80 3677.20 +/- 392.40 11229.00 3603.05

+/- 244.03

+/- 270.63 Pass Pass G-3094, 3095 5/23/2012 Gr. Beta 7.89 +/- 0.16 8.01 +/-0.16 7.95 +/- 0.11 Pass 0 F-3412, 3413 5/23/2012 Gr. Beta 3.46 +/- 0.10 3.33 +/- 0.10 3.40 +/- 0.07 Pass F-3412, 3413 5/23/2012 K-40 2.40 t 0.38 2.55 +/- 0.43 2.48 +/- 0.29 Pass 0 MI-3067, 3068 5/24/2012 K-40 1267.20 +/- 105.00 1305.70 +/- 109.80 1286.45 +/- 75.96 Pass S SO-3305, 3306 5/30/20 12 5/30/2012 Cs-137 Gr. Beta 0.024 +/- 0.013 0.030 +/- 0.015 10.86 +/- 0.89 0.027 +/- 0.010 Pass SO-3305, 3306 10.95 +/- 0.89 10.91 +/- 0.63 Pass 0 SO-3305, 3306 5/30/2012 TI-208 0.068 +/- 0.018 0.062 +/- 0.017 0.065 +/- 0.012 Pass LW-3454, 3455 5/31/2012 Gr. Beta 2.12 +/- 0.86 2.27 +/- 0.77 2.20 +/- 0.58 Pass 0 BS-3697, 3698 6/14/2012 Be-7 2.05 +/- 0.19 2.27 +/- 0.38 2.16 +/- 0.21 Pass 6/14/2012 Cs-137 2.26 +/- 0.66 +/- 0.38 Pass 0 BS-3697, 3698 BS-3697, 3698 6/14/2012 K-40 2.32 +/- 0.39 6.67 +/- 0.28 6.64 +/- 0.42 2.29 6.66 +/- 0.25 Pass 0 VE-3798, 3799 6/20/2012 K-40 5.93 +/- 0.38 6.03 +/- 0.37 5.98 +/- 0.26 Pass WW-4790, 4791 6/20/2012 H-3 251.33 +/- 86.51 372.48 +/- 92.27 311.90 +/- 63.24 Pass 0 DW-30103, 30104 6/27/2012 Ra-226 0.30 +/- 0.08 0.42 t 0.09 0.36 +/- 0.06 Pass 0 DW-30103, 30104 612712012 Ra-228 0.76 +/- 0.54 0.78 +/- 0.54 0.77 +/- 0.38 Pass LW-3970, 3971 6/28/2012 Gr. Beta 1.49 +/- 1.06 0.72 +/- 0.53 1.11 00.59 Pass 0 DW-3949, 3950 6/29/2012 1-131 0.54 +/- 0.26 0.25 +/- 0.26 0.40 + 0.18 Pass 0 SG-4075, 4076 SG-4075, 4076 7/2/2012 7/2/2012 Ac-228 K-40 0.33 +/- 0.09 6.71 +/- 0.58 0.34 +/- 0.06 7.20 +/- 0.32 0.34 6.96

+ 0.05

+/- 0.33 Pass Pass S SG-4075, 4076 712/2012 Pb-214 0.46 +/- 0.05 0.49 +/- 0.03 0.48 +/- 0.03 Pass AP-4390, 4391 7/3/2012 Be-7 0.09 +/- 0.02 0.09 +/- 0.01 .0.09 +/- 0.01 Pass 0 AP-4390, 4391 AP-4012, 4013 7/3/2012 7/5/2012 Be-7 Be-7 0.11 +/-0.02 0.27 +/- 0.09 0.10 +/- 0.01 0.29 +/- 0.16 0.11 0.28

+/- 0.01

+/- 0.09 Pass Pass SW-4033, 4034 7/5/2012 H-3 614.99 +/- 107.99 512.31 +/- 103.83 563.65 +/- 74.91 Pass A5-2

0 0

0 TABLE A-5. In-House "Duplicate" Samples 0 Concentration (pCi/L)a Averaged 0 Lab Code Date Analysis First Result Second Result Result Acceptance 0 VE-4054, 4055 7/9/2012 K-40 7.28 +/- 0.56 7.42 +/- 0.63 7.35 +/- 0.42 Pass 0 VE-4222, 4223 7/13/2012 Be-7 0.16 +/- 0.08 0.22 +/- 0.09 0.19 +/- 0.06 Pass 0 VE-4222, 4223 DW-30113, 30114 7/13/2012 7/13/2012 K-40 Ra-228 7.20 +/- 0.30 1.93 +/- 0.66 6.60 +/- 0.30 1.03 +/- 0.53 6.90 1.48

+/- 0.21

+/- 0.42 Pass Pass DW-30115, 30116 7/13/2012 Gr. Alpha 7.46 +/- 1.21 7.02 +/- 1.14 7.24 +/- 0.83 Pass 0 DW-30124, 30125 7/13/2012 Ra-226 1.16 +/- 0.15 0.90 +/- 0.12 1.03 +/- 0.10 Pass 0 DW-30124, 30125 7/13/2012 Ra-228 1.38 +/- 0.56 1.72 +/- 0.60 1.55 +/- 0.41 Pass DW-30126, 30127 7/13/2012 Gr. Alpha 6.23 +/- 1.16 6.75 +/- 1.29 6.49 +/- 0.87 Pass 0 AP-4433, 4434 7/19/2012 Be-7 0.17 +/- 0.09 0.21 +/- 0.10 0.19 +/- 0.07 Pass S SG-4475, 4476 7/19/2012 Gr. Alpha 17.03 +/- 4.17 15.56 +/- 3.96 16.30 +/- 2.88 Pass SG-4475, 4476 7/19/2012 Gr. Beta 13.23 +/- 2.61 14.36 +/- 2.47 13.80 +/- 1.80 Pass 0 WW-4685, 4686 7/24/2012 H-3 289.00 +/- 99.00 375.00 +/- 103.00 332.00 +/- 71.43 Pass 0 AP-4706, 4707 7/2612012 Be-7 0.28 +/- 0.14 0.24 +/- 0.14 0.26 +/- 0.10 Pass SO-4748, 4749 7/26/2012 Gr. Beta 20.45 +/- 1.04 19.22 +/- 0.94 19.84 +/- 0.70 Pass SO-4748, 4749 7/26/2012 Gr. Beta 20.45 +/- 1.04 19.22 +/- 0.94 19.84 +/- 0.70 Pass 0 SO-4748, 4749 7/26/2012 U-233/4 0.11 +/-_0.02 0.10 +/- 0.01 0.11 +/- 0.01 Pass SO-4748, 4749 7/26/2012 U-238 0.12 +/- 0.02 0.11 +/- 0.01 0.12 +/- 0.01 Pass 0 VE-4832, 4833 8/1/2012 8/1/2012 K-40 4.06 +/- 0.22 4.08 +/- 0.24 4.07 +/- 0.16 Pass DW-30149, 30150 Ra-226 2.69 +/- 0.22 2.79 +/- 0.22 2.74 +/- 0.16 Pass 0 DW-30149, 30150 8/11/2012 Ra-228 2.77 +/- 0.75 1.61 +/- 0.57 2.19 +/- 0.47 Pass 0 SG-4916, 4917 SG-4916, 4917 8/3/2012 8/3/2012 Ac-228 K-40 11.03 +/- 0.33 11.08 +/- 0.44 11.06 +/- 0.28 Pass 6.39 +/- 0.80 6.98 +/- 0.88 6.69 +/- 0.59 Pass 8/9/2012 0 F-5313, 5314 F-5313, 5314 819/2012 Cs-137 Gr. Beta 0.05 +/- 0.02 4.12 +/- 0.08 0.05 +/- 0.02 4.10 +/- 0.08 0.05 4.11

+/- 0.01

+/- 0.06 Pass Pass 0 F-5313, 5314 819/2012 K-40 3.07 +/- 0.42 3.14 +/- 0.40 3.11 +/-0.29 Pass 8/15/2012 0 VE-5166, 5167 VE-5376, 5377 8/2212012 K-40 Gr. Beta 4.26 +/- 0.28 7.72 +/-_0.17 3.66 +/- 0.47 7.61 +/- 0.16 3.96 7.67

+/- 0.27

+/- 0.12 Pass Pass VE-5334, 5335 8127/2012 K-40 1.65 +/- 0.17 1.72 +/- 0.15 1.68 +/- 0.12 Pass 0 VE-5481, 5482 8/28/2012 Be-7 2.52 +/- 0.19 2.65 +/- 0.21 2.59 +/- 0.14 Pass VE-5481,5482 8/28/2012 K-40 5.05 +/- 0.37 4.79 +/- 0.39 4.92 +/- 0.27 Pass VE-5481, 5482 8/28/2012 Sr-90 0.01 +/- 0.00 0.01 +/- 0.01 0.01 +/- 0.00 Pass 0 DW-30164, 30165 8/30/2012 Ra-226 1.33 +/- 0.15 1.59 +/- 0.17 1.46 +/- 0.11 Pass 0 DW-30164, 30165 8/30/2012 Ra-228 2.76 +/- 0.66 1.54 +/- 0.56 2.15 +/- 0.43 Pass VE-5166, 5167 9/4/2012 K-40 2.05 +/- 0.32 2.53 +/- 0.36 2.29 +/- 0.24 Pass ME-5607, 5608 9/4/2012 Gr. Beta 2.92 +/- 0.08 2.89 +/- 0.08 2.90 +/- 0.06 Pass 0 ME-5607, 5608 914/2012 K-40 2.06 +/- 0.32 2.53 +/- 0.36 2.29 +/- 0.24 Pass SW-5901, 5902 9/17/2012 H-3 10909.00 +/- 311.00 10817.00 +/- 310.00 10863.00 +/- 219.56 Pass 0 BS-6048, 6049 9/24/2012 K-40 1.24 +/- 0.20 1.18 +/- 0.21 1.21 +/- 0.14 Pass AP-6482, 6483 9/27/2012 Be-7 0.09 +/- 0.02 0.09 +/- 0.03 0.09 +/- 0.02 Pass A5-3

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a 0 Averaged Lab Code Date Analysis First Result Second Result Result Acceptance 0 G-6090, 6091 10/1/2012 Be-7 3.74 +/- 0.33 3.54 +/- 0.30 3.64 +/- 0.22 Pass 0 G-6090, 6091 10/1/2012 Gr. Beta 10.81 +/- 0.34 10.72 +/- 0.33 10.77 +/- 0.24 Pass G-6090, 6091 10/1/2012 K-40 5.99 +/- 0.47 5.45 +/- 0.44 5.72 +/- 0.32 Pass SO-6111, 6112 10/1/2012 Cs-137 0.06 +/- 0.03 0.04 +/- 0.02 0.05 +/- 0.02 Pass SO-6111, 6112 10/1/2012 K-40 19.66 +/- 0.84 20.09 +/- 0.80 19.88 +/- 0.58 Pass W-6795, 6796 10/1/2012 H-3 215.20 +/- 88.00 292.80 +/- 91.60 254.00 +/- 63.51 Pass 0 AP-6461, 6462 10/2/2012 Be-7 0.07 +/- 0.01 0.07 +/- 0.02 0.07 +/- 0.01 Pass WW-6279, 6280 10/3/2012 Gr. Beta 1.54 +/- 0.68 1.67 +/- 0.75 0 W-6346, 6347 10/3/2012 Ra-226 0.30 +/- 0.10 0.36 +/- 0.10 1.61 +/- 0.51 0.33 +/- 0.07 Pass Pass 0 VE-6503, 6504 10/9/2012 K-40 5.23 +/- 0.83 6.00 +/- 0.45 5.04 +/- 0.27 Pass WW-6606, 6607 10/10/2012 Gr. Beta 3.18 +/- 1.31 2.42 +/- 1.27 2.80 +/- 0.91 Pass WW-6606, 6607 10/10/2012 H-3 273.10 +/- 85.70 219.80 +/- 83.10 246.45 +/- 59.69 Pass 0 WW-7237, 7238 10/12/2012 H-3 175.44 +/- 99.84 180.75 +/- 100.03 178.10 +/- 70.66 Pass F-6627, 6628 10/15/2012 K-40 3.05 +/- 0.39 3.23 +/- 0.37 3.14 +/- 0.27 Pass 0 VE-6669, 6670 10/16/2012 10/1612012 Be-7 0.48 +/- 0.26 0.50 +/-0.13 0.49 +/- 0.15 Pass VE-6669, 6670 K-40 4.06 +/- 0.28 3.68 +/- 0.26 3.87 +/- 0.19 Pass 0 SS-6711, 6712 10/16/2012 Ac-228 0.16 +/- 0.05 0.17 +/- 0.06 0.17 +/- 0.04 Pass 0 SS-6711, 6712 10/16/2012 Bi-214 0.13 +/- 0.03 0.16 +/- 0.03 0.14 +/- 0.02 Pass SS-6711, 6712 10/16/2012 Gr. Beta 14.20 +/- 0.89 12.67 +/- 0.88 13.44 +/- 0.63 Pass SS-6711, 6712 10/16/2012 Pb-212 +/- 0.06 0 SS-6711, 6712 10/16/2012 TI-208 0.15 0.06 +/- 0.02 0.13 0.04

+/- 0.02

+/- 0.02 0.14 +/- 0.03 0.05 +/- 0.01 Pass Pass 0 WW-7258, 7259 10/22/2012 H-3 214.69 +/- 85.42 314.60 +/- 90.25 264.65 +/- 62.13 Pass 10/25/2012 H-3 159.00 +/- 86.10 0 WW-7655, 7656 WW-7747, 7748 10/25/2012 H-3 156.50 +/- 84.70 159.00 170.20

+/- 86.10

+/- 85.30 159.00 +/- 60.88 163.35 +/- 60.10 Pass Pass 0 MI-6963, 6964 10/28/2012 K-40 1384.60 +/- 111.70 1421.60 +/- 107.60 1403.10 +/- 77.55 Pass 11/5/2012 0 MI-7174, 7175 SG-7221, 7222 11/9/2012 K-40 Pb-214 1283.60 31.49

+/- 97.45

+/- 0.70 1293.20 30.11

+/- 91.37

+/- 0.80 1288.40 +/- 66.79 30.80 +/- 0.53 Pass Pass 0 DW-30216, 30217 11/9/2012 Gr. Alpha 2.23 +/- 0.86 2.31 +/- 0.92 2.27 +/- 0.63 Pass DW-30216, 30217 11/9/2012 Ra-226 0.72 +/- 0.12 0.82 +/- 0.14 0.77 +/- 0.09 Pass DW-30216, 30217 11/9/2012 Ra-228 0.92 +/- 0.52 1.26 +/- 0.53 1.09 +/- 0.37 Pass 0 MI-7363, 7364 11/13/2012 K-40 1304.40 +/- 103.30 1496.10 +/- 121.30 1400.25 +/- 79.66 Pass CF-7384, 7385 11/13/2012 K-40 11.75 +/- 0.52 10.94 +/- 0.59 11.35 +/- 0.39 Pass S VE-7489, 7490 11/16/2012 K-40 2.22 +/- 0.23 1.91 +/- 0.22 2.06 +/- 0.16 Pass AP-7531, 7532 11/21/2012 Be-7 0.19 +/- 0.10 0.29 +/- 0.17 0.24 +/- 0.10 Pass 0 BS-7573, 7574 11/24/2012 K-40 7.21 +/- 0.41 7.57 +/- 0.39 7.39 +/- 0.28 Pass LW-7865, 7866 12/512012 Gr. Beta 2.16 +/- 0.56 1.64 +/- 0.62 1.90 +/- 0.42 Pass 0 SG-8095, 8096 12/19/2012 Ac-228 25.15 +/- 0.73 25.47 +/- 0.54 25.31 +/- 0.45 Pass 0 SG-8095, 8096 12/19/2012 Gamma 26.98 +/- 2.72 28.68 +/- 2.89 27.83 +/- 1.98 Pass 0

Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.

a Results are reported in units of pCi/L, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCi/g).

A5-4

S 0

0 0

0 TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).

0 0 Concentration a Known Control 0 Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance 0 STW-1670 02/01/12 1-129 9.31 +/- 0.31 12.29 8.60 - 15.98 Pass 0

STSO-1766d 02/01/12 Am-241 88.50 +/- 8.30 159.00 111.00 - 207.00 Fail 0 STSO-1766 02/01/12 Co-57 1352.10 +/- 4.00 1179.00 825.00 - 1533.00 Pass 0 STSO-1766 STSO-1 766 02/01/12 02/01/12 Co-60 Cs-134 1.70 842.20

+/- 0.70

+/- 4.30 1.56 828.00 1.00 580.00

- 2.00

- 1076.00 Pass Pass 0 STSO-1766 02/01/12 Cs-1 37 0.40 +/- 0.90 0.00 0.00 - 1O00 Pass STSO-1766 02/01/12 K-40 1729.60 +/- 22.20 1491.00 1044.00 - 1938.00 Pass 0 STSO-1766 02/01/12 Mn-54 647.60 +/- 4.20 558.00 391.00 - 725.00 Pass STSO-1766 02/01/12 Ni-63 781.50 +/- 9.70 862.00 603.00 - 1121.00 Pass 0 STSO-1766 STSO-1766 02/01/12 02/01/12 Pu-238 Pu-239/40 142.40 66.10

+/- 9.70

+/- 6.40 136.00 65.80 97.00 46.10

- 177.00

- 85.50 Pass Pass 0 STSO-1766 02/01/12 Sr-90 383.20 +/- 15.30 392.00 274.00 - 510.00 Pass STSO-1766 02/01/12 Tc-99 289.60 +/- 10.90 374.00 262.00 - 486.00 Pass 0 STSO-1766 02/01/12 U-233/4 63.20 +/- 5.40 68.10 47.70 - 88.50 Pass 0 STSO-1 766 STSO-1 766 02/01/12 02/01/12 U-238 Zn-65 310.80 766.70

+/- 12.10

+/- 6.70 329.00 642.00 230.00 449.00

- 428.00

- 835.00 Pass Pass 0 STAP-1772 02/01/12 Am-241 0.062 +/- 0.02 0.073 0.051 - 0.10 Pass STAP-1772 02/01/12 Co-57 0.010 +/- 0.01 0.00 0.000-1.00 Pass 0 STAP-1772 02/01/12 Co-60 2.40 +/- 0.08 2.18 1.53 - 2.84 Pass STAP-1772 02/01/12 Cs-134 2.33 +/- 0.13 2.38 1.67 - 3.09 Pass STAP-1772 02/01/12 Cs-137 2.07 +/- 0.10 1.79 1.25 -2.33 Pass 0 STAP-1772 02/01/12 Mn-54 3.77 +/- 0.14 3.24 2.27 -4.21 Pass STAP-1772 02/01/12 Pu-238 0.003 +/- 0.004 0.002 0.000 -0.10 Pass 0 STAP-1772 02/01/12 Pu-239/40 0.098 +/- 0.017 0.097 0.07 - 0.13 Pass STAP-1772 02/01/12 Sr-90 -0.010 +/- 0.060 0.000 -0.10 -0.13 Pass STAP-1772" 02/01/12 U-233/4 0.016 +/- 0.006 0.019 0.013 - 0.024 Pass STAP-1772 02/01/12 U-238 0.11 +/- 0.02 0.12 0.09 -0.16 Pass STAP-1772 02/01/12 Zn-65 3.67 +/- 0.20 2.99 2.09 -3.89 Pass STAP-1773 02/01/12 Gr. Alpha 0.51 +/- 0.05 1.20 0.40 - 2.00 Pass STAP-1773 02/01/12 Gr. Beta 2.75 +/- 0.10 2.40 1.20 - 3.60 Pass 0

0 STVE-1776 STVE-1776 02/01/12 02/01/12 Co-57 Co-60 14.57 6.45

+/- 0.28

+/- 0.23 12.00 6.05 8.40 4.24 15.60 7.87 Pass Pass 0 STVE-1 776 02101/12 02/01/12 Cs-134 8.39 0.01

+/- 0.29

+/- 0.09 8.43 5.90 - 10.96 Pass Pass STVE-1 776 Cs-137 0.00 0.00 -0.10 0 STVE-1776 02/01/12 Mn-54 0.03 +/- 0.08 0.00 0.00 -0.10 Pass 0 STVE-1 776 02/01/12 Zn-65 10.31 +/- 0.67 8.90 6.23 - 11.57 Pass 0 STW-1960 STW-1960 02/01/12 02/01/12 Gr. Alpha Gr. Beta 1.68 +/- 0.09 6.33 +/- 0.10 2.14 6.36 0.64 - 3.64 3.18 -9.54 Pass Pass 0

0 0

0 A6-1 0

0 0

0 0 TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).

0 Concentration "

Known Control 0 Lab Code b Date Analysis Laboratory result Activity Limits ' Acceptance 0 STW- 1964 STW-1964 02/01/12 02/01112 Am-241 Co-57 1.28 33.30

+/- 0.12

+/- 0.40 1.63 32.90 1.14 -2.12 Pass 23.00 - 42.80 Pass STW-1964 02/01/12 Co-60 23.20 +/- 0.40 23.72 16.60 - 30.84 Pass 0 STW-1964 02/01/12 Cs-134 0.30 +/- 3.00 0.00 0.00 - 1.00 Pass STW-1964 02/01/12 Cs-1 37 40.10 +/- 0.60 39.90 27.90 - 51.90 Pass 0 STW-1964 t STW-1 964 02/01/12 02/01/12 Fe-55 H-3 65.10 +/- 9.50

+/- 12.10 81.90 57.30 - 106.50 Pass 460.00 437.00 306.00 - 568.00 Pass STW-1 964 02/01/12 K-40 153.00 +/- 4.20 142.00 99.00 - 185.00 Pass 0 STW-1 964 02/01/12 Mn-54 32.70 +/- 0.60 31.80 22.30 - 41.30 Pass 0 STW-1964 STW-1964 02/01/12 02/01/12 Ni-63 Pu-238 49.80 0.58

+/- 2.90

+/- 0.06 60.00 0.63 42.00 - 78.00 0.44 - 0.82 Pass Pass 0 STW-1964 02/01/12 Pu-239/40 1.30 +/- 0.15 1.34 0.94-1.74 Pass STW-1964 02/01/12 Sr-90 0.10 +/- 0.20 0.00 0.00 - 1.00 Pass 0 STW-1964 02/01/12 Tc-99 23.70 +/- 0.80 27.90 19.50 - 36.30 Pass 0 STW-1 964 STW-1964 02/01/12 02/01/12 U-233/4 U-238 0.40 2.67

+/- 0.05

+/- 0.13 0.39 2.76 0.27 - 0.51 1.93 - 3.59 Pass Pass STW-1964 02/01/12 Zn-65 0.01 +/- 0.20 0.00 0.00 -1.00 Pass 0

0 STW-5391 08/01/12 1-129 5.73 +/- 0.28 6.82 4.77 - 8.87 Pass 0 STSO-5392 08/01/12 Am-241 129.30 +/- 12.70 111.00 78.00 - 144.00 Pass STSO-5392 08/01/12 Ni-63 376.20 +/- 20.60 406.00 284.00 - 528.00 Pass 0 STSO-5392 08/01/12 Pu-238 118.70 +/- 9.30 105.80 74.10 - 137.50 Pass STSO-5392 08/01/12 Pu-239/40 140.70 +/- 9.90 134.00 94.00 - 174.00 Pass S STSO-5392 STSO-5392 08/01/12 08/01/12 Sr-90 Tc-99 483.52 432.50

+/- 16.47

+/- 23.10 508.00 469.00 356.00 328.00

- 660.00

-610.00 Pass Pass 0 STSO-5394 08/01/12 Co-57 1528.00 +/- 4.10 1316.00 921.00 -1711.00 Pass STSO-5394 08/01/12 Co-60 592.00 +/- 3.20 531.00 372.00 - 690.00 Pass 0 STSO-5394 08/01/12 Cs- 134 933.60 +/- 5.82 939.00 657.00 - 1221.00 Pass STSO-5394 08/01/12 Cs-137 1319.80 +/- 5.50 1150.00 805.00 - 1495.00 Pass 0 STSO-5394 STSO-5394 08101/12 08101/12 K-40 Mn-54 737.30 1083.20

+/- 17.70

+/- 5.20 632.00 920.00 442.00 644.00

-822.00

- 1196.00 Pass Pass STSO-5394 08/01/12 U-233/4 55.80 +/- 4;20 60.30 42.20 - 78.40 Pass STSO-5394 08/01/12 U-238 231.20 +/- 8.60 263.00 184.00 - 342.00 Pass STSO-5394 696.10 +/- 7.00 0 08/01/12 Zn-65 606.00 424.00 - 788.00 Pass 0

0 0

S A6-2

0 0

S TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).

Concentration a 0 Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance 0

STVE-5395 g 08/01/12 Co-57 7.44 +/- 0.17 5.66 3.96 - 7.36 Fail 5.90 +/- 0.15 5.12 3.58 6.66 Pass 0 STVE-5395 STVE-5395 08/01/12 08/01/12 Co-60 Cs-134 7.40 +/- 0.31 6.51 4.56

- 8.46 Pass STVE-5395 08/01/12 Cs-137 5.45 +/- 0.18 4.38 3.07 - 5.69 Pass STVE-5395 08/01/12 Mn-54 4.06 +/- 0.21 3.27 2.29 - 4.25 Pass 0

0 STAP-5398 08/01/12 Gr. Alpha 0.41 +/- 0.05 0.97 0.29 - 1.65 Pass 0 STAP-5398 08/01/12 Gr. Beta 2.11 +/- 0.09 1.92 0.96 -2.88 Pass 0 STAP-5401 STAP-5403

' 08/01/12 08/01/12 Am-241 Co-57 0.12 1.96

+/- 0.02

+/- 0.05 0.08 1.91 0.05 1.34

-0.10

-2.48 Fail Pass S STAP-5403 08/01/12 Co-60 1.76 +/- 0.07 1.73 1.21 -2.25 Pass STAP-5403 08/01/12 Cs-134 2.74 +/- 0.18 2.74 1.92 -3.56 Pass 0 STAP-5403 STAP-5403 08/01/12 08/01/12 Cs-137 Mn-54 0.00 2.52

+/- 0.03

+/- 0.10 0.00 2.36

-0.01 1.65

- 0.01

-3.07 Pass Pass STAP-5403 08/01/12 Pu-238 0.050 +/- 0.015 0.063 0.044 - 0.081 Pass 0 STAP-5403 STAP-5403' 08/01/12 08/01/12 Pu-239/40 U-233/4 0.001 0.009

+/- 0.004

+/- 0.011 0.00081 0.014 0.000 0.010

- 0.010

- 0.018 Pass Fail STAP-5403 08/01/12 U-238 0.08 +/- 0.02 0.10 0.070 - 0.130 Pass 0 STAP-5403 08/01/12 Zn-65 0.01 +/- 0.06 0.00 -0.010 - 0.010 Pass 0

0 STW-5445 08/01/12 Fe-55 79.80 +/- 4.10 89.30 62.50 - 116.10 Pass STW-5445 08/01/12 Ni-63 74.30 +/- 3.40 66.30 46.40 - 86.20 Pass 0 STW-5445 STW-5445 08/01/12 08/01/12 U-233/4 U-238 0.46 3.14

+/- 0.05

+/- 0.14 0.45 3.33 0.32 - 0.59 2.33 - 4.33 Pass Pass 0 STW-54451 08/01/12 Am-241 0.64 +/- 0.04 1.06 0.74-1.38 Fail 0 a Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

S b Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).

0 MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits.

0 d Investigation was inconclusive, there was not enough sample for reanalysis. ERA results (A-7) for the same matrix were acceptable.

e No errors found in calculation or procedure, odginal analysis result; 0.010 +/- 0.010 Bq/filter.

0 f Reanalysis results were within limits, but low. ERA results (A-7) for the same matrix were acceptable.

The efficiency factor was recalculated for the second round of MAPEP testing. Original analysis results 55.8 +/- 12.6 Bq/L.

9 Result of reanalysis; 6.74 +/- 0.15 Bq/sample. Gamma emitters for the vegetation matrix exhibited a high bias, only 0 Co-57 exceeded acceptance limits. Recounted using a geometry more closely matched to the MAPEP sample size.

0 h Result of reanalysis; 0.070 : 0.013 Bq/filter.

Result of reanalysis; 0.013 +/-10.005 pCi/filter. A larger sample size was used to reduce the counting error.

J Result of reanalysis 1.07 +/- 0.06 pCi/L. The analyses of the MAPEP sample matrix resulted in recovery factors greater than 100%.

A correction was made using recovery based on analysis of blank samples. A new tracer solution is on order, future samples for MAPEP testing will include batch spike and blank samples.

A6-3

TABLE A-7. Interlaboratory Comparison Crbsscheck program, Environmental Resource Associates (ERA)a.

Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERAP-1393 03/19/12 Co-60 917.5 +/- 7.0 880.0 681.0 -1100.0 Pass ERAP-1393 03/19/12 Cs-1 34 586.6 +/- 7.4 656.0 417.0 -814.0 Pass ERAP-1393 03/19/12 Cs-1 37 1255.9 +/- 9.4 1130.0 849.0 - 1480.0 Pass ERAP-1393 03/19/12 Mn-54 < 3.4 0.0 Pass ERAP-1393 03/19/12 Zn-65 1085.2 +/- 18.0 897.0 642.0 - 1240.0 Pass ERAP-1394 03/19/12 Am-241 86.9 +/- 2.9 68.8 42.4 - 93.1 Pass ERAP-1394 03/19/12 Pu-238 70.2 +/- 3.6 63.2 43.3 - 83.1 Pass ERAP-1394 03/19/12 Pu-239/40 66.0 +/- 1.0 63.0 45.6 - 82.4 Pass ERAP-1394 03/19/12 Sr-90 112.5 +/- 15.4 89.6 43.8 -134.0 Pass ERAP-1394 03/19/12 U-233/4 43.4 +/- 0.8 47.5 29.4 -71.6 Pass ERAP-1394 03/19/12 U-238 44.0 +/- 1.2 47.1 30.4 -65.1 Pass ERAP-1394 03/19/12 Uranium 89.1 +/- 2.2 96.7 53.5-147.0 Pass ERAP-1396 03/19112 Gr. Alpha 81.1 +/- 1.5 77.8 26.1 -121.0 Pass ERAP-1396 03/19/12 Gr. Beta 68.4 +/- 0.7 52.5 33.2 -76.5 Pass 0 ERSO-1397 03/19/12 Ac-228 1303.4 0 ERSO-1397 03/19/12 Am-241 856.0

+/- 89.3

+/- 123.7 1570.0 938.0 1010.0 -2180.0 549.0 - 1220.0 Pass Pass S ERSO-1397 03/19/12 Bi-212 1379.2 +/- 247.2 1550.0 413.0 - 2280.0 Pass ERSO-1397 03/19/12 Bi-214 965.2 +/- 38.4 1100.0 665.0 - 1590.0 Pass 0 ERSO-1397 03/19/12 Co-60 3693.6 +/- 32.1 3500.0 2370.0 - 4820.0 Pass ERSO-1397 03/19/12 Cs-134 2257.3 +/- 45.4 2180.0 1420.0 -2620.0 Pass S ERSO-11397 03/19/12 Cs-137 9444.5 +/- 58.4 8770.0 6720.0 -11300.0 Pass ERSO-1397 03/19/12 K-40 11277.0 +/- 275.1 11600.0 S ERSO-1397 03/19/12 Mn-54 < 21.0 0.0 8470.0 - 15600.0 Pass Pass 0 ERSO-1397 03/19/12 Pb-212 1208.4 +/- 26.3 1510.0 992.0 -2110.0 Pass ERSO-1397 03/19/12 Pb-214 1041.6 +/- 46.9 1110.0 647.0 - 1650.0 Pass 0 ERSO-1397 03/19/12 Pu-238 921.0 +/- 112.6 984.0 592.0 - 1360.0 Pass ERSO-1397 03/19/12 Pu-239/40 1028.0 +/- 112.6 879.0 575.0 - 1210.0 Pass 0 ERSO-1397 03/19/12 Sr-90 8128.0 +/- 329.0 8800.0 3360.0 - 13900.0 Pass ERSO-1397 03/19/12 Th-234 2711.3 +/- 253.6 2000.0 632.0 - 3760.0 Pass 0 ERSO-1397 03/19/12 U-233/4 1859.3 +/- 126.6 1960.0 1200.0 -2510.0 Pass ERSO-1397 03/19/12 U-238 2003.3 +/- 130.3 2000.0 1240.0 -2540.0 Pass 0 ERSO-1397 03/19/12 Uranium 3939.5 +/- 283.8 4030.0 2190.0 -5320.0 Pass ERSO-1397 03/19/12 Zn-65 4200.4 +/- 65.9 3650.0 2910.0 -4850.0 Pass 0

0 0

A7-1

TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.

0 Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result a Limits Acceptance 0 ERVE-1400 03/19/12 Am-241 4194.8 +/- 199.5 4540.0 2780.0 - 6040.0 Pass 0 ERVE-1400 03/19/12 Cm-244 1471.2 +/- 113.1 1590.0 779.0 - 2480.0 Pass ERVE-1400 03/19/12 Co-60 2347.8 +/- 47.9 2210.0 1520.0 - 3090.0 Pass ERVE-1400 03/19/12 Cs-134 2847.5 +/- 64.0 2920.0 1880.0 - 3790.0 Pass 0 ERVE-1400 ERVE-1400 03/19/12 03/19/12 Cs-137 K-40 1503.5 34105.7

+/- 52.5

+/- 745.3 1340.0 28600.0 972.0 20700.0

- 1860.0

- 40100.0 Pass Pass S ERVE-1400 03/19/12 Mn-54 < 26.8 0.0 Pass ERVE-1400 03/19/12 Pu-238 2509.0 +/- 213.6 2350.0 1400.0 - 3220.0 Pass S ERVE-1400 ERVE-1400 03/19/12 03/19/12 Pu-239/40 Sr-90 2690.4 7881.5

+/- 208.9

+/- 470.8 2570.0 8520.0 1580.0 - 3540.0 4860.0 - 11300.0 Pass Pass ERVE-1400 03/19/12 U-233/4 3149.6 +/- 165.2 3610.0 2370.0 - 4640.0 Pass S ERVE-1400 ERVE-1400 03119/12 03/19/12 U-238 Uranium 3203.6 6463.7

+/- 166.5

+/- 363.2 3580.0 7350.0 2390.0 - 4550.0 4980.0 - 9150.0 Pass Pass S ERVE-1400 03/19/12 Zn-65 2701.9 +/- 105.5 2310.0 1670.0 - 3240.0 Pass 0

0 ERW-1403 03/19/12 Am-241 119.9 +/-3.2 135.0 91.0-181.0 Pass ERW-1403 03/19/12 Fe-55 713.7 +/- 127.4 863.0 514.0 - 1170.0 Pass 0 ERW-1403 03/19/12 Pu-238 131.9 +/- 6.4 135.0 99.9 - 168.0 Pass ERW-1403 03/19/12 Pu-239/40 108.9 +/- 10.2 112.0 86.9-141.0 Pass 0 ERW-1403 03/19/12 U-233/4 93.1 +/- 7.9 105.0 78.9 - 135.0 Pass ERW-1403 03/19/12 U-238 96.9 +/- 5.5 104.0 79.3 128.0 Pass S. ERW-1403 03/19/12 Uranium 190.0 +/- 13.8 214.0 157.0 - 277.0 Pass 0 ERW-1405 ERW-1405 03/19/12 03/19/12 Co-60 Cs-134 858.7 560.4

+/- 5.6

+/- 4.4 875.0 609.0 760.0 - 1020.0 447.0 - 700.0 Pass Pass 0 ERW-1405 03/19/12 Cs-137 1239.9 +/- 7.4 1250.0 1060.0 - 1500.0 Pass ERW-1405 03/19/12 Mn-54 < 7.4 0.0 Pass ERW-1405 03/19/12 Sr-90 944.3 +/- 26.2 989.0 644.0 - 1310.0 Pass ERW-1405 03/19/12 Zn-65 786.9 +/- 20.6 749.0 624.0 - 945.0 Pass ERW-1406 03/19/12 Gr. Alpha 85.9 +/- 3.0 103.0 36.6 - 160.0 Pass 0 ERW-1406 03/19/12 Gr. Beta 45.7 +/- 1.6 43.7 25.0 - 64.7 Pass 0 ERW-1409 03/19/12 H-3 9045.0 +/- 284.0 9150.0 6130.0 - 13000.0 Pass 0

0 Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency 0 8 testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

0 Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation). Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCi/kg).

c Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.

d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". Control limits are not provided.

A7-2

0 0

0 0 APPENDIX B 0

0 DATA REPORTING CONVENTIONS 0

0 0

0 B-1 0

S 0

Data Reporting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end

of the collection period.

0** 2.0. Single Measurements Each single measurement is reported as follows: x+/- s where: x = value of the measurement;

s = 2s counting uncertainty (corresponding to the 95% confidence level).

In cases where the activity is less than the lower limit of detection L, it is reported as: <L, where L = the lower limit of detection based on 4.66s uncertainty for a background sample.

0 3.0. Duplicate analyses 3.1 Individual results: For two analysis results; xi +/- sl and x2 +/- s2

Reported 0A result: x +/- s; where x = (1/2) (xi + x2) and s = (1/2) '/sI + s2 3.2. Individual results: <L1, <L2 Reported result: <L, where L = lower of Li and L2 S 3.3. Individual results: x +/- s, <L Reported result: x +/- s if x > L; <L otherwise.

4.0. Computation of Averages and Standard Deviations S

4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not 0* be the average-of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x1 , x2 ... xn are defined as follows:

= nx x s= n-

4.2 Values below the highest lower limit of detection are not included in the average.

4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.

4.4 If all but one of the values are less than the highest LLD, the single value x and associated two 5sigma error is reported.

4.5 In rounding off, the following rules are followed:

0 4.5.1. If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an example, 11.443 is rounded off to 11.44.

4.5.2. If the figure following those to be retained is equal to or greater than 5, the figure is dropped and the last retained figure is raised by 1. As an example, 11.445 is rounded off to 11.45.

4.6 Composite samples which overlap the next month or year are reported for the month or year in

which most of the sample is collected.

0 S

B -2 0

0 0

0 0 APPENDIX C 0

0 TECHNICAL SPECIFICATION 2.1.3 0

0 REACTOR COOLANT DOSE EQUIVALENT IODINE ABOVE TECHNICAL SPECIFICATION LIMIT 0

0 0

0 0 C-1 0

0 0

During the 2012 reporting period, radioactivity of primary coolant did not exceed the limits of Technical Specification 2.1.3.

0 0

S S

0 0

0 S

0 0

0 c-2 0

0 0

0 APPENDIX D 0

0 SAMPLE LOCATIONS/MAP 0

0 0

0 0 D-1 0

0

0 0

0 0 E 0

0 0

0 0 D-2 0

Radiological Environmental Sampling Locations And Media Approximate Approximate Air Monitoring Approximate Distance from Direction Vegetables Aoximate Center of direction Sector TLD Water Milk Sediment Fish and Food Ground-water Collection Sites (degrees from Containment true north) Airborne Airborne Products (miles) truenorth) Particulate Iodine Onsite Station, 110-meter weather tower 0.53 293 0/WNW P X Onsite Station, adjacent to old plant access road 0.59 207 0/SSW K X X X Offsite Station, Intersection of Hwy. 75 and farm access road 0.94 145 0/SE G X Blair OPPD office 2.86 3050/NW Q X X X Fort Calhoun, NE City Hall 5.18 150 0/SSE H X Fence around intake gate, Desoto Wildlife Refuge 2.07 102 0/ESE F X Onsite Station, entrance to Plant Site from Hwy.

75 0.55 1910/S J X Onsite Station, NW of Plant 0.68 3050/NW Q X Onsite Station, WSW of Plant 0.61 242 0/WSW M X D-3

Radiological Environmental Sampling Locations And Media Approximate Approximate Air Monitoring Approximate Distance from Direction Vegetables Aoximate Center of Sector TLD Water Milk Sediment Fish and Food Ground-water Collection Sites Cneof (degrees from Containment true north) Airborne Airborne Products (miles) Particulate Iodine Offsite Station, SE of Plant 1.07 390/SE G X Metropolitan Utilities Dist.,

Florence Treatment Plant North Omaha, NE 14.3 154 0/SSE H X West bank Missouri River, downstream from Plant discharge 0.45 108 0/ESE F X X Upstream from Intake Bldg.,

west bank of river 0.09 40/N A X X 0

Smith Farm 1.99 134 /SE G X Mohr Dairy 9.86 1860/S J X X Fish Sampling Area, Missouri 0.08 River (R.M. 645.0) 60/N A X Fish Sampling Area, Missouri 17.9 River (R.M. 666.0) 358 0 /N A X Alvin Pechnik Farm 0.94 163 0/SSE H X Valley Substation #902 19.6 221 0 /SW L X X X D-4

Radiological Environmental Sampling Locations And Media Approximate Approximate Air Monitoring Approximate Distance from Vegetables Aoximate Center of Direction Sector TLD Water Milk Sediment Fish and Food Ground-water Collection Sites (degrees from Containment true north) Airborne Airborne Products (miles) Particulate Iodine Bansen Farm 0.65 203 0/SSW K X 0

Herber Acreage 0.65 163 /SSE H X X X X Onsite Farm Field 0.52 118 0/ESE F X Offsite Station Intersection Hwy 75/Co. Rd.

P37 0.75 2270 /SW L X Offsite Station Desoto Township 1.57 144 0/SE G X X X Dowler Acreage 0.73 175 0/S J X X X 0

Sector A-1 1.94 °/NORTH A X 0

Sector B- 1 1.97 16 /NNE B X Sector C-1 1.56 41°/NE C X 0

Sector D-1 1.34 71 /ENE D X Sector E- 1 1.54 90 0/EAST E X 0

Sector F-i 0.45 108 /ESE F X 0

Sector G-1 1.99 134 /SE G X 0

Sector H-1 1.04 159 /SSE H X 0

Sector J-1 0.71 179 /SOUTH J X 0

Sector K-1 0.61 205 /SSW K X Sector L-1 0.74 229 0/SW L X 0

Sector M-1 0.93 248 /WSW M X 0

Sector N-1 1.31 266 /WEST N X D-5

Radiological Environmental Sampling Locations And Media Approximate Approximate Air Monitoring Approximate Distance from Vegetables oi te Center of Direction Sector TLD Water Milk Sediment Fish and Food Ground-water Collection Sites Cneof (degrees from Containment true north) Airborne Airborne Products (miles) truenorth) Particulate Iodine Sector P-1 0.60 291 0/WNW P X Sector Q-1 0.67 307 0/NW Q X 0

Sector R-1 2.32 328 /NNW R X 0

Sector A-2 4.54 350 /NORTH A X 0

Sector B-2 2.95 26 /NNE B X 0

Sector C-2 3.32 50 /NE C X Sector D-2 3.11 75 0/ENE D X 0

Sector E-2 2.51 90 /EAST E X Sector F-2 2.91 110°/ESE F X 0

Sector G-2 3.00 140 /SE G X 0

Sector H-2 2.58 154 /SSE H X 0

Sector J-2 3.53 181 /SOUTH J X Sector K-2 2.52 205 0/SSW K X 0

Sector L-2 2.77 214 /SW L X 0

Sector M-2 2.86 243 /WSW M X 0

Sector N-2 2.54 263 /WEST N X 0

Sector P-2 2.99 299 /WNW P X 0

Sector Q-2 3.37 311 /NW Q X Sector R-2 3.81 328 0/NNW R X D-6

Omaha Public Power District Fort Calhoun Station Unit No. 1 Annual Report For Technical Specification Section 5.9.4.a January 1, 2012 to December 31, 2012 DOCKET NO. 50-285 OPERATING LICENSE DPR-40

0 S

0 0

S 0

0 0

0 Omaha Public Power District 0 Fort Calhoun Station Unit No. 1 0

0 Annual Report For 0 Technical Specifications, Section 5.9.4.a 0

January 1, 2012 to December 31, 2012 0

0 0

0

0 0

0 DOCKET NO. 50-285 OPERATING LICENSE DPR-40

Annual Radiological Effluent Release Report 0

This report is submitted in accordance with Section 5.9.4.a of the

Technical Specifications of Fort Calhoun Station Unit No. 1, Facility

Operating License DPR-40 for the period January 1, 2012 through

December 31, 2012. The Effluent Report is presented in the format 0 outlined in Regulatory Guide 1.21, Revision 2.

In addition, this report provides the results of quarterly dose calculations

performed in accordance with the Offsite Dose Calculation Manual.

Results are presented by quarter for the period January 1, 2012 through

December 31, 2012.

0

Descriptions of any changes made during the preceding twelve months to

the Offsite Dose Calculation Manual and/or the Process Control Program

for the Fort Calhoun Station are presented.

0 0

0 0Q PRO RC OM.)

APRCF~r6"'MA1NDS

~APP'RovAL*

APR 1 0 2013 SPIRO MTM. MINUTEs Division Manager Nuclear Operations/Plant Manage 0

0 0

0

S 0

0 0

TABLE OF CONTENTS 0

Section Section Title I. 1.0 Introduction 1.1 Executive Summary 2.0 Supplemental Information 2.1 Regulatory Limits 2.2 Effluent Concentration Limits 2.3 Measurements and Approximations of Total

Radioactivity 2.4 Estimation of Total Percent Error

2.5 Batch Releases 0 2.6 Abnormal Releases 3.0 Gaseous Effluents 4.0 Liquid Effluents 5.0 Solid Wastes 0

6.0 Related Information 6.1 Operability of Liquid and Gaseous Monitoring

Instrumentation 6.2 Changes to Offsite Dose Calculation Manual (ODCM) or Process Control Program (PCP) 6.3 New Locations or Modifications for Dose

Calculations or Environmental Monitoring 6.4 Noncompliance with Radiological Effluent Control

Requirements 6.5 Modifications to Liquid and Gaseous Waste Treatment and Ventilation Exhaust Systems

6.6 Meteorological Monitoring Program 6.7 Assessment of Doses 6.8 Groundwater Monitoring Program and Observations 0

II. Quarterly Doses from Effluents, Offsite Dose Calculation Manual 0

0 0

0 TABLE OF CONTENTS Ill. Radiological Effluent Releases, Technical Specification 0 (5.9.4.a) 0 111.1; Abnormal Table 111.2; Batch Liquid and Liquid Gas Release T

Table Batch Summary and Gaseous Release Summary Table 111.3; Gaseous Effluents - Summation of All Releases Table 111.4; Gaseous Effluent Releases - Batch Mode 0 Table 111.5; Gaseous Effluent Releases - Continuous Mode Table 111.6; Liquid Effluents - Summation of All Releases Table 111.7; Liquid Effluent Releases - Batch Mode Table 111.8; Liquid Effluent Releases - Continuous Mode Table 111.9; Groundwater Analysis Results IV. Dose From Gaseous Effluents - GASPAR II Output Tables IV-A-1 through IV-A Receptor Dose Projections Table IV-B Dose Contributions at Unrestricted Area Boundary Table IV-C ALARA Annual Integrated Dose Summary V. Dose From Liquid Effluents - LADTAP II Output 0

Summary Dose Projections from Liquid Effluent Releases VI. Radioactive Effluent Releases-Solid Radioactive Waste, Technical Specification (5.9.4.a) 0 VII. ATTACHMENTS

1. Off-Site Dose Calculation Manual (ODCM) and Process 5 Control Program (RW-AD-300) Revisions S 0

2. Joint Frequency Distribution Wind Direction vs. Wind Speed by Stability Class and Meteorological Data 00 S

S S

0 S

0 0

S

0 0

1.0 INTRODUCTION

This Annual Radiological Effluent Release Report, for Fort Calhoun

Station Unit No. 1, is submitted as required by Technical Specification

5.9.4.a for the period January 1, 2012 through December 31, 2012.

O 1.1 Executive Summary 0

The Radioactive Effluent Monitoring program for the year 2012 was

conducted as described in the following report. Major efforts were made to maintain the release of radioactive effluents to the

environment as low as reasonably achievable. The station was

offline the entire year while performing NRC Chapter 0350

inspection.

The total airborne activity released from noble gas was 0.00 curies.

This was a decrease from the 2011 activity of 0.823 curies. This

decrease is attributed to the station being off line the entire year.

The total airborne activity from 1-131, 1-133, and particulates with

half-lives > 8 days in 2012 was 0.00 curies. This was a decrease

from the 2011 activity of 1.09E-5 curies. This decrease is

attributed to the station being off line the entire year. Additionally last year's curie total contained activity associated with worldwide release from Dai-lchi plant, Fukushima Japan.

' The total airborne activity from Tritium was 1.314 curies. This was

a decrease from the 2011 activity of 4.79 curies. This decrease is attributed to the station being off line the entire year.

The total airborne activity from C-14 was 0.00 curies. This was a

decrease from the 2011 activity of 0.68 curies. This decrease is attributed to the station being off line the entire year. Airborne activity from C-14 is included in the 2012 annual report, per

Regulatory Guide 1.21, Revision 2. This is a calculated value

based on power generation and days of operation. Critical organ

doses from C-14 were calculated using a ratio of 15% as CO 2 . This ratio was determined during an NRC in-plant source term study

conducted at the Fort Calhoun Station between 1976 and 1977,

NUREG/CR-0140.

0 Dose contributions from airborne effluents at the unrestricted area boundary were; 0.00 mRad gamma air dose, 0.00 mRad beta air

dose, 3.16E-03 mRem total body dose, and 3.16E-03 mRem

critical organ dose. Gamma and beta dose showed a decrease from 2011 levels of 9.72-04 mRad gamma air dose and 1.53E-03 0

0 -

0 0

0 mRad beta air dose. This decrease is attributed to the station being off line the entire year. Whole body and critical organ doses decreased from 2011 levels of 2.94E-01 mRem total body dose 0 and 1.26E+00 mRem critical organ dose. This decrease is 0 attributed to the station being off line the entire year, with airborne tritium being the only airborne activity being released.

Total water activity (excluding tritium, dissolved gases, and alpha) 0 released in 2012 in liquid effluents was 1.08E-03 curies. This was a decrease from the 2011 activity of 1.97E-03 curies.

The total water tritium activity released in 2012 in liquid effluents was 2.94 curies. This was a decrease from the 2011 activity of 83.2 0 curies. This decrease is attributed to the station being off line the

entire year, and draining the reactor cavity to repair an existing liner to containment sump leak. The combination of decreased volume released (-30% reduction) and lower source term led to this improvement. 0 0

The calculated whole body dose due to liquid effluents at the site discharge from all sources in 2012 was 2.OOE-01 mRem. This was an increase from the 2011 dose of 2.64E-02 mRem. This increase is attributed to the station circulating water pumps being secured 0 for nearly the entire year, lowering dilution flow.

The calculated critical organ dose due to liquid effluents at the site discharge from all sources in 2012 was 2.98E-01 mRem. This was 0 an increase from the 2011 dose of 4.79E-02 mRem. This increase is attributed to the station circulating water pumps being secured for nearly the entire year, lowering dilution flow.

The Fort Calhoun Station meteorological system had a cumulative 0 recovery rate of 80.84% from the station meteorological tower with the remaining 19.16% provided by the National Weather Service, for the joint frequency parameters required by Regulatory Guide 1.23 for wind speed, wind direction, and delta temperature. The 0 low recovery rate was due to the loss of the onsite tower from flood 5 damage. The tower was repaired on March 8, 2012.

There were no abnormal releases during 2012. 0 0

During 2012 there were was no changes to the Offsite Dose Calculations Manual (ODCM) and one change to the Process Control Program (PCP).

0 For 2012, the total volume of solid radwaste released from the unit was 295.3 cubic meters. This was a decrease from the 578.4 cubic S 1-2 00 0

0 0

S 0

meters of solid waste released from the unit in 2011.

The total activity released from the unit for 2012 was 0.207 curies,

0.00 curies from spent resin and 0.207 curies from dry

compressables. This was a decrease from the 2011 value of 5.24 curies. Overall, the radioactive effluent monitoring program was conducted in a manner to ensure the activity released and

associated dose to the public were maintained as low as

reasonably achievable.

S 0*2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits 5The ODCM Radiological Effluent Control Specifications applicable

to the release of radioactive material in liquid and gaseous effluents

are described in the following sections.

S 2.1.1 Fission and Activation Gases (Noble Gases)

The release rate of radioactive material in airborne effluents

shall be controlled such that the instantaneous concentrations of radionuclides do not exceed the values specified in 10 CFR 20 for airborne effluents at the

unrestricted area boundary. To support plant operations,

Supervisor - System Chemistry may increase this limit up to

the limits specified in Technical Specification 5.16.1.g.

Technical Specification 5.16.1.g establishes the

administrative control limit on the concentration resulting

from radioactive material, other than noble gases, released in gaseous effluents to unrestricted areas conforming to ten times 10 CFR 20.1001-20.2401, Appendix B, Table 2,

Column 1. For noble gases, the concentration shall be

limited to five times 10 CFR 20.1001-20.2401, Appendix B,

Table 2, Column 1.

The air dose due to noble gases released in gaseous

effluents to areas at or beyond the unrestricted area

boundary shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5

mRad for gamma radiation and less than or equal to

10 mRad for beta radiation, and 0

0 0

1-3 0

0

b. During any calendar year: Less than or equal to 10 mRad for gamma radiation and less than or equal to 20 mRad for beta radiation.

0 2.1.2 Doses from 1-131, 1-133, C-14, Tritium, and Radioactive Material in Particulate Form with Half Lives Greater than 8 Days (Other than Noble Gases).

a. The dose to an individual or dose commitment to any organ of an individual in unrestricted areas due to the release of 1-131, 1-133, C-14, H-3, and radioactive material in particulate form with half-lives greater than eight days (other than noble gases) in airborne 0 effluents shall not exceed 7.5 millirem from all exposure pathways during any calendar quarter.

b. The dose to an individual or dose commitment to any organ of an individual in unrestricted areas due to the release of 1-131, 1-133, C-14, H-3, and radioactive materials in particulate form with half-lives greater than eight days (other than noble gases) in airborne effluents shall not exceed 15 millirem from all exposure pathways during any calendar year.

2.1.3 Liquid Effluents 0

The release rate of radioactive material in liquid effluents shall be controlled such that the instantaneous concentrations for radionuclides, other than dissolved or entrained noble gases, do not exceed the values specified in 10 CFR 20 for liquid effluents at site discharge. To support plant operations, the Supervisor - System Chemistry may increase this limit up to the limit specified in Technical Specifications 5.16.1 .b.

Technical Specification 5.16.1.b establishes the administrative control limit on concentration of radioactive material, other than dissolved or entrained noble gases, released in liquid effluents to unrestricted areas conforming to ten times 10 CFR 20.1001-20.2401, Appendix B, Table 2, 0 Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.OE-04 pCi/mL total activity.

The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents 1

0 1-4 0 0

0 0

released to unrestricted areas shall be limited to:

a. During any calendar quarter: Less than or equal to

1.5 mRem to the whole body and less than or equal

to 5 mRem to any organ, and

b. During any calendar year: Less than or equal to 3

mRem to the whole body and less than or equal to 10

mRem to any organ.

00 2.1.4 Total Dose-Uranium Fuel Cycle

The dose to any individual from uranium fuel cycle sources

shall be limited to < 25 mRem to the total body or any organ (except the thyroid, which shall be limited to < 75 mRem) during each calendar year.

2.2 Effluent Concentration Limits (ECL) 2.2.1 Liquid Effluents

The values specified in 10 CFR Part 20, Appendix B,

Column 2 are used as the ECL for liquid radioactive effluents released to unrestricted areas. A value of 2.OE-04 pCi/mL is used as the ECL for dissolved and

entrained noble gases in liquid effluents.

0

2.2.2 -Gaseous Effluents

The values specified in 10 CFR Part 20, Appendix B,

Column 1 are used as the ECL for gaseous radioactive

effluents released to unrestricted areas.

0 2.3 Measurements and Approximations of Total Radioactivity

Measurements of total radioactivity in liquid and gaseous

radioactive effluents were accomplished in accordance with the sampling and analysis requirements of Tables 3.1 and 3.2 of Part I 0*of the ODCM.

2.3.1 Liquid Radioactive Effluents

Each batch was sampled and analyzed for gamma emitting

radionuclides using gamma spectroscopy, prior to release.

Composite samples were analyzed monthly and quarterly for the Monitor Tanks and Steam Generators. Composite 0

0

1-5 0

S 0

0 samples were analyzed monthly in the onsite laboratory for tritium and gross alpha radioactivity, using liquid scintillation and proportional counting techniques respectively.

Composite samples were analyzed quarterly for Sr-89, Sr-90, Fe-55, Ni-63, and Gross Alpha by a contract laboratory (Teledyne Brown Engineering, Inc.). A software program was used to project the total body and critical organ dose contribution at the unrestricted area boundary for each release and the percent contribution to the annual objective dose.

There were no continuous releases from the Steam Generator blowdown during the reporting period. 0 2.3.2 Gaseous Radioactive Effluents 0 Each gaseous batch release was sampled and analyzed for radioactivity prior to release. For release of Waste Gas Decay Tanks, noble gas grab samples were analyzed for gamma emitting radionuclides using gamma spectroscopy.

For releases from the Containment Building, samples were taken using charcoal and particulate filters, in addition to noble gas and Tritium grab samples, and analyzed for gamma emitting radionuclides prior to each release. The results of the analysis and the total volume of effluent 0 released were used to determine the total amount of S radioactivity released in the batch mode. A software program was developed and installed that can project the total body and critical organ dose contribution at the unrestricted area boundary for each release and the percent S contribution to the annual objective dose. This program also 0 adds the projected dose to the current actual dose totals in a temporary file, until it is updated with actual release data at the completion of a purge.

Continuous release effluent pathways were continuously sampled using charcoal and particulate filters and analyzed weekly for gamma emitting radionuclides using gamma spectroscopy. Weekly particulate filters were analyzed for gross alpha radioactivity in the onsite laboratory using proportional counting techniques. Quarterly composites of particulate filters were analyzed for Sr-89, Sr-90, and Gross Alpha by a contract laboratory (Teledyne Brown Engineering, Inc.). 0 1

S S

S 1-6 5 S

0 0

2.4 Estimation of Total Percent Error The estimated total percent error is calculated as follows:

0 2

Total Percent Error = (El + E 2 + E3 + ... + En2)0.5 2 2 Where En = percent error associated with each contributing parameter.

Sample counting error is estimated by the Canberra Genie System

Software for samples analyzed by gamma spectroscopy. This calculation can include the error associated with peak area

determination, gamma ray abundance, efficiency and half-life.

Systematic error is estimated for gaseous and liquid effluent

analyses and dilution and wastewater volume.

2.5 Batch Releases

A summary of information for liquid and gaseous batch releases is

included in Table 111.1.

0* 2.6 Abnormal Releases

Abnormal Releases are defined as unplanned and unmonitored releases of radioactive material from the site.

