Text

Revs to ODCM for Zion Station,Including Rev 2 to Chapters 10 & 12
	ML20217N966
Person / Time
Site:	Zion File:ZionSolutions icon.png
Issue date:	03/31/1998
From:	; COMMONWEALTH EDISON CO.
To:	;
References
	PROC-980331, NUDOCS 9805060012
	Download: ML20217N966 (86)
	v • d • e

X244 ALL Document ControlIksk Director of Nuclear Reactor Regulation ,

( U.S. Nuclear Regulatory Commission Mail Station I'l-137 Washington, DC 20555 April 13,1998 Attached is a revision to the Offsite Dose Calculation Manual, LaSalle Annex, Chapters 10 and 12.

Please update your manual as follows:

Remove: ,

l Zion Chapter 10, Revision 1.9 I Zion Chapter 12, Revision 1.8 Insert:

Zion Chapter 10, Revision 2 Zion Chapter 12, Revision 2 t'

(

Please sign below indicating your manual has been updated and that your controlled copy number is correct.

Name- Date Return to:

Comed Central Files 1400 Opus Place,4th Floor Downers Grove,IL 60515 \ \.

~

f~

c oi Central Files p)

\

4th Floor Downers Grove h:\odem\ctridist. doc 9805066012 900331 5 PDR ADOCK O

1 Zion Station Chapter 10 Change Summary ODCM Revision 2, March 1998 Paae Chanae Description

. .10-1 Updated revision number and file designator.

10-ii,1, 2 Changed " Vent" to " Ventilation" to avoid confusion with the Containment Vent.

10-13 Deleted ORT-PR14 from Figure 10-1. This instrument has been abandoned. Deleted A from EPNs for 1RE-0015 and 2RE-0015.

10-13,15' Enlarged figures for better legibility, l

O I

O

ZION Rev sion 2 ZION ANNEX INDEX CHAPTER 10 REVISION 2 l

10 1

i O

zi0r2 doc I

10-i j

ZION Revision 2 March 1998 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS PAGE l 10.1. AIRBORNE RELEASES .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10-1 l

10.1.1 System Description.. .. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 10-1 10.1.1.1 Waste Gas Holdup System ... .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 10-1 10.1.1.2 Ventilation Exhaust Treatment System .... .. .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10-1 10.1.2 . Radiation Monitors ... . .. ....... .. .... .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 10-1 10.1.2.1 Final Ventilation Stack Effluent Monitors........... .. . . .............. ....... .. . . . . . 10-1 10.1.2.2 Auxiliary Building Ventilation Effluent Monitors . . . . . . . . . . . . . . . . . . . . . . . . 10-2 10.1.2.3 Containment Purge Effluent Monitors.... ....... ....... .. . ..... .. .. ... . .. .. .. ......... . . 10-2 10.1.2.4 Waste Gas Decay Tank Monitors... .. .... ... ... ......... . . . . . . . . . . . . . . . . . . . . . 10-2 j 10.1.2.5 Condenser Air Ejector Monitors....... .. .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10-3 10.1.3 Alarm and Trip Setpoints... . . . . .. . . . . .. . . . . . . . . , . . . . . . . . . . . 10-3 10.1.3.1 Setpoint Calculation... . . . . . . . ..... . . . . . . . . . . . . . . . . . . . . . . . . . 10-3 i

10.1.3.2 Release Limits.. . .. . . . ... . . . . . . . . .. . . . . . . . . . . . . . .. . . 10-3 l 10.1.3.3 Release Mixture.... . .. .. .. .... . . . . ...... .. . . . . . . . . . . . . . . . . . . . . . . . . . . 10-4 10.1.3.4 Conversion Factors . . ... . . . .. .... . . . . . . .. . . . .. .. . .. . .. . . . . ... .. . .. . . . 10-4 10.1.3.5 HVAC Flow Rates .. ... . ... . ... ... .... . . . . . . . . . . . . . . . ... . .. . . . . . 10-5 10.1.4 Allocation of Effluents from Common Release Points'.. . .. ..... . . .. ... 10-5 l b

10.1.5 Dose Projections for Batch Releases . ... .. .... . . ......... ......... .. . . . . . . . . . . . . 10-0 L l

10.2 LIQUID RELEASES. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 0-6 10.2.1 System Description. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10-6 10.2.1.1 Lake Disc arge Tanks.. . .. . . . .. . . . . . . . . . . . . . . . . . . . . . .. . . 10-6 10.2.1.2 Turbine Buildeg Fire Sump.. .. . . . . . . . . . . . . . . . . . .. .. . . . . . . . . . . . 10-6 10.2.2 Radiation Monitors... . . . . . .. ...... ... .. .. . . . . . . . . . . . . . .. .. . . 10-6 l

l 10.2.2.1 Lake Discharge Tank Monitors.. .. . . .. ... . . . . . . . . . . . . . . . . .. 10-6 10.2.2.2 Turbine Building Fire Sump Monitor... . . . . . . . . . . . . . . . . . . . . . . .. . 10-6

, 10.2.3 Alarm and Trip Setpoints... . . . . . . . . . . . . . ......................................10-7

! 10.2.3.1 Setpoint Calculation .. . ...... . ...... ... . .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10-7 i !

l !

F l

i-I 1

f

\

! zior2 doc 10-il

Z!ON Revision 2 March 1998 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS (Cont'd)

PAGE Discharge Flow Rates. .. . . 10-8 10.2.3.2 .

10.2.3.2.1 Lake Discharge Tank Discharge Flow Rate... . ... . . . . . . .10-8 10.2.3.2.2 Turbine Building Fire Sump Discharge Flow Rate . .. . . . . . . .10-8 10.2.3.3 Release Limits . . . .. ..... . . .. .. . .10-8 10.2.3.4 Retease Mixture... . .. . . . . . . . . . . .. . ... . . . . . . . . .10-8 i

10.2.3.5 Conversion Factors . . .. . . . . . . . . . . . . . . . . . . .. .10-9 10.2.3.6 Liquid Dilution Flow Rates.. . ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10-9 10.2.4 Allocation of Effluents from Common Release Points . . . . . . . . . . . .10-9 10.2.5 Proiacted Concentrations for Releases.... .. . . .... . . . . .... . . .. 10-9 SOUDIFICATION OF WASTE / PROCESS CONTROL PROGRAM . . . .. .10-9 10.3 O

O zior2. doc 10-iii

ZION Revision 2 March 1998 CHAPTER 10 LIST OF TABLES O

NUMBER TLILE PAGE 10-1 Assumed Composition of the Zion Station Noble Gas Effluent 10-10 10-2 HVAC Exhaust i% Capacities 10-11 10-3 Liquid Dilution Flow Pump Capacities 10-12 O

i O

10-iv

ZION Revision 2 )

March 1998 CHAPTER 10 l I

LIST OF FIGURES NUMBER TITLE PAGF, 10-1 Simplified Gaseous Radwaste and Gaseous Effluent Flow Diagram 10-13 10-2 Simplified Liquid Radwaste Processing Diagram 10-15 10-3 Simplified Liquid Effluent Flow Diagram 10-16 10-4 Simplified Solid Radwaste Processing Diagram 10-17 10-5 Example NMC Monitor Response 10-18 4

i O

zi0r2. doc 10-v i . .

ZION Revision 2 March 1998 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1 System Description A simplified gaseous radweste and gaseous effluent flow diagram is provided in Figure 10-1. The principal release points for potentially radioactive airbome effluents are the two auxiliary building ventilation stacks (designated Unit 1 Ventilation Stack and Unit 2 Ventilation Stack in Figure 10-1). In the classification scheme of Section 4.1.4, each is classified as a ground level release point (see Table A-1 of Appendix A).

10.1.1.1 Waste Gas Holdup System The waste gas holdup system is designed and installed to reduce radioactive gaseous effluents by collecting reactor coolant system off1ases from the reactor coolant system and providing for dt:lav or holdup to reduce the total radioactivity by radiodecay prior to release to the enviro...nent. The system is described in Section 11.1.2.3 of the Zion FSAR.

10.1.1.2 Ventilation Exhaust Treatment System Ventilation exhaust treatment systems are designed and installed to reduce gaseous radiolodine or radioactive material in particulate form in gaseous effluents 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 considered to have any effect 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 Monitors 10.1.2.1 Final Ventilation Stack Effluent Monitors Monitors 1RIA-PR49 (Unit 1) and 2RIA-PR49 (Unit 2) continuously monitor the final effluent from the ventilation stacks. Both ventilation stack monitors feature automatic l isokinetic sampling and grab sampling.

During normal operation, nll three noble gas channels (low range, mid range, high range) are on line and active. A high alarm condition from the mid and/or high range noble gas channels isolates the particulate, iodine, low range noble gas and mid range noble gas channels. The high alarm signal diverts sample flow through a sample cart (particulate and lodine) and then to the high range noble gas channel.

zior2 doc 10-1 J

ZION Revision 2 March 1998 Upon receipt of the high alarm, the control room operator will notify the health physics group and reduce the release rate as appropriate. Due to conservatism built into the setpoint calculations (Section 10.1.3), there is an adequate margin between the high alarm setpoint and the release limit to accommodate this procedure.

Pertinent information on these monitors is provided in UFSAR Table 11.5-1.

10.1.2.2 Auxiliary Building Ventilatun Effluent Monitors l Monitors 1RT-PR25 (Unit 1),2RT-PR25 (Unit 2) and ORE-0014 (common) continuously monitor the effluent from the auxiliary building ventilation stacks.

No automatic isolation or control functions are performed by these monitors. On high alarm, the control room operator will notify the health physis group and reduce the release rate as appropriate. Because of the conservatism built into the setpoint calculations (Section 10.1.3) there is an adequate margin between the setpoint and release limit to accommodate this procedure.

Pertinent information on monitor ORE-0014 is provided in UFSAR Table 11.5-2.

10.1.2.3 Containment Purge Effluent Monitors Monitors 1RT-PR09 (Unit 1) and 2RT-PR09 (Unit 2) continuously monitor the eftiuent from the Unit 1 and Unit 2 containments, respectively. On high alarm, the monitors automatically initiate closure of the four air-operated butterfly valves (RV0001/2/3/4 purge valves for each unit).

Pertinent information on these monitors is provided in UFSAR Tables 11.5-1 and 11.5-2.

Monitors 1(2)RIA-PR40 continuously monitor the Unit 1(2) atmosphere. On high alarm, the monitors automatically initiate closure of valves RV0001-RV0006 inclusive.

10.1.2.4 Waste Gas Decay Tank Monitors Monitors OR1 A-PR10 (Channels 1 and 3) continuously monitor the noble gas activity released from the gas decay tanks.

On high alarm, the monitors automatically initiate closure of the valve ORCV-WG014 thus terminating the release.

Pertinent information on these monitors is provided in UFSAR Section 11.5.2.2.1 and Table 11.5-2.

The monitor is capable of collecting particulate and iodine samples for post release quantification.

l l

zion. doc 10-2 l

l

ZION Revision 2 March 1998 10.1.2.5 Condenser Air Ejector Monitors (q

, Monitors 1RE-0015 and 2RE 0015 continuously monitor the condenser air ejector gas from Units 1 and 2, respectively. No control device is initiated by these channels.

Pertinent information on these monitors is provided in UFSAR Table 11.5-2.

10.1.3 Alarm and Trip Setpoints 10.1.3.1 Setpoint Calculation The effluent noble gas monitor setpoints are conservatively based on the assumption that a release is occurring simultaneously for all seven gaseous release points at the maximum I

expected flow rate for each pathway. Furthermore, the setpoints are chosen such that an l occurrence of simultaneous high alarms on all seven pathways would correspond to a l station release rate of one half of the Technical Specification limit.

P., s 0.5 x Qi, x 1/F" x K" x C" (10-1) l Pp= Setpoint for monitor, u, on release path, P. [ cpm]

l l 0.5 = Factor to reduce release rate by 50%.

l l l Q=i Total Allowed Release Rate, Vent Release [ Ci/sec) l l

l F* = Flow rate through Release Path, P. [ cc/sec) 1 K" = Factor to apportion a fraction of the total release rate, Qi., to release path, P. l

\v C" = Conversion Factor for monitor, u. [ cpm per Ci/cc) 10.1.3.2 Release Limits ,

1 Alarm and trip setpoints of gaseous effluent monitors are established to ensure that the l release rate limits of the RETS are not exceeded. The release limits are found by solving l Equations 10-2 and 10-3 for the total allowed release rate of vent releases, Qiv. l (1.11) Qi,I { V,f i } < 500 mrem /yr (10-2) l Q~ I {(f)i {Li (X/0), exp (-A,R/3600u v) (10-3)

! + 1.11 V,]} < 3000 mrem /yr i

zior2. doc

/"]

\j 10-3

ZION Revision 2 March 1990 The summations are over noble gas radionuclides 1.

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

Ou Total Allowed Release Rate, [pCi/sec)

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

The remaining parameters in Equation 10-2 have the same definitions as in Equation A-8 of Appendix A. The remaining parameters in Equation 10-3 have the same definition as in Equation A 9 of Appendix A.

Equation 10-2 is based on Equation A-8 of Appendix A and the RETS restriction on whole body dose rate (500 mrem /yr) due te noble gases released in gaseous effluents (see Section A.1.3.1 of Appendix A). Eq ation 10-3 is based on Equation A-9 of Appendix A and the RETS restriction on skin dose rate (3000 mrem /yr) due to noble gases released in gaseous effluents (see Section A.1.3.2 of Appendix A).

Equations 10-2 and 10-3 can each be solved for a value of Ow. The monitor alarm and trip setpoints will be established based on the equation which yields the smaller release limit, Qu. The exact settings are selected to ensure that 10 CFR 20 limits are not exceeded.

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 setpoints, the radioactivity mixture in exhaust air is assumed to have the radionuclide composition of Table 10-1. This mixture was conservatively chosen based on station isotopic release data averaged over a period of 7 years (1977 through June 1984).

10.1.3.4 Conversion Factors The response curves used to determine the monitor count rates are chosen in order to best match the reference noble gas mix. Because Xe-133 and Xe-135 comprise 83.6% and 8.79% of this mix respectively, the Xe-133/Xe-135 90%/10% curves are used to ensure that the setpoints would be conservative with raspect to quantity.

Example curves are shown in Figure 10-5.

l 1

l zi0r2. doc 10-4

ZION Revision 2 March 1998 10.1.3.5 HVAC Flow Rates D

ij

' HVAC flow rates are computed for 1(2)RT-PR25, ORE-0014 and 1(2)RIA-PR49 based on the number of operating fans in the monitored flow path.

Fu = EE F,p x N.

(10-4)

Fu = Total Flow in Monitored Flow Path [cc/sec) i i F., = Flow from fan i in path p. [cc/sec)

N, = Number of fans, in operation The maximum flow for each fan is used for setpoint calculations because this maximizes the flow, and therefore minimizes the calculated monitor sensitivity which is conservative.

Pertinent data for the fans is provided in Table 10-2. l l

HVAC flows for the remaining monitors are conservatively fixed at upper bound values.

They are listed below.

