ML090690306

Boiling Water Reactor (LACBWR) - Offsite Dose Calculation Manual, Revision 11

ML090690306
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	12/03/2008
From:	Berg W Dairyland Power Cooperative
To:	NRC/FSME
References
LAC-14058
Download: ML090690306 (102)

Text

I.

LA CROSSE BOILING WATER REACTOR (LACBWR)

OFFSITE DOSE CALCULATION MANUAL Prepared by. /-ý?'

Date IeI2r Health Physics Review:____ ______

Date Radiation Protection Engineer Review: Jz -17eF?

• 1/7 / Date Quality Assurance Review:

Date ORC Approved:

Date December 2008 Revision 11 Dairyland Power Cooperative 3200 East Avenue South La Crosse, WI 54602-0817 I

TABLE OF CONTENTS

1. INT R O DUC T IO N................................................................................ 1 N

1.1 Pu rp os e .............................................................................. . .... 1 1 .2 De fin itio n s ................................................................................ . 1

<'9c E

0

2. OFFSITE DOSE CALCULATIONS ......................................................... 5 2.1 Compliance with the Limitations for Liquid Effluent Releases ............... 5 2.2 Compliance with the Limitations for Gaseous Effluent Releases ........... 12 C:

3. RADIOACTIVE EFFLUENT CONTROL PROGRAM ................................ 35 3.1 Program Requirements ............................................................... 35 3 .2 Liq u id E fflue nts .......................................................................... 36 3.2.1 Sampling and Analysis ....................................................... 36 3.2.2 Liquid Effluent Release Limitation ......................................... 38 3.2.3 Liquid Effluent Instrumentation ............................................. 39 3.3 Gaseous Effluents ...................................................................... 43 3.3.1 Reactor Building Ventilation ................................................ 43 3.3.2 Stack Effluent Sampling and Analyses .................................. 43 3.3.3 Stack Effluent Release Limitation ......................................... 45 E 3.3.4 Instrumentation ................................................................ 49 CU 3.4 Total Dose to a Member of the Public ............................................. 53

4. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ............... 55 4.1 Program Requirements ............................................................... 55 4.2 REMP Description ...................................................................... 56 4.3 REMP Lower Limits of Detection ................................................... 59

.Se z

>0 4.3.1 Calculation of Lower Limits of Detection ................................. 60 4.4 Interlaboratory Comparison Program .............................................. 62 4.5 Reporting Requirements ............................................................. 62 ODCM i Rev. 11

LIST OF TABLES 2.1 Infant Dose Factors Pi (Inhalation) for H-3 and Particulate 2 Gaseous Release Monitor Alarm Setpoint Determinations ........................ 24 E 3.1 Radioactive Liquid Waste Sampling and Analysis Requirements 0

for B atch R eleases ...................................................................... .... 37 3.2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance R eq u ire me nts ................................................................................. 41 0 1 3.3 Radioactive Gaseous Waste Sampling and Analysis .............................. 44 CO a) C 3.4 Radioactive Gaseous Effluent Monitoring Instrumentation ........................ 51

- 3.5 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance

! R e q uire m e nts ............................................................................. ... . 52 OWW C:

4.1 Radiological Environmental Monitoring Program .................................... 57 4 2 E v r n s ....

em tlSa ple

... .... ... ... .... ... .... ... ... .... ... .... ... ... ...................... 61 4.3 Reporting Levels for Radioactivity Concentrations in Environmental

~0 0~ E

,-0

-J ODCM ii Rev. 11

LIST OF FIGURES 2.1 Liquid Release Monitor Alarm Setpoint Determination ............................. 8 2.2 Noble Gas (Kr-85) Release Monitor Alarm Setpoint Calculations ............... 16 0

2.3 Noble Gas (Kr-85) Release Monitor Alarm Setpoint Summary .................... 17 2.4 H-3 and Particulate Gaseous Release Monitor Alarm Setpoint 0 D e te rm ina tio n ................................................................................. 22 2.5 H-3 and Particulate Gaseous Release Monitor Alarm Setpoint Summary ..... 23 2.6 Air Dose Commitment to a Member of the Public from Noble Gas (K r-8 5) R e le ase .............................................................................. 27 LIST OF DIAGRAMS 1.1 Site Map, Including Effluent Release Boundary ...................................... 4 CO C'0

'a

>~ 0

~UJ 0z ODCM iii Rev, 11

1.0 INTRODUCTION

1.1 Purpose L0 The OFFSITE DOSE CALCULATION MANUAL (ODCM) contains the tE methodology and parameters used in (1) the calculation of offsite doses resulting 0

from radioactive gaseous and liquid effluents from LACBWR, and (2) the a) calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints. The ODCM also contains the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs.

0*~

1.2 Definitions P CHANNEL CALIBRATION

'0 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the (Dchannel C-output such that it responds with the necessary range and accuracy to

-L known values of the parameter which the channel monitors. The CHANNEL a- CALIBRATION shall encompass the entire channel including the sensor and

-c alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of

sequential, overlapping or total channel steps such that the entire channel is calibrated.

"o CHANNEL CHECK z

Mo U)

UJ A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where

<possible, comparison of the channel indication and/or status with other ODCM 1 Rev. 11

\K indications and/or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST 2

E, A CHANNEL FUNCTIONAL TEST shall be:

0 C-)

Qa. Analog channels - the injection of a simulated signal into the channel as Xclose to the sensor as practicable to verify OPERABILITY including alarm C:

0 and/or trip functions and channel failure trips.

b. Bistable channels - the injection of a real or simulated signal into the (QQ° sensor to verify OPERABILITY including alarm and/or trip functions.

EFFLUENT RELEASE BOUNDARY The Dairyland Power Cooperative property line within the 1109 ft. (338m) radius EXCLUSION AREA is the EFFLUENT RELEASE BOUNDARY.

"E (See Diagram 1.1.)

ac)

CD EXCLUSION AREA 2 The EXCLUSION AREA is defined as the area within an 1109 ft. (338m) radius ofrom the centerline of the Reactor Building. This was the area established per 10 CFR 100 as the EXCLUSION AREA for plant siting and operation.

--z MAXIMUM PERMITTED CONCENTRATION (MPC) uJ 0z The limiting liquid effluent concentration value 10 CFR 20, Appendix B, Table 2, Column 2.

-J ODCM 2 Rev. 11

MEMBER OF THE PUBLIC MEMBER OF THE PUBLIC shall mean an individual in a CONTROLLED or UNRESTRICTED AREA. However, an individual is not a MEMBER OF THE dose.

the individual receives an occupational E< PUBLIC during any period in which 0

U OPERABLE-OPERABILITY A system, subsystem, train, component or device shall be OPERABLE or have 0

OPERABILITY when it is capable of performing its specified function(s) and (when 0 all necessary attendant instrumentation, controls, a normal or an emergency electrical power source, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function(s) are also capable of performing their related support function(s).

SOURCE CHECK UJ~0 response

-o SOURCE CHECK shall be the qualitative assessment of channel (0  ;:- A when the channel sensor is exposed to a radioactive source.

O)

L~ z U>-

-LJ ODCM 3 Rev. 11

F " Diagram 1.1 SITE MAP INCLUDING EFFLUENT RELEASE BOUNDARY o -0mTEOROLOGICAL TOWER SCALE.

E 1 0 400,So 0

A C, ,7 0

C) PoiT(350) 0- C) 0 ;10HOUS j6~t~u 21*,,*2 MIL IECLIJ',

C' 0 IVDAX

/

-" RE*AS* ..,---LtQUtO EFF'L/EtJJ1 co* MODDA ' V CIO.G1 E I"J

/ATEL g

0 cu)

C13 Q 0*

ODCM 4 Rev. 11

2.0 OFFSITE DOSE CALCULATIONS 2.1 Compliance with the Limitations for Liquid Effluent Releases a) To assure compliance with the limitations of Section 3.2.2.a, Radioactive Effluent Control Program (RECP), the radioactivity monitor alarm setpoint 0

is calculated for the monitor as a function of the maximum effluent flow V rate and the minimum dilution flow rate. The following equation is used to calculate setpoints:

af

<5C (2.1) k( F+f) where:

C= the effluent concentration limit implementing 10 CFR 20 for LACBWR, in pCi/ml.

CU C a = the setpoint (in CPS above background) of the radioactivity monitor 0 >measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, which is inversely proportional to the volumetric flow of the effluent line (f) and proportional to the volumetric flow of the dilution stream plus the effluent stream (F + f), represents a value which, if exceeded, could result in concentrations exceeding the limits of 10 CFR 20.

Szk = the conversion factor, cps per 1aCi/ml, for the liquid waste effluent 0 z monitor based upon most recent calibration of the monitor.

CU>.

ODCM 5 Rev. 11

f= the effluent line volumetric flow setpoint as measured at the C radiation monitor location, in gallons per minute.

F = the dilution stream (LACBWR & Genoa Station No. 3 [G-3]

Condenser Cooling Water) volumetric flow, in gallons per minute.

E Since f << F, Equation 2.1 is satisfied when the following discharge line

.> radioactivity monitor setpoint is met:

kCF cc a < (2.2)

O) f 0

CO Calculation of Instantaneous Allowable Release Rates 0-~

"- LACBWR's liquid radwaste is released in batches. In order to assess the required radioactive liquid effluent line monitor setpoint, a, the following step-by-step method for obtaining data will be performed. The form presented in Figure r-* 2.1 may be used as a worksheet for these calculations. The alarm setpoint CLU 0

E calculation may be performed on an annual basis if the setpoint is determined to 2o5 0be sufficiently conservative so as to prevent exceeding 0.5 MPC at the discharge point where MPC is the isotope weighted effluent concentration release limit for a

( typical LACBWR waste batch based on 10CFR20, appendix B, Table 2, Col. 2 0values.

1. Go to Figure 2.1 Enter the date on the form.

U)

.I > 02. Enter the concentration C, ([tCi/ml) for each isotope i, in a typical 0 z LACBWR waste batch.

J9>

ODCM 6 Rev. 11

3. The values of f and F are determined and recorded at the top of C Figure 2.1. F is the minimum volumetric dilution flow rate during releases at the LACBWR - G-3 outfall which is equal to the LACBWR condenser cooling water flow rate plus the G-3 condenser cooling water volumetric flow, in gallons per minute. The value f is the maximum radioactive liquid E

0 release flow rate (GPM) for the batches discharged during the period. A value of 17 GPM is normally specified for f.

(D Cl)

4. The quantities Ci, and Cj/MPCG are determined and recorded.

0C1N

5. The monitor conversion factor, k, determined at last primary calibration is C) recorded on Figure 2.1, in cps (net) per ltCi/ml.

CN

6. The alarm setpoint, a (cps), with a 0.5 factor for conservatism, for the

, *,lmonitor measuring radioactivity in the liquid effluent line is then I*

a) M determined by:

0.5 kF

• Ci (2.3)

.L~ f Ci/MPCi CC)

C4 U) .-

04 ODCM 7 Rev. 11

F- L Figure 2.1 LIQUID RELEASE MONITOR W

ALARM SETPOINT DETERMINATION Date Maximum Liquid Release Rate for Period, f= GPM Minimum Dilution Flow Rate for Period, F= GPM E

0 0

Average Concentra- MPCG (10 CFR a) a) Nuclide i tion (in Tanks), Part 20, Appendix B C /MPCG 0 Ci (pCi/ml) Table 2, Col. 2)

CL 0

Co-60 3 E-06 Cs-1 37 1 E-06 CWC.'

a) Cs-134 9 E-07 0 C)'

Sr-90 5 E-07 Fe-55 1 E-04 (D

a)

(D Ci Ci/MPCi =

a) 2 0

E

>5 Monitor Conversion Factor, k = cps(net) cu

[Ci/ml 00 C)

C) 0.5 kF Y Ci a <

(alarm setpoint) f Y Ci/MPCG cps above background 0

z 0

>5 CD,

-j wU z

.J ODCM 8 Rev. 11

b) To demonstrate compliance with the limitations of Section 3.2.2.b, dose contributions are calculated at a maximum interval of once every calendar quarter for all radionuclides identified in liquid effluents released to 2 unrestricted areas using the methodology presented in NRC Regulatory Guide 1.109, Rev. 1, October 1977. This methodology takes the form of 0 the following general equation:

0 m

Dar = " (Aair I" Cj/Fj) (2.4) i j=1 0

where:

CDC Da, = the cumulative dose commitment to the total body or any organ T of an individual in age group a from the liquid effluents released in m batches, in mRem.

Cj = the total quantity of radionuclide i, released by batch j, in Ci.

0) M 0 Ai = the site-related ingestion dose commitment factor to the total body or any organ T of an individual in age group a for each identified CD principal gamma and/or beta emitter, in mRem-gal-min- 1 -Ci-1.

F1 = the average dilution water flow rate during batch release j in C)(N gallons/minute.

Equation 2.4 requires the use of a dose factor Aai, for each nuclide, organ and M~ z individual in age group a which includes the factors which determine the ultimate 0zdose received such as pathway transfer factors (e.g., bioaccumulation factors),

pathway usage factors, ingestion dose factors and dilution factors. The following

< philosophy and site-specific conditions determine the site-specific factors ODCM 9 Rev. 11

r--

incorporated into the liquid effluent dose calculation model:

1. Liquid Dose Pathways Due to LACBWR's status as a fresh water site, there is no P

invertebrate pathway. The drinking water pathway is not included, Ej since the nearest community which obtains its drinking water 0 supply from the Mississippi River is located at Davenport, Iowa, which is 195 miles downstream. The drinking water pathway represents < 0.01% of the dose to any organ. The irrigated foods pathway is not included since the river water is not used for 0

irrigation in this area and the shoreline deposits pathway is o insignificant for the Mississippi River. The only significant dose pathway is the dose commitment due to ingestion of fish from the Mississippi River waters.

