Text

Revs to ODCM for Quad Cities,Including Rev 1.8 to Chapters 10,11,12 & App F
	ML20216H884
Person / Time
Site:	Dresden, Quad Cities
Issue date:	06/30/1996
From:	; COMMONWEALTH EDISON CO.
To:	;
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ML20216H409	List: ML20216H404; ML20216H432; ML20216H824; ML20216H855; ML20216H869; ML20216H884; ML20216H904;
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QUAD CmES Rsvision 18 Juns 1996 QUAD CITIES ANNEX INDEX

[EGE REVISION CHAPTER 10 t 10-i 1.8 10-il 1.8 10-iii 1.8 10-iv 1.8 10-v 1.8 10-1 1.8 10-2 1.8 10-3 1.8 10 4 1.8 10-5 1.8 10-6 1.8 10-7 1.8 10-8 1.8 10-9 1.8 10-10 1.8 ,

10-11 1.8 10-12 1.8 10-13 1.8 10-14 1.8 l

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QUAD CITIES Rsvision 1.8 Juna 1996 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS PAGE l NUMBER 10.1 AIRBORNE RELEASES. . ... . . . . . . . . . . . . . . . . . ....... . . 1

1. System Description.. . . . . . . . . . . . . . . . . . . . ... .1

1. Condenser Offgas Treatment System.. . . . .. . . .. 1

2. Ventilation Exhaust Treatment System.. . . . . 1

2. Radiation Monitors.. . . . .. . . . ... . . . . 1

1. Plant Chimney Monitor. . .. . . . . . . .. .. . . 1

2. Reactor Building Vent Stack Effluent Monitor.. .... 2

3. Reactor Building Ventilation Monitors.. . . . . . . . . .. .. 2

4. Condenser Air Ejector Monitors... . . . . .. . 2

3. Alarm and Trip Setpoints. .. . .. . ... . . . . . . . . . . . . 3

1. Setpoint Calculation.. .. . . .. ... . . . . .. 3

1. Reactor Building Vent Stack Monitors. ... .. . . . . . . . . . . . . . *3

2. Condenser Air Ejector Monitors.. .. . . . . . . . . 3 l 3. Plant Chimney Radiatien Monitor. .. . .. . 3

2. Release Limits. . . . 3 l .. . .. . ... . . . . . . . . . .... . .

3. Release Mixture.. . . . . .. .. . .. . . . . . . 4 I

4. Conversion Factors .. . .. ... . . . . . . . . . . . . . 4 l

5. HVAC Flow Rates.. . . . . ... . . . . . . . 5

4. Allocation of Effluents from Common Release Points. . .. .. . . 5

5. Dose Projections... . . . . . ... 5 l

10-ii

QUAD CITIES RLvision 18 Juna'1996 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS (Cont'd)

NUMBER PAGE 10.2 LIQUID RELEASES.. . . . .. . . . . . . . . . . .. 6

1. System Description.. .. . .. . ... . . 6

1. River Discharge Tank.. .. . ... .. ... 6

2. Radiation Monitors.. . . . . . . . . . . ... 6

1. Liquid Radwaste Emuent Monitor... . . . . 6

2. Service Water Emuent Monitors.. . . . . . . ... ... . 6 l

3. Alarm and Trip Setpoints. .. .. . . . . .. . . . . . . . . . . 6

1. Setpoint Calculations. . . . . . . . . . . . . ....... . ..... .. 6

1. Liquid Radwaste Effluent Monitor... . . . . . . . 6 l 2. Service Water Effluent Monitors. .. . . . . 7

2. Discharge Flow Rates.. . . . . . .. . . . . . . . . ,8

1. Release Tank Discharge Flow Rate.. . . ... . . .. . .. . 8

3. Release Limits . . . . . . . . . 8 l

4. Release Mixture.. . . . . . . . .. . . . . . . 9

5. Conversion Factors . . . . . . . . . . . . . . .. 9

6. Liquid Dilution Flow Rates. . . .. . 9

4. Allocation of Effluents f:om Common Release Points. . . . . . . 9

5. Projected Concentra+ ions for Releases. . . .. . . 9 l

10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM . . 10 l

I l

{

10-iii

QUAD CITIES RIvision 1.8 Juna 1996 LIST OF TABLES ,

- None -

l 10-iv

QUAD CITIES Rsvision 18 Juns 1996 CHAPTER 10 i- RADIOACTIVE EFFLUENT TREATMENT AND MONITORING LIST OF FIGURES NUMBER PAGE 10-1 Simplified Gaseous Radweste and Gaseous Emuent Flow Diagram 10-11 10-2 Simplified Liquid Radwaste Processing Diagram 10-12 10-3 Simplified Liquid Effluent Flow Diagram 10-13 10-4 Simplified Solid Radwaste Processing Diagram 10-14 l

)

1 10-v l

l QUAD CITIES Rsvision 1.8 Juna 1996 1

CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1 System Description A simplified gaseous radwaste and gaseous effluent flow diagram is provided in Figure 10-1.

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

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' 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 11.3.2.1.1 of the Quad Cities UFSAR. ,

Ventilation Exhaust Treatment System 10.1.1.2 Ventilation exhaust treatment systems are designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in selected effluent streams by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters prior to release to the environment. Such a system is not conside ed to have any ef'ect on noble gas effluents. The ventilation exhaust treatment systems are shown in Figure 10-1.

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

10.1.2 Radiation Monitore 10.1.2.1 Piet t Chimney Monitor Monitors 1(2)-1730A/B continuously monitor the final effluent from the chimney.

The monitor system has isokinetic sampling, gaseous grab sampling, iodine and particulate sampling, and tntium sampling capability.

10-1

QUAD CITIES Rsvision 1.8 Juna 1996 g The chimney effluent is also monitored by a separate particulate, iodine, and noble gas (SPING-4) system and a Victoreen system. The SPINGNictoreen system has high range capabilities to deal with accident conditions including postaccident sampling capability.

The Victoreen sampling system automatically begins taking samples after a high signal has been received on the SPING-4 low range noble gas monitor. Output from the SPINGNictoreen system is obtainable in the control room.

No automatic isolation or control functions are performed by these monitors. Pertinent information on these monitors is provided in the Quad Cities UFSAR Section 11.5.2.3.

10.1.2.2 Reactor Building Vent Stack Effluent Monitor The combined reactor buil6ng ventilation is also monitored by a SPING-4. This monitor has high range capabilities to deal with accident conditions. The SPING-4 noble gas detectors have ranges that envelope the range for the reactor building vent effluent trip -

point.

The vent stack monitor has isokinetic sampling and iodine and particulate sampling capability.

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

j Pertinent information on this monitor is provided in the Quad Cities UFSAR Section 11.5.2.4.

10.1.2.3 Reactor Building Ventilation Monitors Monitors 1(2)-1735A/B continuously monitor the effluent from the Unit 1(2) reactor building. On high high alarm, the monitors automatically initiate closure of valves A01(2)A-5741, A01(2)B-5741, A01(2)A-5742, and A01(2)B-5742 thus isolating the Unit ,

1(2) reactor building, and initiate startup of the Unit 1(2) standby gas treatment system.

and isolates control room HVAC.

In addition to the above monitors, there is continuous iodine and particulate sampling of the reactor building exhaust.

Pertinent information on these monitors is provided in Quad Cities UFSAR Section 11.5.2.4.

10.1.2.4 Condenser Air Ejector Monitors Monitors 1(2)-1733A/B continuously monitor gross gamma activity downstream of the steam jet air ejector and prior to release to the main chimney.

On high high alarm the monitors automatically activate an interval timer which in turn initiates closure of air operated valve A01(2)-5406, thus terminating the release.

In addition, monitors 1(2)-1741 continuously monitor the final offgas effluent prior to entering the chimney, and monitors 1(2)-1738 continuously monitor gross gamma activity downstream of the steam jet air ejector. No control device is initiated by these monitors.

10-2

QUAD CITIES Rrvision 1.8 Juna 1996 Pertinent information on these monitors is found in Quad Cities UFSAR Sections 11.5.2.1

and 11.5.2.2.

/

10.1.3 Alarm and Trip Setpoints 10.1.3.1 Setpoint Calculations 10.1.3.1.1 Reactor Building Vent Stack Monitors The setpoint for the reactor building vent stack monitor is conservatively set at 2 mr/hr above background. The reactor building ventilation stack release rate, Q , at 2 mr/hr is calculated to be 14,400 pCi/sec. Q. is then substituted into Equations 10-1 and 10-2 to l

determine Q..

l 10.1.3.1.2 ,

Condenser Air Ejector Monitors The high-high trip setpoint is established at $100 Ci/sec per MWt (=2.5E5 Ci/sec) and the high alarm is established at $50 Ci/sec per Mwt (=1.25E5 Ci/sec).

10.1.3.1.3 Plant Chimney Radiation Monitor The setpoints for the plant chimney radiation monitor are conservatively set at 10,000 pCl/sec and 20,000 Ci/sec (high and high-high alarms respechvely).

At this level the combined release from chimney and vent is approximately 10% of the RETS limit. This is determined by solving Equations 10-1 and 10-2 below. ,

10.1.3.2 Release Limits Alarm and trip setpoints of gaseous effluent monitors are established to ensure that the release rate limits of RETS are not exceeded. The release limit Q is found by solving Equations 10-1 and 10-2.

(1.11)I(f, [Q.S, + Q VJ } < 500 mrem /yr (10 - 1:

I (I., f, [ (X/Q), Q. exp (-AR/3600u.) + (X/Q),0 exp (-AR/3600u,)] (10 2;

+ (1.11)(f.)[Q.S,+ Q VJ} < 3000 mremlyr The summations are over noble gas radionuclides i.

f, Fractional Radionuclide Composition l

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

10-3

QUAD CITIES Revision 1.8 Junn 1996 Q. Total Allowed Release Rate, Stack Release ( Ci/sec]

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

Ou Total Allowed Release Rate, Vent Release (pCi/sec)

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

The remaining parameters in Equation 10-1 have the same definitions as in Equation A-8 of Appendix A. The remaining parameters in Equation 10-2 have the same definition as in

- Equation A-9 of Appendix A.

Equation 10-1 is based on Equation A-8 of Appendix A and the RETS restriction on whole body dose rate (500 mremlyr) due to noble gases released in gaseous affluents (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 mremlyr) due to noble gases released in gaseous effluents (see Section A.1.3.2 of Appendix A).

The value of Equation 10-1 (2.3 x 10' Ci/sec) is used as the limiting noble gas release rate. ,

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

10.1.3.3 Release Mixture in the determination of alarm and trip set points the radioactivity mixture in the exhaust air l Is assumed to be the same as the analysis of a representative sample of noble gases collected at the recombiner during the calendar quarter in which the monitor is recalibrated.

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

Reactor building vent efflut 4 :nonitor.

The monitor setpoint is established at 2 mr/hr above background. For the purpose of setpont determination it is assumed that the background is 1 rnt ~<

There is sufficient conservatism in the setpoint calculation to accommodate ,

routine variations in the background. However, the isotopic analysis in Sect:cn l 10.1.3.3 is used to confirm that the setpoint is conservative.

1 Condenser air ejector monitor.

The isotopic analysis in Section 10.1.3.3 and the flow and monitor reading at the time of the analysis are used to establish the conversion factor.

10-4 l

l

QUAD CITIES R& vision 1.8 Juns 1996 Plant chimney monitor.

Calibration of the plant chimney monitor consists of recirculating an amount of off-gas (see 10.1.3.3) through the noble gas monitors and a Marinelli beaker.

After readings have stabilized, the Marinelli beaker is removed and gamma isotopic analysis performed. The efficiency is determined from a plot of average gamma energy of the off-gas sample and net monitor readings.

