ML15056A700

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Boiling Water Reactor - Offsite Dose Calculation Manual, Revision 15
ML15056A700
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 08/26/2014
From: Nick B
Dairyland Power Cooperative
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards
Shared Package
ML15056A702 List:
References
LAC-14331
Download: ML15056A700 (24)
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Text

DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR OFFSITE DOSE CALCULATION MANUAL REVISION 15 PREPARED BY DATE P. -_.2.-,,

I APPROVED BY DATE

TABLE OF CONTENTS Section Pase

1.0 INTRODUCTION

1.1 Purpose ......................................................................................................................... 1 1.2 Definitions ...................................................................................................................... 1 2.0 OFFSITE DOSE CALCULATIONS ............................................................................................ 4 2.1 Compliance with the Limitations for Liquid Effluent Releases .......------------...........--- --------- 4 2.1.1 Calculation of Liquid Effluent Monitor Alarm Settings ... ..................... 4 2.1.2 Calculation of Instantaneous Allowable Release Rates ....................... 4 2.1.3 Calculation of Liquid Effluent Dose Contribution ................................................... 7 2.1.4 Calculation of Dose Commitments from Liquid Effluents ......................................... 8 3.0 RADIOACTIVE EFFLUENT CONTROL PROGRAM 21 3.1 Program Requirements ................................................................................................... 21 3.2 Liquid Effluents .............................................................................................................. 21 3.2.1 Sampling and Analysis .................................................................................... 21 3.2.2 Liquid Effluent Release Limitation ........................................................................... 23 3.2.3 Liquid Effluent Instrumentation .......................................................................... 24 3.3 Total Dose to a Member of the Public ....................................... 32 3.4 Radioactive Effluent Control Reporting Requirements .......................-.................................. 37 3.4.1 Radioactive Effluent Release Report .................................................................. 37 3.4.2 RECP Non-Conformance Reporting .................................................................... 38 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 34 4.1 Program Requirements ............................................................................................... 34 4.2 REMP Description ..................................................................................................... 34 4.3 REMP Lower Limits of Detection .......................................... 36 4.3.1 Calculation of Lower Limits of Detection------------------------------- 36 4.4 Interlaboratory Comparison Program ............................................................................ 38 4.5 Radiological Environmental Monitoring Reporting Requirements ............................................ 38 4.5.1 Radiological Environmental Monitoring Report ........................................................ 38 4.5.2 REMP Non-Conformance Reporting .................................................................. 38 ODCM i Rev. 15

TABLE OF CONTENTS LIST OF TABLES 3.1 Radioactive Liquid Waste Sampling and Analysis Requirements for Batch Releases -------------------------------------------------- 21 3.2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirem ents ................................................................................................................ 25 4.1 Radiological Environmental Monitoring Program .............................................................. 35 4.2 Environmental Sample Analyses Lower Limits Values (LLD) ............................................. 37 4.3 Reporting Levels for Radioactivity Concentrations in Environmental Sam ples ........................................... 3............................................

39 3------------

LIST OF FIGURES 1.1 Site Map, Including Effluent Release Boundary ................................................................ 3 2.1 Liquid Release Monitor Alarm Setpoint Determination ........................................................... 6 ODCM ii Rev. 15 1

1.0 INTRODUCTION

1.1 Purpose The Offsite Dose Calculation Manual (ODCM) contains the methodology and parameters used in (1) the calculation of offsite doses resulting from radioactive liquid effluents from LACBWR, and (2) the calculation of liquid effluent monitoring Alarm/Trip Setpoints. The ODCM also contains the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs.

1.2 Defintions CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and 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.

CHANNEL CHECK 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 indications and/or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be:

a. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions and channel failure trips.
b. Bistable channels - the injection of a real or simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.

EFFLUENT RELEASE BOUNDARY The Dairyland Power Cooperative property line within the 1109-feet (338-meter) radius EXCLUSION AREA is the EFFLUENT RELEASE BOUNDARY (See Figure 1.1.)

EXCLUSION AREA The EXCLUSION AREA is defined as the area within an 1109-feet (338-meter) radius from the centerline of the Reactor Building. This was the area established per 10 CFR 100 as the EXCLUSION AREA for plant siting and operation.