Mo'nitor Flow in cc/ses ORIA-PRIO 6.61E5 1(2)RE 0015 5.60E4 1RT-PR09A 1.65E6 (vent mode) 1.46E6 (mini-purge mode)

.O 1.46E7 (purge mode)

'Q 2RT-PR09A

" 4.35E6 (vent mode)*

4.11E6 (mini-pume mode) 1.99E7 (purge-mode) 2.70E6 (routine, hot lab only) 10.1.4 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the auxiliary building miscellaneous ventilation system and the gas decay tanks are comprised of contributions from both units.

Under normal operating conditions, it is difficult to apportion the radioactivity between the units. Consequently, allocation normally is made evenly between units.

' Flow greater than Unit 1 due to " hot lab" hood exhaust fan flow.

zior2. doc 10-5 l

l

ZION Revision 2 March 'i998 10.1.5 Dose Projections for Batch Releases Projected doses are calculated before purging the containment or venting the waste gas I decay tanks. Per procedure, a representative sample is obtained and analyzed, and the I total tr.,l ease is calculated. Prior to the release the projected dose rate (in mrem / year) is calculated based on the assumption that the release is continuous for the entire year.

10.2 LIQUID RELEASES 10.2.1 System Description A simplified liquid waste processing diagram is provided in Figure 10-2. A simplified liquid effluent flow diagram is provided in Figure 10-3.

The liquid radwaste treatment system is designed and installed to reduce radioective liquid effluents by collecting the liquids, providing for retention or holdup, and providing for treatment by demineralizer for the purpose of reducing the total radioactivity prior to release to the environment. The system is described in Section 11.1.3 of the Zion FSAR.

10.2.1.1 Lake Discharge Tanks There are two take discharge tanks (OA and OB,30,000-gallon capacity each) which receive liquid wasie before discharge to Lake Michigan.

10.2.1.2 Turbine Building Fire Sump The turbine building floor and equipment drain tanks receive turbine building waste which is released to the fire sump for processing by the waste water treatment facility and ultimate discharge into Lake Michigan. The discharge constitutes a low level radioactive release.

10.2.2 Radiation Monitors 10.2.2.1 Lake Discharge Tank Monitors Monitors ORT-PR04 and ORT PROS are used to monitor all releases from the lake discharge tanks. On high alarm, the monitor automatically initiates closure of a valve to prevent further releases. The valve is located over 250 feet downstream of the monitor to allow closure priorto exceeding release limits. The monitor setpoints are found by solving Equation 10-5 for release setpoint P.

Pertinent information on these moqitors is provided in UFSAR Table 11.5-3.

10.2.2.2 Turbine Building Fire Sump Monitor Monitor ORT-PR25 continuously monitors the discharge line from the fire sump pumps to j the waste water treatment facility. On high alarm, the monitor automatically trips all of the fire sump pumps, thereby containing the liquid in the turbine building. The monitor setpoints are found by solving Equation 10-5 for release setpoint P.

Pertinent information on the monitor is provided in UFSAR Table 11.5-3.

l z1or2. doc 10-6 l

ZION Revision 2 M!rch 1998 10.2.3 Alarm and Trip Setpoints 10.2.3.1 Setpoint Calculation

~

Alarrn and trip setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of the Technical Specifications and 10 CFR 20 are not exceeded in the unrestricted area. The monitor setpoints are found by solving Equation i

10-5 for a conservative mixture of radionuclides found in liquid effluents.

P s; K x (Cmpc)(F /F') ,

(10-5)

P Release Setpoint

[ Cl/mL]

The alarm setpoint for radioactivity to be released in liquid effluents.

l .

)

Cmpe Maximum Permissible Concentration [ Ci/mL] l

)

d F Dilution Flow Rate [gpm]

The flow rate of the radwaste dilution stream (condenser cooling water). ;

F' Discharge Flow Rate [gpm]

l I

The flow rate from the lake discharge tank or fire sump as appropriate. f i

K Factor of conservatism.

K = 0.5 forlake discharge tank K = 1.0 for sump l

l 1

i

/N i zior2. doc t

10-7 l '

ZION Revision 2 March 1998 10.2.3.2 Discharge Flow Rates 10.2.3.2.1 Lake Discharge Tank Discharge Flow Rate Prior to each batch release, the water is recirculated, sampled, and analyzed.

The results of the analysis of the waste sample determine the discharge rate of each batch as follows: 1 F'm., = (Cmg)(Fb/C) (10-6)

F'm., Maximum Permitted Discharge Flow Rate [gpm]

The maximum permitted flow rate from the lake discharge tank. [gpm]

F% Actual Dilution Flow Rate [gpm]

The actual flow rate of the radwaste dilution stream (based on pump curves).

C Sample Radioactivity Concentration [ Ci/mL]

The concentration of radioactivity in the lake discharge tank based on measurements of a , ample drawn from the tank.

Cmg has the s6me definition as in Equation 10-5. ,

10.2.3.2.2 Turbine Building Fire Sump Discharge Flow Rate This release path is a continuous discharge. Consequently, the release rate F'in Equation 10-6 is set equa! to maximum design capacity for the pumps on the effluent of the waste water treatmant facility.

10.2.3.3 Release Limits Release limits are determined from 10 CFR 20.

10.2.3.4 Release Mixture The release mixture used for setpoint determination is the worst case radionuclide mix chosen on the basis of station isotopic analysis data reviewed for 1978. j l

1 1

1 zior2. doc 10-8 l

l

.- __ - - - _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ ---__-__-._-a

ZION Revision 2 March 1998 10.2.3.5 Conyarsion Factors p

'f b) The conversion factor for ORT-PR25 (fire sump monitor) is based on detector response curves for 1-131. The conversion factors for monitor ORT-PR04 and ORT-PROS are based on detector response curves for Cs-137.

10.2.3.6 Liquid Dilution Flow Rates Dilution flow rates are computed based on the number of operating pumps in the flow path.

d F = F*, x N, (10-7) d =

F Dilution Flow Rate [gpm]

Fid = Dilution Flow Rate from pump i [gpm]

j N, = Number of pumps of type i operating j Pertinent flow data for the pumps is provided in Table 10-3.

10.2.4 Allocation of Effluents from Common Release Points Radioactive liquid effluents released from the lake discharge tank and turbine building fire sump are comprised of contributions from both units. Under normal operating conditions, it is difficult to apportion the radioactivity between the units. Consequently, allocation is based on the unit discharge canal used for dilution.

O Q 10.2.5 Projected Concentrations for Releases Projected concentrations are calculated before initiating liquid discharges. Per procedure, a representative sample is obtained and analyzed and the projected concentrations are calculated using conservative dilution flows prior to release. Because the fire sump is a continuous a,sase, it is sampled daily and isotopic analyses are performed weekly.

Doses due to liquid effluents are calculated as required by the RETS.

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

1 1

l zior2 doc O' 10-9

ZION Revision 2 ,

March 1998 {

Table 10-1 l

l Assumed Composition of the Zion Station )

Noble Gas Effluent isotone Egreent of Effluent Ar-41 1.92E-1 Kr-83m 1.0E-4 Kr-85m 2.24E-1 Kr-85 5.50E-2 Kr-87 1.22 Kr-88 3.19 Kr-89 1.0E-4 Xe-131m 1.85 Xe-133m 7.56E-1 Xe-133 8.36E1 Xe-135m 1.03E 1 Xe-135 8.79 Xe-137 1.0E-4 Xe-138 4.37E-3 Note: Based on station isotopic release data averaged over 7 years (1977 through June 1984).

zior2. doc 10-10 l

l

1 ZION Revision 2 March 1998 TABLE 10-2 HVAC EXHAUST FAN CAPACITIES 10 FAN CC/SEC CFM CFH

1 Aux. Blda 7

OA Exh. Fan 3.16 x 10 6.70 x 10' 4,020,000 l OB Exh. Fan 3.16 x 10' 6.70 x 10' 4,020,000 l

! OC Exh. Fan 3.16 x 10' 6.70 x 10' 4,020,000 l-

2 Aux. Blda.

OD Exh. Fan 3.16 x 10' 6.70 x 10' 4,020,000 1 7

! OE Exh. Fan 3.16 x 10 6.70 x 10' 4,020,000 l 7

l OF Exh. Fan 3.16 x 10 6.70 x 10' 4,020,000 l #1 Purae Exh.

7 1 A Purge Fan 1.46 x 10 3.10 x 10' 1,860,000 7

1B Purge Fan 1.46 x 10 3.10 x 10' 1,690,000

H2Purge Fan 1 A 1.70 x 10 5

3.60 x 10 2

21,600 i 5 2 H2 Purge Fan 1B 1.75 x 10 3.40 x 10 22.200 l

2 Purae Exh.

7 2A Purge Fan 1.65 x 10 3.50 x 10' 2,102,400 7

2B Purge Fan 1.72 x 10 3.65 x 10' 2,188,800 5 2 H2 Purge Fan 2A 1.82 x 10 3.85 x 10 23,100 5

H2Purge Fan 2B 1.75 x 10 3.71 x 10 2

22,260 8 3 i Hot Lab Exh 0A 1.50 x 10 3.18 x 10 191,000 '

8 Hot Lab Exh. OB 1.18 x 10 2.51 x 10' 150,600 Misc. Exh.

8 l Comp & Misc. Exh. 0A 2.81 x 10 5.95 x 10 357,000 j Comp & Misc. Exh OB 2.81 x 10 8 5.95 x 10 357,000 l

Ser. Bldo.

8 Decon. Rm. Exh. 1.91 x 10 4.04 x 10 2 242,580 Welding Rm. Exh. 1.09 x 10 8 2.30 x 10 138,000 5 8 l

Sandblast Rm. Exh. 9.44 x 10 2.00 x 10 120,000 Cave Exh. 6.14 x 10 5 1.30 x 10 78,000 Machine Shop Exh. 1,42 x 10 8 3.00 x 10 8

180,000 i

I O

l

, z10r2. doc l

10 11

ZlON Revision 2 !

kJlarch 199@ \

TABLE 10-3 LIQUID DILUTION FLOW PUMP CAPACITIES

)

PUMP NUMBER OF PUMPS DILUTION FLOW RUNNING CIRCULATING WATER 1 250,000 gpm CIRCULATING WATER 2 530,000 gpm CIRCULATING WATER 3 640,000 gpm SERVICE WATER 1 13,500 gpm SERVICE WATER 2 27,000 gpm SERVICE WATER 3 40,500 gpm O

l I

l i

l O

210r2 doc I 10-12 )

I O

Aux. Bkl9- ORT-AR03 cubicles (see Ppe tunnels Aux. Bldg. 3 .0 01 detail Sit 2) Misc. areas una t 8 vert M w area u 1 '" 9r s 1 o '

- When i stad

g P g @ P g . drurnrra g

" 4 4 ut g P g i g g l -

T

~

s $ 4 "T N A B V V To E To F Sht. 2 ,, Sit 2

@S E@ E@

i, g

i O

h 1 l

l n a e t . j 1 T PR25

- mlAPM n 4- HG 7 MG LG I P T-LG 1 P ]

8----- G----!- -

ir2, 10PR038 s i ,, C,,Q 3 4 a > n n i E o LG , -- M o E -

I LG lRE-0015 -

E E .

9 3 e M 4 l g e P IRT-PR26 $ i P 8 P O i l r-e i

SJAE & GS Gas Aux. Bldg. Au.t. Bldg. l From Unt1 e ensa dem anerW u mherW

s vents .l l

From unni tanks vents sa 2 D ) c >- - - containmers 0 1 M6830.021 0643 210r2. doc

\

l

' ~

Revision 2 March 1998 i

O 1 j

- Drumming Banery RM.

D

. econ RM Cold lab ttnson tonet, knetion urm2 i __,

i went I "

l na; ir 1r 1r o i l r 9 ,

l I

0.

l ANSTEC l " "

APERTURE l CARD E

2RIA-Preg

, n 2RT-PR25 _

l g t- P I LG MG 7 HG 4 Also Availabb OB

,5 i ,, __

s ,- Aperture Card

= __

'8 ,',l, 20PR038 __L____ ___a i

V f *

, LG --

l 2 LG 2RE-0015 1

% I -

5 4 _ i"~ 9%o50(soo 12-1 l s;As a Gs OFFSITE DOSE CALCULATION MANUAL E i cone n r Ej_ . , ZION STATION

, ont 2

( '__ga_a --- L i Froen ont 2 FIGURE 10-1 SIMPLIFIED GASEOUS RADWASTE AND GASEOUS EFFLUENT FLOW DIAGRAM (SHEET 1 OF 2) 10-13

1 I

Revision 2 UNIT 1 CoffrAINMENT(Typical) March 1998 hargoal M O ob Mai

-!;!-1-P_ __ g f-dn Pur eNo] ;

RCFC (1 of 5) ;;;

l Mini Pur e l 3,000 - D yht.1 IRT-AR04A & B usi Hydrogen Purge (Fuel and ng l IRE-AR02 & 3 (High Range)

=

i 4 hRecomeonerN

-PR@

P l l lLGlMG L.

G Unit 1 Cubicles t x RHR Gas RHR CHG yi.e BA RW PMP Deosy HX PMP EVAP EVAP P P From Unit 2

, , Cubicles v u ir e o o o u F A " U U U

=

, F B 1 RT-PR15 2RT-PR15 DETAIL OF AUX BLDG CUBIC 1,.ES U 44,200 LEGEND Normal or Frequent Alearne Radioactrvnv Flow Path Mantonng Channels

-- Occasional Flow Path p p Area or Duct Radiation Detector ]l lodine

' ] tow Penge Gas

6 HEPA Filter

Mid Range Gas

-h -

. Charcoal Filter HG High Range Gas Gran samones OFFSITE DOSE CALCULATION MANUAL ZION STATION Particulate g Isokinetic Probe O NOTE: Flow rates are design e G Gas l..

SIMPLIFIED GASEOUS RADWASTE AND values (not actual)in CFM. GASEOUS EFFLUENT FLOW DIAGRAM (SHEET 2 OF 2) usu. m s 3 210r2. doc

l

,.s -. !

l Twblaa Buildine Equipament Drase Annaysia Tank b

v' OAOV. a OAOV WD0003 04 hD0004 OAOV WD000s OAOV. n OAOV C WD0007

[) --

Analysia Tank OWDMI my/, F ' '

L% r r, 7 ' ~ d OAOV. CAOV Draia Tank Pommy OE ,WD0017 WD0025

. r t.

suure 17141 -

a Gal.

~~

D0078 g&&. -

=

Draia Tank Pussp OA h ' d-Drals Taak (

To rumadne OAOV WD0013 kNN(d Reactor Coolant d

8~ ;

Oat.

-- OAOV. Frera Drasa Tanks WD0009 Steam lary Buad Equipment Genera w Blowdown System O AOV.

Radweste Annez Bldg. Sump _

$ Sumps OAOV WD0015 High Radiation Systara' Sampling Weste Ammalary Buuding Nor Draan Analysis Tank OAOV AD0001 OAOV-OWD0019

_ d V

1,800 Gal "

F h

OAOV OAOV.

WD0021 WD0011 Leandry Drain Tank OA OAOV.

OAOV AD0002 WD0012 .