10.1.3.5 HVAC Flow Rates The HVAC exhaust flow rates may be obtained from the process computers, indication in the control room, or fan combinations. Setpoints were calculated using the following values:

Chimney Air Flow . .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . 350,000 cfm Combined Reactor Vent * (1 fan) . ...... . ... . .. .. .. . ..... . . .... 48,000 cfm Combined Reactor Vent * (2 fans) .... ..... . . . ......... . ... . . 96,000 cfm

per unit 10.1.4 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the main chimney are comprised of

contributions from both units. Under normal operating conditions, it is difficult to l

allocate the radioactivity between units due to fuel performance, in-plant leakage, l power history, and other vanables. Consequendy, allocation is normally made evenly between the units. During extended unit sh'utdowns or penods of known differences.

l the apportionment is adjusted accordingly. The allocation of effluents is estimated on ..

a monthly basis.

{

! 10.1.5 Dose Projechons l

l Because the gaseous releases are continuous, the doses are routinely calculated m accordance with the RETS.

l 10-5 I

___a

QUAD CITIES Rsvision 1.8 Juna 1996 10.2 LIQUID RELEASES 10.2.1 System Description Simplified liquid radwaste and liquid effluent flow diagrams are provided in Figures 10-2 and 10-3.

The liquid radweste 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 domineralizer for the purpose of reducing the total radioactivity prior to release to the environment. The system is described in Section 11.2 of the Quad Cities UFSAR.

10.2.1.1 River Discharge Tank There is one river discharge tanF. (65,000 gallons capacity) which receives water for discharge to the Mississippi River. This is the only release path in use.

10.2.2 Radiation Monitors 10.2.2.1 Liquid Radwaste Effluent Monitor Monitor 1/2-1799-01 is used to monitor all releases from the river discharge tank. Dn high alarm the release is terminated manually.

Pertinent information on the monitor and associated control devices is provided in Quad Cities UFSAR Sections 11.5.2 and 11.5.3.

l 10.2.2.2 Service Water Effluent Monitors Monitors 1(2)-1799-01 continuously monitor the service water effluent. No control device is initiated by these monitors.

Pertinent information on these monitors is provided in Quad Cities UFSAR 11.5 3 10.2.3 Alarm and Trip Setpoints 10.2.3.1 Setpoint Calculations Alarm and trip setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of RETS are not exceeded in the unrestncted area.

I Currently these setpoints are based on the most conservative releases during the l previous 18 months. If it is determined that tie N no longer conservative, the setpoints are reevaluated.

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

10-6

! QUAD CITIES Rsvision 1.8 I Junn 1996 l P s (K) x [E C,' / I(Cf /10*DWC,)] x ((0.5 F%o + F' ) /F' ]'+ B (10 - 3) ..

P Release Setpoint [ cpm)

C[ Concentration of radionuclide iin [pCi/ml]

the release tank.

F' , Maximum Release Tank Discharge Flow Rate [gpm]

The flow rate from the radwaste discharge tank. i K Calibration constant (cpm /pCi/ml] l DWC, Derived Water Concentration of radionuclide i (pCi/ml)

From Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402.

10' Multiplier granted in Technical Specifications applied to the DWC l

Average dilution flow of initial dilution [gpm)

F%o stream B Background Count Rate [ cpm) 10.2.3.1.2 Service Water Effluent Monitors The monitor setpoint is found by solving equation 10-4.

C P 5 (K) x [I Ci / E (Ci /10*DWC,)] x [(F%o + F' ) / F'M + B (10-4) i l

C, Concentration of radionuclide lin service water if there is no detectable activity then EC/E(C/10*DWC,) is assumed 4

to be 1 x 10 Ci/ml.

F' , Maximum discharge rate of service water for one unit. [gpm]

All other terms are as defined in equation 10-3.

The 10 multiplier may not be used prior to Technical Specification approval.

l 10-7

QUAD CITIES Rsvision 1.8 Juna 1996 10.2.3.2 Discharge Flow Rates j l

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:

F'. = 0.1 (0.5 F' / I(C /10*DWC,))

i (10-5)

The summation is over radionuclides i.

0.1 Reduction factor forconservatism.

i F' , Maximum Permtted Dacharge Flow Rate [gpm)

The maximum permitted flow rate from the radweste discharge tank. i d

F Dilution Flow [gpm)

Ci Concentration of Radionuclide i in the Release Tank [ Ci/ml]

The concentration of radioactivity in ,

I the radweste discharge tank based on measurements of a sample drawn from the tank.

DWC, Derived Water Concentration of radionuclide i [ Ci/mi)

From Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402.

l 10' Multiplier granted in Technical Specifications applied to the DWC 10.2.3.3 Release Limits Release limits are determined from RETS. Calculated maximum permissible discharge rates are divided by 10 and dilution flows are divided by 2 to ensure that releases are well below applicable limits. (The factor of 2 used in the dilution flows accounts for discharging the RDT tank to the south diffuser pipe).

The 10 multiplier may not be used prior to Technical Specification approval.

10-8

QUAD CITIES Rsvision 1.8 Jun31996 10.2.3.4 Release Mixture For the liquid radwaste effluent monitor the release mixture used for the setpoint determination is the radionuclide mix identified in the grab sample isotopic analysis {t plus four additional radionuclides. The additional radionuclides are H-3, Fe-55, Sr-89, and Sr-90. The quantities to be added are determined using scaling factors denved from station release data for the previous six months.

10.2.3.5 Conversion Factors The readout for the liquid radwaste effluent monitor is in CPM. The calibration constant is based on the detector sensitivity to Cs-137.

10.2.3.6 Liquid Dilution Flow Rates The dilution flow is determined using Equation 10-6 below.

8 F = (N" x F" + N" x F" - F'C') (10-6)

F' = Dilution flow (gpm)

N" = Number of circulating water pumps on.

F" = 157000 gpm Flow with one circulating water pump on.

N" = Number of service water pumps on

F" = 13800 gpm Flow with one service water pump on i

F ca = Deicing flow 10.2.4 Allocation of Effluents from Common Release Points ,

't' Radioactive liquid effluent released from the release tank is comprised of contributions from both units.

Allocation of waste is achieved by comparing the pump timer totals for each unit's floor drain and equipment drain pumps to the amount of waste sent to the river discharge tank from the floor drain and waste collector storage tanks. Liquid effluerts from laundry and chemical waste are allocated evenly between units. During extended unit shutdown or periods of significant plant input differences, the apportionment is adjusted accordingly. The allocaton of the effluents is made on a monthly basis.

10.2.5 Projected Concentrations for Releases if total DWC is greater man 25, the projected dose due to liquid effluent releases is calculated. Otherwise, the releases from the previous month are used to estimate trie projected dose for the coming month using the methodology in Seebon A.2 of Appendix A. (See Section A.2.1 of Appendix A).

10-9

i QUAD CITIES Rsvision 1.8 )

Juna 1996 1 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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l l QUAD CITIES Rtvision 1.8 Juns 1996 l CHAPTER 11 Quad Cities Annex Index PAGE REVISION 11-i 1.8 11-ii 1.8 11-1 1.8 11-2 1.8 11-3 1.8 11-4 1.8 !

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11-i

QUAD CITIES R& vision 1.8 l Juna 1996 CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Table of Contents PAGE Radiological Environmental Monitoring Program 11-1 List of Tables NUMBER IIILE PAGE 11-1 Radiological Environmental Monitoring Program 11-2 Uniform Radiological Environmental Monitoring Program 11-9.

l 11-ia 11-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 11-16 11-3 Practical Lower Limits of Detection (LLD) for Standet Environmental Radiological Monitoring Program 11-17 -

I List of Figures NUMBER TITLE f%GE Fixed Air Sampling Sites and Outer Ring TLD Locations 11-20 11-1 inner Ring TLD Locations 11-21 11-2 Milk, Fish, Water, and Sedb.aat Sample Locations 11-22 11-3 l

11-ii

~

l QUAD CITIES Revision 1.8 Juna 1996 l

, CHAPTER 11 Radiological Environmental Monitoring Program l The radiological environmental monitoring program for the environs around Quad Cities Station is l presented in Table 11-1. Figures 11-1 through 11-3 show sampling locations and monitoring locations.

The reporting levels for radioactivity concentrations in environmental samples are given in Table 11-2.

The practical lower limits of detection for this program are given in Table 11-3.

l The Quad Cities Technical Specification are currently in the process of being upgraded. And, as part of l the upgrade, the specifications which govem the Quad Cities Radiological Environmental Monitoring l Program (REMP) are being removed from the Technical Specifications and relocated within the Quad l Cities Chapter 11 and 12 of the ODCM. After this approval, Quad Cities Station will simply determine l the date to begin implementation of the Uniform Radiological Environmental Monitoring Program which l is specifically described in Chapter 9 of ODCM and detailed in this Chapter within Table 11-1a. Similar l to the existing REMP, UREMP utilizes supplemental tables which describe reporting levels and LLDs l that are located in Chapter 9 and figures generally denoting Quad Cities Station sample locations are l contained herein.

