ML20199E418

Rev 11A to Section 8, Radioactive Effluent Treatment Sys, Models for Setting Gaseous & Liquid Effluent Monitor Alarm & Trip Setpoints..., of Offsite Dose Calculation Manual

ML20199E418
Person / Time
Site:	Byron
Issue date:	03/31/1986
From:	COMMONWEALTH EDISON CO.
To:
References
PROC-860331-01, NUDOCS 8606230296
Download: ML20199E418 (37)

Text

I BYRON REVISION llA MA,RCH 1986

- g ODCM TABLE OF CONTENTS FOR BYRON SECTION 8.0 PAGE

~

8.0 RADIOACTIVE EFFLUENT TREATMENT SYSTEMS, MODELS FOR SETTING GASEOUS AND LIQUID EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, AND ENVIRONMENT RADIOLOGICAL MONITORING 8.1-1 8.1 GASEOUS RELEASES 8.1-1 8.1.1

System Design

8.1-1 8.1.1.1 Gaseous.Radwaste Treatment System 8.1-1 8.1.1.2 Ventilation Exhaust Treatment System 8.1-1 8.1.2 Alarm and Trip Setpoints 8.1-1 8.1.3 Station Vent Stack Monitors 8.1-3 8.1.4 Containment Purge Effluent Monitors 3.1-4 8.1.5 Gas Decay Tank Monitors 8.1-5 8.1.6 Allocation of Effluents from Common Release Points 8.1-6 8.1.7 Symbols Used in Section 8.1 8.1-7 8.1.8 Constants Used in Section 8.1 8.1-8 8.2 LIQUID RELEASES 8.2-1 8.2.1

System Design

8.2-1 8.2.2 Alarm Setpoints 8.2-1 8.2.3 Liquid Radwaste Effluent Monitor 8.2-3 8.2.4 Station Blowdown Monitor 8.2-4 8.2.5 Reactor Containment Fan Cooler (RCFC) and Essential Service Water Outlet Line Monitors 8.2-5 8.2.6 Administrative and Procedural Controls for Radwaste Discharges 8.2-6 8.2.7 Determination of Initial Dilution Stream 8.2-6 Flow Rates 8.2.8 Allocation of Effluents from Common Release Points 8.2-7 8.2.9 Symbols Used in Section 8.2 8.2-7 8.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM 8.3-1 8.4 ENVIRONMENTAL RADIOLOGICAL MONITORING 8.4-1 e606230296 860331 PDR ADOCK 05000454 p

PDR 8-1 Q

g j u> of

• L-

. - ~ _.

BYRON REVISION llA MARCH 1986 O

ODCM LIST OF TABLES FOR BYRON SECTION 8.0 i

NUMBER TITLE PAGE i

8.4-1 Environmental Radiological Monitoring Program 8.4-2 8.4-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 8.4-7 8.4-3 Detection capabilities for Environmental Sample Analysis 8.4-8 l

d O

9 O

8-11

,n

---+--,---------,-,n,,.,,---,-,,n

-.m--

-,-e,.--,---,---_--,-.-,,,,-----,,n,-,,vv,.r,-,-_,_,-

---

,--m,-,-_.--n,

i BYRON REVISION llA MARCH 1986 O

ODCM LIST OF FIGURES FOR BYRON SECTION 8.0 NUMBER TITLE 8.1-1 Simplified HVAC and Gaseous Effluent Flow Diagram 8.2-1 Liquid Release Flowpath 8.4-1 Onsite Air Sampling Locations 8.4-2 Offsite Air Sampling Locations 8.4-3 Inner Ring and Outer Ring TLD Locations 8.4-4 Ingestion and Waterborne Exposure Pathway l

i Sample Locations O

O 8-111

BYRON REVISION llA MARCH 1986 8.0 RADIOACTIVE EFFLUENT TREATMENT SYSTEMS, O

MODELS FOR SETTING GASEOUS AND LIQUID EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, AND ENVIRONMENTAL RADIOLOGICAL MONITORING 1

8.1 GASEOUS RELEASES 8.1.1

System Design

8.1.1.1 Gaseous Radwaste Treatment System A gaseous radwaste treatment system shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off-gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

Refer to Figure 8.1-1 for a simplified system flowpath diagram.

8.1.1.2 ventilation Exhaust Treatment System A ventilation exhaust treatment system shall be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior.to the release to the environment (such a system is L

not considered to have any effect on noble gas effluents).

j Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components.

i 8.1.2 Alarm and Trip Setpoints r

l Alarm and trip setpoints of gaseous effluent monitors at

)

the principal points of release of ventilation exhaust air i

8.1-1

BYRON REVISION llA MARCH 1986 containing radioactivity are established to ensure that the release limits of 10 CFR 20 are not exceeded.

