ML20137C001

Odcm,Dresden Annex Revs 1.9 to Chapter 10, Radioactive Effluent Treatment & Monitoring, 1.2 to Chapter 11, Radiological Environ Monitoring Program & 1.3 to Chapter 12, Radiological Effluent Technical Standards

ML20137C001
Person / Time
Site:	Dresden
Issue date:	01/31/1997
From:	COMMONWEALTH EDISON CO.
To:
References
PROC-970131-01, PROC-970131-1, NUDOCS 9703240118
Download: ML20137C001 (97)

Text

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X244 ALL Document Control Desk Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission

/G Mail Station PI-137 Q Washington,DC 20555 ,

March 7,1997 ,

Attached is a revision to the Offsite Dose Calculation Manual, Dresden Annex, Chapters 10 through 12. Please update your manual as follows:

j Remove:

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Dresden Chapter 10, Revision 1.8 Dresden Chapter 11, Revision 1.1  !

Dresden Chapter 12, Revision 1.2 in.ati:

Dresden Chapter 10, Revision 1.9 Dresden Chapter 11, Revision 1.2 Dresden Chapter 12, Revision 1.3 Please sign below indicating your manual has been updated and that your controlled copy number

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Chapter 10 Change Summary l ODCM Revision 1.9, January 1997 i l

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Page Change Descrintion l i

10-1 Updated revision number 10-3 Added descriptive information in parentheses to Section 10.1.2.4.

i 10 Changed statement regarding the location of the definitions of parameters in equations 10-1 and 10-2. The definitions are found throughout Section A.1 of Appendix A and not in only one location as previously stated.

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!' DRESDEN Revision 1.9

January 1997 5l i DRESDEN ANNEXINDEX 1,

CHAPTER 10

REVISION 1.9 i,

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DRESDEN Rsvision 19

, J1nuiry 1997 j CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS PAGE 10.1 AIRBORNE RELEASES . 10-1

1. System Desenption. .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 Effluent Monitors.. 10-2

4. Reactor Building Ventilation Monitors . 10-3

5. Condenser Air Ejector Monitors . 10-3

6. Isolation Condenser Vent Monitor., 10-3

3. Alarm and Trip Setpoints.. 10-3

1. Setpoint Calculations., 10-3

1. Reactor Building Vent Monitors.. 10-3

2. Condenser Air Ejector Monitors . 10-3

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

2. Release Limits.. . . 10-4

3. Release Mixture . 10-5

4. Conversion Factors.. . 10-5

5. HVAC Flow Rates . . 10-6

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

5. Dose Projections.. . 10-6 I

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DRESDEN Rsvision 19 l JInuary 1997 l CHAPTER 10 -

RADIOACTIVE EFFLUENT TREATMENT AND MONITORING i TABLE OF CONTENTS (Cont'd)

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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 Emuent Monitor.. 10-7

2. Units 2 & 3 Service Water Emuent Monitors.. 10-7

3. Chemical Cleaning Facility Service  ;

Water Emuent Monitor.. 10-7

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

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

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

2. Units 2 & 3 Service Water Emuent Monitor.. 10-9

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

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

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

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 Emuents from Common Release Points.. . 10-10

5. Projected Doses for Releases . 10-10 10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM . 10-10 gM10ri-9 doc 10-iii  !

DRESDEN Revision 1.9 Januiry 1997 CHAPTER 10 LIST OF FIGURES NUMBER PAGE 10-1 Simplified Gaseous Radwaste and Gaseous Effluent Flow Diagram 10-11 10-2 Simplified Gaseous Radwaste and Gaseous Effluent Flow Diagram 10-12 10-3 Simplified Liquid Radwaste Processing and Liquid Effluent Flow Diagram 10-13 10-4 Simplified Solid Radwaste Processing Diagram 10-14 l

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DRESDEN Rsvision 1.9 Jtnutry 1997 I CHAPTER 10 I. 1 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES i

10.1.1 System Description 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.

l Each airbome release point is classified as stack, vent, or ground level in accordance with l the definitions in Section 4.1.4 and the results in Table A-1 of Appendix A. The principal release points for potentially radioactive airbome effluents and their classrfications are as follows:

For Dresden 1, the plant chimney (a stack release point).

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 The condenser offgas treatment system is designed and installed to reduce radioactive

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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.

-l 10.1.1.2 Ventilation Exhaust Treatment System Ventilation exhaust treatment systems are designed and installed to reduce gaseous radioiodine or radioactive matenal in particulate form in selected effluent streams by passing i ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters prior to l release to the environment. Such a system is not considered to have any effect on noble gas effluents. The ventilation exhaust treatment systems are shown in Figures 10-1 and 10-2.

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

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DRESDEN Rcvision 19 l Januiry 1997 10.1.2 Radiation Monitors 10.1.2.1 Unit 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 SPlNG continuously monitors the final effluent from the Units 2/3 chimney.

The monitor has isokinetic sampling, gaseous grab sampling, 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.

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No automatic isolation or control functions are performed by this monitor. Pertinent I information on this monitor is provided in the Dresden UFSAR Section 11.5. l In addition to the primary 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 Effluent 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 performed by this monitor.

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DRESDEN Rsvision 19 Janutry 1997 ,

10.1.2.4 Reactor Buik$ing 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 initiate 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.

i 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 monitors automatically activate an interval timer which in turn initiates closure of an air operated valve, thus terminating the release.

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

10 1.2.6 isolation Condenser Vent Monitor The monitor continuously monitors radioactivity in the affluent from the isolation condenser vent. No control device is initiated by this monitor.

Pertinent 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 por MWt (a2.5E5pCi/sec) and the ,

' high alarm is established at s 50pCi/sec per MWt (a1.25E5pCi/sec).

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10.1.3.1.3 Units 2/3 Plant Chimney Radiation Monitor The setpoint is estabhshed at a count rate eni.ef-Mng to no greater than 105,000 pCi/sec.

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DRESDEN Rouiston 9 9 Janucry 1997 10.1.3 2 Release Limits Alarm and tnp 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 soiving Equations 10-1 and 10-2 for the total allowed release rate, Qu.

(1.11) Z( f,[Q.5[+ QuQ) < 500 mrem /yr (10-1)

E ((L,f,[(LO), Q. exp(-A,R/3600u,)

+ (X/O),Ouexp-(A,R/3600u,)] (10-2)

+(1.11Xf)[Q.S, + Q V,])

< 3000 mrem /yr  !

The summations are over noble gas radionuclides i. j f, Fractional Radionuclide Composition ,

The release rate of noble gas radionuclide i divided by the total release rate of all I noble gas radionuclides. I l

O. Total allowed Release Rate, Stack Release

( Ci/sec) l The total allowed release rate of all noble gas radionuclides released as j stack releases.

Ou Total Allowed Release Rate, Vent Release

[ Ci/sec] .

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

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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 released in gaseous effluents (see Section A.1.3.1 of Appendix A). Equation 10-2 is based on Equation A-9 of Appendix A and the RETS restriction on skin dose rate (3000 mrem /yr) due 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 Rsvision 1.9 I

Jtnuary 1997 10.1.3.3 Release Mixture  !

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. In the determination of alarm and trip setpoints the radioactivity mixture in the exhaust air is i assumed to have the following compositions.

Reactor building vent effluent monitors.

The mixture used for the GE monitors is taken from a representative isotopic analysis of the 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 a pseudo-noble gas radionuclide. l Condenser air ejector monitor.

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The mixture used for this monitor is taken from a representative isotopic analysis of  !

noble gases collected at the recombiner outlet during plant operation, since the last alarm setpoint calculation.

I Units 2/3 plant chimney monitors. l 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 SPING is assumed to be a single pseudo-noble gas radionuclide.

10.1.3.4 Conversion Factore The converson factors used to establish gaseous effluent monitor setpoints are obtained as follows.

Reactor building vent effluent monitor.

For the GE monitors, the isotopic analysis in Secton 10.1.3.3 and the monitor reading (in mR/hr) at the time of the analysis or nommel response of detector are used to  !

establish the conversion factor in mR/hr per Ci/cc or pCi/ft'. For the SPING the l converson factor is based on the 0.8 MeV gamme of the pseudo-noble gas radionuchde Condenser air ejector monitor.

The isotope 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 1 pCi/cc or pCi/ft*,

i Units 2/3 plant chimney monitors 4

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 factor in CPS per pCi/cc or pCi/ft'. For the SPING thp conversion factor is based on the 0.8 MeV gamma of the pseudo-noble gas radionuclide. '

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DRESDEN Revision 19 J:nuIry 1997 10.1.3.5 HVAC Flow Rates The HVAC exhaust flow rates are obtained fror'1 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 l 10.1.4 Allocation of Effluents from Commor; Release Points Radioactive gases, particulates, and iodines released from the Unit 1 chimney originate from Unit 1 only. However, radioactive gaseous effluents released from Units 2/3 are comprised of contributions from both units. Estimates of noble gas contnbutions from Units 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 specifically is not as practical and is influenced greatly by in-plant leakage. Under normal operating conditions, allocation is made using reactor coolant iodine activities. During unit shutdowns or periods of known major in-plant leakage, the apportionment is adjusted 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 calculated in accordance with the RETS.

10.2 LlOUID RELEASES 10.2.i 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 reduct,1g the total radioactivity prior to reuse or release to the environment. The system is described in the Dresden UFSAR Section 11.2.

10.2.1.1 Unit 1 Storage Tanks Liquid radioactive effluents are not relecM *iom 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

'There are three waste sample tanks (33,000 gallons each) which receive water from the liquid waste treatment system. These tanks are transferred to the waste surge tank for discharge to the Illinois River via the discharge canal.

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i DRESDEN Ravision 1.9 J:nuity 1997 10 2.1.3 Units 2/3 Floor Drain Sample Tanks l j

O 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  !

for discharge to the lilinois River via the discharge canal.

10.2.1.4 Units 2/3 Waste Surge Tank 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

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i 10.2.2.1 Liqui 1 Radwaste Effluent Monitor ~

The monitor is used to monitor all releases from the waste surge tank. On high alarm. a grab sample of the 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 flow or high flow discharge line valves.

Pertinent information on the monitor and associated cont'ol devices is provided in the  ;

Dresden UFSAR Section 11.5.

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

p Pertinent information 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 cleaning facility by the monitor, On high alarm the release is terminated by manually 4 initiating closure of the isolation valve.

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No control device is initiated by this monitor.

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DRESDEN R:, vision 19 Januiry 1997 10 2.3 Alarm and Trip Setpoints 10.2.3.1 Setpoint Calculations Alarm and trip setpoints of liquid effluent monitors at the pnncipal release points are  !

established to ensure that the limits of 10CFR20 are not exceeded in the unrestncted area. '

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

P g K x (EC[/E(C[/DWC,))x((F' + FL )fF; )

P Release Setpoint [ cpm]

l CT Concentration of radionuclide iin I

[ Ci/ml]

the release tank l l

F;= 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 Calibration constant (cpm /pci/ml]

DWC, Derived Water Concentration (also referred to as Emuent Concentration Limit, ECL) of Radionuclide i [ Ci/ mil 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 DWCi may be used.

1. Dilution Flow [gpm)

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

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DRESDEN Ravision 1.9 JInuiry 1997 10.2.3.1.2 Units 2 & 3 Service Water Effluent Monitor The monitor setpoint is established at two times the background radiation value.

'10.2.3.1.3 Chemical Cleaning Facility Service Water Effluent Monitor 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 Prior to each batch release, a grab sample is obtained.

The results of the analysis of the sample determine the discharge rate of each batch as follows:

I== = 0.1(F'/E(C/DWC))

(10-4)

The summation is over radionuclides 1.

0.1 Reduction factor for conservatism.

F'== Maximum Permitted Discharge Flow Rate [gpm]

The maximum permdted flow rate from the redweste discharge tank. Releases are not permdted if the calculated discharge rate, F.' . , is less than 250 gpm.

F' Dilution Flow [gpm]

Cd Concentrabon of Radionuclideiin (pCi/mq the Release Tank The concentrabon of radioactivity in the radweste discharge tank based on measurements of a sample drawn from the tank.

DWC, Derived Water Concentrabon of Radionuclide 1 [pCi/ml]

The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to 10CFR20.10012402. When technical specifications allow, ten *(10) times the DWCi may be used.

8 Dresden Staten may use ten (10) upon Techncal SpeceAceton approval. Untd then, one (1) tunes the DWC must be used.

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DRESDEN Rsvision 19 J nu ry 1997 10.2.3.3 Release Limits i 1

Release limits are determined from 10CFR20. Calculated maximum permissible discharge rates are divided by 10 to ensure that applicable denved water concentrations ,

(DVC) are not exceeded. t 10.2.3.4 Release Mixture L

l For the liquid radwaste effluent monitor, the release mixture used for the setpoint i

determination is the radionuclide mix identified in the grab sample isotopic analysis. I For all other liquid effluent monitors, no release mixture is used because the setpoint is established at "two times background." l 10.2.3.5 Conversion Factors I

The readout for the liquid radwaste effluent monitor is in CPM. The calibration constant is based on the detector sensitivity to Co-60. i 1

l The readouts for the Units 2 & 3 service water effluent monitors are in pCi/ml. The calibration constants are based on the detector sensitivity to Co-60.

l 10.2.3.6 Liquid Dilution Flow Rates 1

The dilution flow is determined using the installed flowmeter in the discharge canal.  ;

10.2.4 Allocation of Effluents from Common Release Points Radioactive licNid effluents released from the release tanks are comprised of contributions f,om all three units. Under normal operating conditions, it is difficult to apportion the rcdioactivity 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.  ;

Figure 10-4 is a simplified diagram of solid radwaste processing.

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I Dresden Station Chapter 11 Change Sumary O

ODCM Revision 1.2, January 1997 EA9ft 111tm 11-1 Removed page index. Individual pages ro longer updated.

11-2 Removed D-05 and footnote. D-05 deleted in 1995 as indicated 1 by the footnote. Removed asterisk by D-45 indicating it replaced D-05 in 1995.

11-3 Updated location of TLD's 110-3 and 110-4 to reflect current placement. ,

11-6 Added D-50 as a unit 2/3 Cooling Water Sample location.

11-7 Changed Director title due to new department responsibilities.

11-12 Deleted D-05 from map. Location no longer exists.

11-13 Added D-50 location due to new cooling water sample. Updated )

locations for TLD's 110-3 and 110-4 based on current location.  !

11-14 Removed an incorrect milk location from the map; two 1 different locations were given on the map for D-26.  !

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CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l TABLE OF CONTENTS E.6.Qf 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i11  !