0--

2. Dilution The liquid effluent flow from the waste tanks is diluted by the combined total circulating water flow for condenser cooling at both LACBWR and G-3. For offsite dose calculations, no dilution by the Mississippi River flow is considered. Also, under SAFSTOR conditions batch discharges of liquid effluent normally take place during less than 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> per month (< 5% of the time). Therefore, no fish in the river are continuously exposed to a radioactive environment produced by LACBWR liquid effluent as assumed in the calculation of the published bioaccumulation factors for fish.

Based on the above site-specific criteria, the dose factor Aai, is defined as follows:

V

.T z (2.5)

>0 Aai, = K, (UFa)(BFi)(DFai) 0 W where:

Ko = a units conversion constant, 5.03 E5 =

4:

ODCM 10 Rev. 11

I(1 E12 pCi/Ci x .2642 gal/ t) / (8760 hrs/yr x 60 min/hr).

,J UFa = fish consumption usage factor for an individual in age group a, in kg/yr.

> BFi = the bioaccumulation factor in fish for nuclide i, in CL.. pCi/kg per pCi/ t.

0E DFai= the ingestion dose factor for age group a for nuclide i, 0,

o) in organ -r in mRem/pCi.

(D o=_ý Calculation of Dose Commitments from Liquid Effluents DThe equations for this calculation have been formatted on a computer-based Co spreadsheet. The values of UFa, BF,, and DFait specified in NRC Regulatory Guide 1.109 Rev. 1, October 1977, and the constant Ko have been entered on the spreadsheet.

" 4-- To perform the calculation the following information is entered in the appropriate C_-n cells of the spreadsheet for each liquid batch released during the period of 0

-* E interest:

1. Date

2. Release interval, hrs 1c 3. Waste volume, gal

4. Condenser cooling water flow rate, GPM

5. Activity concentration of each isotope, i, in waste, pCi/ml.

The spreadsheet program will then calculate and display the total quarterly dose

,A z 0in mRem to the total body and each organ of an individual in each age group.

0 z The cumulative calendar year doses and the percentage of the limits set forth in (9 Section 3.2.2.b are also calculated. This spreadsheet will also print the data tables for the liquid effluent section of the annual report.

ODCM 11 Rev. 11

2.2 Compliance with the Limitations for Gaseous Effluent Releases a) To assure compliance with the limitations of Section 3.3.3.a, alarm setpoints are established for the gaseous effluent monitor. These 01 setpoints are calculated or checked annually, or as required by procedure, to confirm that the current setpoints are set correctly for one- or two-stack 0

blower operation.

During SAFSTOR, the offgas treatment system from the condenser to the 0

stack is no longer in operation since the plant is shut down. The principal 0 potential gaseous release pathway is from the Reactor Building ventilation exhaust system. The only noble gas potentially available for release from the facility is Kr-85. The irradiated fuel assemblies stored in the Fuel C)

Element Storage Well (FESW) contain essentially all the Kr-85 inventory.

There is a very small potential for a Kr-85 release from the Waste Treatment and Turbine Building ventilation exhaust systems. This would GCa a-) be possible only if FESW water containing Kr-85 were transferred to the CL:

0 SE Spent Resin Receiving Tank (SRRT) or the Waste Water Tanks (WWT).

Activity in particulate form and H-3 can theoretically be released via any of these release pathways. There will be no radioiodine (1-131,1-133) releases since they are no longer being produced and, since shutdown, any residual activity has decayed to insignificant levels.

Noble -gases

-0 nz The following mathematical relationships shall be used to implement the above LUJ requirements for noble gas (Kr-85) release alarm setpoints:

0z

• T D =K' Q (x/Q) (DFB)

ODCM 12 Rev. 11

= K' Qv Fs (x /Q) (DFB) (2.6) 4S D = K' [1.11 Q(x /Q) DFY + Q(x /Q) (DFS)]

> K' Q, F, (x/Q) (1.11 DFY + DFS) (2.7) 0 where:

0 oT

_ *D = the dose rate in mRem/yr to the total body of an individual beyond the EFFLUENT RELEASE BOUNDARY due to Kr-85. This value is to be less than 500 mRem/yr.

0 K' = unit conversion constant, 1 E6 pCi/pCi.

0

-FS = volume flow rate in stack, cc/sec.

Co C1 NQ = average Kr-85 release rate, ptCi/sec.

QV average Kr-85 release concentration, !tCi/cc.

(xJQ) = atmospheric dispersion coefficient for instantaneous releases. (For the FAST alarm setpoint, 6.05 E-5 sec/m 3 is used, based upon Regulatory (D Guide 1.3 criteria. For the SLOW alarm setpoint, 3.90 E-6 sec/in is used, based upon actual historical monthly average xdQ values at the 0 worst case receptor location.)

• • DFB = the total body gamma dose factor for exposure to a semi-infinite cloud of Kr-85 = 1.61 E-5 mRem-m3 per pCi-yr.

°S C,

C) D = the dose rate to the skin of an individual at or beyond the EFFLUENT RELEASE BOUNDARY due to Kr-85. This value is to be less than 3000 mRem/yr.

1.11 = the ratio of the tissue to air energy absorption coefficients over the energy range of photons of interest. This converts dose (mRad) to dose

_z equivalent (mRem).

0 z DFY = the gamma air dose factor for exposure to semi-infinite cloud of Kr-85 =

1.72 E-5 mRad-m3 per pCi-yr.

DFS =the skin beta dose factor for exposure to a semi-infinite cloud of Kr-85 = 1.34 E-3 mRem-m3 per pCi-yr.

ODCM 13 Rev. 11

NOTE: Equations 2.6 and 2.7 incorporate the use of the semi-infinite plume model. The model assumes receptor submersion in a plume of uniform concentration, which is semi-infinite in geometry, having as its only boundary the ground plane. Due to the meteorology and topography at the La Crosse Site, the worst receptor locations are a bluff 1300 m SSE and a bluff 600 m ENE of the facility. At these locations the receptor is 2 submerged in the plume.

Calculation of Instantaneous Release Rate Monitor Setpoints for Noble Gases (Kr-85)

E 0o Equations 2.6 and 2.7 are used to calculate the controlling instantaneous release rate setpoints for dose rates to the total body and skin of an individual due to Kr-85 for one-and two-blower operation.

0 The DFB, DFY and DFS values for Kr-85 are multiplied by the appropriate X/Q value, the conversion constants and the stack flow rate for one- or two-stack blower operation to a),C obtain the values for TBF, SFG and SFB which are then inserted into the following C),

equations to determine gaseous release monitor alarm setpoints, Qvs:

Qvs (Whole Body) = (500 mRem/yr) (2.8)

C * (TBF) 0 Qv (Skin) = (3000 mRem/yr) (2.9)

(SFG + SFB) where:

TBF = (1E6) (xIQ) (DFB) (Fs)

("A SFG = (1.11E6) (x/Q) (DFY) (FS)

SFB = (1E6) (x/Q) (DFS) (Fs)

M

>0 The smaller of the two values calculated is used for the setpoint. This instantaneous release rate setpoint is very conservative since it is the average release rate allowed for a whole year.

ODCM 14 Rev. 11

" The following step-by-step procedure may be used in conjunction with the equations found on Figure 2.2 to calculate the instantaneous release rate limits for Kr-85 for one-or two-stack blower operation:

,' 1. On Figure 2.2, enter the date that the alarm setpoint calculation is (r performed.

o0 2. Note the appropriate value for x/Q.

3,

3. Note the appropriate value of Fs and the number of stack blowers operating for the condition being calculated.

0

4. Using the equations at the top of Figure 2.2, calculate the values of TBF, 0SFG and SFB for one- and two-blower operation and for all appropriate x*Q's, using the DFB, DFY and DFS values for Kr-85 listed on Figure 2.2.

Do, 5. Calculate the values of Q for each case. Select the smallest Q value for each x/Q which will become the FAST and SLOW alarm setpoints for the noble gas monitor.

6. The Qvs values (alarm setpoints) are tabulated on Figure 2.3.

0 a)

NOTE: These alarm setpoints (Qv*) will not need to be recalculated during SAFSTOR unless: (1) limits are changed, (2) .dQ values are changed,

~L. 0 (3) dose factors are changed, or (4) volume flow rate in the stack 2 E5 changes.

a- /0

(

o

-0 Q)

-Dcz uJ

>u-

-J ODCM 15 Rev. 11

Figure 2.2 C"

NOBLE GAS (KR-85) RELEASE MONITOR ALARM SETPOINT CALCULATIONS Calculation for Alarm Condition (FAST or SLOW) 0 I.- YdQ = No. of Stack Blowers = Fs =

E 0 Equations:

3-,

TBF = (1E6) (jQ)(DFB)(Fs) 0 SFG = (1.11 E6) (x/Q) (DFY) (Fs)

Cx SFB = (1E6) (xIQ) (DFS) (FS) 0 where:

00 CNJ C'14 (XdQ) = 6.05 E-5 sec/m 3 or 3.90 E-6 sec/m 3 (FAST) (SLOW) mRem-m 3 Q)

DFB = 1.61 E-5 Cu pCi-yr DFY = 1.72 E-5 mRad-m 3 U) 2)

pCi-yr 0

ca E DFS = 1.34 E-3 mRem-m 3 pCi-yr FS = 1.65 E7 cc/sec or 3.304 E7 cc/sec (1 blower) (2 blowers)

UD Cu 0 CN TBF = mRem-cc

ýiCi-yr SFG+SFB= + = mRem-cc piCi-yr Q,, (whole body) = 500 mRem/yr = !_Ci/cc TBF Q,,(skin) = 3000 mRem/yr = __Ci/cc (SFG + SFB)

ODCM 16 Rev. 11

Figure 2.3 J NOBLE GAS (Kr-85) RELEASE MONITOR ALARM SETPOINT

SUMMARY

(jiCi/cc in stack effluent)

0-U)

~UJ 0z ODCM 17 Rev. 11

H-3 and Particulates The following mathematical relationship shall be used to implement the limitation for H-3 and Particulates with T 12 > 8 days alarm setpoints:

Dp, 1i P i Qpi (X/Q) (2.10)

El 0

where:

(A C:

0 Dp = the dose rate to organ -cof an individual at or beyond the EFFLUENT RELEASE BOUNDARY, due to H-3 and particulates with half-lives greater than 8 days. This value is to be less than 1500 mRem/yr.

CP (U0 = the dose parameter for organ -c, for radionuclide i, for the N inhalation pathway, in mRem-m 3 per ýiCi-yr.

dQ = the atmosphere dispersion coefficient in sec/m3 a) = release rate of nuclide i, in gCi/sec.

aC:

C:

0U Calculation of Release Limits for H-3 and Particulates with Half-Lives 2 E Greater than 8 days

&a)

Since it is impractical to measure instantaneous release rates for radionuclides other than noble gases, the alarm setpoints for radionuclides other than noble gases are expressed in terms of total accumulated activity on sample media for a specified sampling time, AT, which is monitored as gCi by the stack effluent monitor.

M (D Equation 2.11 is used to calculate the release rate limit for all H-3 and particulates with

>~ 0 half-lives greater than 8 days. This equation is based on the dose rate to an infant due

~UJ 0z to inhalation of these radionuclides. In accordance with NUREG-0133, the infant will always receive the maximum dose rate. The atmospheric dispersion coefficients (xIQ)

ODCM 18 Rev. 11

j used are 6.05 E-5 sec/m 3 for the calculation of the FAST alarm setpoint and 3.9 E-6 sec/m 3 for the SLOW alarm setpoint.

CuL Alarm Setpoint Calculations for H-3 and Particulates with Half-Lives Greater than 8 days E

0 Qp, = 1500 mRem/yr (2.11) 0 Yj [Pi, (inhalation) x Rpi] (9IQ) where:

Co Cu.

Qp,= the maximum allowed total release rate of a typical mixture of 0-radionuclides in ýtCi/sec conservatively derived from the allowed annual average dose rate to organ -Tand very conservative xIQ.

0) 0- Rp= the ratio of the activity of nuclide i, to the total activity of all nuclides other than noble gases in a typical mixture being released.

0 >

xQ= the atmospheric dispersion coefficient as given above for FAST or SLOW Q-a)

.cI alarm respectively, in sec/m 3 .

a)

Cu 0 CNJ Resolution of the P1 , term in Equation 2.11 yields:

Pi, (inhalation) = (106 pCi/gtCi) (BR) (DFA ,) 1 (2.12)

'a where:

M)z C> 0 DFA1, = the inhalation dose factor for an infant, for the ith radionuclide, for organ r, in mRem/pCi.

-0 BR = infant breathing rate, in m 3 /yr.

ODCM 19 Rev. 11

To calculate the alarm setpoint in terms of total ý.Ci deposited on filter or cartridge sample media, the following equation is used:

Qsa = Lowest Qp, x A F (2.13) 2 Fs where:

E, 0

Qsa = the activity in tCi (deposited on sample media in sample time AT) which initiates an appropriate alarm in the stack effluent monitor.

U)

Q Q= Ci/sec

.2 Fa = stack flow rate, cc/sec AF = total flow through sample media (cc), in sample time AT, corrected to C) stack gas conditions. AT is normally 7 days.

0-CN The procedure outlined below is used to calculate the release limits for radionuclides other than noble gases. This will be done at least annually.

a Cc CL.