A summary of information for liquid and gaseous abnormal

releases is included in Table 111.2.

0 3.0 GASEOUS EFFLUENTS

The quantities of radioactive material released in gaseous effluents are

summarized in Tables 111.3,111.4 and 111.5. All radioactive materials released in gaseous form are considered to be ground level releases.

4.0 LIQUID EFFLUENTS 0

The quantities of radioactive material released in liquid effluents are summarized in Tables 111.6,111.7 and 111.8.

5.0 SOLID WASTES The quantities of radioactive material released as solid effluents are

summarized in Section VI.

0

6.0 RELATED INFORMATION 0

0 0

1-7 0

0 6.1 Operability of Liquid and Gaseous Monitoring Instrumentation During the reporting period there were two instrument used to 0 monitor radioactive effluent releases that failed to meet the minimum reportable instrument operability requirements listed in the ODCM during the reporting period.

RM-043, Laboratory and Radioactive Waste Processing Building Exhaust Stack Monitor, was inoperable for 44 days (11/18/2012-12/31/2012) due to sample pump issues. The unavailability of replacement parts prevented the monitor from being repaired in less than 30 days. Alternate particulate and iodine sampling was established and shiftly gas grab samples were performed as 0 required in ODCM Table 3.2.1.

RM-063 Post Accident Radiation Monitor was inoperable for 249 days (4/27/2012 - 12/31/2012) due to a defective signal cable.

The unavailability of replacement parts has prevented the monitor from being repaired. Procedure CH-SMP-PA-0005, Post Accident Sampling of the Auxiliary Building Exhaust Stack, provides in part the sampling requirements of the Off-Site Dose Calculation Manual (ODCM) and was a backup contingency plan for obtaining the required inputs to perform dose assessment for auxiliary building releases in the event of a declared emergency.

6.2 Changes to the Offsite Dose Calculation Manual (ODCM) and/or S Process Control Program (PCP) 0 During 2012, no changes were made to the ODCM:

During 2012, the following change was made to the PCP:

0

" Superseding RW-200 with RW-AD-300.

" Remove out of date activities, unnecessary editorial statements and incorrect references. 0 0

6.3 New Locations or Modifications for Dose Calculations or Environmental Monitoring 0

No new sample locations were added to the REMP program.

0 6.4 Noncompliance with Radiological Effluent Control Requirements0 This section provides a list of any event that did not comply with the 1-8

0 0

S 0

applicable requirements of the Radiological Effluent Controls given in the Offsite Dose Calculation Manual (ODCM). Detailed

documentation concerning the evaluations and corrective actions is

maintained onsite.

6.4.1 Abnormal Gaseous and Liquid Releases

No abnormal releases were made during the calendar year

of 2012.

0 6.4.2 Failure to Meet Specified Sampling Requirements

During 2012, there were no instances in which specified

sampling requirements were not met.

6.5 Modifications to Liquid and Gaseous Waste Treatment and

Ventilation Exhaust Systems S

During the reporting period no design modifications were approved nor implemented involving major changes to the Liquid and Gaseous Waste Treatment Systems.

S 6.6 Meteorological.Monitoring Program A summary of hourly meteorological data, collected during 2012, is

retained onsite and is maintained as documentation as required by

Regulatory Guide 1.21 Rev 2. This data is available for review by the Nuclear Regulatory Commission upon request. Joint Frequency tables are included in Section VII, Attachment 2

Real time hourly meteorological data is used to calculate the

annual air effluent dose to individuals. For quarterly estimates during the year an annual average X/Q is used, which is an average of the highest X/Q's calculated for each of the previous

two years. Due to station flooding in 2011 damaging the on-site

weather tower electronics, 19.16% of the meteorological data used the Joint Frequency tables and station doses were supplied by Eppley Airfield Weather Station, a branch of the National Weather

Service.

0 6.7 Assessment of Doses

D 6.7.1 Doses Due to Liquid Effluents S

Total body, skin, and organ dose for liquid releases were calculated in mRem for all significant liquid pathways using

the annual configuration of the LADTAP II program. The site 0

0

1-9 0

discharge location was chosen to present a most conservative estimate of dose for an average adult, teenager, child, and infant. A conservative approach is also presented by the assumption that Omaha and Council Bluffs receive all drinking water from the Missouri River.

The LADTAP II program in its annual configuration was also used to calculate the total body and organ doses for the population of 950,006 within a 50-mile radius of the plant (based on the 2010 census). The results of the calculations are listed in Section V.

0 The doses due to liquid effluents for total body and critical organ are also calculated quarterly using the methods in the ODCM. The results are listed in Section II.

0 6.7.2 Doses Due to Gaseous Effluents Total body, skin and organ doses from ground releases were calculated in mRem to an average adult, teenager, child, 0 and infant in each receptor using the annual configuration of the GASPAR II program. Also, the doses to the same groups, in units of mRad due to gamma and beta radiation carried by air, were computed using GASPAR I1.

The GASPAR II program in its annual configuration was also used to calculate the ALARA integrated population dose summary for the total body, skin and organ doses in person-rem for all individuals within a 50-mile radius. The results of the calculations are shown in Section IV.

0 The doses due to gaseous effluents for total body gamma and beta noble gas air dose are calculated quarterly using the methods in the ODCM with an annual average X/Q. The results are listed in Section II. 0 0

6.7.3 Doses Due to 1-131, 1-133, C-14, H-3, and Particulates with Half Lives Greater than 8 days.

0 The doses due to 1-131, 1-133, C-14, H-3, and Particulates with half-lives greater than 8 days for total body and critical organ dose are calculated quarterly using the highest of infant or child dose factors and an annual average X/Q. The results are listed in Section II for inhalation, ground and food.

6.7.4 Direct Radiation Dose to Individuals and PoDulations 1-10

0 0

0

Direct radiation doses attributed to the gamma radiation emitted from the containment structure were not observed

above local background at any TLD sample locations for this

annual period.

6.7.5 40 CFR 190 Dose Evaluation

ODCM Radiological Effluent Controls require dose

evaluations to demonstrate compliance with 40 CFR Part

190 only if calculated yearly doses exceed two times the annual design objectives for liquid and/or gaseous effluents.

At no time during 2012 were any of these limits exceeded;

therefore, no evaluations were required.

0 6.8 Groundwater Monitoring Program and Observations

OPPD conducted groundwater sampling from 19 wells, 2

surface water sites, and 4 storm water headers within the

site property per NEI 07-07. Two storm water headers were added in the 3 rd quarter per ANI recommendations.

Additionally Nebraska requirements regarding avoidance of

snow runoff were deleted, so storm water sampling is now

performed quarterly, if available.

0 No new monitoring wells were added to the sampling program

during 2012. A rainwater sampling program was initiated prior to

station flooding. Ten sample locations in sectors experiencing

significant (>10%) wind direction were established to assess potential atmospheric deposition. After an initial sampling regime

in all ten sectors displayed no detectable tritium, the sampling

program was switched to 2 affected sectors per rain event and an

upwind background test. Three sampling events were conducted.

No tritium activity in excess of the vendor's Minimum Detectable Activity (MDA) was reported.

No tritium activity in excess of the vendor's Minimum

Detectable Activity (MDA) was reported in Table 111.9. One result greater than a 2 sigma threshold but less than MDA was maintained by plant staff. This result was reported at

MW-6. A duplicate sample at MW-6 also showed tritium

greater than 2 sigma threshold but less than MDA. MW-6 is

hydro-geologically connected to the river and is in close proximity to the licensed effluent release point. MW-6 has

historically had activity identified in excess of the MDA when

river levels are high. All Table 111.9 Sr-90 reported

concentrations represent values greater than a 2 sigma 0

0 11 0

0 0

threshold but less than MDA, which are evaluated by the plant staff as required by the site groundwater monitoring program. EPRI Report No. 1011730, Groundwater Monitoring Guidance for Nuclear Power Plants, documents plant shallow monitoring well Sr-90 results as typically showing a positive bias toward detection (i.e. background greater than zero). The Fort Calhoun Station Sr-90 results reflect this same bias. Although the data set is too small to 0 perform a complete statistical analysis, the measured values have not exceeded a threshold by which the results could be called "significantly different" from a true background value and therefore cannot be attributed to a plant environmental impact. The results are all below NRC, EPA, NEI and FCS groundwater protection program administrative reporting limits. Some hard to detect nuclides, were reduced to an annual sample frequency ( Ni-63, Fe-55, Sr-90 in deep wells) based on 2 years of quarterly sampling with no detections above MDA.

" The Fort Calhoun REMP sampling showed no detected tritium within the Missouri River downstream at the sight boundary or at the nearest municipal drinking water facility.

No groundwater drinking pathway exists on site. No state or federal drinking water limits, and no site groundwater protection program administrative limits were exceeded.

0

" Semi-annual storm water sampling wasn't performed during the 1 quarter due to Nebraska regulations against snow runoff in samples. The SW-6 ISFSI storm water header sample point was not performed for the 3 rd quarter due to drought conditions. 0 0

0 0

1-12 0 0

0 0

SECTION II QUARTERLY DOSES FROM EFFLUENTS Offsite Dose Calculation Manual 0

January 1, 2012 - December 31, 2012 0

S 0

0 0

I1-1

0 0

Quarterly Dose Calculation Results 0 S

January 1, 2012 through December 31, 2012 S

S With the implementation of the Fort Calhoun Station Radiological Effluent 0 Technical Specifications (RETS) on October 1, 1985, radiation doses in 0 the unrestricted area from liquid and gaseous effluents must be calculated on a quarterly basis in accordance with the Offsite Dose Calculation Manual (ODCM). These calculations are performed to ensure the annual 05 dose limits delineated in Appendix I of 10 CFR 50 and implemented by RETS are not exceeded. If the results of the quarterly calculations exceed fifty percent (50%) of the annual limits of Appendix I, actions are taken to reduce effluents so that the resultant doses do not exceed the annual limits during the remainder of the year and a special report is submitted to the Nuclear Regulatory Commission. No special reports were required for 2012 calculated doses.

0 This section presents the results of the quarterly dose calculations performed during the period January 1, 2012 through December 31, 2012.

Details are shown as to the types, sources and resultant doses from the effluents, the annual limits and a comparison to the annual limits.

10 0

0 0

S 0

S S

11-2 0 0

FORT CALHOUN STATION FC-421 CHEMISTRY FORM R8 QUARTERLY CUMULATIVE DOSE CONTRIBUTION FROM RADIOACTIVE EFFLUENTS FORT CALHOUN FIRST QUARTER 2012 DOSE PROJECTIONS 0

0 I. Liquid Effluents: Total Body Critical Organ Dose (mrem) Dose (mrem) 4.51E-03 Batch: 2.92E-03 0 Continuous: 0.OOE+00 0.OOE+00 0 Totals: 2.92E-03 4.51E-03 S

ODCM Quarterly Objective: 1.50E+00 5.OOE+00 0

Percent of Quarterly Obj: 0.19 % 0.09 %

0 3.OOE+00 ODCM Annual Objective: 1.OOE+01 0 YTD Percent of Annual Obj: 0.10 % 0.05 %

0 Total Body Gamma Total Body Beta II. Gaseous Effluents:

0 IT. Gaseous Effluents: Total Body Gamma Dose (mrad)

Total Body Beta Dose (mrad) 0 A. Noble Gas Air Dose: 0.OOE+00 0.OOE+00 0 ODCM Quarterly Objective: 5.OOE+00 1.OOE+01 S 0.00 %

Percent of Quarterly Obj: 0.00 %

0 ODCM Annual Objective: 1.OOE+01 2.OOE+01 YTD Percent of Annual Obj: 0.00 % 0.00 %

0 B. 1-131, 1-133, Tritium, C-14, 0 and Particulates with Half-Lives > 8 Days: Total Body Critical Organ 0 Dose (mrem) Dose (mrem) 0 Inhalation: 1.22E-04 1.22E-04 Ground and Food: 5.64E-04 5.64E-04 0

Totals: 6.86E-04 6.86E-04 0

ODCM Quarterly Objective: 7.50E+00 7.50E+00 Percent of Quarterly Obj: 0.01% 0.01 %

ODCM Annual Objective: 1.50E+01 1.50E+01 YTD Percent of Annual Obj: 0.00 % 0.00 %

11-3 Reviewed by: 411

S FORT CALHOUN STATION FC-421 0 CHEMISTRY FORM R8 QUARTERLY CUMULATIVE DOSE CONTRIBUTION FROM RADIOACTIVE EFFLUENTS FORT CALHOUN SECOND QUARTER 2012 DOSE PROJECTIONS 0

S I. Liquid Effluents: Total Body Dose (mrem)

Critical Organ Dose (mrem) 0 5.91E-04 8.60E-04 0 Batch:

Continuous: 0.OOE+00 0.00E+00 0 Totals: 5.91E-04 8.60E-04 0

0 ODCM Quarterly Objective: 1.50E+00 5.OOE+00 0

Percent of Quarterly Obj: 0.04 % 0.02 %6 0 ODCM Annual Objective: 3.00E+00 1.OOE+01 0 YTD Percent of Annual Obj: 0.12 % 0.05 06 0

0 II. Gaseous Effluents: Total Body Gamma Total Body Beta 0 II. Gaseous Effluents: Total Body Gamma Dose (mrad)

Total Body Beta Dose (mrad) 0 0

A. Noble Gas Air Dose: 0.OOE+00 0.OOE+00 0

ODCM Quarterly Objective: 5.OOE+00 1.OOE+01 0 Percent of Quarterly Obj: 0.00 % 0.00 % 0 ODCM Annual Objective: 1.OOE+01 2.OOE+01 0

0 YTD Percent of Annual Obj: 0.00 % 0.00 %

0 B. 1-131, 1-133, Tritium, and Particulates with C-14, 0 Half-Lives > 8 Days: Total Body Critical Organ 0 Dose (mrem) Dose (mrem)

Inhalation:

0 Ground and Food:

9.25E-05 4.28E-04 9.25E-05 4.28E-04 0

0 Totals: 5.21E-04 5.21E-04 0 ODCM Quarterly Objective: 7.50E+00 7.50E+00 0 Percent of Quarterly Obj: 0.01 % 0.01 % 0 ODCM Annual Objective: 1.50E+01 1.50E+01 0

0 YTD Percent of Annual Obj: 0.01 % 0.01 %

0 0

Reviewed by:.42 0

11-4 0

0 0

FORT CALHOUN STATION FC-421 CHEMISTRY FORM R8 QUARTERLY CUMULATIVE DOSE CONTRIBUTION FROM RADIOACTIVE EFFLUENTS FORT CALHOUN THIRD QUARTER 2012 DOSE PROJECTIONS 0

S I. Liquid Effluents: Total Body Critical Organ Dose (mrem) Dose (mrem) 0 2.24E-03 3.51E-03 Batch:

S Continuous: 0.OOE+00 0.OOE+00 Totals: 2.24E-03 3.51E-03 0

ODCM Quarterly Objective: 1.50E+00 5.00E+00 0

0 Percent of Quarterly Obj: 0.15 % 0.07 %

0 ODCM Annual Objective: 3.00E+00 1.OOE+01 YTD Percent of Annual Obj: 0.15 %6 0.07 %

S 0 II. Gaseous Effluents: Total Body Gamma Total Body Beta 0 II. Gaseous Effluents-Total Body Gamma Dose (mrad)

Total Body Beta Dose (mrad) 0 A. Noble Gas Air Dose: 0.OOE+00 0.OOE+00 0

0 ODCM Quarterly Objective: 5.00E+00 1.OOE+01 Percent of Quarterly Obj: 0.00 % 0.00 %

S 0 ODCM Annual Objective: 1.OOE+01 2.OOE+01 YTD Percent of Annual Obj: 0.00 % 0.00 %

0 B. 1-131, 1-133, Tritium, C-14, 0 and Particulates with Critical Organ Half-Lives > 8 Days: Total Body Dose (mrem) Dose (mrem) 0 Inhalation: 1.38E-04 1.38E-04 0 Ground and Food: 6.37E-04 6.37E-04 Totals: 7.75E-04 7.75E-04 0 ODCM Quarterly Objective: 7.50E+00 7.50E+00 Percent of Quarterly Obj: 0.01% 0.01 %

0 ODCM Annual Objective: 1.50E+01 1.50E+01 S

YTD Percent of Annual Obj: 0.01 % 0.01 °6 Reviewed by:

11-5

FORT CALHOUN STATION FC-421 0 CHEMISTRY FORM R8 QUARTERLY CUMULATIVE DOSE CONTRIBUTION FROM RADIOACTIVE EFFLUENTS FORT CALHOUN FOURTH QUARTER 2012 DOSE PROJECTIONS 0

0 I. Liquid Effluents: Total Body Dose (mrem)

Critical Organ Dose (mrem) 0 9.47E-04 0 Batch: 6.36E-04 Continuous: 0.00E+00 0.OOE+00 0 Totals: 6.36E-04 9.47E-04 0

0 ODCM Quarterly Objective: 1.50E+00 5.OOE+00 0

Percent of Quarterly Obj: 0.04 % 0.02 % 0 ODCM Annual Objective: 3.OOE+00 1.OOE+01 0 YTD Percent of Annual Obj: 0.17 % 0.08 %w 0

0 II. Gaseous Effluents: Total Body Gamma Total Body Beta 0 II. Gaseous Effluents: Total Body Gamma Dose (mrad)

Total Body Beta Dose (mrad) 0 0

A. Noble Gas Air Dose: 0.OOE+00 0.OOE+00 0

ODCM Quarterly Objective: 5.OOE+00 1.OOE+01 0 Percent of Quarterly Obj: 0.00 % 0.00 % 0 ODCM Annual Objective: 1.OOE+01 2.OOE+01 0

0 YTD Percent of Annual Obj: 0.00 % 0.00 %

0 B. 1-131, 1-133, Tritium, and Particulates with C-14, 0 Half-Lives > 8 Days: Total Body Critical Organ 0 Dose (mrem) Dose (mrem)

Inhalation:

0 Ground and Food:

7.97E-05 3.68E-04 7.97E-05 3.68E-04 0

0 Totals: 4.48E-04 4.48E-04 0

ODCM Quarterly Objective: 7.50E+00 7.50E+00 0 Percent of Quarterly Obj: 0.01 %0 0.01 % 0 ODCM Annual Objective: 1.50E+01 1.50E+01 0

0 YTD Percent of Annual Obj: 0.02 % 0.02 %

0 0

0 Reviewed by: 0 0

11-6 0

0 0

S 0

0 0

0 SECTION III S RADIOLOGICAL EFFLUENT RELEASES 0 Technical Specification (5.9.4.a) 0 0

0 Table 111.1 Batch Liquid and Gas Release Summary 0 Table 111.2 Abnormal Batch Liquid and Gaseous Release Summary 0 Table 111.3 Gaseous Effluents - Summation of all Releases 0 Table 111.4 Gaseous Effluent Releases - Batch Mode 0 Table 111.5 Gaseous Effluent Releases - Continuous Mode 0 Table 111.6 Liquid Effluents - Summation of all Releases Table 111.7 Liquid Effluent Releases - Batch Mode 0

Table 111.8 Liquid Effluent Releases - Continuous Mode 0 Table 111.9 Groundwater Tritium Results 0

0 0

January 1, 2012 - December 31, 2012 0

0 0

S 0

Il1-I

TABLE III.1 BATCH LIQUID AND GASEOUS RELEASE

SUMMARY

JANUARY THROUGH DECEMBER 2012 A. Liquid Releases All Sources ist Qtr 2nd Qtr 3rd Qtr 4th Qtr Year 1 . Number of Batch Releases: 21 26 29 27 103

2. Total Time Period for Batch Releases(min): 9,357 10,929 12,509 12,139 44,934

3. Maximum Time Period for Batch Releases(min): 512 488 546 569 569

4. Average Time Period for Batch Releases(min): 446 420 431 450 436

5. Minimum Time Period for Batch Releases(min): 380 70 219 346 70

6. Average Dilution Stream Flow During Periods of Release into the Missouri River(mls/min): 2 .730E+07 2. 637E+07 2.730E+07 2 .730E+07 2. 707E+07 B. Gaseous Releases All Sources 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year

1. Number of Batch Releases: 12 11 14 14 51

2. Total Time Period for Batch Releases(min): 98,185 73,272 110,254 118,089 399,800

3. Maximum Time Period for Batch Releases(min): 17,183 10,114 11,135 10,060 17,183

4. Average Time Period for Batch Releases(min): 8,182 6,661 7,875 8,435 7,839

5. Minimum Time Period for Batch Releases(min): 1,749 179 255 520 179 111-2

TABLE 111.2 ABNORMAL BATCH LIQUID AND GASEOUS RELEASE

SUMMARY

JANUARY THROUGH DECEMBER 2012 A. Liquid Releases All Sources 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year Number of Releases: 0 0 0 0 0 Total Activity Releases(Ci): 0. OOE+00 0. OOE+00 0.OOE+00 0.OOE+00 0. OOE+00 B. Gaseous Releases All Sources ist Qtr 2nd Qtr 3rd Qtr 4th Qtr Year Number of Releases: 0 0 0 0 0 Total Activity Releases (Ci): 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 111-3

TABLE 111.3 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES JANUARY THROUGH DECEMBER 2012 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year A. Fission & Activation Gases Total Release (Ci): 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Average Release Rate (uCi/sec): O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Total Error (%): 21.2 B. Iodines Total Release (Ci): 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Average Release Rate (uCi/sec): 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Total Error (%): 21.2 C. Particulates Total Release (Ci): 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Average Release Rate (uCi/sec): 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Total Error (%): 20.62 Gross Alpha:

Total Error (%): 20.62 4.13E-06 1.92E-06 4.02E-06 5.84E-06 1.59E-05 D. Tritium Total Release (Ci) : 3.71E-01 2.81E-01 4.19E-01 2.43E-01 1.31E+00 Average Release Rate (uCi/sec) : 1.91E-03 1.51E-03 2.13E-03 1.19E-03 1.67E-03 Total Error (%): 25.08 E. Carbon-14 Total Release (Ci): 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Average Release Rate (uCi/sec): 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Total Error (%): 20.62 NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD).

111-4 0 0 0 0 00 00 00 00 00 09 00 00 0 0 0 10 0 0 0 0 0 0 0

TABLE 111.4 GASEOUS EFFLUENTS--GROUND LEVEL RELEASES JANUARY THROUGH DECEMBER 2012 Batch Mode Nuclides(Ci) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter YEAR Fission & Activation Gases Totals for Period: 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0. 00E+00 Iodines Totals for Period: 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0. OOE+00 Particulates 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0. OOE+00 Totals for Period:

Tritium and Gross Alpha H-3 2.52E-01 1.76E-01 2.43E-01 1.20E-01 7. 90E-01 NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD).

111-5

TABLE 111.5 GASEOUS EFFLUENTS--GROUND LEVEL RELEASES JANUARY THROUGH DECEMBER 2012 Continuous Mode Nuclides (Ci) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Fission & Activation Gases Totals for Period: 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0 .OOE+00 Iodines Totals for Period: 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0. OOE+00 Particulates Totals for Period: 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0. OOE+00 Tritium and Gross Alpha ALPHA 4.13E-06 1.92E-06 4.02E-06 5.84E-06 1. 59E-05 H-3 1.20E-01 1.05E-01 1.76E-01 1.23E-01 5.25E-01 NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD).

111-6

TABLE 111.6 LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES JANUARY THROUGH DECEMBER 2012 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year A. Fission & Activiation Products Total Release (No H-3,Gas,Alpha) (Ci): 4.17E-04 1.07E-04 4.33E-04 1.20E-04 1.08E-03 Averaqe Diluted Concentration (uCi/mL): 3.43E-08 9.37E-09 3.68E-08 9.76E-09 9.05E-08 10 CFR 20, ADD. B Limit 1.OOE-06(uCi/mL)

Percent of Limit %): 3 .43E+00 9.37E-01 3.68E+00 9.76E-01 9.05E+00 Total Error (%)- 29.68 B. Tritium Total Release (Ci): 7.09E-01 7.15E-01 6.31E-01 8.83E-01 2.94E+00 Averaqe Diluted Concentration (uCi/mL): 5.83E-05 6.26E-05 5.36E-05 7.19E-05 2.47E-04 10 CFR 20, ADD. B Limit 1.OOE-03 (uCi/mL)

Percent of Limit (%): 5.83E+00 6.26E+00 5.36E+00 7.19E+00 2.47E+01 Total Error (%): 25.08 C. Dissolved & Entrained Gases Total Release (Ci): 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Averaqe Diluted Concentration (uCi/mL): 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 ODCM Limit 2.OOE-04 (uCi/mL)

Percent of Limit (k): 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Total Error (%): 18.14 D. Gross Alpha Radioactivity Total Release (Ci): 0.OOE+00 0.OOE+00 9.61E-06 0.OOE+00 9.61E-06 Total Error (%): 25.08 E. Volume of Waste Released 4.14E+05 4.94E+05 5.67E+05 6.10E+05 2.08E+06 Prior to Dilution (Liters):

F. Volume of Dilution Water 2.55E+08 2.96E+08 3.41E+08 3.31E+08 1.22E+09 Durinq Releases (Liters):

NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD).

111-7

TABLE 111.7 LIQUID EFFLUENTS JANUARY THROUGH DECEMBER 2012 Batch Mode Nuclides (Ci) Ist Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Fission & Activation Gases CS-137 3.OBE-04 5.69E-05 3. 88E-04 1.01E-04 8. 55E-04 CS-134 1.03E-05 4.42E-07 7 .48E-06 1.20E-06 1.94E-05 CO-58 5.13E-05 7.49E-06 3.25E-07 0. OOE+00 5. 91E-05 SB-125 2.31E-05 3.12E-05 2. 77E-05 1.28E-05 9.4 8E-05 SB-124 7.31E-07 3.01E-07 0 . OOE+00 0 . OOE+00 1.03E-06 CO-60 2.30E-05 1 06E-05 9. 05E-06 4.42E-06 4. 70E-05 Totals for Period: 4.17E-04 1.07E-04 4 .33E-04 1.20E-04 1. 08E-03 Dissolved & Entrained Gases Totals for Period: 0.00E+00 0.DOE+00 0.00E+00 0 . OOE+00 0. 00E+00 Tritium and Gross Alpha ALPHA 0 . 00E+00 O.00E+00 9. 61E-06 0 .0E+00 9. 61E-06 H-3 7. 09E-01 7.15E-01 6. 31E-01 8. 83E-01 2. 94E+00 NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD) values.

Reported Alpha activity was attributed to natural short-lived radionuclides. This was confirmed by quarterly offside vendor analysis.

111-8

TABLE 111.8 LIQUID EFFLUENTS JANUARY THROUGH DECEMBER 2012 Continuous Mode Nuclides(Ci) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Fission & Activation Products Totals for Period: 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0 . OOE+00 Dissolved & Entrained Gases Totals for Period: 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0. OOE+00 Tritium and Gross Alpha ALPHA 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0. OOE+00 H-3 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0. OOE+00 NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD).

