ML20205A087

Revs to Odcm,Including Rev 2.0 to Chapter 10, Radioactive Effluent Treatment & Monitoring & Rev 1.9 to Chapter 12, Radiological Effluent Technical Stds (Rets)

ML20205A087
Person / Time
Site:	Dresden
Issue date:	03/22/1999
From:	COMMONWEALTH EDISON CO.
To:
References
PROC-990322, NUDOCS 9903300290
Download: ML20205A087 (90)

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'7, Document Control Desk V' Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Station PI-137 Washington DC 20555 March 22,1999 Attached is n revision to the Offsite Dose Calculation Manual, Dresden Annex, Chaoter 10 cad Chapter i2. Please Lpdate your manual as follows:

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Remove: Insert:

Dresden, Chapter 10, Revision 1.9 Dresden, Chapter 10, Revision 2.0 ,

Dresden, Chapter 12, Revision 18 Dresden, Chapter 12, Revision 1.9 Please sign below indicating your manual has been updated and that your controlled copy number is correct.

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Name Date Return to:

Comed Procedures Clerk 1400 Opus Place,4th Floor Downers Grove, IL 60515

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-or- f'/

Procedures Clerk 4th Floor ETW lli ef Ih]

,O 9903300290 990322 ADOCK 05000010 V PDR P PDR __

290073

e Dresden Station

(~N Chapter 10 Change Summary V, ODCM Revision 2.0, March 1999 Page Change Description 10-i Updated revision number.

10-7 In section 10.2.1.3 changed wording to reflect the fact that the Floor Drain Sample Tanks can be directly discharged into discharge canal.

In section 10.2.2.1 changed the wording from "The monitor is used to monitor all releases..." to "The monitor is used to monitor releases...".

Monitor operability requirements are given in ODCM Table 12.2-1, and there are allowances for discharges without a monitor c,perable.

In section 10.2.2.1 added wording about the other possible discharge pathways which could be monitored by liquid radwaste effluent monitor ,

prior to being discharged into the discharge canal.

10-13 Revised Figure 10-3 to show the presence of" portable waste treatment systems". Portable treatment systems have the flexibility to connect at various locations in the radwaste system for discharge to the river.

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DRESDEN RLvision 2.0 Mirch 1999 DRESDEN ANNEXINDEX O CHAPTER 10 REVISION 2.0 a

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r DRESDEN-Revision 2.0 March 1999 CHAPTER 10

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RADIOACTIVE EFFLtJENT TREATMENT AND MONITORING TABLE OF CONTENTS E6AQg 10.1 AIRBORNE RELEASES, .. .. . ... . . . . . . . . . . . . . .. . 10-1

1. System Description. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .10-1 1.- Condenser Offgas Treatment System.. . . . . . . . . . . . . . . .... . . . 10-1

2. Ventilation Exhaust Treatment System. . . . . . . . . . . . . .. . . 10-1

2. Radiation Monitors.. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. .. 10-2

1. Unit 1 Chimney Monitor.. . . . . . . . . . . . . . . . . . . . ...... . .. . .... .... 10-2

2. Units 2/3 Chimney Monitor.. ... . . ... .. . . .. . ... . . . . . . . . . . . . . ....... 10-2

3. Reactor Building Vent Stack Emuent Monitors.. ... . . . .. . . . . .... . .. . . .... 10-2 I

4. Reactor Building Ventilation Monitors . . . . . . ..- . . . . .. . . . . 3

5. Condenser Air Ejector Monitors. . . . . .. . . . . . . . . . . . . . . .... 10-3

d. Isolation Condenser Vent Monitor.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . 40-3

3. Alarm and Trip Setpoints... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. ....... . . .. 10-3

1. Setpoint Calculations... ...............................................10-3 1.' I,eactor Building Vent Monitors..... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . ... .. 10-3

2. Condenser Air Ejector Monitors . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . .. 10-3

3. Units 2/3 Plant Chimney Radiation Monitor... ......

p . . . . . . . . . . . . ..... . 10 3

2. Release Limits.'. . .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 10 4 3.

Release Mixture . . . .... . . . . .. . .. .. ..... . .. . ... .. .... .. .... . . ... .... . . . . . . . ... 10-6  ;

4. Conversion F tors.... .. ... ............................................... 1066 ;

5. HVAC Flow hates. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... 10 6 l

4. Allocation of Effluents from Common Release Points.. ...........................10-6

5. Dose Projections.. . .. . . . . . . . . . . . . . . .. . . .. ... . . . . 10-6 1

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I DRESDEN Revision 2.0 March 1999 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS (Cont'd)

.PA.G.E 10.2 LIQUID RELEASE . ... 10-6

1. System Description. . ... . . 10-6

1. Unit 1 Storage Tanks . .. . . 10-6

2. Units 2/3 Waste Sample Tanks... . . 10-6

3. Units 2/3 Floor Drain Sample Tanks. . . .. 10-7

4. Units 2/3 Waste Surge Tank. . . . . . . . . 10-7

2. Radiation Monitors. . . . . . . . . 10-7

1. Liquid Radwaste Effluent Monitor.. . . . *10-7

2. Units 2 & 3 Servico Water Effluent Monitors. . . . .. 10-7

3. Chemical Cleaning Facility Service -a Water Effluent Monitor.. . . .. .. .. .. .. . 10-7

3. Alarm and Trip Setpoints.. . . . . . . . . . . . 10-8

1. Setpoint Calculations.. . . .. . . . . . .. . 10-8

1. Liquid Radwaste Effluent Monitor... . . .... ... . . 10-8

2. Units 2 & 3 Service Water Effluent Monitor.. . .. ... . . . . . 10 9

3. Chemical Cleaning Facility Service Water Effluent Monitor. .. 10-9

2. Discharge Flow Rates... . . ... .. . . . . . . . . . . . . . . . . 10-9

1. Release Tank Discharge Flow Rate.. . .. . . . . . . . . . . . .... .. 10-9

3. Release Limits.. ... . . .. . . . . . 10-10

4. Release Mixture . . ... .. . .. . . .. . 10-10

5. Conversion Factors.. . . 10-10

6. Liquid Dilution Flow Rates.. . . .. . 10-10

4. Allocation of Effluents from Common Release Points.. . . . .. . . 10-10

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5. Projected Doses for Releases . . . . . . . . . 10-10 10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM . . . . 10-10 g:W10ri-9 doc e

10-lii L____________________

DRESDEN Revtion 2.0 March 1999 I

CHAPTER 10 LIST OF FIGURES NUMBER PAgg 10-1 Simphfied Gaseous Radwaste and Gaseous Emuent Flow Diagram 10-11 10-2 Simphfied Gaseous Radwaste and Gaseous Effluent Flow Diagram 10-12 i 10-3 Simplified Liquid Radwaste Processing and Liquid Emuent Flow Diagram 10-13 10-4 Simplified Solid Radwaste Processing Diagram 10-14

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DRESDEN Revnion 2.0 March 1999 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1 System Desenption

' A simplified gaseous radwaste and gaseous effluent flow diagram is provided for Dresden Unit 1 in Figure 10-1 and for Dresden Units 2 and 3 in Figure 10-2. Dresden 1 is no longer operational, but monitoring of potentially radioactive releases from the plant chimney continues Each airbome release point is classified as stack, vent, or ground level in accordance with the definitions in Section 4.1.4 and the results in Table A-1 of Appendix A. The principal relean points for potentially radioactive airbome effluents and their classifications are as follows: -

For Dresden 1, the plant chimney (a stack release point). -a For Dresden 2/3:

The ventilation chimney (a stack release point).

The reactor building ventilation stack (a vent release point).

10.1.1.1 Condenser Offgas Treatment System f The condenser offgas treatment system is designed and installed to reduce radioactive

. gaseous effluents by collecting non-condensable off-gases from the condenser and providing for holdup to reduce the total radioactivity by radiodecay prior to release to the environment. The daughter products are retained by charcoal and HEPA filters. The system is described in Section 11.3 of the Dresden UFSAR.

10.1.1.2 Ventilation Exhaust Treatment System I Ventilation exhaust treatment systems are designed and installed to reduce gaseous radioiodine or radioactive materialin particulate form in selected effluent streams by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters prior to release to the environment. Such a system is not considered to have any effect on noble  ;

gas effluents. The ventilation exhau'st treatment systems are shown in Figures 10-1 and i 10 2.

Engineered safety features atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components.

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c DRESDEN Revtion 2.0 q March 1999

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10.1.2 Radiation Monitors 10.1.2.1 Uret 1 Chimney Monitor The SPING continuously monitors the final effluent from the Unit 1 chimney.

The monitor has isokinetic sampling, gaseous grab sampling, and particulate and iodine sampling capability. Tritium samples are obtained using a portable sampling system. A tap is available for obtaining a sample from the isokinetic probe.

In normal operation all three noble gas channels (low, mid-range, high) are on line and active.

No automatic isolation or control functions are performed by this monitor.

10.1.2.2 Units 2/3 Chimney Monitor The SPING continuously monitors the final effluent from the Units 2/3 chimney.

The monitor has isokinetic sampling, gaseous grab samplitig, particulate and iodine sampling, and postaccident sampling capability. Tritium samples are obtained using a portable sampling system. A tap is available for obtaining a sample from the isokinetic probe.

In normal operation the two lower noble gas channels (low and mid-range) are on line and active. The high range noble gas channel flow is bypassed and this channel is in standby.

At a predetermined threshold the low and mid-range noble gas channels are bypassed and only the high range noble gas channel remains active.

No automatic isolation or control functions are performed by this monitor. Pertinent information on this monitor is provided in the Dresden UFSAR Section 11.5.

In addition to the pnmary monitor described above, there is a backup system consisting of two additional detectors and sample taps in series in the primary sample stream.

10.1.2.3 Reactor Building Vent Stack Eftluent Monitors The SPING continuously monitors the final effluent from the reactor building vent stack.

The vent stack monitor has isokinetic sampling, gaseous sampling, and iodine and particulate sampling capability. Tritium samples are obtained using a portable sampling system. A tap is available for obtaining a sample from the isokinetic probe.

All channels are continuously on line and active.

No automatic isolation or control functions are y,arformed by ..., monito/

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DRESDEN Reveon 2.0 March 1999 10.1.2.4 Reactor Building Ventilation Monitors The monitor (located in the ventilation exhaust duct) monitors the effluent from the Unit 2(3) reactor building ventilation. On high alarm, the monitors automatically Mitiate isolation of the Unit 2(3) reactor building ventilation, and initiate startup of the Unit 2/3 standby gas treatment system.

Pertinent information on these monitors is provided in Dresden UFSAR Section 11.5.

10.1.2.5 Condenser Air Ejector Monitors The monitors continuously monitor gross gamma activity downstream of the Unit 2 and 3 steam jet air ejector and prior to release to the main chimney.

At the trip setpoint the moniters automatically activate an interval timer which in tum initiates closure of an air operated valve, thus terminating the release.

Perbnent information on there monitors is found in Dresden UFSAR Section 11.5.

10.1.2.6 Isolabon Condenser Vent Monitor

• The monitor continuously monitors radioactivity in the effluent from the isolation condenser vent. No control device is initiatea by this monitor.

Pertment information on this monitor is provided in Dresden UFSAR Section 11.5.

10.1.3 Alarm and Trip Setpoints 10.1.3.1 Setpoint Calculations 10.1.3.1.1 Reactor Building Vent Monitors The alarm setpoint for the reactor building vent monitor is established at 10 mr/hr.

10.1.3.1.2 Condenser Air Ejector Monitors The high-high trip setpoint is established at s 100 pCi/Sec per MWt (a2.5E5pC1/sec) and the high alarm is established at 5 50pCi/sec per MWt (a1.25E5pCi/sec).

10.1.3.1.3 Units 2/3 Plant Chimney Radiation Monitor The setpoint is established at a count rate corresponding to no gmater than 105,000 pCl/sec.

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DRESDEN Revision 2.0 March 1999 10.1.3.2 Release Limits Alarm and trip setpoints of gaseous effluent monitors are established to ensure that the release rate limits of RETS are not exceeded. The release limits are found by solving Equations 10-1 and 10-2 for the total allowed release rate, Q,.

(1.11)I( ffQ,S, + Q,V,]} < 500 mrem /yr (10-1)

I (ii.,f,[(X/Q), Q, exp(-A,R/3600u,)

• (X/Q),Omexp-(1,R/3600u,)] (10-2)

+(1.11)(f)[Q,S, + Q,VJ}

< 3000 mrem /yr a

The summations are over noble gas radionuclides i.

f, Fractional Radionuclide Composition The release rate of noble gas radionuclide i divided by the total release rate of all.

noble gas radionuclides.

Q. Total allowed Release Rate, Stack Release [ Ci/sec]

The total allowed release rate of all noble gas radionuclides released as stack releases.

Q. Total Allowed Release Rate, Vent Release ( Ci/sec]

The total allowed release rate of all noble gas radionuclides released as vent releases.

Refer to Section A.1 of Appendix A for the definitions of the remaining parameters.