0 2 E, NOTE: This procedure is applicable for the determination of either FAST or SLOW alarms by utilizing the appropriate value for x/Q in the equation.

1. Start on Figure 2.4. Enter the date, the alarm setpoint being calculated, (FAST or SLOW) and the appropriate ./Q value to be used.

2. Enter the average release rate for the period, Qpi, in jiCi/sec, of each

'a

(>~ 00n identified radionuclide. At the bottom of the form, compute and enter the LuJ sum JQPi.

,-W ODCM 20 Rev. 11

3. In the column labeled Rp , enter the ratio of the average period release rate of nuclide i to the average total period release rate, *QPi, for the period.

4. For each organ -r,as noted at the top of the form, calculate and enter the E

0~

value of (x/Q) (Rpi) P i(inhalation) for each nuclide. Pi, (inhalation) values are found on Table 2.1. At the bottom of the column, for each organ, enter the value of Z Rpi Pi (%/Q) for that organ.

oi

.2 o21 5. Go to Figure 2.5. Enter the date and the alarm setpoint being determined.

D C6. Using the equation at the top of Figure 2.5, calculate the release rate limits, Qp,, for each organ -c.

7. Select the lowest value of Qp,, enter at the bottom of Figure 2.5 under

".3 C appropriate blower operation. Multiply the Qp, number times the total sample flow through the sample media, cc, and divide this by the U)O appropriate blower flow rate, cc/sec, to determine the Qsa in [iCi and use these as alarm setpoints.

a)C

-0

>0-CLJ

'0 Ux ODCMV 21 Rev. 11

F I

LARRYepared or Revised By L. NELSON Date 12/02/08 Rad. Prot. Engineer R, Nvj Date Seymour J. Raffetvlk I 12ni9Fl9fl

- I Operations I I A-f7 I3pview Comm. Approval I i II Dat*

a;"--*- .

-]

Figure 2.4 Date H-3 AND PARTICULATE GASEOUS RELEASE MONITOR ALARM SETPOINT DETERMINATION Alarm being calculated (FAST or SLOW) __Q sec/m 3

• Nuclide i QPi Rpi (JQ) Rpi Pi, (inhalation) **

W Body Bone Liver Thyroid Kidney Lung GI-LLI H-3 Co-60 Sr-90 Cs-1 34 Cs-1 37 Ce-1 44 Z-QPi i i

• For FAST alarm use 6.05 E-5 sec/m 3 for x/Q and for SLOW Alarm use 3.90 E-6 sec/m 3

• • Pi,, (inhalation) values found in Table 2.1.

ODCM 22 Rev. 11

7-Figure 2.5 f-v 0

H-3 AND PARTICULATE GASEOUS RELEASE MONITOR ALARM SETPOINT

SUMMARY

Ei Calculation for (FAST or SLOW) alarm.

0 QP-t 1500 mRem/yr Yj [Pi, (inhalation) x Rpi x xJQ]

0

= maximum allowed total release rate, pCi/sec to meet dose rate limit to organ -T.

CL CN 0

T I (XIQ) Rpi Pi, (inhalation)

• Qp (gCi/sec)

-, 0 Whole Body CN Bone Liver Thyroid (D

(D CU Kidney 0 Lung 0 E a, GI-LLI

• From Figure 2.4 c,

One-Blower Operation Two-Blower Operation a) CD (N

C0 (N

Qsa = Lowest Qp, x AF Qsa = Lowest Qp, x AF 1.650E7 3.304E7 M where:

AF = corrected total flow through Qsa = uCi/sec x cc

.(/ z sample media, cc 3.304 E7 cc/sec L.uJ 0 z ýtci cc >_ Qsa = uCi/sec x cc 1.650 E7 cc/sec of

-Ja.i ODCM 23 Rev. 11

L :epared or Revised By I Date II Rad. Prot. Engineer RL ,1 Date I I Op.rations Re-view Conam. Approval I Dat,_ -1 I

I LARRY L. NELSON 1 12/02/08 II I I I Seymour J. Raffety,4a f 12/02/08 I I I/'7/7 *-

Table 2.1 INFANT DOSE FACTORS P, (INHALATION) FOR H-3 AND PARTICULATE GASEOUS RELEASE MONITOR ALARM SETPOINT DETERMINATIONS In Units of mRem-m3/4tCi-yr Nuclide Whole Body Bone Liver Thyroid Kidney Lung GI-LLI H-3 6.47 E2

• 6.47 E2 6.47 E2 6.47 E2 6.47 E2 6.47 E2 CO-60 1.18 E4

• 8.02 E3 *

• 4.51 E6 3.19 E4 SR-90 2.59 E6 4.09 E7 * *

• 1.12 E7 1.31 E5 CS-1 34 7.45 E4 3.96 E5 7.03 E5

• 1.90 E5 7.97E 4 1.33 E3 CS-137 4.55 E4 5.49 E5 6.12 E5

• 1.72 E5 7.13 E4 1.33 E3 CE-144 1.76 E5 3.19 E6 1.21 E6

• 5.38 E5 9.84 E6 1.48 E5 Values in this table are derived from Tables E-5 and E-10 in App. E of NRC Regulatory Guide 1.109 Rev. 1, October 1977.

• No data available.

ODCM 24 Rev. 11

r--

b) To demonstrate compliance with the limitations of Section 3.3.3.b, dose contributions are calculated for any Kr-85 released to unrestricted areas using the following expressions:

Dy (r, 0) = 3.17 E-2 DFY Q [./Q] (r, 0) (2.1 4)

E 0 D" (r, 0) = 3.17 E-2 DF* Q [xQ] (r, 0) (2.1 5) where:

0)

Dy (r, 0) = the dose commitment to the maximum individual due to the U) gamma radiation from Kr-85 at location (r, 0), in mRad.

DB (r, 0) = the dose commitment to the maximum individual due to the beta radiation from Kr-85 at location (r, 0), in mRad.

Cu04 Q C) = the total release of Kr-85 in gaseous effluents for the release period, in ýtCi.

3.17 E-2 = pCi/ýLCi divided by sec/yr U) k

[xIQ] (r, e) = the annual average atmospheric dispersion constant for U) long- term releases at location (r, 0), in sec/m 3 . Since the

2) collection of hourly meteorological data is no longer required a_ 0 E or performed at the LACBWR site, a conservative value U/) based on historical site specific annual average x/Q values will be used. This value is 1.82E-6 sec/m 3.

DFY and DFR = the gamma and beta air dose factors for exposure to a 01 uniform semi-infinite cloud of Kr-85 in (mRad-m 3 /pCi-yr).

0 (N Numerical values are 1.72E-5 and 1.95E-3 respectively.

(N (Ref. NRC Regulatory Guide 1.109 Rev. 1, October 1977.)

M Calculation of Gamma and Beta Air Dose Commitments z

0 U),

-j 0 LU z In accordance with the RECP, the gamma and beta air dose commitments are to be calculated once per calendar quarter and yearly. Equations 2.14 and 2.15 are used to perform these calculations. Since the only noble gas that needs to be considered at ODCM 25 Rev. 11

LACBWR is Kr-85, and since a conservative constant value is used for X/Q, these equations reduce to:

DY = 9.923E-13Q 2

DI = 1.125E-1OQ E

The following step-by-step procedure is used in conjunction with Figure 2.6 to calculate the quarterly cumulative dose commitments due to Kr-85.

C 0-. 1. Go to Figure 2.6. Enter the Date. Enter the period covered by the 0

calculations.

cCO

2. Enter the total Kr-85 activity released in the gaseous effluent during the period being considered, in gCi.

3. Calculate the dose commitments DY (r, 0) and D* (r, 0) due to Kr-85 using the equations on Figure 2.6.

0 0 E 4. Calculate the percent of the current quarterly and annual release limits and enter on Figure 2.6.

C-C)

'0*

(1)

.0 z

~LU

-0 z

'0>

-J ODCM 26 Rev. 11

revared or Revised Bv I -- I

-'-I I,/ reardorReiedBy II Date

• *.i~I III Rad. Prot Enine Rt IA/I

- (~~%LI -. .. . .. . Dat - I C'r~ivne

-w -!' -- -. r, ~Aff~~I~JPWYJva I a.. I I LMr~Nr' T L. INI-LV1JII 1Z/UZ/U0 II sevmour J. 1(aftetv4 #.W(I 121U21U8 I I ~( Qi~- ~-

II I Figure 2.6 Date AIR DOSE COMMITMENT TO A MEMBER OF THE PUBLIC FROM NOBLE GAS (Kr-85) RELEASE Release Period Total Kr-85 Act. Released, Q = pCi Dose Calculation for Release Period DY= 9.923 E-13 Q = mRad DR= 1.125 E-10Q= Q_ mRad Limits Gamma Beta Particle Calendar Quarter < 5 mRad <10 mRad Calendar Year <10 mRad <20 mRad Current Air Dose Commitment Record for Calendar Year

lstQu arter 2n uarter 3rd Quarter .4th Quarter Calendar Year Gamma Beta Gamma Beta Gamma Beta Gamma Beta Gamma Beta Dose, mRad

% of Limit ODCM 27 Rev. 11

c) To demonstrate compliance with the limitations of Section 3.3.3.c, dose contributions are calculated for H-3, and particulates with half-lives greater than 8 days, identified in gaseous effluents released to unrestricted areas using the methodology presented in NRC Regulatory Guide 1.109, Rev 1, October 1977. This methodology takes the form of the following general 0 'equation:

D.a (r, 0) = Mi a W(r, 0) Qi (2.16)

.0 N where:

0 D,a (r,0)= the dose commitment to organ -cof an individual in age group a, at a distance r in sector 0 from the release point, due to the release to the atmosphere of radionuclides other than noble gases, in mRem.

W(r, 0) = the average dispersion parameter for estimating the dose to an individual at the receptor location (r, 0), for the period of release, in sec/m3 or M-2 as required by the characteristics of the exposure pathway.

C = the total activity of each radionuclide i, other than noble gases, in gaseous effluents for the release period of interest, in ýtCi.

CU aIPTa = the dose conversion factor for exposure pathway P to organ

-r of an individual in age group a, for each identified 00 radionuclide i. The units of MPita are (mRem-m 2 )/jiCi or (mRem-m 3 )/jiCi-sec) as required so that the product MWia W(r, 0) is mRem/1 tCi.

Equation 2.16 may be expanded to the following form where each term is the

>~ Z incremental dose received via one of the three major dose pathways.

Da (r, 0) = Z DGita (r, 0) + DAiTa (r, 0) + DDiTa (r, 0) (2.17) ai-ODCM 28 Rev. 11

where the first term on the right is the external dose from direct exposure to activity N deposited on the ground plane, the second term is the dose from inhalation of radionuclides in air, and the third term is the dose from ingestion of foods contaminated by atmospheric releases of radionuclides.

0.

Applying the methodology of NRC Regulatory Guide 1.109 Rev. 1, equation 2.17 is 0

expanded as follows:

D., (r, 0) = mG iTa Qj (D/Q)(r, 0) (2.18)

CZ S0q.

+ MAiTa Qi (.xt/Q)(r, 0) a)

0 Cu + -- M iTa Qi (D/Q)(r, E) + (MDV1 4 Ta Q14 + MDVTTa QT) (!dQ)(r, e) 0 04

+ MD~i~ a Qi (D/Q)(r, E) + (MDMl 4 Ta014+ MDMTTa QT) (xJQ)(r, e)

Wa CU

+

• MDMiTa Qi (D/Q)(r, e) + (MDM1 4 Ta Q14 + MDMTTa QT) (xJQ)(r, e) 01 0~ E) + " MDLiTa Qi (D/Q)(r, E) + (MDL1 4 Ta Q14 + MDLTTa QT) (x/Q)(r, E) cc where:

o a) (x.Q)(r, 0)= the annual average atmospheric dispersion factor for a receptor NI at the distance r in sector 0 from the release point, in sec/m 3 .

For the LACBWR in the SAFSTOR mode, the value for this term is conservatively taken to be the largest historical (1983-1987) undecayed/undepleted xIQ for a real receptor and is 1.82E-6 M

sec/mi3 .

z 0

C/)

-j (D/Q)(r, 0)= 1.82E-9m- 2 . This is based on the relationship D/Q = Vd .xQ where w

0 z Vd = the deposition velocity in m/sec. Vd is generally < 1 E-3m/sec for dry deposition of submicron aerosols which may be CL released from the LACBWR facility during SAFSTOR (Ref Whicker, F. W. and Schultz, V., Radioecology: Nuclear Energy and the Environment, Vol. II, CRC Press, Inc., Boco Raton, Florida, 1982.

ODCM 29 Rev. 11

MGira = 1.06 SF DFGi, (1 - exp(-Xitb))/Xi and according to R.G. 1.109 the dose to all internal organs (t) for all age groups (a) is taken to be the same as F- the total body dose.