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,G CHAPTER 11 LIST OF TABLS NUMBER ILTg M

11-1 Rodiological Environmental Monitoring Program i1-2 I 11-2 Reporting Levels for Radiooctivity Concentrations in Environmental Somples 4

11-8 11-3 Detection Capabilities for Environmental Samplo Anolysis 1I-9 11-iii

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DRESDEN Revision 1.2 January 1997 CHAPTER 11 LIST OF FIGURES NUMBER TjiLE g 11-1 Fixed Air Sampling and TLD Sites and Outer Ring TLD Locations 11-12 11-2 inner Ring TLD Locations and Near 11-13 Station Water Sample Locations Il-3 Milk Sample Locations and More Distant Water Sample Locations 11-14 O

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( CHAPTER 11 I i

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l i

1 The parameters for the radiological environmental monitoring program to be performed in the i environs around Dresden Nuclear Power Station ore given in Tcble 11-1.  !

i

' Figure 11-1 shows the 17 fixed air sampling sites and TLD locations; also shown ore the outer

{

ring TLD locations. Figure 11-2 shcws near station water sample locations and the inner ring TLD j locations. The TLDs are coded as follows:  :

XYY-N i,

X = 1, means inner ring: ,

X = 2. means outer ring: and l

l l YY-N is on identification code.

Figure 11-3 shows the milk sample locations and more distant water sample locations.

The reporting levels for radiooctivity concentrations in environmenial somples are given in  ;

Toble 11-2. The practicallower limits of detection for this program are given in Table 11-3.

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DRESDEN Revision 1.2 January 1997 Toble 11-1 Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency ond/or Somote Somolino or Monitorino LocationsU Collection Frecuency of Anolvsis

1. Aiborne o. Onsite and Hear Field b Continuous sampler operation Radiolodine Canister:

with particulate fifer Radiolodine and D-01 Onsite Station 1. 0.6 mi NW exchange weekty and radio- l-131 onalysis bb Particulates (1.0 km Q) iodine canister exchange weekly c D-02 Onsite Station 2. 0.3 mi NE biweekly c (0.5 km C)

D-03 Onsite Station 3. 0.4 mi S Porticulate Somoler:

(0.6 km J)

D-04 Collins Road,0.9 mi W Gross beta onolysis (1.4 km N) followingfilter D-06 WiB County Rood.1.4 mi SE change (2.2 km G)

D-45 McKinley Woods Road.1.5 mi ENE (2.4 km D)

Samplino Train:

Test and maintenance weekly

b. For Field b Continuous sompter operation Radioiodine Canister:

with particulate filter D47 Clay Products. 2.0 mi S exchange weekly and radio- F131 when analyses (3.2 km J) lodine conister exchange are mode

• D48 Proirie Parks. 4.0 mi SW biweekly c (6.4 km L)

D-09 Cool City. 7.5 mi S (12.0 km J) Porticulate Somoler:

D-10 Goose Lake Village. 3.8 mi SSW (6.1 km K) Gross belo whg**n analy-D-11 Morris. 8.0 mi WSW (12.9 km M) ses are made D-12 Lisbon.10.0 mi NW (16.1 km Q)

I 11-2

. . .. ._... . _. . . . . . - - ~ - . - - . _ - . . .. ~ ---. _ ... - -~. . . .. . . - -- --

O O  !

.?

r DRESDEN Revision 1.2 January 1997 l Toble 11-1 (Cont'd)

Radiological Environmental Monitoring Progrom Exposure Pathway Sompling or Type and Frequency i ond/or Somole Samolino or Monitorino Locotions Collection Frecuency of Analysis  ;

1. Airborne (Cont'd) D-13 Minooko 4.5 mi N (7.2 km A) Somolino Train:

D-14 Channohon. 3.5 mi NE (5.6 km C)

D-15 Joliet.12.5 rni NE (20.1 km C) Test and maintenance D-16 Bwood,8.0 mi E (12.9 km E) weekly D-17 Wilmington,8.0 mi SE (12.9 km G) i

2. Direct Rodiation o. At Air Somohno Sites Quarterly Gamma dose quarterly i

Some locations os fixed air sampling ['

locations in item 1.

b. Inner Rina' D-101-1, 1.0 mi N (1.6 km A)

D-101-2, 1.0 mi N (1.6 km A)

D-102-1,1.3 mi NNE (2.1 km B)

D-102-2, 1.3 mi NNE (2.1 km B)

D-103-1, 1.2 mi NE (1.9 km C)

D-103-2, 1.2 mi NE (1.9 km C)

D-104-1,1.5 mi ENE (2.4 km D) l D-104-2, 1.5 mi ENE (2.4 km D)

D-105-1, 1.4 mi E (2.3 km E)

• D-105-2, 1.4 mi E (2.3 km E)  ;

D-106-1. 0.9 mi ESE (1.4 km F)

D-106-2, 0.9 mi ESE (I.4 km F)

• D-107-1, 1.3 mi SE (2.I km G)  ;

D-107-2, 1.3 mi SE (2.1 km G) r D-106-1,1.9 mi SSE (3.1 km H)

D-108-2. 1.9 mi SSE (3.1 km H)

D-109-1, 0.8 mi S (1.3 km J)

D-109-2. 0.8 mi S (1.3 km J) ,

D-I 10-3 0.8 mi SSW (1.3 km K)  ;

D-110-4. 0.8 mi SSW (1.3 km K) 1 I-3

DRESDEN Revision 1.2 January 1997 Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program Exposure Pathway Sompting or Type and Frequency and/or Somote Somolina or Monitorino Locotions* Collection Frecuency of Anotysis

2. Direct Radiation D-111-1, 0.6 mi SW (0.97 km L)

(Cont'd) D-Ill-2, 0.6 mi SW (0.97 km L)

D-Il20-1,0.8 mi WSW (1.3 km M)

D-112o-2,0.8 mi WSW (1.3 km M)

D-Il3-1, 0.9 mi W (1.4 km N)

D-113-2, 0.9 mi W (1.4 km N)

D-114-1, 1.0 mi WNW (1.6 km P)

D-Il4-2.1.0 mi WNW (1.6 km P)

D-115-1, 0.8 mi NW (1.3 km Q)

D-115-2. 0.8 mi NW (1.3 km Q)

D-116-1 l.0 mi NNW (1.6 km R)

D-116-2. 1.0 mi NNW (1.6 km R)

c. Outer Rino*

D-201-1, 4.5 mi N (7.2 km A)

D-201-2. 4.5 mi N (7.2 km A)

D-202-1, 5.0 mi NNE (8.0 km B)

D-202-2, 5.0 mi NNE (8.0 km B)

D-203-1, 4.5 mi NE (7.2 km C)

D-203-2, 4.5 mi NE (7.2 km C)

D-204-1, 5.0 mi ENE (8.0 km DJ D-204-2. 5.0 mi ENE (8.0 km D)

D-205-1. 4.2 mi E (6.8 km E)

D-205-2. 4.2 mi E (6.8 km E)

D-206-1. 3.5 mi ESE (5.6 km Fl D-206-2, 3.5 mi ESE (5.6 km Fj D-207-1, 4.5 mi SE (7.2 km G)

D-207-2, 4.5 mi SE (7.2 km G)

D-208-1, 5.0 mi SSE (8.0 km H)

D-208-2. 5.0 mi SSE (8.0 km H)

D-209-l. 5.0 mi S (8.0 km J)

D-209-2. 5.0 mi S (8.0 km J)

I 1-4

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)

DRESDEN Revision 1.2 January 1997 Table 11-1 (Cont'd)'

Radiological Environmental Monitoring Program Exposure Pathway Sompiing or Type and Frequency and/or Somole Samolino or Monitorino Locations Collection Frecuency of Analysis

2. Direct Radiation (Cont'd) D-210-1, 4.8 mi SSW (7.7 km K)

D-210-2. 4.8 mi SSW (7.7 km K)

D-211-1, 5.0 mi SW (8.0 km L)

D-211-2, 5.0 mi SW (8.0 km L)

D-212-3, 6.0 mi WSW (9.7 km M)

D-212-4, 6.0 mi WSW (9.7 km M)

D-213-1, 4.5 mi W [7.2 km N)

D-213-2, 4.5 mi W (7.2 km N)

D-214-1, 4.5 mi WNW (7.2 km P)

D-214-2, 4.5 mi WNW (7.2 km PJ D-215-1, 5.1 mi NW (8.2 km Q)

D-215-2, 5.1 mi NW (8.2 km Q)

D-216-1, 4.8 mi NNW (7.7 km R)

D-216-2, 4.8 mi NNW (7.7 km R)

3. Waterborne'8

c. Surface D-21, lilinois River of EJ&E RR Weekly Gomma isotopic on Bndge, I mi WNW (1.6 km P) monthly composite D-22, Illinois River upstreom of Monis Water Works. 8 mi WSW (12.9 km M)

b. Lake Water D-28 Dresden Pool of Illinois River, Weekly Gomma isotopic and (

0.5 mi NW (0.8 km Q) gross beta onolysis D-34A, Cooling Loke, Dresden Road Crossing. 2.6 mi S (4.2 km J)

D-348. Cooling Loke, County l_ine Crossing. 3.0 mi SSE (4.8 km H)

c. Ground / - D-23. Thorsen Well. 0.7 mi S Quarterly Gross beto. gross Well Water (1.1 km J) olpho and trifium D-35 Dresden Lock & Dom. 0.5 mi NW (0.8 km Q) 1 I-5

- - - - ~ - - - - - , ,, - -- -, , ,- -, ,. ,, -,~a- , ,

DRESDEN Revision 1.2 January 1997 Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Somote Somotino or Monitorino locations" Collection Frecuency of Anotysis

3. Waterborne'8. (Cont'd)

d. Coolino Water D-18. Inlet. Unit 1. of Station Weekly Gross beta onolysis Somole D-50. Inlet. Unit 2/3. of Station weekly l D-19. Discharge. Unit 1. of Station D-20. Discharge. Unit 2/3. of Station

e. Shoreline Sediments D-27. Dresden Lock & Dom. 0.5 mi NW Annually Gomma isotopic (0.8 km Q) annually

4. Incestion' O. Milk D-25. Vince Biros Form.11.5 mi SW Weekly: May to October I-131 onalysis on each (18.5 km L) Monthly: November to sa m ple D-26. Holpin's Doiry.16 mi S April (25.7 km J)

b. Fjsh D-28. Dresden Pool of Illinois Semionnua!!y Gammo isotopic onoty-River. 0.5 mi NW (0.8 km Q) sis on edible portions of each somple.

5. Land Use Census

o. Milch Animals 1. Site boundary to 2 miles Annually during Enumeration by a grazing season door-to-door or equivalent counting technique.

2. 2 to 5 miles Annually during Enumeration by using grazing season referenced information from county ,gricultural agencies or other reliable sources.

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DRESDEN Revision 1.2 January 1997 Tobie 11-1 (Cont'd) ,

Radiological Environmentol Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Somote Samolino or Monitorino locations

• Collection Frecuency of Analysis -

5.Lond Use Census 3. At dories listed in item 4.o. Annuolly during inquire os to feeding (Cont'd) grazing season practices:

a. Posture only. ,

b. Feed and chop only. [

c. Posture and feed; if both, ask former to esti- .

mote fraction of food from posture: <25%.

25-50%. 50-75%.

or >75%.

b. Nearest Resident . In oli 16 sectors up to 5 miles. Annuolly

• See Tobie D-16 for definitions of sector codes used with kilometer distances.

• See Figure i1-1. " Fixed Air Sampling and TLD Sites and Outer Ring TLD Locations.'

• Biweekly means every two weeks. i

A gamma isotopic onolysis shall be performed wherever the gross belo concentration in a sample exceeds by five times (5x) the overage concentration of the preceding colendor quarter for the sompie location.

• For field samples are onolyzed when near field results are inconsistent with previous measurements and i radioactivity is confirmed as having its origin in orborne effluents released from the station er at the discretion of the Rodiation Protection Director.

' See Figure Il-2 " Inner Ring TLD Locations and Neor Station Water Sample Locations."

• See Figure 11-3. " Milk Sample Locations and More Distant Water Somple Locations."

Il-7

_ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _..__ ________ ________ -__ _ _ . _ _ _ _ __ _ _ _ . _ _ _ _ _ _ ~ _ . _ _ _ _ _ _ _ _ _ ___

DRESDEN Revision 1.2 January 1997 Table 11-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples Water Airborne Particulate Fish Milk Food Products Analysis (DCi/L) or Goses foci /m'l IoCi/ko. well foci /L1 f DCi/ko. well H-3 20.000 Mn-54 1.000 30.000 Fe-59 400 10.000 Co-58 1,000 30.000 Co-60 300 20.0C0 Zn-65 300 20.000 Zr-Nb-95 400 l-131 2 0.9 3 100 Cs-134 30 10 1.000 60 2.000 Cs-137 50 20 1.000 70 2.000 Bo-La-140 200 300 For drinking water samples. This is 40 CFR Port 141 value.

I l-8

O O O DRESDEN Revision 1.2 '

January 1997 Table 11-3' Detection Copobilities for Environmental Sompie Analysis Lower Limit of Detection fLLDi*

Water Nrborne Portculate Fish Milk Sediment Analysis foci /L) or Goses IoCi/m'l IoCi/ko. well foci /L) loci /ko drvl Gross betab 'S 0.01 1,000 5 2.000 Gomma isotopic 20 0.01 200- 20 200' l-131 5 0.10 100* 5*

Cs-134 10 100 10 Cs-137 - 10 100 5 H-3 200 II-9

i DRESDEN Revision 1.2 January 1997 Table 11-3 (Cont'd)

Detection Copobilities for Environmental Somple Anolysis Notes:

1. Other radionuclides which are measurable and identifiable by gamma roy spectrometry, together with the nuclides indicated in Toble 11-3, shall also be identified and reported when on octual onolysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported os being present at the LLD level for that nuclide.

Footnotes:

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

For a porticular measurement system (which may include radiochemical separation)

(4.66) , (SJ LLD =

( A) - (E) ' (V) - (2.22) - (Y) (exp(-ht)) - (t)

LLD is the g priprilower r limit of detection for a blank somple or background onolysis as defined above (as pCi per unit mass or volume).

5, is the square root of the background count or of a blank somple count; it is the estimated stondord error of a background count or a blank sample count as oppropriate (in units of counts).

E is the counting efficiency (as counts per disintegration). A is the number of gammo rays emitted per disintegration for gommo roy radionuclide anolysis (A = 1.0 for gross cipha and tritium measurements).

V is the somple size (in units of moss or volume).

2.22 is the number of disintegrotions per minute per picocurie.

Y is the fractional radiochemical yield when applicable (otherwise Y = 1.0).

A is the radioactive decoy constant for the particular radionuclide (in units of reciprocal minutes).

at is the elapsed time between the midpoint of somple collection and the stort time of counting. (at = 0.0 for environmental samples and for gross cipha measurements.)

11-10

. ..- . . _ - . . ~.- -. - .- - . - - - , _ , . - . , .. -

DRESDEN Revision 1.2 January 1997 '

i

e Table 113 (Cont'd) l Detection Copobilities for Environmental Sample Analysis 1

Notes (Cont'd):  !

t is the duration of the count (in units of minutes).

The value of S, used in the calculation of the LLD for a detection system shall be based on on octual observed background count or a blank sample count (as appropriate) rather than on on unverified theoretically predicted value. Typical values of E, V, Y, t, and at shall be used in

' the calculation.

For gammo roy radionuclide onolyses the background counts are determined from the total counts in the chonnels which are within plus or minus one FWHM (full width at halt maximum) of the gamma ray photopeak energy normally used for the quantitative onolysis for that radionuclide. Typical values of the FWHM shall be used in the calculation.

