ML20137B469
| ML20137B469 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 01/31/1997 |
| From: | COMMONWEALTH EDISON CO. |
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| References | |
| PROC-970131, NUDOCS 9703210339 | |
| Download: ML20137B469 (84) | |
Text
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t X244 ALL Document Control Desk g
Director of Nuclear Reactor Regulation L/
U.S. Nuclear Regulatory Commission Mail Station PI-137 Washington,DC 20555 1
J March 4,1997 Attached is a revision to the Offsite Dose Calculation Manual, Zion Annex, Chapters 10 and 12.
Please update your manual as follows:
Remove:
Zion Chapter 10, Revision 1.8 Zion Chapter 12, Revision 1.7 Inse-t:
Zion Chapter 10, Revision 1.9 Zion Chapter 12, Revision 1.8 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
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lbUi Central Files c-4th Floor Downers Grove 9703210339 970131 PDR ADOCK 05000295/
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Zion Station Chapter 10 Change Summary ODCM Revision 1.9, January 1997 Pane Channe Description 10-i Updated revision number.
10-5 Revised HVAC flow rate for radiation monitors 1(2)RE-0015 from 7.32 E+05 cc/sec to 5.60 E+04 cc/sec. The HVAC flow rate has changed due to exempt changes 1(2)-%-252 which relocated the sample tap location to the steamjet air ejector (SJAE) discharge header.
10-7 Corrected typographical error.
O O
i ZION Revision 1.9 I
- January 1997 ZION ANNEX INDEX i
f CHAPTER 10 J
l REVISION 1.9 4
i 4
4
)
i 4
i I
l j
i 1
g:\\z10ri-95 104
ZION Redsion 1.9 January 1997 9
CHAPTER 10 RADIOoCTIVE EFFLUENT TREAT 1ENT AND MONITORING TABLE OF CONTENTS PAGE 10.1 AIRBORNE RELEASES 101 10.1.1 System Descripbon 10 1 10.1.1.1 Wbste Gas Holdup System 10-1 10.1.1.2 Ventilation Exhaust Treatment System 10-1 10.1.2 Radiation Monitors..
101 10.1.2.1 Final Vent Stack Emuent Monitors..
10-1 10.1.2.2 Auxiliary 8tilding Vent Emuent Monitors.
10 2 10.1.2.3 Cu daire cri Purge Emuent Morntors.
10-2 10.1.2.4 Vikste Gas Decay Tank Marstors 10-2 10.1.2.5 Ccxiermer Air E$x: tor Monitors 10-3 10.1.3 Aarm and Trip Setpoints 10-3 10.1.3.1 Setpoint Cmh#*ian.....
10 3 10.1.3.2 Release Urnts..
103 10.1.3.3 Release Mxture..
10 4 10.1.3 4 Converson Factors 10-4 10.1.3.5 HVAC Flow Rates 10-5 10.1.4 Allocation of Emuents from Common Release Points 10-5 10.1.5 Dose Projechons for Batd) Releases 10 6 10.2 UQUID RELEASES..
10-6 10.2.1 System Desaiption....
10 6 10.2.1.1 Lake Dscharge Tanks 10-6 10.2.1.2 Turtine Btildng Fire Surm..
104 10.2.2 Radation Monitors..
1%
10.2.2.1 Lake Dscharge Tank Morntors 10-6 10.2.2.2 Turbine Buildng Fire Sump Monitor 10 6 10.2.3 Alarm and Trip Setpoints 10 7 10.2.3.1 Setpoint Calculaban....
10 7 O
g:\\z10ri-9 wpr 10-ii
ZlON Revision 1.9 4
January 1997 CHAPTER 10 RADIOoCTIVE EFFLUENT TREATW_NT AND MONITORING TABLE OF CCNTENTS (Cont'd) f%CE 10.2.3.2 Dscharge Rcw Rates 10-8 1023.2.1 Lake Oscharge Tank Dscharge Fkw Rate-10 8 10.2.3.2.2 Turbine Building Rre Surm Dscharge Flow Rate 10-8 10.2.3.3 Release Umts 10-8 10.2.3.4 Release Mxture 10-8 10.2.3.5 Converson Factors 10 9 1023.6 Uquid Dlution Flow Rates.