OAOV WD0020 -

OWDCl33 k I I.c D

14andry Drale Tank OB 4

OAOV.(

~

l From CVCS OW 0p3 W

nm~n%

m 210r2. doc O

EN MN

R5 vision 2 March 1998 To Blowdown System Mixed Bed D :-- " -

D0030

% To and From 00 Coalescer/ Separator A

L" J." rah.r raas4 f4Tl11$="

% OWD 30,000 OaL OA P 1 P 0108 Jk J k lake Discharge Tasha CASV- OAOV. OWD 3r WD0031WD0041 0148 JL

30,000 OB OM M d OWD1 P 0118 OFCV. OFCV.

i 0147 j g WD10 WD08 9 5058 OAOV-WD0040 From .

Tasks tar D

I e D arge ii Canal 1 Canal 3 JL OWD338 e3 k

OAOV WD0038 h(%

OWD0183 Demineraliser O_h

%7

+ Demerator CrW 1118 I 878"*"'

OAOV WD0039 I glSO b U O r To Primary OAO V- D0044 -

Cater Storsge Tanks OAOV WD0048 8,000 16 OaL 3A Portsbie WD0394 OAOV. Enporaw %eitor Tamb WD0398 aste OAOV WD0048 kv:porato' WD0047 OFFSME DOSE CALCULATION MANUAL ZION STATION M ' Tv*fid MO**,','"

.p and Disposal System

= ' -

FIGUAE 10-2 G

SIMPLIFIED LIQUID RADWASTE PROCESSING DIAGRAM 10-15

Revision 2 l March 1998 O l d onT=s r---"

I um paa , ,

-2 a

MPAAAToA R all a 4 To wic.

owm oncu ma m TANK y

waste WATER TMATMNT mm 60400 GPM i

numuc= !

t=o !

mouc= wars uma conceNesa coNosNesa emcutATwo -

wasus _ ctacuurna ,

Lesit waian U1871 if mAIta

, 'I U8a samnE ssNWK1 Nof12 ~ othCNME tm Nois: WATER 2 WATER TANK OttcMAIG WsTIM TANK sVWTIM G h n G I E i P ---

d1 i 1

I .

I I = ;'t

't r u cameuse g -

n a h

+ .'

- ."M,"u'",'

-~NNmhV tua M oeGAN

'I uTua wiu.

y

.ua.Le O uoisomouainion unem Mo==

OFFSITE DOSE CALCULATION MANUAL

- " ' '

ZION STATION

= "

CoNTRoLPATM Nof5AALLY clo3ED VALVI FIGURE 10-3 vis

' ' * * " * * " "" SIMPLIFIED LlOUlO EFFLUENT

.Mn etow . u ooo c'" ROW NEM

3. FLOW DETIRMINEo OY ' UMP cUnvt9 10-16

'15939 024 4 91

ZION Revision 2 March 1998 Figure 104 Q

V Simplified Solid Radwaste Processing Diagram I

l l

l Solidified i Portable Domin for Uquid b Radweste

~~

R-dwaste Mixed ,

.* "y" > N 'N Bed Domin Rosin Tank Uner

-+rVH--> Mobile

. Radwaste y Solidification System O

V ortsne Disposal l

LEGEND l OFFSITE DOSE CALCULATION MANUAL M Flexible Hose ZION STA110N FIGURE 10-4 l ztor: doc SIMPLIFIED SOLID RADWASTE PROCESSING DIAGRAM 9g7 1

lll ) ;:

uOz

{y yen m c

iseaZi 1

0- _

gy oEOia:$ l : ,

E

" ..g: 1 -

!::i.1.5 n:" " ? n lglnn1 j . .3 : :! l3i

. .I:

.g:

.,:3 I:

j.n.

j

. n !:-

.5:::

?

*Isl. ::1 0 -

j. :. . : . !:-

n 9:0.t p 3

l e..e.:::

i . .: .* 2 :: :

s (

.4 4:. :* :?

!:T:? : . 'b et.::1 3 t:.4:1 .

1

= . ..p . .>- - . T:? : "a4t>.4:i

=- .

. a . +..g: g.:.

i .

.c .e.t::2.+

.r.::- :...b:: 4 a. :?[. n.: "b eb.t. :i .

..... .": . . o

" . .. :.. .. : . :" : - :: . .....a." .

? ::: ". *u .ut$o ts 2 -

l. :I y:....t.

.. a.*"

.. ~ . i..

i..- " n...l::

i...

.". a..~ 0- -

555 888 8

..... . i.

i - " :... . "* :... n.. . -

r- r

- - E r i n .. .::n KKK

. gt

'~

.B 8:::*

Inn" n! ! : ."! i i : = l

! :. ltl ltt .88:l -

.. :..:..:- :- 4 :. :2:! :.ls3 4: I O.

%%% =.p . 4

( - '

' i

.... . r.' .: :: . 4::7:?nabp{. 4:I 1 03 0 531 =. 4 ;~ 4 : '

[

,a

, .;.t* .

, .. p. . .t:-

a.t .4 44.:T:?

7:? =*49 = . *0 g.b.::I 4 4. :

I -

=..p;d :..

. . a." b:: .* -

/ // 3 53333 :. .. a.g . .

n.* . a a .. .

. . o. .

*. 3) 83331

. o

n. g:t .:: :? * :I c:.n . ..e "

r 1 1 1

- - e

..o~.. .

~o :

-" n. .

. . .. l. :. ::" n ..n..

0o KeXXeeX X :.o~..

...... " n.. neuu..$. t t. . - c

% % i E/

0%%%0 00700

. g:t g:

.g:i

.g:t 3:

g: .

.8:

8 8'

.:: ?

?

. tt3.:

."lg

.*lg3

.8 n l 3:l

0. lC 1

5691 =.. q:s.4: j .:.. - g . ...

l

.; r.

4 42 .:

- .:?

= *( ..p4.c 3. : l

.*) g 4 :i 1 u

=

?

E - - - - - q t t.4::

Ls I (

=. q: t.4:: ig.v. .t..* 4:" = ..*

.*4. .. q6. 4. : I

. .?

S .

i.. .

.4..

N O

1 2345 ::...ct" 4 4: j.e .r.:-

. . .* b:. . :T"** :? =.**{.g _

..*.n.

. (.4.:. Y S

P

. o aa~u g

.: . . . t t.b:

i

. .*t. g4. .t. :i 4T 0I c.. .. ..

E !.- .-

" : .. n .

. . .u

..o a~o !.- .

. . - V R :... !.

R : .i:t

" l. n . .:.i:: : . ! :-

."iq.:*

.t r::t s :.

.. g gt.t:l .lnin

.i EI O

T A

..g:t

. .g :*l.

..g 4

=.c;t.4:*

3:

y .. : . t : : I ; .:?

. :?

.? - *<.

.*) 3.

3 s :l

0. C T I 59 g. ;..:.t:-

<:* j.:..:.t:: ..:. a.<. ?- 4. 4 : I 1A N 20A ::. 4 : *. :I O RRD PPI

=.. q ** 4 4:*

=

pt+.4: g.

i..

. ...: .t :: a

. ... 4 * ? .... o

+. =.4o

=.t . 4. 4 :I E M TTPR

=..p .a a o i.-

i

." :..... :. * .g:i 5C RR :. [

i:...r.::. .. .

0R

...tt.g:

....b.::." " f...

a o ..: " n. . . .

bCMN ) )

22 T-

..na".

i i.- .- " : . . . .

E- U

( ( R o l. .

l 1 O : ? .

,l ni l

. 3 :i g :'

hu..n :j .

. 8 8 n:" " ? ..

3:t.g:"

.:t g:

ln . . :-.:j." 8::::?

. :l

l 0.

1 S O

g. :..: . t: 2.c.8t:::? =-

. 3ei.3 :

=..+tt.::'

=q :* 4 4 : *

.' j.: .

.:.t:: : .4a:!:? =.. .

I

= .. c?t.<.:* g .;. . . . .:.t:: *. !:.

i.

i. . . - "

a. 4s:T:?

. . 4. a. : * :? :.

T =.a .

. :I

=..

oaa.b:* i

[. . r .r.t::

. p.b. :. :"T :e =...:

. :i 6

. . . *b.

gtt

. ..n ~ ~ u i.

i .~. " :....

n 0-

... u ~ ~ o i.

i. ~ - " :...a.".

n. . o

..g:i.g:

. . g : t .t :' l.n..n

l. .. .::-

t::

s:-

.8::::;

.8::::?

8::::? :. 8

. l n.a{gg ni E

l t

0

..gt.g: l:..:

l. :.

.:.t:- 83:::? : . *33 3 :l

= . q.st t1 +.4: 3: 5.:..::. :-e .t::2.+.44:T:?

. =.*494

I

I 1

.. l

3. : : i. . . . * :.... 4:.: :? a .*.434

=. q : 4 * .

I

" 2,.+.4.:.:*T :? =...a4 94 q t + . :. :

g.:.:.t:: .. .

g. e.~

. i.

.r.t::sp.e::T:?

. =.. . ...

= . .

p. " a . .

.*{q<. :i 7

...tt.<:* .- " .. . .

n.....

0-

=....-. .~.

~

. " . i.- - .- .- -

i l.

n...~."

= .... .. ~ . "

= .... .. -

E 6 3 2 10 0

0 0+ 0+ s

+ 1

+ O -

E E E E E .

0 O. . O. 0 0 1 1 1 1 I e o 3 t hg C>

r en, s 3, NDz gg to.P ep Hso e gm 7 R

3 69g., ZE() goz! awtOz(nm 5868 .

.- o1 m

l Zion Station A Chapter 12 Change Summary Revision 2, March 1998 m

Page Chance Description 12-il Updated revision number and file designator.

12-1 Added definition for CONTINUOUS SAMPLING FREQUENCY to identify allowances for sampling interruptions of short duration. Corrected capitalization.

12-7 Corrected section reference forindependent sampling requirement.

Corrected punctuation.

12-13,23,26 Corrected punctuations and capitalizations.

27,28,32 34,35,46 12-27,35 Changed wording to be consistent with that in NUREG-1301, 12-12,17,29 Changed " Vent" to " Ventilation" to avoid confusion with the Containment Vent.

12-29 Added footnote notation to Continuous Sampling Frequency for

-- O Continuous Releases, Ventilation Stack.

12-30 Added footnote (h) clarifying CONTINUOUS SAMPLING FREQUENCY exceptions, f

__ ___m

ZION Revision 2 March 1998 O

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

1 O

O h:412r2. doc 12-1

1 ZION Rsvision 2 March 1998 CHAPTER 12 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS i (RETS)

TABLE OF CONTENTS )

PAGE 12.1 DEFINITIONS 12-1 12.2 INSTRUMENTATION l 1. Radioactive Liquid Effluent Monitoring Instrumentation 12-5 l 2. Radioactive Gaseous Effluent Monitoring Instrumentation 12-9 12.3 LIQUID EFFLUENTS

1. Concentration 12-19

2. Dose 12-25 j

3. Liquid Radwaste. Treatment System 12-27 l

12.4 GASEOUS EFFLUENTS '

1. Dose Rate 12-28

2. Dose - Noble Gases 12-31

3. Dose - l-131,1133, Tritium, and Radioactive Materialin Particulate Form 12-33

4. Gaseous Radwaste Treatment System 12 35 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

1. Monitoring Program 12-36

2. Land Use Census 12-48

3. Interlaboratory Comparison Program 12-49 12.6 REPORTING REQUIREMENTS

1. Annual Radiological Environmental Operating Report 12-50

2. Annual Radioactive Effluent Release Report 12-51

3. Offsite Dose Calculation Manual (ODCM) 12-53

4. Mejor Changes to Liquid and Gaseous Radwaste Treatment Systems 12-54 h.\zi2r2. doc 12-iii

ZION Rsvision 2 hlarch 1998 l

CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RiETS) l UST OF TABLES PAGE 12.1-1 Surveillance Frequency Notations 12-4 12.2-1 Radioactive Liquia Effluent Monitoring instrumentation 12-6 12.2-2 Radioactive Liquid Effluent Monitoring instrumentation Surveillance 12-8 12.2-3 Radioactive Gaseous Effluent Monitoring instrumentation 12 10 12.2-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance 12-14 12.3-1 Allowable Concentration of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Effluents 12-21 12.3-2 Radioactive Liquid Effluent Sampling and Analysis Surveillance 12-22 12.4-1 R !oactive Gaseous Effluent Sampling and Analysis Program 12-29 12.5-1 Radiological Environmental Monitoring Program 12-39 12.5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 12-44 12.5-3 Detection Capabilities for Environmental Sample Analysis 12-45 3 9

h.\zi2r2. doc 12-iv

ZION Revision 2 March 1998 12.1 DEFINITIONS (O)

~

12.1.1 ACTION shall be that part of the sections which prescribes remedial measures required under designated conditions.

12.1.2 A BATCH RELEASE is the discharge of liquid wastes of a oiscrete volume. Prior to campling for analyses, each batch shall be isolated and then thoroughly mixed to assure representative sampling.

12.1.3 A CHANNEL CAllBRATION. shall be the adjustment, as necessary, of the channel such that it responds with the necessary range and accu e.cy to known values of input. The CHANNEL CAllBRATION shall encompass the entire channelincluding the sensors (where possible),

alarm interlock and/or trip functions and shall include the CHANNEL FUNCTIONAL TEST.

The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

12.1.4 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shallinclude, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent INSTRUMENT CHANNELS measuring the same parameter.

12.1.5 A CHANNEL FUNCTIONAL CHECK shall be:

a. Instruments-The injection of a simulated signal (s) into the channel as close to the primary sensor (s) as practicable to verify OPERABILITY, including all channel outputs, as appropriate.

/~N b. Logics-The application of input signals, or the operation of relays or switch

(_) contacts, in all the combinations required to produce the required decision outputs including the operation of all ACTUATION DEVICES. Where practicable, the test shallinclude the operation of the ACTUATED EQUIPMENT as well (i.e. pumps will be started, valves operated, etc.).

12.1.6 A COMPOSITE SAMPLE is one in which the quantity of liquid sample 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.

12.1.7 A CONTINUOUS RELEASE is the discharge of liquid or gaseous wastes of a nondiscrete volume (e.g. from a volume or system that has an input flow during the release).

12.1.8 A CONTINUOUS SAMPLING FREQUENCY is uninterrupted sampling with the exception of sampling interruptions of short duration for routine activities (e.g. filter replacements).

12.1.9 DOSE EQUIVALENT l-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, f-132, l 1-133,1-134, and 1-135 actually present. The Thyroid Dose Conversion factors used for this calculation shall be those listed in Table lll of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites" or Table E-7 of NRC Regulatory Guide 1.109 Rev.1, dated October,1977.

12.1.10 MEMBER OF THE PUBLIC means any individual except when that individualis receiving an occupational dose.

/'N ht12r2 doc 12-1

ZION Revision 2 March 1998 12.1.11 OCCUPATIONAL DOSE means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation and/or radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include dose frcm background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the public.

12.1.12 A system, subsystem, train, component or device shel' oe OPERABLE or have OPERABILITY when it is capable of performing its specified functiNis), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsyt tein, train, component, o,-device to perform its function (s) are also capable of performing their related support function (s).

12.1.13 OPERATING is defined as performing the intended function in tne intended manner.

12.1.14 The OPERATING CYCLE shall be the interval between the end of one major refueling outage

) and the end of the next subsequent major refueling outage per unit.