The LLD for all na osurements is defined as on g gdgd (before the fact) limit representing the capability of a truosurement system and not as on g costeriori (ofter the fact) limit for o particular sample measurement.

• Referenced to Cs-137.

• For thyroid.

j

• 0.5 pCi/L on samples collected during the posture season. l I

9 O

DRESDEN Revision 12 January 1997 i ' 1 l

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-. . - . . . . _ _ - . - . . ~ . . . . . . . - - . . . . . . . . _ . - . - . . . . - .

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1 1

Dresden Station

! Chapter 12 Change Summary 00CM Revision 1.3, January 1997

EA92 11AIB 12-11 Revised revision index to 1.3 k 12-111 Modified section titles to be consistent with text.

Added the four existing sections under 12.3.C.

l 12-iv Added the 4 existing sections under 12.4.C and the three t j existing sections under 12.5.C.

j. 12-5 hodified headings to be consistent with table of contents.

k 12-6 Capitalized " Unit" in 12.2.B.I.4. Modified headings to be l consistent with the table of contents.

i 12-7 Added footnote indicating discharge is not allowed if

actions cannot be performed.

! 12-9 Added footnote indicating discharge is not allowed if actions cannot be performed.

- 12-13 Changed Reactor Building Vent Exhaust Duct Radiation i Monitor minimum channels to 2 from 1 and Applicable

[ Operational Modes to 1, 2, 3, and when handling

irradiated fuel in secondary containment from "at all times". This is consistent with Upgraded Tech Specs.

12-14 Deleted 7 day clock and reporting requirement for j Action 20. Upgraded Tech Specs do not address Low l Range 2(3) Chimney noble gas monitoring and change is

] consistent with current Tech Specs. Action 24 was changed a to be consistent with current Tech Specs.

i 12-16 Offq'as monitor Functional Test frequency changed from l- dai y to quarterly and Instrument check-changed from 1 quarte."1y to daily to comply with current Tech Specs.

Reactor Building Vent Exhaust Duct Radiation Monitor

! surveillance frequencies shortened and applicable modes

changed from "at all times" to modes 1, 2, 3, and when

. handling irradiated fuel. This is consistent with upgraded j Tech Specs.

4 12-40 Added a "d" on the end of " describe" in last sentence of 12.5.A.2 to correct grammar.

12-41 Added word " Program" to title of 12.5.B for consistency j: among other section titles.

12-50 Inserted the symbol "E" in place of an "s" to represent the requirement for summing factors.

)o J

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Revision 1.3 January 1997 O

CHAPTER 12.0 SPECIAL NOTE Until the Unit 2 & 3 Radiologk:al Efnuent Technical Spacf&6 haw been approved by the Nuclear Regdatory Conmssion, the requirements of the Technical Speofications shall take prece4xx. over this chapter, should any dfferences occur.

O 12-1 O

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, DRESDEN Revision 1.3

{ January 1997 4

DRESDEN ANPEX INDEX i

CHAPTER 12 Revision 1.3 i,

4 I;

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DRESDEN Revision 1.3 January 1997 1 1

CHAPTER 12 RADIOLOGICAL EFFLUENT TEC)MCAL STANDARDS (RETS)

TABLE OF CONTENTS PAGE 12.1 DEFIMTIONS 12-1 12.2 INSTRUlWENTATION 12-5 A Radioactie Uquid Emuent Monitoring Instrumentation 12-5 '

1. Radioactive Uquid Emuent Moritonng instrumentation Operability 12-5

2. Radioedne Uguid Emuent Monitoring Instnironioini Sunellance 12-5 B. Radioactive Gaseous Emuent Monitoring Instrumentation 12-5

1. Radioactne Gaseous Emuent Monitoring instrumentatico Operability 12-5 1

2. Radoadne Gaseous Emuent Monitoring instrumentation Sunellance 12-6 I C. Uqud and r,aua = Emuents Instrumentation Bases 12-18 12.3 UQlAD EFFLUENTS 12-19 l A Uqud Emuents Umits and Reporting Operability 12-19

1. Ccresaiuiin Unrestrided Areas 12-19 1

2. Dose frorn Uqud Emuents 12-19 I

3. Dose Prolectons 12-20

4. Uqud Radioadne Waste Treatment System 12-21

5. System Operability and Plant Opa aiu 6 12-21 l B. Uguid Emuents Suneillanm 12-21

1. Ccre4.iniin Unrestricted Areas 12-21

2. Dose from Ugud Emuents 12-22

3. Dose Projedmns 12-22 C. Uqud Emuents Bases 12 27

1. Ccre 4aib7 12-27

2. Dose 12-27  !

3. Uquid Weste Treatment 12-27

4. Mediancal Vacuum Pump 12-28 12.4 GASEOUS EFFLUENTS 12-29 Arwe Emuents Umits and Reporting Operability 12-29

1. Dose Rate 12-29

2. Noble Gas Dose 12-29

3. lodne 131, lodine.133, Tritiurn and PartcJale Dose 12-30

4. Off Ges Treatment 12-31

5. Main Condenser Air Ejector 12-32

6. System Operability and Plant Operabons 12-32 B. r,mun= Emuents Suneillance 12-33

'1. Dose Rale 12-33

2. Noble Gas Dose 12-33

3. lodne-131, lodne-133, Tritium and PartcAate Dose 12-33

4. OR-Ges Treatment 12-33

5. Noble Gases at the Main Condenser Air Eyector 12-34 12-iii '

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DRESDEN Rivision 1.3 l

JinuIry 1997

}

j CHAPTER 12 l RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS

(RETS)

] TABt.E OF CONTENTS CONTINUED l

PAGE

12.4 GASEOUS EFFLUENTS (Cont'd) i C. Gaseous Effluents Bases 12-33 l 1. Gaseous Effluents, Dose 12-38

! 2. Dose, Noble Gases 12-38 1

3. Dose, Radiciodines, Radioactive Material in Particulate

', Form and Radionuclides Other than Noble Gases 12-39 l 4. Gaseous Weste Treatment 12-39 i

12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1240 A. Radiolog6 cal Environmental Monitoring Program 1240 B. Radiological Environmental Monitoring Program Surveillance 12-41 C. Radiologmal Environmental Morutoring Program Bases 1248

1. Monitoring Program 1248

2. Land Use Census 12-48

3. Intertsboratory Comparison Program 1248 12.4 RECORDMEEPING AND REPORTING 12-49

1. Station Operating Records 1249

2. Reports 12-49

1. Radioactive Effluent Release Report 12-49

2. Annual Radiological Environmental Operating Report 1249

3. NorWtoutine Env6ronmental Report 12-50

3. Offsite Dose Calculation Manuel(ODCM) 12-51

4. Major Changes to Radioactive Weste Treatment Systems (Liquid and Gaseous) 12-52 12-iv

DRESDEN Revision 1.3 January 1997 i

i CHAPTER 12 l RADIOLOGICAL EFFLUENT TECINCAL STANDARDS (RETS) l UST OF TABLES '

!s5EIE8 TITLE PAGE 12.1-1 Sunellan Frequency Notation 12-3 12.1-2 Cpa. tie-4 Modes 12-4 12.2-1 Radioacbw Uqud Emuent Monitoring l Instrumentabon 12-7 1

12.2-2 Radioactiw Uqud Emuent Abnitoring Instrumentation Surwillanz Regtirements

[

12-9 12.2-3 Radioachw Gaseous Emuent Monitoring Instrumentabon 12-12 12.2-4 Radioecew Gaseous Ef Auent Mondoring i instrumentaban Sur@anz Requrements 12-15 .

I 12.3-1 Allowable CGmi ison of Dssohed l or Entrained Noble Gases Released frorn the Site to Unrestnded Areas in ugud VWste 12-23 1 123-2 Radoacem Ugud Vhste Sampling and Analysis Program 12-24 l

12.4-1 Radioache n aam = Waste Sartpling and Anat/ sis Prognam 12-35 12.5-1 RadiologKal Environmental W Aing Program 1243 12.5 2 Reporting Laels for Radioedmty CG w 4.iic 6 in Environmental Sarrpies 1244 12.5 3 Pracbcal Lcuer Umits of Detecton (LLD) for Standard Radioicgcal Envise sis on Monitoring ,

Program 12-45 l en

,2 e'

DRESDEN Rewsion 1.3 January 1997 i

i

, 12.0 RADIOLOGICAL EFFLUENT TECHMCAL STAICARDS

12.1 DEFIMT10NS i

i

, 1. rh Fewivalent 1-131 - That concentrabon of I-131 (mcrocune/ gram) #1ich alone wotJd produce the same thyrod dose as the quanbty and isotopic mxture of I-131, 1-132,1-133,1-134, and 1-135 actually present. The thyroid dose conersion factors i

used for this calculation shall be those listed in Table til of TID -14844, " Calculation of Dstance Fadors for Pour and Test Reactor Sites".

2. Fram =riev W Table 12.1-1 prowdes the deArvtions of various frequences for which surwillances, sarmiing, etc, are pa knniod unless defined otherwise. Refer to l Tedinical WAe*vi Table 1-1.

l

3. Irmisdiate - Immedate means that the required adKul will be irutated as soon as pracbcable aanedering the safe operabon of the unit and theeiir ,bice of the required 1-adion.

4. Instrument Cahbrabon - An instrument cahbrabon means the actustment of an

instrument egnal output so that it conceponds, wthin smy*ahia range ard acaJracy, to a i<nomi value(s) of the parameter whKti the instrument monitors Calibrabon shall encoripass the entire instrument, includng aduabon, alarm, or trip.

j 5. Instrument Chadc - An instrument dieck is quaktstre ddamlinsson of memretia 1

operability by observabon of instrument behawor during operaton. This determnation shall indude, where pnamhia, corrpenson of the instrument Wth other independent

instruments measuring the same vanable.

i 6.

Instrumert Fundonal Test - A1 instrument funcbonal test means the infecton of a

simulated egnal into the instrument pnmary sensor to wnfy the proper instrument 4

response alam1 and/or initiating ac2on.

4

+

7. Member of the Pubhc - any indudual ecept when that indudual is receiving an

<m =*wrial dose.

8. Idadt - Reactor modes are desaibed in Table 12.1-2 (per Tectinkal Spoofication Table 1-2).

9. Oct2Jpahanal Dose The does roomved by an indmdual in the course of enployment in whKti the indMdual's aamgned dubes invoNe exposure to radiabon and/or to ihm m-tinal from hoensed and unhoensed sources of radiaton, whether in the pnaeamac . of the licensee or other person. @ m%nal dose does not indude dose from badground radiabon, as a ponent from medical pr.-h6, from voluntary participaton in medx:al reseerdi programs, or as a mentier of the public 12-1

DRESDEN ReMson 1.3 January 1997 12.1 DEFIMTIONS(Contd)

10. The Offste Dame CalaAshan Manusi (ODCM) shall contain the n mliedcicgy and paramelens used in the calculabon of offerte doses tusulting from radmediw gene n  ;

and liquid effluents, in the calculabon of gaseous and liquid effluent rnonrtonng Alarrr(Trip Setposits, and in the condud of the Environmental Radologmal Monitonng Prograrn The ODCM shall also contan (1) the Radioedne Effluent Controls and Radologmal Envronmental Monitanng Programs described in Secton 12.5 and (2) descnptons of the irkrmabon that should be irduded in the Annual Radiological l Ermronmental Operabng and Radioachve Efiluent Raiaana Reports required by -

Sechons 12.6.2.1 and 12.6.2.2.

11. Operable - A system, subsystem, train, wip wi or devme shall be OPERABLE or l have OPERABUTY when it is capable of performng its specified fundon(s) and when all necessary attendent instrumentaten, controls, normal or emergency eiedrical pour, cmchng or seal water, Ithncebon or other aumhary equipment that are requred for the system, subsystern train, wipi.ce or device to perform its speafled safety fundion(s) are also capable of perfbrmng their related support functon(s).

12. The Process Canard Program (PCP) shall contan the current formulas, sarghng, e ;, , test, and determnalmns to be made to ensure that procomang and packagrig of solid radmedive vestes bened on demonstrated procesang of adual or amListed wet solid westes vid be socomphshed in aucti a voy as to assure cortphance wth 10 CFR Parts 20, 61, and 71, State regulaimns, tuial ground requrements, and other requrements goverrung the rempnaal of solid radoective wasta

13. Raind Thermal Pbmar - Rated thermal power shall be a total roedor core heat transfer

. rate to the roedor coolant of 2527 thermal mogenetts.

14. Reedor Pomar Opershon - Reedor power opersbon is any opersbon with the mode swtch in the "SartL4WHot Sancby" or "Ruri" pombon wth the reedor critical and above 1% rated thermal poWar.

15. Souren Chadt - The quaktatMe asemesment of Channsi response when the Channel sensor is awpnaart to a radcedne source

16. r_ _.:_.2 r ' * - i to ."__ e g nn== to the PN I L g tha &nM Cm- dar '

Prograin j

1. Adual - Refers to using knowm release data to prqect the does to the public for the pronous monet These data are stored in the reaW- and used to demonstrale oorghance wth the reporting reglaraments of Chapter 12.

2. Prgeded - Refers to using knoum reletse dela kom the previous month or I embmetod reloose data to ferocest a future does to the ptbic These data are

!E ir-pu J into the <tstahama w

12-2 l

- _ - . - . _ _ _ - _. ..--- - - ..- -.- - - . . - - ~ . . . . . - =

DRESDEN Revision 1.3

January 1997 iO l TABLE 12.1-1 i

SURVEILLANCE FREQUENCY NOTATION 4

N2TATION FREQUBOr l

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 />

! D(Daily) At least onz per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> j T Atleast once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> i W(Weeldy) At least onm per 7 days

! M(Monthly) At least once per 31 days 4

~

Q (Quarterty) At least onm per 92 days

SA(Semannually) 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 (Starttp) Prior to each reactor startup

. NA(Not Applicable) Not applicable i

71 l

i l

i i

I

• Each sunellance regtirement shall be performed within the specified time interval with a maximum alloAmble extenamn not to exceed 25% of the sunellance interval The bases to Tedncal Specificabons 4.0.B prtudes danficabon to this statement These defirvbons do not apply to the Radologad Enwonmental Mondoring Program (Sedon 12.5).

DRESDEN Revision 1.3 January 1997 g

TABG 12.12 W OPERAT'ONAL MODES MODE SWTCH AVERA3E REACTOR MODE POSITICN9 COOUWT TEMPERATURE

1. POMR OPERATION Run Any tergature 4

2.STARTUP StartupHot Standby Any tergatJre i

3. HOT SHlRDOW Shutdowr(** > 212 F

4. COLD SHUTDOWN Shutdcw1*** 5 212"F

5. REFUEUNG* Shutdcwn or Refuel (** 514&F 1 TABLE NOTATIONS

, (* The reactor mode swtdi rney be placed in the Run, StartupHot Stancby, or Refuel position to test the setd1 interlock functions provided the control rods are wnfled to remain fuHy inserted by a i second licensed ep .hi or other ted.A ily qualified indvidual

• ) The renr rnode swtdi msy be placed in the Refuel postion while a single control rod drive is being remoed from the reactor pressure vessel per Tedncal S;+f-Mr 3.10.l.