10 9 10.2.4 Allocation of Emuents frorn Common Release Points 10 9 1025 Projected Corehauu6 for Releases 10-9 10.3 SOUDFICATION OF WTTE/Fim CCNTROL PROGRAM 10 9 O
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Oh g:\\z10r1-9xpf 10-iii
ZION Retosion 1.9 January 1997 5
CHAPTER 10 1
UST OF TABLES
~
NUMBER TITLE PAGE 10 1 Assumed Conposition of the Zon Station Noble Gas Emuent 10-10 10-2 HVAC Exhaust Fan Capacities 10 11 10 3 Uquid Dlution Flow Punp Capacities 10-12 1
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ZION Reuson 1.9 January 1997 CHAPTER 10 i '
UST OF FIGURES NUNBER TITLE pg3E j
i 10-1 Srrpiified rm Radweste and G1eeous Emuent Flow Dagram 10-13 10-2 Snplified LJgud Radeste Processing Dagram 10-15 10-3 Smplified laqud Emuent Flow Dagram 10 16 i
i 104 Snplified Solid Radweste Processing Dagram 1017 10-5 Example PMC Marvtor Response 10-18 i
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1 1
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1 g:h10ri-95 10-v
ZlON Remion 1.9 January 1997 CHAPTER 10 RADICETIVE EFFLUENT TREATWNT AND MONITORING l
10.1 AIRBORNE RELEASES 10.1.1 System Desaiption A sinplified gaseous radwaste and gaseous effluent flow diagram is provided in Figure 101. The pnncipal release points for potentially radioactive airborne effluents are the two atmliary building wnt stacks (designated Unit i Vent Stark and Unit 2 Vent Stack in Figure 10-1). In the dassificadon sdiame of Sechon 4.1.4, eadiis dassified as a ground l
lewd release point (see Table A-1 of Appendx A).
l 10.1.1.1 Waste Gas Holdup System Rie waste gas holdtp system is designed and installed to reduce radoactive gaseous effluents by coileding reador coolant system offgases from the reador coolant system i
and prtudng for delay or holdup to reduce the total radoaduty by radiodecay prior to release to the environment The system is desenbod in Sedmn 11.1.2.3 of the Zion FSAR I
l 10.1.1.2 Ventilation Exhaust Treatment System l
Ventilation exhaust treatment systems are desgned and installed to reduce gaseous radiciodine or radioache matenal in partculate form in gaseous efiluents by passing ventilation or wnt exhaust gases through dierocal adsorbers and/or HEPA filters pnor to release to the environment Sudi a system is not oonadered to how any eGect on noble gas effluents. The wntilation exhaust treatment systems are shown in Fgure 101.
y Engineered saMy features atmosphenc deanup systems are not considered to be ventilation exhaust treatment system r.uv imih.
r 10.1.2 Radation Monitors 10.1.2.1 Final Vent Stadt Effluent Monitors Monitors 1RIA-PR49 (Unit 1) and 2RIA-PR49 (Unit 2) continuously monitor the firal l
effluent from the vent stacks Both vent stack nYe dui feature automatic isokinetic sar@ ling and grab sampling.
During normal operation, all three noble gas diannels (Iow range, mid range, high range) are on line and ache A high alarm u,6.cn from the mid and/or high range noble gas l
diannels isolates the particulate, iodne, low range noble gas and mid range noble gas channels. The high alarm sgnal diverts sample flow through a sarmie cart (partictdate and iodine) and then to the high range noble gas channel I
g:\\z10ri-9 vsf 10 1
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ZION Rewsion 19 January 1997 Upon rempt of the high alarm. the contrd roorn cpaator will nobfy the health physics group and reduce the release rate as appropnate. Due to conservatism butt into the setpoint cakxiations (Secton 101.3), there is an Wde trargin between the high alarm setpoint and the release lirnt to Ecu m u.iate ths procedure Pertinent information on these marvtors is provided in UFSAR Tade 11.5-1.
10.1.2.2 Auxiliary Building Vent Emuent Monitors Monitors 1RT-PR25 (Unit 1), 2RT-PR25 (Unit 2) and ORE-0014 (cu m ui) continuously morvtor the effluent from the auxiliary building vent stacks No automatic isolation or contrd functions are pa fu n aj by these monitors. On high alarm, the contrd room operator will notrfy the health physics group and reduce the release rate as appropriate. Because of the mnservatism butt into the setpoint calculations (Seebon 10.1.3) there is an Wda ma@n beteen the setpoint and release lirrat to suumujide this procedure Pertinent liiu n son on rnonitor ORE-0014 is pnuded in UFSAR Table 11.5-2.
10.1.2.3 Contanment Purge Efbent Monitors Morntors 1RT-PR09 (Unit 1) and 2RT-PR09 (Unit 2) continuously monitor the effluent from the Unit 1 and Unit 2 contanments, respectvely On high alarm, the nnitus automshcally irstiate dosure of the four air-operated butterity vanes (RV0001/234 purge valves for end1 ulit).