Equation 10-1 is based on Equation A-8 of Appendix A and the RETS restriction on whole body dose rate (500 mrem /yr) due to noble gases releas d in gaseous effluents (see Section A.1.3.1 of Appendix A). Equation 10-2 is bass' an Equation A-9 of Appendix A and the RETS restriction on skin dose rate (3000 mrem /yr; sue to noble gases released in gaseous effluents (see Section A.1.3.2 of Appendix A).

Calibration methods and surveillance frequency for the monitors will be conducted as specified in the RETS.

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DRESDEN Revision 2.0 March 1999 10.1.3.3 Release Mixture b

47 In the determination of alarm and trip setpoints the radioactivity mixture in the exhaust air is assumed to have the following compositions, f

1

~' Reactor building vent effluent monitors.

The mixture used for the GE monitors is taken from a representative isotopic analysis i of tne vent stack noble gas released since the last calibration, or based on nominal response of detector. The " mixture" used for the SPING is assumed to be a single pseudo-noble gas radionuclide.

Condenser air ejector monitor.

The mixture used for this monitor is taken from a representative isotopic analysis of noble gases collected at the recombiner outlet during olar*t operation, since the last alarm setpoint calcubtion.

Units 2/3 plant chimney monitors.

• The mixture used for the GE monitors is taken from the most recent isotopic analysis of noble gases collected from the chimney monitor which corresponds to an above ~-

background recorder reading. The " mixture" used for the SP!NG is assumed to be a single pseudo-noble gas radionuclide.

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10.1.3.4 Conversion Factors The conversion factors used to establish gaseous effluent monitor setpoints are obtained as w follows.

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i Reactor building vent effluent monitor.  !

Foc t:0 GE monitors, the isotopic analysis in Section 10.1.3.3 and the monitor reading (in mR/hr) at the time of the analysis or nominal response of detector are used to establish the conversion factor in mR/hr per pCi/cc or pCi/ft8 . For the SPING the conversion factor is based on the 0.8 MeV gamma of the pseudo-noble gas radionuclide.

Condenser air ejector monitor.

The isotopic analysis in Section 10.1.3.3 and the flow and monitor reading (in mR/hr) at the time of the analysis are used to establish the conversion factor in mR/hr per pCi/cc or pCi/ft3.

Units 2/3 plant chimney monitors For the GE monitors, the isotopic analysis in Section 10.1.3.3 and flow and monitor reading (in CPS) at the time of the analysis are used to establish the conversion factorin CPS per Ci/cc or pCi/ft*. For the SPING the conversion factor is based on the 0.8 MeV gamma of the pseudo-noble gas radionuclide.

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l DRESDEN Revtion 2.0 Mrrch 1999 l l

10.1.3.5 HVAC Flow Rates The HVAC exhaust flow rates are obtained from either the Units 2/3 process computers or the SPING control station. For the 2/3 Chimney, additional process flow rates must be added to obtain the total chimney flow (see Figure 10-2). Unit operation may affect actual flow rates which therefore may differ from values listed. If the actual flows are not available, the following default values based on design flow can be used:

Units 2/3 Chimney Air Flow 1.25E10 cc/ min Units 2/3 Combined Reactor Vent 6.23E9 cc/ min Unit 1 Chimney Air Flow 1.76E9 cc/ min 10.1.4 Allocation of Effluents from Common Release Points ]

i Radioactive gases, particulates, and iodines released from the Unit 1 chimney originate from Unit i only. However, radioactive gaseous effluents released from Units 2/3 are comprised of contnbutions from both units. Estimates of noble gas contributions from Units i 2 and 3 are allocated considering appropriate operating conditions and measured SJAE off- ]

gas activities. Allocation of radiciodine and radioactive particulate releases to Units 2 or 3 j specifically is not as practical and is influenced greatly by in.-plant leakage. Under normal j operating conditions, allocation is made using reactor coolant iodine activities. During unit j shutdowns or periods of known major in-plant leakage, the apportionment is adjusted I accordingly. The allocation of effluents is estimated on a monthly basis. ),

10.1.5 Dose Projections Because the gaseous releases are continuous, the doses are routinely ca!culated in '

accordance with the RETS.

10.2 LIQUID RELEASES j 10.2.1 System Description A simplified liquid radwaste and liquid effluent flow diagram is provided in Figure 10-3.

The liquid radwaste treatment system is designed and installed to reduce radioactive liquid effluents by collecting the liquids, providing for retention or holdup, and providing for treatment by evaporator, demineralizer, filter, and further vendor processing systems for the purpose of reducing the total radioactivity prior to reuse or release to the environment. The  ;

system is described in the Dresden UFSAR Section 11.2. j 10.2.1.1 Unit 1 Storage Tanks Liquid ra:"aactive effluents are not released from Unit 1 Storage tanks directly to the environment but are made through the Units 2/3 radwaste system.

10.2.1.2 Units 2/3 Waste Sample Tanks l

There are three waste sample tanks (33,000 gallons each) which receive water from the liquid waste treatment systern. These tanks are transferred to the waste surge tank for

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4 discharge to the Illinois River via the discharge canal. l O

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DRESDEN Revision 2.0 March 1999 10.2.1.3 Units 2/3 Floor Drain Sample Tanks -

l There are two floor drain sample tanks (22,000 gallons each) which receive liquid waste from the floor drain treatment system. These tanks are transferred to the waste surge tank or discharged to the lilinois River via the discharge canal.

10.2.1.4 Units 2/3 Waste Surge Tank l The waste surge tank receives processed water from the waste sample tanks and floor drain sample tanks. This tank discharges to the lilinois River via the discharge canal.

10.2.2 Radiation Monitors l 10.2.2.1 Liquid Radweste Effluent Monitor l \

l The monitor is used to monitor releases from the waste surge tank, floor drain sample tanks l or portable waste treatment system tanks. On high alarm, a grab sample of tha effluent is automatically taken from the discharge side of the sample chamber after a 0 to 60 second delay determined by a locally mounted timer. The release is terminated manually by  !

initiating closure of the low ficw or high flow discharge line valves. . )

l Pertinent information on the monitor and associated control devices is provided in the I Dresden UFSAR Section 11.5.

10.2.2.2 Units 2 & 3 Service Water Emuent Monitors l The monitors continuously monitor the service water effluent. On high alarm a grab sample is taken.

1 l Pertinent ir. formation on these monitors is provided in the Dresden UFSAR Section 11.5..

10.2.2.3 Chemical Cleaning Facility Service Water Effluent Monitor

Service water effluent (when in operation) is continuously monitored from the chemical l cleaning facility by the monitor. On high alarm the release is terminated by manually initiating closure of the isolation valve.

l No control device is initiated by this monitor.

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DRESDEN Revision 2.0 March 1999 10.2.3 Alarm and Trip Setpoints 4

10:2.3.1 Setpoint Calculations Alarm and trip setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of 10CFR20 are not exceeded in the unrestricted area.

10.2.3.1.1 Liquid Radwaste Effluent Monitor The monitor setpoint is found by solving equation 10-3 for the total isotopic activity.

(10-3)

P g K x (IC[/Z(C[/DWC)) x ((F8 + Ima)/ 5=)

P Release Setpoint [ cpm]

CT Concentrationof radionuclidelin [ Ci/ml]

the release tank Ima Maximum Release Tank Discharge Flow Rate (gpm]

The flow rate from the radwaste discharge tank.

The maximum pump discharge rate of 250 gpm is used for calculating the setpoint. ,

K Calibrationconstant (cpm /pCl/my DWC, Derived Water Concentration (also referred to as Effluent Concentration Limit, ECL) of Radionuclide i [pCi/ml]

The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to 10CFR20.1001-2402. When technical specifications allow, ten' (10) times the DWC, may be used.

1. Dilution Flow [gpm]

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' Dresden Station may use ten (10) upon Technical Specification approval. Until then, one (1) times the DWC must be used.

gM10ri-9. doc 10-8

DRESDEN Revmon 2.0

' March 1999 i

10.2.3.1.2 Units 2 & 3 Service Water Emuent Monitor

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The monitor setpoint is established at two times the background radiation value.

10.2.3.1.3 Chemeal Cleaning Facility Service Water Effluent Monitor j The monitor setpoint is established at two times the background radiation value.

10.2.3.2 Discharge Flow Rates 10.2.3.2.1 Release Tank Discharge Flow Rate I Prior to each batch release, a grab sample is obtained. l The results of the analysis of the sample determine the discharge rate of each batch as follows I= = 0.1(F8/E(C/DM)) .

(10-4)

The summation is over radionuclides i. ,.; -

0.1 Raductionfactorfor conservabsm.

I= Maximum Permitted Disch' gg Flow Rate [gpm]

j The maximum permitted flow rate from the radweste discharge tank. Releases are not .

permitted if the calculated discharge rate, -

F,,,,,, is less than 250 gpm.

1. Dilution Flow (gpm]

Cs Concentrationof Radionuclideiin (pCi/ml]

the Release Tank The concentration of radioachvity in the radwaste discharge tank based .

on measurements of a sample drawn from the tank.

DM Derived Water Concentration of Radionuclide i [pCi/ml]

The concentration of radionuclide i given in Appendix B. Table 2, Column 2 to 10CFR20.1001-2402. When technical specifications allow, ten8 (10) times the D% may be used.

O .2 Dresden Station may use ten (10) upon Techncal Specdcstm approval. Until then, one (1) times the DWC must be used.

g:W10ri-9. doc 10-9

DRESDEN Revision 2.0 March 1999 10.2.3.3 Release Limits Release limits are determined from 10CFR20. Calculated maximum permissible discharge rates are divided by 10 to ensure that applicable derived water concentrations (DWC) are not exceeded.

10.2.3.4 Release Mixture For the liquid radwaste effluent monitor, the release mixture used for the setpoint determination is the radionuclide mix identified in the grab sample isotopic analysis.

For all other liquid effluent monitors, no release mixture is used becmse the setpoint is established at "two times background."

10.2.3.5 Conversion Factors i ne readout for the liquid radwaste effluent monitor is in CPM. The calibration constant is based on the detector sensitivity to Co-60.

The readouts for the Units 2 & 3 service water effluent monitors are in Ci/ml. The calibration constar.ts are based on the detector sensitivity to Co-60. ~

10.2.3.6 Liquid Dilution Flow Rates The dilution flow is determined using the installed flowmeter in the discharge canal.

10.2.4 Allocation of Effluents from Common Release Points Radioactive liquid effluents released ~from the release tanks are comprised of O contributions from all three units. Under normal operating conditions, it is difficutt to apportion the radioactivity between the units. Consequently, allocation is normally made evenly between units 2 and 3.

10.2.5 Projected Doses for Releases Doses due to liquid effluents are calculated in accordance with the RETS.

10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM The process control program (PCP) contains the sampling, analysis, and formulation {

determination by which solidification of radioactive wastes from liquid systems is ensured. j l

Figure 104 is a simplified diagram of solid radwaste processing.

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, . dyf  ; ODCM Revision 1.9, March 1999 -  !

i J Page- Change Description '

,12-ii_ Updated revision number.

I 12-8 Added information in Action 1 I concerning allowable discharge cases when the monitor is " operable" but conditions can not be established in l

which to utilize it (e.g., low counts, low flow, etc.). Required actions are  !

the same as what was previously present for an inoperable monitor.  !

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, March 1999

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CHAPTER 12.0 1 SPECIAL NOTE -

The requirements of the Technical Specifications shall take precedence over this chapter, should any i differences occur.

The transfer of the Radiological Emuent Technical Specifications (RETS) to the ODCM for Unit i has been approved by the Nuclear Regulatory Commission in Amendment 39.

The transfer of the Radiological Emuent Technical Specifications (RETS) to the ODCM for Units 2  !

and 3 has been' approved by the Nuclear Regulatory Commission in Amendments 150 and 145.