The set-points are found by solving Equations 2.6* and 2.7** for each class of releases.

For these equations, the radioactivity mixture in the exhaust l

air is assumed to have the composition of gases listed in Table 3.5-7 of the Environmental Report Operating License Stage.

According to Subsection 3.5.3.4 of the report, releases of radionuclides in gaseous effluents were calculated using the PWR-GALE computer program and the parameters listed in Table 3.5-5.

Equation 2.6* is rewritten using the fractional composition of each nuclide, ft, and a total release rate, O, f r station vent t

stack releases (the principal point of release of ventilation exhaust air containing radioactivity):

bQ Wi*f)

< 500 mrem /yr (8.1) 1.11 tv i

i f

Fractional Radionuclide Composition g

The release rate of radionuclide i divided by the total release rate of all radionuclides.

l Q

Total Release Rate, Vent Release (UCi/sec) tv The release rate for all radionuclides due to a station vent stack release.

Oiv " Otv i (8.2) f Equation 8.1 can be solved for O f r release limit tv determinations.

Similarly, Equation 2.7** can be rewritten:

g (X/0)y Q fi

• • P I-i R/3600 u ) +

tv y

1.11 V Q

f

< 3000 mrem /yr (8.3) 1 tv i

0-

• Equation 2.9 of Revision 2.

• • Equation 2.10 of Revision 2.

8.1-2

BYRON REVISION llA MARCH 1986 pO and a corresponding release Equation 8.3 can be solved for Otv limit can be determined.

The most conservative release limit from Equations 8.1 and 8.3 will be used in selecting the appropriate alarm and trip setpoints for a vent release.

The exact settings will be selected to ensure that 10 CFR 20 limits are not exceeded.

Surveillance frequencies for gaseous effluent monitors will be as stated in Table 4.3-9 of the Technical Specifications.

Calibration methods will be consistent with the definitions found in Section 1.0 of the Technical Specifications.

8.1.3 Station Vent Stack Monitors Detectors 1RE-PR028A, B, C, D, and E (particulate, low gas,

(_-

iodine, high gas, and background subtraction channels, respec-tively) and 2RE-PR028A, B, C, D, and E monitor station vent stack effluent from the auxiliary building vent stacks.

The particulate detector utilizes a beta scintillator and

-11

-5 has a range of 10 to 10 pCi/cc.

The low and high gas

-6 detectors utilize beta scintillators and have ranges of 10

-2

-2 2

to 10 pCi/cc and 10 to 10 pCi/cc, respectively.

The iodine detector utilizes a NaI(Tl) scintillator and has a range

-11 to 10-5 pCi/cc.

of 10 Both vent stack effluent monitors feature automatic isokinetic sampling, automatic gaseous composite grab sampling, and I

tritium sampling.

The monitor skids with associated pumps, detectors, and local controls are located in the auxiliary building on O-the 477-foot elevation.

8.1-3

--n-

BYRON REVISION llA MARCH 1986 O

Each monitor has a microprocessor (RM-80) which utilizes digital processing techniques to analyze data and control monitor functions.

Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on a CRT display (RM-ll) in the main control room.

A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and provides the high voltage for the detectors.

The power supply unit is located on the monitor skids.

The monitors are powered by local 120-vac instrumentation buses.

Alarm setpoint determination is addressed in Subsection 8.1.2.

The release limits (pCi/sec) obtained from Equations 8.1 and 8.3 are divided by the normal auxiliary building vent

)

stack flow rates (cc/sec) to obtain the pCi/cc alarm setpoint values.

Readouts for the vent stack monitors are in pCi/cc.

The cpm to pCi/cc conversion is accomplished by use of conversion factors in the radiation monitoring system software.

8.1.4 Containment Purge Effluent Monitors Detectors 1RE-PR001A, B, and C (particulate, gas, and iodine channels, respectively) and 2RE-PR001A, B, and C monitor containment purge effluent discharge to the auxiliary building vent stacks for Units 1 and 2, respectively.

The particulate detector utilizes a beta scintillator and

-11

-5 has a range of 10 to 10 pCi/cc.

The gas detector utilizes

-6

-2 a beta scintillator and has a range of 10 to 10 pCi/cc.

The iodine detector utilizes a NaI(Tl) scintillator and

-11

-5 has a range of 10 to 10 pCi/cc.

8.1-4

1 BYRON REVISION 11A MARCH 1986 The nionitor skids with associated pumps, detectors, and O

local controls are located in the auxiliary building on the 475-foot elevation.

Each monitor has a microprocessor (RM-80) which utilizes digital processing techniques to analyze data and control monitor functions.

Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on a CRT display (RM-ll) in the main control room.

A power supply unit furnishes the positive and negative voltages f or the circuits, relays, and alarm lights and provides the high voltage for the detectors.