12.1.15 An OPERATIONAL MODE (i.e., Mode) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.1 of the Technical Specifications, when fuel assemblies are pre',ent in the reactor vessel.

12.1.16 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processirig and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10CFR Parts 20,61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

12.1.17 PURGE OR PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner, that replacement air or gas is required to purify the confinement.

12.1.18 RATED THERMAL POWER shall be a total steady state reactor core heat transfer rate to the ,

reactor coolant of 3250 MWt.

12.1.19 The REACTOR PRESSURE shall be in the pressure in the steam space of the pressurizer.

12.1.20 The SITE BOUNDARY shall be that line beyond which the land is not ownec leased or otherwise controlled by the licensee.

l 12.1.21 SOLIDIFICATION shall be the conversion of radioactive liquid, resin and sludge wastes from l liquid systems into a form that meets shipping and burial site requirements.

12.1.22 A SOURCE CHECK shall be the qualihtive assessment of channel response when the l channel sensor is exposed to a radioa'uve source.

t 12.1.23 The SURVEILLANCE FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 12.1-1.

12.1.24 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

O h \zi2r2. doc 12-2 l

l

\

l ZION Revision 2 l

March 1998 g- 12.1.25 UNRESTRICTED AREA means an area, access to which is neither limited nor controlled by i

i the licensee. j l

12.1.26 VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by i

passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing bdines er particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any affect on noble gas effluents.

12.1.27 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during venting. Vent, used in system names, does not imply a venting process.

12.1.28 WASTE GAS HOLDUP SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System oC-gases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radion.divity prior to release to the environment.

l O

'O l I

("%

b h '212r2 doc 12-3

ZION R: vision 2 March 1998 l l

l TABLE 12.1-1 l

SURVEILLANCE FREQUENCY NOTATIONS 1 NOTATION FREQUENCY

S (Shiftly) At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D (Daily) At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months W (Weekly) At least once per 7 days.

M (Monthly) At least once per 31 days Q (Quarterly) At least once per 92 days SA (Semiannually) At least once per 184 days R (Refueling Cycle) At least once per 18 months S/U (Startup) Prior to reactor startup P (Prior) Complete prior to start of release EFPM At least once per effective full power month N/A Not Applicable Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. These frequency notations do not apply to the Radiological Environmental Monitoring Program as described in Section 12.5.

l O

ht12r2. doc 12-4 l

ZION Revision 2 March 1998 p 12.2 INSTRUMENTATION b 12.2.1 Radioactive Liquid Effluent Monitoring Instrumentation Operability Reauirements 12.2.1.A The radioactive liquid effluent mcaitoring instrumentation channels shown in Table 12.2-1 shall be OPERABLE with their alarm! trip setpoints set to ensure that the limits of Section 12.3.1.A are met.

Acolicability: At all times.

Action

1. With a radioactive liquid effluent monitoring instrument channel trip setpoint less conservative than the value necessary to prevent violating the limits of Section 12.3.1.A, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

2. With one or more radioactive liquid effluent monitoring instrumentation channels inoperable, take the ACTION shown in Table 12.2-1.

Surveillance Reauirements 12.2.1.B.1 The setpoints shall be determined in accordance with procedures as described in the ODCM.

O 12.2.1.B.2 Each radioactive liquid effluent monitoring instrumentation channel shall be h demonstrated OPERABLE by performance of a CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRAT!ON and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 12.2-2.

Bases 12.2.1.C The radioactive liquid effluent instrumentation is ; rovided to monitor and control, as applicable, the release of radioactive materials in liquid effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of RETS.

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63 and 64 of Appendix A to 10CFR Part 50.

O h V12r2. doc 12-5

28 n 9 o 9 i1 s

ih E vc er L

B _

Ra AS _

M CE _

LD I

PO ll l AA l l l

A l

l A

l l

AA ll PM A

N O

I

_ T

_ A T

N E #

_ M N U O

_ R I T

T C 1 1 2 2 33

- S A

- I N

G NI R

O 1

- T I

_ 2 N 1 1 N 2 O NN SE 1

O M g E LL OO .

I Z L T MEB I I TT p

j B N UNA CC A E MNR AA T U N I

AE ee 1 1 11 L I HP ee F

F MCO SS E

D I

U Q

I L

E V

I T

C A

O I

D A

R ) p T

m

_ D u L

gs e

( S in a k

n r e

e r

k n

ide l a lp i

F a

- ve T T oR r e4S 5 m g n e 37 Pf o g0O 2 a g 66 s aRR r

gR S id l

arDD r n hPP e hWW T oo c - -

ldP- i u

sRR BR it B c N it it na iOO eO s

o e s s F F-iOO

- E on D n p n r

o D M

i Mm e i br m i

br i t

e U yr k o n k R e a . u C u o a . .

T t

iT v L1. 2 T1. s T M L1 2 S icic t u e N t . .

o t a

I Aa A B u A. A sm s o n

it R

ot n w r u o o h.

GA C l

F 2r 2

1 1

2 3

t h

ZION Revision 2 March 1998 TABLE Q2_1 1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION (Cont'd)

ACTION 1 With one of the LDT monitors inoperable, all LDT releases shall be made through the OPERABLE monitored pathway. If both monitors are inoperable, effluent releases from the tank may continue for up to 14 days, provided that prior to initiating the release:

1. At least two independent samples of the tank's contents are analyzed, in accordance with Section 12.3.1.B.1, and

2. At least two technically qualified members of the facility staff independently verify the release-rate calculations and discharge flow path valving; l

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 2 With the number of channels OPERABLE less the minimum number required, effluent releases via this pathway may continue, provided that at least once per shift grab samples are analyzed for gross radioactivity (beta / gamma or isotopic) at a lower limit of detection (LLD) as specified in Table 12.3-2.

ACTION 3 With the number of channels OPERABLE less than the minimum number required, i effluent releases via this pathway may continue, for up to 30 days provided the flow rate l 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 used

, to estimate flow.

l i

l l

O

28 n 9 o 9 i1 s

ih v c er Ra M e c

n o

" m t o s o a l

r l

e o

r t

a t

n e o d c a t

a m L

A h

t e -

b E L N d

n l l

C EO) a a N I 2 NT( s h s

A NCT A AA r u

L QQ

/ // K L ANS O N NN c c C I

E HUE o E V CFT y H R a C U h w L S t E .

N ) a p N 1

( N IO N is: A T O h) d H A .

t f le C T LTI T ol a N EA S nt e E NR E s s M NB A

/ *

T io n t a U Al l

RR R N RR L a s i le R HA A loi sy e r .

- T CC N it il f e S O ici od N T I

t aa b s a I

C mp dm o

G 2-N E N

U to ca ier r ea 2 I R CK F ue ah p

S g 2

1 O RC L yt f gE n 7 N E T UE A AA E ni iS y d L I

N OH PP M

/

N

//

NN N a( .

r uA B O SC N t t as dE u A A h ix L T M H t e wE o

T C te s . l f R N L a ans f o H E E r ot C U NK f

o t

sin nio t i sT n

L NC e o dp nt oA F

F AE HH

))

33

((

c n moe ecs iB t

a r E

CC PP D D DD a m dgm e.

id co _

D r onr sia .d o inc I

U o wl e i Q

f r laoa r m god e l l

e lu e ini r I

L p laf lo h iat ye a

E e h t f r f p _

seh e i

d r V u Tt vo lee p e s, I

T e l

c Sf a

csno vu f o C

A gs na) r p i n Eob Ty a ni ou t n i

eT lem l

l a n ls wte si O

I idled v L pu h s

Lae Af v d os isn no t

D oR( mS Nie t oc A rf k ae N aon R POn s a Sr i k

n a O Osl I

r s u s es lchc r nT eF T I

T Tcte a or t l lai h r oo it g A

Cca h sw o t it e4S inag0O 5

2 soi n e 37 sg66 R Noc i ict n Kn s

n o in ar R R g. R pd o a DD r r Und onen . d o l B Fiiri c Co e MmhPPdP yr sRRc -

B R l

miu oB it hWW n c - -

I L

A Lat t

i ninn lut t Ey a

s w

t e C e osFF C Eceaee Hd o iTDiOOeO v n sn MiOOD Nnmt u f

mm Cy l f

L Ln T

ic t

cie i

br ui obr t ee E Nn u iu uu Ant ct r tr r Ea d e

Aa t k a . . u . uu ak N Ha sr ss Nn u N

E smL1 s o 2T1 n

iT t

Ra L1 . 2 N

A CmInCiInn i

No lc M ot n o

w er Ay l in r u . o . H h la Hi a U GAA B. CA l

FA C T a )a )b )c )d Cd i

c R n T s c S )

e o N 1

)

2

)

3 o d.

b I

. . ( ( ( D 2r 1 2 3.

2 1

t h

ZION Revision 2 March 1998 12.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation Operability Recuirements 12.2.2.A The radioactive gaseous effluent monitoring instrumentation channels shown in Table 12.2-3 shall be OPERABLE with :neir alarm / trip setpoints set in accordance with the method prescribed in the ODCM to ensure that the limits of Section 12.4.1.A are met.

Aoolicability: At all times, except as indicated in Table 12.2-3.

Action

1. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Section, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.

2. With one or more radioactive gaseous effluent monitoring instrumentation channels inoperable, take ACTION as shown in Table 12.2-3.

Surveillance Reauirements 12.2.2.B.1 The setpoints shall be determined in accordance with procedures as described in the ODCM.

12.2.2.B.2 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of a CHANNEL CHECK, SOURCE CHECK,

~N CHANNEL CAllBRATION and CHANNEL FUNCTIONAL TEST at the frequencies (Q

shown in Table 12.2-4.

Bases 12.2.2.C The radioactive gaseous effluent instrumentation is provided to monitor, record and control, as applicable, the release of radioactive materials in gaseous effluents during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10CFR Part 20.

f% I t

J h \z12r2 doc

ZION Revision 2 March 1990 m

TABLE 12.2-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM ,

CHANNELS APPLICABLE

. INSTRUMENT OPERABLE ACTION MODES )

1. Gas Decay Tank A. Gas Activity Monitor

1. OR-PRio (Low gas-Channel 1) 1 5 All

2. OR PRio (Mid gas-Channel 3) l 1 5 All '

l B. Flow Rate Monitor I l 1. OF-WG03 1 9 All 1

2. Air Elector Off-Gas A. Gas Activity Monitor !

1. 1R 0015 Gas 1 6 1,2

2. 2R-0015 Gas 1 6 1,2 l

B. Particulate / lodine Monitor

1. 1R-PR26 1 6 1,2

2. 2R-PR26 1 6 1,2

3. Containment Purae or Vent A. Gas Activity Monitor

1. 1R-PR09A Gas 1 6', 7 2 All

2. 2R-PR09A Gas 1 6', 7 2 All

3. 1R PR40E (Channel 5) 1 6',7 2 All

4. 2R-PR40E (Channel 5) 1 O', 7 2 All B. todine Monitor

1. 1R-PR09B lodine 1 6', 7 2 All

2. 2R-PR093 lodine 1 6', 7 2 All

3. 1R-PR40C (Ch.1nnel 3) 1 6', 7 2 All

4. 2R-PR40C (Channel 3) 1 6', 7 2 All

' During VENTING 2

During PURGING h

(d h:\zi2r2 doc 12-10 i

I f

ZION Revision 2 March 1998 TABLE 12.2-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (Cont'd)

MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE ACTION MODES

3. Containment Purae or Vent C. Particulate Monitor

1. 1R-PR09C Particulate 1 6', 7 2 All

2. 2R-PR09C Particulate 1 6', 7 2 All

3. 1R-PR40A (Channel 1) 1 6', 7 2 All

4. 2R-PR40A (Channel 1) 1 6', 7 2 All

4. Auxiliary Buildina Ventilation 9.0A Miscellaneous Ventilation Stack A. Gas Activity Monitor

1. OR-0014 or 1 6 All

2. 1R-PR25 and 2R-PR25 1 6 All

3. 1R-PR49E (Channel 5) 1 13 All

4. 2R-PR49E (Channel 5) 1 13 All B. lodine Monitor

1. OR-PR12B 1 15 1,2,3, and 4 (either unit)

2. 1R-PR49C (Channel 3) 1 14 All

3. 2R-PR49C (Channel 3) 1 14 All l

C. Particulate Monitor

1. OR-PR12A 1 6 1,2,3, and 4 (either unit)

2. 1R-PR49A (Channel 1) 1 14 All

3. 2R-PR49A (Channel 1) 1 14 All D. Flow Rate Monitor

1. 1LP-084 1 9 All

2. 2LP-084 1 9 All

' During Venting 2

During Purging l

l l

l 1

O h:\212r2 doc 12-11

ZION Revision 2 March 1998 TABLE 12.2-3 O- RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (Cont'd) i MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE ACTION MODES

5. Steam Generator Atmospheric Relief and Safety Valves A. 1R-PR58 1 10 1,2,3,7 B. 2R-PR58 1 10 1,2.,3,7 C, 1R-PR59 1 10 1,2,3,7 D. 2R-PR59 1 10 1,2,3,7 E. 1R-PR60 1 10 1,2,3,7 F. 2R-PR60 1 10 1,2,3,7 G. 1R-PR61 1 10 1,2,3,7 H. 2R-PR61 1 10 1,2,3,7 6, Accident Monitorina A. Containment

1. 1R-PR40G (Channel 7) 1 10 1,2,3,4,7

2. 2R-PR40G (Channel 7) 1 10 1,2,3,4,7 O 3.

4.

1R-PR401 (Channel 9) 2R-PR401 (Channel 9) 1 1

10 10 1,2,3,4,7 1,2,3,4,7 B. Miscellaneous Ventilation Stack

1. 1R-PR49G (Channel 7) 1 10 1,2,3,4,7

2. 2R-PR49G (Channel 7) 1 10 1,2,3,4,7

3. 1R-PR491 (Channel 9) 1 10 1,2,3,4,7

4. 2R-PR491 (Channel 9) 1 10 1,2,3,4,7 C. Containment Fuel Handling Area Monitor

1, 1R-AR04A 1 11 6

2. ' 1 R-AR048 1 11 6

? 2R-AR04A 1 11 6

4. 1R AR04B 1 11 6

When purging during fuel handling operations O 4 hv12r2. doc 12-12

ZION Revision 2 March 1998 TABLE 12.2-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ' l (Cont'd) l TABLE NOTATIONS ACTION 5 - With the number of channels OPERABLE less than the minimum number required, the contents of the tank may be released to the environment provided that pnor to initiating the release:

1. At least two independent samples of the tank's content are analyzed, and {

2. At least two technically quahfied members of the facility staff independently venfy the release-rate f calculations and discharge flow path valving; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 6 - With the number of channels OPERABLE less than the minimum number required, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per shift and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 7 - With the number of channels OPERABLE less than the minimum number required, and no redundant monitor OPERABLE in this flow path, immediately suspend PURGING of radioactive effluents via this pathway.

ACTION 8 - With the number of channels OPERABLE less than the minimum number required, effluent releases via this pathway may continue for up tc,30 days, provided samples are continuously collected with auxiliary sampling equipment as required in Table 12.4-1.

ACTION 9 - With the number of OPERABLE channels less than the minimum number required, effluent releases via this pathway may continue provided the effluent flow rate is estimated at least once per shift while release is in progress.