111-9

0 0

0 TABLE 111.9 0

GROUNDWATER ANALYSIS RESULTS 0 pCi/L 0

JANUARY THROUGH DECEMBER 2012 0

ist Quarter 2nd Quarter 3rd Quarter 4th Quarter 0 MW- A O.OOE+00 O.OOE+00 O.OOE+00 O.00E+00 0

Tritium FE-55 NI-63 O.OOE+00 O.OOE+00 0

Sr-90 O.OOE+00 O.OOE+00 O.OOE+00 O.00E+00 Total Gamma O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

MW-IB Tritium O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

FE-55 NI-63 O.OOE+00 O.OOE+00 0

Sr-90 O.OOE+00 Total Gamma O.OOE+00 O.OOE+00 O.OOE+00 O.00E+00 0

MW-2 Tritium O.OOE+00 O.OOE+00 O.OOE+00 O.00E+00 0 O.OOE+00 FE-55 NI-63 O.OOE+00 0 Sr-90 Total Gamma O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 MW-2A 0

O.OOE+00 O.OOE+00 O.00E+00 Tritium FE-55 O.OOE+00 O.OOE+00 0 O.OOE+00 NI-63 Sr-90 O.OOE+00 O.OOE+00 O.OOE+00 O.00E+00 O.00E+00 0

O.OOE+00 O.OOE+00 O.00E+00 Total Gamma 0

MW-2B Tritium O.OOE+00 O.OOE+00 O.00E+00 O.OOE+00 S O.OOE+00 FE-55 NI-63 O.OOE+00 O.OOE+00 0

Sr-90 Total Gamma O.OOE+00 O.OOE+00 O.OOE+00 O.00E+00 0 MW-3 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

Tritium FE-55 O.OOE+00 O.OOE+00 0

NI-63 Sr-90 Total Gamma O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 9

MW-3A 0

Tritium O.OOE+00 O.OOE+00 O.00E+00 O.OOE+00 0 FE-55 O.OOE+00 NI-63 Sr-90 O.OOE+00 O.OOE+00 6.32E-01 O.OOE+00 5.47E-01 0

Total Gamma O.OOE+00 O.OOE+00 O.OOE+00 0

MW-3B Tritium FE-55 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.00E+00 0

NI-63 O.OOE+00 Sr-90 Total Gamma O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 MW-4A 0

Tritium O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 FE-55 NI-63 O.OOE+00 0 O.OOE+00 O.OOE+00 5.53E-01 O.OOE+00 Sr-90 Total Gamma O.OOE+00 O.OOE+00 O.OOE+00 O.00E+00 0 0

0 III-10 0

0

0 0

0 TABLE 111.9 S GROUNDWATER ANALYSIS RESULTS pCi/L 0 JANUARY THROUGH DECEMBER 2012 S

1st Quarter 2nd Quarter 3rd Quarter 4th Quarter MW-4B Tritium 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 FE-55 0.OOE+00 NI-63 0.OOE+00 Sr-90 0.OOE+00 Total Gamma O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 MW-5A Tritium O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 FE-55 0.OOE+00 NI-63 0.OOE+00 Sr-90 O.OOE+00 O.OOE+00 6.01E-01 O.OOE+00 Total Gamma O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 MW -6 M Tritium 0.00E+00 O.OOE+00 1.28E+02 O.OOE+00 FE-55 O.OOE+00 5 NI-63 Sr-90 O.OOE+00 4.72E-01 0.OOE+00 O.OOE+00 O.OOE+00 Total Gamma O.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 O MW-5B Tritium 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 5 FE-55 NI-63 0.OOE+00 O.00E+00

Sr-90 0.OOE+00 Total Gamma O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 MW-7 Tritium 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 FE-55 0.00E+00 5 NI-63 Sr-90 5.15E-01 5.46E-01 0.OOE+00 7.39E-01 0.00E+00 Total Gamma O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 MW-9 Tritium O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 FE-55 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 NI-63 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-90 O.OOE+00 O.OOE+00 6.73E-01 8.90E-01 Total Gamma O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5 MW-10 Tritium O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 FE-55 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 NI-63 O.OOE+00 O.OOE+00 O.OOE+00 O.GOE+00 Sr-90 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Total Gamma 0.00E+00 O.OOE+00 0.00E+00 0.OOE+00 MW-0I Tritium O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 FE-55 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 NI-63 0.00E+00 O.OOE+00 O.OOE+00 O.OE+00 Sr-90 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5 Total Gamma O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5 MW-12A Tritium O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 FE-55 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 NI-63 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-90 O.OOE+00 O.OOE+00 4.75E-01 6.43E-01 S Total Gamma O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 S

5 III-ll S

0 S

TABLE 111.9 GROUNDWATER ANALYSIS RESULTS pCi/L JANUARY THROUGH DECEMBER 2012 0

1st Quarter 2nd Quarter 3rd Quarter 4th Quarter MW-12 B Tritium O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 FE-55 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 NI-63 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-90 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Total Gamma O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 EAST LAGOON 0 Tritium O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 FE-55 0 NI-63 Sr-90 Total Gamma O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

WEST LAGOON Tritium O.OOE+00 O.OOE+00 O.OOE+00 FE-55 NI-63 Sr-90 0

Total Gamma O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 S NORTH STORMWATER HDR Tritium O.OOE+00 O.OOE+00 O.OOE+00 FE-55 0.OOE+00 NI-63 0.OOE+00 Sr-90 0.OOE+00 Total Gamma O.OOE+00 O.OOE+00 O.OOE+00 SOUTH STORMWATER HDR 0 Tritium O.OOE+00 O.OOE+00 O.OOE+00 FE-5S 0.OOE+00 NI-63 0.OOE+00 Sr-90 0.OOE+00 Total Gamma O.OOE+00 O.OOE+00 O.OOE+00 SW-8 NORTH PA Tritium O.OOE+00 O.OOE+00 FE-55 NI-63 Sr-90 Total Gamma 0.00E+00 O.OOE+00 SW-6 ISFSI 0 Tritium 0.OOE+00 FE-S55 NI-63 Sr-90 Total Gamma 0.OOE+00 NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD).

Only Tritium and Gamma are required for each sampling event.

Hard to detect (HTD) nuclide sampling frequency is per station procedures.

Missed sampling events are covered in the executive summary.

0 0

III-12 0

0 0

S 0

0 S

0 0

SECTION IV DOSE FROM GASEOUS EFFLUENTS Technical Specification 5.9.4.a 0

S GASPAR II OUTPUT 0

S January 1,2012 - December 31, 2012 0

0 0

0 S

0 IV-1

0 0

Radioactive Effluent Releases - First, Second, Third and Fourth Quarters 2012 0

GASEOUS EFFLUENTS 0

Radioactive gaseous releases for the reporting period totaled 0.00E+00 curies of inert 0 gas. The gross gaseous activity release rates were 0.OOE+00 pCi/sec for the first quarter, 0.OOE+00 pCi/sec for the second quarter, 0.OOE+00 pCi/sec for the third quarter, and 0.OOE+00 pCi/sec for the fourth quarter.

Radioactive halogens releases for the reporting period totaled 0.OOE+00 curies. The halogen activity release rates were 0.00E+00 pCi/sec for the first quarter, 0.OOE+00 pCi/sec for the second quarter, 0.OOE+00 pCi/sec for the third quarter, and 0.OOE+00 pCi/sec for the fourth quarter from gaseous effluent discharges.

No radioactive particulates with half-lives greater that eight days were released during the reporting period from gaseous effluent discharges.

0 Radioactive tritium released during the reporting period totaled 1.314 curies. 0 Carbon-14 released for the reporting period totaled 0.00 curies, this is a calculated value based on reactor power and days of operation. 0 0

0 Off-site vendor analysis of weekly composite samples indicated that no gross alpha radioactivity was released during the reporting period.

S 0

0 0

0 IV-20 0

0 0 POTENTIAL DOSES TO INDIVIDUALS AND POPULATIONS 0

A. Potential Annual Doses to Individuals from Gaseous Releases Total body, skin, and organ doses from ground releases were calculated in

rmRem to an average adult, teenager, child, and infant using the annual O configuration of the GASPAR II program. Results to each receptor are shown in

Tables IV-A-1 through IV-A-39. Also, the doses to the same groups, Table IV-B-1, in units of mRad, due to gamma and beta radiation carried by air, were computed using GASPAR II. In its annual configuration, GASPAR II O assumes that all release rates are entered in curies per year (Ci/yr).

The inputs to GASPAR II for the annual period from January 1,2012 through December 31, 2012 were as follows:

O (1) All gaseous effluents O (2) Entrained gases (Ar-41, Xe-131M, Xe-133M, Xe-133, Xe-135M, Xe-135, Kr-85M, Kr-87, and Kr-88) from liquid effluents.

0

(3) Annual X/Q at the actual receptor locations, which are corrected for open terrain and plume depletion, are calculated according to Regulatory Guide 1.111. Also included are annual deposition rates corrected for the

open terrain factor.

0

(4) The production, intake and grazing fractions were as follows: 1.0 for leafy vegetables grown in garden of interest, 0.76 for produce grown in garden

of interest, 0.5 for the pasture grazing season of the milk animal, 1.0 for

pasture grazing season of the meat animal, and 8 g/m 3 for the air water

(humidity) concentrations.

(5) All dose factors, transport times from receptor to individual, and usage

factors are defined by Regulatory Guide 1.109 and NUREG-0172.

O (6) Site specific information, within a five-mile radius of the plant, on types of receptors located in each sector was used. That is, if a cow was not present in a sector, then the milk pathway for that sector was not

considered. If it was present, then the actual sector distance was used.

0 0

0

0 0

These inputs introduce a most conservative approach for the following reasons:

(1) The open terrain and deposition corrections increase annual X/Q by a

factor ranging between 1.0 and 4.0 S

(2) The production, intake, and grazing fractions, as defined in the input definition statement, represent the environment in an extremely conservative manner.

B. Potential Semiannual Doses to Population from Gaseous Releases The GASPAR II program in its annual configuration was also used to calculate the ALARA integrated population dose summary for the total body, skin, and 0 organ doses in man-rem for all individuals within a 50-mile radius. The population-integrated dose is the summation of the dose received by all individuals and has units of man-thyroid-rem when applied to the summation of thyroid doses. The same inputs were used as in the individual case with the addition of the following: O 0

(1) A total population of 950,006 (based on the 2010 census) was used to define the sector segments within a 50-mile radius of the plant.

0 (2) Production of milk, meat, and vegetation is based on 1973 annual data for Nebraska as recommended by the Nuclear Regulatory Commission for use in GASPAR I1.

S S

0 0

0 S

0 0

S 0

0 O

0 IV-4 0 0

0

TABLE IV-A- 1 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 1 RES AT 4.36 MILES N ANNUAL BETA AIR DOSE = 5.03E-20 MILLRADS ANNUAL-GAMMAAIRDOSE = 1.69E-20 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

---------------- +--------------+---------------------------------+

PLUME : 9.85E-21 : 9.85E-21 : 9.85E-21 : 9.85E-21 : 9.85E-21 : 9.85E-21 : 1.04E-20 : 2.78E-20

+----- +-----------------+---

- ---------------------- -------------- +

GROUND : 1.44E-18 : 1.44E-18 : 1.44E-18 : 1.44E-18 : 1.44E-18 : 1.44E-18 : 1.44E-18 : 1.75E-18

-+---------------------------------------------------------------------------------------+------------------------------------+

INHAL . . . : : . .

ADULT 4.79E-06 4.79E-06 1.09E-18 4.79E-06 4.79E-06 4.79E-06 4.79E-06 4.79E-06

+---*--------------------------------------------------------- +---------------------------------+

TEEN : 4.83E-06 : 4.83E-06 : 1.54E-18 : 4.83E-06 : 4.83E-06 : 4.83E-06 : 4.83E-06 : 4.83E-06

--- +--------------------------------------------------------------------+-----------------+------------------+-----------------+

CHILD : 4.27E-06 : 4.27E-06 : 2.09E-18 : 4.27E-06 : 4.27E-06 : 4.27E-06 : 4.27E-06 : 4.27E-06

--- +--------------------------------------------------------------------+-----------------------------------------------------+

INFANT : 2.46E-06 : 2.46E-06 : 1.65E-18 : 2.46E-06 : 2.46E-06 : 2.46E-06 : 2.46E-06 : 2.46E-06

-+------- - -------------------------------------- +------------------------------------------------+

IV- 5

TABLE IV-A- 2 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 2 RES AT 1.93 MILES NNE ANNUALBETAAIRDOSE = 4.18E-19 MILLRADS ANNUAL-GAMMAAIRDOSE = 1.41E-19 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

-++--------------------------+-------------------------------------------------+-----------------+

PLUME : 8.19E-20 : 8.19E-20 : 8.19E-20 : 8.19E-20 : 8.19E-20 : 8.19E-20 : 8.61E-20 : 2.31E-19

+ +------------------+

GROUND : 6.67E-18 : 6.67E-18 : 6.67E-18 : 6.67E-18 : 6.67E-18 : 6.67E-18 : 6.67E-18 : 8.09E-18

---------------------------------- -+ - - ----------- ---------------- +

INHAL : . . : : :

ADULT 3.89E-05 3.89E-05 9.47E-18 3.89E-05 3.89E-05 3.89E-05 3.89E-05 3.89E-05

-+----

+

TEEN : 3.93E-05 : 3.93E-05 : 1.33E-17 : 3.93E-05 : 3.93E-05 : 3.93E-05 : 3.93E-05 : 3.93E-05 S--

---------- ------------------------ -+ - - ----------- -------------- +

CHILD : 3.47E-05 : 3.47E-05 : 1.81E-17 : 3.47E-05 : 3.47E-05 : 3.47E-05 : 3.47E-05 : 3.47E-05

S--

-+------------------+----------------- -+ - - ----------- -------------- +

INFANT : 2.OOE-05 : 2.OOE-05 : 1.43E-17 : 2.OOE-05 : 2.OOE-05 : 2.OOE-05 : 2.OOE-05 : 2.OOE-05 S+----------------------+------------------------------+------------------------------------+

IV- 6 ooooo000 oos 00(aoo0 oooooo eoo0 0 ooo 0 0 o(ob

0000000000000000000000000000000000000000000o TABLE IV-A- 3 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 3 RES AT 1.52 MILES NE ANNUAL BETA-AIR DOSE = 5.51E-19 MILLRADS ANNUAL-GAMMAAIRDOSE = 1.85E-19 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

- - +-+------------------------------------------------ -------------------------------------------- +

PLUME : 1.08E-19 : 1.08E-19 : 1.08E-19 : 1.08E-19 : 1.08E-19 : 1.08E-19 : 1.14E-19 : 3.05E-19 :

- -+--

+---------------------------+-----------------+----------------- -+-----------------+

GROUND : 4.83E-18 : 4.83E-18 : 4.83E-18 : 4.83E-18 : 4.83E-18 : 4.83E-18 : 4.83E-18 : 5.86E-18 :

- -+--

+---------------------------+------------------+-----------------+----------------- -+-----------------+

INHAL : : . . : :

ADULT 5.09E-05 5.09E-05 1.23E-17 5.09E-05 5.09E-05 5.09E-05 5.09E-05 5.09E-05

-+--------- -+-_+------------------- ----------------- -------------------------- +------------------+

TEEN : 5.14E-05 : 5.14E-05 : 1.73E-17 : 5.14E-05 : 5.14E-05 : 5.14E-05 : 5.14E-05 : 5.14E-05 :

+------------------------------------- ----------------------- - +------------------+

CHILD : 4.54E-05 : 4.54E-05 : 2.34E-17 : 4.54E-05 : 4.54E-05 : 4.54E-05 : 4.54E-05 : 4.54E-05 :

- S+------

- -------------------------------------- +------------------------------- +-----------------

INFANT : 2.61E-05 : 2.61E-05 : 1.85E-17 : 2.61E-05 : 2.61E-05 : 2.61E-05 : 2.61E-05 : 2.61E-05 :

- ---- ------------------- -+------------------- ----------------- --------------- +------------------+

IV- 7

TABLE IV-A- 4 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 4 RES AT 4.79 MILES ENE ANNUALBETAAIRDOSE = 4.70E-20 MILLRADS ANNUAL-GAMMAAIRDOSE = 1.58E-20 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

----- + -----------------

-+ - ------------ ----------------+

PLUME : 9.22E-21 : 9.22E-21 : 9.22E-21 : 9.22E-21 : 9.22E-21 : 9.22E-21 : 9.69E-21 : 2.60E-20 S--- --------------------------------------------------------- -+------------------ --------------- +

GROUND : 2.11E-19 : 2.11E-19 : 2.11E-19 : 2.11E-19 : 2.11E-19 : 2.11E-19 : 2.11E-19 : 2.57E-19

-- S---- ------------------------------------------------------ +----------------------------------+

INHAL : . :

ADULT 4.79E-06 4.79E-06 1.03E-18 4.79E-06 4.79E-06 4.79E-06 4.79E-06 4.79E-06 4 .+-------------------- +----------- -------- + -------------------

+ ----------------+

TEEN : 4.83E-06 : 4.83E-06 : 1.45E-18 : 4.83E-06 : 4.83E-06 : 4.83E-06 : 4.83E-06 : 4.83E-06

-- - +--------------------------------------------------------------------+-----------------+----------------- -+-----------------+

CHILD : 4.27E-06 : 4.27E-06 : 1.96E-18 : 4.27E-06 : 4.27E-06 : 4.27E-06 : 4.27E-06 : 4.27E-06

-- - +--------------------------------------------------------------------+-----------------+----------------- -+-----------------+

INFANT : 2.46E-06 : 2.46E-06 : 1.55E-18 : 2.46E-06 : 2.46E-06 : 2.46E-06 : 2.46E-06 : 2.46E-06

- -+--

+---------------------------+-----------------------------------+----------------- -+-----------------+

IV- 8 eeeeeeeeeeeee~eeeeee0 0 0 0 0 9 0 0eee

TABLE IV-A- 5 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 5 RES AT 4.67 MILES E ANNUAL BETA AIR DOSE = 7.22E-20 MILLRADS ANNUAL-GAMMAAIRDOSE = 2.43E-20 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

+------------------+------------------------------------

PLUME : 1.42E-20 : 1.42E-20 : 1.42E-20 : 1.42E-20 : 1.42E-20 : 1.42E-20 : 1.49E-20 : 3.99E-20

--- +---------------------------------+------------------+---------------+------------------------------------+------------------

GROUND : 3.48E-19 : 3.48E-19 : 3.48E-19 : 3.48E-19 : 3.48E-19 : 3.48E-19 : 3.48E-19 : 4.23E-19

-+---------------------------------------------------------------------+------------------------------------------------------+

INHAL ADULT 7.49E-06 7.49E-06 1.59E-18 7.49E-06 7.49E-06 7.49E-06 7.49E-06 7.49E-06

-+---------------------------------------------------------------------+------------------------ ------------------------------

TEEN 7.55E-06 : 7.55E-06 " 2.24E-18 : 7.55E-06 : 7.55E-06 : 7.55E-06 : 7.55E-06 : 7.55E-06 S+----------------------+------------------+ ------------------ +------------------+------------------+------------------+

CHILD : 6.67E-06 : 6.67E-06 : 3.03E-18 : 6.67E-06 : 6.67E-06 : 6.67E-06 : 6.67E-06 : 6.67E-06

--- +-------------------------------------------------------------------+------------------+------------------------------------

INFANT : 3.84E-06 : 3.84E-06 : 2.39E-18 : 3.84E-06 : 3.84E-06 : 3.84E-06 : 3.84E-06 : 3.84E-06

-+--

- +------------------+ ------------------------------------- + ---------------

+----------

IV- 9

TABLE IV-A- 6 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 6 RES AT 4.22 MILES ESE ANNUALBETAAIRDOSE = 7.05E-20 MILLRADS ANNUAL-GAMMAAIRDOSE = 2.37E-20 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

+ +------------------+

PLUME : 1.38E-20 : 1.38E-20 : 1.38E-20 : 1.38E-20 : 1.38E-20 : 1.38E-20 : 1.45E-20 : 3.90E-20

- -+--

-------------------------- +---------------------------------- ------------------- +

GROUND : 6.72E-19 : 6.72E-19 : 6.72E-19 : 6.72E-19 : 6.72E-19 : 6.72E-19 : 6.72E-19 : 8.16E-19

- -+--

-------------------------- +-----------------------------------+------------------

INHAL ADULT 6.89E-06 6.89E-06 1.55E-18 6.89E-06 6.89E-06 6.89E-06 6.89E-06 6.89E-06

++------------------------------------+ --------- - --------------- +

TEEN : 6.95E-06 : 6.95E-06 : 2.18E-18 : 6.95E-06 : 6.95E-06 : 6.95E-06 : 6.95E-06 : 6.95E-06

-+--

- ------------------- + -----------

4----------------------------------

- + --------------

+

CHILD : 6.14E-06 : 6.14E-06 : 2.96E-18 : 6.14E-06 : 6.14E-06 : 6.14E-06 : 6.14E-06 : 6.14E-06

------------------- +----------- -------- + ----------------- - - - -----------

+ -------------- +

INFANT : 3.53E-06 : 3.53E-06 : 2.33E-18 : 3.53E-06 : 3.53E-06 : 3.53E-06 : 3.53E-06 : 3.53E-06

- -+--

--------- + --------------------------------- +----------------- ------------------- +

IV-10 0 0 0 0 0

000 0*0 00 00 00 00 00 00 0 0 *0 0 0 0 0 00

TABLE IV-A- 7 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 7 RES AT 1.67 MILES SE ANNUAL BETA-AIR DOSE = 5.03E-19 MILLRADS ANNUAL-GAMMAAIRDOSE = 1.69E-19 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

+------------------+------------------+- - -------------------------

÷ PLUME : 9.85E-20 : 9.85E-20 : 9.85E-20 : 9.85E-20 : 9.85E-20 : 9.85E-20 : 1.04E-19 : 2.78E-19

-- - +----------------------------------------+--------------------------------------------+------------------ +------------------

GROUND . 1.26E-17 : 1.26E-17 : 1.26E-17 : 1.26E-17 : 1.26E-17 : 1.26E-17 : 1.26E-17 : 1.53E-17

-- - +-----------------------------------------+--------------------------------------------+----------------- ------------------- +

INHAL : : . . : :

ADULT 4.79E-05 4.79E-05 1.13E-17 4.79E-05 4.79E-05 4.79E-05 4.79E-05 4.79E-05

-- - +-------------------------------------------------+-----------------------------------+----------------- ------------------- +

TEEN 4.83E-05 : 4.83E-05 : 1.60E-17 : 4.83E-05 : 4.83E-05 : 4.83E-05 : 4.83E-05 : 4.83E-05

-- - +---------------------+---------------------------+------------------------------------+----------------- ------------------- +

CHILD : 4.27E-05 : 4.27E-05 : 2.17E-17 : 4.27E-05 : 4.27E-05 : 4.27E-05 : 4.27E-05 : 4.27E-05

--------------- + ---------------------------------------------------- +---------------

INFANT : 2.46E-OS : 2.46E-05 : 1.71E-17 : 2.46E-05 : 2.46E-05 : 2.46E-05 : 2.46E-05 : 2.46E-05

------------- -------------------------------------------------------------- +-----------------+

IV-ll

TABLE IV-A- 8 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 8 RES AT 0.65 MILES SSE ANNUALBETAAIRDOSE = 3.66E-18 MILLRADS ANNUALGAMMAAIRDOSE = 1.23E-18 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

-+--*4--------------------------------+--------------- ------------ +------------------------------+

PLUME : 7.18E-19 : 7.18E-19 : 7.18E-19 : 7.18E-19 : 7.18E-19 : 7.18E-19 : 7.54E-19 : 2.02E-18 :

+-----------------+---------------+--------------- --------------------------- +---------------+

GROUND : 1.58E-16 : 1.58E-16 : 1.58E-16 : 1.58E-16 : 1.58E-16 : 1.58E-16 : 1.58E-16 : 1.92E-16 :

-+--- - ---------------- +---------------+---------------------------+------------------------------+

INHAL : : . . :

ADULT 3.29E-04 :-3.29E-04 8.23E-17 3.29E-04 3.29E-04 3.29E-04.: 3.29E-04 3.29E-04

+ 4 +----------------------------- +--------------------------------------------

TEEN : 3.32E-04 : 3.32E-04 : 1.16E-16 : 3.32E-04 : 3.32E-04 : 3.32E-04 : 3.32E-04 : 3.32E-04 :

S+------------------------------+--------------- ---------------------------- +---------------+

CHILD : 2.94E-04 : 2.94E-04 : 1.57E-16 : 2.94E-04 : 2.94E-04 : 2.94E-04 : 2.94E-04 : 2.94E-04 :

- ++------------------+------------------------------ -------------------------------------------- +

INFANT : 1.69E-04 : 1.69E-04 : 1.24E-16 : 1.69E-04 : 1.69E-04 : 1.69E-04 : 1.69E-04 : 1.69E-04 :

S-------------------------------------+--------------- --------------------------------------------

IV-12 eeeeeeeeeeeeeeeeeeee0 0 0 0 0 0 0 0e

TABLE IV-A- 9 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 9 RES AT 0.73 MILES S ANNUAL BETA AIR DOSE = 1.88E-18 MILLRADS ANNUAL-GAMMAAIRDOSE = 6.33E-19 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

-+-+--------------------------------+---------------+--------------- +--------- --------------- +

PLUME : 3.69E-19 : 3.69E-19 : 3.69E-19 : 3.69E-19 : 3.69E-19 : 3.69E-19 : 3.88E-19 : 1.04E-18 :

S+-----------------+---------------+---------------+---+ ------------------------------ +-------

GROUND : 6.78E-17 : 6.78E-17 : 6.78E-17 : 6.78E-17 : 6.78E-17 : 6.78E-17 : 6.78E-17 : 8.24E-17 :

S+-------+-----------+---------------+---------------+---------------+---------------+---------------+---------------+

INHAL :

ADULT 1.71E-04 1.71E-04 4.30E-17 1.71E-04 1.71E-04 1.71E-04 1.71E-04 1.71E-04 S++--

+---------------+-

- ----------------------- +-------------+

TEEN : 1.72E-04 : 1.72E-04 : 6.05E-17 : 1.72E-04 : 1.72E-04 : 1.72E-04 : 1.72E-04 : 1.72E-04 :

+-----------------+---------------+---------------

f - ------------------------------ + +-------

CHILD : 1.52E-04 : 1.52E-04 : 8.21E-17 : 1.52E-04 : 1.52E-04 : 1.52E-04 : 1.52E-04 : 1.52E-04 :

+--+-+ --------------- +------------------------------++ - ----------------------- +---------------+

INFANT : 8.75E-05 : 8.75E-05 : 6.48E-17 : 8.75E-05 : 8.75E-05 : 8.75E-05 : 8.75E-05 : 8.75E-05 :

f 4--------------------------------+---------------...------------------------+---------------+

IV-13

TABLE IV-A-10 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 10 RES AT 0.65 MILES SSW ANNUALBETAAIRDOSE = 1.13E-18 MILLRADS ANNUAL-GAMMA AIR DOSE = 3.80E-19 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

-+*

- - ------------------------------- +---------------+------------------------------+

PLUME : 2.22E-19 : 2.22E-19 : 2.22E-19 : 2.22E-19 : 2.22E-19 : 2.22E-19 : 2.33E-19 : 6.25E-19 :

-- +-----------------------------------+---------------+---------------+--------------------------+

GROUND : 2.73E-17 : 2.73E-17 : 2.73E-17 : 2.73E-17 : 2.73E-17 : 2.73E-17 : 2.73E-17 : 3.31E-17 S+-------+-----------+---------------+---------------+---------------+---------------+---------------+---------------+

INHAL ADULT 1.02E-04 1.02E-04 2.60E-17 1.02E-04 1.02E-04 1.02E-04 1.02E-04 1.02E-04

--- +-------------------------------+------------------------------+------------------------------+

TEEN : 1.03E-04 : 1.03E-04 : 3.65E-17 : 1.03E-04 : 1.03E-04 : 1.03E-04 : 1.03E-04 : 1.03E-04 S+-------+-----------+---------------+---------------+---------------+---------------+---------------+:---------------+

CHILD : 9.07E-05 : 9.07E-05 : 4.96E-17 : 9.07E-05 : 9.07E-05 : 9.0 7E-05 : 9.07E-05 : 9.07E-05 S+-------+-----------+---------------+---------------+---------------+---------------+---------------+---------------+

INFANT : 5.22E-05 : 5.22E-05 : 3.91E-17 : 5.22E-05 : 5.22E-05 : 5.22E-05 : 5.22E-05 : 5.22E-05

-+-------+-----------+---------------+---------------+---------------+---------------+---------------+---------------+

IV-14 ooooooooooo9ooooooo*ooo ooooooooooooooooooo

@O@@*O@~Oeeee*eeeeeeeseeeeeeIOOOeO@eeoeeeee TABLE IV-A-11 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 11 RES AT 0.73 MILES SW ANNUAL BETA AIR DOSE = 1.25E-18 MILLRADS ANNUAL-GAMMAAIRDOSE = 4.20E-19 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN S+-------+-----------+---------------+---------------+---------------+---------------+---------------+---------------+

PLUME : 2.45E-19 : 2.45E-19 : 2.45E-19 : 2.45E-19 : 2.45E-19 : 2.45E-19 : 2.58E-19 : 6.91E-19 S+-------+-----------+---------------+---------------+---------------+---------------+---------------+---------------+

GROUND : 1.95E-17 : 1.95E-17 : 1.95E-17 : 1.95E-17 : 1.95E-17 : 1.95E-17 : 1.95E-17 : 2.37E-17 S+-------+-----------+---------------+---------------+---------------+---------------+---------------+---------------+

INHAL : : . : . :

ADULT 1.14E-04 1.14E-04 2.86E-17 1.14E-04 1.14E-04 1.14E-04 1.14E-04 1.14E-04

......... +..--.----. --- -- +-...------------------------------ +------- ------------------------------

TEEN : 1.15E-04 : 1.15E-04 : 4.03E-17 : 1.15E-04 : 1.15E-04 : 1.15E-04 : 1.15E-04 : 1.15E-04 S+------------------+---- --- + -------------- ----------------... +-------------------------+

CHILD : 1.01E-04 : 1.01E-04 : 5.47E-17 : 1.01E-04 : 1.01E-04 : 1.01E-04 : 1.01E-04 : 1.01E-04

-- -+------------------+---------------+---------------+----------------------------------------+

INFANT : 5.83E-05 : 5.83E-05 : 4.31E-17 : 5.83E-05 : 5.83E-05 : 5.83E-05 : 5.83E-05 : 5.83E-05

--- *------------------+---------------+---------------+--- -+------- ------------------------------

IV- 15

TABLE IV-A-12 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 12 RES AT 1.06 MILES WSW ANNUALBETAAIRDOSE = 1.15E-18 MILLRADS ANNUAL-GAMMAAIRDOSE = 3.88E-19 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

-+--------------------------- + ------------------------------------------------- +-----------------+

PLUME : 2.26E-19 : 2.26E-19 : 2.26E-19 : 2.26E-19 : 2.26E-19 : 2.26E-19 : 2.38E-19 : 6.38E-19

-+--------------------------- + ---------------------------- -+------------------+------------------+

GROUND : 1.01E-17 : 1.01E-17 : 1.01E-17 : 1.01E-17 : 1.01E-17 : 1.01E-17 : 1.01E-17 : 1.23E-17

- - ------------------------------------------------------ --------------- +------------------+

INHAL ADULT 1.08E-04 1.08E-04 2.64E-17 1.08E-04 1.08E-04 1.08E-04 1.08E-04 1.08E-04

-+----------- +--------------+ -------------------------------------------------- +-----------------+

TEEN : 1.09E-04 : 1.09E-04 : 3.71E-17 : 1.09E-04 : 1.09E-04 : 1.09E-04 : 1.09E-04 : 1.09E-04

- -+--

+----------------- ------------------- +

CHILD : 9.61E-05 : 9.61E-05 : 5.04E-17 : 9.61E-05 : 9.61E-05 : 9.61E-05 : 9.61E-05 : 9.61E-05

- -+--

+----------------- ------------------- +

INFANT : 5.53E-05 : 5.53E-05 : 3.98E-17 : 5.53E-05 : 5.53E-05 : 5.53E-05 : 5.53E-05 : 5.53E-05

- - - -------------------- +------------------+------------------------------- -----------------+

IV-16 0 0 0o0o 0e 0 0 0 00 0 oo 0

0 00 oo 0o 0 0 0 00 0

TABLE IV-A-13 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 13 RES AT 1.20 MILES W ANNUALBETAAIRDOSE = 7.84E-19 MILLRADS ANNUAL--GAMMAAIRDOSE = 2.64E-19 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

- ----------------- +---------------+----------------------------- +f

--------------- +

PLUME 1.54E-19 : 1.54E-19 : 1.54E-19 : 1.54E-19 : 1.54E-19 : 1.54E-19 : 1.62E-19 : 4.33E-19 S+ --------------------------------

+-----------------------------+----+------------------------

GROUND : 1.02E-17 : 1.02E-17 : 1.02E-17 : 1.02E-17 : 1.02E-17 : 1.02E-17 : 1.02E-17 : 1.24E-17

........-------------------------------------------- +------------------------------++-------------

INHAL ADULT 7.19E-05 7.19E-05 1.79E-17 7.19E-05 7.19E-05 7.19E-05 7.19E-05 7.19E-05 S+-------+-----------+---------------+---------------+---------------+---------------+---------------+---------------+

TEEN : 7.25E-05 : 7.25E-05 : 2.51E-17 : 7.25E-05 : 7.25E-05 : 7.25E-05 : 7.25E-05 : 7.25E-05 S+-----------------+----------------------------- ++--------------------------+---------------+

CHILD : 6.40E-05 : 6.40E-05 ý 3.41E-17 : 6.40E-05 : 6.40E-05 : 6.40E-05 : 6.40E-05 : 6.40E-05

-- ------------------- +----------------------------+----------------+----------- --------------- +

INFANT : 3.68E-05 : 3.68E-05 : 2.69E-17 : 3.68E-05 : 3.68E-05 : 3.68E-05 : 3.68E-05 : 3.68E-05 S+-------------------4+---------------------------- +---------------++

-+------------------------

IV-17

TABLE IV-A-14 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 14 RES AT 2.27 MILES WNW ANNUAL BETA AIR DOSE = 1.96E-19 MILLRADS ANNUAL-GAMMAAIRDOSE = 6.58E-20 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

-+-+- --------------------------------------------------------------- +--------------------------- +

PLUME : 3.84E-20 : 3.84E-20 : 3.84E-20 : 3.84E-20 : 3.84E-20 : 3.84E-20 : 4.03E-20 : 1.08E-19

-- +---------------------------------------------------------------+------------------------------+

GROUND : 2.93E-18 : 2.93E-18 : 2.93E-18 : 2.93E-18 : 2.93E-18 : 2.93E-18 : 2.93E-18 : 3.56E-18

-+-------+-----------+---------------+---------------+---------------+---------------+---------------+---------------+

INHAL : : . . . .