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~~4. COLD SHUTDOWN Shutdown (*** s 212*F i~~
~~5. REFUELING " Shutdown or Refuel'** 5 140*F ,~~
TABLE NOTATIONS (a) The reactor mode switch may be placed in the Run or Startup/ Hot Standby postbon to test the switch interlock functions provided the control rods are verifled to remain fully inserted by a second licensed operator or other technically qualified individual. ,,
(b) The reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per Technical SpiK.;Lig,n 3.10.1.
(c) Fuel in the reactor vessel with one or more vessel head closure bolts less than fully tensioned or with the head removed.
(d) See Technical Specification Special Test Exceptions 3.12.A and 3.12.B.
(e) The reactor mode switch may be placed in the Refuel position while a single control rod is being recoupled or withdrawn provided the one-rod-out intertock is OPERABLE.
(f) When there is no f'uel in the reactor vessel, the reactor is considered not to be in any OPERATIONAL MODE. The reactor mode switch may then be in any posmon or may be inoperable.
EPSPROJ/odenVguad/12ri.af 12-8
QUAD CITIES Revision 1.8 June 1996 12.2 lNSTRUMENTATION 12.2.1 Radinar+ive Liould Emuent Instrumentation Ooer=hilihr Raouirements l 12.2.1.A The effluent monitoring instrumentation shown in Table 12.2-1 shall be OPERABLE with alarm setpoints set to ensure that the limits of 12.3.1.A are not exceeded. The alarm setpoints shall be determined in accordance with the ODCM.
Aophcabihty Applies to radioactive effluents from the plant.
Action.
1. With a radioactive liquid effluent monitoring instrument alarm / trip setpoint less conservative than required, without delay suspend the release of radioactive liquid effluents monitored by the affected instrument, or declare the instrument inoperable, or change the setpoint so it is acceptably conservative.
2. With one or more radioactive liquid effluent monitoring instruments INOPERABLE, take the ACTION shown in Tablo 12.2-1. Exert best efforts to retum the instr'ument to l operable status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
3. In the event a limiting condition for operation and associated action requirements cannot be satisfied because of circumstances in excess of those addressed in the specifications, provice a 30-day written report to tne NRC and no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into an operational mode.
Surveillance Raouirements 12.2.1.B Each radioactive liquid effluent monitoring instrument shown in Table 12.2-2 Shall ce ;
demonstrated operable by performance of tha given source check, instrument check. ;
calibration, and functional test operations at the frequencies shown in Table 12 2 2 Anohcability. Applies to the periodic measurements of radioactive effluents Bases 12.2.1.C The radioachve liquid effluent instrumentation is provided to monitor the release of radioactive materials in liquid effluents during releases. The alarm setpoints for the instruments are provided to ensure that the alarms will occur prior to exceeding the limits of RETS and 10 CFR 20.
EPSPROJ/odem/ quad /12ri-8f 12-9
QUAD CITIES RIvision 1.8 June 1996 TABLE 12.2-1 .
RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum No.
of Operable Total No.
Channels of Channela Parameter ActionUI 1 1 Service Water A Effluent Gross Activity Monitor 1 1 Liquid Radweste C Effluent Flow Rate Monitor 1 1 Liquid Radwaste B Effluent Gross Activity Monitor
[1] Notes Action A- With less than the minimum number of operable channels, releases via this pathway may continue, provided that at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months grab samples are collected and analyzed for beta or gamma activity at an LLD of less than or equal to 10# pCl/ml. {
Action B: With less than the minimum number of operable channels, effluent releases via this pathway may continue, provided that prior to initiating a release, at least 2 independent samples are analyzed in accordance with Section 12.3.A.1, and at least 2 members of the facility staff independently venfy the reiease calculation and discharge valving. Ot'.erwise, suspend release of radioactive effluents via this pathway.
Action C: With less than the minimum number of operable channels, releases via this pathway may continue, provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump curves may be utilized to estimate flow.
EPSPROJ/odem/ quad /12rt-af 12-10
QUAD CITIES Rsvision 1.8 Juna 1996 TABLE 12.2-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument Functional Source Instrument Checkfi) Calibration (1)(3) Testfi)(2) Check (1)
Liquid Radwaste Effluent D E Q(7) (5)(6)
Gross Activity Monitor Service Water Emuent D E Q(7) (5)
Gross Activity Monitor Liquid Radwaste Effluent (4) E NA NA Flow Rate Monitor -
Natsta (1) D= once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Q= once per 92 days E= once per 18 months (550 days)
(2) The Instrument Functional Test shall also demonstrate that control room alarm annunciation occurs, if any of the following conditions exist, where applicable.
~~a. Instrument indicates levels above the alarm setpoints.~~
~~b. Circuit failure.~~
~~c. Instrument indicates a downscale failure,~~
~~d. Instxment controls not set in OPERATE mode.~~
(3) Calibration shall include performance of a functional test.
(4) Instrument Check to verify flow during periods of release.
(5) Calibration shall include performance of a source check.
(6) Source check shall consist of observing instrument response during a discharge.
(7) Functional test may be performed by using trip check and test circuitry associated with the monitor chassis.
EPSPROJ/odem/ quad /12ri af 12-1)
QUAD CITIES RIvision 1.8 Jun31996 12.2 INSTRUMENTATION 12.2.2 Radioactive Gaseous Effluent Instrumentation Ocar=hilav Raanirement 12.2.2.A The effluent monitoring instrumentation shown in Table 12.2-3 shall be OPERABLE with alarm / trip setpoints set to ensure that the limits of Section 12.4 are not exceeded. The alarm / trip setpoints shall be determined in accordance j with the ODCM. l l
Amphcability As shown in Table 12.2-1.
&GilG0;
1. With a radioactive gaseous effluent monitoring instrument alarm / trip set point less conservative than required, without delay suspend the release of radioactive gaseous effluents monitored by the affected instrument, or declare the instrument inoperabie, or change the setpoint so it is acceptably conservative.
2. With one or more radioactive gaseous effluent monitoring instruments inoperable, take the action shown in Table 12.2-3. Exert best efforts to retum the instrument to operable status within 30 days and, if -
unsuccessful, explain in the next Semi-Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely p manner. This is in lieu of an LER. i[
3. In the event a limiting condition for opersbon and associated action requirement cannot be satisfied because circumstances in excess of those addressed in the specifications, provide a 30<$ay wntten report to the NRC and no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into an operational mode.
Surv*Mmes Raauirements 12.2.2.B Each radioachve gaseous radiation monitoring instrument in Table 12.2-4 shall be demonstrated operable by performance of the given source check, instrument check, calibration, and functional test operations at the frequency shown in Table 12.2 4.
r 12.2.2.C The radioachve gaseous effluent instrumentation is provided to monitor the release of radioactive materials in gaseous effluents during releases.
The alarm setpoints for the instruments are provided to ensure that the alarms will occur prior to exceeding the limits of RETS and 10 CFR 20.
EPSPROJ/odem/ quad /12ri-8f 12 12
QUAD CITIES Ravision 1.8 Juna 1996 TABLE 12.2-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum No.
of Operable Total No.
Channelsd3 of Channels Parameter AchorJ2) 1 2 SJAE Radiation Monitors D 1 2 Main Chimney Noble A Gas Activitv Monitor 1 1 Main Chimney lodine C Sampler 1 1 Main Chimney C Particulate Sampler 1 1 Reactor Bldg. Vent B Sampler Flow Rate Monitor i
1 1 Reactor Bldg. Vent C lodine Sampkr 1 1 Reactor Bldg. Vent C Particulate Sampler 1 1 Main Chimney Sampler B Flow Rate Monitor 1 1 Main Chimney Flow B Rate Monitor 1 2 Reactor Bldg. Vent E Noble Gas Monitor i
1 1 Main Chimney F I High Range Noble Gas Monitor Notes j (1) For SJAE monitors, applicable during SJAE operation. For other instrumentation, applicable at all times.
(2) Action A: With the number of operable channels less than the minimum requirement, effluent releases via this pathway may continue, provided grab samples are taken at least once per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months shift and these samples are analyzed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
EPSPROJ/odem/ quad /12ri-8f 12-13
QUAD CITIES Rsvision 1.8 Juna 1996 TABLE 12.2 3 (Con't)
RADIOAC1NE GASEOUS EFFLUENT MONITORING INSTRUMENTATION l
\
l Action B: With the number of operable channels less than the minimum required, effluent releases i via this pathway may continue provided that the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .
Action C: With less than the minimum channels operable, effluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling equipment, as required in Table 12.4-1.
Action D: With less than the minimum channels operable, gases from the main condenser off gas system may be released to the environment for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months provded at least one chimney monitor is operable; otherwise, be in STARTUP in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
Action E: With less than the minimum channels operable, immediately suspend release of radioartve effluents via this pathway.
Action F: With less than the minimum channels operable, initiate the proplanned altemate method of monitoring to appropriate parameter (s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:
(1) eitheir restore the inoperable channel (s) to operable status within 7 days of the event,or (2) prepare and submit a Special Report to the Commission within 30 days following the -
event out'ining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status.
(
EPSPROJ/odem/quadI12ri-ef 12-14 l
QUAD CITIES Ravision 1.8 Juna 1996 TABLE 12.2-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS <
Instrument Calibra- Functional Source Instrument Mode (2) Chad 5l1)_ tion (1)(4) Testfi){3) Check (1)
Main Chimney Noble Gas B D E Q M Activity Monitor Main Chimney Sampler B D E Q51 NA Flow Rate Monitor Reactor Bldg. Vent Sampler B D E Q51 NA Flow Rate Monitor Main Chimney Flow Rate B D E Q NA Monitor Reactor Bldg Vent B D E Q Q Activity Monitor SJAE A D E Q E Main Chimney lodine and B D53 NA NA NA Particulate Sampler Reactor Bldg. Vent lodine B D51 NA NA NA and Particulate Sampk,r Main Chimney High Range B D53 E Q M l Noble Gas Monitor )
Notes (1) D= once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months M= once per 31 days Q= once per 92 days E= once per 18 months (550 days)
(2) A= during SJAE operation l B= at all times l
(3) The Instrument Functional Test shall also demonstrate that control room starm annunciation occurs, if any of the following conditions exist, where applicable:
~~a. Instrument indicates levels above the alarm setpoint~~
~~b. Circuit failure~~
~~c. Instrument indicates a downscale failure~~
~~d. Instrument controls not set in OPERATE mode EPSPROJ/odemleuad/12ri-8f 12-15~~
QUAD CITIES RIvision 1.8 Juns 1996 TABLE 12.2-4 (cont'd)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILt.ANCE REQUIREMENTS (4) Calibration shall include performance of a functional test.
(5) Instrument check to verify operability of the instrument; that the instrument is in place and functioning properly. 4 (6) Functional test shall be performed on local switches providing low flow alarm.
e EPSPROJ/odem/ quad /12ri-8f 12-16
QUAD CITIES Rsvision 1.8 Juns 1996 12.3 LIQUID EFFLUENTS I
- 1
( 12.3.1 Concentration nnarnhilihr Ranniramanha 12.3.1.A. The concentration of radioacdve material released from the site to unrestricted areas (at or beyond the site boundary, see Quad Cities Station ODCM Annex, Appendix F, Figure F-1) shall be limited to 10' times the concentrations specified in Appendix B, Table 2. Column 2 to 10 CFR 20.1001-20.2402 with the Table 12.3-1 values representing the AC's for noble gases.
Anolicability: At all times AGii0L With the concentration of radioachve material released from the site to unrestncted areas exceeding the above limits, without delay decrease the release rate of radioactive materials and/or increase the dilution flow rate to restore the concentrction to within the above limits.
Surveillance Requirements 12.3.1.B The concentration of radioactive material in unrestricted areas shall be determined to be within the prescribed limits by obtaining the representative-samples in accordance with the sampling and analysis program specified in Table 12.3 2. The sample analysis results will be used with the calculational l methods in the ODCM to determine that the concentrations are within the limits j of Specification 12.3.A.
Bases 12.3.1.C This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas wol be less than 10' times the concentration levels specified in Appendix B, Table 2 Column 2 to 10CFR20.1001 - 20.2402. The concentration limit for noble gases was converted to an equivalent concentration in water using the intomational Commission on Radiological Protection (ICRP) Publicabon 2.