ODCM 1 of 21 Rev. 15 I

MAXIMUM PERMITTED CONCENTRATION (MPC)

The limiting liquid effluent concentration value 10 CFR 20, Appendix B, Table 2, Column 2.

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 PUBLIC during any period in which the individual receives an occupational dose.

OPERABLE-OPERABILITY A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s) and when 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 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

ODCM 2 of 21 Rev. 15 I

FIGURE 1.1 SITE MAP INCLUDING EFFLUENT RELEASE BOUNDARY

  • -METEOROLOGICAL TOWER SCALE 400' 800' a

ODCM 3 of 21 Rev. 15 I

2.0 OFFSITE DOSE CALCULATIONS 2.1 Compliance with the Limitations for Liquid Effluent Releases 2.1.1 Calculation of Liquid Effluent Monitor Alarm Setpoints To assure compliance with the limitations of Section 3.2.2a, Radioactive Effluent Control Program (RECP), the liquid effluent monitor alarm setpoint is calculated as a function of the maximum effluent flow rate and the minimum dilution flow rate. The following equation is used to calculate the setpoint:

af < C (2.1) k(F+f)

Where:

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

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

k= the conversion factor, CPS per pCi/ml, for the liquid waste effluent monitor based upon most recent calibration of the monitor.

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

F= the dilution stream, Genoa Station No. 3 (G-3) Circulating Water volumetric flow, in gallons per minute.

Since f << F, Equation 2.1 is satisfied when the following discharge line liquid effluent monitor setpoint is met:

a< k(2.2) f 2.1.2 Calculation of Instantaneous Allowable Release Rates LACBWR's river water infiltration is collected in the turbine building east sump._jn order to assess the required liquid effluent monitor alarm setpoint, a, the following step-by-step method for obtaining data will be performed. The form presented in Figure 2.1 may be used as a worksheet for these calculations. The alarm setpoint calculation may be performed on an annual basis if the setpoint is determined to be 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 10 CFR 20, appendix B, Table 2, Column 2 values.

ODCM 4 of 21 Rev. 15 I

1) Go to Figure 2.1. Enter the date on the form.
2) Enter the concentration Ci (pCi/ml) for each isotope, i, in a typical LACBWR river water discharge.
3) The values of f and F are determined and recorded at the top of Figure 2.1.

F is the minimum volumetric dilution flow rate during release at the LACBWR/G-3 outfall which is equal to the G-3 Circulating Water flow rate in gallons per minute. The value f is the maximum radioactive liquid release flow rate (GPM) for the discharge during the period. A value of 17 GPM is normally specified for f.

4) The quantities ZCi and ZCi/MPCi are determined and recorded.
5) The monitor conversion factor, k, determined at last primary calibration is recorded on Figure 2.1, in CPS (net) per pCi/ml.
6) The alarm setpoint, a (in CPS with a factor of 0.5 for conservatism), for the liquid effluent monitor measuring the radioactivity concentration in the effluent line is then determined by:

a 0.5kF Z Ci(

a E (2.3)

ODCM 5 of 21 Rev. 15 I

FIGURE 2.1 LIQUID RELEASE MONITOR ALARM SETPOINT DETERMINATION Date Maximum Liquid Release Rate for Period, f= GPM Minimum Dilution Flow Rate for Period, F= GPM Average Concentration (10 CFR Part 20,:- C MP -.

Nu. C..(pCi/m.l' ". " Appendix B

_ _ _ _ _ _ _ _ _ _:T a b le 2 , C o1..2 ) '

tCo-60 3 E-06 Cs-1 37 1 E-06 Cs-134 9 E-07 Sr-90 5 E-07 Fe-55 1 E-04

CCi/MPC;=

Monitor Conversion Factor, k =CPS (net) pCi/ml Liquid Release Monitor Alarm Setpoint, 0 .5kF T.C_

a= f -7Ci/M PCi -FECC CPS above background ODCM 6 of 21 Rev. 15 1

2.1.3 Calculation of Liquid Effluent Dose Contribution To demonstrate compliance with the limitations of Section 3.2.2b, dose contributions are calculated at a maximum interval of once every calendar quarter for all radionuclides identified in liquid 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 equation:

DaT= .i (AaiT Zj=1 Ci/Fj) (2.4)

Where:

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

C1i = the total quantity of radionuclide i, released j, in Ci.