ADULT 1.83E-05 1.83E-05 4.34E-18 1.83E-05 1.83E-05 1.83E-05 1.83E-05 1.83E-05

+-+-----------------------------------+---------------------------+------------------------------+

TEEN ; 1.84E-05 : 1.84E-05 : 6.10E-18 : 1.84E-05 : 1.84E-05 : 1.84E-05 : 1.84E-05 : 1.84E-05

-+ -----------------------------------------------------------------------------------------

÷ + +

CHILD : 1.63E-05 : 1.63E-05 : 8.28E-18 : 1.63E-05 : 1.63E-05 : 1.63E-05 : 1.63E-05 : 1.63E-05

+ + +--------------- ------------- +------------------------------+

INFANT : 9.36E-06 : 9.36E-06 : 6.53E-18 : 9.36E-06 : 9.36E-06 : 9.36E-06 : 9.36E-06 : 9.36E-06

-+-+----------------------------------+--------------- +------------------------------------------+

IV-18 00 0 00 0 0 00 0 0 000 900 0 0 00 0 0 00 0 0

- OeeOS*O@@@@S@@O@@@ee@*eefee@.@.@@@@@@e@@eg TABLE IV-A-15 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 15 RES AT 2.40 MILES NW ANNUAL BETA AIR DOSE = 1.99E-19 MILLRADS ANNUAL-GAMMAAIRDOSE = 6.69E-20 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN S+ ----------------------- + +------------------+-------------------------------+-----------------

PLUME : 3.90E-20 : 3.90E-20 : 3.90E-20 : 3.90E-20 : 3.90E-20 : 3.90E-20 : 4.10E-20 : 1.10E-19

+----- - - - - -------------------------------------- +---------- -+------------------------------------+

GROUND : 4.53E-18 : 4.53E-18 : 4.53E-18 : 4.53E-18 : 4.53E-18 : 4.53E-18 : 4.53E-18 : 5.50E-18

-- - +-------------------------------------------------------------------------------------+----------------- ------------------- +

INHAL : . . :

ADULT 1.86E-05 1.86E-05 4.38E-18 1.86E-05 1.86E-05 1.86E-05 1.86E-05 1.86E-05

-+---------------------------+------------------+------------------+------------------+ -+-------------------------------+

TEEN : 1.87E-05 : 1.87E-05 : 6.15E-18 : 1.87E-05 : 1.87E-05 : 1.87E-05 : 1.87E-05 : 1.87E-05

-- - +-------------------------------------------------------------------------------------+----------------- ------------------- +

CHILD : 1.65E-05 : 1.65E-05 : 8.35E-18 : 1.65E-05 : 1.65E-05 : 1.65E-05 : 1.65E-05 : 1.65E-05

+ * ------------------

+------------------ +---------- -+------------------------------------+

INFANT : 9.52E-06 : 9.52E-06 : 6.59E-18 : 9.52E-06 : 9.52E-06 : 9.52E-06 : 9.52E-06 : 9.52E-06 S+ ---- .. +------------------+-------------------------------------------------------------------+

IV-19

TABLE IV-A-16 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 16 RES AT 2.08 MILES NNW ANNUAL BETA-AIR DOSE = 3.03E-19 MILLRADS ANNUAL-GAMMAAIRDOSE = 1.02E-19 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

-+

4-------------------------------+--------------- +-------------------------------------------

PLUME : 5.93E-20 : 5.93E-20 : 5.93E-20 : 5.93E-20 : 5.93E-20 : 5.93E-20 : 6.23E-20 : 1.67E-19

-+--+----------------+------------------------------+------------------------------+---------------

GROUND : 9.07E-18 : 9.07E-18 : 9.07E-18 : 9.07E-18 : 9.07E-18 : 9.07E-18 : 9.07E-18 : 1.10E-17

-+-------+-----------+---------------+---------------+---------------+---------------+---------------+---------------+

INHAL : : : :

ADULT 2.82E-05 2.82E-05": 6.71E-18 2.82E-05 2.82E-05 2.82E-05 2.82E-05 2.82E-05

- +--------------------------------+--------------- +-------------------------------------------+

TEEN : 2.84E-05 : 2.84E-05 : 9.44E-18 : 2.84E-05 : 2.84E-05 : 2.84E-05 : 2.84E-05 : 2.84E-05 S+-------------+- - -- - -------------------------------- +-------------------------------------------+

CHILD : 2.51E-05 : 2.51E-05 : 1.28E-17 : 2.51E-05 : 2.51E-05 : 2.51E-05 : 2.51E-05 : 2.51E-05

+-+- ------------------ --------------

+---------------- +---------------------------+---------------+

INFANT : 1.44E-05 : 1.44E-05 : 1.01E-17 : 1.44E-05 : 1.44E-05 : 1.44E-05 : 1.44E-05 : 1.44E-05 S+-----------------+---------------+---------------+- --------------------- ------------------ +

IV-20

@O@@OS*Oeeeee@ee@eOOeeOee@*eeOee@@@@eeeeeee TABLE IV-A-17 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 17 VEG AT 1.59 MILES NE ANNUAL BETA-AIR DOSE = 5.03E-19 MILLRADS ANNUAL-GAMMAAIRDOSE = 1.69E-19 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

+----------- -------------- -+-+------------------+--------------------------------+----------------

PLUME : 9.85E-20 : 9.85E-20 : 9.85E-20 : 9.85E-20 : 9.85E-20 : 9.85E-20 : 1.04E-19 : 2.78E-19

-- - +----------------------+---------------------------+-----------------------------------+----------------- ------------------- +

GROUND : 4.46E-18 : 4.46E-18 : 4.46E-18 : 4.46E-18 : 4.46E-18 : 4.46E-18 : 4.46E-18 : 5.42E-18

-+-- ------------------------------------------- +------------------

- +4 ------------- +------------

VEGET . . . . . .

ADULT 8.68E-05 8.68E-05 6.08E-17 8.68E-05 8.68E-05 8.68E-05 8.68E-05 8.68E-05

_+------------ ------------- +-+------------------+---------- -+------------------+-----------------+

TEEN : 9.93E-05 : 9.93E-05 : 8.78E-17 : 9.93E-05 : 9.93E-05 : 9.93E-05 : 9.93E-05 : 9.93E-05

+----------- -------------- -+-+------------------+------------------------------- ----------------+

CHILD : 1.54E-04 : 1.54E-04 : 2.02E-16 i 1.54E-04 : 1.54E-04 : 1.54E-04 : 1.54E-04 : 1.54E-04

-- -- - -------------------- +---------------------------+------------------------------------+----------------- ------------------- +

IV-21

TABLE IV-A-18 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 18 VEG AT 4.79 MILES ENE ANNUALBETAAIRDOSE = 4.70E-20 MILLRADS ANNUAL-GAMMAAIRDOSE = 1.58E-20 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

-+------------------------+------------------+------------------+"+ ---------------- 4----------

PLUME : 9.22E-21 : 9.22E-21 : 9.22E-21 : 9.22E-21 : 9.22E-21 : 9.22E-21 : 9.69E-21 : 2.60E-20

--- -+----------------------- +-----------------+- ----------------- - ------------

+- ----------------

GROUND : 2.11E-19 : 2.11E-19 : 2.11E-19 : 2.11E-19 : 2.11E-19 : 2.11E-19 : 2.11E-19 : 2.57E-19

- -+--

+-----------------+----------------- -+-----------------+

VEGET : . . . :

ADULT 8.68E-06 8.68E-06 2.88E-18 8.68E-06 8.68E-06 8.68E-06 8.68E-06 8.68E-06

. . . +. -+.------------------

. . . ..-- +...------------------+-----+--+-----------------..+----------- -+----------------+

TEEN : 9.93E-06 : 9.93E-06 : 4.15E-18 : 9.93E-06 : 9.93E-06 : 9.93E-06 : 9.93E-06 : 9.93E-06

. . +------ -+*------------------ ---------- ------------------------ +------------ +--------------

CHILD : 1.54E-05 : 1.54E-05 : 9.54E-18 : 1.54E-05 : 1.54E-05 : 1.54E-05 : 1.54E-05 : 1.54E-05

-+++----------------------------------------------------------+-----------------------------------

IV-22 OOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOO0 00 0 0

TABLE IV-A-19 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 19 VEG AT 1.74 MILES SE ANNUAL BETA AIR DOSE = 4.69E-19 MILLRADS ANNUAL-GAMMAAIRDOSE = 1.58E-19 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

-+---------------------------------------------------------------------+------------------+------------------+-----------------+

PLUME : 9.20E-20 : 9.20E-20 : 9.20E-20 : 9.20E-20 : 9.20E-20 : 9.20E-20 : 9.67E-20 : 2.59E-19

-+---------------------------------------------------------------------+------------------+------------------+-----------------+

GROUND : 1.18E-17 : 1.18E-17 : 1.18E-17 : 1.18E-17 : 1.18E-17 : 1.18E-17 : 1.18E-17 : 1.43E-17

-+-----------------------------------+------------------+---------------+------------------+------------------+-----------------+

VEGET ADULT 8.14E-05 8.14E-05 1.60E-16 8.14E-05 8.14E-05 8.14E-05 8.14E-05 8.14E-05

- ------- + +------------------------------------

TEEN . 9.31E-05 : 9.31E-05 : 2.32E-16 : 9.31E-05 : 9.31E-05 : 9.31E-05 : 9.31E-05 : 9.31E-05 S------------------------------------------------------+------------------ ------ +------------------+

CHILD : 1.45E-04 : 1.45E-04 : 5.33E-16 : 1.45E-04 : 1.45E-04 : 1.45E-04 : 1.45E-04 : 1.45E-04

" ----------------------------------------- +-- + ----------------- - -----------

+--+ --------------- +

IV-23

TABLE IV-A-20 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 20 VEG AT 0.94 MILES SSE ANNUALBETAAIRDOSE = 1.57E-18 MILLRADS ANNUAL-GAMMAAIRDOSE = 5.27E-19 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

*---------------------------------+--------------- +----------------------++-------------

PLUME : 3.07E-19 : 3.07E-19 : 3.07E-19 : 3.07E-19 : 3.07E-19 : 3.07E-19 : 3.23E-19 : 8.67E-19 :

-------------------------------- +--------------- +4 +----------------------+-------------+

GROUND : 7.01E-17 : 7.01E-17 : 7.01E-17 : 7.01E-17 : 7.01E-17 : 7.01E-17 : 7.01E-17 : 8.51E-17 :

-+-------+-----------+---------------+---------------+---------------+---------------+---------------+---------------+

VEGET : . : . : :

ADULT 2.60E-04 2.60E-04 9.53E-16 2.60E-04 2.60E-04 2.60E-04 2.60E-04 2.60E-04

+ + ---------------------- -------------- +

TEEN : 2.98E-04 : 2.98E-04 : 1.38E-15 : 2.98E-04 : 2.98E-04 : 2.98E-04 : 2.98E-04 : 2.98E-04 :

S-------------------------------------+---------------+--------------- +------------------------- +

CHILD : 4.63E-04 : 4.63E-04 : 3.16E-15 : 4.63E-04 : 4.63E-04 : 4.63E-04 : 4.63E-04 : 4.63E-04 :

--+ - -- +------------------------------+---------------+--+ -- ------------------------------ +-------

IV-24 000 0 0 00 0 0 10 0 00 0 0

0 00 0 0 0 0 00 0 0

@S@O@OOOeOeee@@eeeeeeeOeee@@eeeeeOeeeeeeee@

TABLE IV-A-21 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 21 VEG AT 2.60 MILES S ANNUAL BETA-AIR DOSE = 8.21E-20 MILLRADS ANNUAL-GAMMAAIRDOSE = 2.76E-20 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

++----------- -------------- +-+------------------------------ -+-----------------------------------+

PLUME 1.61E-20 : 1.61E-20 : 1.61E-20 : 1.61E-20 : 1.61E-20 : 1.61E-20 1.69E-20 : 4.54E-20

-+------------------+-----------------+

GROUND : 2.48E-18 : 2.48E-18 : 2.48E-18 : 2.48E-18 : 2.48E-18 : 2.48E-18 : 2.48E-18 : 3.01E-18

-+-----------------------------------+

VEGET ADULT 1.41E-05 1.41E-05 3.37E-17 1.41E-05 1.41E-05 1.41E-05 1.41E-05 1.41E-05

------------------------------------------------------ +

TEEN : 1.61E-05 : 1.61E-05 : 4.87E-17 : 1.61E-05 : 1.61E-05 : 1.61E-05 : 1.61E-05 : 1.61E-05

-+ L ---------------------------- +------------------------------------ - ------------ +---------------

CHILD : 2.51E-05 : 2.51E-05 : 1.12E-16 : 2.51E-05 : 2.51E-05 : 2.51E-05 : 2.51E-05 : 2.51E-05

-- - +---------------------+---------------------------+------------------------------------+----------------- ------------------- +

IV-25

TABLE IV-A-22 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 22 VEG AT 2.00 MILES SSW ANNUALBETAAIRDOSE = 8.03E-20 MILLRADS ANNUAL_-GAMMAAIRDOSE = 2.70E-20 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

- -+-

+-----------------------------------

++-- ---------------

+ +----------

PLUME : 1.57E-20 : 1.57E-20 : 1.57E-20 : 1.57E-20 : 1.57E-20 : 1.57E-20 : 1.65E-20 : 4.44E-20 :

-+-+------------------------+-----------------------------------+* - ----------- --------------- +

GROUND : 1.78E-18 : 1.78E-18 : 1.78E-18 : 1.78E-18 : 1.78E-18 : 1.78E-18 : 1.78E-18 : 2.17E-18 :

-------------------- +------------------------------------

+ --------------- +

VEGET : :

ADULT 1.36E-05 1.36E-05 2.43E-17 1.36E-05 1.36E-05 1.36E-05 1.36E-05 1.36E-05

+---------------------+------------------+-------------------+-------

÷ 7 - ------------------------ +

TEEN : 1.55E-05 : 1.55E-05 : 3.51E-17 : 1.55E-05 : 1.55E-05 : 1.55E-05 : 1.55E-05 : 1.55E-05 :

++--- ----------------- ------------------------------------- -----------

+ ------------------- +

CHILD : 2.41E-05 : 2.41E-05 : 8.06E-17 : 2.41E-05 : 2.41E-05 : 2.41E-05 : 2.41E-05 : 2.41E-05 :

-+------------------------- +------------------------------------ - -----------

+ ------------------- +

IV-26 00 o 0 00 00 0 00o00 0 0 00 00 0 o9 00 00 0o 0o00 00 0o 0

TABLE IV-A-23 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 23 VEG AT 0.73 MILES SW ANNUAL BETA-AIR DOSE = 1.25E-18 MILLRADS ANNUAL-GAMMAAIRDOSE = 4.20E-19 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

-- - +------------------------------+------------------------------------------------------+----------------- ------------------- +

PLUME : 2.45E-19 : 2.45E-19 : 2.45E-19 : 2.45E-19 : 2.45E-19 : 2.45E-19 : 2.58E-19 : 6.91E-19

-+--------------------------------------------------- -------------------------- +------------------

GROUND : 1.95E-17 : 1.95E-17 : 1.95E-17 : 1.95E-17 : 1.95E-17 : 1.95E-17 : 1.95E-17 : 2.37E-17

-- - +---------------------+---------------------------+------------------------------------+----------------- ------------------- +

VEGET : : . : : :

ADULT 2.06E-04 2.06E-04 2.65E-16 2.06E-04 2.06E-04 2.06E-04 2.06E-04 2.06E-04

-- - +---------------------+---------------------------+------------------------------------+----------------- ------------------- +

TEEN -: 2.36E-04 : 2.36E-04 : 3.83E-16 : 2.36E-04 : 2.36E-04 : 2.36E-04 : 2.36E-04 : 2.36E-04 CH LD :3.6----- ------------------ 0- ----------------------

0-- 04-.------------------------------------

CHILD :3.66E-04 :3.66E-04 :8.80E-16 :3.66E-04 :3.66E-04 :3.66E-04 :3.66E-04 :3.66E-04

-- - +-----------+- ---------------------------- +------------------------------------+----------------- ------------------- +

IV-27

TABLE IV-A-24 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 24 VEG AT 1.21 MILES WSW ANNUALBETAAIRDOSE = 7.88E-19 MILLRADS ANNUAL-GAMMAAIRDOSE = 2.65E-19 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID. LUNG SKIN

-+---------------------------- - ----------------- +-------------+----------------------------------+

PLUME : 1.54E-19 : 1.54E-19 : 1.54E-19 : 1.54E-19 : 1.54E-19 : 1.54E-19 : 1.62E-19 : 4.35E-19

-- +------------------ ------------------ - - ------------------- ++---- ---------------

+----------

GROUND : 6.58E-18 : 6.58E-18 : 6.58E-18 : 6.58E-18 : 6.58E-18 : 6.58E-18 : 6.58E-18 : 7.99E-18

- -+--

+------------------------------------------- ------------------ -+-----------------+

VEGET : : : . :

ADULT 1.36E-04 1.36E-04 8.95E-17 1.36E-04 1.36E-04 1.36E-04.: 1.36E-04 1.36E-04 S+--------------------------------------+----------------------------- - -------------

+

TEEN : 1.55E-04 : 1.55E-04 : 1.29E-16 : 1.55E-04 : 1.55E-04 : 1.55E-04 : 1.55E-04 : 1.55E-04

-- - +-----------------------------------------+--------------------------------------------+----------------- -+-----------------+

CHILD : 2.41E-04 : 2.41E-04 : 2.97E-16 : 2.41E-04 : 2.41E-04 : 2.41E-04 : 2.41E-04 : 2.41E-04

- -+--

------------------- +

IV-28 0 0 00 0 00 0 00 0 0* 0 0* 0 00 0 00 0 00 0 00 0

@@@@S@@e@@@sOeeeeeOeeeeeeeeeOeee@@eeeOeeOee TABLE IV-A-25 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 25 VEG AT 1.30 MILES W ANNUAL BETA-AIR DOSE = 6.18E-19 MILLRADS ANNUAL-GAMMAAIRDOSE = 2.08E-19 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

- +- --------------------- +--------------------------------------------------- +----------------

PLUME : 1.21E-19 : 1.21E-19 : 1.21E-19 : 1.21E-19 : 1.21E-19 : 1.21E-19 : 1.27E-19 : 3.41E-19

++-----------------------+--------------------------------------------------- +----------------

GROUND : 8.06E-18 : 8.06E-18 : 8.06E-18 : 8.06E-18 : 8.06E-18 : 8.06E-18 : 8.06E-18 : 9.78E-18

-- - +------------------------------- ------------------------------------- +-----------------+----------------- -+-----------------+

VEGET ADULT 1.03E-04 1.03E-04 1.10E-16 1.03E-04 1.03E-04 1.03E-04 1.03E-04 1.03E-04

--- +--+ ------------------- +------------------4------------------+-- - - - --------- ------------------

TEEN : 1.18E-04 : 1.18E-04 : 1.58E-16 : 1.18E-04 : 1.18E-04 : 1.18E-04 : 1.18E-04 : 1.18E-04 S+---------------------+------------------+-----------------+4 - ------------------------- +

CHILD : 1.83E-04 : 1.83E-04 : 3.64E-16 : 1.83E-04 : 1.83E-04 : 1.83E-04 : 1.83E-04 : 1.83E-04 S+ - ----------------------- +--------------------------------------------------- +----------------

IV-29

TABLE IV-A-26 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 26 VEG AT 2.27 MILES WNW ANNUALBETAAIRDOSE = 1.96E-19 MILLRADS ANNUAL-GAMMAAIRDOSE = 6.58E-20 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

+------------------+-----------------+-----------------+----------------- -+-----------------+

PLUME : 3.84E-20 : 3.84E-20 : 3.84E-20 : 3.84E-20 : 3.84E-20 : 3.84E-20 : 4.03E-20 : 1.08E-19 :

- -+--

+------------------+-----------------+-----------------+----------------- -+-----------------+

GROUND : 2.93E-18 : 2.93E-18 : 2.93E-18 : 2.93E-18 : 2.93E-18 : 2.93E-18 : 2.93E-18 : 3.56E-18 :

- -+--

+-----------------+----------------- -+-----------------+

VEGET : : . . . :

ADULT 3.31E-05 3.31E-05 3.99E-17 3.31E-05 3.31E-05 3.31E-05 3.31E-05 3.31E-05

- -+--

+-----------------+----------------- -+-----------------+

TEEN : 3.78E-05 : 3.78E-05 : 5.76E-17 : 3.78E-05 : 3.78E-05 : 3.78E-05 : 3.78E-05 : 3.78E-05 :

-- - +-------------------------------------------------------------------+------------------+----------------- -+-----------------+

CHILD : 5.88E-05 : 5.88E-05 : 1.32E-16 : 5.88E-05 : 5.88E-05 : 5.88E-05 : 5.88E-05 : 5.88E-05 :

-+---

+ +---------------------------------------------------------------------

IV-30 OOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOO*O0 00 0 e0 0

TABLE IV-A-27 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 27 VEG AT 2.40 MILES NW ANNUAL BETA-AIR DOSE = 1.99E-19 MILLRADS ANNUAL-GAMMAAIRDOSE = 6.69E-20 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

+ ---------------------------------------- +--------- -+----------------------------------+

PLUME : 3.90E-20 : 3.90E-20 : 3.90E-20 : 3.90E-20 : 3.90E-20 : 3.90E-20 : 4.10E-20 : 1.10E-19

--------------------- -+ - ----------- ----------------

GROUND : 4.53E-18 : 4.53E-18 : 4.53E-18 : 4.53E-18 : 4.53E-18 : 4.53E-18 : 4.53E-18 : 5.50E-18

- -+--

+--------+--------------------------+-----------------+----------------- -+-----------------+

VEGET : :

ADULT 3.36E-05 3.36E-05 6.16E-17 3.36E-05 3.36E-05 3.36E-05 3.36E-05 3.36E-05

- -+--

+------------------+----------------- -+-----------------+

TEEN : 3.85E-05 : 3.85E-05 : 8.90E-17 : 3.85E-05 : 3.85E-05 : 3.85E-05 : 3.85E-05 : 3.85E-05

-+--+---------------------------------------- +- ------------------ + ---------------

+ +----------

CHILD : 5.98E-05 : 5.98E-05 : 2.05E-16 : 5.98E-05 : 5.98E-05 : 5.98E-05 : 5.98E-05 : 5.98E-05

- -+--

+-----------------+----------------- -+-----------------+

IV-31

TABLE IV-A-28 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 28 VEG AT 3.73 MILES NNW ANNUALBETAAIRDOSE = 8.21E-20 MILLRADS ANNUAL-GAMMAAIRDOSE = 2.76E-20 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

------------------ - - ------------------ +---- + ---------------

4 +-----------

PLUME : 1.61E-20 : 1.61E-20 : 1.61E-20 : 1.61E-20 : 1.61E-20 : 1.61E-20 ; 1.69E-20 : 4.54E-20 :

+----- - - - - ------------------------------------------------------ +------------------ ---------------

GROUND : 2.OOE-18 : 2.OOE-18 : 2.OOE-18 : 2.OOE-18 : 2.OOE-18 : 2.OOE-18 : 2.OOE-18 : 2.43E-18 :

S+---------------------+------------------ ---- +----------------- - ------------

+ ----------------

+

VEGET . . . : : . :

ADULT 1.41E-05 1.41E-05 2.72E-17 1.41E-05 1.41E-05 1.41E-05 1.41E-05 1.41E-05

+--------------------+------------------ ---- - - ------------------ +"l ÷ 4------------------------

TEEN : 1.61E-05 : 1.61E-05 : 3.94E-17 : 1.61E-05 : 1.61E-05 : 1.61E-05 : 1.61E-05 : 1.61E-05 :

-- - +--------------------------------------------------------------------+---------------------------------- ------------------- +

CHILD : 2.51E-05 : 2.51E-05 : 9.05E-17 : 2.51E-05 : 2.51E-05 : 2.51E-05 : 2.51E-05 : 2.51E-05 :

- ------------------- +-----------------+---- +++ ---------------- 4----------- ----------------- +

IV-32 OOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOO*OOOOOOOO 00 0 00 0

TABLE IV-A-29 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 29 BEEF AT 4.91 MILES E ANNUAL BETA AIR DOSE = 6.72E-20 MILLRADS ANNUAL-GAMMAAIRDOSE = 2.26E-20 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

-+-----------

+------------------+

++---------

PLUME : 1.32E-20 : 1.32E-20 : 1.32E-20 : 1.32E-20 : 1.32E-20 : 1.32E-20 : 1.38E-20 : 3.71E-20

+-- ------------------------------------- +----+-+-----------------+- ---------------

+----------

GROUND : 3.01E-19 : 3.01E-19 : 3.01E-19 : 3.01E-19 : 3.01E-19 : 3.01E-19 : 3.01E-19 : 3.65E-19

- +-+-+------------------+-------------------------------- --------------- +------------------+

MEAT : : . . :

ADULT 1.79E-06 1.79E-06 1.84E-19 1.79E-06 1.79E-06 1.79E-06 1.79E-06 1.79E-06

+--- - - - - - ------------------------------------------------------- -----------

+-+--- --------------- +

TEEN : 1.07E-06 : 1.07E-06 : 1.53E-19 : 1.07E-06 : 1.07E-06 : 1.07E-06 : 1.07E-06 : 1.07E-06

--- +--------------------+- ----------------

4------------------ + + ---------------

+ +----------

CHILD : 1.29E-06 : 1.29E-06 : 2.84E-19 : 1.29E-06 : 1.29E-06 : 1.29E-06 : 1.29E-06 : 1.29E-06

+----------------------------------------+----+ ----------------- -----------

+--+-- --------------- +

IV-33

TABLE IV-A-30 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 30 BEEF AT 1.82 MILES SSE ANNUAL BETA-AIR DOSE = 3.27E-19 MILLRADS ANNUAL-GAMMAAIRDOSE = 1.10E-19 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

-- -- - ------------------------------------------------------------------- +-----------------+----------------- -+-----------------+

PLUME 6.41E-20 : 6.41E-20 : 6.41E-20 : 6.41E-20 : 6.41E-20 : 6.41E-20 : 6.74E-20 : 1.81E-19

-- - +---------------+----------------------------------------------------+-----------------+----------------- -+-----------------+

GROUND : 1.37E-17 : 1.37E-17 : 1.37E-17 : 1.37E-17 : 1.37E-17 : 1.37E-17 : 1.37E-17 : 1.67E-17

-- -- - ------------------------ :-------------------------------------------+-----------------+----------------- -+-----------------+