The power supply unit is located on the monitor skids.

The monitors are powered by local 120-Vac instrumentation buses.

A containment atmosphere sample is obtained and analyzed

[)

prior to each containment purge release.

The isotopic analysis results of this sample are used to determine the maximum allowed containment purge flow rate.

This isotopic analysis or the containment atmosphere monitor 1(2)RE-PR0ll readings are utilized as the basis for determining the containment purge effluent monitor setpoints.

8.1.5 Gas Decay Tank Monitors t

l Detectors. ORE-PR002A and B (low range gas and high range gas, respectively) monitor the radiation level of the gas decay tank discharge to the auxiliary building vent stacks.

Detectors ORE-PR002A and B are interlocked with valve OGWRCV014.

Automatically, on a high radiation and/or instrument f ailure signal f rom the detectors, vent valve OGWRCV014 closes to i

isolate the gas decay tank discharge line.

8.1-5

l BYRON REVISION llA MARCH 1986

()

Both the low range and high range gas detectors utilize

-6

-2 beta scintillators and have ranges of 10 to 10 pCi/cc

-2 2

and'10 to 10 pCi/cc, respectively.

The monitor skid with associated pump, detectors, and local controls is located in the auxiliary building on the 346-foot elevation.

The monitor has a microprocessor (RM-80) which utilizes digital processing techniques to analyze data and control monitor functions.

Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on a CRT display (RM-ll) in the main control room.

A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and provides the high voltage for the detectors.

The power

)

supply unit is located on the monitor skid.

The monitor is powered by local 120-Vac instrumentation buses.

A grab sample from the gas decay tank to be released is obtained and analyzed prior to each gas decay tank discharge.

The isotopic analysis results of this sample are used to determine the maximum allowed gas decay tank discharge line flow rate and as a basis for determining the gas decay tank monitor interlock and high alarm setpoints.

8.1.6 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the auxiliary building, miscellaneous ventilation system, and the gas decay tanks are comprised of contributions from both units.

Under normal operating conditions, it is difficult to apportion the radioactivity between the units.

Consequently, allocation

()

will normally be made evenly between units.

8.1-6

1 BYRON REVISION llA MARCH 1986 U

8.1.7 Symbols Used in Section 8.1 1

SYMBOLS NAME UNIT Q

Total Release Rate, Vent Release (pCi/sec) tv V

Gamma Whole Body Dose Constant, g

Vent Release (mrad /yr per pCi/sec) f Fractional Radionuclide Composition f

3 L

Beta Skin Dose Constant (mrem /yr per pCi/m )

g (X/Q)y Relative Effluent Concentration, 3

Vent Release (sec/m )

A Radiological Decay Constant (hr-1)

O g

R Downwind Range (m) u Average Wind Speed, Vent Release (m/sec) y Q

Release Rate, Vent Release (pCi/sec) gy V

Gamma Dose Constant, Vent Release (mrad /yr per pCi/sec) g l

l 8.1-7 l

J 7

BYRON REVISION 11A I

MARCH 1986 1

8.1.8 Constants Used in Section 8.1 NUMERICAL VALUE NAME UNIT i

i-1.11 Conversion Constant (mrem / mrad) i I

3600 Conversion Constant (sec/hr)

I I

i i,

i i

,~

I i

4

)

i 1

a i

l T

8.1-8

REVISION llA MARCH 1986 Iv

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.bo w, g'e $p 3000 y

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bueida.g t.a. vents B fl 3 1000 peneeee i

g yg s,

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...is M 14 105g "

'* 8" a

M 4 250 R

e L.was,y F

P g

y BYRON STATION FIGURE 8.1-1 SIMPLIFIED HVAC AND GASEOUS EFFLUENT FLOW DIAGRAM 37asa (SHEET 10F 2) 04 279

REVISION 11 A MARCH 1986 4

4--

N 1.432 Gland steam 1.400 g y

condenser y

y H C C H ear et or Stack 1 Stack 2 1.400 p N

1.432 Gland steam e

condenser gr p

4 Steem let 32 eir elector p

2 Sche redoeste g

te$. n 3.100

/

Volume reduction H C C H 200 6 A Containment atmosphere radiation monitor C Charcoal f6fter F Refueling G Noble ses radiation monitor (offline)

H HEpA filter 4

M Three-channel radiation monitor for particulate, lodine, and noble gas (offline)

N Normel operation P Particulate monitor (offline)

R Hydrogen recombiner S Normel range stock radiation monitor (particulate, lodine, and noble gas)

W Wide range stock noble gas radiation monitor An sio. rates are cubic feet per minute BYRON STATION FIGURE 8.1-1 SIMPLIFIED HVAC AND GASE0US EFFLUENT FLOW DIAGRAM (SHEET 2 0F 2) ar2o.m on.ee-m

BYRON REVISION llA MARCH 1986 8.2 LICUID RELEASES 8.2.1

System Design

A liquid radwaste treatment system shall be a system designed and installed to reduce radioactive liquid effluents by collecting the liquids, providing for retention or holdup, and providing for treatment by demineralizer or a concentrator for the purpose of reducing the total radioactivity prior to release to the environment.