Aai, = 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 principal gamma and/or beta emitter, in mRem-gal-min'-Ci'.

Fj = the average dilution water flow rate during release j, in gallons per minute.

Equation 2.4 requires the use of a dose factor AaI, for each nuclide, organ and individual in age group a, which includes the factors which determine the ultimate dose 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 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 invertebrate pathway. The drinking water pathway is not included, since the nearest community which obtains its drinking water 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 irrigation in this area and the shoreline deposits pathway is insignificant for the Mississippi River. The only significant dose pathway is the dose commitment due to ingestion of fish from the Mississippi River waters.
2) Dilution The liquid effluent flow from the east turbine sump is diluted by Circulating Water from G-3. For offsite dose calculations, no dilution by the Mississippi River flow is considered. Also, discharges of influx river water normally take place on average 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 as assumed in the calculation of ODCM 7 of 21 Rev. 15 I

the published bioaccumulation factors for fish.

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

AaiT=Ko(UFa)(BFj)(DFaiT) (2.5)

Where:

K, = a units conversion constant, 5.03 E+5 =

(1 E+12 pCi/Ci x 0.2642 gal/I) / (8760 hrs/yr x 60 min/hr).

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 pCi/kg per pCi/ I.

DFaiT = the ingestion dose factor for age group a, for nuclide i, in organ T, in mRem/pCi.

2.1.4 Calculation of Dose Commitments from Liquid Effluents The equations for this calculation have been formatted on a computer-based spreadsheet. The values of UF,, BF, and DFaiT specified in NRC Regulatory Guide 1.109 Rev. 1, October 1977, and the constant K. have been entered on the spreadsheet.

To perform the calculation the following information is entered in the appropriate cells of the spreadsheet for each liquid effluent released during the period of interest:

1) Date
2) Release interval, hrs
3) Waste volume, gal
4) Circulating 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 in mRem to the total body and each organ of an individual in each age group.

The cumulative calendar year doses and the percentage of the limits set forth in Section 3.2.2b, are also calculated. This spreadsheet will also print the data tables for the liquid effluent section of the annual Radioactive Effluent Release Report.

ODCM 8 of 21 Rev. 15 I

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 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 liquid effluents released from LACBWR to ensure the concentrations in effluents released to 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 liquid monitoring instrumentation, including surveillance test and setpoint determination in accordance with Section 2.0, Offsite Dose Calculations, will be included in this program.

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.

3.2 Liquid Effluents 3.2.1 Samplinq and Analysis All liquid effluent releases at LACBWR will be from the east turbine building sump. Prior to discharge a representative sample will be analyzed.. The radioactive content of each discharge shall be determined in accordance with Table 3.1.

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.

ODCM 9 of 21 Rev. 15 I

TABLE 3.1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS REQUIREMENTS FOR EAST.TURBINE BUILDING SUMP RELEASES Type of Activity Analysis(c) SamplingFrequency MinimumAnalysis.

" - '.Frequency .

Principal Gamma emitters(b) Prior to discharge Each discharge - prior to Each discharge - prior to 2 Gross Alpha Prior to discharge discharge 3 Tritium Prior to discharge Each discharge 4 Sr-90 and Fe-55 Beta emitters Prior to discharge Quarterly Composite(a)

NOTES:

(a) A composite sample is one made up of individual samples which are proportional to the 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 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 and reported.

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

ODCM 10 of 21 Rev. 15 I

3.2.2 Liquid Effluent Release Limitation a) Concentration - the concentration of radioactive material released in liquid effluents at any time to areas beyond the EFFLUENT RELEASE BOUNDARY shall be limited to concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.

If the concentration of radioactive material released beyond the EFFLUENT RELEASE BOUNDARY exceeds the above limits, restore 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.

b) Dose - the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to areas beyond the Effluent Release Boundary shall be limited to:

Calendar Quarter Calendar Year

< 1.5 mRem total body < 3 mRem total body

< 5 mRem to any organ < 10 mRem to any organ The cumulative dose contribution from liquid effluent shall be determined at least once per calendar quarter in accordance with 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 exceeding the limit(s) and defines the corrective actions which have 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 ll.A, Ill.A, IV.A and Annex of Appendix 1,10 CFR Part 50. The dose calculations in Section 2.0 implement the requirement in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.