MEAT : : : : :

ADULT 7.80E-06 7.80E-06 8.43E-18 7.80E-06 7.80E-06 7.80E-06 7.80E-06 7.80E-06

-+-------------------------------------------- + -------------------------------- -+----------------+

TEEN : 4.65E-06 : 4.65E-06 : 7.01E-18 : 4.65E-06 : 4.65E-06 : 4.65E-06 : 4.65E-06 : 4.65E-06

+--- --- +- - ------------------ +-----------------------------------+4--------- ----------------

CHILD : 5.63E-06 : 5.63E-06 : 1.30E-17 : 5.63E-06 : 5.63E-06 : 5.63E-06 : 5.63E-06 : 5.63E-06

-+----------- --------------- ------------------ +---------------------------- +------------------+

IV-34

0000000000000000900000000000000000000000000o TABLE IV-A-31 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 31 BEEF AT 2.60 MILES S ANNUAL BETA AIR DOSE = 8.21E-20 MILLRADS ANNUAL-GAMMAAIRDOSE = 2.76E-20 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

+----+ ----------------- - ----------

+-

+----------------

PLUME : 1.61E-20 : 1.61E-20 : 1.61E-20 : 1.61E-20 : 1.61E-20 : 1.61E-20 : 1.69E-20 : 4.54E-20

-+--4+------------------+----------------------- ---------------- +----------------+----------------

GROUND : 2.48E-18 : 2.48E-18 : 2.48E-18 : 2.48E-18 : 2.48E-18 : 2.48E-18 : 2.48E-18 : 3.01E-18

- -+--

+------------------+----------------- -+-----------------+

MEAT ADULT 2.03E-06 2.03E-06 1.52E-18 2.03E-06 2.03E-06 2.03E-06 2.03E-06 2.03E-06

- ++--- - --------------------------------------------------------- +------------ - ---------------

TEEN : 1.21E-06 : 1.21E-06 : 1.26E-18 : 1.21E-06 : 1.21E-06 : 1.21E-06 : 1.21E-06 : 1.21E-06 S----------------------------------------------+ ----------------- 4 - - - --------------------------

+

CHILD : 1.46E-06 : 1.46E-06 : 2.34E-18 : 1.46E-06 : 1.46E-06 : 1.46E-06 : 1.46E-06 : 1.46E-06

- -+--

+------------------+-----------------+-----------------+----------------- -+-----------------+

IV-35

TABLE IV-A-32 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 32 BEEF AT 2.00 MILES SSW ANNUALBETAAIRDOSE = 8.03E-20 MILLRADS ANNUAL-GAMMAAIRDOSE = 2.70E-20 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

--- -+------+-- -+---------------------------------------------------------------- +----------------+

PLUME : 1.57E-20 : 1.57E-20 : 1.57E-20 : 1.57E-20 : 1.57E-20 : 1.57E-20 : 1.65E-20 : 4.44E-20 :

-+ +---------------------------------------------------------+------------------

+----------------+

GROUND : 1.78E-18 : 1.78E-18 : 1.78E-18 : 1.78E-18 : 1.78E-18 : 1.78E-18 : 1.78E-18 : 2.17E-18 :

- -+--

+------------------+----------------- -+-----------------+

MEAT : : . : : :

ADULT 1.95E-06 1.95E-06 1.09E-18 1.95E-06 1.95E-06 1.95E-06 1.95E-06 1.95E-06

-+----- ------------------- +-------------------+-----------------++ --------------- +----------

TEEN : 1.16E-06 : 1.16E-06 : 9.10E-19 : 1.16E-06 : 1.16E-06 : 1.16E-06 : 1.16E-06 : 1.16E-06 :

-+---------------------+------------------+---------------------------------------------------+

CHILD : 1.41E-06 : 1.41E-06 : 1.69E-18 : 1.41E-06 : 1.41E-06 : 1.41E-06 : 1.41E-06 : 1.41E-06 :

-+

+- ++ -----------

+------------------------------------ ---------------- +

IV-36 OOOOOOOOOOO0O0OO0OOOO0O0OOOOOOOOOOOO0O0O0

TABLE IV-A-33 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 33 BEEF AT 0.73 MILES SW ANNUAL BETA-AIR DOSE = 1.25E-18 MILLRADS ANNUAL-GAMMAAIRDOSE = 4.20E-19 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

-+ --------------

+----------- ----------------- +-----------------------------+------------------+

PLUME : 2.45E-19 : 2.45E-19 : 2.45E-19 : 2.45E-19 : 2.45E-19 : 2.45E-19 : 2.58E-19 : 6.91E-19

-+++----------

+

GROUND : 1.95E-17 : 1.95E-17 : 1.95E-17 : 1.95E-17 : 1.95E-17 : 1.95E-17 : 1.95E-17 : 2.37E-17

-+

+-------------------------------------------------+-----------------+

MEAT : . : : .

ADULT 2.96E-05 2.96E-05 1.20E-17 2.96E-05 2.96E-05 2.96E-05 2.96E-05 2.96E-05

+----+------------------ ------------------ +---+-----------------+------ ---------- +---------------

TEEN : 1.77E-05 : 1.77E-05 : 9.93E-18 : 1.77E-05 : 1.77E-05 : 1.77E-05 : 1.77E-05 : 1.77E-05

-+---

- - - - - - - - -------------------- +------------------------------+---------------------------------

CHILD : 2.14E-05 : 2.14E-05 : 1.84E-17 : 2.14E-05 : 2.14E-05 : 2.14E-05 : 2.14E-05 : 2.14E-05

-+ -+ ------------------ ------------------

+-+ ---------------- - ++ --------------

+----------

IV-37

TABLE IV-A-34 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 34 BEEF AT 2.42 MILES WSW ANNUALBETAAIRDOSE = 1.39E-19 MILLRADS ANNUAL-GAMMAAIRDOSE = 4.69E-20 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

-+-------------------------------------------------- -------- +------------------------------------+

PLUME : 2.73E-20 : 2.73E-20 : 2.73E-20 : 2.73E-20 : 2.73E-20 : 2.73E-20 : 2.87E-20 : 7.70E-20

+- - +------------------------------ ----------------- +--------+------------------------------------+

GROUND : 1.08E-18 : 1.08E-18 : 1.08E-18 : 1.08E-18 : 1.08E-18 : 1.08E-18 : 1.08E-18 : 1.31E-18

+-"+-------------------------------- ----------------- -------------------------- ------------------ +

MEAT . : : : :

ADULT 3.59E-06 3.59E-06 6.G1E-19 3.59E-06 3.59E-06 3.59E-06 3.59E-06 3.59E-06

+- +----+--------------------+------------------+----------- -+-----------------------------------+

TEEN : 2.14E-06 : 2.14E-06 : 5.49E-19 : 2.14E-06 : 2.14E-06 : 2.14E-06 : 2.14E-06 : 2.14E-06

++---------------------------+ ------------------------------ -+-----------------------------------+

CHILD : 2.59E-06 : 2.59E-06 : 1.02E-18 : 2.59E-06 : 2.59E-06 : 2.S9E-06 : 2.59E-06 : 2.59E-06

+-+-------------------------------------------------- -------------------------- +------------------

IV-38

eeeeee~eeee@eefleeeeleeeOOe~eeeeeeeOeeee~e@e

@@OS@@*O@@e@O@seeeOOeeeOeeeOeeOeOO@@@eeeeee TABLE IV-A-35 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 35 BEEF AT 3.25 MILES W ANNUAL BETA AIR DOSE = 7.38E-20 MILLRADS ANNUAL-GAMMAAIRDOSE = 2.48E-20 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

+-+------------------------------+-----------------------------------+

PLUME : 1.45E-20 : 1.45E-20 : 1.45E-20 : 1.45E-20 : 1.45E-20 : 1.45E-20 : 1.52E-20 : 4.08E-20

--------------- +-- +-------------------------------+------------------+----------------

GROUND : 7.25E-19 : 7.25E-19 : 7.25E-19 : 7.25E-19 : 7.25E-19 : 7.25E-19 : 7.25E-19 : 8.81E-19 S+----------- +---------------------------------------------------------------+----------------+

MEAT : . . :

ADULT 1.87E-06 1.87E-06 4.45E-19 1.87E-06 1.87E-06 1.87E-06 1.87E-06 1.87E-06

+------------------------------+------------------------------------------------ -+---------------+

TEEN : 1.12E-06 : 1.12E-06 : 3.70E-19 : 1.12E-06 : 1.12E-06 : 1.12E-06 . 1.12E-06 : 1.12E-06

- ---------- -------------- 06 --------------- .--- 3------------------05-----------------------------

CHILD :1.35E-06G 1.35E-06 :G.86E-19 :1.35E-06 :1.35E-06G 1.35E-06G 1.35E-06 :1.35E-06

+------------------+-----------------------------------+------------------------------------+

IV-39

TABLE IV-A-36 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 36 BEEF AT 2.27 MILES WNW ANNUALBETAAIRDOSE = 1.96E-19 MILLRADS ANNUAL-GAMMAAIRDOSE = 6.58E-20 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

++------------------+------------------ +-------------------------------+

PLUME : 3.84E-20 . 3.84E-20 : 3.84E-20 : 3.84E-20 : 3.84E-20 : 3.84E-20 : 4.03E-20 : 1.08E-19

-+---- ------------------- ++------------------+------------------ - -----------

+ --------------

4 +

GROUND : 2.93E-18 : 2.93E-18 : 2.93E-18 : 2.93E-18 : 2.93E-18 : 2.93E-18 : 2.93E-18 : 3.56E-18

-+-+

+ + + --------------

+ +----------

MEAT : . : : : :

ADULT 4.76E-06 4.76E-06 1.80E-18 4.76E-06 4.76E-06 4.76E-06 4.76E-06 4.76E-06

+---------- ----- +---+ ----------------- -+ - - ----------- --------------- +

TEEN : 2.83E-06 : 2.83E-06 : 1.49E-18 : 2.83E-06 : 2.83E-06 : 2.83E-06 : 2.83E-06 : 2.83E-06

+---------------+---+ ----------------- - - - -----------

+ --------------- +

CHILD : 3.43E-06 : 3.43E-06 : 2.77E-18 : 3.43E-06 : 3.43E-06 : 3.43E-06 : 3.43E-06 : 3.43E-06

+ ------------------ +

IV-40

TABLE IV-A-37 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 37 BEEF AT 3.73 MILES NNW ANNUAL BETA AIR DOSE = 8.21E-20 MILLRADS ANNUAL-GAMMAAIRDOSE = 2.76E-20 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

+----------------------------- -+------------------ +-----------------+

PLUME : 1.61E-20 : 1.61E-20 : 1.61E-20 : 1.61E-20 : 1.61E-20 : 1.61E-20 : 1.69E-20 : 4.54E-20

+ +---------------------------------- +------------ ------------------ +

GROUND : 2.OOE-18 : 2.OOE-18 : 2.OOE-18 : 2.OOE-18 : 2.OOE-18 : 2.OOE-18 : 2.OOE-18 : 2.43E-18

+- -----------------------------------

+--- +----------- ---------- -------------- +----------

MEAT ADULT 2.03E-06 2.03E-06 1.23E-18 2.03E-06 2.03E-06 2.03E-06 2.03E-06 2.03E-06 S+---------- ------------------- - - ---------------- ----------------------------- +--------------+

TEEN : 1.21E-06 : 1.21E-06 : 1.02E-18 : 1.21E-06 : 1.21E-06 : 1.21E-06 : 1.21E-06 : 1.21E-06

- - ---------- +-------------- -- --------------------------- -- - -+------------------+------------------+

CHILD : 1.46E-06 : 1.46E-06 : 1.89E-18 : 1.46E-06 : 1.46E-06 : 1.46E-06 : 1.46E-06 : 1.46E-06

+---------- -+------------------ +-----------------+

IV-41

TABLE IV-A-38 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS SPECIAL LOCATION NO. 38 COW AT 3.50 MILES S ANNUALBETAAIRDOSE = 4.51E-20 MILLRADS ANNUAL-GAMMAAIRDOSE = 1.52E-20 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

--+ ------------------- +---------------+---------------+---------------+- ---------------

+---------

PLUME : 8.85E-21 : 8.85E-21 : 8.85E-21 : 8.85E-21 : 8.85E-21 : 8.85E-21 : 9.30E-21 : 2.49E-20

- + -------------------- +---------------+---------------

+---------------------------+---------------

GROUND : 1.28E-18 : 1.28E-18 : 1.28E-18 : 1.28E-18 : 1.28E-18 : 1.28E-18 : 1.28E-18 : 1.56E-18 S+-------+-----------+---------------+---------------+---------------+---------------+---------------+---------------+

COW MILK : : : : :

ADULT : 2.56E-06 2.56E-06 1.08E-17 2.56E-06 2.56E-06 2.56E-06 2.56E-06 2.56E-06

+ +------- --------------- +-------------+

TEEN : 3.34E-06 : 3.34E-06 : 1.97E-17 : 3.34E-06 : 3.34E-06 : 3.34E-06 : 3.34E-06 : 3.34E-06 S+-------+-----------+---------------+---------------+---------------+---------------+---------------+---------------+

CHILD : 5.29E-06 : 5.29E-06 : 4.77E-17 : 5.29E-06 : 5.29E-06 : 5.29E-06 : 5.29E-06 : 5.29E-06 S+-------+-----------+---------------+---------------+---------------+---------------+---------------+---------------+

INFANT : 8.02E-06 : 8.02E-06 : 9.96E-17 : 8.02E-06 : 8.02E-06 : 8.02E-06 : 8.02E-06 : 8.02E-06

-+-+------------------+---------------+--------------- +---------------------------+---------------

IV-42

TABLE IV-B-I FORT CALHOUN 1 DOSE CONTRIBUTIONS FROM GASEOUS EFFLUENTS UNRESTRICTED AREA BOUNDARY REQUIRED BY TECHNICAL SPECIFICATION 5.9.4.a.

JANUARY 1, 2012 TO DECEMBER 31, 2012 MAXIMUM SITE BOUNDARY GAMMA AIR DOSE 0.OOE+00 MILLRADS MAXIMUM SITE BOUNDARY BETA AIR DOSE 0.OOE+00 MILLRADS IV-43

TABLE IV-C-1 FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS ALARA ANNUAL INTEGRATED POPULATION DOSE

SUMMARY

(PERSON-REM)

PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

-+---------------------+----------------------+ -------------------------------------------------- +

PLUME 7.57E-19 7.57E-19 7.57E-19 7.57E-19 7.57E-19 7.57E-19 8.11E-19 2.58E-18 0.00% 9 0 .00% 0.15% 0.00% 0.00% 9 0.00% 0 .00% : 0.00% :

-- - +----------------------------------------- -------------------------- +------------------+----------------- -+-----------------+

GROUND 6.24E-17 6.24E-17 6.24E-17 6.24E-17 6.24E-17 6.24E-17 6.24E-17 7.58E-17 00.00* 0.00% 12.20% 0.00% 0.0016 0.00% 0.00% 0.00%

+--- - - - - - ---------------------------------------------------------------------- -+----------------+

INHAL 5.69E-04 5.69E-04 1.34E-16 5.69E-04 5.69E-04 5.69E-04 5.69E-04 5.69E-04

38.33%6 38.33% 26.27% 38.33% 38.33% 38.33% 38.33% 38.33%

+---- - - - -------------------- +-----------------------------------+---------------------------------

VEGET 6.43E-04 6.43E-04 1.15E-17 6.43E-04 6.43E-04 6.43E-04 6.43E-04 6.43E-04

43.29% 43.29% 2.24% 43.29% 43.29% 43.29% 43.29% 43.29%

--- S+ - - -------------------------------------------------------- - - ----------

+ +----------------

COW MILK 1.28E-04 1.28E-04 2.55E-16 1.28E-04 1.28E-04 1.28E-04 1.28E-04 1.28E-04 8.62% 8.62% 49.87% : 8.62% 8.62% 8.62% 8.62% 8.62%

-- - +--------------------------------+------------------+----------------+------------------+----------------- -+-----------------+

MEAT 1.45E-04 1.45E-04 4.74E-17 1.45E-04 1.45E-04 1.45E-04 1.45E-04 1.45E-04 9.76%6 9.76% 9.27% 9.76% 9.76%* 9.76% 9.76% 9.76%

- -+--

+------------------+----------------+------------------+----------------- -+-----------------+

TOTAL* : 1.49E-03 : 1.49E-03 : 5.11E-16 : 1.49E-03 : 1.49E-03 : 1.49E-03 : 1.49E-03 : 1.49E-03

-+---

- - - - - - - - -------------------- +------------------------------+- - ------------------------------

IV-44

0 0

0 S

0 0

S S

SECTION V 0

0 DOSE FROM LIQUID EFFLUENTS 0 LADTAP II OUTPUT S Technical Specification 5.9.4.a S

January 1,2012 - December 31, 2012 0

S 0

0 S

S 0

0 V-1

0 0

Radioactive Effluent Releases - First, Second, Third, and Fourth Quarters 2012 LIQUID EFFLUENTS 0 During the reporting period, a total of 1.08E-03 curies of radioactive liquid materials less tritium, dissolved noble gases, and alpha were released to the Missouri River at an average concentration of 9.05E-10 pCi/mL. This represents 9.05E-02 percent of the limits specified in Appendix B to 10 CFR 20 (1.OE-06 pCi/mL for unrestricted areas), 0 2.94 curies of tritium were discharged at an average diluted concentration of 2.43E-06 pCi/mL or 0.243 percent of ECL (1.OE-03 pCi/mL).

No gross alpha radioactivity or Ni-63 was identified by Off-site vendor analysis of 0 quarterly liquid composites for the reporting period.

Dilution water during the period amounted to 1.22E+9 liters, while liquid waste 0 discharges consisted of 2.08E+06 liters of radioactive liquid waste. 0 V

0 0

V-2 0 0

0 0

A. Potential Annual Doses to Individuals from Liquid Releases

Total body, skin, and organ mRem for liquid releases were calculated for all O significant liquid pathways using the annual configuration of the LADTAP II O program.

O The inputs to LADTAP II for the annual period from January 1, 2012 through December 31, 2012 were as follows:

0 0 (1) All liquid effluents were as described in Section IV except for entrained noble gases (Ar-41, Xe-131M, Xe-133M, Xe-133, Xe-135M, Xe-135,

Kr-85M, Kr-87, and Kr-88).

0 O (2) An average plant discharge rate of 15.9 cubic feet per second (CFS) was utilized for 2012. The average discharge rate during releases was 1.61 0 cubic feet per second (CFS).

O (3) Dilution factors (inverse of the mixing ratios) were computed based on

Regulatory Guide 1.113 (equation 7 in Section 2.a.1 of Appendix A) for a one dimensional transport model.

(4) Drinking water transport times of 6.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to the Omaha intake and

7.0 hours0 days 0 hours 0 weeks 0 months to the Council Bluffs intake were used for dose calculations.

(5) A shorewidth factor of 0.2 was used.

O (6) All dose factors, transport times from receptor to individual, and usage

factors are defined by Regulatory Guide 1.109 and NUREG-0172.

The discharge site was chosen to present the most conservative estimate of

mRem dose for an average adult, teenager, child, and infant. A conservative

approach is also presented by the assumption that Omaha and Council Bluffs receive all drinking water from the Missouri River.

0 0

l 0

0 0

0 V-3 S

0 0

0 B. Potential Annual Doses to Population from Liquid Releases 0 The LADTAP II program in its annual configuration was also used to calculate to total body and organ doses for the population of 950,006 within a 50-mile radius of the plant (based on the 2010 census). The same input was used as in the individual cases with the addition of the following:

(1) Dilution factors and transport times for the pathways of sport fish, commercial fish, recreation and biota were calculated based on a distance of two miles downstream as approximately the distance to the nearest recreation facility - DeSoto National Wildlife Preserve.

0 (2) The total fish harvest for both sport and commercial purposes was calculated using an average commercial fish catch for Nebraska.

V 0

S 0

0 0

S 0

0 0

v-4 S 0

...e@.O@eOOe.*seee~eeeeoeoe*@e@OO@@S@@@@OOO

L AAA AAA PPPP IIIII 11111 DDDD TTTTT I I *

L A A D D T A A P P I I *

L A A D D T A A P P I I *

L AAAAA D D T AAAAA PPPP I I *

L A A D D T A A P 11I1I 11III *

LLLLL A A DDDD T A A P

EVALUATION OF RADIATION DOSES FROM RELEASES OF RADIACTIVITY IN NUCLEAR POWER PLANTS LIQUID EFFLUENTS

REVISION DATE: PNL VAX - OCTOBER 1985

FORT CALHOUN ANNUAL 2012, DOSE PROJECTIONS

RADIOLOGICAL ASSESSMENT BRANCH *

DIVISION OF SYSTEMS INTEGRATION *

U. S. NUCLEAR REGULATORY COMMISSION *

WASHINGTON, D. C.

V-5

LOCATION FRESHWATER INTAKE ADULT DOSES DOSE (MREM PER YEAR INTAKE)

PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 2.81E-02 3.89E-02 2. 57E-02 3.21E-05 1.32E-02 4 .42E-03 8. 11E-04 DRINKING 1. 16E-04 4.54E-04 4. OOE-04 2.94E-04 3 .48E-04 3. 12E- 04 3 04E-04 SHORELINE 4.45E-05 3.82E-05 3.82E-05 3. 82E-05 3.82E-05 3.82E-05 3.82E-05 3. 82E-05 SWIMMING 1.52E-07 1.52E-07 1. 52E-07 1.52E-07 1.52E-07 1. 52E-07 1. 52E-07 BOATING 7. 59E-08 7. 59E-08 7. 59E-08 7.59E-08 7. 59E-08 7.59E-08 7. 59E-08 TOTAL 4 .45E-05 2. 82E-02 3.94E-02 2 .61E-02 3.64E-04 1.36E-02 4.77E-03 1. 15E-03 USAGE (KG/YR,HR/YR) DILUTION TIME (HR) SHOREWIDTH FACTOR=0.2 FISH 21.0 7.3 24.00 DRINKING 730.0 30.8 18.60 SHORELINE 12.0 7.3 0.00 SWIMMING 12.0 7.3 0.00 BOATING 12.0 7.3 0.00 T E E N AG E R DOSES DOSE (MREM PER YEAR INTAKE)

PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 3 . OOE-02 4.05E-02 1. 43E-02 2.46E-05 1. 38E-02 5. 36E-03 6. 18E-04 DRINKING 1. 14E-04 3. 60E-04 2. 61E-04 2.07E-04 2. 59E-04 2.27E-04 2 14E-04 SHORELINE 2.49E-04 2. 13E-04 2.13E-04 2. 13E-04 2.13E-04 2. 13E-04 2.13E-04 2. 13E-04 SWIMMING 8 .47E-07 8 .47E-07 8 .47E-07 8.47E-07 8 .47E-07 8.47E-07 8 .47E-07 BOATING 4 .24E-07 4 .24E-07 4 .24E-07 4.24E-07 4 .24E-07 4 .24E-07 4 .24E-07 TOTAL 2 .49E-04 3. 04E-02 4. 11E-02 1 .47E-02 4.46E-04 1 .42E-02 5. 81E-03 1 05E-03 USAGE (KG/YR,HR/YR) DILUTION TIME (HR) SHOREWIDTH FACTOR=0.2 FISH 16.0 7.3 24.00 DRINKING 510.0 30.8 18.60 SHORELINE 67.0 7.3 0.00 SWIMMING 67.0 7.3 0.00 BOATING 67.0 7.3 0.00 V-6

CHILD DOSES DOSE (MREM PER YEAR INTAKE)

PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI -LLI FISH 3.78E-02 3. 66E-02 5.49E-03 2.04E-05 1. 19E-02 4.31E-03 2 55E-04 DRINKING 3.32E-04 7.18E-04 4.46E-04 3.97E-04 5. 01E-04 4. 35E-04 4. 03E-04 SHORELINE 5. 19E-05 4 .45E-05 4.45E-05 4.45E-05 4.45E-05 4 .45E-05 4 .45E-05 4 .45E-05 SWIMMING 1.77E-07 1.77E-07 1.77E-07 1.77E-07 1 .77E-07 1.77E-07 1 .77E-07 BOATING 8.85E-08 8.85E-08 8.85E-08 8.85E-08 8. 85E-08 8. 85E-08 8. 85E-08 TOTAL 5. 19E-05 3.82E-02 3.74E-02 5.98E-03 4.62E-04 1. 25E-02 4.79E-03 7 04E-04 USAGE (KG/YR,HR/YR) DILUTION TIME (HR) SHOREWIDTH FACTOR=0.2 FISH 6.9 7.3 24.00 DRINKING 510.0 30.8 18.60 SHORELINE 14.0 7.3 0.00 SWIMMING 14.0 7.3 0.00 BOATING 14 n0 7_3 0.00 INFANT DOSES DOSE_(MREM PER YEAR INTAKE)

PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 0. OOE+00 0. OOE+00 0.OOE+00 0.OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 DRINKING 3 .43E-04 7.95E-04 4.20E-04 3.90E-04 4.98E-04 4 .34E-04 3. 94E-04 SHORELINE 0. OOE+00 0. OOE+00 0. OOE+00 0.OOE+00 0.OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 TOTAL 0. OOE+00 3 .43E-04 7. 95E-04 4.20E-04 3.90E-04 4.98E-04 4 .34E-04 3.94E-04 USAGE (KG/YR,HR/YR) DILUTION TIME (HR) SHOREWIDTH FACTOR=0.2 FISH 0.0 7.3 24.00 DRINKING 330.0 30.8 18.60 V-7

LOCATION IS SITE DISCHG.