MA ia = 3.17E-2 BRa DFAi-a and for the ingestion pathway (DV) for produce (non-leafy-vegetables, fruits, and grains)

E 0 MDViTa = 1.1 E2 DFliTa UVa fg exp(-Xith)(r(1 - exp(-XEite))/YvkEi +

Biv (1-exp(-Xiitb))/ Pki) for all radionuclides except C-14 and H-3 0

MDV14Ta = 22 DFI 14Ta UVafg p for C-14 a) 0-MDVTTa = 12 DFITTa UVa fg/H for tritium 04 for thi ingestion pathway (Dm) for milk MDMiTa =1.1E2 DFlia Um Fmi QFexp(-i tf)(fp fs (1-exp(-X, th)) + exp(-ki th))

U1) x (r(1 -exp(-?,Ei te))IYv kEi + Biv (1 - exp(-Xi tb))/PXi) for all radionuclide except C-14 and H-3 CO mDM14Ta - 22DFI14Ta Um Fmi QF p(exp(-Xl4tf)) for C-14 04 mDmT~a = 12DFITTa U"lFmi QFexp(-XTtf)/H for tritiun n for the ingestion pathway (DM) for meat MDMiTa = 1.1 E2 DFliTa Um Ff Qfexp(-Xits) (fpfs (1 - exp(-Xith)) + exp(-Xith))

>0 (N x (r(1 -exp(-XEite))/YvXEi + Bjv(1 - exp(-Xitb))/PXi)

CO for all radionuclides except C-14 and H-3

.!0 z mDM14Ta = 22DFI14,a Um Ff14 QF p(exp(-)1 4 ts)) for C-14

'a)

(D-j MDMTTa - 12 DFITta Um Frr QFexp(-XTts)/H for tritiun TI ODCM 30 Rev. 11

for the ingestion pathway (DL) for leafy vegetables:

MDLia " 1 .1 E2DFlita fe exp(-Xth)(r(1 - exp(-XEte))/YvXEi+Biv(l - exp(-Xitb))/Pki) for all radionuclides except C-14 and H-3.

f MDL1 4 ta= 22DFI14,a UafeP for C-14 E

MDLTTa = 12DFITra Uafe/H for tritium 0

a) The values used for the various parameters in the above equations are those recommended in NRC Regulatory Guide 1.109, Rev. 1, for the maximum exposed 0

CU a) individual.

0 Parameter Dimensions Description/Source sL, 1.0E6 pCi/PCi CO DFGir mRem-m 2/pCi-hr from table E-6 in R.G.

0C'- DFAiTa mRem/pCi inhaled from table E-7 thru E-10 in R.G.

DFA14Ta mRem/pCi inhaled from table E-7 thru E-10 in R.G.

DFATra mRem/pCi inhaled from table E-7 thru E-10 in R.G.

0 DF/iTa+ mRem/pCi ingested from tables E-1 1 thru E-14 in R.G.

CO DF/14,a mRem/pCi ingested from tables E-1 1 thru E-14 in R.G.

DFITra mRem/pCi ingested from tables E-1 1 thru E-14 in R.G.

00 SF = 0.7 dimensionless attenuation factor accounting for 0

shielding by residential structures CN Xi hr-1 radiological decay constant for nuclide i.

tb = 1.31x10 5 Hr period of long-term buildup for activity in soil (nominally 15 yrs)

M~ z 3.17x1 0-2 pCi - yrlICi - sec

> 0 inhalation rate for age group a.

0z BRa m 3 1yr Table E-5 in R.G.

1.1x1 02 pCi - yrliCi - hr ODCM 31 Rev. 11

AC Parameter Dimensions Description/Source

.8 0

UI kg/yr consumption rate of produce for individual in age group a. Table E-5 of R.G.

2 fg = 0.76 Dimensionless fraction of produce ingested that is grown in garden of interest.

0. th hr time delay between harvest of 0.

vegetation or crops and ingestion.

A-) =0 for pasture grass by animals a)

= 2160 for stored feed by animals Cl)

C 0 = 24 for leafy vegetables by man

= 1440 for produce by man 0 r = 0.2 dimensionless fraction of deposited activity retained on crops, leafy vegetables, or a) pasture grass.

Cu C

?'Ei = Xj + Xw hr-1 the effective removal rate constant for radionuclide i from crops.

Xw = .0021 hr-1 removal rate constant for activity on plant or leaf surfaces by weathering 0 (-: to 14 day half-life) te hr period of crop, leafy vegetable, or C

pasture grass exposure during growing season.

= 720 for grass-cow-milk-man pathway uJCO = 1440 for crop/vegetation-man pathway Yv kg/m 2 agricultural productivity (measured in wet weight)

O = 0.7 for grass-cow-milk-man pathway aD Ca 0

= 2.0 for produce or leafy vegetables ingested by man Biv dimensionless pCi/kg in vegetation per pCi/kg in soil for nuclide i. Table E-1 in R.G.

>1 CO)

P = 240 kg/m 2 effective surface density of soil (dry z weight) 0 22 pCi- yr- m 31pCi- kg -

-j 0 sec z

M p dimensionless the ratio of the total annual release time for C-14 to the total annual time during which photosynthesis occurs with the condition that p< 1.0 ODCM 32 Rev. 11

Parameter Dimensions Description/Source N, = 1.0 for continuous C-14 releases.

CU 12 pCi- g - yr/iCi- kg - sec C H = 8.0 g/m 3 average absolute humidity of the C

atmosphere at location (r,0)

Uam liters/yr consumption rate of milk for E

individual in age group a. Table E-5 of R.G.

Cn F*i day/I factor for estimation of activity of nuclide i in milk from that in animal 0

feed (pCi/I in milk per pCi/d ingested by the animal) Table E-1 in R.G.

CO QF = 50 kg/day feed or forage consumption rate 0

(wet weight) by milk cow or beef cattle ci) tf = 48 hr transport time from animal feed-milk-CuC~%4 man.

0 fp = 0.5 dimensionless fraction of the year that animals graze on pasture.

C', fS = 1.0 dimensionless fraction of daily feed that is pasture

'A, when the animal is on pasture a)

Ua kg/yr consumption rate of meat & poultry a) for individual in age group a. Table 1=

0, E-5 of R.G.

0 Ff i day/kg factor for estimation of activity of 0) a- E, nuclide i in meat from that in animal feed (pCi/kg in meat per pCi/day I0 ingested by the animal) Table E-1 in R.G.

a), 0 Co (N

ts a

= 480 hr kg/yr average time from slaughter of meat animal to consumption of meat consumption rate of leafy vegetables for individual in age group a. Table E-5 in R.G.

fe = 1.0 dimensionless fraction of leafy vegetables grown in CO, garden of interest.

D Z

0 LU

-J ODCM 33 Rev. 11

Calculations of Dose Commitments due to Gaseous Release other than Noble Gases

-J In accordance with the RECP, the maximum commitment to a MEMBER OF THE PUBLIC from H-3 and all radionuclides in particulate form with half-lives greater than 8 days shall be determined at least quarterly.

E To perform this calculation Eq 2.18 has been formatted on a computer-based spreadsheet. The quantity in curies of each nuclide (i) released to the atmosphere from the LACBWR facility during the calendar quarter is entered in the appropriate cell of the spreadsheet. The spreadsheet program calculates and displays the total quarterly dose in mRem to the total body and each organ of an individual in each of four age groups and the cumulative calendar year dose to the total body and each organ. It also determines the maximum exposed organ (and its dose) for each age group each quarter and the dose to the maximum exposed organ in all age groups. The quarterly and cumulative calendar year doses to the maximum exposed organ are compared to the limits and the relation in terms of percent of the limit is displayed. The maximum incremental organ dose received through each of the three major pathways is also a) determined for each age group each quarter.

(U 0

>0

.~z ODCM 34 Rev. 11

3.0 RADIOACTIVE EFFLUENT CONTROL PROGRAM 3.1 Program Requirements The Radioactive Effluent Control Program (RECP) shall conform to the guidance of 10 CFR 50.36a for the control of radioactive effluents and for maintaining the 0 doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. This program shall establish the requirements for monitoring, sampling and analysis of radioactive gaseous and liquid effluents 0~

released from LACBWR to ensure the concentrations in effluents released to 0 areas beyond the EFFLUENT RELEASE BOUNDARY conform to 10 CFR Part 20, Appendix B, Table 2, Columns 1 and 2. It shall provide limitations on the annual and quarterly dose commitment to a MEMBER OF THE PUBLIC from radioactive effluents in conformance with Appendix I of 10 CFR Part 50.

The limitations of operability of gaseous and liquid monitoring instrumentation, including surveillance test and setpoint determination in accordance with Section 0E2.0, Offsite Dose Calculations, will be included in this program.

Requirements for the Reactor Building Ventilation System, including filtration and elevated stack release of exhausted air is included in Section 3.3.1.

co o In accordance with provisions of 40 CFR 190, the restrictions and surveillance requirements for total dose to any MEMBER OF THE PUBLIC from all LACBWR related sources and dose pathways are presented in Section 3.4.

LuJ ODCM 35 Rev. 11

3.2 Liquid Effluents 3.2.1 Sampling and Analysis 0 ~All liquid effluent releases at LAG BWR will be in batch form. A batch release is the discharge of liquid wastes of a discrete volume. Prior to 2L sampling for analysis, each batch shall be isolated and then thoroughly mixed, to assure representative sampling. The radioactive content of E

0 o each batch of radioactive liquid waste to be discharged shall be determined, as per the following table:

U)

C 0

0 CO C)

CNJ CN C:1

~0 2 ,

0_C C)

C:04 CNJ Maz

>-0 ODOM 36 Rev. 11

Table 3.1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS REQUIREMENTS FOR BATCH RELEASES CL SAMPLING. MINIMUM TYPE OF ACTIVITY ANALYSIS (c) FREQUENCY ANALYSIS FREQUENCY 0~

Q 1. Principal Gamma emitters (b) Prior to discharge Each discharge - prior to Includes KR-85 discharge 0 2. Gross Alpha Prior to discharge Each discharge - prior to discharge

3. Tritium Prior to discharge Each discharge

4. Sr-90 and Fe-55 Beta emitters Prior to discharge Quarterly Composite (a) a)

CU (a) A composite sample is one made up of individual samples which are proportional to the 0 quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquid release.

(b) The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Co-60, Cs-1 34, and Cs-137. This list does not mean that cr only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified C

and reported.

0- (c) Methods of calculating the Lower Limits of Detection (LLD) shall be contained in plant procedures and are calculated in accordance with criteria of NUREG-0473, Rev. 2.

a) 0 0 The results of pre-release analyses shall be used in accordance with the Offsite Dose Calculations methodology to assure that the concentration at the point of release is maintained within the limits specified in this RECP.

M z

~0 0 C',

cc -ju-CdL 9D z ODCM 37 Rev. 11

3.2.2 Liquid Effluent Release Limitation a) Concentration - the concentration of radioactive material released in 2 /liquid effluents at any time to areas beyond the EFFLUENT RELEASE BOUNDARY shall be limited to concentrations specified in 10 CFR E

001 Part 20, Appendix B, Table 2, Column 2.

()

If the concentration of radioactive material released beyond the C

EFFLUENT RELEASE BOUNDARY exceeds the above limits, restore 0 the concentration to within the above limits without delay.

This limit is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.

C b) Dose - the dose or dose commitment to a MEMBER OF THE PUBLIC 2 0Efrom radioactive materials in liquid effluents released to areas beyond

&a) the Effluent Release Boundary shall be limited to:

Calendar Quarter Calendar Year C)

<1.5 mRem total body < 3 mRem total body

< 5 mRem to any organ < 10 mRem to any organ M

The cumulative dose contribution from liquid effluent shall be determined at least once per calendar quarter in accordance with

.0 z Section 2.0, Offsite Dose Calculations. If this calculated dose exceeds the above limits, prepare and submit to the Commission, within 30 days, a Special Report which identifies the cause(s) for ODCM 38 Rev. 11

7,_ exceeding the limit(s) and defines the corrective actions which have

.1 been or will be taken to assure that subsequent releases shall be in compliance with the above limits.

This limit is provided to implement the requirements of Sections ILA, III.A, IV.A and Annex of Appendix 1, 10 CFR Part 50. The dose E calculations in Section 2.0 implement the requirement in Section III.A of Appendix I that conformance with the guides of Appendix I be a) shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate a) pathways is unlikely to be substantially underestimated.

co CN 3.2.3 Liquid Effluent Instrumentation The following radioactive liquid effluent monitoring instrumentation channels shall be OPERABLE, with their alarm setpoints set to ensure that the limits of Section 3.2.2.a are not exceeded, at all times when releasing liquid radioactive effluents.

Liquid Radwaste Effluent Line Monitor (U

and 00 cc Liquid Radwaste Effluent Line Flow Meter The alarm setpoints for this monitor will be determined and adjusted using methodology in Section 2.0, Offsite Dose Calculations.

Mn z SThe radioactive liquid effluent instrumentation is provided to monitor the releases of radioactive materials in liquid effluents during actual or

<_potential releases of liquid effluents with the alarm setpoints set to ensure that the alarm will occur prior to exceeding the limits of 10 CFR Part 20.

ODCM 39 Rev. 11

a) Surveillance Requirements - each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated o ~ OPERABLE by performance of the CHANNEL CHECK, M~ SOURCE CHECK, CHANNEL FUNCTIONAL TEST, and CL CHANNEL CALIBRATION operations at the frequencies shown in the following table.

E 0

x NN 0

0 0

04 0-(

C:

wJ 0

co' C-4 a)

.W z

-J ODCM 40 Rev. 11

Table 3.2 l

C-RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 2

Channel Insruen Channel Source Functional Channel E Check....Checks....Test....Calibration E

0 Liquid Radwaste orPrior Priit to Prior to Quarterly At LiqueidnRdwae te discharge (See Note perleast once 18 months C- Effluent Line Monitor discharge (See Note 4) (See Note 3) 0)

Liquid Radwaste At least once Effluent Line Flow (See Note 2) N/A N/A per 18 months 0 Meter (See Note 5)

C)

CUCN NOTES:

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room C

U-I 0 2

ICU E

(D (2) alarm annunciation occurs if any of the following conditions exist:

Instrument indicates measured levels at the alarm setpoint.