Refer to Figure 8.2-1 for a simplified system flowpath diagram.

8.2.2 Alarm Setpoints i

Alarm setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of 10 CFR 20 are not exceeded in the unrestricted area.

Prior to each batch release, a grab sample from the release tank is obtained and analyzed.

Equation 8.4 is evaluated for the radionuclide mix identified in the grab sample iso-l topic analysis results to determine the maximum allowable flow rate in the liquid radwaste discharge line.

d y

F,,,

=

+ K (8.4)

IMPC g l

F[ax Maximum Permissible Flow Rate, Radwaste Discharge (gpm)

The maximum flow rate permitted in the liquid radwaste discharge line that meets 10 CFR 20 limits.

O 8.2-1 i

__,.-._.,._____.,__..~,____,-__.____.-,.__,_._.,,....___,_.,._._..m

BYRON REVISION llA MARCH 1986 O

F Actual Flow Rate, Initial Dilution ct Stream (gpm)

The actual flow rate of the initial dilution stream which carries the radionuclides to the unrestricted area boundary.

i MPC Maximum Permissible Concentration 1

of Radionuclide i in the Unrestricted Area (10 CFR 20, Appendix B, Table II, Column 2)

(pCi/ml)

C Concentration of Radionuclide i g

in the Release Tank (pCi/ml)

O-K Conservatism Constant Determined by Station Procedures for Liquid Releases; K> 1.0.

Division by K allows station management to provide a margin of conservatism for liquid batch releases.

After determining F,,, from Equation 8.4, 10 CFR 20 compliance is verified using Equations 8.5 and 8.6.

ax (8.5)

C"i = Ci r

d p

,p max act C" =

Concentration of Radionuclide i

~

in the Unrestricted Area.

(pCi/ml) bC a

i

]

MPC 1

(8.6) g l

8.2-2 1

BYRON REVISION 11A MARCH 1986

'b

\\_/

The alarm setpoints for the liquid radwaste effluent monitor (ORE-PR001) are determined prior to each release and are based on the isotopic analysis results of the release tank grab sample.

The alarm setpoints are set so that any deviations from the i

isotopic analysis results will result in the automatic ter-mination of the release.

Readouts for the liquid effluent monitor are in pCi/ml.

The cpm to pCi/ml conversion is accom-plished by use of conversion factors in the radiation monitoring system software, j

8.2.3 Liquid Radwaste Ef fluent Monitor Radiation monitor ORE-PR001 monitors liquid radwaste ef fluent and is interlocked with release tank discharge valve OWX353.

On high radiation in the liquid radwaste effluent, the release tank discharge valve is closed automatically.

(

Each release tank (OWXOlT and OWX26T) holds 30,000 gallons.

Both are located in the turbine building on the 401-foot elevation.

The monitor utilizes a NaI(Tl) detector with a range for

-8

-2 gamma radiation of 10 pCi/ml to 10 pCi/ml.

The monitor skid and associated features are located in the turbine building on the 401-foot elevation.

The monitor has a microprocessor (RM-80) which utilizes l

digital processing techniques to analyze data and control

]

monitor functions.

Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on a CRT display (RM-11) in the main control room.

O 8.2-3

REVISION llA BYRON MARCH 1986 A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and provides the high voltage for the detector.

The power supply is located on the monitor skid.

The monitor is powered from local 120-Vac instrumentation buses.

A discussion of alarm setpoints for ORE-PR001 is incl'uded

~

in Subsection 8.2.2.

8.2.4 Station Blowdown Monitor Radiation monitor ORE-PRO 10 continuously mo'nitors the circulating water blowdown for radioactivity.

The monitor utilizes a

~0 NaI (Tl) detector with a range for gamma radiation of 10 pCi/ml

-2 to 10 Ci/ml.

The monitor skid and associated features are located in the turbine building on the 364-foot elevation.

I p km The monitor has a microprocessor (RM-80) which utilizes digital processing techniques to analyze data and control monitor functions.

Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on a CRT display (RM-ll) in the main control room.

A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and provides high voltage for the detector.

The-power supply is located on the monitor skid.

The monitor is powered from local 120-Vac instrumentation buses.

The alarm setpoints for the station blowdown monitor are determined prior to each release and are based on the isotopic analysis results of the release tank grab sample and the

("*)

actual dilution flow rates.