ACTlON 10 - With the number of channels OPERABLE less than the minimum number required, restore the inoperable monitor to OPERABLE status within 30 days or establish an alternate means of monitonng the parameter.

ACTION 11 - With the number of OPERABLE channels less than the minimum number required, suspend vent and purge operations and close each vent and purge valve providing direct access from the containment atmosphere to the outside atmosphere or suspend the movement of nuclear fuel and reactor components in the vicinity of the reactor, refuehng cavity, and transfer canal (containment side).

ACTION 12 - With the number of OPERABLE channels less than the minimum number required, effluent releases via this pathway may continue provided the effluent flow is being accounted for in the total plant effluent.

ACTION 13 - With the number of OPERABLE channels less than the minimum number required, restore the channel to OPERABLE status within 30 days or conduct a station review to determine a plan of action to restore the channel to OPERABLE status. Effluent release via this pathway may continue provided grab samples are taken at least once per shift and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 14 - With the number of OPERABLE channels less than the minimum number required, restore the channel to OPERABLE status within 30 days or conduct a station review to determine a plan of action to restore the channel to OPERABLE status. Effluent release via this pathway may continue provided grab samples are continuously collected with auxiliary sampling equipment as required in Table 12.4-1.

ACTION 15- With the number of OPERABLE channels less than the minimum number required, Auxiliary Building Cubicle ventilation shall be routed through the Auxiliary Building ventilation charcoal adsorber unsts.

hTzi2r2. doc 12-13 l

28 n 9 o 9 i1 s

ih vc zr Ra M

L A

L N EO)

I 2 )

NT( 5 NCT (

AN S QQ Q QQ QQ HU E CF T E

C N

A L

L I

E V )

1 R (

U N S -

LO N ET I

O NA I

T NR A AB A T Hll RR /

RR RR N CA N E C M

U R

T S

N I

4- G 2 N I

E N 2 R CK O 1 O RC I

Z E T UE A 4 L I N OH PP /

N MM MM 1 _

B SC 2 -

O 1 M

T N

E U

L L F E F NK E

NC S

U AE HH PP P DD DD O CC E

S A

G E

V ))

I 1 3 T lel C e A n na n n

O I

a h h D CC A -

s s

- r R a o g ag it n

r wd r o ooi it LM r o ss t aa M n(( o inGG e o00 it 3 o n 66 n0 M1RR y

1 oG s a M155 1 id22 oRR k y00 n iPP t

- Me-W G- it 00 I

/eP P a v f - - -

T iRR t

COO t

aO F f O

ivRR t

t laRR y R c1 2 u 1 2 a A r o A c c s w t s i

tr e a . . lo c e

a a . .

D G1 2 F1. G1. 2 i

P12 s E c a r o

. . i . . d A

]Q

(

G B A A B 2r 2

1

\

z 1 2 h

28 n99 o

i1 s

ih vcr RaM L

A L N EO)

I 2 NT(

NC T QQQQ OQQQ QQQQ AN S HU E CF T E

C N

A L

L I

E )

V 1 R (

U N S L O I N ET O NA I

T NR RRRR RRRR RRRR A AB T HIL N CA E C M

U R

T S

IN 4- G 2 N ) E 2

I R d CK 5 N 1 O 't RC 1 O n UE I E L

T o I

OH MMMM MMMM MMMM 2 Z

B N C ( SC 1

A O T M T

N E

U L L F E F NK E NC DDDD DDDD DDDD S A E U HH O CC E

S A

G E

V TI C

A O

I

))

55

))

33

))

1 1 D l lee l l A lee nn lee R nn nn nn nn nn t

n aa aa aa hh hh hh e r CC CC CC V o (( (( r ((

r it o o nAAEE o9900 BBCC i t

CCAA 9900 n9900

_ T e M0044 r0044 o0044

_ N E

a r

u y RRRR PPPP toRRRR MRRRR nPPPP i

e PPPP it M P v ----

iRRRR o ---- - - - -

M1RRRR laRRRR t

U t n

t c1 21 2 21 2 u 1 21 2

_ R e A e c T m s in it S n a r a

N I

i t

a n

G1 234. d . 234.

l o 1 . .

P1. 234.

o . . .

C A B C 1

. z

\:

3 h

28 n9 o 9 i1 is h vc er Re M L A

N

' L EO)

I 2

(( NT(

NCT QQQQ QQQ QQQ QQ AN S HU E CF T E

C N

A L

L I

E V )

1 R (

U N S LO N ET I

O NA T

I NR RRRR A AB RRR RRR RR T Hll _

N CA _

E C _

M _

U _

R .

T -

S _

N I

4- G 2 N )

I E

N 2 R dt CK AA O

1 O 'n RC MMMM MMM MMM

// 6 I E T o UE NN 1 Z L N C I

OH 2 B ( SC 1 j A O T M T

N E

U _

L L F E -

F E NK NC S

U AE DDDD DDD DDD DD HH O CC E

S A

G E

V I

T C 5 ^

A 2 O R)) )) ))

I D d P55 33 1 1 A n k Tlee l lee l l l ee a c nn nn R n at Rnnnn nn nn o S it n r2 odhh aa aa hh aa r .hh a o o s nCC CC CC it aa((

l it i (( r (( r t

8 o n la e nG5EE o 299 2 CC iAAA t

t o

T i

99 n299 i V n t M1 4 R44 r 1 44 o1 44 n44 N o e y0PRR oRRR MRRR o88 E n V it 0 TPP i

t nPPP ePPP M00 - -

M id s v iRRRR o --- t

- - - ePP U l iu uoe t

cO1 12 M O1 RRR 2 laRRR u O1 2 t

a LL ,

R B A e c R 12 T y n s in i S a t

r w r

a . . . a o N

I i l

i a

x l

l e

c G1234. d . 23 l

o 1 P1. 23.

. l F12 c

j s o u i d.

A M A B C D 2r 2

1

4. k.

h

28

_ o 9 n9 l

_ i1 s L

- vc ih A

t. r L N Ra EO)2 )) ))

M I 4444

- NT( ((((

NCT OQOOQQQO QQQQ OQQQ QQQQ AN S HU E CF T E

C -

N A

L L

I E )

V 1 R (

U N S LO I N ET O NA I

T NR RRRRRRRR RRRR RRRR RRRR A AB T Hl l N CA E C M

U R

T S

N I

4- G 2 N ) E ))))

2 I

R d CK AAAA AAAA 3333

(((( 7 N 1 O 't RC MMMMMMMM

////

NNNN

////

NNNN MMMM 1 O E n UE -

T o 2 OH I

Z L N C I

1 B

A O

( SC T M T

N E

U L L F E F NK AAAA AAAA E NC //// ////

S A E DDDDDDDD NNNN NNNN DDDD U HH O CC E

S A

G E

VI T

C f A ie k O

I le ))

77)) t c))

a77))

D R 99 Sleel l l99 A c leel l l

R i nnee nnnee r

e nnnn onnnn h aann iaann t

p hhaa lahh aa s CChh i CChh t

a o ((CC(( n((CC (( e t

m a

GG1 0000 1 VEGG9999 1 1 rA8AB A4444 A s n 4444 s4444 g0000 r e o v i

r t

n RRRR uRRRR nRRRR t

a o ePPPP oPPPP e ---- iAAAA l

T r a l

it mRRRR d - - - -

N e V 8899001 1 55556666 n o

nRRRR a nRRRR E n RRRRRRRR in1 21 2 l 1 21 2 a1 1 22 e y M a l

e H M t PPPPPPPP t c

- U G fe - - - - - - - - t n n s le RRRRRRRR R

T m S a

a 1 21 21 21 2 d e o ..234 C1 . .

i . . .

M1 234.

u F1. 234.

S e dn ic

- N I

t S a 1 2345678 A c

A B. C W

5 6 i{ l( il

ZION Revision 2 !

March 1998 i.

7. Table 12.2-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE (Cont'd)

TABLE NOTATIONS (1) CHANNEL CAllBRATION shallinclude performance of a CHANNEL FUNCTIONAL TEST.

(2) The CHANNEL FUNCTIONA L TEST shall also demonstrate that any automatic isolation occurs; and that Control Room al .n annunciation occurs if any of the following conditions exist (if the capability is installed):

a) Instrument indicates measured levels above the alarm setpoint.

b) Circuit failure, c) Instrument indicates a downscale failure.

d) Instrument controls not set in " operate" mode.

(3) Daily when PURGING the containment during fuel handling operations.

(4) Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to commencing refueling operations.

(5) OPERABILITY test only.

(~)'\

l l

t i

l n

'N h:V12r2. doc j p,j g

ZION R:, vision 2 March 1998 12.3- LIQUID EFFLUENTS O 12.3.1 Concentration Operability Reauirements 12.3.1.A.1 The concentration cf radioactive material released from the site to UNRESTRICTED AREAS (see Zion 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 10CFR20.1001 20.2402, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentrations shall be limited to the values listed in Table 12.3-1.

12.3.1.A.2 During the release of radioactive liquid wastes, a minimum dilution water flow rate of 200,000 gpm is required.

Acolicability: At all times.

- l

1. With the concentration of radioactive materials released from the site to UNRESTRICTED AREAS exceeding the limits specified in Section 12.3.1.A, immediately decrease the release rate of radioactive materials and/or increase

)

the dilution flow rate to restore the concentration to within the above limits. I I

Surveillance Reauirements i 1

O 12.3.1.B.1 The radioactivity content of each batch of radioactive liquid waste shall be determined Q prior to release by sampling and analysis in accordance with Table 12.3-2. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of l

Section 12.3.1.A. j 12.3.1.B.2 Post-release analyses of samples composited from BATCH RELEASES shall be performed in accordance with Table 12.3-2. The results of the previous post-release analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Section 12.3.1.A. ,

12.3.1.B.3 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 12.3-2.

The results of the analysis shall be used with the calculational methods in the ODCM to assure that the concentratior" Jt the point of release are maintained within the limits of Section 12.3.1.A.

12.3.1.B.4 At least one circulating water pump shall be operational on the discharge path, b

O ht12r2. doc j g,j g

ZION Revision 2 March 1998 Bases 12.3.1.C This Section is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to UNRESTRICTED AREAS will be less than ten (10) times toe concentration levels specified in Appendix B, Table 2, Column 2 to 10CFR 20.1001-20.2402. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outsida the site will result in exposures within (1) the Section ll.A design objectives of Appendix 1,10 CFR 50. to a MEMBER OF THE PUBLIC, and (2) the limits of 10CFR20.1301.

O O

hM12r2. doc

i ZION Revision 2 l March 1998 l

t f- TABLE 12 3-1

( i ALLOWABLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID EFFLUENTS

{

4 i

)

NUCLIDE A(uCil.m0* 4 i

Kr-85m 2 X 10" l Kr-85 5 X 10" l Kr-87 4 X 10-5 Kr-88 9 X 10-5 Ar-41 7 X 10-5 Xe 131m 7 X 10" Xe-133m 5 X 10" Xe-133 6 X 10" Xe-135m 4 2 X 10 O

! Xe-135 2 X 10" l

l

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

i.

t O

ht12r2 doc jg,gj

ZION Revision 2 March 1998 TABLE 12.3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE MINIMUM LOWER LIMIT OF LIQUID RELEASE SAMPLING ANALYSIS TYPE OF TYPE DETECTION (LLD)

FREQUENCY FREQUENCY ACTIVITY ANALYSIS (pCl/ml)(a e)

A. Lake Discharge Prior to Each Release Prior to Each Principal Gamma SE-7 Tank (c) Release Emitters (e) 1-131 1E-6 P M Dissolved and 1E-5 One Batch /M(c) Entrained Gases (Gamma Emitters)

P M Tritium 1E-5 Each Batch (c) Composite (b)

Gross Alpha 1E 7 P Q Sr 89, Sr-90 SE-8 Each Batch (c) Composite (b)

Fe-55 1E-6 B. Turbine Building Continuous During W Principal Gamma SE-7

. Fire Sump (f) Release (d) Emitters (e)

() 1-131 1 E-6 Dissolved and 1 E-5 Entrained Gases (Gamma Emitters)

Contini.ot s (d) M Tritium 1E-5 Composite (b)

Gross Alpha 1E 7 Continuous (d) Q Sr-89, Sr-90 SE-8 Composite (b)

Fe-55 1E-6 C. Waste Neutralizing Prior to each Release Prior to each Principal Gamma SE 7 Tank Release Emitters (e) 1-131 1E-6 P M Tritium 1E-5 Each Batch (c) Composite (b)

Gross Alpha 1 E-7 O '

hM12r2 d 12-22

ZION Revision 2 March 1998 TABLE 12.3-2 i TABLE NOTATIONS RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE (Cont'd)

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

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

LLD = 4 66 s.,

A

E V + 2.22 a Y exp (-Aat)

Where:

LLD is the lower limit of detection as defined above in picocuries (pCi) per unit mass or volume, sois the square root of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

A is the number of gamma rays ernitted per disintegration for gamma ray radionuclide analysis (A = 1.0) for gross alpha, strontium, and tritium measurement.

E is the counting efficiency (as counts per gamma),

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

2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield when applicable (otherwise Y = 1.0)

A is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental sample).

The value of s oused in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theon.tically predicted variance. In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples.

Typical values of E, V, Y, and At shall be used in the calculation. The background count rate is calculated from the background counts that are determined to be within i one FWHM (Full Width at Half Maximum) eriergy band about the energy of the gamma ray peak used for the quantitative analysis for that radionuclide.

O h \z12r2 doc 12-23

ZION Revision 2 March 1998

, ~3 TABLE 12 3-2 f i V TABLE NOTATIONS RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE (Cont'd) 1 For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near their sensitivity limits when other nuclides are present in the sample in much greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentrations of such radionuclides using observed ratios with those radionuclides which are measurable.

b. A COMPOSITE SAMPLE is one in which the quantity of liquid sampled 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.

1) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

2) The weekly and monthly Proportional Composite samples are not required provided that (1) the analysis required for each of these composite samples has been run on each batch discharged, and (2) a monthly record of radionuclides discharged (isotope and ,

quantity) is maintained. I

(~~ c. A BATCH RELEASE is the discharge of liquid wastes of a discrete volume. Prior to sampling for Q} analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampung.

j

d. A CONTINUOUS RELEASE is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the continuous release.

e. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141,'

and Ce-144. This list does not mean that only these nuclides are to be detected and reported.

Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses shall be reported as "less than" the nuclide's LLD, and shall not be reported as being present at the LLD level for that nuclide. The "less than" values shall not be used in the required dose calculations.

f. If the fire sump composite sampler is inoperable, grab samples will be taken from the turbine building fire sump once per shift.