Instrument indicates a downscale (circuit failure) failure.

CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on co C'n days in which continuous, periodic, or batch releases are made.

(3) The CHANNEL CALIBRATION shall include the use of a known liquid radioactive source positioned in a reproducible geometry with respect to the 0o (D,C) sensor. The source will have the gamma emitting radionuclide mixture and C0 activity concentration which would normally be measured by the channel during batch discharges.

(4) Background radiation may be used for the source check.

-0 CD (5) The CHANNEL CALIBRATION will be in accordance with plant procedures.

V z

> 0 0z Cu>

ODCM 41 Rev. 11

b)~ Correctivep Ac~tion

-I -k O (1) With the Liquid Radwaste Effluent Line Monitor channel alarm/trip-point setpoint less conservative than that required 2 by Section 3.2.2(a), immediately suspend the release or change the setpoint so that it is acceptably conservative.

E (2) With the Liquid Radwaste Effluent Line Monitor NOT U) OPERABLE, or if its alarm setpoint is found to be less 0 conservative than required, suspend release of liquid radioactive effluent without delay. Effluent releases may be 0

resumed without the Liquid Radwaste Effluent Line Monitor OPERABLE, provided that at least two independent samples 0-0~

are analyzed and that at least two technically qualified members of the staff independently verify the release rate calculations. If the monitor is not operable for more than 30 UCU continuous days, explain in the next Annual Effluent Report.

0 (3) With the flow meter not OPERABLE, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.

UD)Co (N

U)

>~ 0 U)j

-LJ ODCM 42 Rev. 11

3.3 Gaseous Effluents 3.3.1 Reactor Building Ventilation Normal air discharge from LACBWR is made as an elevated stack P* release. Air is swept through the Turbine and Reactor Building and then

< discharged out the stack. Whenever the Reactor Ventilation dampers are E

0E open, the air from the Reactor Building shall be discharged through a set Sof HEPA particulate filters to reduce the amount of radioactive particulates IN being released to the environment. This filtration of the Reactor Building Ventilation System exhaust implements the requirements of 10 CFR CI o Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50.

With Reactor Building Ventilation System exhaust being discharged without filtration, prepare and submit to the Commission within 30 days a

_ Special Report which discusses the circumstances and what action will be 0 taken to prevent a recurrence.

3.3.2 Stack Effluent Sampling and Analyses CO The radioactive gaseous discharge from LACBWR will be sampled and analyzed as per the following table.

M

()U)

" LU

-JI ODCM 43 Rev. 11

Table 3.3 F

J RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS Release Sampling Minimum Analysis Type of 0 Type Frequency Frequency Activity Analysis (d)

Stack Continuous (b) Weekly (a)Particulate Sample Principal Gamma Emitters (c)

Effluent E

0 Continuous (b) Quarterly Particulate Sample Sr-90

§ Composite Continuous (b) Weekly (a)Particulate Sample Gross Alpha CC Continuous (b) Noble Gas Monitor Noble Gases Gross Beta 0

and Gamma

_Monthly Monthly H-3 00 a) 12 NOTES:

C) r-(a) The filter sample shall be changed at least weekly, and filter analyses shall be completed within seven (7) days.

(b) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation.

0 (c) The principal gamma emitters for which the LLD specification applies exclusively are E

the following radionuclides: Mn-54, Co-60, Zn-65, Cs-1 34, Cs-1 37, and Ce-144 for W

particulate emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable and measurable, together with those of the above nuclides, shall also be analyzed and reported in the annual Radioactive Effluent Release Report.

(d) Lower Limits of Detection (LLD) are determined in accordance with plant procedures (N and are calculated in accordance with criteria of NUREG-0473, Revision 2.

0 z

0 (0

-U -j uLJ z

ODCM 44 Rev. 11

3.3.3 Stack Effluent Release Limitation a) Instantaneous Dose Rate - the dose rate due to radioactive materials released in gaseous stack effluents to areas beyond the EFFLUENT RELEASE BOUNDARY shall be limited to:

2

< The dose rate limit for noble gases shall be < 500 mRem/year E to the total body and < 3000 mRem/year to the skin.

0

. The dose rate limit for H-3 and for all radionuclides in ID particulate form with half-lives greater than 8 days shall be <

Tu X1500 mRem/year to any organ.

0 The dose rate due to noble gases in gaseous stack effluents shall be determined to be within the above limits in accordance with Section 2.0, Offsite Dose Calculations.

The dose rate due to H-3 and for all radioactive materials in particulate form with half-lives > 8 days in gaseous stack effluents shall be determined to be within the above limits in accordance with Section 2.0, Offsite Dose Calculations, by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 3.3.

0-If the dose rate(s) exceeds the above limits, without delay decrease the release rate to within the above limit(s).

>0 LU 0~ z ODCM 45 Rev. 11

This instantaneous dose rate limit is provided to ensure that the dose rate at any time at the EFFLUENT RELEASE BOUNDARY from gaseous effluents from LACBWR will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table 2, Column 1. These limits provide reasonable EE 00 assurance that radioactive material discharged in gaseous effluents

> will not result in the exposure of an individual in an unrestricted area,

_ Ioutside the EFFLUENT RELEASE BOUNDARY to annual average concentrations exceeding the limits specified in Appendix B, Table 2 0

of 10 CFR Part 20. For individuals who may at times be within the EFFLUENT RELEASE BOUNDARY, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the EFFLUENT RELEASE BOUNDARY. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the EFFLUENT RELEASE BOUNDARY to

<500 mRem/year to the total body or to < 3000 mRem/year to the skin. These release rate limits also restrict, at all times, the corresponding organ dose rate above background to an individual via the inhalation pathway to < 1500 mRem/year.

b) Dose from Noble Gas - the air dose to a MEMBER OF THE PUBLIC due to noble gases released in gaseous effluents to areas beyond the

.LD z a (n EFFLUENT RELEASE BOUNDARY shall be limited to:

0 z Calendar Quarter

< 5 mRad from gamma radiation

< 10 mRad from beta particulate radiation ODCM 46 Rev. 11

Calendar Year

<10 mRad from gamma radiation

< 20 mRad from beta particulate radiation The cumulative dose contributions shall be determined at least once per calendar quarter in accordance with Section 2.0, Offsite Dose E

E 0

Calculations.

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions which have been taken or will be taken to reduce the releases of radioactive noble gases in gaseous effluents so that the cumulative dose during each subsequent quarter and the dose for the calendar year will be within the above limits.

This limit is provided to implement the requirements of Sections II.B, w0 EII.A, and IV.A of Appendix 1,10 CFR Part 50. The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated.

M

>z

.9 c) Dose from Radionuclides other than Noble Gases - the dose to a MEMBER OF THE PUBLIC from H-3, and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous

< effluents released to areas beyond the EFFLUENT RELEASE l-t BOUNDARY shall be limited to:

ODCM 47 Rev. 11

Calendar Quarter F- < 7.5 mRem to any organ Calendar Year

• < 15 mRem to any organ 0

o E The cumulative dose contributions shall be determined at least once E0 per calendar quarter in accordance with Section 2.0, Offsite Dose

> Calculations.

0 With the calculated dose from the release of H-3 and all (U

o radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days a Special Report which CN identifies the cause(s) for exceeding the limit and defines the corrective actions which have been taken or will be taken to reduce these releases in gaseous effluents during remaining quarters so that the cumulative dose during each subsequent quarter and during the SE calendar year will be within the above limits.

.c/

This limit is provided to implement the requirements of Sections II.C, OIl.A, IV.A and Annex of Appendix 1, 10 CFR Part 50. The ODCM Ccalculational methods specified in the surveillance requirements (NI implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational M procedures based on models and data such that the actual exposure

-J of an individual through appropriate pathways is unlikely to be Ssz a) j substantially underestimated.

ODCM 48 Rev. 11

13 4 ln~trument~tion The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.4 shall be OPERABLE with their alarm setpoints set to ensure that the limits of Section 3.3.3a are not exceeded. The stack noble gas instrumentation alarm setpoint will be determined and adjusted in Er 0 accordance with the methodology and parameters in Section 2.0, Offsite Dose Calculations.

C,,

.0 The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in 0

gaseous effluents during actual or potential releases of gaseous effluents.

The only significant noble gas remaining is Kr-85. The alarm setpoints for these instruments shall be set to ensure that the alarm will occur prior to exceeding the limits of 10 CFR Part 20.

a) Gaseous Effluent Instrumentation Surveillance Requirements -

Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations at the frequencies

,00 shown in Table 3.5.

C) b) Corrective Action A2 z (1) With a radioactive gaseous effluent monitoring instrumentation channel alarm setpoint less conservative 0 z than that required, declare the channel inoperable or change the setpoint so that it is acceptably conservative.

ODCM 49 Rev. 11

(2) With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION required by Table 3.4. Exert best efforts to return the instruments to OPERABLE status within 30 days

< and, if unsuccessful, explain in the next Annual Radioactive E Effluent Release Report why the inoperability was not corrected in a timely manner.

a)

CD 0

CN CUC LU) 0-U)

CL)

>0 (DU) oz E-J ODCM 50 Rev. 11

Table 3.4

-- RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE CONDITIONS ACTION

>1.

a System Building Ventilation Monitor Reactor

< a. Particulate Activity Monitor 1

• A E b, Gaseous Activity Monitor 1

• A 0

c. Sampler Flow Rate Measuring 1

• B Device

2. Stack Monitor System 0

a. Gaseous Activity Monitor 1 ** C

b. Particulate Activity Monitor 1 ** D

c. Sampler Flow Rate Measuring 1 ** B Device S* When Reactor Building Ventilation System is in operation.

• • At all times, unless alternate monitoring is available ACTIONS:

=c A. With the number of channels OPERABLE less than required by the Minimum 0 Channels OPERABLE requirement, effluent releases through this pathway may 2 continue as long as a stack monitor is OPERABLE; otherwise, secure the Reactor n) Building Ventilation.

B. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue a, provided the flow rate is estimated at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

0 C. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the Reactor Building Gaseous Activity Monitor is OPERABLE; otherwise,

>ý secure the Reactor Building Ventilation.

.T z D. With the number of channels OPERABLE less than required by the Minimum

> Channels OPERABLE requirement, effluent releases via this pathway may continue

_j provided continuous collection of samples with auxiliary sampling equipment is 0 initiated within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

a-J a)-i ODCM 51 Rev. 11

Table 3.5 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL C HANNEL SOURCE FUNCTIONAL CHANNEL (4)

INSTRUMENT CHECK CHECK TEST CALIBRATION

1. Reactor Building Ventilation Monitor System Ec a. Particulate Activity DAILY MONTHLY QUARTERLY At LEAST E

A 0 Monitor (1) ONCE PER U) 18 MONTHS

>1 b. Gaseous Activity Monitor DAILY MONTHLY QUARTERLY AT LEAST (1) ONCE PER W) 18 MONTHS 0

c. Sampler Flow Rate DAILY MONTHLY QUARTERLY AT LEAST Measuring Device (3) ONCE PER 18 MONTHS a)

2. Stack Monitor System 04 C)J a. Noble Gas Activity DAILY MONTHLY QUARTERLY AT LEAST Monitor (2) ONCE PER 18 MONTHS

b. Particulate Activity DAILY N/A QUARTERLY AT LEAST Monitor (2) ONCE PER cc 18 MONTHS a)

c. Sampler Flow Rate DAILY N/A QUARTERLY AT LEAST LU 0

Measuring Device (3) ONCE PER 0 18 MONTHS CL E U)

NOTES:

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

W) 0 U) 0 (N. a. Instrument indicates measured levels at or above the alarm setpoint.

b. Instrument indicates a downscale failure.

c. Instrument indicates a circuit failure.

-o (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm 00 annunciation occurs if any of the following conditions exist:

mA z

a. Instrument indicates measured level above the alarm setpoint on one channel.

>0 b. Instrument indicates a failure by a LowFlow and Low Count Rate signal.

U)~~

(3) The CHANNEL FUNCTIONAL TEST shall also demonstrate that the control room local alarm occurs if the flow instrument indicates measured levels below the minimum and/or above the maximum alarm setpoint.

(4) The CHANNEL CALIBRATION shall be conducted in accordance with plant procedures.

ODCM 52 Rev. 11

3.4 Total Dose to a Member of the Public The dose equivalent to any MEMBER OF THE PUBLIC due to release of radioactivity and radiation, shall be limited to < 25 mRem to the total body or any "0- organ (except the thyroid, which is limited to < 75 mRem) over a period of one calendar year.

E E

0 With the calculated doses from the release of radioactive materials in liquid or Q gaseous effluents exceeding twice the calendar year dose limits specified in Sections 3.2.2b, 3.3.3b, or 3.3.3c, a determination should be made, including a)

Qu direct radiation from Reactor Building and radioactive waste storage tanks to determine if the above limits have been exceeded. Ifthese limits have been exceeded, prepare and submit a Special Report (including an analysis which estimates the radiation exposure to a MEMBER OF THE PUBLIC for the calendar year) to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent 0 recurrence of exceeding these limits. Ifthe release condition resulting in the excess has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190.

cu Submittal of the Special Report is considered a timely request, and a variance is granted until staff action on the request is complete.

Cumulative dose contributions from liquid and gaseous effluents shall be determined quarterly and annually in accordance with Section 2.0, Offsite Dose T) z Calculations.

0 z Cumulative dose contributions from direct radiation from the reactor containment or radioactive waste storage tanks shall be determined once per year in ODCM 53 Rev. 11

F- accordance with Section 4.0, Radiological Environmental Monitoring Program.