'The 10 multiplier may not be used prior to Technical Specification approval.
EPSPROJ/odenVguad/12r1.et 12-17 l
I
QUAD CITIES R: vision 1.8 Juna 1996 l
1 TABLE 12.31 ALLOWABLE CONCENTRATION (AC) QF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE NUCLIDE AC(uCi/ml)*
d Kr-85m 2x10 _,,
4 Kr-85 5x10 4
4 Kr-87 4x10 Kr-88 9x10 4 Ar-41 7x104 Xe-131m 7x10" Xe-133m 5x10" d
Xe-133 6x10
,m-Xe-135m 2x10" d
(
Xe-135 2x10
~~Computed from Equation 20 of ICRP Publication 2 (1959), adjusted for infinite cloud submersion in water, and R = 0.01 rem / week, density = 1.0 g/cc and Pw/Pt = 1.0.~~
l l
l EPSPROJ/odan/ quad /12rt-8f 12-18 l
L_ __
QUAD CITIES Rsvision 1.8 Juna 1996 TABLE 12.3-2 RAQlOACTNE LIQUID WASTE SAMPLINQ AND ANALYSIS PROGRAM LIQUID RELEASE SAMPLING MINIMUM TYPE OF LOWER LIMIT OF TYPE FREQUENCY ANALYSIS ACTIVITY ANALYSIS DETECTION
~~FREQUENCY (LLD) (pCi/ml)~~
~~A. Prior to Each Butch Prior to Each Batch Principal Gamma 5x10 Emitters~~
4 l-131 1x10 Prior to Each Batch M Gross Alpha 1x10 Batch Waster Composite
~~RIlease Tanks H-3 1x10~~
Prior to Each Batch Q Fe-55 1x10*
Composite * .
Sr-89, Sr-90 5x10' Prior to One Batch /M M Dissolved & Entrained 1x10
Gases'(Gamma Emitters) 4 B. M* (Grab Sample) M* l-131 1x10 Principle Gamma 5x10' Plant Continuous Emitters
~~R11 eases Dissolved and 1x10' Entrained Gases' (Gamma Emitters)~~
H-3 1x10' ,
Gross Alpha 1x10 Q* (Grab Sample) Q* Sr-89, Sr-90 5x10*
Fe-55 1x10' EPSPROJ/odem/ quad /12ri-8f 12-19
QUAD CITIES R: vision 1.8 Juna 1996 TABLE 12-3-2 (Continued)
/*
RADIOACTNE LIQUID WASTE SAMPLING (
AND ANALYSIS PROGRAM i
TABLE NOTATION
~~a. The LLD is defined in Notation A of Table 12.5-3. 1 I~~
b. A composite sample is one in which the quantity of liquid samples is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
c. If the alarm setpoint of the service water effluent monitor as determined in the ODCM is exceeded, the frequency of analysis shall be increased to daily until the condition no longer I exists. l I
d. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for j analyses, each batch shall be isolated then thoroughly mixed to assure representative I sampling. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., J from a volume or system that has an input flow during the release,
e. The principal gamma emitters for which the LLD specification applies exclusive!y are the following radionudides Mn-54, Fe-59, Co-60, Zn-65, Co-58, Mo-99, Cs-134, Cs-137, Ce-141 and Co-144. Other peaks which are measurable and identifiable by gamma ray spectrometry together with the above nudides, shall be also identified and reported when the actual analysis .-
~~is performed on a sample. Nudides which are below the LLD for the analyses shall not be e reported as being present at the LLD level for that nudide.~~
f. The dissolved and entrained gases (gamma emitters) for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138. Other dissolved and entrained gases (gamma emitters) which are measurable and identifiable by gamma-ray spectrometry, together with the above nudides, shall also be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being present at the LLD level for that nuclide.
EPSPROJ/odem/ quad /12r1-af 12-20
QUAD CITIES R3 vision 18 Juna 1996 12.3 LIQUID EFFLUENTS t
12.3.2 Dose 0
nnmenhilihr Dannirarnante 12.3.2.A The dose or dose commitment above background to a member of the public from radioachve materials in liquid effluents released to unrestricted areas (at or beyond the site boundary) from the site shall be limited to the following:
~~1. During any calendar quarter:~~
(a) Less than or equal to 3 mrom to the whole body.
(b) Less than or equal to 10 mrom to any organ.
Apolicabihty At all times
~~2. During any calendar year:~~
~~(a) Less than or equal to 6 mrom to the whole body.~~
(b) Less than or equal to 20 mrom to any organ.
AdiQL
1. With the calculated dose from the release of radioachve materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the correcove actions taken and the proposed acbons to be taken to ensure that future releases are in compliance with 12.3.2.A. This is in lieu of a Licensee Event Report.
2. With the calculated dose from the release of radioac0ve materials in liqu.o effluents exceeding the limits of Specification 12.3.2.A., prepare and submit a Special Report to the Commission within 30 days an limit the subsequent releases such that the dose or dose commitment to a merrce, of the public from all uranium fuel cycle sources is limited to less than or equal to 25 mrom to the total body or any organ (except thyroid, which s limited to less than or equal to 75 mrom) over 12 consecutive months.
This Speaal Report shall include an anatysis which demonstrates that radiation exposures to all members of the public from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are 'ess than the 40 CFR Part 190 Standard. Otherwise obtain a variance from e Commission to permit releases which exceed the 40 CFR Part 190 Standard. The radiation exposure analysis contained in the Special Report shall use methods prescribed in the ODCM. This report is in lieu of a Licensee Event Report.
3. With the projected annual whole body or any intomal organ dose computed at the nearest downstream community water system is equal to or exceeds 2 mrom from all radioachve materials released in liquid effluents from the Station, prepare and submit a Special Report within 30 days to the operator of the communrty water system. The report is prepared to assist the operator in meeting the requirements of 40 CFR 141: EPA Primary Drinking Water Standards. A copy of this report will be sent to the NRC. This is in lieu of a Licensee Event Report.
EPSPROJ/odem/ quad /12r1.at 12-21
]
QUAD CITIES Revision 1.8 Juna 1996 12.3 UQUID EFFLUENTS 12.3.2 Dose (Cont.) .
Surveillance Requirements 12.3.2.8.1. The dose contributions from measured quantities of radioactive material shall be determined by calculation at least once per 31 days and a cumulative summation of these total body and organ doses shall be maintamed for each calendar quarter.
12.3.2.B.2 Doses computed at the nearest community water syetem will consider only the drinking water pathway and shall be projected using the methods prescribed in the ODCM at least once per 92 days.
Bases 12.3.2.C This spedik,stion is provided to implement the requirements of Sechons ll.A.
Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Umiting Condition for Operation implements the guides set forth in Section ll.A of Appendix 1. The statements provide the required operating flexibility and at the same time implement the guides set forth in Sechon IV.A of Appendix 1 to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable" The dose calculations in the ODCM implement the requirements in Section lil.A of Appendix 1 that conformance with the guides of Appendix 1 be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriete pathways is unlikely to be substantially underestimated. The equations specified in the jr 4'
ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendix I", April 1977.
NUREG-0113 provides methods for dose calculations consistent with Reg Guide 1.109 and 1.113.
EPSPROJ/odem/ouad/12r1-8f 12-22
QUAD CITIES Rrvision 1.8 Juna 1996 i 12.3 LIQUID EFFLUENTS
?
12.3.3 Liquid Radwaste Treatment System Operability Requirements l l
12.3.3.A At all times during processing prior to discharge to the environs, process and l ccntrol equipment provided to reduce the amount or concentration of j radioactive materials shall be operated when the projected dose due to liquid l effluent releases to unrestricted areas (see Appendix F, Figure F-1), when !
averaged over 31 days, exceeds 0.13 mrem to the total body or 0.42 mrem to !
any organ I Action I
1. If liquid waste has to be or is being discharged without treatment as J required above, prepara and submit to the Commission within 30 days, a report which includes the following information:
~~a. Identification of the defective equipment.~~
~~b. Cause of the defective equipment.~~
~~c. Action (s) taken to restore the equipment to an operating status.~~
~~d. Length of time the above requirements were not satisfied.~~
~~e. Volume and curie content of the waste discharged which was not processed by the inoperable equipment but which required processing.~~
~~f. Action (s) taken to prevent a recurrence of equipment failures.~~
2. In the event a limited and/or associated action requirements identified in Sections 12.3.3.A cannot be satisfied because of circumstances in excess of those addressed in this Sectiori, no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into an operational mode.
Surveillance Requirements 12.3.3.B Doses due to liquid releases to unrestricted areas (at or beyond the site boundary) shall be projected at least once per 31 days in accordance with ODCM.
Bases 12.3.3.C The operability of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section 11.D of Appendix 4 to 10 CFR Part 50.
I EPSPROJ/odem/ quad /12ri-81 12-23
QUAD CITIES Rtvision 1.8 q Jun31996 12.4 GASEOUS EFFLUENTS ,
i 12.4.1 Dose Rate -
Operability Requirements 12.4.1.A The dose rate in unrestncted areas (at or beyond the site boundary, see Quad Cities Station ODCM Annex, Appendix F, Figure F-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following:
~~1. For Noble Gases:~~
(a) Less than 500 mrom/ year to the whole body.
(b) Less than 3000 mrom/ year to the skin.
~~2. For iodine-131, for iodine 133, and for all radionuclides in particulate form~~
with half-lives greater than 8 days less than 1500 mrom/ year, 8GliQQ' If the dose rates exceed the above limits, without delay decrease the release rates to bring the dose rates within the limits, and to provide prompt notification to the Commission (12.6)
Surveillance Requirements .
4 12.4.1.8 The dose rates due to radioachve materials reinsed in gaseous effluents from the site shall be determined to be within the prescribed limits by obtaining representabve samples in accordance with the sampling and analysis program specified in Table 12.4-1. The dose rates are calculated using methods prescribed in the Offsite Dose Calculation Manual (ODCM).
Bases 12.4.1.C This specification is provided to ensure that the dose at the unrestricted area boundary from gaseous effluents from the units on the site will be within the annual dose limits of 10CFR20. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not nesult in the exposure of an individualin an unrestricted area to annual average concentrations exceeding the limits specified in Appendix B, Table 2 of 10CFR20. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the unrestricted area boundary to less than or equal to a dose rate of 500 mrom/ year to the total body or to not less than or equal to a dose rate of 3000 mrom/ year to the skin. These rolesse rate limits also restrict, at all times, the cwi fu, ding thyroid dose rate above background via the inhalation pathway to not less than or equal to a dose rate of 1500 mrom/ year. For purposes of calculating doses resulting from airbome releases the main chimney is consulered to be an elevated release point, and the reactor vent stack is considered to be a mixed mode reisese point.
EPSPROJ/odenVgueW12ri-ar 12-24
QUAD CITIES Rtvision 1.0 ;
Juna 1996 TABLE 12.4-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOWER LIMIT OF GASEOUS RELEASE SAMPLING ANALYSIS TYPE OF DETECTION
~~i TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (LLD) (pCi/ml)~~
~~A. Main Chimney M M* Principal Gamma 1x10" Reactor Bldg. Grab Sample Emitters~~
Verit Stack 4 M Tritium 1x10 B. All Release Continuous (d) W l-131 1x10a2 Types as Listed Charcoal in A Above Sample 1-133 1x10" )
~~l Continuous (d) W Principal Gamma Particulate Emitters~~
~~1 x10'"~~
Sample (1-131, others) j Continuous (d) Q SR-89 1 x10'"
Composite Particulate SR-90 1 x10'"
Sample Continuous (d) M Gross Alpha 1x10 "
Composite Particulate Sample C. Main Chimney Continuous (d) Noble Gas Noble Gases 1x10' Monitor D. Reactor Bldg. Continuous (d) Noble Gas Noble Gases 1x10' Vent Stack Monitor i
l EPSPROJ/odctr/ Quad /12ri-8f 12-25 j
i QUAD CITIES RCvision 1.8 !
Juno 1996 TABLE 12.41 (Continued) l RADIOACTNE GASEOUS WASTE SAMPLING ,
AND ANALYSIS PROGRAM TABLE NOTATION
~~a. The lower limit of detection (LLD) is defined in Notation A of Table 12.5-3.~~
1
b. Sampling and analyses shall also be performed followmg shutdown, startup, or a thermal power l change exceeding 20 percent of rated thermal power in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months unless (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the primary coolant has not increased more than a factor of 5, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.
c. Samples shall be changed at least once per 7 days and the analyses ceir-;':^d within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after removal from the sampler. Sampling shall also be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following each shutdown, startup, or thermal power level change exceeding 20% of rated thermal power in one hour. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the primary coolant has not increased more than a factor of 5, and (2) the noble gas activity monitor shows that affluent actnnty has not increased by more than a factor of 3. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLD's may be increased by a factor of 10.