1

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DRESDEN RIvision 1.9 M rch 1999 DRESDEN ANNEX INDEX 9

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r DRESDEN Revtion 1.9 March 1999 CHAPTER 12 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS (RETS)

TABLE OF CONTENTS PAGE 12.1 DEFINITIONS 12-1 12.2 INSTRUMENTATION 12-5 A. Radioactive Liquid Effluent Monitoring Instrumentation 12-5

1. Radioactive Liquid Effluent Monitoring instrumentation Operability 12-5 l

2. Radioactive Liquid Effluent Monitoring Instrumentation Surveillance 12-5 j B. Radioactive Gaseous Emuent Monitoring instrumentation 12-5 1

1. - Radioactive Gaseous Effluent Monitoring instrumentation Operability 12-5

2. Radioactive Gaseous Effluent Monitoring instrumentation Surveillance l 12-6 C. Liquid and Gaseous Effluents Instrumentation Bases 12-19 12.3 LIQUID EFFLUENTS 12-20 l

A. Liquid Effluents Limits and Reporting Operability 12-20

1. Concentration in Unrestncted Areas 12-20

2. Dose from Liquid Effluents 12-20

3. Dose actions 12-21

4. Liquid kadioachve Waste Treatment System 12-22

5. System Operability and Plant Operations 12-22 B. Liquid Effluents Surveillance 12-22

1. Concentration in Unrestricted Areas 12-22 O 2. Dose from Liquid Effluents 12-23 V 3. Dose Projections 12-23 C. Liquid Emuents Bases 12-30

1. Concentration 12-30

2. Dose 12 30

3. Liquid Waste Treatment 12-30

4. Mechanical Vacuum Pump 12-31 12.4 GASEDUS EFFLUENTS 12-32 A. Gaseous Effluents Limits and Reporting Operability 12-32

1. Dose Rate 12-32

2. Noble Gas Dose 12-32

3. lodine-131, lodine-133, Tritium and Particulate Dose 12-33

4. Off-Gas Treatment 12-34

5. Main Condenser Air Ejector 12-35

6. System Operability and Plant Operations 12 35 B. Gaseous Emuents Surveillance 12-36

1. Dose Rate 12-36

2. Noble Gas Dose 12-36

3. lodine-131, lodine-133, Tritium and Particulate Dose 12-36

4. Off-Gas Treatment 12-36

5. Noble Gases at the Main Condenser Air Ejector 12-37

. g:vnurphywdemunnexwreedenwn12rt-a. doc 12-iii

DRESDEN Revision 1.9 MCrch 1999 CHAPTER 12 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS (RETS)

TABLE OF CONTENTS CONTINUED P.AG,g 12.4 GASEOUS EFFLUENTS (Cont'd)

C. Gaseous Effluents Bases 1243

1. Gaseous Effluents, Dose 1243 T

2. Dose, Noble Gases 1243 ,J$c

3. Dose, Radiciodines, Radioactive Material in Particulate Form and Radionuclides Other than No'cle Gases 12=44

4. Gaseous Waste Treatment 12-44 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12 45

1. Monitoring Program 1245

2. Land Use Census 12 59 -

3. Intertaboratory Comparison Program 1240 {,

12.6 RECORDKEEPING AND REPORTING 1241

1. Station Operating Records 1241 --

2. Reports 1241

1. Radioactive Effluent Release Report 1241

2. Annual Radiological Environmental Operating Report 1241

3. Non-Routine Environmental Report 1242

3. Offsite Dose Calculation Manual (ODCM) 1243

4. Major Changes to Radioactive Waste Treatment Systems (Liquid and Gaseous) 1244 s

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I g:vnurphywdctmannexwresdenun12ri-8. doc 12-iv i t

DRESDEN Revision 1.9 l March 1999 j

.O l

CHAPTER 12 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS l

(RETS)

LIST OF TABLES l

)

NUMBER TITLE A ,gg

.P_A.

12.1 1 Surveillance Frequency Notation 12-3 12.1-2 Operational Modes 12-4 1

12.2-1 Radioactive Liquid Emuent Monitoring Instrumentation 12-7 12.2-2 Radioactive Liquid Emuent Monitoring Instrumentation Surveillance Requirements 12 4 12.2-3 Radioactive Gaseous Emuent Monitoring Instrumentation 12-12 12.2-4 Radioactive Gaseous Emuent Monitoring instrumentation Surveillance Requirements 12-16 12.3-1 Allowable Concentration of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Waste 12-24 O

V 12.3-2 Radioactive Liquid Waste Sampling and Analysis Program 12-25 12.4-1 Radioactive Gaseous Waste Sampling and Analysis Program 12-38 12.5-1 Radiological Environmental Monitoring Program 12 48 12.5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 12 54 Reporting Levels 12.5-3 Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection

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DRESDEN Revision 1.9 MIrch 1999 i

I 12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS C 12.1 DEFINITIONS l

1. Dose Eauivalent 1-131 - That concentration of I-131 (microcurie / gram) which alone would produce the sarr.e thyroid dose as the quantity and isotopic mixture of I-131,1-132,1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table ill of Tf D -14844, " Calculation of Distance Factors for Power and Test Reactor Sites".

2. Freauency Notation- Table 12.1-1 provides the definitions of various frequencies for which surveillances, sampling, etc., are performed unless defined otherwise. Refer to Technical Specification Table 1-1.

3. Immediate - Immediate means that the required action will be initiated as soon as practicable considering the safe operation of the unit and the importance of the required action.

4. Instrument Calibration - An instrument calibration means the adjustment of an instrument signal output so that it corresponds, within acceptable range and accuracy, to a known' value(s) of the parameter which the instrument monitors. Calibration shall encompass the entire instrument, including actuation, alarm, or trip.

S. Instrument Check - An instrument check is qualitative determination of acceptable operability by observation of instrument behavior during operation. This determination l q shall include, where possible, comparison of the instrument with other independent lh instruments measuring the same variable.

l 6. Instrument Functional Test - An instrument functional test means the injection of a l simulated signal into the instrument primary sensor to verify the proper instrument response alarm and/or initiating action.

7. Member of the Public - any individual except when that individual is receiving an occupational dose.

8. Medg - Reactor modes are described in Table 12.1-2 (per Technical Specification Table 12).

9. Occuoational Dose-The dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation and/or to radioactive material from licensed and unlicensed sources of radiation, whether in l the possession of the licensee or other person. Occupational dose does not include

( dose from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the public.

\

g:VnurphybacrniannexWresdenwn12ri-8. doc 1

12-1

DRESDEN Revision 1.9 M:rch 1999 12.1 DEFINITIONS (Cont'd)

10. The Offsite Dose Calculation Manual (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and  !

liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip l Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM thall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs describcd in Section 12.5 and (2) descriptions of the information that should be included in the Annual Raducgical Environmental Operating and Radioactive E' fluent Release Reports required by Sections 12.6.2.1 and 12.6.2.2.

11. Operable - A system, subsystem, train, component or device shall be OPERABLE or -

have OPERABILIT( when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for ,he system, subsystem, train, component or device to perform its specified safety function (s) q.tc.

are afsc capable of performing their related support function (s). ,2j .-

04

12. The Process Control Proaram (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be mrde to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated w'et solid wastes wi'l be accomplished in such a way as to assure compliance with 10 CFR Parts 20,61, and 71, State regulations, burial ground requirements, snd other requirements goveming the disposal of solid radioactive waste.

13. Public Dose rooer the dose received by a member of the public from exposure to radiation or n.dinWe material released by a licensee, or to any other source of radiadon under the control of a licensee. Public dose does not include occupational dose or dosca received from background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released in accordance with 10CFR35.75, or from voluntary participation in medical research .

programs.

14. Rated Thermal Power - Rated thermal power shall be a total reactor core heat transfer rate to the reactor coolant of 2527 thermal megawatts.

15. Reactor Power Ooeration - Reactor power operation is any operation with the mode switch in the "Startup/ Hot Standby" or "Run" position with the reactor critical and above ,

1% rated thermal power. Q

\

~. a l 16. Arca Check - The qualitative assessment of Channel response when the Channel #9 sensor is exposed to a radioactive source. 7

! 17. Definitions _&bted to Estimatino Dose to the Public Usinc the ODCM Computer Proaram:

1. Actual - Refers to using known release data to project the dose to the public for the previous month. These data are stored in the database and used to demonstrate compliance with the reporting requirements of Chapter 12.

2. Projected - Refers to using known release data from the previous meath or ,

estimatec release data to forecast a future dose to the public. These data are NOTincorporated into the database.

i g:Vnurphyiodctn\annexWresdenWn12ri.8 doc 12-2

DRESDEN Revmon 1.9 March 1999 TABLE 12.1-1 SURVElLLANCE FREEUENCY NOTATION NOTATION . FREQUENCY

• S (Shiftly) At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> l

1 D (Daily) _ At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> T At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> W(Weekly) At least once per 7 days t

M (MonthF/) Atleast once per 31 days O (Quarterly) At least once per 92 days .

SA (Semiannually) At least once per 184 days A(Annually) At least once per 366 days E (Sesquiannually) At least once per 18 months (550 days)

S/U (Startup) Prior to each reactor startup j NA (Not Applicable) Not applicable j

I

• Each surveillartce requirement shall be performed within the specified time it'terval with a maximum allowable extension not to exceed 25% of the surveillance interval. The bases to. Technical 7, .

Specifications 4.0.B provides clarification to this statement. These definitions do not apply to the Radiological Environmental Monitoring Program (Section 12.5).

O g:VnurphyWdemunnexWreedenWn12rt 4 doc 12-3

ORESDEN R; vision 1.9 March 1939 TABLE 12.1-2 OPERATIONAL MODES 9

MODE SWITCH AVERAGE REACTOR MODE POSITIONS COOLANT TEMPERATUR.E

1. POVER OPERATION Run Any temperature

2. STARTUP StartuptHot Standby Any temperature

3. HOT SHUTDOWN Shutdown'** > 212*F .;,

-y

4. COLD SHUTDOWN Shutdown (*" 5 212*F ..mi.',

sw '*

5. REFUEL!NGia Shutdown or Refuel ** 5140*F .

TABLE NOTATIONS .

(* The reactor mode switch may be placed in the Run, Startup/ Hot Gtandby, or Refuel posit 6n to test ~ g85 the switch interlock functions provided the control rods are verified to remain fully inserted by a ~ ;.'i#

second licensed operator or other technically qualified individual. s

• The reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per Technical Specification 3.10.1.

(* Fuel in the reactor vessel with one or more vessel heed closure bolte less than fully tensioned or with the head removed.

(* See Technical Specification Special Test Exceptions 3.12.A and 3.12.B.

• The reactor mode switch may be placed in the Refuel position while a single control rod is being ";

S moved provided the one-rod-out interlock is OPERABLE.

M When there is no fuel in the reactor vessel, the reactor is considered not to be in any + Mlt F %

OPERATIONAL MODE. Th6 reactor mode switch may then be in any position or may be M A~

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gitmpf LT,wnnextandenwn12r1-8. doc 12-4 i

DRESDEN Revision 1.9 March 1999 12.2 INSTRUMENTATION A. Radioactive Liauid Effluent Monitorina instrumentation

1. Radioactive Liauid Effluent Monitorina instrumentation Operability 1;

The effluent monitoring instrumentation shown in Tab la 12.2-1 shall be operable with alarm trip setpoints set to insure that the limits of Section 12.3.A are not exceeded. The alarm setpoints shall be determined in accordance with the ODCM.

2. With a radioactive liquid effluent monitonng inetoment alarm / trip setpoint less conservative than required, without de!ay suspend the release of radioactive liquid effluents monitored by the affected instrument, or declare the instrument inoperable, or change the setpoint so it is acceptably conservative.

3 With one or more radioactive liquid effluent monitoring instruments inoperable, take the action shown in Table 12.2-1. Retum the instrument to operable status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner. This is in lieu of an LER.

4. In the event operability requirements and associated action requirements cannot be satisfiert because of circumstances in excess of those addressed in the specifications, piwide a 30-day written report to the NRC and no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into any operational mode.

2. Radioactive Liauid Emuent Monitorina instruma,i.iicn Surveihnce

1. Each radioactive liquid effluent monitoring instrument shown in Table 12.2-2 shall be demonstrated operable by performance of the given source check, instrument checs calibration, and functional test operations at the frequencies shown in Table 12.2-2.

B. Radioactive Gaseous Effluent Monitorino Instrumentation

1. Radioactive Gaseous Effluent Monitorina Instrumentation Ooerability

1. The effluent monitoring instrumentation shown in Table 12.2-3 shall be operable with alarm / trip tetpoints set to ensure that the limits of Section'12.4.A are not exceeded. The alarm / trip setpoints shall be determined in accordance with the ODCM.

2. With a radioactive gaseous effluent monitoring instruments alarm / trip set point less conservative than required, without delay suspend the release of radioactive gaseous effluents monitored by the affected instrument, or declare the instrument inoperable, or change the setpoint so it is acceptably conservative.

g:VnurphybdcmbnnexWresdenWn12ri-8. doc 12-5

DRESDEN Revision 1.9 March 1999 12.2.8.1 Radioactive Gaseous Effluent Monitorino Instrumentation Operability (Cont'd)

3. With one or more radioactive gaseous effluent monitoring instruments inoperable, take the action shown in Table 12.2-3. Retum the instrument to operable status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release >

I Report why the inoperability was not corrected in a timely manner. This is in ileu of an LER.

4. The Unit 2/3 plant chimney gas sampling system may be out of service for 46 hours5.324074e-4 days <br />0.0128 hours <br />7.60582e-5 weeks <br />1.7503e-5 months <br /> for the purpose of servicing the high range noble gas monitor as long as the following conditions are satisfied:

1. Both units are at steady state conditions with the recombiners and charcoai absorbers in servipe for the operating' unit (s).

2. The dose rate in unrestricted araas must be shown by calculation to be less than the limits of 12.4.A assuming the charcoal absorbers are bypassed on both units. /.

~

. 3. Both offgas monitors on Unit 2 and Unit 3 must be operational and the monitor reading correlated to the chimney release rate based on the conservative

• assumption of both units' charcoal absorbers being bypassed.

4. If the provisions of 12.4A1.1,12.4.A.1.2, or 12.4.A.1.3 cannot be met, an orderfy load reduction of the unit (s) shall be initiated immediately.

5. In the event operability requirements and associated action requirernents cannot be satisfied because of circumstances in excess of those addressed in this Section, provide a 30-day written report to the NRC and no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into any operation mode.

2. Radioactive Gaseous Effluent Monitorino Instrumentation Surveillance Each radioactive gaseous radiation monitoring instrument in Table 12.2-4 shall be demonstrated operable by performance of the given source check, instrument check, calibration, and functiona! test operations at the frequency shown in Table 12.2-4.