ODCM 11 of 21 Rev. 15 1

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 3.2.2a, are not exceeded, at all times when releasing liquid radioactive effluents.

  • Liquid Radwaste Effluent Line Monitor and;

" 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.

The 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.

a) Surveillance Requirements - each radioactive liquid 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 shown in Table 3.2.

b) Corrective Action

1) With the Liquid Radwaste Effluent Line Monitor channel alarm/trip-point setpoint less conservative than that required by Section 3.2.2a, immediately suspend the release or change the setpoint so that it is acceptably conservative.
2) With the Liquid Radwaste Effluent Line Monitor NOT OPERABLE, or if its alarm setpoint is found to be less conservative than required, suspend release of liquid radioactive effluent without delay. Effluent releases may be resumed without the Liquid Radwaste Effluent Line Monitor OPERABLE, provided that at least two independent samples are analyzed and that at least two technically qualified members of the staff independently verify the release rate calculations. Ifthe monitor is not operable for more than 30 continuous days, explain in the next annual Radioactive Effluent Release Report.
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.

ODCM 12 of 21 Rev. 15 1

TABLE 3.2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

  • Channel Instrment Channel- Source Chne Instrument Functional Channel Calibration Check Checks Test Liquid Radwaste Prior to Prior to discharge Quarterly )

(SeNt At least once per 18 months Effluent Line Monitor discharge (See Note 4)(See 1) Note 18month (See 4 Note ) (See Note 3)

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

NOTES:

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that an alarm indication occurs ifany of the following conditions exist:

  • Instrument indicates measured levels at the alarm setpoint.

" Instrument indicates a downscale (circuit failure) failure.

(2) The 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 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 sensor. The source will have the gamma emitting radionuclide mixture and activity concentration which would normally be measured by the channel during batch discharges.

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

(5) The CHANNEL CALIBRATION will be in accordance with approved procedures.

ODCM 13 of 21 Rev. 15 I

3.3 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 organ (except the thyroid, which is limited to < 75 mRem) over a period of one calendar year.

With the calculated doses from the release of radioactive materials in liquid 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 direct radiation from Reactor Building and radioactive waste storage tanks to determine ifthe above limits have been exceeded. If these 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 recurrence of exceeding these limits. If the 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. 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 effluents shall be determined quarterly and annually in accordance with Section 2.0, Offsite Dose Calculations.

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 1,10 CFR Part 50, a Special Report will be submitted which describes a course of action which should result in the limitation of dose to a real 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 MEMBER OF THE PUBLIC will be assumed to be the sum of the maximums from each dose pathway even though the actual maximally exposed individual for each of the pathways could not be the same person.

ODCMV 14 of 21 Rev. 15 I

3.4 Radioactive Effluent Control Reporting Requirements 3.4.1 Radioactive Effluent Release Report Paragraph (a)(2) of 10 CFR 50.36a, "Technical Specifications on Effluents from Nuclear Power Reactors," requires that a report be made to the Commission annually. The report shall specify the quantity of each of the principal radionuclides released to unrestricted areas by liquid or gaseous effluents during the previous year. With the exception of the collection of hourly meteorological data, the information submitted shall be in accordance with Appendix B of Regulatory Guide 1.21 (Revision 1) dated June 1974 with data summarized on at least a quarterly basis. The Radioactive Effluent Release Report shall be submitted by March 1 of each year.

This same report shall include an assessment, performed in accordance with the ODCM, of radiation doses to members of the public from radioactive liquid effluents released beyond the effluent release boundary. This report shall contain any changes made to the ODCM during the previous twelve months.

3.4.2 RECP Non-Conformance Reporting

1) With the Radiological Effluent Control Program not being conducted as specified in Sections 3.2.2b, 3.3.1, 3.3.3b, and 3.4; 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 or will be taken to assure that subsequent releases shall be in compliance with the stated limits.

Refer to Sections 3.2.2b, 3.3.1, 3.3.3b, and 3.4 for specific information.