The alarm setpoints are set so V

8.2-4 4

BYRON REVISION llA MARCH 1986 O

\\s /

that unexpected deviations from the isotopic analysis results l

or f rom the specified dilution flow rate will result in an alarm from the monitor.

Between batch releases, the station blowdown monitor alert and high alarm setpoints are established at levels specified by station procedures.

l 8.2.5 Reactor Containment Pan Cooler (RCFC) and Essential Service Water Outlet Line Monitors Radiation monitors 1RE-PR002, 2RE-PR002,1RE-PR003, and 2RE-PR003 monitor the RCFC and essential service water out-let lines for radioactivity.

The monitor utilizes a NaI(Tl)

-8 detector with a range for gamma radiation of 10 pCi/ml

-2 to 10 pCi/ml.

The monitor skid and associated features are located in the auxiliary building on the 402-foot eleva-tion.

The monitor has a microprocessor (RM-80) which utilizes digital processing techniques to analyze data and control monitor functions.

Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on a CRT display (RM-11) in the main control room.

A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and provides high voltage for the detector.

The power supply is located on the monitor skid.

The monitor is powered from local 120-Vac instrumentation buses.

Unit I radiation monitor high alarm setpoints are based on detector response to a mix of several radionuclides -

those listed on Table 11.2-4 of FSAR which are capable of O

8.2-5

BYRON REVISION llA MARCH 1986 O

being detected by the monitor's sodium iodine detector.

Each nuclide in the mix is at a concentration which is 10%

of the MPC value given in 10 CFR 20 Appendix B Table 2, Column 2.

Each monitor alert alarm setpoint is set at 50%

of the high alarm setpoint.

During Unit 2 start-up, alert and high alarms are set at twice the observed background.

8. 2.6 Administrative and Procedural Controls for Radwaste Discharges Administrative and procedural controls have been designed to ensure proper control of radioactive liquid radwaste discharge in order to preclude a release in excess of 10 CFR 20 limits.

The discharge rate for each batch is calcu-lated by radiation chemistry personnel (Equation 8.4) and then provided to operating staff personnel.

All liquid radwaste discharges will be from either release tank OWX0lT

)

or release tank OWX26T.

On high radiation in the liquid radwaste effluent, the release tank discharge valve 0WX353 is closed automatically.

The proper valve lineup is performed by the operator prior The actual to each batch discharge, per station procedures.

discharge is authorized by the shift engineer.

The ef fluent monitoring instrumentation system is equipped with alarm / trip setpoints which, if exceeded, initiate auto-matic valve closure on the release tank discharge line.

This system is used to prevent exceeding 10 CFR 20 liquid release limits.

Determination of Initial Dilution S tream Flow Rates 8. 2.7

()

For those release paths which have installed flow monitoring instrumentation, that instrumentation will be used to deter-This mine the flow rate of the initial dilution stream.

8.2-6

BYRON REVISION 11A MARCH 1986 O

instrumentation will be operated and maintained as prescribed by the Technical Specifications.

For those release paths which do not have installed flow monitoring instrumentation, flow rates will be determined by use of appropriate engineering data such as ramp curves, differential pressures, or valve position indication.

8. 2.8 Allocation of Ef fluents f rom Common Release Points Radioactive liquid effluents released from either release tank (OWXOlT or OWX26T) are comprised of contributions from l

both units.

Under normal operating conditions, it is difficult to apportion the radioactivity between the units.

Conse-quently, allocation will normally be made evenly between units.

8. 2.9 Symbols Used In Section 8.2 v

SYMBOL NAME UNIT C

Concentration of Radionuclide 1 (pCi/ml) a in the Unrestricted Area C

Concentration of Radionuclide 1 (pCi/ml) g in the Release Tank MPC.

Maximum Permissible (pC i/ml) f Concentration of Radionuclide i in the Unrestricted Area F

Maximum Permissible Flow (gpm)

Rate, Radwaste Discharge Ffet Actual Flow Rate, (gpm)

Initial Dilution Stream 8.2-7

b:

BYRON REVISION 11A MARCH 1986 2

K Conservatism Constant Determined by Station l

1

)

Procedures for Liquid Releases; i.

l K.> 1.0 I

I i

l 4

l 4

1 1

j i

)

i i

i I

l l

l i~

i i

1 2

i i G 8.2-8 h

.. = -..=

REVISION 11A 1RE PX002 ItARCH 19E6 Unit 1 RCFC A & C

r O

Sa System 1RE PR003 Unit 1 RCFC B & D r

$s System 2AE-PR002 Unit 2 RCFC A & C

r Su System 2RE-PR003 Unit 2 RCFCB&D Su System O

Release tank OWXOIT ORE PR001 (Flowrate Determined By Station Prior to Each Release)

)

Station Slowdown *

(Flowtato Measured By Relesw M Station Prior to Each Release)

OWX26T

)

OPE PR010 L tr Rock River L

Liquid Process Radiation Monitor BY RON ST ATION RCFC - Reactor Containment Fan Cooler FIGURE 8.2-1 r

LIQUID RELEASE FLOWPATH 3720 04 2,79

BYRON REVISION llA MARCH 1986

()

8.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM The process control program (PCP) shall contain the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is ensured.

r r

O f

I I

O 8.3-1

BYRON REVISION llA MARCH 1986

O 8.4 ENVIRONMENTAL RADIOLOGICAL MONITORING The environmental radiological monitoring program for the environs around Byron Station is given in Table 8.4-1.