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12 6

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DRESDEN Revtion 1.9 March 1999 TABLE 12.21 t

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION I

l UNIT 1 Minimum Total Channels No. of Instrument Operable Channels Action l Discharge Canal 1 1 12 Sampler

• ACDONS .

ACTION 12 - Operability is venfied pnor to performing and once a day during planned discharge.

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• When instrument is unavailable and associated actions cannot be performed, then discharges may not be made -

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DRESDEN Revision 1.9 March 1999 TABLE 12.2-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION UNITS 2 & 3 .

1 Minimum Total l Channels No. of l Instrument Operable Channels Action j i

1. Service Water Effluent 1 1 10 l Gross Activity Monitor ,

n

2. Liquid Radwaste Effluent 1 1 11 .4 ?;*.,

Gross Activity Monitor -!df ACTIONS l

ACTION 10 - With less than the minimum number of operable channels, releases via this pathway may continue, provided that at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> grab samples are collected and {

4 analyzed for beta or gamma activity at an LLD of less than or equal to 10 uOi/ml. 'C (The grab sample should normally t;e taken at the Service Water Monitor or at a

%q $ p ,

location which would be represeatative of the Service Water which is monitored.) f ACTION 11 - With less than a minimum number of operable channels, ehluent releases via this ..

pathway may continue, provided that prior to initiating a release, at least 2 independent 4r,f "

samples are analyzed, and at least 2 members of the facility staff independently verify the release calculation and discharge valving. Otherwise, suspend release of j-radioactive effluent via this pathway.

Effluent release via th:3 pathway may continue when either-

1. The flow through the monitor cannot be established and maintained within 2 {

design parameters, or

2. Effluent activity is below the range of detection fcr the monitor.

h~. l Provided that prior to initiating a release, at least 2 independant samples are analyzed, 5.

and at least 2 members of the facility staff independently verify the release calculations [

and discharge valving. K 1

w Otherwise suspend release of radioactive effluent via this pathway. t 9

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T,- -

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g:VnurphybdcrnunnexWresdenWn12rt 8. doc l 12-8

7-

DRESDEN Revision 1.9 l M

rch 1999 TABLE 12.2-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS UNIT 1 Functional Calibration ** Instrument Source 1 Instrument Test Checkm Check  ;

Discharge Canal Sampler * * '

I

• When instrument is unavailable and associated actions cannot be performed, then discharges may not. ;

I be made. I l

9 l

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9:WETAiGiaarwterWresdenWn12r1-8 doc 12-9

DRESDEN Revision 1.9 March 1999 TABLE 12.2-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS UNITS 2 & 3 Functional Calibration *m Instrument Source Instrument Test'*da Checkm Check

1. Liquid Radwaste Emuent Gross Q* E* D E*

Activity Monitor ,;. . _ _

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2. Service Water .

Effluent Gross Q* E* D E Activity Monitor

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g:VnurphybdemunnerWresdenWn12r1-8. doc 12-10

1 DRESDEN Revision 1.9' Mai:h 1939 TABLE 12.2-2 (Cont'd)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIONS

(*

The instrument Functional Test shall also demonstrate that control room alarm annunciation occurs, if any of the following cunditions exist, where applicable.

1. Instrument indicated levels above the alarm setpoint.

{

2. Circuit failure.

I

3. Instrument indicates a downscale failure.

4. Instrument controls not set in OPERATE mode.

• Calibration shallinclude performance of a functional test.

Calibration shallinclude performance of a source check.

Source check shall consist of observing instrument response during a discharge.

Functional tests may be performed by usin.g trip check and test circuitry associated with the monitor chassis.

Functional tests, calibrations, and instrument checks are not required when these instruments are not required to be operable or are tripped. Calibration is not required to be performed more than once every 18 months.

• Operability is verified prior to performing discharge and once a day during planned discharge.

1 l

i O g:Vrup/4,MnnexWresdenWn12r1-8 doc 12-11

l DRESDEN Revision 1.9 March 1999 TABLE 12.2-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION UNIT 1 Minimum Total Applicable Channels No. of Operational instrument Operable Channel3 Modes Action l

1

1. Main Chimney SPING Noble Gas 1 3 28 Monitors y;;

2. Main Chimney Particulate 1 1 27 7d? j Samplers .2(

. j 1

3. Main Chimney lodine Samplers 1 1 27 1

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l. DRESDEN Revision 1.9 l'

March 1999 TABLE 12.2-3  !

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION UNITS 2 & 3 I I

l Minimum Total Applicable

, Channels No. of Operational I

Instrument Operable Channels Modes Action

1. Main Chimney Noble Gas /SPING/ 1 3 20 GE Low Range Activity Monitor i

2. Main Chimney SPING Noble Gas 1 1 26 Monitors Mid, Hi Range

3. Main Chimney lodine Sampler 1 1 22

4. Main Chimney Particulate Sampler 1 1 22 i

5. Main Chimney Flow Rate Monitor 1 1 21

6. Main Chimney Sampler Flow Rate 1 1 21 Monitor

7. Reactor Building Vent Exhaust See Technical Specifications Section 3/4.2 I q Duct Radiation Monitor

8. Reactor Building Vent SPING 1 1 25 Noble Gas Monitor Low, Mid, High Range

9. Reactor Building Vent F;ow 1 1 21 i Rate Monitor

10. Reactor Building Vent Sampler 1 1 21 Flow Rate Monitor

11. Reactor Building Vent lodine 1 1 22 Sampler

12. Reactor Building Vent i 1 22 Particulate Sampler -

13. Offgas Radiation Activity 1 2 29 Monitor L

• At all times.

l " During Steam Jet Air Ejector operation, l

Q g:VnurphyWdemunnenWreedonWn12ri-8. doc 12-13

l DRESDEN Revision 1.9 March 1999 l TABLE 12.2-3 (Cont'd)

RAD;OACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ACTIONS AND TABLE NOTATIONS ACTION 20 - With less than the minimum channels operable, effluent releases via this pathway may I continue for up to 30 days provided grab samples are taken at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and analyzed for noble gas within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(The SPING has one low range noble gas channel, Channel 5, while the GE Low Range Activity Monitor has two low-range noble gas channels.

The grab samples are usually taken at either the SPING, if it is aligned in the flow path, or at the GE Low Range Activity Monitor Skid.)  ;

1 ACTION 21 - With' the number of operable channels less than the minimum required, effluent I releases via this pathway may continue provided that the flow rate is estimated at least j once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

(The Main Chimney Flow Rate Monitor and the Reactor Building Vent Flow Rate . ]

Monitor are used for flow through the ChimneyNent. Channel 10 of the SPING gives the ChimneyNent flow rate. This value can also be obtained from Point History.

l The Main Chimney Sampler Flow Rate Monitor and the Reactor Building Vent Sampler Flow Rate Monitor are used for the flow through the SPING or backup sampler. Channel 15 of the SPING gives the sampler flow rate for the SPING. The U2, U3 and GE Backup systems each have a flow rate monitor.) _

ACTION 22 - With less than the minimum channels operable, effluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling equipment, as required in Table 12.4-1.

~

(The normal sampler for 2/3 ?,*ain Chimney is the 2/3 Main Chimney SPING while for the 2/3 Reactor Building Vent it is the 2/3 Reactor Building Vent SPING.

If the 2/3 Chimney SPING is not operational, the normal backup is the GE Low Range Activity Skid. This skid collects an lodine and Particulate sample.

If the 2/3 Reactor Building Vent SPING is not operational, the normal backups are the U2 and U3 Reactor Building Vent Samplers. The sampler for each vent collects _,

an lodine and Particulate sample. #

lf the normal backup sampler is not available, use of an attemate sampler should be *

~

used as long as it pulls from the same process stream.)

.f ACTION 25 - With less than the minimum channels operable, effluent releases via this pathway may ,

continue provided that the minimum number of operable channels for the Reactor Building Vent Exhaust Duct Radiation Monitor are operable.

(These are Channels 5 (low-range),7 (mid-range) and 9 (high-range) on the 2/3 Reactor Building Vent SPING.)

fynurphybdcmunnexWresdenWn12r1-8. doc O

12-14

DRESDEN Revision 1.9 March 1999 ACTION 26- With less than the minimum channels operable, effluent releases via this pathway may

, continue provided the low range monitor is operable and on scale. Restore the inoperable equipment to operable status within 21 days, or prepare and submit a report to the Commission pursuant to Technical Specification 6.9.B within the next 30 days outlining the plans, actions taken and procedures to be used to provide for the loss of sampling capability of the system.

(These are Channels 7 (mid-range) and 9 (high-range) on the 2/3 Main Chimney SPING.)

ACTION 27- The main chimney SPING monitor may be out-of service for calibration and maintenance provided that particulate and iodine samples are taken and analyzed.

The samples shall be collected using altamate filter holders and pumps connected to the main chimney sample stream.

(The normal lodine and Particulate sampler for Di Main Chimney is the D1 Main Chimney SPING. If the D1 Chimney SPING is not operational, the normal backup is a sample pump attached to the sample stream from the Main Chimney, The sample pump collects an lodine and Particulate sample.) .

ACTION 28 - With less than the minimum channels operable, effluent releases via this pathway may continue provided daily noble gas samples are taken and analyzed daily. Restore the inoperable equipment to operable status within 30 days. If service can not be retumed, document equipment availability difficulties within the Radioachve Effluent l Release Report for the period including actions taken in response to the equipment i and procedures used to provide for the loss of sampling capability of the system.

(The normal noble gas monitors are Channels 5 (low-range), 7 (mid-range) and 9 O

(high-range) on the D1 Chimney SPING. Grab samples can either be taken off of the SPING or taps on the piping for the sample stream.)

ACTION 29 - With less than the minimum channels operable, gases from the main condenser off gas system may be released to the environment for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided the off t gas system is not bypasse?' and at least one chimney monitor is operable;

otherwise, be in HOT STANDBY in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

_ :e w

I ,

O ginurphybdcmunnexWreedenWn 12r1 8. doc 12-15 L

DRESDEN Revision 1.9 March 1999 TABLE 12,2-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS UNIT 1 Applicable Functional Calibration *' Instrument Source Operational Instrument Test

• Check Check Modes

1. Main Chimney SPING Q E D M Noble Gas Mnnitor Low Range -1. ,

m+$

g. 'e jP

• At all times.

• , d j

,...a--

T

= -. .

ga

. .l. "

l.OC C

+%..s .w. ,

,L:Gk S .9b.

^c.$.' w.

l'#g',

k a'. 4 7

,C*

5 A b .$

12-16

n DRESDEN R;vklon 1.9 M:rch 1999 TABLE 12.2-4 b

O RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS UNITS 2 & 3 Applicable Functional Calibration ***' instrument Source Operational Instrument Tesf***' Check (* Check Modes 1, Main Chimney Noble O E D M

• l Gas Activity Monitor j

2. Main Chimney SPING Q E D M Noble Gas Monitor Lo, Mid, High Range

3. Main Chimney NA NA D(* NA

• Particulate and lodine Sampler

4. Main Chimney Flow Q E D NA

• Rate Monitor

5. Main Chimney Sampier O'S E D NA

• i Flow Rate Monitor '

(9

• g 6. Reactor Bldg Vent See Technical Specifications Section 3/4.2 ]

Exhaust Duct Radiation Monitor l

7. Reactor Bldg Vent O E D M

• SPING Noble Gas Monitor Lo, Mid, High Range

8. Reactor Bldg Vent Q E D NA

• Flow Rate Monitor

9. Reactor Bldg Sampler Q(* E D NA

• Flow Rate Monitor

10. Reactor Bldg Vent NA NA D'S NA

• Particulate and lodine Sampler

11. Cff Gas Radiation Q E D E Activity Monitor

• At all times.

" During Steam Jet Air Ejector operation.

O g:WapirfodemWmexWresdenWn12ri-8. doc 12-17

I l l

DRESDEN Revision 1.9 M:rch 1999 TABLE 12.2-4 (Cont'd)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIO; SURVEILLANCE REQUIREMENTS TABLE NOTATIONS I

I

(*) '

The instrument Functional Test shall also demonstrate that control room alarm annunciation occurs, if any of the following conditions exist, where applicable.

~~

1. Instrument indicates levels above the alarm setpoint.

2. Circuit failure.

3. Instrument indicates a downscale failure. y-

d. Instrument controls not set in OPERATE mode. .

• ) Calibration shallinclude performance of a functional test. ,

(* Instrument check to verify operability of sampler; that the sampler is in place and functioning properly.

(* Functional test shall be performed on local switches providing low flow alarm.

.}

(* Funct.ional tests, calibrations, and instrument checks are not required when these instruments are not required to be operable or are tripped. Calibration is not required to be performed more than ~

once every 18 months.

l l

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.2 '

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g:VnurphybdomunnexWresdenMn12ri-8. doc 12-18 l

I i

DRESDEN Revrion 1.9 March 1999 12.2.C Uauid And Gaseous Effluents Instrumentation Bases

1. The radioactive liquid and gaseous effluent instrumentation is provided to monitor the release of radioactive materials in liquid and gaseous effluents during releases. The alarm setpoints for the instruments are provided to ensure that the alarms will occur pnor to exceeding the limits of RETS.