,m

( )

L/

hM12r2. doc j g,74

ZION Revision 2 March 1998

.g 12.3.2 Dose Operabilitv Reauirements 12.3.2.A The dose or dose commitment to a MEMBER OF THE PUBLIC above background from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS (see Zion Station ODCM Annex, Appendix F, Figure F-1) shall be limited:

1. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and

2. During any calendar year to less than or equal to 3 mrem to the' total body and to )

j less than or equal to 10' mrem to any organ.

l Acolicability: At all times.-

Action l

1. With the calculated dose from the release of radioactive materials in liquid i

effluents exceeding twice the limits specified in Section 12.3.2.A, limit the subsequent releases such that the dose or dose commitment to a MEMBER OF THE PUBLIC from all uranium fuel cycle sources is limited to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months. Demonstrate 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 40CFR Part 190 and 40CFR Part 141 Standard, otherwise obtain a variance

,O. from thn Commission to permit releases which exceed the 40CFR Part 141 or 190 Standard. The radiation exposure analysis shall use methods prescribed in the ODCM.

j Surveillance Reauirements 12.3.2.8 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodologies and parameters of the ODCM at least once per 31 days.

l l

1 O

Mz12r2. doc 12-25

ZION Revision 2 March 1998 Bases 12/3.2.C This Section is provided to implement the requirements of Sections ll.A. Ill.A and IV.A of Appendix I,10CFR Part 50. The limiting Condition of Operation implements the guides set forth in Section ll.A of Appendix 1. The ACTION 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 tne releases of radioactive materialin liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies, which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are excess of the requirements of 40CFR 141. The dose calculations in the ODCM implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix l 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 equations specified in the ODCM for calculating the dose due to the actual release rate of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109; Calculation of Annual Doses to Man from Routine Releases of Radioactive Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix 1, Revision 1, October 1977 and Regulatory Guides 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977. l This Section applies to the release of liquid effluents from each unit at the site. For shared radwaste treatment systems, the liquid effluents from the shared systems are proportioned among the units sharing the system.

O O

ht12r2 d 12-26

1 j ZION Revision 2 March 1998 f~

l t 12.3.3 Liquid Radwaste Treatment System Operability Reauirements 12.3.3.A The Liquid Radwaste Treatment System shall be OPERABLE

and appropriate portions of the system shall be used to reduce the radioactive materials in liquid effluents prior to discharge when the projected doses due to liquid effluent, from each unit, to UNRESTRICTED AREAS (see Zion Station ODCM Annex, Appendix F, Figure F-1) l would exceed 0.06 mrem to the total body or 0.20 to any organ in a 31-day period.

The liquid Radwaste Treatment System shall be considered OPERABLE, if liquid waste can be held up and/or discharged within applicable limits.

l Apolicability: At all times.

Action With the Liquid Radwaste Treatment System inoperable for more than 30 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, retum the system to OPERABLE status and place the appropriate portions of the system in use.

Surveillance Reauirements 12.3.3.8 Doses due to liquid releases from the site to UNRESTRICTED AREAS, shall be projected at least once per 31 days in accordance with the methodologies and l parameters of the ODCM when the Liquid Radwaste Treatment System is not being fully

'p utilized.

O Bases 12.3.3.C The OPERABILITY of the Liquid Radwaste Treatment System ensures that the 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 Section implements the ,

requirements of 10CFR Part 50.36a, General Design Criterion of Appendix A to 10CFR l Part 50 and the design objective given in Section ll.D of Appendix I to 10CFR Part 50.

The specified limits goveming the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a 2% fraction of the dose design objectives set forth in Section ll.A of Appendix 1,10CFR Part 50, for liquid effluents.

l l

O hM12r2. doc 12-27

ZION Revision 2 March 1998 12.4 GASEOUS EFFLUENTS 12.4.1 Dose Rate Operatino Reauirements 12.4.1.A The dose rate due to radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY (see Zion Station ODCM Annex, Appendix F, Figure F 1), shall be limited to the following:

1. For noble gases: Less than or equal to 500 mrem /yr to the whole body and less than or equal to 3000 mrem /yr to the skin, and

2. For !odine-131, lodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem /yr to any organ. l ADolicability: At all times.

Action With a release exceeding the above limits, immediately reduce the release rate to within the above limits.

Surveillance Reauirements 12.4.1.B.1 The dose rate due to radioactive materials in gaseous effluents shall be determined to be within the prescribed limits in accordance with the methods and procedures of the ODCM.

12.4.1.B.2 The dose rate due to radioactive materials, other than noble gases in gaseous effluents shall be determined to be within the prescribed limits in accordance with the methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 12.4-1.

Bases 12.4.1.C This Section is provided to ensure that the dose at or beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10CFR Part 20.1301. The specified release-rate limits restrict, at all times, the l

corresponding gamma and beta dose rates above background to an individual at or beyond the SITE BOUNDARY to 500 mrem / year to the total body or to less than or equal to 3000 mrem / year to the skin. These release-rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation [

pathway to less than or equal to 1500 mrem / year. For purposes of calculating dose resulting from airborne releases, the stack is considered a ground-level release.

l O.

h T12r2 doc I

$ 7,73 l

l l

l ZION Revision 2 March 1998 TABLE 12.4-1 i RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT OF MINIMUM TYPE OF DETECTION (LLD) l GASEOUS RELEASE SAMPLING ANALYSIS ACTIVITY (pCl/cc)(f)

! TYPE FREQUENCY FREQUENCY ANALYSIS l !

A. Gas Decay Tank Grab Sample Prior to Prior to Each Noble Gases Each Release Release l Principal Gamma 1 E-4 Emitters (d) I B. Containment Vent Prior to Each Prior to Each Noble Gases 1 E-4 and Purge Release (a) Releas Principal Gamma i Emitters (d)

Tritium 1 E-6 !

l C. Continuous Grab (b) Monthly Noble Gases 1 E-4 l

Releases l Principal Gamma Ventilation Stack for Emitters (d) both (2) units l

Tritium 1 E-6 l Continuous (b)(h) Weekly 1-131 1E 12 l

(Charcoal Sample) l l-133 1 E-10 (Charcoal Sample) l Continuous (b)(h) Weekly (c) Particulate 1 E-11 l

Principal Gamma l Emitters (e) l l

I l Composite Quarterly Sr-89 Particulate 1 E-11 l Sr-90 Particulate 1E 11 l Gross Alpha 1 E-11 ;

Continuous (g)(h) N.A. Noble Gases, 1 E-6 l

Noble Gas Monitor Ga ma L

O h,\zi2r2 doc 12-29

1 i

I ZION Revision 2 i March 1998 TABLE 12.4-1 TABLE NOTATIONS RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM (Cont'd)

a. Should a shutdown, startup or power change greater than 50% occur which could alter the

'rixture of radionuclides after sampling, another analysis shall be performed prior to release.

b. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period in Section 12.4.1.

c. The particulate filter (s) shall be saved for a quarterly composite analysis for Sr-89 and Sr-90.

d. For gaseous emissions, the principal 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 peaks which are measurable and identifiable by gamma-ray spectrometry, together w!!h the above nuclides, shall also be identified and reported when an actual analysis is performed on a sample. Nuchdes which are t'olow the LLD for the analyses shall not be reported as being at the LLD level for that nuclide.

e. f~or particulate emissions, the princioal gamma emitters for which the LLD specif cation applies exclusively are the following radir.r.uclides: Mn-54, Fe-59, Co-60, Zn-65, Co-58, Mo-99, Cs-134, Cs 137, Ce-141, and Ce-144 Otner peaks which are measurable and identifiable by gamma-ray spectrometry, together with the above nuclides, shall also be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being at the LLD level for that nuclide,

f. The LLD is defined in Notation a of Table 12.3-2.

g. Refer to Table 12.2-3 for required actions when the noble gas monitor is not in service.

h. Sampling interruptions of short duration for routine activities, e.g. filter replacement, do not '

constitute a deviation from the requirements for continuous sampling.

O h:\zi2r2. doc 12-30

ZION Revision 2 March 1998 i

l 12.4.2 Dose - Noble Gases Operability Reauirements 12.4.2.A The air dose due to noble gases released in gaseous effluents from each unit to areas at or beyond the SITE BOUNDARY (see Zion Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the following:

1. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation j and less than or equal to 10 mrad for beta radiation, and

2. During any calendar year: Less than or equa! to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

Acolicabilitv: At all times D

1. With the calculated air dose from gaseous effluents exceeding the i above limits, define the corrective action (s) to be taken to ensure that future releases are in compliance with Section 12.4.2.A.

2. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding twice the limits of Section 12.4.2.A:

a. Limit subsequent releases such that the dose or dose L

commitment to a MEMBER OF THE PUBLIC from all uranium fuel cycle sources is limited to less than or equal to 25 mrem to l\ the total body or any organ (except the thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months.

b. Prepare an analysis which demonstrates that radiation

{

exposures to all MEMBERS OF THE PUBLIC from all uranium i fuel cycle sources (including all effluents pathways and direct i radiation) are less than the 40 CFR Part 190 Standard.

Surveillance Reouirements 12.4.2.B Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodologies and parameters of the ODCM at least once every 31 days.

12-31 l-

ZION Revision 2 March 1990 Bases 12.4.2.C This Section implements the ree,irements of Sections 11.8, Ill.A and IV.A of Appendix 1, 10CFR Part 50. The Operability .iequirements implement the guides set forth in Section 11.8 of Appendix 1. The ACTION 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 radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculation procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated.

O l

l h V12r2 doc

1 1

i ZION Revision 2 March 1998 12.4.3 Dose - I-131, l-133, Tritium, and Radioactive Material in Particulate Form Operability Rec uirements 12.4.3.A The dose to a MEMBER OF THE PUBLIC from I-131,1133, tritium, and all radionuclides in particulate form with half-lives greater than 8 day in gaseous effluents released from each unit to areas at or beyond the SITE BOUNDARY (see Zion Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the following:

1. During any calendar quarter: Less than or equal to 7.5 mrem to any organ, and j l

2. Dunng any calendar year: Less than or equal to 15 mrem to any organ. j 1

Acolicability: At all times.

Action With the calculated dose from the release of lodine-131, lodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents exceeding twice the limits of Section 12.4.3.A:

1. Limit subsequent releases such that the dose or dose commitment to a MEMBER OF THE PUBLIC from all uranium fuel cycle sources 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.

2. Prepare an analysis which demonstrates that radiation exposures to all

( MEMBERS OF THE PUBLIC from all uranium fuel cycle sources j (including all effluent pathways and direct radiation) are less than the '

40CFR Part 190 Standard. Otherwise, request a variance from the Commission to permit release which exceeds the 40CFR Part 190 Standard. The radiation exposure analysis shall use the methods prescribed in the ODCM.

Surveillance Reauirements 12.4.3.8 Cumulative dose contribution for the current calendar quarter and current calendar year for 1-131,1-133, tritium. and all radionuclides in particulate form with half-lives greatar than 8 days shai! De determined in accordance with the methodologies and parameters in the ODCM at least once per 31 days.

l i

l t

/

(

hv12r2. doc j g.33

ZION Revision 2 Eiarch 1998 Bases 12.4.3.C This Section implements the requirements of Sections ll.C, Ill.A and IV.A of Appendix 1, 10CFR Part 50. The Operability Requirements are the guides set forth in Section ll.C of Appendix l. The ACTION 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 radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculation methods specified in the Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I is to 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 release-rate l

specifications for radioiodines, radioactive material in particulate form and radiciodines other than noble gases are dependent on the existing radionuclide pathways to man, at or beyond the SITE BOUNDARY. The pathways which are examined in the i development of these calculations are: 1)individualinhalation of airbome rad;onuclides,

2) disposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy Feas where milk animals and meat producing animals graze with consumption of the milk and meat by man.

O 6

9 h \r12r2. doc

l l

l ZION Revision 2

March 1998 l

l l 12.4.4 Gaseous Radwaste Treatment System

( Operability Reauirements I

( 12.4.4.A The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE

and appropriate portions of these systems shall be used to reduce radioactive materials in gaseous effluents when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at or beyond the SITE BOUNDARY (see Zion Station ODCM Annex, Appendix F, Figure F-1) would exceed: 1

1. 0.2 mrad to air from gamma radiation, or

2. 0.4 mrad to air from beta radiation, or

3. 0.3 mrem to any organ.

l -

The installed VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS I HOLDUP SYSTEM shall be considered OPERABLE by meetings Section 12.4.1, 12.4.2 and/or 12.4.3, as applicable.

Acolicability: At all times.

Action: With the Gaseous Radwaste Treatment System inoperable for more than 30 days or with radioactive gar n.s wasic being discharged without treatment and in excess of the above limits, retum the system to OPERABLE status and place the appropriate portions of the system in us6 I Surveillance Reauirements 12.4.4.8 Doses due to gaseous releases from each unit to areas at or beyond the SITE l h(~N BOUNDARY shall be projected at least once per 31 days in accordance with *l the methodologies and parameters in the ODCM when the Gaseous Radwaste Treatment Systems are not being fully utilized.

Bases 12.4.4.C The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment.

The requirement that the appropriate portions of this system be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This section implements the t quirement of 10CFR50.36a, General Design Criterion 60 of Appendix A to 10CFR50 and the design objective given in Section ll.D of Appendix I to 10CFR50. The specified limits goveming the use of appropriate portions of the Gaseous Radwaste Treatment System were specified as a 2% fraction of the dose design objectives set forth in Section ll.B and ll.C of Appendix 1,10CFR50, for gaseous effluents.

'h jv hM12r2 d*

12-35 l

ZION Revision 2 March 1998 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Monitoring Program Operability Reouirements

)

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

Apolicability: At all times.

Action

1. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 12.5-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting a program as required and the plans for preventing a recurrence.

Deviation.s are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of sampling equipment, if a person who participates in the program goes out of business or no longer can provide sample, or contractor omission which is corrected as soon as discovered. If the equipment malfunctions, corrective actions shall be completed as soon as practical, if a person / business supplying samples goes out of business, a replacement supplier shall be found as soon as possible. All deviations from the sampling schedule shall be described in the Annual Radiological Environmental Operating Report.

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

to a MEMBER OF THE PUBLIC is less than the calendar year limits of Section 12.3.2,12.4.2, or 12.4.3.

When more than one of the radionuclides in Table 12.5.2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) + concentration (2) + . > 1.0 _

reporting level (1) reporting level (2)

When radionuclides other than those in Table 12.5-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Section 12.3.2,12.4.2, or 12.4.3. ~ This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such a event, the condition shall be reported and desenbed in the Annual Radiological Environmental Operating Report.

The methodology and parameters used to estimate the potential dose to a MEMBER OF THE PUBLIC shall be indicated in the report.

O h \zi2r2 doc g7,3g I

l l

ZION Revision 2 March 1998 m

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

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

Surveillance Reauirements 12.5.1.B.1 The Radiological Environmental Monitoring samples shall be collected from the locations specified in the ODCM and analyzed pursuant to Table 12.5-1 and the detection capabilities required by Table 12.5-3.

Bases 12.5.1.C The Radiological Environmental Monitoring Program required by this section provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the static,n operation. This monitoring program implementsSection IV.B.2 of Appendix l to 10CFR50 and thereby supplements the radiological effluent monitoring program by verifying that that y measurable concentrations of radioactive materials and levels of radiPMon are not higher than expected on the basis of the effluent measurements and modeling of tho environmental exposure pathways. Guidance forthis monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring.

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

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLD). The LLDs required by Table 12.5-3 are considered optimum for routine environmental measurements in industrial laboratories.