~~d. The ratio of sample flow rate to the sampled stream flow rate shall be imown. ,y.~~
y
~~e. The principal gamma emitters for which the LLD speGc. tion applies exclusively are the '~~
followiry radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xo-138 for gaseous emissions, and Mn-54, Fe-59, Co 60, Zn-65, Co-58, Mo-99, Cs-134, Cs-137, Co-141, and Co-144 tr particulate emissions. Other peaks which are measurable and identifiable by gamma lay sWueir,etry, together with the above nuclides, shall be also identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being present at the LLD level for that nuclide.
F EPSPROJ/odem/guad/12r14f 12-26
QUAD CITIES Rsvision 1.8 Jun31996 12.4 GASEOUS EFFLUENTS 12.4.2 Dose - Noble Gases Operability Requirements 12.4.2.A The air dose in unrestricted areas (at or beyond the site boundary) due to Noble Gases released in gaseous affluents from the unit shall be limited to the following:
~~1. For gamma radiation:~~
(a) Less than or equal to 5 mrad during any calendar quarter.
(b) Less than or equal to 10 mrad during any calendar year.
~~2. For Beta radiation:~~
(a) Less than or equal to 10 mrad during any calendar quarter.
(b) Less than or equal to 20 mrad during any calendar year.
Achon-
1. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to ensure that future releases are in compliance with 12.4.2.A.
~~This is in lieu of a Licensee Event Report.~~
2. With the calculated air dose from radioachve noble gases in gaseous effluents exceeding the limits of Spedindwn 12.4.2.A, prepare and submit a Special Report to the Commission within 30 days and limit the subsequent releases such that the doses or dose commitment to a member of the public from all uranium fuel cycle sources is limited to less than or equal to 25 mrom to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrom) over 12 consecutive months. This Special Report shall include an analysis which demonstrates that radiation exposure to all members of the public from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard. The radiation ,
/
exposure analysis contained in the Special Report shall use the methods prescribed in the ODCM. This report is in lieu of a Licensee Event Report.
Surveillance Requirements 12.4.2.B The air dose due to releases of radioachve noble gases in gaseous effluents shall be determined to be within the presenbed limits by obtaining representative samples in accordance with the sampling and analysis program speedied in sections A and B of Table 12.4-1. The allocation of effluents between units having shared effluent control systems and the air doses are det.ormined using methods prescribed in the ODCM at least once every 31 days.
EPSPROJ/odctrVgueW12r18f 12-27
QUAD CITIES Revision 1.8 Juno 1996 12.4 GASEOUS EFFLUENTS 12.4.2 Dose - Noble Gases (Cont.)
Bases 12.4.2.C This specification is provided to implement the requirements of Sections 11.B, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Umibng Condition for Operabon implements the guides set forth in Sechon 11.8 of Appendix 1. The statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix i to assure that the releases of radioachve matanul in gaseous effluents will be kept "as low as is -
reasonably achievable." The Surveillanu Requirements implement the requirements in Sechon Ill.A of Appendix l that conformance with the guides of Appendix 1 is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioachve noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of EvaluaGng Compliance with 10 CFR Past 50, Appendix 1," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors", Revision 1, July 1977. The ODCM equations provide for determining the air doses at the unrestricted boundary based upon the histoncel average atmospheric ccaditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.10g and 1.111. {,
L EPSPROJ/odenVgued/12ri 8f 12-28
QUAD CITIES Rsvision 1.8 Juns 1996 12.4 MSEOUS EFFLUENTS i 12.4.3 Dose - Radioiodine - 131 and 133, Tritium and Radionuclides in Particulate Form Operability Requirements 12A.3.A The dose to a member of the public in unrestricted areas (at or beyond the site boundaty) from iodine-131, iodine-133, tntium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the unit shall be limited to the following:
~~1. Less than or equal to 7.5 mrem to any organ during any calendar quarter.~~
~~2. Less than or equal to 15 mrem to any orgran during any calendar year.~~
Apphcability. At all times
&GhQD.
1. With the calculated dose from the release of iodine-131, iodine-133, tntium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and defines the -
~~corrective actions taken and the proposed actions to be taken to ensure that future releases are in compliance with 12.4.3.A This is in lieu of a Licensee Event Report.~~
2. With the calculated dose from the release of iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents exceeding the limits of Section 12.4.3.A, prepare and submit a Special Report to the Commission within 30 days and limit subsequent releases such that the dose or dose commitment to a member of the public from all uranium fuel cycle sources is limited to less than or equal to 25 mrem to the total body or organ (except the thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months. This Special Report shall include an analysis which demonstrates that radiation exposures to all members of the public from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard. The radiation exposure analysis contained in the Special Report shall use the methods presenbed in the ODCM. This report is in lieu of a Licensee Event Report.
l EPSPROJ/odem/ quad /12r1-of 12-25
QUAD CITIES Rsvision 1.8 Juna 1996 12.4 GASEOUS EFFLUENTS .
12.4.3 Dose - Radioiodine - 131 and 133. Tritium and Radionuclides in Particulate Form (Cont.)
Surveillance Requirements 12.4.3.B.1 The dose to a member of the public due to releases of iodine-131, iodine-133, 1 tritium, and all radionuclides in particulate form with half-lives greater than 8 days shall tm determined to be within the prescribed limits by obtaining i representative samples in accordance with the sampling and analysis program specified in Table 12.4-1.
12.4.3.B.2 For radionuclides not determined in each batch or weeldy composite, the dose contribution to the current calendar quarter cumulative summation may be estimated by assuming an average monthly concentration based on the previous monthly or quarterly composite analyses. However, for reporting l purposes, the calculated dose conM5utions shall be based on the actual composite analyses when possible. The allocation of effluents between units having shared effluent control systems and the doses are determined using the methods prescribed in the ODCM at least once every 31 days.
Bases 12.4.3.C This WTn tion is provided to implement the requirements of Sections ll.C, til.A and IV.A of Appendix 1,10 CFR Part 50. The Limsting Conditions for Operabon are the guides set forth in Sechon ll.C of Appendix t. The statements provide the required operating flexibility and at the same time implement the guides set forth in Sechoq IV.A of Appendix i to assure that the /
releases of radioachve materials in gaseous effluents will be kept "as low as :s i reasonable achievable." The ODCM calculabonal methods specified in the surveillance requirements implements the requirements in Secbon Ill.A of Appendix i that conformance with the guides of Appendix 1 be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods approved ev NRC for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routne Releases of Reactor Effluents for the Purpose of Evaluabng Compliance we J 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Gwoe
,1,111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous effluents in Routine Releases from Light-Water-Cooled Reactors.-
Revision 1 July 1977. These equations also provide for determining the ach.m dosee based upon the historical average atmospheric conditions.
The release rate specificabons for radioiodine, radioactive material in partculate form and radionuclides other than noble gases are dependent on the exisbng radionuclide pathways to man, in the unrestncted area. The pathways whch were examined in the development of these specificabons wors: 1) individual inhalation of airbome radionuclides,2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by nren and 3) deposition onto grassy areas where milk animals graze with consumption of the milk by man.
EPSPROJ/odanIquad/12rt.8r 12-30
QUAD CITIES Rsvision 1.8 Junn 1996 12.4 GASEOUS EFFLtJENTS 12.4.4 Off-Gas System Operability Requirement 12.4.4.A At all times dunng pecessing for discharge to the environs, process and control equipment provided to reduce the amount or concentration of radioactive matonals shall be operated.
Apohcabihty and Achorr The above specification shall not apply for the Off-Gas Charcoal Adsorber Beds below 30 percent of rated thermal power.
1. The release rate of the sum of the activibes from the noble gases measured at sie main condenser air ejector shall be limited to less than or equal to 100 microcunesteoc per MWt (after 30 minutes decay) at all times. With the release rate of the sum of the activities from noble gases at the main condenser air ejector exceeding 100 microcuries/sec per MWt (after 30 minutes decay), restore, the release rate to within its limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or be in at least STARTUP with the main steam isolation valves closed within tha next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 
2. Wlth all chsenal beds bypassed for more than 7 days in a calendar quarter whhe operahng above 30 percent of rated thermal power, prepara and ashmit to the Commesion within 30 days a special report which includes the following informaton-
~~a. Identification of the defective equipment.~~
~~b. Cause of the defective equipment.~~
~~c. Adon(s) taken to restore the equipment to an operating status~~
~~d. I.engt of time the above requirments were not sabsfied~~
~~e. Volunie and curie content of the waste discharged which was~~
~~. not pecessed by the inoperable equipment but which requaeo processing.~~
~~f. Action (s) tanen to prevent a recurrence of equipment failures~~
3. In the event a Omit and/or ==encinead action requireme*it identified in Sechon 12.4.4.A cannot be sabsfied because of circumstances in excess of those addressed in this Sechon, no changes are requireo n the operational condition of the plant, and this does not prevent the ;
plant from entry into an opersbonal mode.
Surveillance Requirements 12.4.4.B.1 Doses due to treated gases released to unrestncted areas at or beyond the see ,
boundary shall be projected at least once per 31 days in accordance with the !
ODCM.
12.4.4.B.2 The radioactmty rate of noble gases at (near) the outlet of the main condenser air ejector shall be conhnuously moratored in accordance with Specification 12.2.2.A. The release rata of the sum of the actmties from noble gases from the main condenser air ejector shall be determined to be within the limits of EPSPROJ/odomhiuad/12rt-of 12-31
QUAD CITIES WiE7ismR June 1996 Spoofication 12.4.4.A at the following frequencies by pedeT-Jng an isotope ar.alysis of a representative sample of gases taken at the recombiner outlet, or f*
at the air ejector outlet if the recombiner is bypassed.
~~a. At least once per 31 days.~~
b. Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following an increase, as indicated by the main condenser air ejector noble gas activity monitor, of greater than 50%,
after factoring out increases due to danges in thermal power level and off gas flow, in the nomina' %-state fisson gas release from the primary coolant.
e t
EPSPROJ/odem/ Quad /12ri-8f 12-32 1
1
1 I
QUAD CITIES Rsvision 1.8
! June 1996 12.4 GASEOUS EFFLUENTS l 12.4.4 Off-Gas System (Cort.)
l Reeme
12.4.4.C The requirement that the appropriate portions of these systems be used, when l specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonable achievable".
~~This sML 6i implements the requirements of 10 CFR 50.36a, General l Design Criterion 60 of Appendix A to 10CFR50, and the design objectives given~~
~~in Section 11.0 of Appendix 1 to 10CFR50. The specded limits goveming the~~
! use of appropriate portions of the systems were specded as a suitable fraction of the dose design objectives set forth in Sechons 11.3 and 11.0 of Appendix 1, 10CFR50, for gaseous effluents.
l l-l l
l .
{
l i
l l
l l
l ,
I i
1 EPSPROJ/odem/med/12ri-8f 12 33
QUAD CITIES Rsvision 1.8 '
l Juna 1996 12.4 GASEOUS EFFLUENTS 12.4.5 Total Does Operability Requirements 12.4.5.A The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactuty and to radiation from uranium fuel cycle sources shall be imited to less than or equal to 25 mroms to the whole body or any organ, emospt the thyroid, which shall be limited to less than or equal to 75 mroms.
Apphcatulity At all times.
Achon