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a-O 9:Mi ThWmedenWn12ri-8. doc j

i 12-19 ,

1 i

F DRESDEN Revision 1.9 March 1999 12.3 LlOUID EFFLUENTS 12.3.A Liould Effluents Limits and Reportina Operability

1. Concentration in Unrestncted Areas The concentration of rartioactive material released from the site to unrestricted areas (at or beyond the site boundary, Dresden Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the concentrations specified in Appendix B, Table 2. Column 2 to 10CFR20.100120.2402', for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the coricentration shall be limited to the values listed in Table 12.3-1.

With the concentration of radioactive material released from the site to ,

unrestricted areas exceeding the above limits, without delay decrease the release e gc ?

rate of radioactive materials and/orincrease the dilution flow rate to restore the concentration to within the above limits. 7Q

2. Dose from Licuid Eff!Lents The dose or dose commitment above background to a member of the public fr6m radioactive materials in liquid effluents released to unrestricted areas (at or beyond the site boundary) from the site shall be limited to the following:

1. During any Calendar Quarter .[

(1) Less than or equal to 3 mrem to the whole body. _i '

(2) Less than or equal to 10 mrem to any organ. .

2. During any Calendar Year. _ .. L (1) Less than or equal to 6 mrem to the whole body.

(2) Less than or equal to 20 mrem to any organ. ,

i i

3. With the calculated dese 'r m the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days a Special Report which identifies the j cause(s) and defines the corrective actions taken and the proposed J actions to be taken to ensure that future releases are in compliance with . "2. i Sections 12.3A2.1 and 12.3A2.2. This is in lieu of a Licensee Event gAy;.

Report.

us:#

, A,~

- }.[i!

u 4

g e

• Upon technical specification approval, ten (10) times the Appendix B value may be used to determine the maximum instantaneousliquid release. s l

gh57%TAannexWreedenWn12r18. doc

~

12-20

f DRESDEN Revision 1.9 1 Mtrch 1999 )

i 12.3.A Liouid Effluents Limits and Reportino Ooerability (Cont'd)

{

4. With the calculated dose from the release of radioactive materials in liquid effluents exceeding the limits of Sections 12.3.A.2.1 or 12.3.A.2.2.,

prepare and submit a Special Report to the Commission within 30 days and limit the subsequent releases such that the dose or dose commitment to a member of the public from all uranium fuel cycle sources is limited to less than or equal to 25 mrem to the total body or

, any organ (except thyroid, which is limited to less than or equal to 't5 L mrem) over 12 consecutive months. This Special Report shall inc.ade an

analysis which demonstrates that radiation exposures to all real

individuals from all uranium fuel cycle sources (including all effluent l pathways and direct radiation) are less than the 40 CFR Part 190 I Standard. Otherwise obtain a variance from the Commission to permit rrAeases which exceed the 40 CFR Part 190 Standard. The radiation

, exposure analysis contained in the Special Report shall use methods l prescribed in the ODCM. This report is in lieu of a Licensee Event l Report.

5. When the projected annual whole body or any intemal organ dose computed at the nearest downstream community water system is equa,I to or e.vceeds 2 mrem from all radioactive materials released in liquid effluents from the Station, prepare and submit a Special Report within 30 days to the operator of th'e community water system. The report is  !

prepared to assist the operator in meeting the requirements of 40 CFR Part 141, EPA Primary Drinking Water Standards. A copy of this report will be sent to the NRC. This is in lieu of a Licensee Event Report.  !

3. Dose Projections At all times during processing prior to discharge to the environs, process and i control equipment provided to reduce the amount or concentration of radioactive materials shall be operated when the projected dose due to liquid effluent releases to unrestricted areas (Dresden Station ODCM Annex, Appendix F. I Figure F-1), when averaged over 31 days, exceeds 0.12 mrem to the total :ody or 0.40 mrem to any organ *.

'These values represent 2% of the annual dose limits of Appendix 1 to 10CFR50.

f U

ghwphfodem\ennexWreedenWn t 2r1 8. doc l 12-21

l)

DRESDEN Revision 1.9 l March 1999 l 12.3.A Liouid Effluents Limits and Reoortino Ooerability (Cont'd)

4. Liouid Radioactive Waste Treatment System if liquid waste has to be or is being discharged without treatment as required above, prepare and submit to the Commission with 30 days, a report which includes the following information.

1. Identification of the defective equipment.

2. Cause of the defect in the equipment.

3. Action (s) taken to restore the equipment to an operating status.

4. Length of time the above requirements were not satisfied. ,

.:. ' l S. Volume and curie content of the waste discharged which was not ,.

processed by the appropnate equipment but which required processing. '

)

1

6. Action (s) taken to prevent a recurrence of equipment failures.

This is in lieu of a Licensee Event Report.

I

5. System Operability and Plant Occrations  !

In the event a limit and/or associated action requirements identified in Sections

~-

12.3.A and 12.3.B cannot be satisfied because of circumstances in excess of ~

those addressed in this Section, no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into any operational mode.

12.3.B tiouid Effluents Surveillance

1. Concentration in Unrestricted Areas The concentration of radioactive materialin unrestricted areas shall be determined to be within the prescribed limits by obtaining representative samples in accordance with the sampling and analysis program specified in Table 12.3-2. i The sample analysis results will be used with the calculational methods in the j '

ODCM to determine that the concentrations are within the limits of Section 12.3.A.1. .. .-

_ 7. N l

t l

g:Vf turphybdcmunnexWresdenWn12r1 8. doc 9

12-22

r- -

L DRESDEN . Revision 1.9 l

March 1999

) 12.3.B Liouid Emuents Surveillance (Cont'd) =

' 2. Dose from Licuid Emuents The dose contnbution from measured quantities of radioactive material shall be 4 determined by calculation at least once per 31 days and cumulative summation of these total body and organ dosed shall be maintained for each calendar quarter.

l Doses computed at the nearest community water system will consider only the l drinking water pathway and shall be projected using the methods prescribed in ODCM, at least once per 92 days.

3. Dose Proiections Doses due to liquid releases to unrestricted areas (at or beyond the site boundary) shall be projected at least once per 31 days in accordance with the '

ODCM.

I I

1 I

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l O g:WEF.iG AenneiddreedonWn12ri 8 doc 12-23 i- .

J

DRESDEN Revision 1.9 March 1999 TABLE 12.3-1 ALLOWABLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID _ WASTE NUCLIDE AC(uCi/ml)*

Kr-85m 2 x 10d ,_

Kr-85 5 x 10d ;r .

. . v.

Kr-87 4 x 104 f.ic y ;.

Kr-88 9 x 10 5 .

Ar-41 7 x 10'5 .

Xe-131m 7 x 10d Xe-133m 5 x 10d .

Xe-133 6 x 10*

Xe-135m 2 x 10d Xe 135 2 x 10" J-::

1

. . : t..

+,

Computed from Equation 20 of ICRP Publication 2 (1959), adjusted for infinite doud submersion in ,;g;.

water, and R = 0.01 rem / week, density = 1.0 g/cc and Pw/Pt = 1.0. , @j,[

(( %

, .y L' M -'

.. u 2^

4

.; jh

g:Vnu.-A,v,deiAannexWresdenwn12ri 8. doc 12-24

_ _ - - - . _ _ _ _ _ _ _ . _ _ _ _.___________________d

DRESDEN Revision 1.9

, Mirch 1999 TABLE 12.3-2 i

! v- RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM UNIT 1 LOWER LIMIT OF TYPE OF ACTIVITY DETECTION L! QUID RELEASE SAMPLING MINIMUM ANALYSIS ANALYSIS (LLD)"3 (pCi/ml)

TYPE FREQUENCY

• FREQUENCY

• l Above See TS 3/4.8.J See TS 3/4.8.J Principal Gamma 5x10#

Ground Emitters *  ;-

Liquid Storage Dissolved & Entrained - ,1x104 Tanks Gases * (Gamma .

l Emitters) i l

l l

I l

l l

l O g:Vnurphybdcmu.vexWresdenWn12ri 8. doc 12-25 L.

r DRESDEN Revision 1.9 M3ch 1999 TABLE 12.3-2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM t- UNITS 2 & 3 LOWER LIMIT OF TYPE OF ACTIVITY DETECTION LIQUID RELEASE SAMPLING MINIMUM ANALYSIS ANALYSIS (LLD)m (pCi/ml)

TYPE FREQUENCY 4' FREQUENCY

• A. Batch Prior to Prior to Principal Gamma 5x10#

Release Each Batch Each Batch Emi+!ers* -

Tanks 1-131 1x104 1x10#

Prior to M Gross Alpha Each Batch Composite

• H-3 1x104 4 t

[

Prior to Q Fe-55 1x104 Each Batch Composite

• Sr-89, Sr-90 5x104 Prior to M Dissolved & Entrained 1x104 One Batch /M Gases *(Gamma ,

Emitters) .

B. Plant MS M* l-131 1x104 Continuous (Grab Sample) ( )

Releases * ,

MS MW Principal Gamma 5x10 #

(Grab Sample) Emitters

• MS M* Dissolved & Entrained 1x104 (Grab Sample) Gases * (Gamma Emitters)

MS M* H-3 1x104 (Grab Sample)

Gross Alpha 1x10#

Q* Q* Sr-89, Sr-90 5x104 (Grab Sample)

Fe-55 1x104 l

C. Above Ground See TS 3/4.8.J See TS 3/4.8.J Principal Gamma 5x10#

Liquid Storage Emitters

• Tanks s

^

Dissolved & Entrained 1x104 Gases5)(Gamma Emitters) g:WurphybdamannexWresdenWn12ri 8. doc 12-26 1

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y -- ]

l DRESDEN Rev'zion 1.9 March 1999 L

i i V b TABLE 12.3-2 (Cont'd)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM l TABLE NOTATION

(" 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% probability with only 5% probability of falsely concluding that a blank .

observation represents a "real" signal.

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

l LLD = 4 66S- I E V 2.22 x 10r Y exp (-Aat)

Where:

~

LLD = the lower limit of detection (microCuries per unit mass or volume),

s, = the standard deviation of the background counting rate or of the counting rate of a~

blank sample as appropriate (counts pt r minute),

E = the counting efficiency (counts per disintegration),

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

2.22 x 10' = the number of disintegrations per minute per microcurie, l

Y = the fractonal radiochemical yield, when applicable.

l ,

A= the radioactive decay constant for the particular radionuclide (sec4), and At = the elapsed time between the midpoint of sample collection and the time of counting

! (sec).

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

Allemate LLD Methodoloav l An altamate methodology for LLD determination follows and is similar to the above LLD

' equation:

~

(2.71 + 4.65VB)+ Cca.ay )

LLD =  ;

E q b Y t (2.22E06)

P 1

g:Wwg,/GT,WnnexWreedenWn12r14 doc '

l

~

12-27 t

l'  :

L b

I DRESDEN Revision 1.9 March 1999 TABLE 12.3-2 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION Where:

B = background sum (counts)

E = counting efficiency, (counts detected / disintegrations) q = sample quantity,(mass or volume) b = abundance,(if applicable)

Y = fractional radiochemical yield or collection efficiency, (if applicable) \

p t = count time (minutes) .

2.22E06 = number of disintegrations per minute per microcurie ,

(2.71 + 4.65V8) = k2 + (2k V 2 V B), and k = 1.645.

(k=value of the t statistic from the single-tailed t distribution at a significance level of 0.95% and infinite degrees of freedom. This means that the LLD result v. 3 -

represents a 95% detection probability with a 5% probability of falsely concluding ~~~_

that the nuclide present when it is not or that the nuclide is not present when it is.)

~

Decay = e* [ ART /(1-e")][AT./(1-e#8)], (if applicable) ,

A = radioactive decay constant, (units consistent with At, RT and T.)

at = ' delta t", or the elapsed time between sample collection or the midpoint of sample collection and the time the count is started, depending on the type of sample, (units consistentwith A)

RT = elapsed real time, or the duration of the sample count, (units consistent with A)

T. = sample deposition time, or the duration of analyte collection onto the sample z .t:E r media, (unit consistent with A) g:,

The LLD may be determined using installed radioanalytical software, if available. In ;7 addition to determining the correct number of channels over which to total the ;Wi. t background sum, utilizing the software's ability to perform decay corrections (i.e. during M sample collection, from sample collection to start of analysis and during counting), this attemate method will result in a more accurate determination of the LLD.

it should be recognized that the LLD is defined as a before the fact limit and not as an after the fact limit for a particular measurement. y

O .

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g:Vnurphybdcm\anneMresdenWn12ri-8. doc 12-28

DRESDEN Revision 1.S March 1999 f-~ TABLE 12.3-2 (Cont'd)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION

• A composite sample is one in which the quantity of liquid samples is 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 liquids released.

• If the alarm setpoint of the service water effluent monitor as determined in the ODCM is l exceeded, the frequency of analysis shall be increased to daily until the condition no longer exists.

W A batch release is the discharge ofliquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated and then thoroughly mixed to assure representative sampling. A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g.,

from a volume or system that has an input flow during the release.

• The pnncipal gamma emitters for which the LLD specification applies exclusively are the foliqwing radionuclides: Mn-54, Fe-59, Co-60, Zn-65, Co-58, Mo-99, Cs-134 Cs-137, Ce-141, and Ce-144.