This requirement is provided to meet the dose limitations of 40 CFR 190.

Whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I, a Special Report will be submitted which

<E* describes a course of action which should result in the limitation of dose to a real E individual for 12 consecutive months to within the 40 CFR 190 limits.

For conservatism, for compliance with this limit, the maximum total dose to any gt MEMBER OF THE PUBLIC will be assumed to be the sum of the maximums C11 from each dose pathway even though the actual maximally exposed individual for 0

each of the pathways could not be the same person.

0)0 CN The maximum potential dose to a MEMBER OF THE PUBLIC from direct radiation from the Reactor Building and radioactive waste storage tanks is determined by TLD dosimeters located at various locations around the perimeter of the LACBWR access controlled area and the EFFLUENT RELEASE C

UJ BOUNDARY for the environmental monitoring program. For compliance with this 2 5.a limit, the actual maximum possible exposure to an actual MEMBER OF THE

~0 Cu PUBLIC from direct radiation may be determined from maximum possible exposure times relative to the continuous exposure dose measured by the TLD's.

Conservative maximum possible exposure times will be determined by actual C)

-observation of the areas of interest by LACBWR management and/or security personnel.

O

>0)

LuJ 0z CU>-

Ca ODCM 54 Rev. 11

4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 4.1 Program Requirements The Radiological Environmental Monitoring Program (REMP) shall conform to the guidance of Appendix I to 10 CFR Part 50. The REMP shall provide the 0

requirements for monitoring, sampling, analyzing, and reporting radiation and E

0 radionuclides in the environment resulting from the LACBWR facility and/or its effluents. These requirements have been established to ensure the measurements of radiation and of radioactive material in potential exposure opathways to MEMBERS OF THE PUBLIC are performed. Various environmental

& samples will be taken within the area surrounding LACBWR and in selected controlled or background locations. An Interlaboratory Comparison Program a) 0shall be established to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in the environmental sample matrices are performed, as part of quality control for environmental monitoring.

a)C The radiological monitoring program required by this specification provides CD measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from plant effluents. This monitoring program theory supplements the radiological effluent monitoring program by CN verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent M

D Zmeasurements and modeling of the environmental exposure pathways.

The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the

__< measurements of radioactive material in environmental samples are performed to demonstrate that the results are reasonably valid.

ODCM 55 vv Rev 11

4.2 REMP Description Radiological environmental monitoring samples will be collected and analyzed in accordance with Table 4.1. The specific sample locations are listed in HSP-03.1.

Section 3 of the Health and Safety Procedures (HSP's) shall contain procedures CL to provide specific guidance to the HP technicians in the collection and analysis EI of each environmental sample.

E, 0

0 0

C) 0C a,

(D)

,UJ 0

a-CU

_0 a,

VZ a)

CU>

0-Z ODCM 56 Rev. 11

Date j Rad. Prot. Engineer Re w Date Operations Review Comm. Approval DOt:L P LARRY apared or Revised By L. NELSON 121021081 Sey mour J. RaffetvU i1 12/022108 07'c_*-,-- 6, -

r Table 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Sampling and Collection Type and Frequency of Analysis and/or Sample Samples (A) Frequency

1. AIRBORNE Three (3) Continuous operation (1) Analyze each filter for gross beta PARTICULATES of sampler with radioactivity > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter sample collection as change. Perform gamma isotopic analysis required by dust on each sample when gross beta activity is loading, but at least > 10 times the control sample (La Crosse).

weekly.

(2) A composite of particulate filters from each location will be gamma analyzed at least once per quarter.

2. DIRECT Eight (8) At least 1) Gamma dose - at least semi-annually.

RADIATION semiannually.

3. WATERBORNE Two (2) Monthly. 1) Gamma isotopic analysis monthly on each (River Water) sample.

2) Tritium analysis on composite sample from each location quarterly.

(A) Exact sample locations are listed in HSP-03.1.

ODCM 57 Rev. 11

- apared or Revised By I Date Rad. Prot. Engineer Re = Date ions Reyow ComM. Approval I Dak.

LARRY L. NELSON 12/02/08 Seymour J. Raffety W I 12/02/08 O - - I.

Table 4.1 - (cont'd)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Sampling and and/or Sample Samples (A) Collection Frequency Type and Frequency of Analysis

4. RIVER Two (2) Semi-annually (1) Gamma isotopic analysis on each SEDIMENT sample.

5. INGESTION

a. Fish One (1) sample of two At least semi-annually (1) Gamma isotopic analysis of the (2) different species in edible portions of each sample.

area important as a recreational or commercial species.

b. Milk As Determined Obtain sample if (1) Gamma isotopic analysis on each abnormal stack sample.

particulate release occurs

c. Vegetation As Determined Obtain sample if (1) Gamma isotopic analysis of the abnormal stack edible portion of each composite particulate release occurs sample.

(A) Exact sample locations are listed in HSP-03.1.

ODCM 58 Rev. 11

4.3 REMP Lower Limits of Detection (LLD)

The sampling techniques and counting equipment used for the analysis of samples collected as requirements of the REMP will meet LLD's calculated in accordance with criteria of NUREG-0473, Rev. 2. LACBWR's LLD's are E

c3 calculated as follows and are essentially the same as those found in NUREG-U)

C, 0

01 C)

CN

()Co CL.

0 (U

Co C=)

Ma~ z C/)~

-J ODCM 59 Re\ ,.11

4.3.1 Calculation of Lower Limits of Detection:

The LLD is the smallest concentration of radioactive material in a sample that will

-- rbe detected with 95% probability, with 5% probability of falsely concluding that a blank observation represents a "real" signal.

Q For a particular measurement system (which may include radiochemical separation):

LLD= 4.66 S_

E x V x 2.22 x Y x Exp (-XAt)

E 0

0

.WHERE:

LLD is the priori lower limit of detection as defined above (as picocurie per unit M2 mass or volume).

C2 o Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute).

E is the counting efficiency (as counts per gamma).

00.

(N V is the sample size (in units of mass or volume).

2.22 is the number of transformations per minute per picocurie.

Y is gamma abundance for isotope of interest.

0. is the radioactive decay constant for the particular radionuclide.

0 E U, At is the elapsed time between sample collection (or end of the sample collection period) and time of counting.

_C a) C..

>0~-

Q)

LU)

_)j W.>

ODCM 60 Rev. 11

_ *eparedor Revised By I Date II Rad. Prot. Engineer Re IV, Date I Operations Review Comm. Approval Dat. 7 I

LARRY L. NELSON I 12/02/08 II Sey'mour J. RaffetvA -12/02/08 I'-6 Table 4.2 ENVIRONMENTAL SAMPLE ANALYSES LOWER LIMITS OF DETECTION VALUES (LLD)

Sample Type Analysis Water Airborne Particulate Fish Milk Sediment pCi/I or Radioiodine (pCi/m 3) (pCi/Kg, Wet) (pCi/I) (pCi/Kg Dry)

Gross Beta 6 1 E-2 H-3 3500(2000)a Mn-54 15 130 Co-60 15 130 Zn-65 30 260 Cs-134 15 5 E-2 130 15 150 Cs-137 18 6 E-2 150 18 180 a For drinking water.

ODCM 61 Rev. 11

4.4 Interlaboratory Comparison Program An Interlaboratory Comparison Program will be established to ensure that the analyses being performed to comply with the REMP is accurate. A suitable offsite laboratory will be used to supply NIST traceable or equivalent standard 0

spiked sample media for analysis. The offsite laboratory will supply a report to DPC of the comparison results. The Interlaboratory Comparison Program will be E

0 conducted annually. The results of this comparison will be included in the Annual Radiological Environmental Monitoring Report.

Cn C:

0 4.5 Reporting Requirements 0

0 a) An Annual Radiological Environmental Monitoring Report shall be submitted to the Administrator of the Regional Office of the NRC. This C'J report shall include summarized and tabulated results, including interpretations and analysis of data trends, of environmental samples taken during the previous calendar year. In the event that some results a -are not available for inclusion with the report, the report shall be submitted C: -

0 SE noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The report shall also include the following: a summary description of the N Radiological Environmental Monitoring Program, a map of all sampling locations keyed to a table giving distances and directions from the plant, the results of the Interlaboratory Comparison Program, and a discussion (D

T~ Z a)0 of all analyses in which the LLD was not achievable.

-j ODCM 62 Rev. 11

b) With the REMP program not being conducted as specified in Table 4.1,

'_V prepare and submit to the Commission, in the Annual Radiological Environmental Monitoring Report, a description of the reasons for not 2 conducting the program as required, analysis of the cause of unexpected

< results, and the plans for preventing a recurrence.

E 00 c) With the Interlaboratory Comparisons not being performed, report the in the JEE corrective actions taken to prevent a recurrence to the Commission CU2 Radiological Environmental Monitoring Report.

d) With radiological environmental sample analysis in excess of the reporting CD levels listed in Table 4.3, when averaged over any calendar quarter, o prepare and submit to the Commission a Special Report within 30 days, with a description of the reasons for exceeding these reporting levels.

CL1

,UJ 0

CU C-4 C)

M

.Ln z 0z ODCM 63 Rev. 11

Table 4.3 Reporting Levels for Radioactivity Concentrations in Environmental Samples 0 Water Airborne Particulate Fish Mil Analysis pOi/I - -Ci/M 3 pCi/kg' (wet) P~i/l 0 H-3 20,000 ...--.

C-)

Mn-54 1,000 -- 30,000 --

U)

C 0

Co-60 300 -- 10,000 Zn-65 300 -- 20,000 --

00 Cs-134 30 10 1,000 60 CN, Cs-137 50 20 2,000 70 CN 0

0E 00 C)

T~ z

-J ODCM 64 Rev. 11

SECTION B ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

INTRODUCTION:

The RadiologicalEnvironmental Monitoring (REM) Programis conducted to comply with the requirements of the ODCM and in accordance with 10 CFR 50 Appendix I. The REM Programprovides measurements of radiationand of radioactive materialsin those exposure pathways and for those radionuclides which could potentially lead to radiationdoses to Members of the Public resulting from plant effluents. Environmental samples-are taken within the surrounding areas of the plant and in selected control or backgroundlocations.

The monitoring program at the LACBWR facility includes monitoring of liquid and gaseous releases from the plant, as well as environmental samples of surface air,river water, river sediment, milk, fish, and penetratingradiation.

The REM program theory supplements the Radioactive Effluent analyses by verifying that the measurable concentrationsof radioactivematerials and levels of radiation are not higherthan expected on the basis of the effluent measurements and modeling of the environmental exposure pathways using the methodology of the Offsite Dose Calculation Manual (ODCM).

An InterlaboratoryComparison Programis provided to ensure that independent checks on the precision and accuracyof the measurements of radioactive materialin environmental samples are performed.

1

RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 1.0 SAMPLE COLLECTION Environmental samples are collected from the area surrounding LACBWR at the frequencies outlined in the ODCM. A series of figures and tables are included in this report to better show LACBWR's environmental program.

FIGURE 1 This map includes the plant boundary, roads, other generation plants, and the relationship of the plant to the nearest local community.

FIGURE 2 This map shows the location of LACBWR's permanent environmental monitoring stations.

FIGURES 3&4 These maps show the location of LACBWR's TLDs.

TABLE 5 This table shows the sampling frequency of the various environmental samples and the analyses performed on these samples TABLE 6 This table shows the permanent monitoring stations used in LACBWR's environmental program.

TABLE 7 This table shows the TLD locations.

TABLE 8 This table shows the number of various samples collected and analyzed during 2008.

2.0 RESULTS OF THE 2008 RADIO-ENVIRONMENTAL MONITORING SURVEYS During 2008, activity levels in the local environment were normal, indicating no significant plant attributed radioactivity.

2.1 PENETRATING RADIATION The environmental penetrating radiation dose is measured by thermo luminescent dosimeters consisting of four lithium fluoride (LiF) chips. These TLD's are changed on a quarterly basis and are sent to an outside contractor for reading. The TLD results for 2008 are shown on Table 9.

2

RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd) 2.2 AIR PARTICULATE Air samples are collected continuously from various sites (see Table 6) around LACBWR. An air sampler is also located 18 miles north of the plant in La Crosse, Wisconsin, to act as a control station.

Particulate air samples are collected at the rate of approximately 30-60 Ipm with a Gelman Air Sampler. The air filter consists of a glass fiber filter with an associated pore size of approximately 0.45 pm. The particulate filters are analyzed weekly for gross beta activity with an internal proportional counter, and the monthly particulate composites are gamma analyzed for individual isotopic concentration.

TABLE 10 This table shows the weekly gross beta gamma activity concentration from the air particulate filters.

TABLE 11 This table shows the composite air particulate isotopic analysis.

Comparison between the control station at La Crosse and the other stations near LACBWR indicate that there was no significant plant attributable airborne particulate activity.

2.3 RIVER WATER River water is collected monthly. River water samples above at, and below the plant site are collected and are gamma analyzed for isotopic concentration. The river water gamma isotopic analysis results are shown in Table 12. The results indicate that there was no significant plant attributable radionuclides in the river water.

3

RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd) 2.4 SEDIMENT SAMPLES Sediment samples were collected twice per year above, at, and below the plant outfall. These samples were gamma analyzed and these results appear on Table 13. They indicated that small amounts of plant-attributed radionuclides have accumulated in river sediments near the outfall. The amount of radionuclide in this sediment declined significantly after plant shutdown. These amounts have remain relatively constant the last few years.