(* Fuel in the reador vessel wth one or more vessel head dosure bolts less than fully tensioned or

with the head remoed

(* See Technical Speaficaban Speaal Test Sr--;4xe 3.12.A and 3.12.B.

4 (* The reador mode sutdi msy be placed in the Refusi poston while a single contrd rod is being recoupled or wthdrami provided the oneuxkut interlock is OPERABLE.

M Mhen there is no fuel in the reador wesel, the reactor is consdered not to be in any OPERATIONAL MODE. The reador nude swtd) may then be in any postum or may be inoperable 12 4 g

_.- . . . _ . _.. __ - ~ _ . . . _ _ . . . . . _ -. _ .._ ,

,l 4 ,

DRESDEN Revision 1.3 j January 1997 4

! 12.2 INSTRUNENTATION l A R**w*w I W M Effluent W Lirsi instn Te-22:m '

1. R=*=*w I n M Effluent L. Lug Instn Te

:m MIN I

1. The ef!!uent rnonitonng instrumentabon shtmn in Table 12.2-1 shall be operable j with alarm trip setpoints set to insure that the limits of Section 12.3.A are not

exceeded The alarm setpoints shall be determned in accgdcmxe wth the s

g

2. Wth a radioactive liquid effluent monitoring instrunc

t adamYtrip setpoint less

, ariservahve than required, wthout delay suspend the release of radioactiw liquid effluents monitored by the affected instrument, or declare the instrument j inoperable, or change the setpoint so it is accer Liy conservatiw.

i 3. Wth one or more radioediw liquid effluent monitoring instruments inoperable, i take the ac2cn shown in Table 12.21. Retum the instrument to operable 1

status wthin 30 days and, if una rr===f d, t explain in the next Radioactive Ef!Iuent Release Report why the inoperability as not cxxteded in a timely manner This isin lieu d an LER

4. . In the event operability requrements and assocated acton requirements cannot be sabshed harm na d drcumstances in amena of those addressed in

the spea6cabons, prcMde a 30<isy wntlen report to the MRC and no changes i

are requred in the operabonal aandeon d the plant, and this does not prevent the plant from entry into any opensbonal mode.

l

2. R**w*w I la M Eftluant m se g inse Surr"" w l

1. Each radioactw liquid effluent nu .L #4 instrument shown in Table 12.2-2 l

shall be demonstnuled operable by performance of the given source check,  ;

instrument check, calibnsbon, and functonal test operations at the frequences

shown in Table 12.2-2.

B. R**w*w F-= Effluart WWL y Inne l 1. R**=*ve r-= Efnuart Mondonna Ire MIN ,

d 1 1. The effluent nu. Lug instrumentabon shom in Table 12.2-3 shall be operable j

j with alarTMnp setpoints set to ensure that the limts of Sec$on 12.4.A are not

• • The alamYtrip setporits shall be determined in E=.wdas n.= wth the

ODCM

2. Wth a radioecem ganaa m effluent monitoring instruments alamVtrip set point i less consenabve than requred, wthout delay suspend the release of

! radioeceve gaseous ef!Iuents monitored by the a#eded instrument, or dedare

! the instrument inoperable, or change the setpoint so it is wrartshly conservahve 3

s 5

(

12-5 s

DRESDEN Revision 1.3 January 1997 12.2.B.1 Radoachver*=uus Emuent 6 nuirg Instruro,Lsbon Coerabihtv (Cortd)  !

3. Wth one or more radioactne gaseous emuent troritonng instruments inoperade, take the action shown in Table 12.2-3. Return the instrument to operable status l within 30 days and, if ur=w=ful, explain in the next Radoactive Emuent l Release Report why the inopaiststy was not corrected in a timely manner Ths  !

is in lieu of an LER j

4. The Urvt 2/3 plant cNmney gas sampling system may be out of service for 48 i hours for the purposa of servicing the high range noble gas maritor as long as the following conditions are satisfied:

1. Both units are at steady state conditions with the recorrbiners and charcoal istAtoms in service for the operating urit(s).

2. The dose rate in unrestrided areas must be shown by calculation to be less than the lirnts d 12.4.A assurnng the charcoal absorbers are bypassed on both units.

3. Both offgas monitors on Unit 2 and Unit 3 must be operational and the monitor readng correlated to the chimney release rate based on the conrervatne assumphon d both units' dian: cal absorbers being bypa==M l l

4. If the provisions d 12.4.A1.1,12.4A1.2, or 12.4.A1.3 cannot be met, an orderty load reduchon of the unit (s) shall be initiated immedately. j i

5. In the ewint operability requirements and assodated acbon regtirements cannot be satisfied becaurs of circumstances in excess of those addressed in this l Sedian, provide a 304sy wntten report to the NRC and no changes are reqdred  !

in the operabonal 0x4600 of the plant, and this does not prewint the plant from entry into any cpa.607 node.

r m Emuert L auirq Instruve Mr.n Surveillanm

2. Ra&wtw *== l Eadi radoachve gaseous radsbon monitoring instrument in Table 12.2-4 shall be demonstrated operable by pab n-ice of the given source check, instrument check, calibrabon, and functonal test (#5 60 = at the frequency shown in Table 12.2-4.

124

DRESDEN Revson 1.3 January 1997 i

TM.LE 12.2-1 i

RADIOGVE UQUID EFFLUENT MONITORjNG INSTRUMENTATION UNIT 1 Mnimurn Total Channels No. of Instnment Operable Channels Action

1. Service VMer Emuent 1 1 10 i Gross Actvity Marstor*

2. Dscharge Canal 1 1 12 Sampier*

ACTIONS ACTION 10- Wth less than the minunurn nunter of operable channels, releases via this pathury may continue, prmded that at least once per 24 hotra grab sarmies are callected and analyzed for beta or gamma acevity at an LLD of less than or equal to 10r' pCi/ml.

AC110N 12 - Operability is wnfied prior to perfaming and once a day during planned dscharge

• Wen Instrument is uravailable and associated actons cannot be p fe6 d then distwgpm may not be made.

l l

l 12-7

DRESDEN Rewsion 13 January 1997 TABLE 12.2-1 RADICETVE UQUID EFFLUENT MONITORING INSTRUMENTATION I UNITS 2 & 3 '

I Mnimtm Total Channels No. of instrument Operable Channels Action

1. Service Water Emuent 1 1 10 Gross Actmty Monitor

2. Uguid Radwaste Emuent 1 1 11 Gross ActMty Monitor l

l ACTIONS j i

ACTION 10 - Wth less than the nirimum nunter of operable channels, releases via this pathway j rnay continue, prtuded 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 sarmies are dieded ,

and analyzed for beta or gamma admty at an LLD of bas than or equal to 10' i uCi/nt ACTION 11 - Wth less than a mirimum nurrber of operable channels, emuent releases via tNs pathay may continue, prcMded that prior to iratiating a release, at least 2 independent sarmies are analymd, and at least 2 irw1=is of the faality staff independently wnfy the release W% and dscharge vaMng. Otherwise, suspend release of radoadne emuent via this pathay l

l l

l 12-8

DRESDEN Rewson 1.3 January 1997 d

f TABLE 12.2-2 l t

RADIOACTIVE UQUID EFFLUENT MOMTORING INSTRUIENTATION SURVEILLANCE REQUIREMENTS UNIT 1 Fundonal Calibrabon*" Instrument Source Instrument Test ChecW9 Check ,

1. Serwoe VWder Emuent Gross O'**) E* D E i A2wty Morvtor" w an MMN ,M %M '

be rnade.

• 12-9 L

DRESDEN Reusson 13 January 1997 TABLE 12.2-2 RADIGCTIVE UQUID EFFLUENT MONITORING INSTRUPENTATION SURVElLLANCE REQUIRENENTS UNITS 2 & 3 Funcdonal Calibratiorf" Instnment Source instrument Test ** Cteck" Check

1. Uquid Radwaste Emuent Gross Q* E4 D E*

ActMty Mondor

2. Servi Veter Emuent Gross Q* E" D E Actmty Monitor O

l I

l l

i 12-10

Y DRESDEN Revsion 1.3 January 1997 i i

.  ?

TABLE 12.2-2 (Coned) l RADIOoCTNE UQUID EFFLUENT MONITORING INSTRUNENTATION SURVEILLANCE REQUIREENTS  !

TABLE NOTATIONS i

• i The instrument Functional Test shall also dnmonstrate that control room alarm annuncation occurs, if any of the folkwng condrtrys east, where applicable.

1. Instrument iruficated leels above the alarm setpoint.  !

2. Circuit failure. [

3. Instrument indK: ales a dcunscale falure

4. Instrument controls not set in OPERATE mode  !

• Calibraton shall indude performance d a functonal test f M Calibration shall indude periormance of a source check.

• Source (teck shall consst d obeemng rutrument response during a damerge

• Fundianal tests may be performed by using trip check and test on:urtry mammM with the monitor chases M Func2 anal tests, calibrabons, and instrument checks are not requred when these instruments are not requred to be operable or are inpped Cahbration is not requred to be performed more than once every 18 months.

• Operability is wnfied prior to performng discharge and once a day during planned discharge 12-11

DRESDEN Reason 1.3 i January 1997 l

TABLE 12.2-3 l RADICETVE CASEOUS EFFLUENT MONITORING INSTRUMENTATION UNIT 1 Mnimum Total Applicable Channels No. of Operats-s Instrument Operable Channels Modes M on

1. Main Chimney SRNG Noble Gas 1 3 28 Manitors

2. Main Chirmey Particulate 1 1 27 Samplers

3. Main Chimney lodine Samplers 1 1 27 1

l l

O

• At all times.

12-12 g,

DRESDEN Revson 1.3 I January 1997 I

TABLE 12.2-3 RADIOACTIVE CASEOUS EFFLUENT MONITORING INSTRUNENTATION UNITS 2 & 3

, Mnimum Total Applicable 1

Channels No. of Operabonal ,

instrument Operable Channels Modes Ation l l

1. Main Chimney Noble Ges/SPINGr 1 3

• 20 GE Low Range Activity Morntor l 2. Main Chirmey SRNG Noble Gas 1 1 26 Morstors Md, H Range

3. Main Chimney lodine Sarmier 1 1 22

4. Main Chimney PartxxJiate Sarmier 1 1 22

5. Main Chimney Flow Rate Morntor 1 1 21

6. Main Chimney Sampler Flow Rate 1 1 21 Mondor

, 7. Reador Buildng Vent Exhaust 2 2 1, 2, 3 and *" 24 Dud Radiation Marvtor

8. Reactor Bdidng Vent SPING 1 1 25 Noble Gas Monitor Low, Md, High Range

9. Reactor Bdidng Vent Ficw 1 1 21 Rate Morntor

10. Rauer Building Vent Sarmier 1 1 21 Flow Rate Monitor

11. Reador Buiking Vent lodne i 1 22 Sampier

12. Reactor Buildng Vent i 1 22 Paraculate Sampler

13. Offgas Radiabon Aduty "

1 2 29 Monitor

• At all times.

" During Steam Jet Air E}edor operaton.

• "Vhen handing irradated fuel in the 5edidsy contanment.

l 12-13

1 i DRESDEN Rews on 13 January 1997 TABLE 12.2-3 (Cont'd) l RADICETNE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ACTIONS AND TABLE NOTATIONS ACTION 20 - Wth less than the mnimurn channels operable, effluent releases wa ths patnway .

may ccntinue for up to 30 days prowded grab sarmies are taken at least once emy I 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 wtNn 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l ACTION 21 - Wth the number of operable channels less than the mnimurn reqdred, effluent releases via this pathway may continue prowded that the flow rate is estimated at least onz per 4 houns.

ACTION 22 - Wth less than the rrinimum channels operable, effluent releases via this pathway may continue prowded sarmies are continuously collected wth auxiliary sanpling equpment, as required in Table 12.4-1.

ACTION 24 - A channei may be placed in an irupa abie status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required survedlance enthout plaang the channel in the tripped condition prowded the functional urut maintains isolation aduation capability An irupa abie channel need not be placed in the tripped condition where this would cause a tnp fundion to occur. In tNs case, the iruparabie channel shall be restored to operable status wthin 2 hotrs, or the following action taken. Wth less than the rdnimum channels opa able, establish Secondary Contanment Integnty wth the Standby Gas Treatment System opera:ing within one hour.

ACTION 25 - Wth less than the mnimum rt==imis operable, effluent releases via this pathway may continue prowded that the mnimum number of Opa &ie channels for the Reador Buildng Vent Exhaust Dud Radation Monitor are operable ACTION 26 Wth less than the rdnimum channels operable, ef!!uent releases via this pathway may continue prowded the low range monitor is operable and on scale. Restore the inoperable equipment to operable status wthin 21 days, or prepare and submt a report to the commission pursuart to Techncal Speafication 6.6.8 (Sedion 6.6.A in Upgraded Technmal Speaficabons) within the next 30 days outlining the plans, adions taken and procedures to be used to prowde for the loss of sampling capability of the system ACTION 27- The main chimney SRNG monitor may be out-of-service for calibration and maintenance provided that parbctiate and iodne sarmies are taken and analyzed.

The sarmies shall be collected using alternate filter holders and punps cu rected to the main chimney sample stream ACTION 28 - Wth less than the rdrimurn channels operable, effluent releases via this pathway may continue prowded daily noble gas samples are taken and analyzed daily.

Restore the inoperable equipment to operable status wthin 30 days. If service can not be retumed, document eqtipment availability dffictitles wthin the Radioactne Effluent Release Report for the penod includng achons taken in rwa 5 to the equipment and procedures used to prowde for the loss of sar@ ling capability of the system AC110N 29- Wth less than the rdnimum channels operable, gases from the rnain condenser off gas system may be released to the enwronment 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 gas system is not byr=wd and at least one ctimney monitor is operable, otherwse, 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 />.

12-14

. . -..- - . - = . . _ - .

DRESDEN Revson 1.3 January 1997 TABLE 12.24 RADICACTIVE CASEOUS EFFLUENT MONITORING INSTRUNENTATION SURVEILLANCE REQUIREENTS ,

UNIT 1 Applicable 1 Functional Calibrabon*' instrument Source Operational  !

Instrument Test ** Check Chec:k Modes  !

i I

1. Main Chimney SRNG O E D M

• Noble Gas Mondor Low Range i

i i'

• At all times.

i

?

i i

I i

i i

t i

\ 12-15 l

e-DRESDEN Revson 1.3 January 1997 TABLE 12.24 RADIOoCTI'E CASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIRENENTS UNITS 2 & 3 Applicable Fundional CalibratiorP* Instrument Source OWstc s instrurnent Test"* Check (* Check Modes

1. Main Chimney Noble Q E D M

• Gas Actmty Monitor

2. Main Chimney SPING Q E D M

• Noble Gas Monitor Lo, Md. Hgh Range

3. lWain Chimney NA NA D* NA

• Particulate and lodine Sarmier

4. Main Chimney Row Q E D PM

• l Rate Monitor '

5. Main Chimney Sarrpier Q* E D NA

• Flow Rate Monitor i

6. Reador Bldg Vent M Q S O 1,2,3,and -

Exhaust Duct Radiation Monitor j

7. Reactor Bldg Vent Q E D M

• SPING Noble Gas l Monitor Lo, Md, Hgh Range 1

8. Reador Bldg Vent Q E D NA

• Flow Rate Moner j

9. Reador Bldg Sartpler QS E D NA

• Row Rate Moner

10. Reactor Bldg Vent NA NA D* NA

• Particulate and I lodine Sarmier

11. Off Gas Radation Q E D E "

Actmty Monitor j

• At all times.