Other peaks which are measurable and identifiable by gamma ray spectrometry together with the above nuclides, shall be also identified and reported when the actual analysis is performed on's sample. Nuclides which are below the LLD for the analyses shall not be reported as being present at the LLD level for that nuclide.

• The dissolved and entrained gases (gamma emitters) for which the LLD specification applies exclusively are the following radionuclides: Kr-67, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138.'

O Other dissolved and entrained gases (gamma emitters) which are measurable and identifiable by

\ gamma ray spectrometry, together witt. the above nuclides, shall also be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being present at the LLD level for that nuclide.

I l

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g:VmT,hi4TAnnnexWresdeMdn12r14 doc 12-29 4 i

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I DRESDEN Revtion 1.9 March 1999 12.3.C LIQUlO EFFLUENTS BASdS

1. Concentration This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in Appendix B, Table 2, Column 2 to 1CCFR20.1001-20.2402.

2. Dose This specification is provided to implement the requirements of Sections ll.A, Ill.A and IV.A of Appendix 1.10 CFR Part 50. The operational requirements implements the guides set forth in Section I!.A of Appendix 1. The statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive matenal in liquid effluents will be kept "as low as reasonably achievable". The dose calculations in the ODCM implement the requirements in Section Ill.A of Appendix 1 that conformance with the guides of Appendix i +

be shown by calculational procedures b Sed on models and data such that the actual oxposure of an individual through appropriate pathways is unlikQ to be substantially underestimaied. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodo'ogy provided in Ryulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Emuents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1 October 1977 and Regulatory .

l Guide 1.113 " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendix I", April 1977.

NUREG-0113 provides methods for dose calculations consistent with Reg Guide 1.109 {

and 1.113. I

, 3. Liguid Waste Treatment The operability of the liquid radwaste treatment system ensures that this system will be )

available for use whenever liquid effluents require treatment prior to release to the I environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will oe kept "as low as reasonably achievable". This specification implements the requirements of 10 CFR Part 50.3Sa, General Design Criterion 60 of Appendix A to 10 l CFR Part 50 and design objective Section 11.D of Appendix l to 10 CFR Part 50. j

.n 6 )

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I DRESDEN Revtion 1.9 '

Mamh 1999 ,

i 12.3.C LlOUID EFFLUENTS BASES -(Continued)

4. Mechanical Vacuum Pumo

%u The purpose of isolating the mechanical vacuum line is to limit release of activity from the main condenser. During an accident, fission products would be transported from the reactor through the main steam line to tite main condenser. The fission product radioactivity would be sensed by the main steamline radioactiv;ty monitors which initiate isolation.

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O g:VnurphybdomwnnenWresdenWn12r1-8. doc 1

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Revision 1.9 I DRESDEN March 1999 12.4 GASEOUS EFFLUENTS A. Gaseous Effluents Limits and Reportino Ocerability 1

1. Dose Rate j i

The dose rate in unrestricted areas at or beyond the site boundary (Dresden Station ODCM Annex, Appendix F, Figure F-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following.

1. For Noble Gases:

(1) Less than a dose rate of 500 mrem / year to the whole body.

(2) Less than a dose rate of 3000 mrem / year to the skin.

2. For iodine-131, for iodine-133, tritium and for all radionuclides in particut is ^

a form with half 4ives greater than 8 days, less than a dose rate of 1500 mrern/ year.

3. If the dose rates exceed the above limits, without delay decrease the release rates to bnng the dose rates within the limits, and provide notification to

~~

the Commission (per 10 CFR Part 20.2203).

2. Noble Gas Dose The air dose in unrestricted areas at or beyond the site boundary due to noble gases I_

released in gaseous effluents from the unit shall be limited to the following:

1. For Gamma Radiadon (1) Less than or equal to 5 mrad during any calendar quarter. ~

(2) Less than or equal to 10 mrad during any calendar year.

2. For Beta Radiation (1) Less than or equal to 10 mrad during any calendar qua ter.

(2) Less than or equal to 20 mrad during any calendar year.

3. With the calculated air dose from radioactive noble gases in gaseous _ ,.7 .

effluents exceeding any of the above limits, prepare and subrnit to the .7..

Commission within 30 days, a Special Report which identifies the cause(s) for  ;

exceeding the limit (s) and defines the corrective actions to be taken to ensure that future releases are in compliance with Sections 12.4.A.2.1 and _ , ; .4 12.4.A.2.2. This is in lieu of a Licensee Event Report. h. '

Q 4 x g:vnurph/4. AannexWresdenWn12r1-8. doc 9

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DRESDEN Revi: ion 1.9 March 1999 12.4.A Gaseous Effluents Limits and Reoortina Operability (Cont'd)

4. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding the limits of Sections 12.4.A.2.1 or 12.4A2.2, prepare and submit a Special Report to the Commission within 30 days and limit the subsequent releases such that the doses or dose commitment to a member of the public from all uranium fuel cycle sources is limited to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months. This Special Report shall include an analysis which demonstrates that radiation exposures to all members of the public from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than 40 CFR Part 190 Standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40CFR Part 190 Standard. The radiation exposure analysis contained in the Special Report shall use the methods presenbed in the ODCM. This report is in lieu of a Licensee Event Report.

~

5. Process and control equipment provided to reduce the amount or concentration of radioactive materials shall be operated when the projected dose due to gaseous effluents released to the unrestncted areas, when averaged over 31 days, exceeds 2% of the annual dose limits of Appendix ~

1 to 10CFR50.

3. lodine-131. lodine-133. Tritium. and Par %%te Dose The dose to a member of the public in unrestricted areas at or beyond the site -

boundary from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the unit shall be g, limited to the following.

1. Less than or equal to 7.5 mrom to any organ during any calendar quarter,

2. Less than or equal to 15 mrem to any organ during any calendar year.

3. With the calculated dose from the release of iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents exceeding any of the above limits, prirpare and submit to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and defines the correchve actions taken to ensure that future releases are in compliance with Section 12.4A3.1 and 12.4.A.3.2. This is in lieu of a Licensee Event Report.

4. With the calculated dose from the release of iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents exceeding the limits of Sections 12.4A3.1. or 12.4A3.2.,

prepare and submit a Special Report to the Commission within 30 days and limi subsequent releases such that the dose or dose commitment to a member of the public from all uranium fuel sources O gNnurphyiodanunnexWreedenWn12ri 8. doc 12-33

DRESDEN Revtion 1.9 March 1999 12.4.A Gaseous Effluents Limits and Reportina Ooerability (Cont'd) is limited to less than or equal to 25 mrem to the total body or organ (except the thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months. This Special Report shallinclude an analysis which demonstrates that radiation exposures to all members of the public from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard. The radiation exposure analysis contained in the Special Report shall use the methods prescribed in the ODCM. This report is in lieu of a Licensee Event Report.

5. Process and control equipment provided to reduce the amount or concentration of radioactive materials shall be operated when the projected dose due to gaseous effluents released to the unrestricted areas, when averaged over 31 days, exceeds 2% of the annual dose limits of Appendix 1 to 10CFRSO.

4. Off-Gas Treatment ,

1. At all times during processing for discharge to the environs, process and control quipment provided to reduce the amount of concentration of radioactive materials shall be operated.

2. The above specification shall not apply for the Off-Gas Charcoa! Adsorber Beds below 30 percent of rated thermal power.

3. The recombiner shall be operable whenever the reactor is operating at a pressure greater than 900 psig.

• . The recombiner may be inoperable for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

5. With either the recombiners inoperable, or all charcoal beds by-passed for more than 7 days in a calendar quarter while operating above 30 percent of the rated thermal power, prepare and submit to the Commission within 30 days a Special Report which indudes the following information.

a. Identification of the defective equipment.

b. Cause of the defect in the equipment.

c. Action (s) taken to restore the equipment to an operating status. i

d. Length of time the above requirements were not satisfied.

e. Volume arid curie content of the waste dischargeo which was not processed by the inoperable equipment but which required processing.

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1 12-34

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l DRESDEN Revision 1.9 March 1999 l 12.4.A Gaseous Fffluents Limits and Reoortino Ooerabilitv,(Cont'd)

f. _ Action (s) taken to prevent a recurrence of equipment failures, l

~

This is in lieu of a Licensee Event Report.

5. Main Condenser Air Eiector l

l The release rate of the sum of the activities from the noble gases measured at the main condenser air ejector shall be limited to 5100 microcuries/sec per MWt (after 30 minutes decay) when in modes 1,2*, and 3* With the release rate of the sum of the l activities from noble gases at the main condenser air ejector effluent (as measured i prior to the offgas holdup line) > 100 microcunes/sec per MWt, after 30 minutes decay, restore the relaasc rate to within its limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or be in at least STARTUP with the main steam isolation valves closed within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. (Refer to Technical Specification 3.8.1.)

6. System Operability and Plant Operations In the event a limit and/or associated action requirements identified in Sections 12.4.A and 12.4.B cannot be satisfied because of circumstances in excess of those adoressed in this Section, no changes are required in the operational conditioriof the plant, and this does not prevent the plant from entry into any operational mode.

O .

l l

I i

)

*When the main condenser air ejector is in operation.

dc g:Wwr#./enwnnexWresdenWn12r1 8. doc 12-35

DRESDEN Revrion 1.9 March 1939 l

12.4.B Gaseous Effluents Surveillance i

1. Dose Rate The dose rates due to radioactive materials released in gaseous effluents from the site shall be determined to be within the prescribed limits by obtaining representatNe f samples in accordance with the sampling and analysis program specified in Table 12.4-1. The dose rates are calculated using methods prescribed in the ODCM.

2. Noble Gas Dose

~

The air dose due to releases of radioactive noble gases in gaseous effluents shall be determinert to be within the presenbed limits by obtaining representative samples in accordance with the sampling and analysis program specified in Sections A and B of Table 12.4-1. The allocation of effluents between units having shared effluent control -

system and the determination of cumulative and projected dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once every 31 days. ;72

3. lodine-131. lodine-133. Tritium and Particulate Dose The dose to a member of the public due to releases of iodine-131, iodine-133,lritium, and all rodionuclides in particulate form with half-lives greater than 8 days shall be determined to be within the prescribed limits by obtaining representative samples in accordance with the sampling and analysis program specified in Table 12.4-1.

For radionuclides not determined in each batch or weekly composite, the dose contribution to the current calendar quarter cumulative summation may be estimated by assuming an average monthly concentration based on the previous monthly or quarterly composite analyses. However, for reporting purposes, the calculated dose contributions shall be based on the actual composite analyses when possible.

The allocation of effluents between units having shared effluent control system and the determination of cumulative and projected dose contributions for the current calendar quarter and current calendar year shall bJ determined in accordance with the methodology and parameters in the ODCM at least once every 31 days.

4. Off-Gas Treatment Doses due to treated gases released to unrestricted areas at or beyc' 3 the site boundary shall be projected at least once per 31 days in accordance with the ODCM. a 7-Q .'

. WA..

4-.

tg-..

y O

g.VnurphybdcrrnannexWresdenWn12ri-8. doc 12-36

p DRESDEN Revision 1.9 Mrrch 1999 a

- 12.4.B Gmus Effluents Surve lance - Continued

5. Noble Gases at the Main Condenser Air Elector The release rate of noble gases from the main condenser air ejector shall be continuously monitored. The release rate of the sum of the activities from noble l

_ gases from the main condens... ur ejector shall be determined to be within the limits of 12.4.A.5 at the following fruquencies by performing an isotopic analysis of a representative sample of gases taken at the recombiner outlet, or at the air ejector outict if the recombiner is by-passed.

! 1. _ At least once per 31 days.

2. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> followting determination of an increase of greater than 505 (Refer to Technical Specification 4.8.l.)

l l

i l

D.

.V g:WwrphyWdemunnexWreedenWn12ri-8 doc 12-37

DRESDEN Revision 1.9 M rch 1999 TABLE 12.4-1

~

RADIOACTIVE GASEOUS WASTE SAMPLING 0

AND ANALYSIS PROGRAM

• UNIT 1 GASEOUS SAMPLING MINIMUM TYPE OF ACTIVITY LOWER LIMIT OF RELEASE FREQUENCY ANALYSIS ANALYSIS DETECTION (LLD)"3 TYPE FREQUENCY (pCi/ml)

A. Main M M Principal Gamma 1x10d ..

Chimney (Grab Sample) Emitters

• Tritium 1x104 Noble Gases 1x104 MS*) M* l-131 1x10"2 (Continuous) lodine Sample 1-133 1x10d*

MS M* Principal Gamma 1x10-"

(Continuous) Particulate Sample Ernitters

• Q Q Sr-89, Sr-90 1x10-"

(Continuous) Composite Gross Alpha Particulate Sample

h. .

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12-38 1

c:

'DRESDEN - Revison 1.9 March 1999 Table 12.4-1 f

iL'g) RADIOACTIVE GASEOUS WASTE SAMPt.ING AND ANALYSIS PROGRAM UNITS 2 & 3 LOWER LIMIT

GASEOUS SAMPLING MINIMUM TYPE OF ACTIVITY .