1. With the r*sh doses from the rolesse of radioachve matenals in liquid or gassaus effluents exceeding twice the limits of Sechons 12.3.2, 12.4.2, or 12.4.3, calculations should be made including direct radiation contnbubons tom the units and from outside storage tanks to determine whether the above limits of Sechon 12.4.5.A have been am if auch is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Speciflcabon 6.9.2, a Special Report that deAnos the correchve achon to be taken to reduce subsequent raiseses to prevent recurrence of exceeding the above '
limits and includes the schedule for achieving conformance with the above limits. This Specal Report, as defined in 10 CFR 20.2203, shall include an analysis that eshmates the radiation exposure (dose) to a MEMBER OF THE PUBLIC frorn uranium fuel cycle sources, including all effluent paesveys and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radimikm and concentration of radioachve material involved, and the cause of the exposure levels or concentrabons. If the eshmated dose (s) exceeds the above limits, and if the release condition resulting in velsbon of 40 CFR Part 190 has not already been corrected, the Specal Report shall include a request for a variance in accordance witi the provisions of 40 CFR Part 190. Submittal of the report is consulered a timely request, and a variana is granted until staff acbon on tie request is complete.
Surveillanu Requirements 12.4.5.1.A Cumulauwe does contrbutions from liquid and gaseous effluents shall be determined in accontence with Seebons 12.3.2,12.4.2, and 12.4.3, and in accordance with 9:e . l{-ME-gy and parameters in the ODCM.
12.4.5.2.B Cumulative does contibubons from direct radiation from the units and from radweste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in ACTION 1 of Sechon 12.4.5.A.
EPSPROJ/odenVgued/12rt-ar 12-34
l l
l QUAD CITIES Rsvision 1.8 June 1996 12.4 GASEOUS EFFLUENTS 12.4.5 Total Dose (Cont.)
Bases 12.4.5.C This section is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The section ,
requires the preparation and submetal of a Special Report whenever the calculated doses due to releases of radioactrvity and to radiation from uranium fuel cycle sources exceed 25 mroms to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites ,
containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will eased the does limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of 1 Appendix 1, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the does commdment to the MEMBER OF THE PUBLIC from other uramum fuel cycle sources is negligible, with the {
exception that dose contributions from other nuclear fuel cycle facilities at the
{
same site or within a radius of 8 km must be considured if the dose to any ' !
MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR l Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violabon of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203, is considered to be a trnely request and fulfills the requirements of 40 CFR Part 190 until NRC staff schon is completed The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitatica of 10 CFR Part 20, as addressed in Sections 12.3.1 and 12.4.1. An individualis not considered a MEMBER OF THE PUBLIC during any period in whch he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
')
l i
EPSPROJ/odem/ quad /12ri-8f 12-35
I QUAD CITIES Rsvision 1.8 Jun31996 12.4 GASEOUS EFFLUENTS 12.4.6 Dose Limits for Members of the Public Ooer=hiliev Ranuirements 12.4.6.A The licenses shall conduct operations such that the TEDE to individual MEMBERS OF THE PUBLIC does not exceed 100 mrom in a year. In addition, the dose in any unrestncted area from external sources does not exceed 2 mrem in any one hour. The Efiluents Program shall implement monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10CFR20.1302 and with the methodology and parameters in the ODCM.
Appheatuity. At all times.
Achon-
1.
If the calculated dose from the release or exposure of radiation meets rv exceeds the 100 mrem / year limit for the MEMBER OF THE PUBLIC, prepare and submit a report to the Corrmsson in accordance with 10CFR20.2203.
2. If the dose in any unrestncted area from extemal sources of radiation meets or exceeds the 2 mrom in any one hour limit for the MEMBER OF THE PUBUC, prepare and submit a report to the Commission in accordance with 10CFR20.2203.
Surr"- s p==i-.T .:-
12.4.6.B Calculate the TEDE to individual MEMBERS OF THE PUBLIC annually to determine compliance with the 100 mrom/ year limit in accordance with the ODCM. In addition, evaluate and/or determine if direct radiation exposures exceed 2 mrom in any hour in unrestricted areas.
12.4.6.C This sechon applies to direct exposure of radioactive materials as well as radioactive meterials released in gaseous and liquid effluents 10CFR20.1301 sets forth the 100 mromfyear dose limit to members of the public; 2 mrom in any one hour limit in the unrestncted arms; and restorates that the licensee is also required to most the 40CFR190 standards. 10CFR20.1302 provides options to determme compliance to 10CFR20.1301. Comphance to the above operabihty requirement is band on 10CFR20,40CFR190 and Quad Cities Station Techn cal Specifications.
EPSPROJ/odamfgued/12ri ef 12-36
1 l QUAD CITIES Rsvision 1.8 June 1996 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l
l 12.5.1 Monitoring Program (If UREMP has been implemented, see 12.5.4 for requirements.)
Operability Requirernents 12.5.1.A The environmental monitoring program given in Table 12.5-1 shall be conducted except as specified below. 1 Aoolit shilitv: At all times Action.
1. With the radiological environmental monitoring program not being conducted ac speedied in Table 12.5-1, prepare and submit to the Commission, in the Annual Radiological Operating Report, a description of the rearons for not mnducting the program as required and the !
plans for preventing a recurrence. Deviations are permitted from the !
required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, contractor omission l
which is corrected as soon as discovered, malfunction of sampling equipment, or if a person who participates in the program goes out of.
business. If the equipment malfunctions, corrective acticns shall be completed as soon as poss!ble. If a person supplying samples goes out of business, a replacement will be found as soon as possible. All deviations from the sampling schedule shall be described in the annual report.
2. With the level of radioactmty in un environmental sampling medium at one or more of the ic,:abons specified in the ODCM exceeding the l limits of Table 12.5 2 when averaged over any calendar quarter, j prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a Special Report which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of Table 12.5-2 to be exceeded. This report is not required if he measured level of radioacavity was not the result of plant effluents, however, in such an event the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
" 3. With milk samples unavailable from one or more of the sample locations required by Table 12.5-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program wenn 30 days. The locations from which samples were unavailable may then be deleted from the monitoring program. In lieu of a Licensee Event Report, identify the cause of the unavailabihty of samples and identify the new location (s) for obtaining replacement samples in the Annual Radiological Environment Operating report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).
EPSPRO.1/odem/ quad /12rt-8f 12-37
QUAD CITIES Rsvision 1.8 Jun21996 12.5 RADIOLOGICAL ENVIRCt""*NTAL MONITORING PROGRAM l 12.5.1 Monitoring Program (Cont.)(if UREMP has been implemented, see 12.5.4 for requirements.)
Surveillance Requirements 12.5.1.B.1 The radiological environmental morutonng samples shall be collected pursuant to Table 12.5-1 from the locahons specifled in the ODCM, and shall be arimiyzd. pursuant to the requirements of Table 12.5-3.
12.5.1.B.2 The results of analyses performed on radiological envuonmental monitoring samples shall be summenzed in the Annual Radiological Environmental Operstmg Report.
Bases 12.5.1.C The radiological monitoring program required by this specification provides measurements of radiation and of radioeceve matenals in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the stabon opersbon. This monotonng program thereby supplements the radiological ofRuent monitoring program by vonfying that the measurable concentrations of radioachve materials and lovels of radiation are not higher than expected on the basis of' the ofRuont measurements and modeling of the envronmental exposure pathways. Program changes may be initiated bened on opersbonal experience.
.The detachon capabilities required by Table 12.5-3 are state of-the art for routine envronmental measurements in industnal laboratones. The specified lower limits of detachon for 1-131 in water, mik and other food products correspond to =-;=Mr ' ', one quarter of the Appendix i to 10 CFR Part 50 design otsective doeo equivalent of 15 mrom/ year for atmosphenc relecses and 10 mrom/ year for liquid releases to the most sensitive organ and individual.
They are based on the assumptions given in Regulatory Guide 1.109,
" Calculation of Annual Donos to Man from Roubne Roleseos of Reactor EfRuents for the Furpose of Evaluating Comphance with 10 CFR Part 50, Appendix I", October 1977, except the change for an infant consuming 330 liter / year of drinking water instead of 510 hters/ year.
I EPSPROJ/odomhquad/12r1-Or 12-36
l l
QUAD CITIES Revision 1.8 June 1996 TABLE 12 5-1 NOTE: This table is superseded upon UREMP Implementation. See Chapter 9 for UREMP sampilng l parameters.
RADIOLOGICAL ENVIRONMENTAL MONITORING PRQGRAM Exposure Pathway Minimum Number of Samples Sampling and Col- Type and Frequency and/or Samole and Samole Loentinns* leMinn Freouancv of Analvsis
~~1. AIRBORNE~~
~~a. Particulates 16 locations Continuous opera- Gross beta and tion of sampler gamma Isotopic as for a week specified in ODCM.~~
~~b. Radioiodine 16 locations Continuous opera- I-131 as speci-tion of sampler fled in ODCM.~~
~~for two weeks~~
~~2. DIRECT RADIATION Forty Locations Quarterly (Minimum of two TLDs per packet) 9 WATERBORNE~~
~~a. Public Water 2 Locations Monthly composite Gamma Isotopic of weekly collec- analysis of each ted samples composite sample~~
b. Sediment i downstream location Annually Gamma Isotopic in receiving body of analysis of each water sample i
c. Plant Cooling intake, Discharge Weekly composete Gross seta analy-Water sis of each sample
~~4. INGESTION~~
a. Milk 2 Locations At least once 1-131 analysis of weekly when ani- each sample animals are on pasture; at least once per month at other times.
b. Fish 1 location in receiv- Semi-annually Gamma Isotopic ing body of water analysis on edible portions Sample locations are described in the ODCM EPSPROJiodcrWouad/12rt 8f 12-39
QUAD CITIES Rsvision 1.8 Jun31996 TABLE 12.5 2 NOTE: This table is superseded upon UREMP Implementation. See Chapter 9 for UREMP reporting levels.
REPORTING LEVELS FOR RADIOACTMTY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels Analysis Water Airbome Particulate Fish Milk Food Products (pCi/I) or Gases (pCi/m*) (pCi/Kg, wet) (pCi/l) (pCi/Kg, wet)
H-3 2 x 10'(a)
Mn-54 1 x 10 8 3 x 10' Fe-59 4 x 102 1 x 10' Co-58 1 x 108 3 x 10' Co-60 3 x 10 1 x 10' Zn-65 3 x 102 2 x 10' Zr-Nb-95 4 x 102 1-131 2 0.9 3 1x9 Cs-134 30 10 1 x 10 8 60 1 x *:
Cs-137 50 20 1 x 10 8 70 2 ':
Ba-La-140 2 x 102 3 x 10' a) for drinking water samples. This is 40 CFR Part 141 value.
EPSPROJ/odem/ quad /12ri.8f 12-40
1
}
QUAD CITIES Rsvision 1.8 June 1996 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l 12.5.2 Land Use Census (if UREMP has been implemented, see 12.5.5 for requirements.)
Operability Requirements 12.5.2.A The land use census shall be conducted at least once per twelve months between the dates of June 1 and October 1 by a door-to-door survey, aerial survey, road survey, or by consulting local agriculture authorities.
12.5.2.A.1 A census of nearest residences of animals producing milk for human consumption shall be conducted annually (during the grazing season for animals) to determme their locahon and number with respect to the site. The nearest resKience in each of the 16 it::::+A-gical sectors shall also be determined within a distance of five miles. The census shall be conducted under the following conditions:
1.
~~Within a 2-mile radius from the plant site, enumeration of animals and nearest rendences by a door-to-door or equivalent counting technique.~~
~~2. Within a 5-mile radius, enumeration of animals by using referenced ,~~
information from county agricultural agents or other reliable sources. !
M100.
i
~~1. With a land use census identifying locahon(s) of animals which yield (s) ;~~
an ODCM calculated dose or dose commitment greater than the values currently bemg calculated in Specificabon 12.4.3, the new location (s) shall be added to the radiological environmental monitoring program !
with 30 days, if possible.
The sampling locabon, having the lowest calculated dose or dose ,
commitment (via the same exposure pathway) may be deleted from S i monitoring program after October 31 of the year in which this land w census was conducted.
Surveillance Requirements 12.5.2.B The results of the land use census shall be included in the Annual Radiologe.m Environmental Operating Report.