Reporting levels and lower limits of detection for this program are given in Tables 8.4-2 and 8.4-3, respectively.

Figures 8.4-1, 8.4-2, 8.4-3, and 8.4-4 show sampling and l

monitoring locations.

O 1

o 8.4-1 i

4 s

O TABLE 8.4-1 ENVIROletENTAL RADIOLOGICAL MONITORINC PROGRAN*

~

EXPOSURE PATHWAY SAMPLING OR TYPE AND FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORINC IDCATIONS COLLECTION FREQUENCY OF ANALYSIS

1. Direct Radiation Indicatore Quarterly Casuna dose quarterly

a. Inner Ring 101-1, 1.2 mi NNE 101-2, 1.2 mi NME 102-1, 1.0 mi NME 102-2, 1.0 mi NME 103-1, 1.7 mi NE 103-2, 1.6 mi NE 104-1, 1.4 mi ENE 104-2, 1.4 mi ENE 105-1, 1.3 mi E 4

105-2, 1.3 mi E 106-1, 1.4 mi ESE 106-2, 1.4 mi ESE 107-1, 1.4 mi SE 107-2, 1.4 mi SE 108-1, 0.6 mi SSE 108-2, 0.6 mi SSE 109-1, 0.6 mi S w

109-2, 0.6 mi S o

Z

!!0-1, 0.6 mi SSW 110-2, 0.6 mi SSW I

111-1, 0.9 mi SW 7

!!!-2, 0.8 mi SW N

112-1, 0.8 mi WSW

!!2-2, 0.7 mi WSW

!!3-1, 0.7 mi W 113-2, 0.7 mi W 114-1, 0.8 mi WNW 114-2, 0.8 mi WNW 115-1, 1.0 mi NW l

115-2, 1.0 mi NW 116-1, 1.4 mi NNW 116-2, 1.4 mi NNW

b. Outer Ring 201-1, 4.8 mi N 201-2, 5.2 mi N 202-1, 4.5 mi NME 202-2, 5.2 mi NME

$w 203-1, 5.1 mi NE 203-2, 5.1 mi NE 2$

HO 204-1, 4.2 mi ENE 204-2, 4.1 mi ENE m

205-1, 3.9 mi E

• [

205-2, 4.1 mi E

j

g L

J TABLE 8.4-1 (Cont'd)

EXPOSURE PATWAY SAMPLING OR TYPE AND PREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING EDCATIONS COLLECTION FREQUENCY OF ANALYSTS I'. Direct Radiation (Cont'd)

Indicators (Cont'd)

b. Outer Ring (Cont'd) 206-1, 4.2 mi ESE 206-2, 4.3 mi SE 207-1, 4.2 mi SE 207-2, 3.7 mi SE 208-1, 4.1 mi SSE 208-2, 3.8 mi SSE 209-1, 3.8 mi S 209-2, 3.9 mi SSW 210-1, 3.6 mi SSW 210-2, 3.6 mi SW 211-1, 5.2 mi SW 211-2, 4.8 mi WSW 212-1, 4.9 mi WSW 212-2, 5.1 mi W 213-1, 5.0 mi W 213-2, 5.2 mi WW 214-1, 4.8 mi WW 214-2, 5.2 mi W 215-1, 5.4 mi NW 215-2, 5.2 mi W 216-1, 4.8 mi NW 216-2, 5.1 mi NNW 5u

c. Special Interest m

• s e

At each of the airborne pathway indicator locations specified in Part 2 of this table.

Controls At each of the airborne pathway control locations specified in Part 2 of this table.

2. Air'oorne Radioiodine and Indicators Continuous sampler operation Radiciodine Canisters Particulates

a. Near Site Boundary with sample collection 1-131 analysis weekly.

l BY-21, North Parking Lot, 0.27 mi N weekly, or more frequently BY-22, CECO Property. 0.30 mi E if required by dust loading.

Particulate Samplert l

BY-23, South of Plant on Deerpath Road,

s. Cross beta radioactivity gg 0.59 mi S analysis folloging

o <

BY-24, Met Tower, 0.66 mi'SW filter change.