OF RELEASE FREQUENCY ANALYSIS ANALYSIS DETECTION l TYPE FREQUENCY (LLD)")(pCi/ml) 1-A. Main M M<2) Principal

Chimney (Grab Sample) Gamma Emitters (5) 1x10d I Reactor-Bldg. . M Tritium 1x104 Vent -

Stack .

B. All Continuous (*) WS) 1-131 1x10"8 Release lodine Sample 1-133 1x10-* -

Types as Listed in A above

'O CoNinuous(*) W8)

Particulate Sample Principal Gamma Emitters (5) 1x10-"

Continuous (d) 'Q Sr-89 1x10-"

Composite l Particulate Sample Sr-90 1x10-"

! Continuoust') Q Gross Alpha 1x10-"

Composite Particulate Sample C. Main Continuous (d) Noble Gas Monitor Noble Gases 1x104 l l Chimney .

D. Reactor Continuous (*) Noble Gas Monitor ' Noble Gases 1x10d l

Bldg.

Vent Stack l~

l.

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DRESDEN Revision 1.9 March 1999

)

TABLE 12.4-1 (Cont'd)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Ol '

TABLE NOTATION N 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% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

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

LLD = 4 66S,

^

E V 2.22 x 10*

• Y + exp (-AAt)

Where:

LLD = the lower limit of detection (microCuries per unit mass or volume),

s = the standard deviation of the background counting rate or of 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 x 10' = tt e number of disintegrations per minute r w microCd.

Y = the fractional radiou.a. deal yield, when applicable, j

(

d A= the radioactive decay constant for the particular radionuclids (sec ), and at = the elapsed time between the midpoint of sampia milect:en and the time of counting (sec).

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

Altemate LLD Methodolor y An attemate methodology for LLD determination follows and is similar to the above LLD O

equation: 7. , .,

(2.71 + 4.65VB). Decay LLD =

E q b Y t(2.22E06) g:W1urphybdcmunnexWresdenWn12ri-8. doc O

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e DRESDEN Revtion 1.9 M rch 1999

)

TABLE 12.4-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMFLING AND ANALYSIS PROGRAM i TABLE NOTATIONS l Where:

B = background sum (counts)

E = counting efficiency, (counts detected / disintegrations) q = sample quantity, (mass or volume) b = abundance, (if applicable) j Y = fractional radicchemical yield or collection efficiency, (if applicable)

~

t = count time (minutes) l 2.22E06 = number of disintegrations per minute per microcurie (2.71 + 4.65VB) = k2 + (2k V 2 4 B), an.d k = 1.645.

]

(k=value of the t statistic from the single-tailed t distribution at a significance level

-(Q/ of 0.95% and infinite degrees of freedom. This means that the LLD result represents a 95% detection probability with a 5% probability of falsely concluding i that the nuclide present when it is not or that the nuclide is not present when it is.)  ;

i Decay = e*[ ART /(1-e")][AT,/(1-e#8)],(if applicable)

+ adioactive decay constant, (units consistent with At. RT and T,)

i at = "deita t", or thz elapsed time between sample collection or the midpoint of sample  ;

. fNiection and the time the count is start 6d, depending on the type of sample, I (units ccmsistent with A) ,

1 J

RT = elapsed real time, or the duration of the sample count, (units consistent with 1)

T, = sample deposition time, or the duration of analyte collection onto the sample media,(unit consistentwith A)

The LLD may be determined using installed radioanalytical software, if available in addition to determining the correct number of channels over which to total the l background sum, utilizing the software's ability to perform decay corrections (i.e. during sample collection, from sample collecbon to start of analysis and during counting), this allemate method will result in a more accurate determination of the LLD. ,

i It should be recognized that the LLD is defined as a before the fact limit and not as an after the fact limit for a particular measuremen'.

g:6Wn12r1-8. doc

! 12-41 l

)

l I

DRESDEN Revision 1.9 March 1999 TABLE 12.4-1 (Cont'd)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM l TABLE NOTATION

• Sampling and analyses shall also be performed following shutdown, startup, or a thermal power change exceeding 20 percent of rated tt'ermal power in i hour unless (1) analysis shows that the dose equivalent 1 131 concentration in the primary coolant has not increased more than a factor of 5, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.

• Samples shall be changed at least once per 7 days and the analyses completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after removal from the sampler. Sampling shall also be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following each shutdown, startup, or thermal power level change exceeding 20% of rated thermal power in one hour. This requirement does not apply if 1) analysis shows that the dose equivalent 1-131 concentration in the primary coolant has not increased more than a factor of 5, and 2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.

When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10.

~

W The ratio of sample flow rate to the sampled stream flow rate shall be known.

• The principal f,amma emitters for which the LLD spe6fication applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous t: missions, and Mn-54, Fe-59, Co-60, Zn-65, Co-58, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. Other peaks which are measurable and identifiable by gamma ray spectrometry, together with the above nuclides, shall be also identified and reported when an actual analysis is performed on a sample Nuclides which are below the LLD for the analyses shall not be reported as being present at . '1e LLD level for the nuclide.

• Analysis frequoney shall be increased to 1/ week if release rates exceed 1% of any applicable limit referenced in the ODCM, when added to Units 2 and 3 airbome effluents.

5.

61

(

j i i

l '

\

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.DRESDEN Revi: ion 1.9 March 1999 L

12.4.C gmous Effluents Bases i

. 1. Gaseous Effluents. Dose l

This Section is'provided to ensure that the dose at the unrestricted area boundary from gaseous effluents from the units on site will be within the annual dose limits of 10CFK20 for unrestricted areas. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area to annual average concentrations exceeding the limits specified in Appendix B, Table 2 of 10CFR20.1001-2402. The release rate limits restrict, at all times, l the corresponding gamma and beta dose rates above backgttund to an individual at or beyond the unrestricted area coundary to less than or equal to 500 mrem / year to the total body or to less than or equal to 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rr!.e above background via the ,

inhalation pathway to less than cc equal to 1500 mremQear. For purposes of calculation i doses resulting from airbome releaset the main chinney is considered to be an elevated release point and the reactor t'uilding ver,t stack is .:onsidered to be a mixed m9de ..

release point. .

2. Dose. Noble Gases This Section is provided to implemen', the .equirements of Sections ll.B. lil.A and IV.A of Appendix 1,10 CFR Part 50. The 00errhility Requirements implement the guides set forth in Sechon 11.3 of Appendix 1. The statements provide the required operating flexibility i and at the same time implemerd the. guides set forth in Sechon IV.A of Appendix i to

assure that the releases of rat.cacieve material in gaseous effluents will be kept "as low l l as is reasonably achievable." The surveillance requirements implement the requirements in Section Ill.A of Appendip that conformance with the guides of Appendix I is to be shown by calculationai procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, l

July 1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. .

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L

DRESDEN Revision 1.9 March 1999 12.4.C Gaseous Effluents Bases (Cont'd)

3. Dose. Radiciodines. Radioactive Materialin Particulate Form and Radionuclides Other than Noble Gases This Section is provided to implement the requirements of Sections ll.C, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Operability Requirements are the guides set forth in Section ll.C of Appendix 1. The statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the release 6 of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section ill.A of Appendix l that conformance with the guides of Appendix ! 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. The ODCM calculational methods approved "

by NRC for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109. m,

" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the .

Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1,-October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," ~

Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate limits for radioiodines, radioactive material in particulate form tsnd radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these limits were: 1) -

individual inhalation of abbome radionuclides,2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man and 3) deposition onto grassy .

areas where milk animals graze with consumption of the milk by man. .

4. Gaseous Waste Treatment The operability of the gaseous waste treatment which reduces amounts or concentrations of radioactive materials ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be operable when specified provides reasonable am urance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable". This specification implements the requirements or 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section ll.D of Appendix 1 to 10 CFR Part 50. ,

_l.

g:VTuarphybdcm\annexWresdenWn 12r1 8. doc 9

12-44 )

I

DRESDEN- Revbion 1.9 March 1999 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Monitonna Prooram i

Operability Reouirements

- 12.5.1. A The Radiological Environmental Monitoring Program shall be conducted as specified in Table 12.5-1.

AEEEsMity: At all times. i 6st!gn: i

1. With the Radiological Envircnmental Monitoring Prograr: 't ir j conducted as j specified in Tabh 12.5-1, prepare and submit to the Corn 1 the Annual j Radiological Environmental Operating Report required by Secbo. 46.0, e '

description of the reasons for not conducting the program as requred and the  ;

plans for preventing a recurrence. '

Deviations are permitted from the required sampling schedule if speciinens are l unobtainable due to hazardous conditions, seasonal availability, malfunction of sampling equipment, if a person / business who participates in the program goeis ou* of business or no longer can provide sample, or contractor omission which is corrected as soon as discovered.' If the equipment malfunctions, corrective .

accons shall be completed as soon as practical. If a person / business supplying  !

samples goes out of business, a replacement supplier shall be found as soon as  ;

possible. All deviations from the sampling schedule will be described in the  !

Anm:al Radiological Environmental Operating Report.-

2. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a speci6ed locabon exceeding the reporting levels of Table 12.5-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Technical Speciiketion 6.9.B, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose

• to a MEMBER OF THE PUBLIC is less than the calendar year limits of Section 12.3.A.2,12.4.A.2, or 12.4.A.3. When more than one of the radionuclides in Table 12.5-2 are detected in the sampling medium, this report shaP be submitted if:

concentration (1) . concentration (2) + ...>. 1.0 reporting level (1) reporting level (2)

When cadic nuclides other than those in Table 12.5-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annuai dose

• to A MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Section 12.3.A.2,12.4.A.2, or 12.4.A.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Section 12.6.1.

• The methodology and pararr,eters used to estimate the potential annual dose to a MEMBER OF THE g PUBLIC shall be indicated it: this report.

g:Vnurphy edcmunnexWresdenWn12ri-8. doc 12-45

DRESDEN Revtion 1.9 March 1999 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued)

3. If the sample type or sampling location (s) as required by Table 12.5-1 become(s) permanently unavailable , identify suitable attemative sampling media for the pathway of interest and/or specific locations for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program as soon as practicable. The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Prepare and submit controlled version of the ODCM within 180 days including a revised figure (s) and table reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of new location (s) for obtaining samples.

Surveillance Recuirements 12.5.1.B The radiological environmental monitoring program samples shall be collected pursuant to Table 12.5-1 from the specific locations given in the table and figure (s) in the ODCM.and shall be analyzed pursuant to the recuirements of Table 12.5-1 and the detection capabilities required by Table 12.N.

Bases 12.5.1.C The Radiologica! Environmental Monitoring Program required by this section provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix 1 to 10 CFR Part 50 and thereby supplements the radiviogical 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 the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring.

The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this penod, program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 12.5-3 are considered optimum for routine environmental measuremt.ats in industrial laboratories. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement.

Detailed dbcussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, LA., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem.

40, 586-93 (1968), and Hartwell, J.K., " Detection Limits for Radioanalytical Counting f Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975). I I

l g:Vnurphybdcrn\annexWresdenWn P O

12-46

[-J u .

l DRESDEN Revision 1.9 I M!rch 1999 l l

t 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued)

Interpretations 12.5.1.D Table 12.5-1 requires "one sample of each community drinking water supply downstream j of the plant within 10 kilometers." Drinking water supply is defined as water taken from j nvers, lakes, or reservoirs (not well water) which is used for drinking.

i l l

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7 DRESDEN Revision 1.9 March 1999 I I

TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS (1) Specific parameters of distance and direction from the centerline of the midpoint of the )

two units and additional descnption where pertinent, shall be provided for each and every sample locatien in Table 1.1-1 of the ODCM Station Annexes. Refer to NUREG-0133,

" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"

October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979.

(2) Far field samples are analyzed when the respective near field sample results are inconsistent with previous measurements cnd radioactivity is confirmed as having its origin in airbome effluents from the station, or at the discreticn of the Radiation Protection Director.

(3) Airborne particulate sample filters shall be ana'yned for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />  ;

or more after sampling to allow for redon and thoron daughter decay, if gross beta 'l activity in air particulate sampes is greater than 10 times the yearly mean of control ,, 1 samples, gamma isotopic analysis shall be performed on the individual samples. j (4) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station.

(5) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. Film badges shall not be used as dosimeters for measuring diremt radiation. '

The 40 locations is not an absolute number. The nurn'Jer of direct radiation monitonng O stations may be reduced according to geographicallimitations; e.g., if a station is adjacent to a lake,'some sectors may be over watsr thereby reducing the number of dosimeters whch could be placed et the indicated distances.' The frequency of analysis or readout for TLD systems will depend upon the characteristics 9f the specific system used and should be selected to obtain oWimum dose information with minimal fading.

(6) Groundwater samples shall be taken when this source is tapped fo. drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

(7) The " downstream" sample shall be taken in an area beyond but near the mixing zone.

The " upstream sample" shall be taken at a distance beyond significant influence of the discharge. Upstream samples in an estuary must be taken far enough upstream to be

~

beyond the station influence.

(8) If milking animals are not found in the designated indicator locations, or if the owners decline to participate in the REMP, all milk sampling may be discontinued.

(g) Biweekly refers to every two weeks.

(10) 1-131 analysis means the analytical separation and counting proceduro are specific for this radionuclide.