' " Dunng Steam Jet Air Ejector operation.

" Operation reqtired when handing irradated fuel in the sew iday contanment.

I 12-16

DRESDEN Revson 1.3 January 1997 1

TABLE 12.24 (Cont'd)

RADICACTNE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIRENENTS

} TABLE NOTATIONS The Instrument Fundional Test shall also demonstrate that control roorn alarm annunciation occurs, if any of the following conditions exist, where applicable.

1. Instrument incicates levels above the alarm setpoint '

2. Circut failure.

3. Instrument indcates a downscale failure.

4. Instrument controls not set in OPERATE mode.

• Calibrabon shall indude performance of a functional test Instrument check to venfy operability of sarmier; that the sar@ier is in place and funcboning property

(*

Functional test shall be performed on local switches prodng icw flow alarm

• Fundianal tests, calibrabons, and instrument checks are not reqtared h these instruments O are not required to be operable or are tripped. Calibrabon is not regtired to be performed more than once every 18 months.

12-17

l l

DRESDEN Reusion 1.3 January 1997 12.2.C Uatid And Gaseous ESEsts IrstruTembon h

1. The radioachve liquid and gaseous effluent instrumentabon is provided to monitor the release of radioacbve materials in liquid and gaseous effluents dunrg releases The alarm setpoints for the instruments are provided to ensure that the alarms will ocx:ur pnor to exceedirg the lirnts of RETS.

I 1

I 12-18

DRESDEN Revson 1.3 January 1997 12.3 UQUID EFFLUENTS 12.3.A Uauid Effluents Urnts and Rarvvtina r hrabilrty

1. Co o,e.uon in U,vi-Lhi Areas The concentration of radioactive malarial relaaemd frorn the ste to unrestncted areas (at or beyond the sie boundary, Dresden Station ODCM Annex.

Appendix F Figure F-1) shall be limted to the concentrations speafied in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402', for radionuclides other than dissolved or entrained noble gases For dissolved or entrained noble gases, the cxxx:entration shall be limted to the values listed in Table 12.3-1.

Wth the concentrabon of radioactive rnsterial released from the site to unrestncted areas exceedng the abom limts, wwthout delay decrease the release rate of radoactve rnstenais and/or increase the dilution flow rate to restore the concentrabon to within the abom limts.

2. Done from Uquxi Ef!Iuarts The dose or dose commtment above background to a menter of the public from radmachve materials in liquid ef!Iuents released to unrestricted areas (at or beyond the sie boundary) from the site shall be limted to the folkwng:

1. During any Calender Quarter (1) Less than or equal to 3 mrem to the whole body.

(2) Less than or equal to 10 nTem to any orgart

2. During any Calendar Year:

(1) Less than or equal to 6 mrem to the whole body.

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

3. Wth the calcdated dose from the release of radioadive materials in liquid effluents avraading any of the above limts, prepare and submt to the Cu m mi within 30 days a Special Report whK:h idenbfies the cause(s) and defines the comrtive actions taken and the proposed achons to be taken to ensure that future releases are in compliance with Sectons 12.3.A2.1 and 12.3.A2.2. This is in lieu of a Umnsee Event Report.

2Upon technmal specification approval, ten (10) times the Appendix B value may be used to determine the maximum instantaneous liquid release 12-19

DRESDEN Revision 13 January 1997 12.3.A Uauid Effluents Umts and Reoartina Coerabihtv (Cont'd)

4. Wth the calculated dose frorn the release of radioacbve rnatenals in liquid effluents exceeding the limts of Sections 12.3.A2.1 or 12.3.A2.2., prepare and submt a Speaal Report to the Comrnssion i wthin 30 days and limt the 9*= w1t rei- sudi that the dose or '

dose w m s 6it to a member of the public frorn all uraniurn fuel cyde sources is limted to less than or equal to 25 mrem to the total body or ,

any organ (except thyroid, which is limted to less t..an or equal to 75 1 mrern) over 12 consecutive months This Speaal Report shall indude an analysis whKh demonstrates that radiation exposures to all real l indivduals from all uranium fuel cyde sources (induding all effluent pathways and dred radiation) are less than the 40 CFR Part 190 Standard Otherwse obtain a variance from the Commssion to permt releases whKh W the 40 CFR Part 190 Standard The radiation exposure analysis contained in the Speaal Report shall use rnethods presenbed in the ODCM This report is in lieu of a Ucensee Event Report.

5. Wien the pivpcted annual whole body or any intemal organ dose computed at the neanest downstream commurvty water system is equal to nr exceeds 2 mrom from all radoadiw matenals released in liquid effluents from the Station, prepare and submit a Spedal Report wthin 30 days to the operator of the community water systern The report is prepared to assst the operator in meeting the requrements of 40 CFR Part 141, EPA Primary Drinking Weer Standards A copy of this report will be sent to the NRC. This is in lieu of a Ucensee Event Report  ;

3. Dose Prgedians At all times during processing prior to dscharge to the environs, pro ss and ,

contrd equipment prcMded to reduce the anount or w @ 6a6on of radoadive materials shall be Opor.iod when the projedad dose due to liquid effluent releases to unrestrided ansas (Dresden Staban ODCM Annex, Appendix F, Figure F-1), when averaged omr 31 days, exceeds 0.12 rrrem to the total body or 0.40 mnem to any orgarf

'These values represent 2% of the annual dose limts of Appenix 1 to 10CFR50 12-20

DRESDEN Rewsion 13 January 1997 l 12.3.A tnad EfRuants Umits and Ramrtina Onerability (Cont'd) i A Q 4. I imid Radkw*ve p Treatment Svstern If liquid waste has to be or is being dsdiarged wthout treatment as requred above, prepare and submrt to the Commission with 30 days. a report whidi indudes the following informabon.

1. Idenbfication of the defectiw equipmert

2. Cause of the defed in the equipmert

3. Acton(s) taken to restore the equipment to an operatng status.

4. Length of time the abow requirements were not satisfied.

5. Volume and curie content of the waste diedunwed which was not promssed by the appropriale equipment but whidi reqtired processing.

6. Aton(s) taken to prment a rectnence of equipment failures.

This is in lieu of a Uoensee Event Report. i

5. Svstem Miitv and Ptart rhwahans in the event a limit and/or naamshid acton requirements denbfied in Sections 12.3.A and 12.3.B cannot be sabsned because of drcumstances in excess of those addressed in this Sechon, no dienges are reqtired in the operational uid6cn of the plant, and this does not preent the plant from entry into any

\v operational mode 12.3.B laqud EfRuanta Stnellanm

1. Concentrabon in Unrestnded Areas The coricentrabon of radioachve melenal in unrestncted areas shall be determned to be wthin the prescribed limits by obtaining ropa da6m samples in acmrdance with the sarmling and analysis program spedfied in Table 12.3 2. The sarmle analysis results will be used with the calculational methods in the ODCM to determine that the concentrations are within the limts of Secton 12.3.A1.

i 12-21 ha t

DRESDEN Reusion 1.3  ;

January 1997 l

12.3 B Lauid Effluents Sunellans (Cont'd)

2. Dose from imJd Emuents The dose contnbution frorn measured quantties of radioactive matenal shall be determned by caletdation at least on per 31 days and cumulatie surrmabon  !

of these total body and organ dosed shall be rnantained for each calendar quarter. I Doses computed at the nearest cxmnunity water system will consider only the drinking water pathway and shall be projected using the rnethods prescnbed in i ODCM, at least once per 92 days. j

3. Dose Prcnedians Doses due to liquid releases to unrestricted areas (at or beyond the site boundary) shall be projected at least once per 31 days in rusdr= s with the ODCM 1

i O

,2 22 g

l DRESOEN Revson 1.3 l January 1997 i

i TABLE 12.3-1

! ALLOWABLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE NUCLIDE riuCihW)*

Kr-85m 2x10*

Kr-85 5 x 10d Kr-87 4 x 105 Kr-88 9x10' h41 7x108 Xe-131m 7 x 10d Xe-133m 5 x 10d Xe 133 6 x 10d Xe-135m 2 x 10d Xe-135 2 x 104 Conputed frorn Equebon 20 of ICRP Publicabon 2 (1950), a4usted for infinite doud submersion in vnter, and R = 0.01 i.ri;d; density = 1.0 g/cc and FWPt = 1.0.

~

12-23 l

DRESDEN Revson 1.3 January 1997 TABLE 12.3-2 RADICACT1VE UQUID V%STE SAPX'UNG AND ANALYSIS PROGRAM UNIT 1 LCMER UMIT OF TYPE OF ACTIVITY DETECTION UQUID RELEASE sat &'UNG MNIMUM ANALYSIS NMLYSIS (LLD)") (pCi/ni)

TYPE FREQUENCY *) FREQUENCY')

A Servim M M l-131 1x10' Yhter Neases('"

M M Priropal Gamma 5x10 7

(Grab Sartple) Emtters(5)

M M Dssched & Entrained 1x105 (Grab Sarrple) Gases")(Gamma Emtters)

M M i+3 1x105 (Grab Sample) (Curvate)

Gross Alpha 1x10' Q Q Sr-89, Sr-90 5x10'

( }

Fe-55 1x10' LOWER UMT OF TYPE OF ACTMTY DETECTION UQUID RELEASE SAPM' LING MNIMUM ANALYSIS ANALYSIS (LLD)") (pCi/tri)

TYPE FREQUENCY

• FREQUENCY')

B. Above Ground T T Principal Garima 5x10 7 Uquid Storage Emtters(5)

TanksM DssoNed & Entrained 1x105 Gases")(Gamma Emrtters) 12-24

DRESDEN Revison 1.3 January 1997 TABLE 12.32 RADCMCTNE UQUID WASTE SAMPUNG AND ANALYSIS PROGRAM l

UNITS 2 & 3 LCMER UMT OF TYPE OF ACTIVITY DETECTION UQUID RELEASE SAWUNG MNIMUM ANALYSIS ANALYSIS (LLD)") (pO/ni)

TYPE FREQUENCY

• FREQUENCY

• A Batch Prior to Prior to Principal Gamrm 5x10 7 Release Ead Batch Eam BatM Emttent*

Tanks 1-131 1x10' Prior to M Gross Alpha 1x10r7 Ea2 Batch Cury.&'* H-3 1x105 Prior to Q Fe-55 1x10*

Ea6 Bats Currate m Sr-89, Sr-90 5x10' Prior to M Dssched & Entrained 1x105 One BatdWI Gaaan (*(Gamma Emtbers)

8. Plant MS MS I-131 1x104 Continuous (Grab Sarmie)

MS MM Priropel Gamma 5x10 7

(Grab Sarmie) Emttent*

MS MS DssoNed & Entrained 1x105 (Grab Sample) Gesaf* (Gamma Emtters)

MS M* H-3 1x105 I I Gross Alpha 1x107 QM QS Sr 89, Sr-90 5x10*

( )

Fe 55 1x10' C. Above Ground T T Priropel Gamma 5x107 bqud Storage Emttent*

Tanksm DssoNed & Entrained 1x10 5 Gesat* (Gamma Emtters)

G 12-25 C/

DRESDEN Rewsaon 1.3

, January 1997 TABLE 12.3 2 (Cont'd) i TAFu F NOTATION

• The LLD is defined in the OOCM i m

A corrposte sanple is one in which the quanbty of liquid sarrples is proportional to the quantty of liquid waste disdiarged and in which the method of samplirg eriployed rest.its in a speamen which is representabve d the liquids released j

• If the alarrn setpoint of the service water effluent nunitor as deta rrirsj in the ODCM is 1

exceeded, the frequency of analysis shall be increased to daily unbl the condtion no longer .

exists. I A batch release is the dsdage of liquid wastes of a dscrete volume. Prior to sanpling for I analyses, each batch shall be isolated and then thoroughly nixed to assure representatve  !

sampling. A condnuous release is the dscharge of liquid wastes of a nondiscrete volume; e g.,

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

• The principal gamma erntters for which the LLD speafication applies exdusively are the following radonudides: th54, Fe-59, Co40, ZMS, Co-58, Mo 99, Cs-134, Cs-137, Ce-141, and Ce-144. Other peaks whK:h are measurable and identifiable by gamma ray sixGun esy together with the abom nudides, shall be also idenbfied and reported when the actual analysis is paiun ad on a sample Nudides whKh are below the LLD for the analyses shall not be reported as being presert at the LLD lewl for that nudide.

• The dssoled and entrained gases (gamma erntlers) for whKh the LLD speofication applies exduswly are the follomng radionudides: Kr-87, Kr-88, Xe 133, Xe-133m, Xe-135, and i Xe-138. Other dissoNed and entrained gases (gamma emitters) which are measurable and idenbfiable by gamma ray spa.ku ndy, together wth the above nudides, shall also be idenbfied and reported when an adual analyms is performed on a sanple Nudides which are below the LLD for the analyses shall not be repaded as being present at the LLD lemi for that nudide.

m A sarTple(s) front Unit 1: Ead1 of the above-grade liquid weste tanks. If no addrbons to a tank have been rnade sin the last sanple, the tank need not be sanpled until the next addition.

Units 2 & 3: The Wale Sample Tanks, Floor Drain Sample Tanks and the Veste Surge Tanks, shall be taken, analyzed, and recorded every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If no addtions to a tank have been rnade since the last sample, the tank need not be sartpled until the next addition.

• Sampling and analyses required only when system is operating.

12-26

. _. . _ - - . . _ = - - . _ . - . -

DRESDEN Revision 1.3 January 1997 12.3.C UQU!D EFFLUENTS BAen O

h 1. Core 6aban

' Ths speofication is prcMded to ensure that the riis iabon of radioacbve rnatenals released in liqud waste effluents frorn the site to unrestncted areas wil be less than the 4

cs w &aGon lewis speofied in Appendix B, Table 2. Column 2 to 10CFR20.1001-20.2402.

2. DQ6e This speofication is prcmded to irTplement the requirements of Sedions ll A lil.A and IV.A of Appendix 1,10 CFR Part 50. The cpitaucmai reglarements inplements the l guides set forth in Section ll.A of Appendx 1. The statements provide the required operating flembility and at the same time implement the gudes set forth in Sedian IVA of Appendix 1 to assure that the releases of radioedive material in liquid effluents will be kept "as low as reaeci=sbiy achevable" The dose cakulabons in the ODCM implement the regtirements in Seebon lit.A of Appendix 1 that w u% micx wth the gudes of Appendx 1 be shown by cakulational procedures based on models and data sudi that the actual exposure of an indmdual through appropriate pathweys is unlikely to be substantiary undereshmated. The equabons W_ in the ODCM for  !

calctdating the doses due to the adual release rates of rancedre materials in liquid ef!!uents will be consistent wth the ir=0 udciogy prcuded in Regulatory Gude 1.109,

" Calculation of Annual Doses to Man from Routine Releases of Reador Effluents for l the Purpose of Evaluating Coridiance wth 10 CFR Part 50, Appendx I", Revision 1, 4

Ortnhar 197/ and Regulatory Gude 1.113, " Estimating Aquabc Dispersion of Effluents

, from Aasdental and Routine Paartnr Releases for the Purpose of Irrpiementing 4

Appendix I", Apnl 1977. NUREG 0113 prcudes methods for dose caktdations contiistent with Reg Gude 1.109 and 1.113.