ADULT DOSES DOSE_(MREM PER YEAR INTAKE)

PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 2.05E-01 2.84E-01 1.88E-01 2.34E-04 9.65E-02 3.22E-02 5. 92E-03 DRINKING 3.57E-03 1 .40E-02 1.23E-02 9.04E-03 1. 07E-02 9.60E-03 9. 38E-03 SHORELINE 3 .25E-04 2. 79E-04 2 .79E-04 2.79E-04 2.79E-04 2 .79E-04 2 .79E-04 2. 79E-04 SWIMMING 1.11E-06 1.l1E-06 1.lIE-06 1. I1E-06 1.lIE-06 1. 11E-06 1. lIE-06 BOATING 5. 54E-07 5. 54E-07 5.54E-07 5.54E-07 5.54E-07 5. 54E-07 5. 54E-07 TOTAL 3 .25E-04 2.09E-01 2.98E-01 2.OOE-01 9. 55E-03 1.07E-01 4.21E-02 1. 56E-02 USAGE (KG/YR,HR/YR) DILUTION TIME (HR) SHOREWIDTH FACTOR=0.2 FISH 21.0 1.0 24.00 DRINKING 730.0 1.0 12.00 SHORELINE 12.0 1.0 0.00 SWIMMING 12.0 1.0 0.00 BOATING 12.0 1.0 0.00 TEENAGER DOSES DOSE_(MREM PER YEAR INTAKE)

PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 2. 19E-01 2. 96E-01 1. 04E-01 1.80E-04 1. 01E-01 3. 92E-02 4. 51E-03 DRINKING 3. 50E-03 1.11E-02 8. 04E-03 6.37E-03 7 .97E-03 7. OOE-03 6.59E-03 SHORELINE 1.81E-03 1. 55E-03 1.55E-03 1. 55E-03 1.55E-03 1 .55E-03 1.55E-03 1.55E-03 SWIMMING 6. 19E-06 6.19E-06 6 19E-06 6.19E-06 6 .19E-06 6. 19E-06 6. 19E-06 BOATING 3.09E-06 3. 09E-06 3. 09E-06 3. 09E-06 3 .09E-06 3. 09E-06 3.09E-06 TOTAL 1.81E-03 2. 24E-01 3.08E-01 1. 14E-01 8.11E-03 1. 10E-01 4 .77E-02 1.27E-02 USAGE (KG/YR,HR/YR) DILUTION TIME (HR) SHOREWIDTH FACTOR=0.2 FISH 16.0 1.0 24.00 DRINKING 510.0 1.0 12.00 SHORELINE 67.0 1.0 0.00 SWIMMING 67. 0 1.0 0.00 BOATING 67.0 1.0 0.00 V-8

CHILD DOSES DOSE (MREM PER YEAR INTAKE)

PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 2 .76E-01 2.67E-01 4. 01E-02 1.49E-04 8.71E-02 3. 14E-02 1.86E-03 DRINKING 1.02E-02 2.21E-02 1 .37E-02 1.22E-02 1. 54E-02 1. 34E-02 1.24E-02 SHORELINE 3 .79E-04 3 .25E-04 3.25E-04 3 .25E-04 3.25E-04 3.25E-04 3 .25E-04 3.25E-04 SWIMMING 1. 29E-06 1.29E-06 1. 29E-06 1.29E-06 1.29E-06 1. 29E-06 1.29E-06 BOATING 6 .46E-07 6.46E-07 6 .46E-07 6.46E-07 6.46E-07 6 .46E-07 6. 46E-07 TOTAL 3 . 79E-04 2. 87E-01 2.90E-01 5 .41E-02 1.27E-02 1.03E-01 4. 52E-02 1 .46E-02 USAGE (KG/YR,HR/YR) DILUTION TIME (HR) SHOREWIDTH FACTOR=0 .2 FISH 6.9 1.0 24.00 DRINKING 510.0 1.0 12.00 SHORELINE 14.0 1.0 0.00 SWIMMING 14.0 1.0 0.00 BOATING 14.0 1.0 0.00 INFANT DOSES DOSE_(MREM PER YEAR INTAKE)

PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 0. OOE+00 0. OOE+00 0.OOE+00 0.OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 DRINKING 1. 06E-02 2.45E-02 1.29E-02 1.20E-02 1.53E-02 1.34E-02 1.21E-02 SHORELINE 0. OOE+00 0. OOE+00 0. OOE+00 0.OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 TOTAL 0. OOE+00 1. 06E-02 2.45E-02 1.29E-02 1.20E-02 1. 53E-02 1.34E-02 1.21E-02 USAGE (KG/YR, HR/YR) DILUTION TIME (HR) SHOREWIDTH FACTOR=0.2 FISH .0.0 1.0 24.00 DRINKING 330.0 1.0 12.00 V-9

*

FISH CONSUMPTION POPULATION DOSES * *

PERSON-REM

________SPORT HARVEST_____

DOSE (PERSON-REM)--------------------------

PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH ADULT 6.10E+04 8.15E-02 1.13E-01 7.46E-02 9.30E-05 3.83E-02 1.28E-02 2.35E-03 FISH TEENAGER 7.12E+03 1.34E-02 1.80E-02 6.34E-03 1.09E-05 6.12E-03 2.38E-03 2.75E-04 FISH CHILD 4.93E+03 2.70E-02 2.61E-02 3.92E-03 1.46E-05 8.52E-03 3.07E-03 1.82E-04 FISH TOTAL 7.30E+04 1.22E-01 1.57E-01 8.48E-02 1.18E-04 5.30E-02 1.83E-02 2.81E-03 LOCATION DILUTION CATCH TIME(HR)-INCLUDES FOOD PROCESSING TIME OF 1.68E+02 HR POPULATION=1.24E+04 7.30E+00 7.30E+04 1.69E+02 AVERAGE INDIVIDUAL CONSUMPTION (KG/YR) ADULT=6.90E+00 TEEN=5.20E+00 CHILD=2.20E+00 COMMERCIAL HARVEST DOSE (PERSON-REM)-

PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH ADULT 4.18E+06 9.27E-03 1.28E-02 8.48E-03 1.06E-05 4 .36E-03 1.46E-03 2. 67E-04 FISH TEENAGER 4.88E+05 1.52E-03 2.05E-03 7.21E-04 1.24E-06 6.96E-04 2 .71E-04 3.12E-05 FISH CHILD 3.38E+05 3.07E-03 2.97E-03 4.46E-04 1.66E-06 9. 69E-04 3. 50E-04 2.07E-05 FISH TOTAL 5.01E+06 1.39E-02 1.79E-02 9.65E-03 1.35E-05 6. 03E-03 2 . OBE-03 3. 19E-04 LOCATION DILUTION CATCH TIME(HR)-INCLUDES FOOD PROCESSING TIME OF 2.40E+02 HR POPULATION=8.53E+05 7.30E+00 7.30E+04 2.41E+02 AVERAGE INDIVIDUAL CONSUMPTION (KG/YR) ADULT=6.90E+00 TEEN=5.20E+00 CHILD=2.20E+00 V-10

*

POPULATION WATER CONSUMPTION DOSES * *

SUPPLIER-OMAHA

------DOSE (PERSON-REM)- -------------------------

PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI DRINKING ADULT 1.39E+08 2.21E-02 8.64E-02 7.61E-02 5.59E-02 6.62E-02 5.94E-02 5.80E-02 DRINKING TEENAGER 1.51E+07 3.37E-03 1.07E-02 7.75E-03 6.13E-03 7.67E-03 6.74E-03 6.35E-03 DRINKING CHILD 2.48E+07 1.61E-02 3.49E-02 2.17E-02 1.93E-02 2.43E-02 2.11E-02 1.96E-02 DRINKING TOTAL 1.79E+08 4.16E-02 1.32E-01 1.06E-01 8.13E-02 9.82E-02 8.72E-02 8.39E-02 POPULATION=5.29E+05 DILUTION=3.08E+01 TRANSIT TIME=3.06E+01 HR (INCLUDING 24 HR FOR TREATMENT FACILITY)

AVERAGE INDIVIDUAL CONSUMPTION (L/YR) ADULT=3.70E+02 TEEN=2.60E+02 CHILD=2.60E+02 SUPPLIER-COUNCIL BLUFFS

DOSE (PERSON-REM)--------------------------

PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI DRINKING ADULT 2.29E+07 3.57E-03 1.40E-02 1.23E-02 9.04E-03 1.07E-02 9.61E-03 9.38E-03 DRINKING TEENAGER 2.49E+06 5.46E-04 1.73E-03 1.25E-03 9.93E-04 1.24E-03 1.09E-03 1.03E-03 DRINKING CHILD 4.07E+06 2.61E-03 5.64E-03 3.51E-03 3.12E-03 3.94E-03 3.42E-03 3.17E-03 DRINKING TOTAL 2.94E+07 6.73E-03 2.14E-02 1.71E-02 1.32E-02 1.59E-02 1.41E-02 1.36E-02 POPULATION=8.70E+04 DILUTION=3.13E+01 TRANSIT TIME=3.10E+01 HR (INCLUDING 24 HR FOR TREATMENT FACILITY)

AVERAGE INDIVIDUAL CONSUMPTION (L/YR) ADULT=3.70E+02 TEEN=2.60E+02 CHILD=2.60E+02 CUMULATIVE

TOTAL -----

PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI DRINKING CUMUL TOTAL 2.08E+08 4.83E-02 1.53E-01 1.23E-01 9.44E-02 1.14E-01 1.01E-01 9.75E-02 NEPA DOSES NOTE--TOTAL NEPA DOSE INCLUDES SPORT CATCH

DOSE (PERSON-REM)--------------------------

PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH ADULT 1.22E+05 1.63E-01 2.26E-01 1.49E-01 1.86E-04 7.67E-02 2.56E-02 4.70E-03 FISH TEENAGER 1.42E+04 2.67E-02 3.60E-02 1.27E-02 2.19E-05 1.22E-02 4.77E-03 5.49E-04 FISH CHILD 9.85E+03 5.40E-02 5.23E-02 7.83E-03 2.91E-05 1.70E-02 6.14E-03 3.64E-04 FISH TOTAL 1.46E+05 2.44E-01 3.14E-01 1.70E-01 2.37E-04 1.06E-01 3.65E-02 5.62E-03 HYDROSPHERE TRITIUM DOSE AVERAGE INDIVIDUAL WATER CONSUMPTION = 3.0 L/DAY PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI WATER TOTAL 2.86E+11 0.00E+00 2.24E-05 2.24E-05 2.24E-05 2.24E-05 2.24E-05 2.24E-05 V-1l

*

RECREATION POPULATION DOSES * *

LOCATION- DOWN STREAM SWIMMING DILUTION= 7.30E+00 TRANSIT TIME= 6.70E-01 HR SWF= 0.2

-DOSE (PERSON-REM)

PATHWAY AGE GROUP USAGE SKIN TOTAL BODY THYROID SHORELINE TOTAL POPUL 4. 10E+07 1.52E-01 1.30E-01 1.30E-01 LOCATION- DOWN STREAM SWIMMING DILUTION= 7.30E+00 TRANSIT TIME= 6.70E-01 HR DOSE (PERSON-REM)

PATHWAY AGE GROUP USAGE SKIN TOTAL BODY THYROID SWIMMING TOTAL POPUL 4. 10E+07 5.19E-04 5.19E-04 LOCATION- DOWN STREAM BOATIb DILUTION= 7.30E+00 TRANSIT TIME= 6.70E-01 HR DOSE (PERSON-REM)

PATHWAY AGE GROUP USAGE SKIN TOTAL BODY THYROID BOATING TOTAL POPUL 4. 10E+07 2.59E-04 2.59E-04

DOSE TO BIOTA * *

MRADS PER YEAR BIOTA DILUTION= 1. OOE+00 TRANSIT TIME= 0.OOE+00 HR INTERNAL EXTERNAL TOTAL FISH 6.21E-01 1. 02E+00 1.64E+00 INVERTEBRATE 3.16E-01 2. 03E+00 2.35E+00 ALGAE 1.84E-01 8. 09E-04 1.85E-01 MUSKRAT 3. 39E+00 6. 78E-01 4.07E+00 RACCOON 1.26E+00 5. 09E-01 1.77E+00 HERON 1.97E+01 6. 78E-01 2.04E+01 DUCK 3. 09E+00 1. 02E+00 4.11E+00 V-12 000000000000000000000000000*000000000000000o

0 0

S 0

0 0

0 SECTION VI RADIOACTIVE EFFLUENT RELEASES - SOLID RADIOACTIVE WASTE Technical Specifications 5.9.4.a 0 January 1, 2012 - December 31, 2012 0

0 0

VI-1

S 0

0 III. RADIOACTIVE EFFLUENT RELEASE- SOLID RADIOACTIVE S

WASTE EFFLUENT AND WASTE DISPOSAL REPORT 0

January 1,2012 through December 31, 2012 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 0 S

A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED) 0 Month Number of Volume Curie Est. Total 0

1. Type of Waste Shipped Shipments Cu. Meter Content % Error 0

a. Spent resins, filter January 0 0 0 N/A sludges, evaporator February 0 0 0 N/A 0 bottoms, etc. March 0 0 0 N/A 0 April 0 0 0 N/A 0 May 0 0 0 N/A June 0 0 0 N/A 0 July 0 0 0 N/A 0 August 0 0 0 N/A 0 September 0 0 0 N/A 0 October 0 0 0 N/A November 0 0 0 N/A S December 0 0 0 N/A 0 S

Total (Type a) 0 0 0 N/A 0

S

b. Dry compressable, January 0 0 0 N/A 0 contaminated equipment, February 1 36.25 1.37 E-2 20 S

etc. March 0 0 0 N/A April 0 0 0 N/A 0 May 1 41.55 1.52 E-2 20 0 June 0 0 0 N/A 0 July 0 0 0 N/A August 1 72.5 2.32 E-2 20 S

September 0 0 0 N/A 0 1

October 1

72.5 8.97 E-2 20 0 November 72.5 6.53 E-2 20 S

December 0 0 0 N/A 0

Total (Type b) 5 295.3 2.07 E-1 20 S 0

S 0

VI-2 0

0

0 0

0 S III. RADIOACTIVE EFFLUENT RELEASE - SOLID RADIOACTIVE 0 WASTE EFFLUENT AND WASTE DISPOSAL REPORT 0 (Continued) 0 0

0 Month Number of Volume Curie Est. Total

1. Type of Waste Shipped Shipments Cu. Meter Content % Error C. Irradiated components January 0 0 0 N/A and other categories. February 0 0 0 N/A 0 March 0 0 0 N/A April 0 0 0 N/A May 0 0 0 N/A 0 June 0 0 0 N/A 0 July 0 0 0 N/A August 0 0 0 N/A 0 September 0 0 0 N/A 0 October 0 0 0 N/A November 0 0 0 N/A 0 December 0 0 0 N/A 0 Total (Type c) 0 0 0 N/A 0

d. Other January 0 0 0 N/A February 0 0 0 N/A March 0 0 0 N/A 0 April 0 0 0 N/A 0 May 0 0 0 N/A 0 June 0 0 0 N/A July 0 0 0 N/A 0 August 0 0 0 N/A September 0 0 0 N/A 0 October 0 0 0 N/A November 0 0 0 N/A 0 December 0 0 0 N/A Total (Type d) 0 0 0 N/A VI-3

Ill. RADIOACTIVE EFFLUENT RELEASES-SOLID RADIOACTIVE (Continued) 0 B. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (By Type of Waste) 0 0

1. Percentage of Curies from Represented Isotopes 0

Isotope Percent Curies 0 0

a. N/A N/A N/A 0 0

b. Cs-137 45.0 9.33 E-2 0 Ni-63 36.8 7.63 E-2 0 Co-60 5.6 1.16 E-2 Co-58 4.2 8.67 E-3 All other Nuclides constitute 0

H-3 2.0 4.24 E-3 less than 1% 0 Nb-95 1.6 3.29 E-3 0 Tc-99 1.02 2.11 E-3 0 Cs-1 34 1.0 2.00 E-3 0

S

c. N/A N/A N/A 0 S

d. N/A N/A N/A 0 0

S C. SOLID WASTE (DISPOSITION) 0 Number of Shipments Transportation Mode Destination 0 5 Sole Use Vehicle Energy Solutions 0 Bear Creek, Tennessee 0

D. IRRADIATED FUEL SHIPMENTS (DISPOSITION) 0 0

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

S 0

0 0

S 0

VI-4 0 0

0 0

0 S

0 0 SECTION VII 0

0 ATTACHMENT 1 0 ODCM and PCP revisions for the period January 1, 2012 through December 31, 2012 0 in accordance with Technical Specification 5.17.d and 5.18.d, the radioactive effluent release report shall include any revisions to the Offsite Dose Calculation Manual 0 (ODCM) and the Process Control Program (PCP).

0 0

0 0 revision(s) made to the Offsite Dose Calculation Manual (ODCM).

0 0 1 revision(s) made to the Process Control Program (PCP).

0 0

0 S

VII-1

0 0

Page 1 of 12 0 0

0 0

RW-AD-300 0

0 0

Process Control Program 0

Revision 0 0 0

0 Safety Classification: Usage Level:

Information 0 I Non-Safety 0 0

0 0

Change No.: EC 54576 0

Reason for Change: Superseding RW-200 with RW-AD-300. Remove out of date activities, unnecessary editorial statements and 0

incorrect references.

Requestor: E. Breault 0 Preparer: E. Breault S Issued: 01-17-12 3:00 pm 0

0 0

Fort Calhoun Station 0

0 0

RW-AD-300 Information Use Page 2 of 12

Process Control Program Revision 0 0 1.0 PURPOSE AND SCOPE 1.1 Purpose 1.1.1 To provide guidance and boundary conditions for preparation of specific 01 procedures for processing, sampling, analyzing, packaging and shipping

solid radioactive waste in accordance with State and Federal regulatory requirements.

1.2 Scope 0

1.2.1 This program is applicable to the Fort Calhoun Station Unit No. 1 solid radwaste system. Wastes considered in this program are primary and

radwaste liquid processing resins, oil and filters. Dry Active Waste is only

included as it applies to assurance that packaged waste is suitable for

shipment and burial in accordance with applicable State and Federal regulations. Concentrates and aqueous liquids are not considered due to the

present decisions not to utilize the waste evaporator as a means for

processing liquid wastes.

2.0 DEFINITIONS 2.1 Batch - The specific quantity of waste transferred to a disposal container to be

sampled, classified and characterized.

2.2 Chelating Agent - For the purpose of this program, CHELATING AGENTS are amine

polycarboxylic acids (e.g., EDTA, DTPA), hydroxy-carboxylic acids, and polycarboxylic acids (e.g., citric acid, carbolic acid, picolanic acid and gluconic acid ) as defined in 10CFR61.2.

0 2.3 Low-Level Radioactive Waste (LLW) - Those low-level radioactive wastes containing source, special nuclear, or by-product material that are acceptable for disposal in a land disposal facility. For the purposes of this definition, low-level radioactive waste

has the same meaning as in the Low-Level Waste policy Act, that is radioactive waste

not classified as high-level radioactive waste, transuranic waste, spent nuclear fuel, or by-product material as defined in Section 11 e.(2) of the Atomic Energy Act (uranium or 0*thorium tailings and waste).

2.4 Operable - A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s),

and when all necessary attendant instrumentation, controls, electrical power, cooling 0and seal water, lubrication and other auxiliary equipment that are required for the

system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

2.5 Processing - Modifying the physical form and packaging of radioactive waste to meet

the requirements of 10 CFR 61.56.

0 0

0

0S RW-AD-300 Information Use Page 3 of 12 Process Control Program Revision 0 0 0

2.6 Quality Assurance/Quality Control - As used in this document, "quality assurance" 0 comprises those planned and systematic actions necessary to provide adequate 0 confidence that a structure, system, or component will perform satisfactorily in service.

Quality assurance includes quality control, which comprises those quality assurance actions related to the physical characteristics of a material, structure, component, or system which provide a means to control the quality of the material, structure, 0 component, or system to predetermined requirements. 0 2.7 Sampling Plan - A sampling program implemented to ensure that representative 0 samples from the feed waste and the final waste form are obtained and tested for 0 conformance with parameters stated in the Process Control Program and waste form 0 acceptance criteria.

2.8 Stability - As used in this program, STABILITY means structural stability. Stability 0 requires that the waste form maintain its structural integrity under the expected 0 disposal conditions.

2.9 Waste Container - A vessel of any shape, size, and composition used to contain the 0 final processed waste. 0 2.10 Waste Form - Waste in a waste container acceptable for disposal at a licensed 0 disposal facility.

3.0 RESPONSIBILITIES S 3.1 The Supervisor-Radioactive Waste Operations is responsible for:

S 3.1.1 Maintenance of and compliance with this Process Control Program; 3.1.2 Record keeping and document control of shipping and processing data; and S

3.1.3 Assuring Radwaste Personnel are appropriately trained and qualified to perform waste processing and packaging activities.

S 3.2 The Manager-Shift Operations is responsible for:

3.2.1 Providing trained personnel to operate appropriate radwaste process equipment; and 3.2.2 Defining those Operations positions which require training. S 3.3 The Manager Training is responsible for:

3.3.1 Development and implementation of performance-based training for designated personnel in accordance with Training Division procedures.

S 0

0 RW-AD-300 Information Use Page 4 of 12 0 Process Control Proqram Revision 0 0

0 3.4 All OPPD and OPPD contract personnel are responsible for:

0 3.4.1 Implementation of procedures and good practices so as to provide Quality 0 Assurance and maintain exposures ALARA.

0 3.5 The Nuclear Quality Assurance Department is responsible for:

0 0 3.5.1 Establishment of a Quality Assurance Program addressing Radwaste 0 processing and packaging; and 3.5.2 Performing audits of activities associated with this Process Control Program to assure compliance with the Quality Assurance Plan.

3.6 The Plant Review Committee is responsible for:

0 3.6.1 Reviewing and approving changes to this Process Control Program prior to 0 implementation of the changes; and S 3.6.2 Reviewing and approving engineering and 50.59 reviews performed in support of changes to this Process Control Program.

0 3.7 The Station Engineering Manager is responsible for:

0 3.7.1 Ensuring engineering and 50.59 and/or 72.48 reviews are performed for 0 changes made to this Process Control Program; and 0

3.7.2 Submitting these reviews to the Plant Review Committee for review and 0 approval prior to implementation of the changes evaluated.

0 4.0 TOOLS AND EQUIPMENT 0

None 0

0 5.0 PRECAUTIONS AND LIMITATIONS 0 None 6.0 PREREQUISITES AND INITIAL CONDITIONS S

6.1 All personnel performing activities under the control of and described by this Process Control Program shall have been successfully trained and qualified to perform the described activities before actually performing the activities.

6.2 Procedures have been developed for implementation of this Process Control Program.

0 RW-AD-300 Information Use Page 5 of 12 Process Control Program Revision 0 0 7.0 PROCEDURE 0 7.1 Waste Types 7.1.1 Primary Resin 0 A. The contaminated waste product generated as a result of reactor water purification and demineralization, cation ion exchange, deborating ion exchange and spent fuel pool demineralization.

B. Waste consists of contaminated bead ion exchange resins at varying degrees of exhaustion, small concentrations of various solids, activated and non-activated corrosion products and fission products.

7.1.2 Radwaste Liquid Processing Resin 0 A. The contaminated waste product generated as a result of processing radwaste liquids using a demineralization system. This system may be 0 vendor supplied.

B. Waste consists of contaminated bead ion exchange resins at varying degrees of exhaustion, small concentrations of various solids, activated 0 and non-activated corrosion products and fission products.

7.1.3 Filters A. The contaminated waste product generated as a result of liquid processing activities and the removal of cartridge elements from the processing systems.

B. Waste consists of contaminated mechanical filtration cartridges containing various amounts of particulate solids, corrosion products, activation and fission products.

71.4 Oil A. The contaminated waste product generated as a result of leakage or intentional drainage and replacement of various plant component 0 lubricating and/or control fluids.

B. Waste consists of contaminated oils and greases of various grades both S synthetic and natural, in free form or containing various amounts of solid 0 material.

0 0

0

0 0 RW-AD-300 Information Use Page 6 of 12 Process Control Program Revision 0 0 7.1.5 Dry Active Waste A. The contaminated waste product generated as a result of plant

maintenance and repair and routine plant operations.

B. Waste generally consists of contaminated trash in the form of plastics,

papers, wood, steel and cloth items with varying concentrations of

corrosion, activation and fission products.

7.1.6 Non-Standard Wastes 0

A. The contaminated waste product generated as a result of non-routine plant operation, maintenance and or repair activities.

B. Waste consists of plant components, irradiated hardware and other specialty items contaminated with varying concentrations of corrosion, activation and fission products. The waste may also be those items

which have become activated with contamination being a minimal

fraction of the total radioactivity.

7.2 Process Description 0

7.2.1 Primary Resin A. Primary resins are obtained from the CVCS, purification ion exchangers,

and the spent fuel storage pool demineralizer. These resins are

collected in the Spent Resin Storage Tank.

B. The contents of the tank are pumped into a disposal/transport container

within a shielded shipping cask or process shield after which the

contents are dewatered and shipped from the plant.

7.2.2 Radwaste Liquid Processing Resin 0

A. Radwaste liquids are processed using a Filtration-Ion Exchanger (FIX) system.

B. Radioactive liquids are normally transferred from the waste holdup tanks

to the demineralization system using the waste holdup transfer pumps.

Specific maintenance and/or decontamination activities may require the

use of portable transfer pumps and hoses.

0 C. The processed liquids are directed to the monitor tanks to be analyzed and discharged to the Missouri River through the overboard discharge

piping.

0 D. The depleted resins in the demineralization system vessels are sluiced into a transport container to be shipped off-site.

0 0

RW-AD-300 Information Use Page 7 of 12 Process Control Program Revision 0 0 0

7.2.2 (continued) 0 E. When stabilization is required (i.e., Class B or C), then a High Integrity Container (HIC) shall be used.

7.2.3 Filters S

A. Used filter cartridges originate from the purification filters, the waste filters, the spent fuel pool cooling system filter, and ultrasonic cleaning unit.

0 B. Filters are removed from their respective system and permitted to drain excess liquids from the elements.

0 C. The filters are then transferred in a container for disposal.

1. When stabilization is required, (i.e. Class B or C) the filters shall be disposed of in a HIC.

0 7.2.4 Oil A. Oil generated during operation and maintenance is collected in containers in appropriate approved areas of the plant.

B. The filled and labeled containers are sealed and moved to available areas for temporary storage. 0 0

C. Oils may be shipped off site to a contracted and licensed vendor for processing or incineration.

0 7.2.5 Dry Active Waste A. Dry Active Wastes are collected from radiologically controlled areas throughout the plant.

0 B. The waste is sorted to remove reusable and wet items at the source of generation.

0 C. The Dry Waste material is then collected in a vendor's container, metal boxes or metal drums. Material with elevated dose rates will be segregated for shielded transport (cask) to the vendor processing facility.

0 0

RW-AD-300 Information Use Page 8 of 12 Process Control Program Revision 0 0* 7.2.6 Non-Standard Waste A. Reactor components and irradiated hardware are waste which are not routinely generated.

B. These types of non-standard waste will be handled on a case-by-case

basis through the implementation of special procedures approved by the Plant Review Committee.

7.3 Process Control 7.3.1 Radioactive waste processing instrumentation and equipment shall be subject to formal calibration and preventative maintenance programs.

7.3.2 Primary and Radwaste Liquid Processing Resin A. Primary resins will be transferred into containers for processing using

plant installed and vendor supplied equipment.

B. Radwaste Liquid Processing will be performed using a vendor supplied FIX system.

C. Referenced Radwaste Procedures controlling the processing, transfer and dewatering activities shall be observed.

D. The vendor supplied system shall be operated in accordance with the

system operating procedures and applicable station Radwaste Procedures.

7.3.3 Filters A. Filter processing is controlled by referenced Radwaste Procedures.

B. Filters requiring stability are packaged as described in Section 7.2.3.

7.3.4 Oil A. Waste oil is collected in metal containers, sampled and transferred to a

) processing vendor.

7.3.5 Dry Active Waste 0

A. Dry Active Waste is processed in accordance with referenced Radwaste Procedures.

0 0

0 RW-AD-300 Information Use Page 9 of 12 Process Control Program Revision 0 0 7.3.6 Non-Standard Waste 0

A. These procedures would have to be written after the non-standard waste is identified.

7.4 Product Control S

7.4.1 A sample from each batch of waste shall be analyzed quantitatively for activity and isotopic identity as required in station procedures. If radionuclide distributions are shown to be consistent between similar batches, consideration may be given to decreasing the frequency of routine measurements. Frequency of sampling is as described in Radiation Protection Procedure RW-221, "10CFR61 Sampling". This constitutes the sampling plan.

0 7.4.2 Scaling factors for nuclides which are hard to identify are established for waste streams by using analyses performed and provided by an off-site vendor. 5 S

7.4.3 This frequency of sampling shall be raised or lowered based upon consideration of waste stream or radionuclide characteristics. Factors which would influence this consideration include the frequency of process vessel changeout or waste shipment, the difficulty (e.g. Costs, occupational exposures) in obtaining a representative sample of a particular waste stream, the variability of the radionuclide distribution within the waste stream over time, and the availability of analytical capability for particular radionuclides.

If radionuclide distributions are shown to be consistent between similar batches, consideration may be given to decreasing the frequency of routine measurements. If onsite samples show a variation from presently used scaling factors by more than a factor of 10, samples will be sent offsite for analysis to establish new scaling factors.

7.5 Training S

7.5.1 Processing of solid radioactive waste shall be performed by qualified and 5 trained personnel.

7.5.2 Training records of processing personnel shall be maintained by the Training Division.

7.6 Procedure Control S

7.6.1 On site processing of radioactive waste shall be performed in accordance with approved station procedures.

7.6.2 Procedures for processing, containerization and transport of wastes shall ensure that specific DOT, 10CFR and burial site requirements are satisfied.

S S

0

RW-AD-300 Information Use Page 10 of 12

Process Control Program Revision 0 0

0 7.6.3 Procedures for specific radwaste systems supplied by vendors for on-site

processing shall be reviewed and referenced in station procedures.

0 7.7 Records 7.7.1 Waste classification records, waste form records and other records required

for the preparation of the Fort Calhoun Station Unit No. 1 Annual Radioactive Effluent Release Report shall be prepared and retained in accordance with the requirements of 10CFR20, 10CFR71, 10CFR72, 49CFR1 70-178 and the

Fort Calhoun Station Technical Specifications.

0 7.7.2 Records of processing data, test and analysis results and results of training, inspection and audits are retained in accordance with the Fort Calhoun

Station Quality Assurance Plan and applicable station Administrative Procedures.

7.7.3 All certificates of compliance, licenses, criteria and regulations pertaining to

processing, packaging, shipment and disposal of radioactive materials

controlled under this Process Control Program shall be maintained in the most current status. OPPD, Fort Calhoun Station Unit No. 1 shall be currently registered, as necessary, to use applicable packagings.

7.8 Quality Assurance 7.8.1 Quality Assurance shall be maintained as defined by the Fort Calhoun

Station Quality Assurance Plan, Section 11.

7.8.2 The QA Plan shall ensure compliance with NRC and burial site criteria for 0*waste classification and waste form.

7.8.3 Audits shall be conducted in accordance with NQA Audit Section Instructions.

7.8.4 The Topical Reports of vendor supplied radwaste processing systems shall

undergo review either by the Supervisor-Radioactive Waste Operations or the Manager-Radiation Protection. The review shall ensure the vendor

supplied system will be compatible with plant operations and that the Topical

report has been submitted to the NRC for review. The review shall be

documented by a memo addressed to file.

7.8.5 Audits of a sampling of implementing procedures shall be performed at least

once every 24 months. Procedures should be reviewed to ensure continual

compliance with the requirements and process parameters of this Process Control Program.

7.8.6 Radioactive wastes not described within this document must be evaluated

and approved for inclusion in this Process Control Program or in a vendor Process Control Program prior to processing.

0 0

0 RW-AD-300 Information Use Page 11 of 12 Process Control Program Revision 0 0 0

0 7.9 Revisions 0

7.9.1 Changes or modifications made to design and/or operation of radioactive waste processing, treatment and/or packaging systems or activities, as described within this Process Control Program, shall require formal engineering evaluation and performance of a 50.59 review in accordance with 10CFR50.59.

7.9.2 Changes made to this Process Control Program and supporting engineering, S 50.59 reviews shall be reviewed and approved by the Plant review Committee prior to implementing the changes.

7.9.3 Changes to the Process Control Program approved by the Plant Review Committee shall be submitted to the Nuclear Engineer-In-Charge of Licensing, for input to the Annual Radioactive Effluent Release Report and USAR applicability.