Q"

b. Near Community with Highest Calculated

b. Canuna isotopic analysis

$O Annual Average Ground Level D/Q of composite (by "g

BY-1, Byron, 3.5 mi NNE location) quarterly.

w

c. Sr-89, 90 analysis of composite (by location) quarterly.

D,

%.)}

q,)

TABLE 8.4-1 (Cont'd)

SAMPLINC OR TYPE AND FREQUENCY EXPOSURE PATHWAY AND/OR SAMPLE SAMPLING OR MONI1DRINC IDCATIONS COLLECTION FREQUENCY OF ANALYSIS 2.

Airborne (Cont'd)

Indicators (Cont'd)

c. Other BY-2, Stillman Valley, 6.2 mi NE BY-3, Nearsite - East, 3.8 mi E BY-4, Paynes Pt., 4.5 mi SE BY-5, Nearsite - South, 3.6 mi S BY-6, Oregon, 4.6 mi SSW Controle BY-7, Mt. Morris, 7.8 mi WSW BY-8, Leaf River, 7.0 mi NW

3. Waterborne

a. Surface Indicators Weekly Crossbetaanalysisweegly.

BY-9, Woodland Creek, 2.3 mi W camma isotopic analysis BY-12, Oregon Pool of Rock River, monthly. Composite for Downstream of Discharge, 4.5 mi SSW tritium and Sr-89, 90 analysis quarterly.

to Controls BY-13. Rock River, Upstream of Intake, y

.y O

2.6 mi WNW z

b. Cooling Water Indicators Weekly Cross beta analysis weekly.

BY-!!, Byrnn Discharge Pipe / River, at Station composite for gassna isotopic, tritium and Sr-89, 90 analysis monthly.

Controle BY-10, Byron Intake Pipe / River, at Station

c. Cround Indicatore Quarterly Canuma isotopic", tritium, BY-18, McCoy Farmstead, 1.25 mi SW gross beta and Sr-89, 90 analysis quarterly.

I Controls l

BY-14, CECO Property, 0.3 mi E gW

d. Sediment from Shoreline Indicatore Yhree times a year Cansna isotopig and gross yQ BY-12, Oregon Pool of Rock River, beta analysis three times ow

• U Downstream of Discharge, 4.5 mi SSW a year.

NO WZ to Controls w

BY-13, Rock River. Upstream of intake, 2.6 mi WNW

-.~

i bv TABLE 8.4-1 (Cont'd)

EXPOSURE PAYHWAY SANPLING OR YYPE AND FREQUENCY AND/OR SANPLE SAMktING OR MONITORINC IACATIONS COLLECTION FREQUENCY OF ANALYSIS

3. Waterborne (Cont'd)

e. Precipitation BY-15, J. A. Reeverts Fine Hill Dairy, Monthly Cross beta analysis monthly.,

3.2 mi ESE Composite for gasmas isotopic,

BY-16, Kenneth Durien Farm, 7.0 mi SE tritium and Sr-89, 90 analysis BY-17, Bosecker/Lingel Farm, 7.0 mi NE quarterly.

BY-20 Ed Seabold Farm, 2.5 mi NE i

f. Aquatic Plants Indicators 1hree times a year Cross beta and gammaa isotopic

• BY-12, Oregon Pool of Rock River, analysis three times a

{

Downstream of Discharge, 4.5 mi SSW year Controle BY-13, Rock River, Upstream of Intake.

2.6 ml WNW

4. Ingestion l

a. Milk Indicatore BY-15, J. A. Reeverts Pine Hill Dairy, Biweekly when animals are Caumsa isotopic *, 1-131 and 3.2 mi ESE on pasture, monthly at other Sr-89, 90 analysis biweekly on BY-16, Kenneth Durien Farm, 7.0 mi SE times.

when animals are on pasture, g

BY-20 Ed Seabold Farm, 2.5 mi NE monthly at other times.

z e*

Controls BY-17, Bosecker/Lingel Farm, 7.0 mi NE

b. Fish and Invertebrates Indicators 1hree times per year (spring, Camma isotopic", gross beta Representative samples of BY-12, Oregon Pool of Rock River, susumer, and fall).

and Sr-89, 90 analysis on comunercially and Downstream of Discharge, 4.5 mi SSW edible portions.

recreationally important species.

Controls i

BY-13, Rock River, I?pstream of Intake, l

2.6 mi WNW i

c. Vegetables Indicators Annually Cross beta, gaanna isotopic

• BY-19-1, Orestin Vegetable Stand, 7.5 mi SSW and Sr-89, 90 analysis BY-19-2, Oregon Vegetable Stand, 7.5 mi SSW annually. 1-131 analysis gM on leafy vegetables annually.

wE i

os e

mm l

d. Cattle Feed and Crass Indicatore Quarterly Cross beta, gesuma isotopic and g

BY-15, J. A. Reeverto Pine Hill Dairy, Sr-89, 90 analysis quarterly.

wz 3.2 mi ESE

%g BY-16, Kenneth Durien Farm, 7.0 mi SE w

BY-20, Ed Sasbold Farm, 2.5 mi NE Controls BY-17, Bosecker/Lingel Dairy Farm. 7.0 mi SE

M...