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

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL 300 (revised annually), Currie, LA., " Limits for Qualitative Detection and Quantitative Determination-Application to Radiochemistry," Anal. Chem, 4Q, 586-93 (1968), and Gartwell, J.K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA 215 (June 1975).

l O

ht12r2. doc 12-37

ZION Revision 2 March 1990 Interpretations 12.5.1.D Table 12.5-1 requires "one sample of each community drinking water supply downstream of the plant within 10 kilometers." Drinking water supply is defined as water teken from river, d.es, or reservoirs (not well water) which is used for drinking. Since Lake Mi;higan has no designated downstream or upstream direction, two drinking water locations (one north /one south) within 10 kilometers shall be sampled as drinking water inde.ator locations, and two other locations (one north /one south) beyond 10 kilometers shall be sampled as control locations.

O O

ht12r2. doc g,g

28 n 9 o 9 i1 s ly ih vc ld c er e b eie F i ept Ra O f

r M a wtoi s Y e g s ood ple C n

- N n i nimf wa or i

.O E S UI QS EY tg rk( .

e es o

r l

omcae lomn f ao n sgly n s ee e

isdr o t

R AL i wlp lo F n lynen bm i

_ N a m a atratio D A C sas a n N

A e lylo is S a *eu a ag qco n e lA.

E at r eanWsys i t t d nn la P o ao u bhibe

_ Y i c 1 c c s c sysp l T id 3d a 1 n it r

a oeaem srl r r t l nl a t

- R 1 a PGf af s i i d

_ N n n O a M ni o I

,n A T ot c fi) gi o R C it al eynt G E rl ic pc l e ot n de

_ O LY L e al l

- R OC oeuloo c

- P C E N r lp qt r e es e G DU lp mr a f ut N

I R

NQ AE mser on ar ot a ds i sa

_ O T

GR NF su l

meceu I

N I ucrdv .i y oio t L u r (dt l O P n pl aye r ack e 1

- M M it ki uieo 5 A nhe o ti e qd w L S N A eai 2

1 T Cwwr rb

- O I

Z E N 9 3-L E 5 0 B M 2 OT A N W 2

( m 1 1

S k n O EN m 0 i

h R

I VO I I s:

n k 1 i t

V TT o 4 o w N AA it a in t

4s r n

o E TC c h no i

t L NO o i t

it a c

A E S

L l t

w h t

c e

_ C EE h s n iws lo I

L ig l

- G R P e o sn t o

r)

O P it a ne t i E M f

cs. or nm L o ld i e o RA o o r t

ie d af f O

l S a l l ci c6 _

I F F t ie mce lodn t

D o a8 OD r F A N t

a a e

os r r l i a m1 e o R

RA E m N f t sn F a n) f r t BS le er o i im 2 E

o r r

- e r pe it lp(6

_ ML f s t o

mi f

f t o d2 l o

UP e a c ad a da 6 r mm

_ NM lp i s n ic et o t

n ak s 0 A d d o S m I n ri u) In e r5 C e3

_ a oi h n S a. Fm b. T (2 c Oto Y -

A E -

WL _

HP -

_ TM d AA n _

PS a

ER es -

RO ine _

U I eda t

SD miu ol _

ON oiioc c PA bdt o r

X r iaa d.

o E ARP 1

2r 2

t u

_ b _

28 n 9 o 9 i1 is h vc er RaM F -

O Y

C E

N UIS QS D

L T

h c

9 EY a R AL e F

N n o

DA N e s

A o E d .y P al r Y me T mt a a r

Gq u

N M O I

A T R C G E O L L Y R OC P C E N G DU N

I NQ R AE

)

dT O GR eI NF ly uN I

L r nO P t e

inM A t

M r a

oL u CA S Q N (

T O

I 1- N 0 4-Z 5. a 2ME 8 F 2 t

O n N hh 9

)4 r 1 1 N S it it )

Dn a e EO EN ww De Li h p t R v LR VO r r eot a e Lh t T n Y Tt i i n a Eno ig BI V TT I I h) r sir e ,

sw e n e

d eeMd Bsi n o

A N AA it De ira i r, r v ch at EE it T E TC eLs et oD r

eo a sTo: t i

g lpdMh . s c L NO E L n(ds oregw ScN eU Sc e n n eoal sa e t

o A 0 0 lsdn l

IC S

EE it at eirll no 0sO 0l 1 aB 2aa io t

a b yr e c o bh ee wc lor L

G O

R P P

t smu gi s o f

( c iE g

(

ic;)

gi c

o t

ssio e t na e) t n

o L E M n oeasas goT g om l Dn mnD c RA nl I

inl e Loe i L e O S irdmd o ioS r Rro2 m i r Tt ae o mtuT I

F i t e Roe r o6 o o m hechlowCr t

D nr c s r ei e OD n ce folp r eh e e o o

- A R RA N o mst eneen y, a et t n ef Inmo; )

t u et Om0 t br i

A t

fo tsea ov e r

br i

A E 3 B E niml r h em ai r h( 3 hc b.

erAI c e erChaS Ls0 h s o cr c c .

ML UP i

t uur m uu o t aa5 t o a aem a1 n n d Be0 t

lo a c.

NM ol r osu t ael ic n a1 c k r

e ed t n laie l t

c Ue3 y( t r e1 ymiinn di e o r in di0 h a a a aiPo bir n o

t at r A t t e . ctsEp l

e a S o he en t r r

t Ine n Ine1 O ee C p no .n e1 .no n a. h peHm n aOg0 bot O1 Oin

_ Ft Oc c TsRTe d Y

A WE HP *n L

TM it o AA a P S id

_ ER a R R UO t

_ SD e

/

c

_ ON r i c o

P X

E A D 2

2 t

T d

2r z

9 h

28 n

io 9

9 1

s ih vc er RaM F e; e; m O cit u .

- Y is po op is ci t po op it it ri t s e

C t y t y ' ;o y p isoml oml r N

E S oer ct s

ioe "s lkem V UI QS a

mlyau r a mlyau ct r is ly e oc w

EYL mh q mth q a y t

a n on n sl r

. R A go a n n go o a ise F c lytr DA N dmn s dm s ip . a a N ns i an nsioy oy n aq u A a oy . t l a) l a) a e. s l ol a an E

P te "s ant e be as o i

tbe e "s nt as o a n n i

iu t e o bs Y s smp s smp ma i y y s s T sl y oaim r

nior t u oaim sl r

u mim a

sl oa r n c Gs e t

nior Gat c Gat Ga N

M O I

A T R C

_ G E O L Y L

R OC s

s. s P C E N e e e

- lp lp lp G DU N m m m NQ I a a a R AE s s ly s

)

d T O GR b a

b a

l a

b a

e I NF r g

r g u r

_ u N I L n g n O P ly ly n ly i

k k a k t

n M M e e e o L A e e im e C S e N (

A T

W W S W O

I 1

- N j

- Z 5 E 4, 2 M )

g f p o

in e j

1 N "S )

E O EN kh i b L B

R I

VO I I nt iyi r

dbm

)

2 m

A V TT .

6 T N AA yd2 e

e g (

. E TC it ntc(6 a r

m L NO u e k

- A E S

L mf f m h c 0 .

- C I EE L mak oe0 .

is d

1

- G R P cb1 e f i n -

O P o h L

O I

D EM RA F

S hding r cl a uht ha e cwcsoi m

a e

r it lp e

w --

A OD N mta ei g d t

s R o p m RA E

rh rf f t ao u a s

B S e yh e E r p lpcm le r e l

g ML o m udr pi e sa l o p o n o eg r a

t UP a c as t r

m t

a h

_ NM i d Sr on t

ns on a s ic t s a a

r t e s c A d n eteiw e hc naa o C e lnD

- S t n i I

n I l t i s I

a. Owtsd a. O a. Ad ab

_ Y s A E e

- WL lp HP m TM S a -

AA ._

PS r e

E R R e)5 t a _

U O m (g )

/ o n (e

t n W S D br k i lol r p e g O N e nr t nm im in P

X A a D t

i oa d lo h CS e o 2r E W a .

S C 2

3. b c

. . t z

d \.

h

28 n 9 o 9 1

is ih sra vc is tu l) e eJ F ys i h

R laat p r lb c M O npaA d i

a Y a nly h e e C

oh t g n n o o N

E S UI QS 3

1 1 en 1- ls ),

d a r

a mh u

o or r e t

r

s isy s

is y

la O

EYL nmeb aib la n a

R n m n F A oe a Wc N Wc at n cv c DA ipeOo i p ip N oh h N o o A t o wg u (s t o

t o

E is* o e i .

s is P alyrh m as a . e Y mke ti t mno mlp T meyr a he mt i m

a or a m awMt Gb(

i o Gp Gsa N r O e M T I

n ,b A C o )r m R E eee r b v G L aoo L Y t

O scN R OC la P C E N mhO e (s ingm .

G DU a ui ot ly N NQ nr r la u

I R AE h eht eh

). n

) O GR w ytoi a

l r

n a

dT N F

Mt p s

eI I L y( aA e y uN P lk elyh m l inO l

e rh g i a

M t u

t n M A etutnor iws u

o o n n

oL S Bpmh a w CA t T A N (

T O 7 I

1 N S f .

4 Z o a y 5.

2ME E e b ") p L m. r n r j 1 N P ue a d o O

l l

o d e d e a o t EO M imcn r t )

ng n n c p )

it a a c

LR A3 xa at ni om ara a e icri nom t e d i

BI V S "S ms c lyh lyu ij r a2 g

in a 6 c l e

pm6 i

AN f

T EN a )d 8 las lan e S v o VO i

E i t a1 icd ic r t i h o( U r

o t

I I L TT mm o so r

en e on t wm e (

r iam A AA f r 2 la3 t

mis m s t mf k lp le l

k C TC s6( m9 me me oo0 r m b a

im0 s3 oic oic f h 1 a NO I

G la in( c e c e scn s t e so O

E S

L mk m am f p f p eai le g et i

os os lp eth e lp5 L EE L n 0 a1 gk n

i0 st st ena miwn i

b a v m1n O RP gn len a t f s n)

I P lk3 pt a lpt e a ai imto e wd D ini r g le sh A EM h mo r mo oan e ei t

RA k ti l

iw m5 ap ap vrl v d vw R

F S m s o 1

sm ei sm.

eie g it gr a s e t

o a

o ia n t

).

mn fr in t nyv o r t n wi OD erom ivy ivyr r b N r oio eth r t

aa l

l t l

l a r ewa (o sehts e e RA E t o f r t a l o lpw i

t o t n n l

o aah tn n c o n o

n o lo s g6 e 8 a sc m n a o eios t

a r r B c eo t r

a o idc ei st t r i c pa t n epr a t t t r pes1 M d i

lple n o si e r ae n o

stad e

r et d i

r s

a s

a n o

el r pt o t d U n me C ea n pr e ce C pr n n od a le e C om3 N

I a

. a r St h b nco Ol I

a Rr b e ca Rr pel I

a

. wo u Tf qo t

A l

t A b

. wa Ts( 9 Y

A E

WL HP TM AA PS s E

R R t

c U O u

d

/ n o SD o Wlk P r

ON it s h c o

P X A is O

e i d

g M F o d.

E n .

o 2r I

a b F 2

1 4 c t h

2 98 l n

n9 la i de eb a

h b o1 s is n c s r o

st iad s y is ih , y oi t

n cl t

is a vcr t n

l

~

a t r p e f, niu x oo o nod at n o i

e a e ic v lu e m

]R M n i

ht t o iaih g caetnos ehd s t

n c f y

di s f

it f ohc a e t lp n pN r i e o n p pne i d a a h e lps fat n a t u lp oT a n m t n i i a d s m ei r t erah r om o is n , r a h an c d d a ag t

e d oge .s de t e

k s

n eie a s;calpm u wpa a r l st a l er r s b w _

nrB opt s r.

tnto f o e t a u c eon e g im _

wp u l bl o et l

n l a

i"e t

p ,n ece b y 0ibs y i

i3m r

c3 mr e

loma ir t

t a4 ads t

t l k

in P, s1 s rDi las a meiuch imof i d

r M

e0s u ol o e E s n lyTl ci y d - se s .l he c t r b R Gs aio et gt n n y u a cp it n e laE n A mec o a o n cis u oRl t i

lp c m uihoih m ht iUa so mf o intapweh n dNi cg ur m it t oP a n a tndr i ast i s a h oagef r o e r doo ivn c .

e at l eo r e e

t s crt eote so o t

a e n dreio ri t m e ecgmic n p id i a

nf d pt f d t e ic l c t M aea sRR h ia i d t

ay el r i

l c ar ri d t ossi t oi r f

I it r u n

n o

A a r a u e gde a o c _

wR t

o mye p .

R i

.o n sgnf t id d _

n u st t ne io oni dido a c "m o a ie G ed r a u r r r t _

O oxn eh r e d g oea e e r f R t nwea t t io sf s

oh t s

a r

ian s cbh c t r

s in is h

ic e

p P e n8, no n r s ue g

n de amc r

ue p lc t s

G N

hA7 f

t n1 9 o ci n t om hi t i

t t omdnh cr eoce e t u

d e

f r

o r o

oiro n d s t I ie 4 im n r c c R t na e t

ec r

2 0 1 e rf uh dsdt p o a e i f a r

) O t b r s y a nr egu n i c t ioSo ai d n e n dT p t s e t

iav m ater n "m . o w p o eI geeid c _

uNS idMc it ih inmb n ad s c C O s ydu pe uh t ctr m ee e e l inON m D "s, st ae a g

ri u o aer e t r

s m h r l

i n MO t f t et r a ot r a oLT I

heOt n e o r ia d e f

o s

admyd nwfr o r o e r

t o

CAA t ea lp ar r g n essbl l oe s, u h

]N (

TT f hl ot P mn a o mane rdie o ri w dp n o

d e

g u

NO "

i ai o g'\b d s g 1

ef or e

t e is t

a o et h f e it c o 5.E N n st a bs ic f,usr s ei at mn ob a o n _

i w e t c r e _

2M 1 NL E l r - o e1 1

dt s l sl sp f

it r

eegt sa et d it yl l a lo p

e P ie e n g om g l

t b b n a yf ih _

EOB n1 e r f h r a mt ri wsla bs r o n r LRA BIV T ce a l e

rt a

em ga r s u

q a oorDm a

icg n t

a i

t n l a

h nieLi e t

ebl oe s .

c u 3 nor d lpl i A

T N h Tu a c f tae n cl l n a oo r nvTn p p i

d o c

lp 4-am t

E dl a n mn N ef h meo im m 2 l

eup ea i

L o ir ivs t zcm n io s nbf tht d d

n a s

1 r nf o t

A c n yi t r a io ds eiaoyui h s e a C

f nis o ee pu laas ta e zgt ow t r ne t

a n f

o n npl I

G oaci o t

sf l

a a ic irdiamdn ao oa t n

g o t h

ef nw i

O it r e ir u f i u ad s ei t a ig cot a ee bead t

n sba r r rt oe is r L el ir eifc hm inv i

e s emtccom tosa i c t

d e a e O

d pic9 l .