2.5 FISH Fish samples were collected quarterly above and below the plant discharge. The results of gamma spectral analysis of edible portions of fish samples appear in Table 14. There has been no significant accumulation of plant-attributed radionuclides in fish in the vicinity of LACBWR.

3.0 CONCLUSION

S All environmental samples collected and analyzed during 2007 exhibited no significant contribution from LACBWR.

4

RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd) 4.0 INTERLABORATORY COMPARISON PROGRAM RESULTS During 2008, interlaboratory comparison samples were obtained from an outside contractor. The equipment used to analyze the environmental samples was tested against the contractors' results. The following is the result of this comparison.

LACBWR CONTRACTOR ANALYSIS RESULTS RESULTS RATIO GROSS BETA 183 pCi 173 pCi 1.06 GROSS ALPHA 81.2 pCi 96.9 pCi 0.84 Ce-141 164 pCi 162 pCi 1.02 Cr-51 217 pCi 208 pCi 1.05 Cs-134 95 pCi 113 pCi 0.84 Cs-137 102 pCi 101 pCi 1.01 Co-58 86 pCi 87.8 pCi 0.98 Mn-54 133 pCi 128 pCi 1.04 Fe-59 94 pCi 84.6 pCi 1.11 Zn-65 163 pCi 154 pCi 1.06 Co-60 117 pCi 112 pCi 1.04 H-3 8.30E3 pCi/f 1.02E4 pCi/K 0.81 5

RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd)

-LUSION- BOUNDAT 1109 ft radiu!

1000 500 0 1000 SCALE OF FEET T-1OI-N. , R.-3-W.

OF THE 5th PM.-

JEFFERSON TOWNSHIP HOUSTON COUNTY, / /

MINNESOTA t

1 v/ ISLAND 126 IS UNDER JURISDICTION OF UPPER MISSISSIPPI RIVER THE WILD M-678 INO1CATES MILES ABOVE THE LIFE AND FISH REFUGE.

MOUTH OF THE OHIO RIVER.

FIGURE 1 - LACBWR PROPERTY MAP 6

RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd)

Enviromrental A= Sample Locations 4\\~Q.

FIGURE 2 - PERMANENT ENVIRONMENTAL MONITORING STATION LOCATIONS (Refer to Table 6) 7

RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd)

FIGURE 3 - LACBWR ENVIRONMENTAL DOSE ASSESSMENT LOCATIONS 8

0 I-"

0 i-m z

0 z

m z

.- t I--

0 z

0 (D

z C) m "u

0

.-I C) 0

RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd)

TABLE 5 SAMPLE FREQUENCY AND ANALYSIS OF RADIO-ENVIRONMENTAL SAMPLES SAMPLE FREQUENCY ANALYSIS PERFORMED TLD (LiF) Dosimeters Quarterly Dose in mRem Particulate Air Glass Weekly Gross Beta and Gamma Fiber Filters Spectroscopy of Composites Monthly (HPGe-MCA)

Milk Obtain sample as directed if Gamma Spectroscopy abnormal stack particulate release occurs.

Sediment Twice per year Gamma Spectroscopy Fish Quarterly Gamma Spectroscopy River Monthly Gamma isotopic analysis and tritium (Liquid Scintillation Analyzer)

Vegetation Obtain sample as directed if Gamma Spectroscopy' abnormal stack particulate release occurs.

10

RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd)

TABLE 6 PERMANENT ENVIRONMENTAL MONITORING STATION LOCATIONS (Refer to Figure 2) 1 Radio Tower x 2 Dam No. 8 x 3 Trailer Court x 4 Crib House x 5 Main Office x 11

RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd)

TABLE 7 ENVIRONMENTAL TLD LOCATIONS LOCATION NO. LOCATION 1 LA CROSSE MAIN OFFICE AIR SAMPLER BOX 2 DAM #8 AIR SAMPLER BOX 3 RADIO TOWER BUILDING AT AIR SAMPLER 4 TRAILER COURT AIR SAMPLER BOX 5 CRIBHOUSE AIR SAMPLER BOX 6 G-3 CONTROL ROOM 7 SW GATEPOST AT END OF G-3 DIKE 8 ON FENCE N. SIDE OF FISHERMAN'S ROAD 9 SITE ENTRANCE GUARD AREA 10 ON FENCE AT NE CORNER OF THE SWITCHYARD 11 ON N. SITE AREA FENCE GATE 12 G-1 CRIBHOUSE 13 ON MOORING WALKWAY WEST OF LACBWR #2 WAREHOUSE 14 G-3 COAL UNLOADING CRANE 15 POWER POLE ON BLUFF SIDE EAST OF PLANT 16 RESTRICTED AREA FENCE N. SIDE 17 RESTRICTED AREA FENCE E. SIDE 18 RESTRICTED AREA FENCE S. SIDE 19 RESTRICTED AREA FENCE SW CORNER 20 RESTRICTED AREA FENCE W. SIDE 21 RESTRICTED AREA FENCE NW CORNER 12

RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd)

TABLE 8 RADIO-ENVIRONMENTAL SAMPLES COLLECTED JANUARY-DECEMBER 2008 NUMBER OF TYPE OF SAMPLE SAMPLES Penetrating Radiation (TLD's) 78 Air Particulate 244 River Water 36 Sediment 6 Fish 8 13

RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd)

TABLE 9 QUARTERLY THERMOLUMINESCENT DOSIMETER DOSE MEASUREMENTS IN THE LACBWR VICINITY JANUARY - DECEMBER 2008 BACKGROUND CORRECTED STATION 1st QUARTER 2nd QUARTER 3rd QUARTER 4th QUARTER NO. mRem mRem mRem mRem 1 0 0 0 0 2 Missing 0.9 0 0 3 Missing 0 0 0 4 0 0 2.3 2.7 5 3.7 2.4 1.9 1.9 6 0 0 0 0 7 0 0 Missing 0 8 0 0 0.1 0 9 0 0 1.0 0 10 0 0 0 0 11 0 0 0.2 0 12 0 2.5 2.8 2.7 13 0 0 0 0 14 Missing 0 0 0 15 Missing 5.4 5.0 6.7 16 9.9 7.9 11.9 8.4 17 Missing 9.0 11.0 9.7 18 20 23.4 25.8 24.7 19 5.3 11.5 13.7 11.6 20 1.9 3.0 0.8 4.1 21 22.3 11.2 5.9 6.9 Station #1 (La Crosse Main Office) located approximately 16 miles north of LACBWR is considered the Control TLD.

14

TABLE 10 WEEKLY GROSS BETA AIR PARTICULATES IN THE LACBWR VICINITY (Reporting Level = 10 times Control Value)

COLLECTION LACBWR PLANT TRAILER COURT DAM #8 RADIO TOWER LA CROSSE DATE pCi/m3 pCi/m3 pCi/m3 pCi/m3 CONTROL 01-02-08 .031 + .003 .024 + .002 .024 + .004 00S .029 + .003 01-09-08 .024+.003 .023+.003 .012+.004 00S .027+.003 01-16-08 .033+.003 .029+.003 .029+.004 00S .032+.003 01-23-08 .026 + .003 .022 + .002 .025 + .004 00S .033 + .003 01-29-08 .038 + .004 .022 + .003 .025 + .004 00S .035 + .003 02-06-08 .026 + .002 .020 + .002 .016 + .003 00S .022 + .002 02-13-08 .030 + .003 .021 + .002 .029 + .004 00S .027+ .003 02-20-08 .031 + .003 .017 + .002 .021 + .003 00S .029 + .003 02-27-08 .027 + .003 .019 + .002 .022 + .004 00S .027 + .002 03-05-08 .024 + .003 .018 + .002 .017 + .003 00S .023 + .002 03-12-08 .026 + .003 .020 + .002 .022 + .004 .050 + .003 .024 + .002 03-19-08 .015 + .002 .013+ .002 .013+ .003 .013+ .002 .016 + .002 03-26-08 .014+.002 .015+.002 .012+.003 .015+.002 .016+.002 04-02-08 .016+.002 .012+.002 .009+.003 .013+.002 .014+.002 15

TABLE 10 WEEKLY GROSS BETA AIR PARTICULATES IN THE LACBWR VICINITY (Reporting Level = 10 times Control Value)

COLLECTION LACBWR PLANT TRAILER COURT DAM #8 RADIO TOWER LA-CROSSE DATE 2009 pCi/mr3 pCi/m 3 pCi/m 3 pCi/mr3 CONTROL 04-09-08 .020+.002 1015 +.002 .015+.003 .016+.002 .018+.002 04-16-08 .012+.002 .008+.002 .011+.003 .010+.002 .010+.002 04-23-08 .020+.002 .016-+ .002 .008+.002 .019+.004 .016+.002 05-07-08 .022+.002 .017+.002 .015+.003 .020+.002 .022+.002 05-14-08 .017+.002 .012+.002 .009+.003 .014+.002 .012 +..002 05-21-08 .012+.002 .011 +.002 .007+.002 .013+.002 .011 +.002 05-28-08 .009 + .002 .007 + .002 .007 + .003 .008 + .002 .010 + .002 06-04-08 .016+.002 .016+.002 .010+.002 .013+.001 .015+.002 06-11-08 .010+.001 .010+.001 .009+.002 .024+.005 .013+.002 06-18-08 .014+.002 .010+.001 .009+.002 .010+.001 .013+.001 06-24-08 .015+.002 .015'+.002 .008+.001 .011 +.002 .011 +.002 07-02'-08 .016+.002 .020+.002 .010+.002 .016+.002 .018+.002 07-09-08 .013+.002 .009+.001 .007+.002 .012+.002 .008+.001 07-16-08 .014+.002 .013+.002 .009+.002 .013+.002 .014+.002 16

TABLE 10 WEEKLY GROSS BETA AIR PARTICULATES IN THE LACBWR VICINITY (Reporting Level = 10 times Control Value)

COLLECTION LACBWR PLANT TRAILER COURT DAM #8 RADIO TOWER 3 LA CROSSE DATE pCi/m3 pCi/m3 pC pCi/im CONTROL 07-23-08 .019 + .002 .016 + .002 .007 + .003 .015 + .002 .020 + .002 07-30-08 .019+.002 .020+.002 .018+.003 .017+.002 .019+.002 08-06-08 .018+.002 .018+.002 .016+.003 .020+.002 .016+.002 08-13-08 .013 + .002 .012+ .002 .005 + .002 NO SAMPLE .013 + .002 08-20-08 .020+.002 .02 2+.002 .009+.002 .021+.002 .019+.002 08-27-08 .013+.002 .014+.002 .008+.002 .017+.002 .015+.002 09-09-08 .014+.002 .012+.002 .008+.002 .014+.002 .011 +.002 09-17-08 .012+.002 .012+.002 .007+.001 .014+.002 .011 +.001 09-24-08 .032 + .003 .033 + .002 .027+ .003 .030 + .002 .029 + .002 10-01-08 .026+.002 .026+.002 .017+.003 .026+.002 .026+.002 10-08-08 .022+.002 .015+.001 .011 +.002 .017+.002 .018+.002 10-15-08 .017+.002 .019+.002 .016+.003 .017+.002 .018+.002 10-22-08 .011 +.002 .016+.002 .014+.003 .017+.002 .018+.002 10-28-08 .015+.002 .016+.002 .004+.002 .015+.002 .014+.002 17

TABLE 10 WEEKLY GROSS BETA AIR PARTICULATES IN THE LACBWR VICINITY (Reporting Level = 10 times Control Value)

COLLECTION LACBWR PLANT TRAILER COURT DAM #8 RADIO TOWER LA CROSSE DATE 2009 pCi/mr3 pCi/m 3 pCi/mr3 pCi/mr3 CONTROL 11-05-08 .035 + .003 .038+ .003 .046 + .006 .038 + .002 .037 + .003 11-12-08 .006 + .001 .010 + .002 .006 + .002 .009 + .001 .017 + .002 11-18-08 .005+.001 .015+.002 .009+.001 .016+.002 .013+.002 11-26-08 .009 + .002 .019 + .002 .014 + .003 .021 + .002 .021 + .003 12-03-08 .009+.002 .018+.002 '.014+.003 .017+.002 .019+.002 12-10-08 .009+.002 .013+.002 .013+.003 .019+.002 .016+.002 12-17-08 .014+.002 .017+.002 .019+.003 .020+.002 .023+.002 12-23-08 .016+.002 .017+.002 .018+.003 .022+.002 .026+.003

>12-31-08 .021+ .002 .028 + .003 .020 + .002 .036 + .002 .041 + .003 18

TABLE 11 AIR PARTICULATE COMPOSITE RESULTS 3

(Concentrations in pCi/m )

LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 1-02-08 1-02-08 1-02-08 1-02-08 1-02-08 END DATE 1-29-08 1-29-08 1-29-08 1-29-08 1-29-08 ISOTOPES/RL* OOS Cs-1 34/10 <3.60E-3 <3.21 E-3 <3.24E-3 <6.09E-3 Cs-1 37/20 <3.86E-3 <3.44E-3 <3.18E-3 <6.75E-3

• RL = REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 1-29-08 1-29-08 1-29-08 1-29-08 END DATE 2-27-08 2-27-08 2-27-08 2-27-08 ISOTOPES/RL* OOS Cs-1 34/10 <3.02E-3 <3.03E-3 <5.56E-3 <2.81E-3 Cs-1 37/20 <3.08E-3 <3.14E-3 <5.63E-3 <2.98E-3

• RL = REPORTING LEVEL 19

TABLE 11 AIR PARTICULATE COMPOSITE RESULTS 3

(Concentrations in pCi/m )

LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 2-27-08 2-27-08 2-27-08 2-27-08 2-27-08 END DATE 4-02-08 4-02-08 4-02-08 4-02-08 4-02-08 ISOTOPES/RL*

Cs-134/10 <1.43E-3 <1.82E-3 <1.71E-3 <3.45E-3 <1.80E-3 Cs-137/20 <1.45E-3 < 1.89E-3 <1.77E-3 <3.52E-3 <1.84E-3

• RL = REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 4-02-08 4-02-08 4-02-08 4-02-08 4-02-08 END DATE 4-30-08 4-30-08 4-30-08 4-30-08. 4-30-08 ISOTOPES/RL*

Cs-134/10 <2.09E-3 <2.36E-3 <2.12E-3 <3.87E-3 <2.25E-3 Cs-1 37/20 <2.20E-3 <2.33E-3 <2.21 E-3 <3.99E-3 <2.32E-3

• RL = REPORTING LEVEL 20

TABLE 11 AIR PARTICULATE COMPOSITE RESULTS 3

(Concentrations in pCi/m )

LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 4-30-08 4-30-08 4-30-08 4-30-08 4-30-08 END DATE 5-28-08 5-28-08 5-28-08 5-28-08 5-28-08 ISOTOPES/RL*

Cs-134/10 <2.07E-3 <2.32E-3 <2.11E-3 <4.50E-3 <2.19E-3 Cs-1 37/20 <2.11 E-3 <2.13E-3 <2.184E-3 <4.57E-3 <2.25E-3

• RL = REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 5-28-08 5-28-08 5-28-08 5-28-08 5-28-08 END DATE 6-24-08 6-24-08 6-24-08 6-24-08 6-24-08 ISOTOPES/RL*

Cs-134/10 <2.50E-3 <2.42E-3 <2.13E-3 <3.73E-3 <2.21 E-3 Cs-137/20 <2.54E-3 <2.40E-3 <2.15E-3 <3.78E-3 <2.23E-3

• RL = REPORTING LEVEL 21

TABLE 11 AIR PARTICULATE COMPOSITE RESULTS 3

(Concentrations in pCi/m )

LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 6-24-08 6-24-08 6-24-08 6-24-08 6-24-08 END DATE 7-30-08 7-30-08 7-30-08 7-30-08 7-30-08 ISOTOPES/RL*

Cs-134/10 <2.26E-3 <2.27E-3 <1.95E-3 <3.17E-3 <1.73E-3 Cs-137/20 <2.26E-3 <2.24E-3 <2.1OE-3 <3.24E-3 <1.78E-3

• RL = REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 7-30-08 7-30-08 7-30-08 7-30-08 7-30-08 END DATE 9-03-08 9-03-08 9-03-08 9-03-08 9-03-08 ISOTOPES/RL*

Cs-1 34/10 <2.20E-3 <1.72E-3 <1.15E-3 <3.42E-3 <1.69E-3 Cs-137/20 <2.28E-3 <1.75E-3 <1.13E-3 <3.38E-3 <1.80E-3

• RL = REPORTING LEVEL 22

TABLE 11 AIR PARTICULATE COMPOSITE RESULTS 3

(Concentrations in pCi/m )

LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 9-03-08 9-03-08 9-03-08 9-03-08 9-03-08 END DATE 10-01-08 10-01-08 10-01-08 10-01-08 10-01-08 ISOTOPES/RL*

Cs-134/10 <2.27E-3 <2.78E-3 <2.05E-3 <4.17E-3 <1.91E-3 Cs-1 37/20 <2.31 E-3 <2.84E-3 <2.27E-3 <4.40E-3 <2.02E-3

• RL = REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 10-01-08 10-01-08 10-01-08 10-01-08 10-01-08 END DATE 10-28-08 10-28-08 10-28-08 10-28-08 10-28-08 ISOTOPES/RL*

Cs-134/10 <2.68E-3 <2.69E-3 <2.62E-3 <5.30E-3 <2.43E-3 Cs-137/20 <2.74E-3 <2.86E-3 <2.55E-3 <5.40E-3 <2.42E-3

• RL = REPORTING LEVEL 23

TABLE 11 AIR PARTICULATE COMPOSITE RESULTS 3

(Concentrations in pCi/m )

LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 10-28-08 10-28-08 10-28-08 10-28-08 10-28-08 END DATE 11-26-08 11-26-08 11-26-08 11-26-08 11-26-08 ISOTOPES/RL*

Cs-134/10 <2.29E-3 <2.78E-3 <2.72E-3 <5.36E-3 <2.69E-3 Cs-137/20 <2.31E-3 <2.84E-3 <2.81E-3 <5.78E-3 <2.80E-3

• RL = REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 11-26-08 11-26-08 11-26-08 11-26-08 11-26-08 END DATE 12-31-08 12-31-08 12-31-08 12-31-08 12-31-08 ISOTOPES/RL*

Cs-1 34/10 <1.82E-3 <2.65E-3 <2.43E-3 <4.OOE-3 <2.13E-3 Cs-137/20 <2.05E-3 <2.71 E-3 <2.45E-3 <3.98E-3 <2.26E-3

• RL = REPORTING LEVEL 24

TABLE 12 RESULTS OF ANALYSIS OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR (Report Concentrations in pCi/Liter)

SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPLE #1 SAMPLE #2 SAMPLE #3 COLLECTION DATE: 1-08-08 1-08-08 1-08-08 2-12-08 2-12-08 2-12-08 SAMPLE LOCATION: DAM 8 OUTFALL VICTORY DAM 8 OUTFALL VICTORY ISOTOPES/RL

• H-3 <182 <182 <182 195 +/- 138 210 +/- 139 <147 Mn-54/1000 <5.61 <5.45 <5.37 <5.37 <5.58 <5.53 Co-60/300 <5.96 <5.89 <5.86 <5.82 <5.73 <5.68 Zn-65/300 <12.1 <12.4 <12.2 <12.3 <12.6 <12.1 Cs-134/30 <5.99 <6.03 <5.78 <6.06 <6.12 <6.07 Cs-1 37/50 3.80 +/- 1.2 <3.21 <3.62 <6.10 <6.28 <6.20 i i i. -4 i -

• RL = REPORTING LEVEL 25

TABLE 12 RESULTS OF ANALYSIS OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR (Report Concentrations in pCi/Liter)

SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPLE #1 SAMPLE #2 SAMPLE #3 COLLECTION DATE: 3-11-08 3-11-08 3-12-08 4-08-08 4-08-08 4-08-08 SAMPLE LOCATION: DAM 8 OUTFALL VICTORY DAM 8 OUTFALL VICTORY ISOTOPES/RL

• H-3 227 +/- 1.48 326 +/- 150 311 +/- 141 <159 <159 <159 Mn-54/1000 <5.49 <5.43 <5.45 <4.28 <4.22 <4.13 Co-60/300 <5.82 <5.84 <5.82 <4.15 <4.34 <4.31 Zn-65/300 <12.2 <12.1 <12.3 <9.70 <9.31 <9.74 Cs-1 34/30 <6.03 <6.14 <6.07 <4.74 <4.63 <4.70 Cs-137/50 <6.24 <5.95 <6.03 <4.67 <3.14 <3.00

• RL = REPORTING LEVEL 26

TABLE 12 RESULTS OF ANALYSIS OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR (Report Concentrations in pCi/Liter)

SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPLE #1 SAMPLE #2 SAMPLE #3 COLLECTION DATE: 5-12-08 5-12-08 5-12-08 6-09-08 6-09-08 6-09-08 SAMPLE LOCATION: DAM 8 OUTFALL VICTORY DAM 8 OUTFALL VICTORY ISOTOPES/RL

• H-3 <159 <159 <159 <163 <163 <163 Mn-54/1000 <3.96 <4.06 <4.01 <4.02 <4.22 <4.02 Co-60/300 <4.32 <4.15 <4.46 <4.22 <4.33 <4.47 Zn-65/300 <9.29 <9.71 <8.86 <9.38 <9.69 <9.72 Cs-134/30 <4.34 <4.56 <4.63 <4.56 <4.61 <4.54 Cs-i 37/50 <4.87 <4.85 <4.61 <4.94 <4.90 <4.68

• RL = REPORTING LEVEL 27

TABLE 12 RESULTS OF ANALYSIS OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR (Report Concentrations in pCi/Liter)

SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPLE #1 SAMPLE #2 SAMPLE #3 COLLECTION DATE: 7-08-08 7-08-08 7-08-08 8-12-08 8-12-08 8-12-08 SAMPLE LOCATION: DAM 8 OUTFALL VICTORY DAM 8 OUTFALL VICTORY ISOTOPES/RL

• H-3 <152 278 +/-145 <152 <154 <154 <154 Mn-54/1000 <4.04 <4.07 <3.99 <4.16 <4.14 <4.14 Co-60/300 <4.32 <4.34 <4.23 <4.30 <4.49 <4.41 Zn-65/300 <9.60 <9.26 <9.31 <9.85 <9.40 <9.96 Cs-134/30 <4.54 <4.63 <4.55 <4.70 <4.56 <4.70 Cs-1 37/50 <4.63 <2.76 <4.76 <4.77 <4.68 <4.78

-I 4 4- .4 I

• RL = REPORTING LEVEL 28

TABLE 12 RESULTS OF ANALYSIS OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR (Report Concentrations in pCi/Liter)

SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPLE #1 SAMPLE #2 SAMPLE #3 COLLECTION DATE: 9-09-08 9-09-08 9-09-08 10-07-08 10-07-08 10-07-08 SAMPLE LOCATION: DAM 8 OUTFALL VICTORY DAM 8 OUTFALL VICTORY ISOTOPES/RL

• H-3 <162 <162 <162 <164 <164 <164 Mn-54/1000 <4.04 <4.08 <4.15 <3.99 <4.05 <4.02 Co-60/300 <4.45 <4.41 <4.46 <4.32 <4.41 <4.50 Zn-65/300 <9.22 <9.19 <9.54 <9.76 <9.63 <9.28 Cs-134/30 <4.69 <4.57 <4.52 <4.65 <4.57 <4.44 Cs-137/50 <4.69 <4.69 <4.89 <4.67 <4.66 <4.68

• RL = REPORTING LEVEL 29

TABLE 12 RESULTS OF ANALYSIS OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR (Report Concentrations in pCi/Liter)

SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPLE #1 SAMPLE #2 SAMPLE #3 COLLECTION DATE: 11-12-08 11-12-08 11-12-08 12-08-08 12-08-08 12-08-08 SAMPLE LOCATION: DAM 8 OUTFALL VICTORY DAM 8 OUTFALL VICTORY ISOTOPES/RL

• H-3 <168 <168 <168 <149 <149 <149 Mn-54/1000 <4.02 <4.14 <4.19 <4.04 <4.12 <3.95 Co-60/300 <4.22 <4.32 <4.16 <4.38 <4.28 <4.22 Zn-65/300 <9.52 <9.32 <9.54 <9.69 <9.30 <9.19 Cs-134/30 <4.80 <4.79 <4.71 <4.56 <4.81 <4.38 Cs-137/50 <4.83 <4.86 <4.95 <4.58 <4.76 <4.85

• RL = REPORTING LEVEL 30

TABLE 13 RESULTS OF ANALYSIS OF MISSISSIPPI RIVER SEDIMENT IN THE VICINITY OF LACBWR (Concentration in pCi/Kg)

(Reporting Level = 10 times Control Value)

SAMPLE LOCATION UPSTREAM OUTFALL DOWNSTREAM UPSTREAM OUTFALL DOWNSTREAM COLLECTION DATE 5-22-08 5-22-08 5-22-08 8-20-08 8-20-08 8-20-08 ISOTOPES Cs-134 <4.96 <5.03 <10.1 <4.87 <4.22 <8.96 Cs-137 <3.33 209 +/- 8.62 62.8 +/- 4.18 <3.33 37.0 +/- 2.29 72.2 +/- 4.33 Co-60 11.6 +/- 1.30 3.76 +/-.80 i i + 4 31

TABLE 14 FISH SAMPLE ACTIVITY IN THE VICINITY OF LACBWR (Report Concentrations in pCi/Kg)

SAMPLE TYPE: CARP WALLEYE WALLEYE CARP CARP BASS COLLECTION DATE: 3-31-08 3-31-08 5-22-08 5-22-08 8-20-08 8-20-08 ISOTOPES/RL*

Mn-54 / 3E4 <6.21 <8.86 <6.39 <6.23 <6.04 <6.79 Co-60/1 E4 <6.90 <10.4 <7.31 <7.52 <7.40 <7.61 Zn-65/2E4 <16.0 <23.3 <16.8 <16.9 <16.4 <17.8 Cs-134/1E3 <6.37 <9.13 <7.14 <6.93 <6.92 <7.08 Cs-137/2E3 31.2+3.23 11.9+2.79 6.88+2.00 <4.98 <7.26 7.87+2.78

+i

• RL =REPORTING LEVEL 32

TABLE 14 FISH SAMPLE ACTIVITY IN THE VICINITY OF LACBWR (Report Concentrations in pCi/Kg)

SAMPLE TYPE: WALLEYE CARP COLLECTION DATE: 10-23-08 10-23-08 ISOTOPES/RL*

Mn-54/3E4 <7.35 <6.21 Co-60/1E4 <8.34 <6.21 Zn-65/2E4 <19.4 <16.1 Cs-134/ 1E3 <7.88 <7.02 Cs-137/2E3 <7.20 40.0 +/- 3.83 Cd-109 123 +/- 61.6

• RL =REPORTING LEVEL 33