3. bound Waste Treatment The operabRty of the liquid radweste treatment system ensures that this system will be available for use wheneer liquid effluents regtire treatment prior to release to the e environment. The requirement that the appropriate porbons of this system be used when W pnwides assurance that the releases of radioactme materiais in liquid emuents will be kept "as kw as reascrisbiy achevable". This spooficabon iriplements i the requirements of 10 CFR Part 50.36a, General Design Cnterion 60 of Apperdx A to 10 CFR Part 50 and design objectne Sedion 11.D of Appendx l to 10 CFR Part 50.

4 d

d 4

12-27 I

DRESDEN )

Revison 13 '

=

Januan/1997 1

12.3.C UQUtD EFFLUENTS Bpg . (Catnued) l

4. Mechanical V=,a m Pumo The purpose of isdatirg the rnechanical vacuum iine is to lirnt release of actMty from the main condenser During an accident, fisson products would be transported from

! the reactor through the rnan steam line to the main condenser The fisson product radioacovity would te sensed by the rnain steaniine radioactmty rnorntors which intate ,

isdation.

)

l I

O l

12-28 1

l

DRESDEN Revison 1.3 )

! January 1997 l

l l

12.4 GASEOUS EFFLUENTS A h a Effluents Umts and MMic M.lity ,

1. Dose Rate l

The dose rate in unrestricted areas at or beyond the site boundary (Dresden j Station ODCM Annex, Appendx F, Figure F-1) due to radicadve matenals  !

released in gaseous effluents from the ste shall be timted to the following.

1. For Noble Gases (1) Less than a dose rate of 500 mrent/ear to the whole body. l (2) Less than a dose rate of 3000 mrenVyear to the sidn. l

2. For iodne-131, for iodne 133, tritium and for all radionudides in particulate :

form wth half-lies greater than 8 days, less than a dose rate of 1500 l mrenvyear. '

3. If the dose rates exceed the abow lirrits, without delay decrease the  !

release rates to bring the dose rates wthin the limits, and provde l notificabon to the Commission (per 10 CFR Part 20.2203).

2. Noble Gas Done The air dose in unrestrided areas at or beyond the site boundary due to noble gases released in puw= effluents frorn the unit shall be limtad to the following:

1. For Genma Radiabon (1) Less than or equal to 5 mrad during any calandar quarter (2) Less than or equal to 10 mrad during any calendar year.

2. For Beta Radiation (1) Lees than or equal to 10 mrad during any calendar quarter (2) Less than or equal to 20 mrad during any calendar year. '

3. Wth the cakdated air dose from radoactive noble gases in gaseous effluents exceedng any of the abow limts, prepare and submt to the l Commission wthin 30 days, a Speaal Report whidi idenbfies the cause(s) l for exceedng the limt(s) and defines the corrective adons to be taken to I ensure that future releases are in cormliance wth Sections 12.4.A2.1 and 12.4.A2.2. This is in lieu of a Ucensee Emnt Report. i l

l

! Ay) 12-29 i

i DRESDEN Reusion 1.3 i January 1997 l

12.4 A Gaseous Effluents Umts and Re00 doc Or=rability (Contd)

4. Wth the calctiated air dose from radioactiw noble gases in gaseous e ;!

effluents exceeding the limts of Sections 12.4.A2.1 or 12.4.A2.2. prepare and submt a Specal Report to the Commssion wthn 30 days and limt the

9 hce ant releases such that the doses or dose commtment to a meriter of the public from all uraruum fuel cyde sour s is limted to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limted to less than or equal to 75 mrem) over 12 consecubw montre TNs i

Speaal Report shall indude an analysis which demonstrates that radiadon exposures to all nanss of the public from all urarium fuel cyde sour s (induding all effluent pathways ard drect radation) are less than 40 CFR Part 190 Standard Otherwise, obtan a vanance frorn the Corrmssion to permt releases wbch exceed the 40CFR Part 190 Standard The radiation  ;

exposure analysis contained in the Spedal Peport shall use the n di.cdi, I prescnbed in the ODCM. This report is in lieu of a boensee Event Report. j

5. Process and control eqtipment provded to redu the amount or crfuziuddon of radioactive materials shall be cpa Es when the projected dose due to gaseous effluents released to the unrestricted areas, when averaged cNer 31 days, exceeds 2% of the annual dose limts of Appendix i to 10CFR50

3. lodne-131. todne-133. Tritium and Partin m Onaa I The dose to a member of the ptblic in unrestnded areas at or beyond the site boundary from iodne-131, iodne-133, tntium, and all radonudides in particulate fomn wth half-lins gnsater than 8 days in gaseous emuents released from the unit j shall belimted to the following. '

1. Less than or equal to 7.5 mrem to any organ during any caksim quarter.

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

3. Wth the calculated dose frorn the release of iodine-131, iodine-133, tntium, and all radonudides in particulate form wth half 4ives greater than 8 days in gaseous effluents exceeding any of the abcNe limts, prepare and submt to the Cormission within 30 days, a Spedal Report which identifies the cause(s) for exceeding the limt and defines the correctNe aC! ions taken to ensure that future releases are in cortpliance with Sedian 12.4.A3.1 and 12.4A3.2. This is in lieu of a Ucansee Event Report.

4. Wth the cala.Jated dose frorn the release of iodine-131, iodine 133, tndum, and all radonudides in partictiate form with half-lies greater than 8 days in gaseous emuents exceedng the limts of Sedions 12.4.A3.1. or 12.4A3.2., prepare and submt a Special Report to the Commssion within 30 days and limt 9 h== ant releases sudi that the dose or dose wmiuiail to a member of the public from all uranium fuel sour s I

DRESDEN Revision 1.3 January 1997 12.4.A h m Effluarts Urnits and 4 -we Mhtv (Cont'd)

O Q -

is firnted to less than or equal to 25 rnern to the total body or organ (except the thyroid, which is iirrsted to less than or equal to 75 mrem) over 12 conseaJtive months. Blis Spedal Report shall indude an analysis which demonstrates that radiation exposures to all ice d= 5 of the public from all uranium fuel cyde sources (induding all effluent pathways and drect radiabon) are less than the 40 CFR Part 190 Standard Otherwse, obtain a varian from the Commission to permt releases whid1 ex ed the 40 CFR Part 190 Standard The radiation exposure analysis contaned

. in the Speaal Report shall use the methods prescnbed in the OOCM. This >

l report is in lieu of a tacensee Event Report

! 5. Process and control equipment prcmded to reduce the amount or

! concentrabon of radiosdie materiais shall be operated when the projected l dose due to gaseous effluents rh to the unreatnded areas, when averaged over 31 days, excoods 2% of the annual dose lirnts of Appendix l to 10CFR50 l

4. Off-Gas Treatment

1. At all times during promesing for decharge to the environs, process and control equipment provided to reduce the amount of concentration of radicadive matenais shall be operated

2. The abCNe speOficebon shall not apply for the Off-Ges Charcoal Adsorter Beds below 30 percent of rated themini pomer.

I 3. The remmtaner shall be operable wheneer the reactor is operating at a pressure greater than 900 peig.

4. 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. Wth other the recombiners inoperable, or all charcoal beds by-passed for l more than 7 days in a calender quarter vdiile operating above 30 percent of the rated thermal power, prepare and sLbmit to the Conmssion wthin 30 days a Speaal Report whidiindudes the follovsng iriuirson.

L a. Idenbficabon of the defedive equipment.

b. Cause of the defect in the equipment.

c. Adion(s) taken to restore the eqtipment to an operating status.

)

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

i

e. - Volume and curie content of the veste discie vod whid1 was not j gr- 1 the inoperable equipment but whidi regtired 7 by  ;

procesang.

1 I

12-31 l l i

~

l l

DRESDEN Ression 1.3 l January 1997 12.4.A hm Ehents Urrits and Reoortino nns_qbility (Cont'd)

f. Action (s) taken to preent a recurenm of equipment failures. Ol1 Ths is in lieu of a Uoensee Event Report.

5. Main Cuew Air Eiedor The release rate of the sum of the activities from the noble gases rneasured at the nun cxxidenser air ejector shall be lirrited to < 100 rricrocunes/sec per NW (after 30 rrinutes decay) when in modes 1,2', and 3' , Wth the release rate of the sum of the actMbes from noble gases at the rnain condenser air ejector effluent (as measured prior to the offgas hoidup line) > 100 niorocunes/sec per MM, after 30 ninutes decay, restore the release rate to within its firnts within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or be in l

at least STARTUP with the main steam isolation vanes dosed wittin the next 8 l hours. (Refer to Tedvical Speaficabon 3.8.1)

6. Svstem Miitv and Plant n-<aucrs in the ewnt a limit and/or assodated acdon requirements idendfied in Sections 12.4.A and 12.4.B cannot be satisfied W e of drcx,ioi.u:::i,in excess of those addressed in this Section, no d1arges are reqtired in the operational condition of the plant, and this does not preent the plant fmm entry into any operational mode.

O l

I l

'Wien the main condenser air ejector is in operatiort 12-32

i l

DRESDEN Revson 1.3 ,

Janusy 1997 l 124 B Gassous Effluents Sunmilanz l

1. Done Rate I The dose rates due to radicadive materials raiaamari in gareous effluents from the site shall be determned to be within the prescibed limts by obtaining  ;

representabve samples in Aued=Yei wth the sampling and analysis program  !

spoofied in Tab 6e 124-1. The dose rates are calctdated using methods prescnbed in the oOCM.

2 Noble Gas Dose The air dose due to releases d radoadive noble gases in gaseous emuents shall be detemined to be wthin the prescrrbed limts by obtaining representative samples in accordance wth the sampling and analyms program spoofied in Sedons A and B d Table 1241. The allocaton d effluents betmen unds having shaned effluent contrd system and the determnaton d cumulative and prqeded dose contribubans for the arrent calendar quarter and anent calendar year shall be detemined in acmrdanz with the ive udv;cgy and p--T_ s in the 00CM i at least once every 31 days.  !

3. ladins-131. lodins-131 Tritium and Parm rina. l The does to a member d the pubic due to releases of iodne 131, iodne-133, tritium, and all radionudades in partx:Liste form with half-lives greater than 8 days shall be determned to be wthin the prenaibed limits by obtaining raprL 4 6ve sarrpies in aa:ordance wth the sampling and analysis program spoofied in Table 1241.

I For radionudidos not determned in endi batch or weeldy w We, the dose mntnbuton to the cument anlender quarter cuminative summabon may be estimated by assuming an average nonthly concentrabon based on the previous monthly or quarterty u,vg analyses. HouMar, for reporting purposes, the calculated does contnbutions shall be based on the actual u,TpE analyses  ;

when pnanNa  !

The alloadion of emuents betman units having shared emuent contrd system and the detemiration of cumulative and prgeded dose contribubons for the current calender quarter and cunent calendar year disil te detemined in a. d.m with the iceudu;egy and p= =T_. in the oDCM at least once every 31 days.

4. off-Gas Treatmart Doses due to treated gases released to unrestnded areas at or beyond the site boundary shall be prqected at least once per 31 days in ayud w wth the ooCu 12-33

DRESDEN Revison 1.3 January 1997 12.4.B Gaseous Emuents Sunellance - Contiroed

5. Noble R= at the Main Condenser Air 8ector The release rate of noble gases frorn the rmin wn::iar air ejector shall be continuously monitored. The release rate of the surn of the actMties from noble gases from the rnain w ti:fii:( air ejector shall be dshwirnW to be wthin the linits of 12.4.A5 at the following frequences by perfoming an isotopic atyss of a representative sample of gases taken at the recombiner outlet, or at the air ejector outlet if the recombiner is by-passed

1. At least once per 31 days.

2. Wthin 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following detemination of an irxrease of greater than 504 (Refer to Technical Specrficaban 4.8.1)

O.

I 12-34

DRESDEN Revson 1.3 January 1997 i

ry TABLE 12.4-1 RADICACTIVE G'GEOUS V%STE SAMPUNG AND ANALYSIS PROGRAM UNIT 1 LCMER UMT OF GASEOUS SANFLING MNIMUM TYPE OF DETECTION (LLD)")

RELEASE FREQUENCY Al% LYSIS ACTNITY (pO/ni)

TYPE FREQUENCY ANALYSIS i A Main Prindpal Gamma 1x10' Chimney M Emitters

• y (Grab Sample) Tritium 1x10*

Noble Gases 1x108 M ")

M* 1x1gia

( ") lodne Sample l-131 I-133 1x10" MS M* Prindpal Gamma (Continuous) Particulate Sample Emmers

• 1x10"

. ( Q Q

--m Sr-89, Sr-90 1*IE,,

(Continuous) [g Gross Alpha

)

4 d

l l

DRESDEN Revsion 13 January 1997 l Table 12.4-1 RADIOoCTIVE CASEOUS WASTE SAhPUNG

)

AND NMLYSS PROGRAM UNITS 2 & 3 LCMER UMT GASEOUS SANPUNG MNIMUM TYPE OF ACTIVITY OF l RELEASE FREQUENCY ANALYSS ANALYSS DETECTION TYPE FREQUENCY (LLD)")(pCi/rri)

A kn Principal W

M M3 Gamma Emtiers(* 1x10' '

Bdg. (% W) Tritium 1x10' Vent Stack B. All gg43 W" l-131 1x10':

Release lodine Sample 1-133 1x105 as Principal Gamma ContiW') WM Usted Particdate Sample ers (5) 1x10" in A atx m Q Sr-89 1x10"  !

Continucxd') C uT r aia i Partxulate Sarmle Sr-90 1x10" Continuoudd)

O Gross Alpha m 1x10" Cm v_-_ . =_

Particulate Sarmle C. Main Continuoud') Noble Gas Monitor Noble Gases 1x10*

Chirmey D. Reactor Bdg.

Vent Continuoud') Noble Gas Monitor Noble Gases 1x10' Stack 12-36

DRESDEN Revsion 1.3

January 1997 I -TABLE 12.41 (Cont'd)

[

RADIOCTIVE GASEOUS VASTE SMNG '

AND ANALYSIS PROGRAM i TABLE NOTATION j -W The lour limt d detection (LLD) is defined in the ODCM.

!

• Sampling and W=.l,.c shall also be paismod following shutdown, startup, or a thermal pour i

diange exceedng 20 percent d rated thermal pcmer in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> unless (1) analysis shows that

! the dose equivalent 1-131 concentraton in the prirnary coolant has not increased more than a i fador of 5, and (2) the noble gas adivity monitor shows that effluent acewty nas not increased by more than a factor d 3.