t o

l la yd i

d i

rl pF riee r ta fa e p

e /

e w

D nb ht n e i si s o er s A dme7 n a p9 er i sviei h a .deyn sf r u ps h

t s

m R a sS1 hi a st t ssf i r in k la u e yl r w n r ch eat s are omlae e ,

e e ic lo cr a e di t n n ht r ons t

ingr d e t y v necb en l

i a o f

a e c ee sao r a n

u w la a avimn zi lyg e ed t

umb n o d ,f foh o o n f t

s eh e a

i r lp be m ssou i m )o y mu

,s c f w a o idcv n o s D.dsi t t o a t i

d neo a s mssm r is t n dnZc nm n y s o aTN r

f t

ao o ly ege 1

e r

e t is ht e r gi sr f gr a nh e. eupi t

5. h e v s n s c n1, an te f e n miTiqo r a e n o ea e ( 2t c r t a

te el fuoi n p e sv ea i

a I lu y.be a

c . t ua . er ina r r sgr k f 1 f n

o ls a t o e l l

a moEi rf s lph c ia ipo n i

n e blaet t

e hb o s ie m. s r

m s

h s

af v ms l oi n e tr cl a eimaTo t l pdeha r

l e a a t

oa t

ci ind a

p ecR da sd s is s t

r o ont

,u o .o em S 2 a eu f

e r

is l

y lp e

di r mtntetn ed st gn a cig vo n, de e es a e ly n m i

f ol o l

m nt i mh r o6 ini t k a a icr ioi ie r rh s o gly t oiouec nt l cec t r n k n o e s epds it f i f mm eio t a a e ei l

e 1 e

p= ao r n ao bua ir an a or n dsjsl dbdi e t f ht ei imsc i w 3 1 n St RP Fc Ad a Gf Oaaads Rw If di B 1 O

)

7N ' )

1

(

)

2

(

)

3

(

)

4

(

)

5

(

)

6

(

)

7

(

)

8

(

)

9

(

)

0 1

(

h 2r 2

t

\

z h

28 n 9 o 9 i1 s

i h ~ .

v c er d

e R: s u

OM b e

y a

m I

/

i C p 0

S 0 T 0, C 0 3

U D )

f o

O t e e S P R w 0 0 l

u a

E g 0 0 0 v L D k/ 0 0, 0, a P 1 M O O iC p 1 2 s, A F (

t s

S i x

L e A y a

T N w E ht M K ) 0 0 0 p

a -

l

/ 3 0 N L i 6 7 3 r M pC I

O t e

R I

( a V w N g E i n

k N

I i n .

r 1 2-S dd. e N o us 5 5

2 I T

O )

t e f I

n e

2 1 -

d 1

A w 0 0

0 0

0 0 0 0 0 .b le E R 0 0 0 ey b nZo 0 H g 0, 0, 0, 0, 0, 0 a v L T S 0, 0, lua B N I k

/ 0 0 0 0 0 1 2 am T i

3 1 3 2 A E F Cp 1 vl /

f o

T C 1i s

N

( 4C 1 p t

n O tr 0 e 4 C a2 m 4-Pf o e 2 Y i r

1 T Re u I

Fu q V e I

T Cl a r C E 0 v e T 4 a h A A s t _

O L is, d -

I U st n D ) is o A IC3m hix y R Te e T i /

.y b R R A p C s a s e

O P ( 9 lew ph s F 0 0 0 ly S E S 1 2 mt a a L N E S ap s r n -

a E R A r e r V

E O B G t et a o L R R aw w g f

s G

I A O gn le v

N ni ik e I

T W k n l

_ ni r g R

O R )

0 0

0, 0

0 0 0

0 0 0 0

0 0

2 0 0 0 0

ird d o i t

n P E l/ 0, 4 0, 3 3 4 3 5 2 r n r o

E T i 0 1 1 o p R A C (p 2 FI f e

r W s i

n _

t a _

n .

o _

c

'C S I

S Y 4 5

9 4 7 0

4 1

le b

a d m

L 5- 9 8 0 5 b 3 3 a t is 2r A 3-5 5 6 N 1

3 , 1 1 L- 2 N n e o o n r- 1 s s

a h i A H M )) T z F C C Z Z 1 C C B 1 2

((

o t

28 n99 o

i1 s

ih v c er Ra M

T )y Nrd E ,

0 0 Mgk 5 8 I

1 1 Di/

E S (p C -

St ) .

Te .

Cw U ,

g DDk / 0 6

0 6

0 8

OOi .

8 OR F P (p C .

"SI S

N Y

L A

)

A Kl l)

5 E Li MpC I /

L 5 5 8 5 1 1 1 P ( 0 M "

A S ")

D L L A L

( )

T t N N e E O w 3- M I T H g, 0 0 0 0 0 0 0 0 5 N C Sk I / 0 3 6 3 6 0 0 0 2

1 O E Fi C 0 1 2 1 2 1 1 1 --

R 1

A T p E I V E (

m L N D .

Z B E F A O ) .

T R O T I

'm/

F M i

5 S I EC Tp 4-L E

I R EA( 1 2

T E NLS 0 1

I L

W R UE 0 7 1 1 B

I O OICS A 0 0 0 A BT 0 0 P

L RR G 0 A

C AIPO AR _

N O

I T

C E

T E

D R '

El )l "0 )

Ti AC 4 0

0, 5 0 5 0 5 "5 5 8 5 W (p 2 1 3 1 3 1 1

/ 1 1 1 1

S I

t a 0 S e 0 4 6, 5 ) -

Y B 4 9- 6 4 7 1

L s 5- 9 8 5 b

(

3 3 a A s 3- 5-5 6-N-

1 3 1 1

L-N o n o n - s a A

r H M e C Z r 1

- s C B G F Z l C

O e 2r 2

1 t

h

ZION Revision 2 March 1998 TABLE 12.5-3 (Continued)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS (1) This table contains lower limits of detection for analyses beyond the requirements of Table 12.5-1. This table does not imply that only these nuclides are to be detected and reported; other peaks which are measurable and identifiable in the analyses required by Table 12.5-1 shall be reported in the Annual Radiological Environmental Operating Report.

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

(3) The Lower Limit of Detection (LLD) is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5%

probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation, the LLD is defined as follows:

4.66 So + 3/to LLD =

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

4.66 So LLD ~

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

Where: 4.66 So >> 3/to LLD = the "a priori" Lower Limit of Detection (picocuries per unit mass or volume),

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

4 Total Counts

=

tb E = the counting efficiency (counts per disintegration),

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

2.22 = the number of disintegrations per minute per picocurie, l Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (sec"),

to = counting time of the background or blank (minutes), and ht12r2 doc 12-46

ZION Revision 2 March 1998 l

i TABLE 12.5-3 (Continued)

.A DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS l

l At = the elapsed time between sample collection, or end of the sample collection l

period, and the time of counting (sec).

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

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

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally, background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

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

(5) A value of 0.5 pCi/l shall be used when the animals are on pasture (May through October) and a value of 5 pCl/l shall be used at all other times (November through April).

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

(7) This is the minimum required LLD, however, environmental samples analyzed off-site will be required to use 200 pCi/l.

m U

hv12r2. doc 12 47

ZION Revision 2 Ma:t.h 1998

e. Total body doses to the maximally exposed individual in unrestricted areas from direct radiation from the facility should be included in the report. Associated (Q) population dose is not required to be included.

f. Total body doses to the population and average doses to individuals in the population from all receiving-water-related pathways are not required to be included.'

g. Total body doses to the population and average doses to individuals in the population from gaseous effluents to a distance of 50 miles from the site and beyond will not be included.

"A sin 0le submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the '

submittal shall specify the releases of radioactive material from each unit.

i l

l l

l i

1

^N

[O l 4

h:\zi2r2. doc 12-52 I I

l

ZION Revision 2 March 1998 l

12.6.3 Offsite Dose Calculation Manual (ODCM) l 12.6.3.1 Changes to the ODCM:

l

a. Shall be documented and records of reviews performed shall be retained as l required by Specification 6.5.2 (ITS 5.5.1). This documentation shall contain:

1. Sufficient Information to support the change together with the appropriate analyses or evaluations justifying the change (s); and

2. 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 effluent, dose, or setpoint calculations.

3. Documentation of the fact that the change has been reviewed and found acceptable by the Onsite Review Function.

b. Shall become effective after review and acceptance by the Onsite Review and Investigative Function and the approval of the Plant Manager on the date specified by the Onsite Review and Investigative Function.

I c. Shall be submitted to the Commission in the form of a complete, legible copy of the l entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release l Report for the period of the report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the j date (e.g., month / year) the change was implemented.

i l

l 1

l O

ht12r2.d 12-53

l ZION Revision 2 March 1998 12.6 REPORTING REQUIREMENTS l I

(m.

12.6.1 Annual Radiolooical Environmental Operatino Report

Routine Annual Radiological Environmental Operating Report covering the operation of the Unit (s) during the previous calendar year shall be submitted according to Technical Specification 6.6.1.D (ITS 5.6.3). The Annual Radiological Environmental Operating l Report shallinclude summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including, as found appropriate, a comparison of preoperational studies with operat;onal controls or with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

l The Annual Radiological Environmental Operating Report shallinclude the results of all l radiological environmental samples and of all environmental radiation measurements '

taken during the period pursuant to the locations specified in the tables and figures in the Chapter 11 of the ODCM Station Annexes, as well as summarized and tabulated results ,

of these analyses and measurements in the format of the table in the Radiological l Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data j shall be submitted as soon as possible in a supplementary report. '

The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; legible maps covering all sampling locations keyed to a table giving distances and directions from the midpoint between the two units; reasons for not conducting the Radiological Environmental Monitoring Program as required by Section 12.5.1, and discussion for all deviations from the sampling schedule (av) of Table 11.1-1; a Table of Missed Samples and a Table of Sample Anomalies for all deviations from the sampling schedule of Table 11.1-1; discussion of environmental l

sample measurements that exceed the reporting levels of Table 12.5-2 but are not the '

result of plant effluents; discuscion of all analyses in which the LLD required by Table 12.5-3 was not achievable; res Its of the Land Use Census required by Section 12.5.2; and the results of licensee participation in an interlaboratory comparison program and the corrective actions being taken if the specified program is not being performed as required by Section 12.5.3.

The Annual Radiological Environmental Operating Report shall also include an annual summary of hourly meteorological data collected over the applicable year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Annual Radiological Environmental Operating Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

I A single submittal may be made for a multiple unit station.

/3 i

V) hat 12r2. doc 12-50

ZION Revision 2 March 1998 The Annual Radiological Environmental Operating Report shall also include an assessment O

of the radiation doses due to the radioactive liquid and gaseous effluents released from the ,

Unit or Station during the previous calendar year. This report shall also include an I assessmer:t of radiation doses to the most likely exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM and in compliance with 10 CFR 20 and 40 CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Power Operation."

12.6.2 Annual Radioactive Effluent Release Repori" The Annual Radioactive Effluent Release Reports shallinclude 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, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materialin Liquid and Gaseous Effluent from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The Annaal Radioactive Effluent Release Report shall include a list and description of unplanned releases of radioactive materialin liquid effluents from the site to UNRESTRICTED AREAS and of unplanned releases of radioactive materialin gaseous effluents from the site to areas at or beyond the SITE BOUNDARY during the reporting period.

The Annual Radioactive Effluent Release Report shallinclude any changes made during the reporting period to the Process Control Program as well as any major changes to Liquid, Gaseous or Solid Radwaste Treatment Systems, pursuant to Section 12.6.4.

The Annual Radioactive Effluent Release Report shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Section 12.2.1 or 12.2.2, respectively; and description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specification 3.11 (ITS 5.5.10) or 3.12 (ITS 5.5.10),

respectively.

12.6.2.1 Exceptions to Regulatory Guide 1.21 Reporting Requirements:

a. All references to " semiannual

are not applicable. The report will be submitted according to Technical Specifications.

b. Hourly meteorological data is recorded for all periods throughout the year, and quarterly summaries will be reported. Separate meteorological data for periods of batch releases are not required to be included,

c. Total body and significant organ doses to the maximally exposed individual from receiving-water-related exposure pathways will be provided. Associated population dose is not required to be included.

f

d. Organ doses to the maximally exposed individual in unrestricted areas from radioactive iodine and radioactive materialin particulate form from all exposure pathways will be provided. Associated population dose is not required to be included.

h V12r2, doc j7,$9

I l

ZION Revision 2 l March 1998 12.5.2 LAND USE CENSUS Q

Q Operability Reouirements 12.5.2.A A Land Use Census shall be conducted and shall identify within a distance of 10 {

km (6.2 mi) the location, in each of the following meteorological sectors, A, J, K, l L, M, N, P, Q, and R, of the nearest milk animal, the nearest residence", and an enumeration of livestock. For dose calculation, a garden will be assumed at the nearest residence.

l Apolicability: At all times.

l l

Action:

With a Land Use Census identifying location (s) that yields a calculated dose or ,

dose commitment, via the same exposure pathway 20% greater than at a '

location from which samples are currently being obtained in accordance with Section 12.5.1, add the new location (s) within 30 days to the Radiological' Environmental Monitoring Program given in Chapter 11 of the ODCM Station Annexes. The sampling location (s), excluding the control location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Submit in the next Annual Radiological Environmental Operating Report documentation for a change in the ODCM including revised figure (s) and table (s) for the ODCM reflecting the new location (s) with information supporting the change in sampling locations.

O "

The nearest industrial facility shall also be documented if closer than the nearest residence.

Surveillance Reouirements I

12.5.2.8 The Larid Use Census shall be conducted during the growing season, between ;

June 1 and October 1, at least once per calendar year using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report.

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

l This census satisfies the requirements of Section IV.B.3 of Appendix l to 10 CFR Part 50. An annual garden census will not be required since the licensee will assume that there is a garden at the nearest residence in each sector for dose calculations.

A l

h:\zi2r2 dm j 7,4g l i l

ZION Revision 2 March 1998 12.5.3 INTERLABORATORY COMPARISON PROGRAM Operability Reauirements 12.5.3.A Analyses shall be performed on radioactive materials supplied as part of an interlaboratory comparison program that correspond to samples required by Table 12.5.1.

Applicability: At all times.

Action:

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

Surveillance Reauirements 12.5.3.B A summary of the results obtained as part of the above required interlaboratory comparison program shall be included in the Annual Radiological Environmental Operating Report.

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

l l

h \zi2r2. doc ggg l

L- 2

I i

ZION Revision 2 March 1998 12.6.4 Maior Chanoes to Liould and Gaseous Radwaste Treatment Systems *"

Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous):

a. Shall be reported to the Commission in the Annual Radioactive i

Effluent Release Report for the period in which the evaluation was reviewed by the Onsite Review and Investigative Function. 4 The discussion of each change shall contain:

1'

1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; ;

2) Sufficient detailed information to totally support the reason for the change without benefit of additional and j supplemental information; )

3) A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems.

4) An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous a effluents that differ from thuse previously predicted in the l License application and amendments thereto;

5) An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC and g' to the general population that differ from those previously estimated in the License application and amendments thereto;

6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, to the actual l releases for the period prior to when the changes are to be made;

7) An estimate of the exposure to plant operating personnel as a result of the change; and B) Documentation of the fact that the change was reviewed and found acceptable by the Onsite Review and Investigative Function.

b. Shall become effective upon review and acceptance by the Onsite Review and Investigative Function.

" Licensees may choose to submit the information called for in this standard as part of the annual FSAR update.

O hM12r2 d*

12-54

ML20217N966

Text

Navigation menu

Search