\\

a TABI.E A.4-1 (Cont'd)

Isotes:

' Deviations are permitted from the required esepling schedule if speeleens are unobtainable due to hasardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasona. If specimeno are unobtainable due to esepling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the nest sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report. It le recognized that, at times, it may not be possible or practicable to continue to obtain samples of the ordia of choice at the most desired location or time. In these instances suitable alternative media and locatione may be chosen for the particular pathway in question and appropriate substitutione made within 30 days in the radiological environmental sonitoring program. 1he cause of the unavailability of samples for that pathway and the new locationf o) for obtaining replacement samplea shall be identified in a Special Report to the lhselear Regulatory Coussission within 30 days. The report shall also include a revised figure (s) and table for the ODCM reflecting the new location (s).

bAirborne particulate sample filtere shall be analysed for arosa beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more af ter sampling to allow for redon and thoron i

daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, sanos isoteric analyele shall be performed on the individual samples.

'Casume isotopic analysis means the identification and quantification of' aseena-emitting radionuclides that may he attributable to the effluents from the facility.

I i

to O*:

am 9

on E i'l n5

R

I

~

O O

O TABLE 8.4-2 REPORTING LEVELS FOR RADIOACTIVITY CONCEfffRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS FISH MILK FOOD PRODUCTS AIRBORNE PARTICUlp)TE WATER OR CASES (pCi/m (pCi/kg, wet)

(pCi/E)

(pCi/kg, wet)

ANALYSIS (pCi/E)

H-3 20,000*

Mn-54 1,000 30,000 Fe-59 400 10,000 co-58 1,000 30,000 M

Co-60 300 10,000 Z

i ao Zn-65 300 20,000 8

Zr-Nb-95 400 1-131 2

0.9 3

100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 NN

• For drinking water samples. This is 40 CFR Part 141 value.

If no drinking water pathway exists,

$d l

a value of 30,000 pCi/ E may be used.

mg eO 1

l O

O

/~T U

V TABLE 8.4-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS *'

l LOWER LIMIT OF DETECTION (LLD)

FISH MILK FOOD PRODUCTS SEDIMElfr AIRBORNE PARTIy) TE WATER OR CAS (pCi/m (pCi/kg, wet)

(pCi/E)

(pCi/kg, wet)

(pCi/kg, dry)

ANALYSIS (pCi/E)

Cross Beta 4

0.01 H-3 2000*

i Mn-54 15 130 Fe-59 30 260 to Co-58,60 15 130 y

o m

Z Zn-65 30 26 0 l

Zr-Nb-95 15 d

I-131 I

0.07 1

60 l

Cs-134 15 0.05 130 15 60 150 J

CS-137 18 0.06 150 18 80 180 Ba-La-140 15 15 NN tn <

'e m

• If no drinking water pathway exists, a value of 3000 pCi/E may be used.

NO P

4

BYRON REVISION llA MARCH 1986 TABLE 8.4-3 (Cont'd)

• This list does not mean that only these nuclides are to be considered.

Other peaks that are identifiable, together with those of the above nuclides, l

shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.

b Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

1 The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4.66 s b

~

E

• V + 2.22 + Y + exp (- Alt) where:

LLD = the "a priori" lower limit of detection (picoCuries per unit I

mass or volume),

\\_/

s the standard deviation of the background counting rate or of s

=

b the counting rate of a blank sample as appropriate (counts per minute),

E

= the counting efficiency (counts per disintegration),

V

= the sample size (units of mass or volume),

2.22 = the number of disintegrations per minute per picocurie, Y

= the fractional radiochemical yield, when applicable, A

= the rgdioactive decay constant for the particular radionuclide, (sec

), and At

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

Typical values of E, V, Y, and At should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system j

and not as an a posteriori (after the fact) limit for a particular l

measurement. Analyses shall be performed in such a manner that the j

stated LLDs will be achieved under routine condit. ions. Occasionally 8.4-9

BYRON l

REVISION llA MARCH 1986 TABLE 8.4-3 (Cont 'd)

O background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.

In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental l

Operating Report.

d LLD for drinking water samples.

If no drinking water pathway exists, an LLD of 60 pCi/t may be used.

4 0

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===== EXCLUSION AREA BOUNDARY

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REVISION llA MARCH 1986 O

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FIGURE 8.4-4 INGESTION AND WATERBORNE EXPOSURE PATHWAY SAMPLE LOCATIONS

-- -