• Sarmies shall be danged at least once per 7 days and the Wi

, i .; cxxmleted wthin 48 i hours aAer removal from the sargier. Sargling shall also be performed wthin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

! fdiowing and1 shutdown, startup, or thermed power leNel dlange am6ng 2@% of rated 1

thermal power in one hour. This requirement does not apply if 1) analyms shows that the dose equivalent 1-131 concentration in the primary coolant has not irnessed more than a factor of 5, j and 2) the noble gas adMty monitor shows that effluent adMty has not inaensed by more than a factor of 3. Wien sarmies ooiledad for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the &ampsiding LLDs

! may be increased by a factor of 10.

W The ratio of sargie flow rate to the sarmied stream flow rate shall be known.

l

!

• 1he prinopel game emitters for whidi the LLD specificalmn apples endusvely are the

folkming radonuddes. Kr-87, Kr-88, Xe 133, Xe-133m, Xe 136, and Xe-138 for gaseous i 3 } ensomns, and IWh-54, Fe-59, Co40, Zn46, Co 58, Mo.99, Co-134, Co-137, Ce-141, and f

Ce-144 for porticulate emocions. Other peaks whid1 are measurable and identifiable by gamma ray spedrometry, together wth the abowe nuddes, shall be also identified and reported vdlen an adual analyms is performed on a sargie Nuddes vdied1 are below the LLD for the W4,s.;.c. shall not be reported as being present at the LLD leNel for the nucide

• Analyas frequency shall be inaeemed to 1heek if reisene rates exceed 1% of any applicable limit referenced in the ODCM, vdien added to Units 2 and 3 arbome effluents.

l I

l

)

12-37

DRESDEN Reusion 1.3 January 1997 12.4.C Gaseous Effluents h

1. h = Effluents . rha, This Section is provided to ensure that the dose at the unrestricted area boundary from

' gaseous effluents from the units on site will be wthin the annual dose limts of 10CFR20 for unrestrided areas. These limts provide reasonable assurance that radioactrve material disd==ved in gaseous efliuents wil not result in the exposure of an individual in an unrestricted area to annual awrage risuin iu abons exceeding the limts specified in Appendx B, Table 2 of 10CFR20.1001-2402. The release ratelimts restrict, at all times, the unio.pordng ganma and beta dose rates above background to an indMdual at or beyond the unrestrided area boundary to less than or equal to 500 niemWar to the total body or to less than or equal to 3000 mromWar to the skin.

These release rate limts also restrict, at all times, the uaio.pcidng thyroid dose rate above background via the inhalation pathway to less than or equal to 1500 mrenhear.

For purposes of @A*Jn doses resulting from airtome releases, the main chimney is consdered to be an elevated release point and the reactor txilding wnt stack is consdered to be a mixed mode release point.

2. Dose Noble Gasas This Section is prtMded to implement the regtirements of Sectons 11.B, Ill.A and IVA of Appendx 1,10 CFR Part 50. The Operability Regtirements ir@lement the gudes set forth in Secton 11.3 of Appendx 1. The statements prtMde the reqtired operating flexibility and at the same time iirATa i the gudes set forth in Secton IVA of Appendix 1 to assure that the releases cif radioactw matenal in gaseous effluents will be kept "as low as is r;,J aretly adievable " The surveillance requirements implerrent the requirements in Seaban Ill.A of Appendix 1 that u.niunami.e with the gudes of Appendx 1 is to be shown by calculabonal procedures based on models and data such that the adual exposure of an indMdual through the appropriate patheys is unlikely to l be substanbally undensabmeted The dose calculabons established in the OOCM for calctiating the doses due to the actual release rates of radoacaw noble gases in i gaws = effluents will be consistent wth the methodology provded in Regulatory Gude 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents t for the Purpose of Evaluating Carmiiance with 10 CFR Part 50, Appendx 1," Revision i 1, Odober 1977 and Regulatory Gude 1.111, " Methods for Estimating Abruopiaic Transport and Disperson of Gaseous Efiluents in Routine Reieases from UghtMter Cooled Reactors," Revision 1, Jtiy 1977. NUREG0133 prtudes ir=0 uds for dose

@ d*Jns consstent with Regulatory Glades 1.109 and 1.111.

I 12-38

_ __ ._.__ _ _ ___ _ . _ . _ . - _ . _ _ . . _ . _ . - _ . _ _ . _ . _ _ _ __ _ _ __ _ _ .m. _

DRESDEN Rewsion 1.3

January 1997 l

l 12.4.C Gaseous Emuents Bones (Cont'd) l l 3. rw RM~vunes. R*-M t'Hal in Partin htm Form and RMm rMac Other than Noble Games i This Section is prtuded to irmiement the regtirements of Sections ll.C. Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Operability Reqtarements are the guides set forth in Section ll.C of Appendix 1. The statements prtMde the required operating flexibility and at the same time ir@iement the gudos set forth in Section IV.A of Appendix I to 1

assure that the releases of radoedive malenals in gaseous emuents will be kept "as j low as reasonably achievable " The ODCM calculabonal methods specified in the

! sunellance requrements implement the requirements in Sechon Ill.A of Appendx l that i

g, Ann w wth the gudos of Appendx 1 be show1 by calculabonal procedures based

on models and data such that the actual exposure of an indMdual through appropnate l pathmiys is unkkely to be substantWly undereebmeted. The ODCM cakulabonal

methods apprtwed by NRC for calculating the doses due to the adual release rates of the subjed metsnais are regured to be conomient wth the w.4 Q prcMded in Regulatory Glade 1.100. 'CalctAabon of Annual Domes to Men from Routine Releases i of Randor Emuents for the Rspose of Evaluabng Compliance wth 10 CFR Part 50, l Appendx I", Revmon 1, Odober 1977 and RegiAatory Gude 1.111 " Methods for j Estimating Almosphenc Transport and Disperson of naam = Emuents in Routine Reisenes from Ught-Wster-Cooled Reactors," Reumon 1 July 1977 These equabons i i also pnude for c_.n g the adusi doses bened upon the hatoncel average i atmosphenc condrhons. The release rate lirnts for radicioenes, radoedive material in

! perixxAate form and radionuddes other then noble genes are dependent on the i

existing radonudde pathusys to man, in the unreatncted area. The pathmeys whidi vere exarnned in the denlopment of these limits were: 1)indMdualinhalabon of airbome radonuddes, 2) deposeon d radonuddes onto green leafy vegetabon wth j = *=ar= =nt coneurmbon by man and 3) depombon onto grassy areas where mik j animals graze wth consumption of the mik by man.

• i l

l 4. Geneous Mhate Treatment

{ The operabihty of the geneous veele treatment whicti rat ran amounts or

! concentrabons d radiondre matenals ensures that the system will be avalable for use l wheneer gaseous amuents reqtare treatment prior to rolesse to the environment. The requirement that the appropnate portions of this system be operable when apaanari provides reasonable aneurance that the releases of radioedive metenals in gaseous emuents will be kept "as low as reasonably adioevable" This anar*=han implements

. the regurements of 10 CFR Part 50.36a, General Demgn Cn erion 60 of Appendx A to j 10 CFR Part 50, and desgn objedive Sedian ll.D of Appendx I to 10 CFR Part 50.

1 12-39 I

4 s

a

-w--- -. -

-,.m - - , . . - - . - wegw-<.,,.

DRESDEN Rewsion 1.3 January 1997 12.5 RADIOLOGICAL ENVIROMENTAL MONITORING PROGRAM A Radiokncal Ermrwnei i Moritsiru Proaram

1. The Radiological Envice T= 4 i Monitoring Program given in Table 12.5-1 shall be conducted except as speofied below.

2. Wth the Radiological Ermiersia dal Morntoring Program not being conducted as speofied in Table 12.5-1, prepare and submit to the Commsson, in the Annual RadiologK:ai Ermier ra dW Operating Report, a descripbon of the reasons for not conducting the program as requred and the plans for preventing a recurrence Deviabons are pan.e,d frem the required sanpling schedule if spedmans are unobtainable due to hazardous conditions, seasonal unavailability, contrador omsson vduch is corrected as soon as discovered, malfuncoon of sampling eqtipment, or if a person who ps 'ucipates in the program goes out of business. If the eqtipment malfunc6ans, corrective achons shall be compMted as soon as prac$ cal if a person supplying sanples goes out of business, a replacement supplier Wil be found as soon as possible.

All deviations from the sampling schedtie shall be descnbed in the Annual i Report I

3. V\ hen the level of ridicrctivity in an environmental sanpiing medium at one or more of the locabons speafied in the Table 12.5-1 ernaark the limits of the Table 12.52 when awraged over any calendar quarter, prepare and submt to the Corrmsman within 30 days from the end of the a#eded calendar quarter, a "fanal Report vdsch indudes an evaluabon of any release u,Wucrs, environmental fadors or other marwr* whKh caused the limits of the Table 12.5-2 to be eynaadad This report is not regtired if the measured lewi of fr.diciidivity was not the readt of plant effluents; houher in such an eent the condition shall be reported and described in the Annual Raddogical Envireoa44 Operating Report

4. Wth milk samples unavailable frorn one or more of the sanple locations required by Table 12.5-1, identify locabons for obtaining replacement sanpies and add them to the Radiologk:al Environmental Monitoring Pmgram within 30 days. The locabans from whch sanpies were unavailable may then be deleted from the monitoring prograrn in lieu of boensee Event Report, idenbfy the cause of the unavailability of sanples and idenbfy the new location (s) for obtaining replacement samples in the Annual Rrido;cgical EnvironmEnd Operating Report and also irdude in the report a revised figure (s) and teble refledire the newlocabon(s).

,n>.,_a. m.m.s. --~-<.~...--.a.. am.a... . , - . e w .s nn - . a. am rm s,.- s., u s n . u. mu as-- ws. a m. r.,m a. n _..saxn. 2.s ma.a u s a s m A.. , _.s u ,

j DRESDEN Revision 1.3 January 1997 i l

i~ 12.5.A RMw Erurer v.=id L-;Liiic Prcxram (Cont'd) i

! 5.

' A census of nearest resdences and of animals producing nilk for human consugbon shall be corw* r*=d annually (dunng the grazing season for animals) to detemine their location and number with reaped to the site. The i nearest residenz in each of the 16 ii ,_ viegical sedors shall also be determned within a chstance of fNG niles. The census shall be conducted under the following(zndrbons l i

) 1. Wthin a 2-nile radius from the plant site, enumerabon of animals and nearest residences by a door-to door or eqdvalent counbng technique.

4 1 2. Wthin a 5-mie radius, enumerabon of animals by using 1;&uid u aviii uvo from coLEtry agrK1AtLFal agerts or other reliable sourcxis.

3 i.

6. Wth a land use census idenbfying locahon(s) of animals whch yield (s) caloJiated done or dose commtment greader than the values currently being calm datad in Secton 12.4.A3, the new locabon(s) shall be added to Vie Radiologmal Ermronmental W.6 6 Program withm 30 days, if possible.

t The sampling locabon, having the lowest calcdated dose or dose commtment (via the same exposure pathney) may be deleted from this monrtoring program

! aAer n**wr 31 of the year in which this land use census was corv* rtad 4

7. . Radiologmal W ,a shall be performed on sagles representative of those in i

1

Table 12.51, supplied as a part of an Intertaboratory Cunvi1.On Rvy iu.

i

)

8. Wth analyses not being performed as regt.iired, report the corredive adions j taken to preent a recurrence to the Cvim sision in the Annual Radiologmal

Erwironmental Operstmg Report i

4

9. System Operability and Plant Operabons In the event a limit and/or maannasad adion requirements xientifled in Sec$ons 2

12.5.A and 12.5.B cannot be sabslied harnuma of drcumstances in excess of

those addressed in these Sectons, no dienges are required in the Opa.60nal i condibon of the plant, and this does not prevent the plant from entry into any operabonal mode.

i

! B. RN Erurenmental L-au.g Pmaram Stre mraga l {1 l 1. The radiologmal erwronmental n u.6 i sanples shall be collected pursuant to Table 12.5-1 from the locations speafled in the ODCM and shall be analyzed

pursuant to the requirements of Table 12.5-3.

}

4

't 1

12-41 i

3 1

1 4

r- - . .- - - - - 4 , , -, , - ,-- ,

DRESDEN Reusion 1.3 January 1997 l

l 12.5.B Radidoaical Erwire n se Ma uuiiic Suneillan (Cont'd)

2. The results d analyses pedsird on radidogical envire iraiW nunitonng sanpies shall be sum miad in the Annual Radidogical Envirc n oiw Operating Report

3. The land use census shall be conduded at least on per tvelve months between the dates d June 1 and October 1 by a door-to<ioor suney, aenal suney, road suney, or by consulting local agria.dture authonties.

4. The results d the land use census shall be induded in the A'nual Radidogical EnvireiTo64 Operating Report

5. The results d the analyses pafuire as part d the required Interlaboratory Conperison Program shall be included in the Annual Radidogical Environmental Operating Report The analyses shall be done in ac uuare wm ODCM Table 11-1.

1 O

i i

l 1242 1

.. - - - - - - . _ . - ~ _ . .. . -.. - . - - - - _- -..

DRESDEN Revision 1.3 January 1997 O

V TABLE 12.51 RADIOLOGICAL ENVIROMENTAL MONITORING PROGRAM MNIMUM NUNEER EXPOSURE PATHWAY OF sat #LES AND S% FLING AND TYPE AND AND/OR S4FLE S4#tE COLLECTION FREQUENCY OF LOCATIONS

• FREQUENCY ANALYSIS

1. AIRBORNE A Partictdates 17 locations Condnuous operation of Gross beta and gamma l

sarmier for a week isotopic as speofied in j ODCM Table 11-1.

l B. Radiciodne 17 locabons Continuous Op=duen of l-131 as speofied in sampier for two meks ODCM Table 11-1.

2. DIRECT 42 locabons (Mnimum Quarterly RADIATION of two TLDs per pedust)

3. VRTERBORNE A Surface Water 2 locabons MontNy wTyc.e of Gamma Isotopic meidy colleded samples analysis of ead) wivoie sartple O B. Sedment 1 downstreamlocaban in reoerving body of Ainually Gamma Isotopic analysis of eadi sanple water C. Rant Cooling

%hter intake, Discharge Wealdy Curyc.E Gross Beta analysis of eadisample

4. INGESTION A Mik 2 locahons At least onm me.dy when 1-131 analysis of each animals a aipasture; at sarmie least once per month at other times B. Fish 1 locabon in receiving Sernannually Garma Isotopic body of water analysis on edbie porbons

• Sample locabons are desenbed in ODCM Chapter 11.

1243

DRESDEN Revision t3 January 1997 Table 12.5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIROMENTAL SAhPLES l FOOD ANALYSIS V%TER AIRBORNE PARTICULATE FISH MLK PRODUCTS (poll) ,

OR GASES (pO/nf) (pOFG wet) (poll) (pO/Kg, wet)

H-3 2 X 10' (see Note 1)

Nh-54 1 X 10' 3 X 10' Fe-59 4 X 102 1 X 10' Co-58 1 X 10' 3 X 10' Co60 3 X 10' 2 X 10' Zn65 3 X 102 2 X 10' Zr-M>-95 4 X 102 1-131 2 0.9 3 1 X 102 Cs-134 30 10 1 X 10' 60 2 X 10' Cs-137 50 20 1 X 10' 70 2 X 10' .