(11) One sample shall consist of a volume / weight of sample large ertough to fill contractor specified container.

5 gNnurgybdcrnunnexWreedenWn12r1-6. doc 12-53

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DRESDEN Revision 1.9 March 1999 TABLE 12.5-3 (Continued)

DETER. TION CAPABILITIES FOP ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS (1) The nuclides on this list are not the only nuclides intended to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.

(2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.

(3) The Lower Limit of Detection (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% probability with only 5% probability o' falsely concluding that a blank observation represents a "real" signal For a particular measurement system, which may include radiochemical separation, the LLD is defined as follows:

4.66 S, + 3/t, LLD =

(E)(V) (2.22) (Y) (exp (-ht)) -

4.66 S, LLD -

(E) (V) (2.22) (Y) (exp (-bt))

Where: 4.66 S >> 3/t, .

LLD = the "a priori" Minimum Detectable Concentration (picoCuries per unit mass or volume),

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

JTotal Counts

, is 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 radioactive decay constant for the particular radionuclide (sec), 4 g-Vnurphybdctn\annerWresdenWn12ri 8. doc O

12.-56 i

1

._________________________________________________]

1 DRESDEN Revision 1.9 ,

March 1999 l

l TABLE 12.5-3 (Continued) J DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS )

TABLE NOTATIONS t, =

counting time of tne background or blank (minutes), and at =

the elapsed time between sample collection, or end of the sample collection period, and the 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 a before the fact limit representing the capability of a (

- measurement system and not as an after the fact limit for a particular measurement.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. <

Occasionally, background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or )

other uncontrollable circumstances may render these LLDs unachievable, in such cases, the contributmg factors  !

shall be idenbfied and described in the Annual Radiological Environmental Operating Report. -

. Altemate LLD '.ti,edeiesy ,

An altemate methodology for LLD determination follows and is similar to the above LLD equation:

(2.71 + 4.65VB) Decay ,. .

LLD = i E q b Y t (2.22E06) lVO t- .

B = background sum (counts)

E = counting efficiency, (counts detected /disintegmtions) q = sample quantity,(mass or volume) b = abundance, (if applicable)

Y = frachonal rad;ed,wrui yield or collechon efficiency, (if applicable) . :, .

t = count time (minutes) 2.22E06 = number of disintegrations per minute per rc,, Curie (2.71 + 4.65VB) = k2 + (2k V 2 4 B), and k = 1.645.

(k=value of the t statistic from the single-tailed t distribution at a significance level of 0.95% and infinite degrees of freedom. This means that the LLD result represents a 95% detection probability with a 5% probability of falsely concluding that the nuchde present when it is not or that the nuclide is not present when it is.)

Decay = e* [lRT/(1 e"))[AT,/(1-e**)], (if applicable)

E sW#semmmet2r14 doc 12-57 M+

I

DRESDEN Revision 1.9 March 1999 TABLE 12.5-3 .

OETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS A = radioactive decay constant, (units consistent with at, RT and T.)

At = " delta t", or the elapsed time between sample collection or the migipoint of sample l l

collection and the time the count is started, depending on the type of sample, l l

(units con.sistent with A)

RT = elapsed real time, or the duration of the sample count, (units consistent with A) l T, = sample deposition time, or the duration of analyte collection onto the sample I media, (unit consistent with A)

~

The LLD may be determined using instal!ed radioanalytical software, if available. In addition to determining the correct numoer of channels over which to total the background sum, utilizing the software's ability to perform decay corrections (i.e. during sample collection, from sample collection to start of analysis and during coun'ung), this a!!emate method will result in a more accurate determination of the LLD.

It should be recognized that the LLD is defined as a before the fact limit and not as an after the fact limit for a particular measurement.

(4) If no drinking water pathway exists, the value of 15 pCill may be used.

(5) A value of 0.5 pCl/l shall be used when the animals are on pasture (May through October) and a value of 5 pCl/l l

shall be used at all other times (November through April). .

(6) This LLD applies only when the analytical separation and counting procedure are specific for this radionuclide.

(7) This LLD is the minimum allowable, however, vendors performing environmental sample analyses off-site will be required to meet an LLD of 200 pCill.

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DRESDEN Revision 1.9 March 1999

-12.5.2 Land Use Census

(

Ooerability Reauirements 12.5.2.A. A Land Use Census shall be conducted and shall identify within a distance of 10 km (6.2 miles) the locabon in each of the 16 meteorological sectors

• of the nearest milk animal, the nearest resdence",

and an enumeration of livestock. For dose calculation, a garden will be assumed at the nearest residence.

ADoiscability: At all times.

6gggn: *

1. With a Land Use Census identifying a location (s) that yields a calculated dose or dote commitment, via the same exposure pathway 20% greater than at a locabon from which samples are currently being obtained in accordance with Sechon 12.5.1, add the new locabon(s) within 30 days to the Radiological E:;vironmental Monitoring Program given in Chapter 11. The sampling location (s), excluding the control location, having the lowest calculated dose or dose C commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Submit in the next Annual Radiological Environmental Operating Report documentation for a change in thaODCM including a revised figure (s) and table (s) for the ODCM reflecting the new locahon(s) with information supporting the change in sampling locabons.

'This requirement may be reduced according to geographical limitations; e.g. at a lake site where . ,,, ,

some sector's will be over water. $3#g g "The nearest industrial facility shall also be documented if closer than the nearest residence.

Rafp Surveillance Reauirements *GF

. JW 12.5.2.8 The Land Use Census shall be conducted during the growing see:on, between June 1 and October 1, at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agricu!ture authonbes The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report.

Bases n.

J.:

12.5.2.C This r@ecificebon is provided to ensure that changes in the use of areas at and beyond the SITE 1 BOUNDARY are identified and that modificabons to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of this census. .

W Jg, This census satisfies the requirements of Sechori N.B.3 of Appendix 1 to 10 CFR Part 50. An annual j garden census will not be required since the licentse will assume that there is a garden at the nearest i resdence in each sector for dose calculat'ens. i 7:

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DRESDEN l Revision 1.9 l March 1999 l l

12.5.3 Intertaboratory Companson Procram Operability Recu'rements  !

l 12.5.3.A Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that correspond to samples required by Table 12.5-1.

Apolicability: At all times.

Action:

1. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

~

Surveillance Recuirements .;

12.5.3.B A summary of the results obtained as part of the above required intertaboratory Compadson Program shall be included in the Annual Radiological Environmental Operating Report.

Bases 12.5.3.C The requirement for participation in an Intertaboratory Comparison Program is provided to ensure that independent checks.on the precision and accuracy of the menurements of radioactive material in environmental samples matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix 1 to 10 CFR Part 50.

A W

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DRESDEN Revision 1.9 March 1999 12.6 ~4ECORDKEEPING AND REPORTING 1'2.6.1. Station Ooeratino Records ,

1. Records and/or logs relative to the following items shall be kept in a manner convenient for review and shall be retained for at least five years.

1.' Records and periodic checks, inspection and/or calibrations performed to venfy the surveillance requirements (Sc the applicable surveillance in the instrumentation, Liquid Effluents, Gaseous kiffluents, and Radiological Environmental Monitoring Seebons) are being met. All equipment failing to meet surveillance requirements and the corrective action taken shall be recorded

2. Records of radioachve shipments.

2. Records and/or logs relative to the following items shall be recorded in a manner convenient for review and shall be retained for the lifa of the plant.

1. Records of off-site environmental monitoring surveys.

2. Records of radioactivity in liquid and gaseous wastes released to the environment.

3. Records of reviews performed for changes made to the ODCM.

12.6.2. Reports

1. Radioachve Effluent Release Report I The Radioactrve Effluent Release Report covering the operation of the unit during the provous 12 months of opera 6on shall be sutxtutted to the Commesen prior to April 1 of each year. The ;eport shall include a summary of the quanttna of radioachve liquid and gaseous effluents and solid waste released from the unit.

The matenal provided shall be (1) consistent with the objectives outfitted in the ODCM aad PCP and (2) in conformance with 10 CFR Part 50.36a and Sechon IV.B.1 of Appendix i to 10 CFR Part 50.

2. Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operstmg Report covering the operation of the unit during the prevous calendar year shall be submitted prior to May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program frar the reporting period. The material provided shall be consistent with the objecbves in (1) the ODCM and (2) Sechons IV.B.2., IV.B.3, and IV.C of Appendix 1 to 10 CFR Part 50. A detailed listing of the requirement of the report is given below:

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DRESDEN Revtion 1.9 March 1999 12.6.2 Reports -(Cont'd)

(a) Results of environmental samp;ing summarized on a quarterly basis following the format of Regulatory Guide 4.8 Table 1 (December 1975);

(individual sample results will be retained at the station);

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. Summaries, interpretations, and analysis of trends of the results are to be provided.

(b) An assessment of the monitoring results and radiation dose via the principal pathways of exposure resulting from plant emissions of mdioactivity including the maximum noble gas gamma and beta air doses in the unrestricted area. The assessment of radiation doses shall be performed in accordance with the ODCM.

(c) Results of the census to determine the locations of animals producing milk for human consumption, and the pasture season feeding practices at dairies in the monitoring program.

(d) Tne reason for the omission if the nearest dairy to the station is not in the monitoring program.

(e) An annual summary of meteorological conditions concurrent with the releases of gaseous effluents in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.

(f) The results of the interlaboratory comparison program described in Section 12.5.3.

(g) The results of the 40 CFR Part 190 uranium fuel cycle dose analysis for each calendar year.

(h) A summary of the monitoring program, including maps showing sampling locations and tables giving distance and direction of sampling locations from the station.

3. Non-Routine Environmental Report (a) If a confirmed measured radionuclide concentration in an environmental sampling medium averaged over any calendar quarter sampling period excueds the reporting level given in Table 12.5-2 and if the radioactivity is attnoutable to plant operation, a written report shall be submitted to the Regional Administrator of NRC Regional Office, with a copy to the Director, Office of Nuclear Reactor Regulation, within 30 days from the end of the quarter. When more than one of the radionuclides in Table 12.5-2 are detected in the medium, the reporting level shall have been exceeded if IC/(RL),is equal to or greater than 1 where C is the concentration of the i* radionuclide in the medium and RL is the reporting level of radionuclide i.

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DRESDEN

, Revision 1.9 March 1999 12.6.2 Reports-(Cont'd) s (b) If radionuclides other than those in Table 12.5-2 are detected and are due to plant effluenM, a reporting level is exceeded if the potential annual dose to an individual is equal to or greater than the design objective doses of 10 CFR Part 50, Appendix 1.

(c) This report shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous affect.

12.6.3. Offsite Dose C=8minn Manual (ODCM)

1. The ODCM shall contain the rnethodology and pararneters used in the calculation of offsde doses due to radioachve gaseous and liquid erfluents and in the calculation of gaseous and liquid effluent monitonng Alarm / Trip set %ints and in the conduct of the Radiological Environmental Monitonng mssa. The GMM shall also contain (1) the Radioachve Effluent Controls and Radiological Environmental Monitoring Programs desenbed in Sechon 12.2 - 12.5 and (2)-

descriptior:s of the informabon that should be included in the Annual Radiological Environmental Operating and Radioachve Effluent Release Reports required by Sechona 12.6.2.1 and 12.6.2.2.

The ODCM shall be subject to review and approval by the Commission prior to initialimplementabon a.

2. Changes to the ODCM:

(1) Shall be docurnented and records of roiews performed shall be retained as required by Technical SpMacec6 6.14.A. This documentation shall contain:

(a) Sufficient information to suppoit the change together with appropriate analyses or evaluations justifying the change (s); and (b) A determination that the change will maintain the level of radioachve effluent control required by 10 CFR Part 20.1302,40 CFR Part 190,10 CFR Part 50.36a, and Appendix i to 10 CFR -

Part 50 and not adversely impact the accuracy or reliability of ,

effluent, dose or set point calculations, u~

(2) Shall be effechve after review and acceptance by Independent Technscal Revow and PORC/ Station Manager, on the date specified by the revision package.

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March 1999 12.6.3 Offsite Dose Calculation Manual (ODCMMCont'd) ,

(3) Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM or updated pages, if the Commission retains a controlled copy. If an entire copy of the ODCM is submitted, it shall be submitted as a part of or concurrent with the Radioactive Efflu6nt Release Report for the period of the report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.

12.6.4. Maior Chances to Radioactive Waste Treatment Systems (Liauid and Gaseous)  !

NOTE: This information may be submitted as part of the annual FSAR update.

1. Licensee initiated major changes to the radioactive waste systems may be made provided:

The change is reported in the Monthly Operating Report for the period in which the evaluation was reviewed by independent Technical Review. The discussion of each change shall contain:

(1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59; (2) Sufficient detailed information to support the reason for the change; (3) A detailed description of the equipment, components, and process involved and the interfaces with other plant systems; (4) An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the license application and amendments; (5) A comparison of the predicted releases of radioactive materials in liquid and gaseous effluen3 to the actual releases for the period in which the changes were made; (6) An estimate of the exposure to plant operating personnel as a result of the change; and (7) Documentation of the fact that the change was reviewed and found acceptable by Independent Technical Review.

2. The change shall become effective upon review and acceptance by Independent Technical Review.

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