ODCM 15 of 21 Rev. 15 1

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 requirements for monitoring, sampling, analyzing, and reporting radiation and 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 pathways to MEMBERS OF THE PUBLIC are performed. Water and sediment samples will be taken as per Table 4.1.. An Interlaboratory Comparison Program shall 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.

The radiological monitoring program required by this specification provides 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 verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements 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.

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 RP-03.01. Section 3 of the Radiation Protection Procedures shall contain procedures to provide specific guidance to the HP technicians in the collection and analysis of each environmental sample.

ODCM 16 of 21 Rev. 15 I

TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

  • Exposure Pat.hWay -Number of. Sampling and Collection and/oran Sample Samp"esa) .:.....

/ M WSam.ples:. Frequency.

,Frequenwy:'.i'.:"..!*." :Type

. Frequency and.:,..:  :"-. of .. Analysis "1. WATERBORNE Two (2) Semi-annually 1) Gamma isotopic analysis semi-annually on each (River Water) sample.

2) Tritium analysis on composite sample semi-annually on each sample.
2. RIVER SEDIMENT Two (2) Semi-annually 1) Gamma isotopic analysis on each sample.,

NOTE: (a) Exact sample locations are listed in RP-03.01.

ODCM 17 of 21 Rev. 15 I

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 LLDs calculated in accordance with criteria of NUREG-0473, Rev. 2. LACBWR's LLDs are calculated as follows and are essentially the same as those found in NUREG-0473, Rev. 2. Table 4.2 lists these values.

4.3.1 Calculation of Lower Limits of Detection:

The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability, with 5% probability of falsely concluding that a blank observation represents a "real" signal.

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

4.66 Sb E x V x2.22 x Y x exp (-AAt)

Where:

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

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

E= counting efficiency (as counts per gamma).

V= sample size (in units of mass or volume).

2.22 = number of transformations per minute per picocurie.

Y= gamma abundance for isotope of interest.

A= radioactive decay constant for the particular radionuclide.

At = elapsed time between sample collection (or end of the sample collection period) and time of counting.

ODCM 18 of 21 Rev. 15 I

TABLE 4.2 ENVIRONMENTAL SAMPLE ANALYSES LOWER LIMITS OF DETECTION (LLD) VALUES Samnple Type Analysis. Water . Sediment.

pCi/I (pCVKg-Dry)

Gross Beta 6 1 E-2 H-3 3500(2000)(8)

Mn-54 15 Co-60 15 Zn-65 30 Cs-134 15 150 Cs-137 18 180 NOTE: (a) For drinking water.

ODCM 19 of 21 Rev. 15 I

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 spiked sample media for analysis. The offsite laboratory will supply a report to DPC of the comparison results. The Interlaboratory Comparison Program will be conducted annually. The results of this comparison will be included in the Radiological Environmental Monitoring Report.

4.5 Radiological Environmental Monitoring Reportingq Requirements 4.5.1 Radiological Environmental Monitoring Report The Radiological Environmental Monitoring Report shall be submitted annually to the Administrator of the Regional Office of the NRC. This 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 are not available for inclusion with the report, the report shall be submitted 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 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 of all analyses in which the LLD was not achievable. The Radiological Environmental Monitoring Report shall be submitted by March 1 of each year.

4.5.2 REMP Non-Conformance Reportinq

1) With the Radiological Environmental Monitoring Program not being conducted as specified in Table 4.1, prepare and submit to the Commission, in the Radiological Environmental Monitoring Report, a description of the reasons for not conducting the program as required, analysis of the cause of unexpected results, and the plans for preventing a recurrence.
2) With the Interlaboratory Comparisons not being performed, report the corrective actions taken to prevent a recurrence to the Commission in the Radiological Environmental Monitoring Report.
3) With radiological environmental sample analysis in excess of the reporting levels listed in Table 4.3, when averaged over any calendar quarter, prepare and submit to the Commission a Special Report within 30 days, with a description of the reasons for exceeding these reporting levels.

ODCM 20 of 21 Rev. 15 I

TABLE 4.3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Analysis Water

_ . . . . . ". .. . pC i/l.I H-3 20,000 Mn-54 1,000 Co-60 300 Zn-65 300 Cs-134 30 Cs- 137 50 ODCM 21 of 21 Rev. 15 I

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