Ba-La-140 2 X 102 3 x 102 Note: 1) For drinidng water sanpies. This is 40 CFR Part 141 value.

9 O - -

9

rw p. ^g

( (

DRESDEN Revision 1.3 January 1997 Table 12.5-3 PRACTICAL LOMER UMTS OF DETECTION (LLD) FOR STANDARD RADIOLOGICAL ENVIROMENTAL MONTORING PROGRAM (LLD)**

SAMElEDIA ANALYSIS (4.660) UMTS Antxxne "Partrolate" Gross Betaf" 0.01 pCMnfo Ganma Isotopc 0.01 pCi/nfG Autxxne 1-131 lodre131 0.10 pCi/nfA Mik/PLbicWiler 1-131 99 pCill Cs-134 10 pCill Cs-137 10[Q pCill Tritium 200 pCl/l Gross Belaf* 5 pCl/l Gamma Isotopo 20 pCWhudide Sedment Gross Betaf* 2 pCilg dry Ganma Isotopo 0.2 pCi/g dry Fish Tissue 1-133-Thyrod 0.1 pCi/g wet Cs-134,137 0.1 pCi/g wet Gross Beta /* 1.0 pCi/g wet Gamma isotopo 0.2 pCl/g wet Note:

W O.5 pCill on mik sarmies collected during the pasture seasort

(* Reference to Cs-137

(* 5.0 pCill on milk samples (Notes continued next two pages) 12-45 ,

I DRESDEN Ret 4sion 13 January 1997 i

Table 12.5-3 (Cont'd)

PRACTICAL LCMER LIMTS OF DETECTION (LLD) FOR STANDARD IBRlOLOGICAL F3MRCtMNTAL MONITOPJNG PROGRAM TAR F NOTATION

• The LLD is the smallest concentration of radoactiw material in a sample that will be detected with 95 pycent probability with only 5% probability of falsely conduding that a blank observation represents a "real" signal For a particdar measurement system (whKh rnay indude radoctemical separation) 4.66 - (Ss)

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

Vbere U.D is the "A priori" icmer limit of detechen for a blank sanple or background analysis a defined abam (as pCi per unit mass or volure).

S5 is the scluare root of the badground munt or of a blank sanple cod is l the estimated standard error of a background count or a blank sanple count as appropriate (in units of counts).

E is the counting emoency (as munts per dsintegration).

A is the number of ganma rays omrtted per dsintegration for gamma ray radonudide analysis (A = 1.0 for gross alpha and tntium measurements).

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

2.22 is the number of dsintegrat,ons per ninute per picocune Y is the fradional risdicc%rksi yield when applicable (otherwise Y=1.0). l l

1 is the radicadrve decay constant for the particular radonudide (in units  !

of reciprocal ninutes).

at is the elapsed time between the mdpoint of sanple collection and the start time of counting. (t = 0.0 for envine.mrdd samples and for gross alpha measurements).

t is the duration of the count (in units of ninutes).

The value of "S3"used in the calculation of the LLD for a detedian system shall be based on an adual observed background count or a blank sample count (as appropriate) rather than on an unverified theorebcally predcted value. Typical values of "E", 'V', 'Y', "t", and "ot" shall be used in the calcdation.

12-46

1 DRESDEN Rewsion 1.3 January 1997

!O Table 12.5-3 (Cont'd)

PRACTICAL LOMR UNITS OF DETECTION (LLD) FOR STANDARD RADIOLOGICAL ENVIROMENTAL MONITORING PROGRAM l TABLE NOTATIONS

. For gamma ray radionudide analyses the badground counts are determned frorn the total  :

i counts in the channels whid1 are wthin plus or minus one FVA4A (Fdi Wdth at Half Maximum) i of the gamma ray photopeak energy normally taed for the quanbtative analysis for that radonudide. Typical values of the FVeN shall be used in the calculation.

The LLD for all measurements is defined as an "A priori" (before the fact) limt representing the

capability of a measurement system and not as an "a posteriori"(after the fact) limt for a j partimlar sarmie measurement. .

• Other radonuclides whid1 are measurable and idenbfiable by ganma ray Wwroby, together wth the nudides indk:sted in Table 12.5-3, shall also be identi6ed and reported when an actual analyss is pefvormd on a sample Nuclides whKh are below the LLD for the

, analyses shall not be reported as being present at the LLD level for that nudide.

i l

i f

(/

l 1

i i

12-47

DRESDEN Redsson 1.3 January 1997 l

1 12.5.C Radioloaical Enviru.y-d ; Wituirg Proaram h 0

1. Muntuiirg Proaram The radiological envite n a dai monitoring program required by this Section provides

! measurements of radation and of radioactNe materials in those exposure pathways l

~

and for those radonudides, which lead to the highest potenbal radiation exposures of individuals resulting from the station ef=av0i. This monitoring program thereby l

supplements the radiological emuent monitoring program by venfying that the measurable concentrations of radoadive matenals and lewis of radiation are not higher than aww*=d on the basis of the emuent measurements and modeling of the envirs sia M exposure pathways Program changes may t:e '.JJtiated based on operational expenence The detection capabilities reqdred by Table 1253 are state of-theHrt for routine enviiu na dai measurements in industrial lai.saiuies. The specdied kmer limits of detecbon for 1-131 in water, milk and other food products u,w;ut to approximately onegaarter of the Appendx I to 10 CFR Part 50 desgn objectiw doseapvalent of 15 mremWar for ahim piaic releases and 10 mrer# year for liquid releases to the most sensitive organ and indv6 dual They are based on the assumptions given in Regulatory Gude 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reador Emuents for the Purpose of Evaluating Cormiiance with 10 CFR Part 50, Appendix I",

October 1977, except the change for an infant consuming 330 liter / year of drinking veter instead of 510 litenvyear

2. Land Use Census This Secbon is provided to ensure that dianges in the use of unrestrided areas are idenbfied and that modificabons to the monitoring program are made if required by the results of this mnsus. This mnsus satisfies the requirements of Sedion IV.B.3 of Appendx 1 to 10 CFR Part 50.

3. Ire 1.bu.iuv Cururrmeii Proaram lhe requirement for partopabon in an InteriabuaiO~y Cormarison Program is provided to ensure that independent checks on the precision and acuracy of the measurements of radoadiw material in enviiu n a dai sample matrims are perfe u ad as part of the quality assurance program for environmental monitoring in order to days obaie that the resdts are ree uiatiy valid.

l l

. . , . _ _ . _ . _ . _ . . _ = _ _ _ . _ _ _ . _ _ . _ . _ . _ . _ _ . _ . . . _ . _ _ _ _ . _ . _ _ _ _ . _ _ _ _ . . _ _ _ _ _ _ . _ _ _ . _ _ _ . . _ . _ _ _ . .

DRESDEN Revision 1.3 January 1997 i'

i l 12.6 RECORDKEEPING AND REPORTING

1. Staban Operahng Remds l.

l 1. Records and/or logs relatiw to the following items shall be kept in a manner

convenient for review and shall be retained for at least five years.

l 1. Records and penode checks, inspection and/or calibrations poitis

.to wrify the surveillance regtirements (See the applicable sunellan l in the Instn,r= 4.Wri, Uquid Effluents, Gaseous Emuents, and Radiological Ermronmental Moratoring Seebons) are being met. All

! equipment failing to meet sunmilanm requirements and the comediw j acton taken shall be recorded.

! 2. Records d radioactNe shipments.

L

! 2. Records and/or logs relatne to the folloung items shall be remrded in a

j. menner mnvenient for review and shall be retained for the life d the plant.

i 1. Records d df-site environmental monitoring suneys l

2. Records d radioedsty in liquid and & = westes released to the environment, s

3. Records d reviens performed for changes made to the ODCM.

2. Reports

1. Radioacte Effluent Release Report The Radoedne EM Release Report cowenng the operabon d the unit dunng the pnyvious 12 months of operaban shall be sutmtled to the Conmssion prior to April 1 d oech year. The report shall indude a sunrnary d the quantities d radoedNo liquid and gaseous emuents and solid waste rolessed from the unit. The malarial pn:Mded shall be(1) mnaistent with the objedives oulkned in the ODCM and PCP and (2) in nan co with 10 CFR Part 50.36e and Sedian IV.B.1 of Appendx I to 10 CFR Part 50. l

2. Annual Radological Environmental Operabng Report The Annual Radioicgcal Erh Operating Report ocMiring the opersbon of the unit dunng the pnmous calender year shall be submrtted prior to May 1 d each year. The report shall indude sumenes, irnerpnstabons, and analysis of trends of the reeldts of the Radiological Environmental Monitoring Program for the reporting penod. The metanal pn:Mded shall be consistent with the objednes in (1) the OOCM and (2) Sechons IV.B.2., IV.B.3, and IV.C of Appendix to 10 CFR Part 50. Ah listing of the requirement of the report is given below 12-49 e

- - ,- r

. .. . ._ --- - ._ ~ - -.

DRESDEN Reusion 1.3 January 1997 12.6.2 Reports - Continued (a) Results of erurv-ara dai sampling summanzed on a quarterty tes fdlowing the format of Regulatory Guide 4.8 Table 1 (Decarter 1975);

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

in the eent that some results are not available for indusion with the report, the report shall be sutmtted noting and explaining the reasons for the nissing results. Suninanes, interpretations, and analysis of

! trends of the results are to be provded (b) M -ement of the montoring results and radiation dose via the prinapal pathways of exposure resulting from plant errissions of radioactivity irduding the rinximum noble gas gamma and beta air i

doses in the unrestnded area. The assessment of radiation doses t

shall be pa iuu =d in suud.n= with the ODCM.

(c) Results of the mnsus to detemine the locations of animals producing l rnik for human consumphon, and the pasture season feeding practices i j at dairies in the monitoring progrant 1

(d) The reason for the omission if the nearest dairy to'the station is not in

the nonstoring guy n (e) An annual summary of n aimiciegicai 0sivatkn 6 concurrent with the reiamaan of gaseous effluents in the form of joint frequency distributions i of Wnd speed, wind diredion, and ain ampimiic stability.

The results of the interlatu aluy u.niymi=O7 program descnbed in (f)

Sedian 12.5.A7.

(g) The restits of the 40 CFR Part 190 uraniurn fuel cyde dose analysis for each calendar year.

(h) A summary of the monitoring geymit indudng maps showing sarnpling 10gidu 6 and tables giving dstan and drection of sanpling 100,iic 6 from the statiort

3. Nor> Routine Envk0 o a de Report (a) If a v.n siired measured radionudide concentration in an envirc irantal sampling modum averaged car any calendar quarter sanpling period an=ria the reporting level ginn in Table 12.5 2 and if the radioactivity is attributable to plant operation, a vwitten report shall be submtted to the Regonal Administrator of NRC Regonal Omoe, with a copy to the credor, Omoe cf Nuclear Ra=*r Regulation, witNn 30 days from the end of the quarter % hen more than one of the radonudides in Table 12.5-2 are detaded in the medum, the reporting lemi shall have been exceeded if IC/(RL), is equal to or greater than 1 vdwre C is the conmntration of the i* radonudide in the medium and RL is the reporting lewi of radonudide i.

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12.6.2 Reports-Continued (b) If radionudidos other than those in Table 12.5-2 are detected and are j due to plant effluents a reporting lewl is exrmadad if the potential annual dose to an indivUual is equal to or greater than the desgn l

objedive doses of 10 CFR Part 50, Appendix 1..

(c) 'ihis report shall indude an evaluabon of any release conditions.

environmental factors, or other mapar* necessary to explain the

,- anomalous affect.

l' 12.6.3. Offsite Dose Caledaban Manual (ODCM) l 1. The OOCM shall contain the n-Giedvicgy and parameters used in the j calculaton of offste doses due to radmache gaseous and liquid effluents and

in the calculabon of gaseous and liquid effluent monitoring AlarmTrip setpoints i and in the conduct of the Radiological Eruronmental Monitoring Prograrn The

! ODCM shall also contan (1) the Radmediw Eduent Controls and Radologmal l Enwonmental Monitonng Programs deaalbed in Sechon 12.2 - 12.5 and (2) i desaiphons of the informsbon that should be induded in the Annual

! Radmiogmal Enwonmental Operstmg and Radmedive Effluent Release

! Reports requred by Sectons 12 6.2.1 and 12.6.2.2.

F

- The OOCM shall be subjed to rtMew and approval by the Commission prior to j initial implementaban.

l 2. Changes to the OOCM N

l (1) Shall be doornented and records of reviews imdvin ad shall be j retained as requred by Tactincal Sp.JcaG06 6.14A This i documentaban shall conten.

l' (a) Suffloent informsbon to support the cfiange together with j appropnale W l,n or evalustons jushfying the d1ange(s); i

, and l (b) A determneten that the dienge will rnaintain the lewl of

! ratsoedia effluent control requred by 10 CFR Part 20.1302, l 40 CFR Part 190,10 CFR Part 50.36e, and Appendx i to 10

CFR Part 50 and not adersely inped the accuracy or reliability of effluent, dose or set point calculabons i

I (2) Shall be effective after rtMew and acceptanz by the Onsite Review &

l Irweebgabw Functon and the appnwal of the Staten Manager, on the d

date spealled by the Onste Review and Irwesbgetive Funcbon

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12.6.3 Offsste Dose Caledation Manual (ODCMWCont'd)

(3) Shall be submitted to the Commssion in the fomn of a corrplete, legible copy of the endre ODCM or updated pages, if the Commssion retans a controlled copy. If an entire copy of the ODCM is submtted, it shall be submtted as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made effedive Each change shall be identified by rnarkings in the margin of the affected pages, dearly indicating the area of the page that was OWged, and shall indicate the date (e.g.,

month / year) the d1ange was implemented.

12.6.4. Maior Chanaes to Radinx*ve Vhta Trn-d Systems (Lund and R ~m) l NOTE This information rnay be submitted as part of the annual FSAR update.

)

1. Ucensee initiated maior changes to the radioactive waste systems may be made prtuded The change is reported in the Monthly Operating Report for the period in which the evaluation was rewewed by the Orh9te Review and Inestigative Function.

The dscussion of ead1 change shall contart (1) A sunmary of the evaluation that led to the deternination that the change cxxAd be made in au.udi @ with 10 CFR Part 50.59; i

(2) Suflicient detailed iiiu n = lion to support the reason for the change, (3) A detailed description of the eqtipment, cuYpuws, and process  !

inwled and the interfaces with other plant systems, I l

(4) M evaluabon of the change which shows the predicted releases of radioactve materials in liquid and gaseous effluents that differ from those prewously predicted in the license application and e.Tu-drents; (5) A conperison of the predded reim of ii fsictiw materials in liquid l and pm ef!Iuents to the actual releases for the period in whidi the l changes we made, l

(6) M estimate of the exposure to plant operating p6ws mi as a result of the change; and (7) Documentation of the fact that the change was rewewed and found  !

m --jde by the Orx9te Review and Irwesbgative Function.

2. The change shall become effechw upon rewsw and av =pu= 2 by the On-Site l

ReMew and Invesbgabe Functon. l l

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