0

8.0 REFERENCES

AND COMMITMENTS 8.1 Fort Calhoun Station Unit No. 1 Technical Specifications Sections 5.18 and 5.9.4 0

8.2 Fort Calhoun Station Unit No. 1, Updated Safety Analysis Report 8.3 RW-201, Control of Containers 0

8.4 RW-202, Collection/Sorting/Segregation of Dry Active Waste (DAW) 5 8.5 RW-204, Packaging Non-Compactable Dry Active Waste 0

8.6 RW-206, Transfer of Spent Primary Resin to Disposal Containers 8.7 RW-207, Operation of the Fix Radwaste Liquid Processing System 0

8.8 RW-208, Transfer of Spent Fix System Resin to Disposal Containers 8.9 RW-209, Dewatering Spent Radwaste Liquid Processing Resin and Primary Resin in Disposal Containers 8.10 RW-21 1, Storage of Filters from Radwaste Systems 5 0

8.11 RW-214, Collection of Oils 8.12 RW-216, Testing of Sorbent Materials 0 8.13 RW-218, 10CFR61 Classification 5 8.14 RW-221, 10CFR61 Sampling 0

0

0 0 RW-AD-300 Information Use Page 12 of 12 Process Control Program Revision 0 0

S

8.15 Current Vendor Processing Topical Report S

8.16 Current Vendor Operating Procedures as referenced in RW-207 8.17 49CFR Parts 170 through 178 0

8.18 10CFR Parts 20, 50, 61, and 71 8.19 USNRC Low Level Waste Licensing Branch; Technical Position on Radioactive Waste

Classification, Current Revision 8.20 USNRC Low Level Waste Licensing Branch; Technical Position on Waste Form,

Current Revision 0

8.21 FCS Quality Assurance Plan, Section 11.1 and 11.2 9.0 ATTACHMENTS 0 ~None 0

0 0

SECTION VII S

ATTACHMENT 2 JOINT FREQUENCY DISTRIBUTION WIND DIRECTION VS. WIND SPEED BY STABILITY CLASS AND METEOROLOGICAL DATA (Regulatory Guide 1.21) 0 January 1, 2012 - December 31, 2012 0 0

0 0

S 0

0 0

0 S

0 0

0 VII-2 0

0 S

0 JOINT FREQUENCY DISTRIBUTION WIND DIRECTION VS. WIND SPEED BY

STABILITY CLASS AND METEOROLOGICAL DATA 0

A. Meteorological Data Recovery 5Data availability from the on-site weather tower for the period

January 1, 2012 through December 31, 2012 was greater than the

D previous 12 months due to the onsite meteorological tower being repaired

on March 8, 2012 following the 2011 damage from flood waters. This resulted in a cumulative recovery rate of 80.84% from the meteorological

tower with the remaining 19.16% provided by Eppley Airfield Weather

Station, a branch of the National Weather Service. The data provided by

Eppley Airfield Weather Station was treated in accordance with monthly correction factors and a proceduralized Pasquill-Turner transformation which utilizes solar angle, time of day, cloud cover, and wind speed to

determine the Pasquill Class. The following table is a summary of the

parameters and their respective recovery rates for the period. The higher

fraction of offsite data produced more conservative results than a data set calculated using > 95% onsite data. The 2012 calculations, although

statistically different from previous data sets, is bounded by USAR

estimates.

The tabulations of the Weather Tower Data for the period January 1, 2012 through December 31, 2012 look appropriate for the season indicated.

The Pasquill Classes observed for the twelve-month period are detailed

below.

Pasquill Class A B C D E F G Total

% Obs. 2.42 3.19 6.10 47.89 24.26 9.68 6.46 100 On the basis of the data and its cross-checks, the weather data as

amended is completely valid for use in tabulating atmospheric releases.

0S 0

0 0

VII-3 0

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS EXTREMELY UNSTABLE (delta T/ delta z < -1.9)

PERIOD OF RECORD: JAN 2012 - DEC 2012 PASQUILL A WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 0 0 2 1 7 9 4 1 0 0 0 24 NNE 0 0 1 0 1 3 0 0 0 0 0 5 NE 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 1 0 0 0 0 0 1 E 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 1 0 0 0 0 0 1 SE 0 0 0 0 1 1 0 1 0 0 0 3 SSE 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 1 1 0 0 2 SSW 0 0 1 0 0 0 1 2 2 0 0 6 SW 0 0 0 1 1 2 0 0 0 0 0 4 WSW 0 0 0 1 4 4 0 0 0 0 0 9 W 0 0 1 1 8 5 1 0 0 0 0 16 WNW 0 1 1 6 9 11 3 4 0 0 0 35 NW 0 0 1 2 9 17 15 13 9 0 0 66 NNW 0 0 2 1 9 12 9 3 1 0 0 38 Total 0 1 9 13 49 66 33 25 13 0 0 209 Number of Calms 1 Number of Invalid Hours 0 Number of Valid Hours 210 VII-4

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS MODERATELY UNSTABLE (-1.9 <= delta T/ delta z <= -1.7)

PERIOD OF RECORD: JAN 2012 - DEC 2012 PASQUILL B WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >

Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 0 1 5 7 21 10 1 0 0 0 0 48 NNE 0 0 0 0 2 0 1 0 0 0 0 3 NE 0 0 1 2 1 0 0 0 0 0 0 4 ENE 0 0 0 1 2 0 0 0 0 0 0 3 E 0 1 1 0 0 0 0 0 0 0 0 3 ESE 0 0 0 0 0 2 4 0 0 0 0 6 SE 0 0 0 0 0 1 3 0 1 0 0 5 SSE 0 0 0 1 1 0 0 1 0 0 0 3 S 0 0 0 0 0 0 1 3 4 0 0 8 SSW 0 0 0 0 0 3 5 0 6 0 0 14 SW 0 0 0 2 0 0 3 0 1 0 0 6 WSW 0 0 1 0 3 0 0 1 0 0 0 5 W 0 0 0 1 3 1 1 0 0 0 0 6 WNW 1 0 0 2 4 1 1 1 1 0 0 11 NW 0 1 1 5 8 12 9 6 3 0 0 46 NNW 0 0 2 4 27 33 23 9 7 1 0 106 Total 1 3 11 25 72 63 52 21 23 1 0 272 Number of Calms 5 Number of Invalid Hours 0 Number of Valid Hours 277 VII-5

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS SLIGHTLY UNSTABLE (-1.7 < delta T/ delta z <= -1.5)

PERIOD OF RECORD: JAN 2012 - DEC 2012 PASQUILL C WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >

Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 0 10 14 13 19 11 2 1 0 0 0 78 NNE 0 2 1 3 6 2 0 0 0 0 0 19 NE 0 1 3 1 4 0 0 0 0 0 0 9 ENE 0 0 3 1 5 2 0 0 0 0 0 11 E 0 4 0 2 3 2 0 0 0 0 0 12 ESE 0 5 2 0 2 3 3 0 5 4 0 33 SE 0 3 3 7 1 2 3 9 2 0 0 34 SSE 0 1 3 9 2 1 1 3 3 1 0 32 S 0 5 4 6 1 3 1 3 4 1 0 33 SSW 0 2 1 0 1 1 6 7 5 4 1 30 SW 0 1 2 3 4 2 1 2 1 0 0 21 WSW 0 1 1 2 3 4 0 0 .0 0 0 11 W 0 1 4 4 2 1 1 0 0 0 0 14 WNW 0 2 2 7 2 4 1 3 0 0 0 24 NW 1 2 1 6 10 10 6 4 5 0 0 50 NNW 0 3 8 16 29 27 18 9 2 1 0 119 Total 1 43 52 80 94 75 43 41 27 11 1 468 Number of Calms 62 Number of Invalid Hours 0 Number of Valid Hours 530 VII-6 OOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOO 0

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS NEUTRAL (-1.5 < delta T/ delta z <= -0.5)

PERIOD OF RECORD: JAN 2012 - DEC 2012 PASQUILL D WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 0 21 40 74 94 91 43 15 6 0 0 392 NNE 0 24 28 34 31 9 6 3 0 0 0 138 NE 0 9 21 32 25 Ii 0 0 0 0 0 98 ENE 2 10 16 21 39 20 2 1 0 0 0 i1 E 0 8 13 26 59 36 12 0 1 0 0 159 ESE 0 11 7 20 62 43 19 7 7 4 1 187 SE 0 7 10 35 61 59 68 50 52 7 0 359 SSE 0 4 7 32 79 102 79 95 138 35 3 576 S 0 1 5 22 67 67 78 107 121 46 6 522 SSW 1 2 6 16 28 32 54 40 59 27 6 271 SW 0 4 6 20 20 17 11 7 7 2 0 95 WSW 0 5 4 13 11 10 4 2 3 0 0 54 W 1 10 7 8 24 10 4 5 6 3 0 81 WNW 0 8 8 9 29 37 15 17 3 1 0 127 NW 1 7 27 33 80 69 57 46 33 5 0 363 NNW 0 11 28 76 177 145 110 49 21 4 0 628 Total 5 142 233 471 886 758 562 444 457 134 16 4108 Number of Calms 53 Number of Invalid Hours 0 Number of Valid Hours 4161 VII-7

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS SLIGHTLY STABLE (-0.5 < delta T/ delta z <= 1.5)

PERIOD OF RECORD: JAN 2012 - DEC 2012 PASQUILL E WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1 6.1- 8.1- >

Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 5 9 12 10 8 1 2 0 0 0 0 47 NNE 1 13 3 3 1 1 0 0 0 0 0 22 NE 0 15 10 8 2 0 0 0 0 0 0 35 ENE 3 16 10 8 3 0 0 0 0 0 0 40 E 0 15 27 10 13 4 1 0 0 0 0 70 ESE 0 11 23 34 46 11 1 1 0 0 0 127 SE 1 13 26 36 81 62 34 8 1 0 0 262 SSE 2 13 9 25 107 91 42 20 14 1 0 324 S 2 7 4 12 66 101 84 41 30 8 0 355 SSW 1 8 5 6 28 41 51 33 27 3 0 203 SW 3 6 4 6 13 11 10 8 2 0 0 63 WSW 5 8 6 1 6 5 0 0 0 0 0 31 W 2 20 10 7 11 7 1 0 0 0 0 58 WNW 8 49 25 10 15 6 0 0 0 0 0 113 NW 3 38 38 46 56 21 6 2 2 0 0 212 NNW 3 20 22 30 48 17 6 0 0 0 0 146 Total 39 261 234 252 504 379 238 113 76 12 0 2108 Number of Calms 0 Number of Invalid Hours 0 Number of Valid Hours 2108 VII-8

@@eeeee0eeeeeO0ee@@e@Oe@OeOO0e@@e0eeeeeee0e

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS MODERATELY STABLE (1.5 < delta T/ delta z <= 4.0)

PERIOD OF RECORD: JAN 2012 - DEC 2012 PASQUILL F WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >

Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 2 5 0 4 2 0 0 0 0 0 0 20 NNE 0 1 1 0 0 0 0 0 0 0 0 2 NE 1 5 3 1 0 0 0 0 0 0 0 10 ENE 0 6 3 0 0 0 0 0 0 0 0 9 E 4 13 11 2 3 0 0 0 0 0 0 33 ESE 1 17 15 7 12 0 0 0 0 0 0 62 SE 5 16 20 23 37 13 3 2 0 0 0 120 SSE 3 13 8 16 40 6 1 0 0 0 0 87 S 2 23 4 5 22 14 1 0 1 0 0 75 SSW 5 13 2 2 6 10 3 2 0 0 0 43 SW 12 16 5 2 5 0 0 0 0 0 0 42 WSW 16 21 2 1 1 2 1 0 0 0 0 44 W 14 40 8 1 3 2 0 0 0 0 0 68 WNW 14 77 17 4 4 2 0 0 0 0 0 118 NW 6 27 13 12 9 6 0 0 0 0 0 76 NNW 2 10 3 4 4 3 0 0 0 0 0 32 Total 87 303 115 84 148 58 9 4 1 0 0 809 Number of Calms 32 Number of Invalid Hours 0 Number of Valid Hours 841 VII -9

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS EXTREMELY STABLE (delta T/ delta z > 4.0)

PERIOD OF RECORD: JAN 2012 - DEC 2012 PASQUILL G WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 5 2 4 1 0 0 0 0 0 0 0 19 NNE 3 6 1 0 0 0 0 0 0 0 0 10 NE 5 7 2 0 0 0 0 0 0 0 0 15 ENE 4 12 2 0 0 0 0 0 0 0 0 18 E 10 20 3 3 1 0 0 0 0 0 0 37 ESE 9 41 15 6 5 3 0 0 0 0 0 81 SE 6 33 18 9 4 1 1 0 0 0 0 74 SSE 10 27 9 8 3 0 1 0 0 0 0 58 S 8 16 4 4 3 0 0 0 0 0 0 35 SSW 14 24 4 3 4 4 3 0 0 0 0 57 SW 11 17 1 0 3 1 0 0 0 0 0 37 WSW 9 14 2 1 0 0 0 0 0 0 0 29 W 15 8 2 1 0 0 0 0 0 0 0 30 WNW 4 13 6 2 1 0 0 0 0 0 0 26 NW 3 5 1 1 0 0 0 0 0 0 0 15 NNW 8 4 3 0 0 0 0 0 0 0 0 20 Total 124 249 77 39 24 9 5 0 0 0 0 527 Number of Calms 34 Number of Invalid Hours 0 Number of Valid Hours 561 Hours Accounted For: 8688 VII- 10

eeeee eOOe@@@*e@S@@O@@S@@O@O@O@@@@@@Oe Oe@*

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT EXTREMELY UNSTABLE (delta T/ delta z < -1.9)

PERIOD OF RECORD: JAN 2012 - DEC 2012 PASQUILL A WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >

Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total 0.02..0.01...0.08...0.10...0.05...0.01...0.00...0.00....

N .0.00 0.00 0.02 0.01 0.08 0.10 0.05 0.01 0.00 0.00 0.00 0.28 NNE 0.00 0.00 0.01 0.00 0.01 0.03 0.00 0.00 0.00 0.00 0.00 0.06 NE 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.00 ENE 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.01 E 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.00 ESE 0.00 0.00 0.00 0.00 0.01 0.01 0.00 0.00 0.00 0.00 0.00 0.01 SE 0.00 0.00 0.00 0.00 0.01 0.01 0.00 0.01 0.00 0.00 0.00 0.03 SSE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 S 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.01 0.00 0.00 0.02 SSW 0.00 0.00 0.01 0.00 0.00 0.00 0.01 0.02 0.02 0.00 0.00 0.07 SW 0.00 0. 00 0.00 0.01 0.01 0.02 0.00 0.00 0.00 0.00 0.00 0.05 WSW 0.00 0.00 0.00 0.01 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.10 W 0.00 0.00 0.01 0.01 0.09 0.06 0.01 0.00 0.00 0.00 0.00 0.18 WNW 0.00 0.01 0.01 0.07 0.10 0.13 0.03 0.05 0.00 0.00 0.00 0.40 NW 0.00 0.00 0.01 0.02 0.10 0.20 0.17 0.15 0.10 0.00 0.00 0.76 NNW 0.00 0.00 0.02 0.01 0.10 0.14 0.10 0.03 0.01 0.00 0.00 0.44 Total 0.00 0.01 0.10 0.15 0.56 0.76 0.38 0.29 0.15 0.00 0.00 2.41 Percent of Calms 0.01 Percent of Invalid Hours 0.00 Percent of Valid Hours 2.42 VII-11

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT MODERATELY UNSTABLE (-1.9 <= delta T/ delta z <= -1.7)

PERIOD OF RECORD: JAN 2012 - DEC 2012 PASQUILL B WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >

Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N..... 0..00... 0. 01... 0. 06... 0. 08... 0. 24... 0. 12... 0. 01... 0. 00... 0. 00... 0. 00... 0.0... 0..

55...

N 0.00 0.01 0.06 0.08 0.24 0.12 0.01 0.00 0.00 0.00 0.00 0.55 NNE 0.00 0.00 0.00 0.00 0.02 0.00 0.01 0.00 0.00 0.00 0.00 0.03 NE 0.00 0.00 0.01 0.02 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.05 ENE 0.00 0.00 0.00 0.01 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.03 E 0.00 0.01 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.03 ESE 0.00 0.00 0.00 0.00 0.00 0.02 0.05 0.00 0.00 0.00 0.00 0.07 SE 0.00 0.00 0.00 0.00 0.00 0.01 0.03 0.00 0.01 0.00 0.00 0.06 SSE 0.00 0.00 0.00 0.01 0.01 0.00 0.00 0.01 0.00 0.00 0.00 0.03 S 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.03 0.05 0.00 0.00 0.09 SSW 0.00 0.00 0.00 0.00 0.00 0.03 0.06 0.00 0.07 0.00 0.00 0.16 SW 0.00 0.00 0.00 0.02 0.00 0.00 0.03 0.00 0.01 0.00 0.00 0.07 WSW 0.00 0.00 0.01 0.00 0.03 0.00 0.00 0.01 0.00 0.00 0.00 0.06 W 0.00 0.00 0.00 0.01 0.03 0.01 0.01 0.00 0.00 0.00 0.00 0.07 WNW 0.01 0.00 0.00 0.02 0.05 0.01 0.01 0.01 0.01 0.00 0.00 0.13 NW 0.00 0.01 0.01 0.06 0.09 0.14 0.10 0.07 0.03 0.00 0.00 0.53 NNW 0.00 0.00 0.02 0.05 0.31 0.38 0.26 0.10 0.08 0.01 0.00 1.22 Total 0.01 0.03 0.13 0.29 0.83 0.73 0.60 0.24 0.26 0.01 0.00 3.13 Percent of Calms 0.06 Percent of Invalid Hours 0.00 Percent of Valid Hours 3.19 VII-12 OOOOOOOOOOOOOOOOOOOOOOOOOOOOO*OOOOOOOOOOOOOOO 0 0 00 00 0 0

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT SLIGHTLY UNSTABLE (-1.7 < delta T/ delta z <= -1.5)

PERIOD OF RECORD: JAN 2012 - DEC 2012 PASQUILL C WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >

Direct 0 .5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 0 .00 0.12 0.16 0.15 0.22 0.13 0.02 0.01 0.00 0.00 0.00 0.90 NNE 0 .00 0.02 0.01 0.03 0.07 0.02 0.00 0.00 0.00 0.00 0.00 0.22 NE 0 .00 0.01 0.03 0.01 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.10 ENE 0 .00 0.00 0.03 0.01 0.06 0.02 0.00 0.00 0.00 0.00 0.00 0.13 E 0 .00 0.05 0.00 0.02 0.03 0.02 0.00 0.00 0.00 0.00 0.00 0.14 ESE 0 .00 0.06 0.02 0.00 0.02 0.03 0.03 0.00 0.06 0.05 0.00 0.38 SE 0 .00 0.03 0.03 0.08 0.01 0.02 0.03 0.10 0.02 0.00 0.00 0.39 SSE 0 .00 0.01 0.03 0.10 0.02 0.01 0.01 0.03 0.03 0.01 0.00 0.37 S 0 .00 0.06 0.05 0.07 0.01 0.03 0.01 0.03 0.05 0.01 0.00 0.38 SSW 0 .00 0.02 0.01 0.00 0.01 0.01 0.07 0.08 0.06 0.05 0.01 0.35 SW 0 .00 0.01 0.02 0.03 0.05 0.02 0.01 0.02 0.01 0.00 0.00 0.24 WSW 0 .00 0.01 0.01 0.02 0.03 0.05 0.00 0.00 0.00 0.00 0.00 0.13 W 0 .00 0.01 0.05 0.05 0.02 0.01 0.01 0.00 0.00 0.00 0.00 0.16 WNW 0 .00 0.02 0.02 0.08 0.02 0.05 0.01 0.03 0.00 0.00 0.00 0.28 NW 0 .01 0.02 0.01 0.07 0.12 0.12 0.07 0.05 0.06 0.00 0.00 0.58 NNW 0 .00 0.03 0.09 0.18 0.33 0.31 0.21 0.10 0.02 0.01 0.00 1.37 Total 0 .01 0.49 0.60 0.92 1.08 0.86 0.49 0.47 0.31 0.13 0.01 5.39 Percent of Calms 0.71 Percent of Invalid Hours 0.00 Percent of Valid Hours 6.10 VII-13

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT NEUTRAL (-1.5 < delta T/ delta z <= -0.5)

PERIOD OF RECORD: JAN 2012 - DEC 2012 PASQUILL D WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >

Direct 0 .5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 0).00 0.24 0.46 0.85 1.08 1.05 0.49 0.17 0.07 0.00 0.00 4 .51 NNE 0 .00 0.28 0.32 0.39 0.36 0.10 0.07 0.03 0.00 0.00 0.00 1.59 NE 0 .00 0.10 0.24 0.37 0.29 0.13 0.00 0.00 0.00 0.00 0.00 1.13 ENE 0 .02 0.12 0.18 0.24 0.45 0.23 0.02 0.01 0.00 0.00 0.00 1.28 E 0 .00 0.09 0.15 0.30 0.68 0.41 0.14 0.00 0.01 0.00 0.00 1.83 ESE 0 .00 0.13 0.08 0.23 0.71 0.49 0.22 0.08 0.08 0.05 0.01 2 .15 SE 0 .00 0.08 0.12 0.40 0.70 0.68 0.78 0.58 0.60 0.08 0.00 4 .13 SSE 0 .00 0.05 0.08 0.37 0.91 1.17 0.91 1.09 1.59 0.40 0.03 6 .63 S 0 .00 0.01 0.06 0.25 0.77 0.77 0.90 1.23 1.39 0.53 0.07 6.01 SSW 0 .01 0.02 0.07 0.18 0.32 0.37 0.62 0.46 0.68 0.31 0.07 3 .12 SW 0 .00 0.05 0.07 0.23 0.23 0.20 0.13 0.08 0.08 0.02 0.00 1.09 WSW 0 .00 0.06 0.05 0.15 0.13 0.12 0.05 0.02 0.03 0.00 0.00 0 .62 W 0 .01 0.12 0.08 0.09 0.28 0.12 0.05 0.06 0.07 0.03 0.00 0 .93 WNW 0 .00 0.09 0.09 0.10 0.33 0.43 0.17 0.20 0.03 0.01 0.00 1.46 NW 0 .01 0.08 0.31 0.38 0.92 0.79 0.66 0.53 0.38 0.06 0.00 4 .18 NNW 0 .00 0.13 0.32 0.87 2.04 1.67 1.27 0.56 0.24 0.05 0.00 7.23 Total 01.06 1.63 2.68 5.42 10.20 8.72 6.47 5.11 5.26 1.54 0.18 47.28 Percent of Calms 0.61 Percent of Invalid Hours 0.00 Percent of Valid Hours 47.89 VII-14

e...@@@@@e.@.@..@...@Oeee.@@@OOOOOOO@@eO@OO Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT SLIGHTLY STABLE (-0.5 < delta T/ delta z <= 1.5)

PERIOD OF RECORD: JAN 2012 - DEC 2012 PASQUILL E WIND SPEED (m/s) AT 10-m LEVEL Wind 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >

Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total 0.01.. 0. 02... 0. 00... . 00... 0. 00..

N 0.06 0.10 0 .14 0 .12 0.09 0.01 0.02 0.00 0.00 0.00 0.00 0. 54 NNE 0.01 0.15 0 .03 0. 03 0.01 0.01 0.00 0.00 0.00 0.00 0.00 0.25 NE 0.00 0.17 0 .12 0.09 0 .02 0.00 0.00 0.00 0.00 0.00 0.00 0.40 ENE 0.03 0.18 0. 12 0.09 0.03 0.05 0.00 0.00 0.00 0.00 0.00 0.46 E 0.00 0.17 0.31 0 .12 0 .15 0.05 0.01 0.00 0.00 0.00 0.00 0.81 ESE 0.00 0.13 0.26 0.39 0 .53 0.13 0.01 0.01 0.00 0.00 0.00 1.46 SE 0.01 0.15 0.30 0.41 0 93 0.71 0.39 0.09 0.01 0.00 0.00 3 .02 SSE 0.02 0.15 0 .10 0.29 1.23 1.05 0.48 0.23 0.16 0.01 0.00 3 .73 S 0.02 0.08 0.05 0. 14 0.76 1.16 0.97 0.47 0.35 0.09 0.00 4.09 SSW 0.01 0.09 0.06 0.07 0.32 0.47 0.59 0.38 0.31 0.03 0.00 2 .34 SW 0.03 0.07 0 .05 0.07 0 .15 0.13 0.12 0.09 0.02 0.00 0.00 0 .73 WSW 0.06 0.09 0.07 0.01 0.07 0.06 0.00 0.00 0.00 0.00 0.00 0.36 W 0.02 0.23 0 12 0.08 0 .13 0.08 0.01 0.00 0.00 0.00 0.00 0.67 WNW 0.09 0.56 0.29 0 .12 0 .17 0.07 0.00 0.00 0.00 0.00 0.00 1.30 NW 0.03 0.44 0.44 0 .53 0 .64 0.24 0.07 0.02 0.02 0.00 0.00 2 .44 NNW 0.03 0.23 0.25 0.35 0 .55 0.20 0.07 0.00 0.00 0.00 0.00 1.68

24.26-Total 0.45 3.00 2.69 2.90 5.80 4.36 2.74 1.30 0.87 0.14 0.00 24.26 Percent of Calms 0.00 Percent of Invalid Hours 0.00 Percent of Valid Hours 24.26 VII-15

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT MODERATELY STABLE (1.5 < delta T/ delta z <= 4.0)

PERIOD OF RECORD: JAN 2012 - DEC 2012 PASQUILL F WIND SPEED (m/s) AT 10-m LEVEL Wind 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >

Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total 0.00 0.23 N 0.02 0.06 0.00 0.05 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.02 NNE 0.00 0.01 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.12 NE 0.01 0.06 0.03 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.10 ENE 0.00 0.07 0.03 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.38 E 0.05 0 .15 0.13 0.02 0.03 0.00 0.00 0.00 0.00 0.00 0.00 0.71 ESE 0.01 0.20 0.17 0.08 0.14 0.00 0.00 0.00 0.00 0.00 SE 0.06 0 .18 0.23 0.26 0.43 0.15 0.03 0.02 0.00 0.00 0.00 1.38 SSE 0.03 0 .15 0.09 0.18 0.46 0.07 0.01 0.00 0.00 0.00 0.00 1.00 S 0.02 0.26 0.05 0.06 0.25 0.16 0.01 0.00 0.01 0.00 0.00 0.86 SSW 0.06 0 .15 0.02 0.02 0.07 0.12 0.03 0.02 0.00 0.00 0.00 0.49 SW 0.14 0 .18 0.06 0.02 0.06 0.00 0.00 0.00 0.00 0.00 0.00 0.48 WSW 0.18 0.24 0.02 0.01 0.01 0.02 0.01 0.00 0.00 0.00 0.00 0.51 W 0.16 0.46 0.09 0.01 0.03 0.02 0.00 0.00 0.00 0.00 0.00 0.78 WNW 0.16 0.89 0.20 0.05 0.05 0.02 0.00 0.00 0.00 0.00 0.00 1.36 NW 0.07 0.31 0.15 0.14 0.10 0.07 0.00 0.00 0.00 0.00 0.00 0.87 NNW 0.02 0 .12 0.03 0.05 0.05 0.03 0.00 0.00 0.00 0.00 0.00 0.37 Total 1.00 3.49 1.32 0.97 1.70 0.67 0.10 0.05 0.01 0.00 0.00 9.31 Percent of Calms 0.37 Percent of Invalid Hours 0.00 Percent of Valid Hours 9.68 VII-16

@Oe@@O@O0e@OO@OO@@Oe@OO0ee@@@eO@@@@oO0e@@@@

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT EXTREMELY STABLE (delta T/ delta z > 4.0)

PERIOD OF RECORD: JAN 2012 - DEC 2012 PASQUILL G WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >

Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N.....0..06..0.02...0.05....0.01..0.00...0.00...0.00...0.00...0.00...0.00...0.00...0.22....

N 0.06 0.02 0.05 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.22 NNE 0.03 0.07 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.12 NE 0.06 0.08 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.17 ENE 0.05 0.14 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.21 E 0.12 0.23 0.03 0.03 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.43 ESE 0.10 0.47 0.17 0.07 0.06 0.03 0.00 0.00 0.00 0.00 0.00 0.93 SE 0.07 0.38 0.21 0.10 0.05 0.01 0.01 0.00 0.00 0.00 0.00 0.85 SSE 0.12 0.31 0.10 0.09 0.03 0.00 0.01 0.00 0.00 0.00 0.00 0.67 S 0.09 0.18 0.05 0.05 0.03 0.00 0.00 0.00 0.00 0.00 0.00 0.40 SSW 0.16 0.28 0.05 0.03 0.05 0.05 0.03 0.00 0.00 0.00 0.00 0.66 SW 0.13 0.20 0.01 0.00 0.03 0.01 0.00 0.00 0.00 0.00 0.00 0.43 WSW 0.10 0.16 0.02 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.33 W 0.17 0.09 0.02 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.35 WNW 0.05 0.15 0.07 0.02 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.30 NW 0.03 0.06 0.01 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.17 NNW 0.09 0.05 0.03 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.23 Total 1.43 2.87 0.89 0.45 0.28 0.10 0.06 0.00 0.00 0.00 0.00 6.07 Percent of Calms 0.39 Percent of Invalid Hours 0.00 Percent of Valid Hours 6.46 Percent of Hours Accounted For: 100.00 VII- 17

0 0

0 Joint Frequency Distribution 2012 FCS Meterological Tower 0

N 0 12.52 0

7.00 0

0 0

0 0 W E 0

0 0

S Calms excluded.

3.5 6.9 11.5 18.4 24.2 Rings drawn at 5% intervals.

0.1 Wind flow is FROM the directions shown.

Wind Speed (Miles Per Hour) No observations were missing.

LIC-13-0043, Submittal of Radiological Effluent Operating Environmental Release Report for Year 2012

Contents

Text

Reference:

SUBJECT:

Enclosures:

1.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

8.0 REFERENCES

Navigation menu

LIC-13-0043, Submittal of Radiological Effluent Operating Environmental Release Report for Year 2012

Text

Reference:

SUBJECT:

Enclosures:

1.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

8.0 REFERENCES

Navigation menu

Search