Bases 12.5.2.C This specification is provided to ensure that changes in the use of unrestncted areas a.e identified and that modifications to the monitoring program are maoe if required by the results of this census. This census satisfies the requirements of Sechon IV.B.3 of Appendix I to 10 CFR Part 50.
e.
EPSPROJ/odenVgued/12rt-8f 12-41 1
\
QUAD CITIES Rsvision 1.8 Juns 1996 12.5' RADIOLOGICAL ENVIRONuCNTAL MONITORING PROGRAM 12.5.3 Interlaboratory Compenson Program (if UREMP has been implemented, see 12.5.6 for requirements.)
l Operability Requirements 12.5.3.A Radiological analyses shall be performed on samples representative of those in Table 12.5-1, supplied as a part of an intertsboratory Comparison Program .
6GilotL
~~1. With analyses not being performed as required, report the corrective schons taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.~~
2. In the event a limit and/or ==*=ted actions requirements identified in Sechons 12.5.A and 12.5.B cannot be sabsfied because of circumstances in excess of those addressed in these Sechons, no changes are required in the sW conditica of the plant, and this does not prevent the plant from entry into an opershonal mode Surveillance Requirements 12.5.3.B The results of the analyses performed as part of the required crosscheck progrFm shall be included in the Annual Radiological Environmental Operating Report. The analyses shall be done in accordance with Sechon 5.3.1 and Chapter 11.
Bases 12.5.3.C The requirement for participabon in the interlaboratory comparison crosscheck program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioachve matenal in environmental sample matrices are performed as part of the quality assurance program for environrrental monitoring in order to demonstrate that the results are reasonably valid.
EPSPROJ/odomhsues12ri-er 12-42
QUAD CITIES Revision 1.0 June 1996 TABLE 12.5-3 NOTE: This table is superseded upon UREMP Implementation. See Chapter 9 for UREMP LLDa/MDCs.
PRACTICAL LOWER LIMITS OF DETECTION ft i n)
FOR STANDARD ENVIRONMFNTAL RADIOLOGICAL MONITORING PROGRAM Sample Media Analvsis LLQ'2 UDitt
! (4.66 a )
! Airbome " Particulate" Gross Beta + 0.01 pCi/m' Gamma Isotopic 0.01 pCi/m*
Airbome 1-131 lodine 131 0.10 pCi/m8 Milk /Public Water 1-131 5' pCi/l Cs-134 10 pCl/l j Cs-137 10 a pCi/l
~~Tritium 200 pCl/l i~~
Gross Beta + 5 pCill Gamma Isotopic 20 pCill/nuclide Sediment Gross Beta + 2 pCilg diy Gamma Isotopio 0.2 pCilg dry Fish Tissue 1-131 Thyroid 0.1 pCilg wet Cs-134,137 0.1 pCi/g wet Gross Beta + 1.0 pCi/g wet i
Gamma Isotopic 0.2 pCilg wet 0.5 pCi/l on milk samples collected during the pasture season.
+ Referenced to Cs-137 A 5.0 pCl/l on milk samples l
1 I
EPSPROJ/odem/ quad /12ri-8f 12-43
I l
QUAD CITIES Rsvision 1.8 !
Juna 1996 j TABLE 12.5 3 (Continued)
PRACTICAL LOWER LIMITS OF DETECTION (LLD)
FOR STANDARD ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM TABLE NOTATION A. The LLD is the smallest concentration of radioachve metenal in the sample that will be detectisd with 95 percent probability with only 5% probability of falsely concluding that a blank observation represents a "real" sequel.
For a particular measurement system (which may include radiochemical separation) 4.66.s.
LLD =
A ' E ' V 2.22 Y exp (-A a t) t Where:
LLD is the "a priori" lower limit of detecbon for a blank sample or background analysis as defined above (as pCi per unit mass or volume).
j s, is the square root of the background count or of a blank sample count; is the estimated l standard error of a background count or a blank sample count as appropriata (in units of counts).
j E is the counting officency (as counts per disintegrabon).
l l A is the number of gamma rays emitted per disintegrabon for gamma ray radionuclide t
analysis (A=1.0 for gross alpha and tritium measurements).
V is the sample size (in units of mass or volume).
l 2.22 is the number of disintegrabons per minute per picoeurie.
Y is the frschonal radio <:hormcal yield when applicable (otherwise Y = 1.0).
A is the radioachve decay constant for the particular radionuclide (in units of reciprocal minutes).
i at is the elapsed time between the midpoint of sample collechon and the start time of l counting. (at = 0.0 for environmental samples and for gross alpha measurements).
t is the durabon of the count (in units of minutes).
I l
l EPSPROJ/ockmVgued/12rt-8f 12-44 s
QUAD CITIES Rr, vision 1.8 Juna 1996 TABLE 12.5-3 (Continued)
PRACTICAL LOWER LIMITS OF DETECTION (LLD)
FOR STANDARD ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM TABLE NOTATION )
The value of "s," used in the calculatiori of the LLD for a detecbon system shall be based on an actual observed background count or a blank sample count (as appropriate) rather than on an unverified theoretically predicted value. Typical values of "E", "V", "Y", "t", and "At" shall be used in the calculation.
For gamma ray radionuclide analyses the background counts are determined from the total counts in the channels which are within plus or minus one FWHM (Full Width at Half Maximum) of the gammts ray photopeak energy normally used for the quantitative analysis for that radionuclide. Typical values of the FWHM shall be used in the calculation.
The LLD for all measurements is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular sample measurement.
B. Other radionuclides which are measurable and identifiable by gamma-ray spectrometry, together with the nuclides indicated in Table 12.5 2, shall also be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being present at the LLD level for that nuclide.
EPSPROJ/odem/ quad /12ri-8f 12-45
I QUAD CITIES Rsvision 1.8 Jun31996 l 12.5.4 Mondonna Pronram (if UREMP has not been implemented, see Sechon 12.5.1.)
l Ooer=hiliev paaniements l
12.5.4.A ' The Radiological Environmental Monitonng Program shall be conducted as l specified in Table 9.1-1 of Chapter 9 and Chapter 11.
Anchcatuidy- At all times.
l l bgll90'
~~1. With the Radiological Environmental Monitonng Program not being l conducted as specified in Table 9.1-1 of Chapter 9 and Chapter 11, 1 l~~
see Chapter 9 for required schons l
l- Surr '"- a p=i_..a.
l 12.5.4.B The radiological environmental monitonng program samples shall be collected pursuant to Table 9.1-1 of Chapter 9 and Chapter 11. See Chapter 9 for detailed survedlance requirements.
12.5.4.C The Radiological Envuonmental Monitonng Program required by this specificebon pnmdes measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radabon exposures of MEMBERS OF THE PUBLIC resulting from the station opersbon See Chapter 9 for detailed informahon in addition, this requirement is stated in Technical Speedestions.
EPsPROJ/odom/gued/12ri-Of 12-46
QUAD CITIES Rsvision 1.8 June 1996 l 12.5.5 Land Use Census (if UREMP has not been implemented, see Section 12.5.2.)
Onar= hili +v Raanirements 12.5.5.A. A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of the census.
l Anchcabihty' At all times.
l Achon l 1. See Sechon 9.2 of Chapter 9 for more details.
Survaillance Raaniraments l 12.5.5.B See Sechon 9.2 of Chapter 9 for more details.
p____
12.5.5.C See Secbon 9.2 of Chapter 9 for required surveillances and T6chnical Specifications for more bases details. !
l EPSPROJ/odenWoueW12rt et 12 47 i
QUAD CITIES Rsvision 1.8 Juns 1996 l 12.5.6 Intertaboratarv Can= deen Prooram (If UREMP has not been implemented, see Section 12.5.3.)
Ooerability Reauirements i
12.5.6.A Participation in an interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurement of radioactive materials in the environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
Anchcability At all times.
Action l 1. See Sechon 9.2 of Chapter 9 for required actions.
Surveillance Reauirements l 12.5.6.0 See Seebon 9.2 of Chapter 9 for surveillance requirements.
Bases 12.5.6.C See Sechon 9.2 of Chapter 9 for more information. In addition, this requirement is stated in Technical Specifications.
EPSPROJ/odem/gued/12r14f 12-48
QUAD CITIES Rsvision 1.8 June 1996 l 12.6 REPORTING REQUIREMENTS Records and/or logs relative to the following items shall be kept in a manner convenient for review and shall be retained for at least 5 years:
Records and penodic checks, inspechon and/or calibrabons performed to verify that the surveillance requirements (see Sechon 6.4 of the Technical Specifications) are being met (all equipment failing to meet survedlance requirements and the corrective action taken shall be recorded);
Records of radioachve shipments; Records and/or logs relatrve to the following items shall be recorded in a manner convenient for review and shall be retained for the life of the plant Records of offsite environmental monitonng surveys; Records of radioactmty in liquid and gaseous wastes releaser' to the environment; Records of reviews performed for changes made to the Offsete Dose Calculation Manual.
12.6.1 Radioachve Effluent Release Report .
The Radioachve Emuent Release Report covering the opershon of the unit during the previous 12 months of operation shall be submitted prior to April 1 of each year. The report shallinclude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objechves outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Sechon IV.B.1 of Appendix i to 10 CFR Part 50.
The Radioachve Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring Evaluabng, and Reporting Radioactivity in Solid Wastes and Releases of Radioachve Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summanzod on a quarterly basis following the format of Appendix B thereof.
The Radioachve Effluent Release Reports shall include a list and description of unplanned releases from the site to areas beyond the site boundary of radioactive matenals in gaseous and liquid effluents made during the reporting penod The Annual Radioachve Effluent Release Reports shall include any changes made dunng the reporting penod to the PCP, as well as any major changes to Liquid, Gaseous or Solid Radwasts Treatment Systems, pursuant to Section 12.6.3.
"A single sutwnsttal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the stabon; however, for units with separate radweste systems, the submittal shall specify the releases of radioactive matenal from each unit.
EPSPROli .. , "'12r14f 12-4g
QUAD CITIES Rsvision 1.8 June 1996 The Annual Radioactive Effluent Release Reports shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentabon was not corrected within the specified time and description of the events leading to liquid holdup tanks or gas storage tanks exceeding .the limits of Technical Specifications.
12.6.2 Annual Radiological Environmonial Operahng Report (if UREMP has been implemented, see 12.6.3 for requrements.)
An annual report containing the data taken in the standard radiological monitoring program (Table 12.5-1) shall be sutxnitted prior to May 1 of each year. The content of the report shallinclude:
a. Results of all environmental measuromonts summartzed in the format of the Regulatory Guide 4.8 Table 1 (December 1975). (Individual sample results will be retained r' the Station). In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for missmg resubs. Summanos, interpretabons, and ana ysis of trends of the results are to be provided
b. An assessment of the monstonng results and radiation dose via the principal pathways of exposure resultmg from plant emiassons of radioactuty including the maximum noble gas gamme and beta air doses in the unrestncted area.
~~The assessment of radiation doses shall be performed in accordance with the Offsite Does Calculation Manual (ODCM).~~
~~c. Results of the census to determme the locahons of nearest residences and of neertpy animals producmg milk for human consumphon (Table 12.5-1).~~
~~d. The reason for the emission if the nearest dairy to the station is not in the monitonng program (Table 12.5-1).~~
e. An annual summary of huisical conditions concurrent with the releases of gaseous effluents in the form of joint frequency distributions of wind speed wind direchon, and atmospheric stability.
~~f. The results of the interlaboratory Comparison Program described in Secnon 12.5.C.3.~~
~~g. The results of the 40 CFR 190 uranium fuel cycle does analysis for eace calendar year.~~
h. A summary of the monitoring program, including maps showing sampling locahons and tables giving distance and direction of samping locations from ***
~~Stabon~~
3. If a confirmed measured radionuchde concentration in an environmental sampling l medium averaged over any calendar quarter sampling penod exceeds the reportmg level given in Table 12.5-2 and if the radioactrvity is attributable to plant operation. a wntten report shall be submitted to the Administrator of the NRC Regional Office. em a copy to the Director, Office of Nuclear Reactor Regulation, within 30 days from the end of the quarter.
EPSPROJ/odan/ quad /12rt.at 12-50 1
}
\
QUAD CITIES Rsvision 1.8 June 1996 12.6.2 Annual Radiological Environmental Operating Report (Con't)
~~a. When more than one of the radionuclides in Table 12.5-2 are detected in the medium, the reporting level shall have been exceeded if~~
._ C _ E 1 R. L .,
where C, is the average quarterty concentration of the i radionuclide in the medium and RL is the reporting level of radionue!& l.
b. If radionuclides other than those in Table 12.5-2 ore detected and are due to plant effluents, a reporting level is exceeded if the potential annual dose to an individual is equal to or greater than the design objective doses of 10 CFR 50, Appendix 1,
~~c. This report shall include an evaluation of any release conditions, environmental (actors, or other aspects necessary to explain the anomalous effect.~~
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I EPSPROJ/odcrivguad/12ri-8f 12-51
QUAD CITIES Rsvizion 1.8 June 1996 12.6 REPORTING REQUIREMENTS 12.6.3 Annual Radiological Environmental Operating Report (if UREMP has not been implemented, see i Section 12.6.2.) !
Ooer=hiliev Raanirements 12.6.3.A Routine Annual Radio'ogical Environmental Operating Report covering the operation of the Units during the provous calendar year shall be submitted prior to May 1 of each year.
Annicabsbtg. At all times.
&GtlGG
~~1. See Sechon 9.4 of Chapter 9 for information.~~
Survedlanca Requiramari'd _
12.6.3.B Se,4 Sechon 9.2 of Chapter 9 for more information p __
12.6.3.C See Sechon 9.2 of Chapter 9 for more information and Technical Specification 6.9.1.6.
EPSPROJ/odom4 ped /12ri-of 12-52
QUAD CITIES Rsvision 1.8 June 1996 12.6.4 OFFSITE DOSE CALCULATION MANUAL (ODCM)
The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid emcents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs described in sechons 12.2-12.5 and (2) descriptions of the infocn &, that should be included in the Radioactive Effloant Release Reports and in the Annual Radiological Environmental Operating Reports roouired by sections 12.6.2.
The ODCM shall be subject to review and approval by the Commission prior to implementation.
Changes to the ODCM:
~~1. Shall be documented and records of reviews performed shall be retained as required by Specification 6.5.8.14(Upgraded Specdcation 6.14.A). This documentabon shall contain:~~
~~a. Sufficent informahon to support the change together with the ,~~
~~appropnate analyses or evaluabons justifying the change (s) and~~
b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and Appendix 1 to 10 CFR Part 50 and not adversely impact the accuracy or reliability of ef!Iuent, dose, or setpoint calculations.
2. Shall become effechve after review and acmptance by the Onsite Review and investigabwe Function and the approval of the Plant Manager on the date specded by the Onsite Review and Invesugative Funcbon
3. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM or updated pages, if the Commmasion retains a controlled copy if an entire copy of the ODCM is submitted, it shall be submitted as a part of or concurrent with the Radioachve Effluent Release Report for the period of the report in which any change to the ODCM was made effeebve Each change shas be identified by markings in the margin of the affected pages, clearfy indicabng the area of the page that was changed, and sha!I indicate the date (e.g., i month / year) the change was implemented.
l l
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EPSPROJ/odenvoundM2rt 8r 12 53 1
QUAD CITIES Rzvision 1.8 June 1996 12.6.5 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (LIQUID AND GASEOUS)
A. Licensee initiated major changes to the radioactive waste systems may be made provided:
~~1. The change is reported in the Monthly Operating Report for the period in whien the evaluation was reviewed by the onsite revew function. The discussion of each change shall contain:~~
~~a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10CFR50.59;~~
~~b. Sufficient detailed information to support the reason for the change;~~
~~c. A detailed description of the equipment, coroponents, and process involved and the interfaces with other plant systems;~~
d. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous emuents and (or quantity of solid waste that differ from those previously predicted in the license applicabon and amendments);
~~e. A comparison of the predicted releases of rad a materials in liquid and gaseous emuents and in solid waste to the actual releases for the period in which the changes were made;~~
~~f. An estimate of the exposure to plant operating personnel as a result of the change; and~~
~~g. Documentation of the fact that the change was reviewed and found acceptable by the onsite review function.~~
~~2. The change shall become effective upon review and acceptance by onsite review function.~~
EPSPROJ/odem/qued/12r1-8f 12-54
l QUAD CITIES Rsvision 1.8 Juna 1996 APPENDIX F Quad Cities Annex Index EAGE REYlSlQH PAGE REVISION F-i 1.8 F-38 1.8 F-ii 1.8 F-37 1.8 F-iii 1.8 F-38 1.8 F-iv 1.8 F-39 1.8 F-1 1.8 F-40 1.8 F-2 1.8 F 41 1.8 F-3 1.8 F-42 1.8 F-4 1.8 F-43 1.8 F-5 1.8 F 44 1.8 F-8 1.8 F-45 1.8 F-7 1.8 F-46 1.8 F-8 1.8 F-47 1.8 F-9 1.8 F-48 1.8 F-10 1.8 F-49 1.8 F-11 1.8 F-12 1.8 F-13 1.8 l F-14 1.8 F-15 1.8 l i F-18 1.8 F-17 1.8 F-18 1.8 F-19 1.8 F-20 1.8 F-21 1.8 F-22 1.8 F-23 1.8 F-24 1.8 l F-25 1.8 '
F-26 1.8 F-27 1.8
. F-28 1.8 F-29 1.8 F-30 1.8 F-31 1.8 F-32 1.8 F-33 1.8 i
F-34 1.8 F-35 1.8 l
l l
EsPO4 w it;r '7. ; ef F-i
l TelEhReinLJ tr(eVisionYt.)
June 1996 l APPENDIX F STATION-SPECIFIC DATA FOR QUAD CITIES UNITS 1 and 2 TABLE OF CONTENTS }
l l
PAGE F.1 INTRODUCTION F-1 F.2 REFERENCES F-1
. .k l
'h, 1
O ESP 0,ModcrWquadMM-St F.;i
l QUAD CITIES Rsvision 1.8 Juna 1996 APPENDlX F LIST OF TABLES NUMBER IIILE PAGE F-1 Aquatic Environment Dose Parameters F-2 F-2 Station Characteristics F-3
> F-3 Critical Ranges F-4 F-4 Average Wind Speeds F-5 F-5 X/Q and D/Q Maxima at or Beyond the Unrestricted Area Boundary F-6 F-Sa X/Q and D/Q Maxima At or Beyond the Restricted Area Boundary F-7 F-6 D/Q at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles F-8 F-7 Maxime:n Offsete Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestncted Area Boundary for Selected Nuclides F9 F-7a Maximum Offsete Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boundary for Selected Nuclides F-24 F-8 Parameters for Calculation of N-16 Skyshine Raciation from Quad Cities F-39 Supplemental Tables A Elevated Level Joint Frecuency Distribution Table Summary - 296 Foot Elevation Data F4:
-Summary Table of Percent by Direction and Class
-Summary Table of Percent by Direction and Speed
-Summary Table of Percent by Speed and Class B Mixed Mode Joint Frequency Distribution Table Summary - 196 Foot Elevation Data F4:
-Summary Table of Percent by Direction and Class
-Summary Table of Percent by Direebon and Speed
-Summary Table of Percent by Speed and C. ass C Ground Level Joint Frequency Distribution Table Summary - 33 Foot Elevation Data F46
-Summary Table of Percent by Direction and Class
-Summary Table of Percent by Direction and Speed
-Summary Table of Percent by Speed and Class ESM1MoslowMguedW1-Of F-iii
QUAD CITIES Rcvision 1.8 l
Juna 1996 APPENDIX F LIST of FIGURES NUMBER IIILE PAGE F-1 Unrestncted Area Boundary F-48 F-2 Restncted Area Boundary F-49 4
w -of F-iv
l QUAD CITIES Rsvision 1.8 June 1996 APPENDIX F STATION-SPECIFIC DATA FOR QUAD CITIES UNITS 1 and 2 F.1 INTRODUCTION This appendix contains data relevant to the Quad Cities site. Included are a diagram of the unrestricted l area boundary and tables of values of parameters used in offsite dose assessment.
F.2 REFERENCES
~~1. Sargent & Lundy, Ar$alysis and Technology Division, Quad Cities Calculation No. ATD-0148, l Revision 0,1 and 2.~~
~~2. Sargent & Lundy, "N-16 Skyshine Ground Level Dose from Quad Cities Turbine Systems and Piping," Revision O.~~
~~3. " Quad Cities Public Water Supply" letter from B.S. Ferguson (NSEP) to G. Wassenhove U.S.~~
Army Corps of Engineers, February 16,1989. !
l 4. " Verification of Environmental Parameters used for Commonwealth Edison Company's Offsite
! Dose Calculations", NUTECH Engineering Group,1992.
~~5. " Verification of Environmental Parameters used for Commonwealth Edison Company's Offsite Dose Calculations", NUS Corporation,1988.~~
ESP 0hdcrMpue&H.0f F.1
l QUAD CITIES Rsvision 1.8 June 1996 Table F-1 -
Aquatic Environment Does Parameters General Information' Existence of irrigation not mentioned in Quao Cities Final Safety Ana'ysis Report (FSAR), UFSAR, or Plant Design Analysis.
Recreation includes one or more of the following: boating, water skiiing, swimming and sport fishing.
The station liquid discharge flows into the Mississippi River. Mississippi River Lock and Dam Number 14 is located between the station discharge and the E. Moline intaka (see Figure 12 of the Quad Cities Unit 1 Plant Dessgn Analysis, Volume ll, and Figure 2.4.1 of the Quad Cities Safety Analysis Report.)
Water and Fish inamahn Paranators Parameter
Value 1/M",1/M' 1.0 F",cfs 5.75E4 F', cfs 5.75E3 t', hr* 24.0 t",hrd 8.0 Limits on RntrW in Unsic:W Outdoor Ttanks Not Applicable (See Section A.2.4 of Appendix A)
Quad Cities Updated Final Safety Analysis Report (USFAR) updated through Amendment 5 (9-3-87)
Section 1.5.2 and Quad Cities Plant Design Analysis, Section 4.4 The parameters are defined in Sechon A.2.1 of Appendix A.
~~l t' (br) = 24 hr (all stabons) for the fish ingestion pathway t" (br) = 8 hr (Distance to the nearest public potable water intake, E. Moline, is 16 miles; flow rate of 2 mph is assumed)~~
Espo::::2: ~. e-ar F.2
l QUAD CITIES Rsvision 1.8 s, Jun31996 l
Table F-2 ,
Station Characteristics l 1
~~ation: Quad Cities Nuclear Power Station Location: Cordova, Illinois Characteristics of Elevated Release Point~~
~~1) Release Height = 94 49 m' 2) Diameter = 3 35 m~~
~~3) Exit Speed = 16.0 m s"* 4) Heat Content = .SR.kCa1 s"'~~
~~Characteristics of Vent Stack Release Point~~
~~1) Release Height = 48.5 m' 2) Diameter = 2.74 m~~
3) Exit Speed = 14 8 m s"*
~~Characteristics of Ground Level Release~~
~~1) Release Height = 0 m~~
2) Building Factor (D) = 43A _m*
Meterological Data A 296 ft Tower is Located 1523 m SSE.of Elevated Release Point Tower Data Used in Calculations Wind Speed and Differential Release Point Direction Temoerature Elevated 296 ft 296-33 ft Vent 196 ft 196-33 ft Ground 33 ft 196-33 ft Used in calcul4 ting the meteorological and dose factors in Tables F-5, F-6, and F7. Sw Sections B.3 through B.6 of Appendix B.
ESPOatJ ,
^:.;4f F-3
l l QUAD CITIES Rsvision 1.0 June 1996 i
Table F-3 ;
Critical Ranges i
Unrestncted Area Restricted Area Nearest Dairy Farm )
Boundary
~~Boundary~~
~~Nearest Resident" within 5 Miles * {~~
Direction (m) (m) (m) (m)
N 864 219 800 None NNE 1029 224 1200 None NE 1212 265 2000 None ENE 1367 393 2000 None E 1170 867 3600 None ESE 1170 924 4800 5600 SE 1189 1010 4000 None l SSE 1422 1059 1600 None S 1198 762 1200 None SSW 2140 335 4800 None SW 1372 232 4800 None WSW 823 189 3200 None W 713 189 3600 None WNW 713 183 3600 None NW 823 210 3600 None NNW 1481 224 2800 None l
4
' Nearest land in unrestricted area. Used in calculating the meteorological dose factors in Tables F -
and F-7. See Sechons B.3 through B.6 of Appendix B.
These values are to the edge of the Mississippi River, where applicable.
The distances are rounded to the nearest conservative 100 meters.
Used in calculating the D/Q values in Table F-6. The distances are rounded to the nearest conservative 100 meters. A default value of 8000 meters is ur,ed when there are no dairies withm 5 miles.
ESPOAdcrWgus#f er F-4
Ju h QUAD CITIES Table F 4 Average Wind Speeds Average Wind Speed (m/sec)*
Ground Levef Mixed Mode Downwind Elevated
2.6 Direction 5.0 6.9 2.8 N 4.6 6.2 2.4 NNE 3.7 5.3 2.8 NE 4.4 6.0 3.2 ENE 5.0 3.7 6.9 E 5.2 3.6 7.1 ESE 4.9 3.5 6.5 SE 4.5 3.4 5.7 SSE 4.4 3.3 5.6 S 4.4 5.6 3.0 j SSW 4.6 '
3.4 5.8 SW 4.7 3.1 6.0 4.8 WSW 6.1 2.6 W 4.5 2.4
! 6.0 WNW 4.4 2.5 5.9 NW 4.7 6.5 NNW i
fr t
January 1978 through December 1987 d l ses.
~~Based on Quad Cities site lysis and 1982-1987 meteorological da a, data for eleva ground level and mixed mode release anaCalculate~~
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l QUAD CITIES Rsvision 18 i Juna 1996 Table F-8 Parameters for Calculations of N 16 Skyshine Radiation Fmm Quad Cities i l
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Location Activity Occupancy Occupancy Shielding Distance Number Hours Factor Factor R. k OH,' OF, SF, (m) 1 Living at home 8616 0.9836 0.7 800" (nearest resident) 2 Fishing 36 0.00410 1.0 233* 3 Fishing 51 0.00586 1.0 344' 4 Fisning 31 0.00351 1.0 361* 5 Fishing 26 0.00293 1.0 680* M,,= 5' K = 3.80E-05 mrem /(MWe-hr) These parameters are used to obtain an initial estimate of skyshine dose to the maximally exposed member of the public using Equation A-34 in Appendix A. If desired, more realistic parameters cow be used in place of these to refine the estimate. For example, one could determine whether the nearest resident really fishes the specified number of hours at the specified location. The amount of time in a year that a maximally exposed fisherman would spend fishing near the s a is estimated as 12 hours per week for 8 months per year. This yields an estimate of: [12 hours / week] [(8 months /yr)/(12 months /yr)] x [52 weeks /yr] = 416 hours /yr The remaining time is assumed to be spent at the nearest residence. Distance to nearest residence (See Table F-3).
Estimated from drawings of the site.

The OF,is the quotient of the number of hours a location is occupied and the number of hours .n a ,
year. Thus OH,/8760 hours = OF, rounded to the 0.01 digit. l l Multiplication factor for hydrogen addition. Refer to equation A-34 of Appendix A. NE F-39
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