Pertinent iiiuirdon on these monitors is prcMded in UFSAR Tables 11.51 and 11.5-2.
Monitors 1(2)RIA-PR40 continuously marvtor the Unit 1(2) abumpiae. On high alarm, the iru siors automshcally initiate doeure of valves RV0001-RV0006 indusive.
10.1.2.4 V\\hste Gas Decay Tank Monitors Monitors OR1A PR10 (Channels 1 and 3) continuously monitor the noble gas activity relaawd from the gas decay tanks.
On high alarm, the monitors automabcally initiate dosure of the vane ORC \\/-W3014 thus terrrinating the release Pertinent infun son on these iro stors is pnuded in UFSAR Section 11.5.2.2.1 and Table 11.5-2.
The monrtor is capable of collecting particulate and iodne samples for post release qui =4Tcscri g:\\t10ri-9
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ZION Revision 1.9 j
January 1997 10.1.2.5 Condenser Ar Fpdor Morators Monitons 1RE@15 and 2RE@15 conbnuously monitor the condenser air ejedor gas from Units 1 and 2, respectively. No control dewce is iritiated by these diannels.
Pertinent hkiT-tion on these cruitors is prcMded in UFSAR Table 11.5-2.
l 10.1.3 Alarm and Trip Setpoints i
10.1.3.1 Setpoint Calculaban The emuent noble gas nmtor setpoints are consensbvely based on the assunpuon that a release is occumng simultaneously for all seven gaseous release points at the mammum *W flow rate for each pathmsy Furthermore, the setpoints are diosen such that an ocx:urrence d simultaneous high alarms on all seNen pathways would i
u,T+4 to a staban release rate d one hatt d the Technical Speaficabon limit.
P, s 0.5 x 4 x 1F x W x C" (10-1)
P, =
Setpoult for monitor, M, on release path, P.
[ cpm]
[
0.5=
Factor to reduce release rate by 50%
4=
Total Alicmed Release Rale, Vent Release
[pCi/sec)
F=
Flow rate through Release Path, P.
[ oc/sec)
K" =
Factor to w1ics a frachon d the total release rate, 4, to release path, P.
C" =
Corwermon Factor for monitor, M
[ cpm per pCi/cc]
I 10.1.3.2 Release Umits Alarm and trip setpcnnts d gaseous emuent monitors are estabhehed to ensure that the release rule limits d the RETS are not e. The release limits are found by solving Equebons 102 and 103 for the total allowed release rate d vent (1.11)0,, E {(f,} < 500 mrem /yr (10-2) 0, E { { f,)[((X/0), exp(-1,R/3600u,)
1 (10-3)
+ 1.11 V,]} < 3000 mrem /yr h
O * -9 wpf 10 3 O
ZION Rewsion 19 January 1997 The sunrnations are cNer noble gas radionudides i.
f, Fractional Radionudide Composition The release rate of noble gas radionudide i divided by the total release rate of all noble gas radionudides.
O, Total AJlcmed Release Rate.
Vent Release
[pCi/sec)
The total alloAed release rate of all noble gas radionudides released as vent releases The remaining Darameters in Equation 10-2 have the same definitions as in Equation A8 o' Appendx A The remaining peiisiciers 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 Appendx A and the RETS restriction on veiole body dose rate (500 mrerrvyr) due to noble Om released in gaseous effluend (see Seebon A1.3.1 of Appendx A). Equation 10-3 is based on Equation A-9 of Appendix A and the RETS restriction on skin dose rate (3000 mrerrvyr) due to noble gases released in gaseous effluents (see Seeban A1.3.2 of Appendx A).
Equations 10-2 and 103 can each be soNed for a value of Q, The monitor alarm and trip setpoints will be established based on the equation whidi yelds the smaller release limit, Q, The exact settings are selected to ensure that 10 CFR 20 tirnts are not exceeded-Calibration ivoli 01. and suneillance frequency for the irc stus will be conducted as speofied in the RETS 10.1.3.3 Release Mxture in the detemination of alarm and trip setpoints, the radioactivity nixture in e:diaust air is assumed to have the ra:Sonudide composibon of Table 10-1. This nixture was consenetnely chosen based on staban isotope release data averaged over a period of 7 years (1977 through June 1984).
10.1.3.4 Conversion Fadors The response cunes used to detemine the monitor count rates are chosen in order to best match the reference noble gas nix. M =a Xe-133 and Xe 135 comprise 83.6% and 8.79% of this nix respectively, the Xe-133/Xe-135 90%/10% cunes are used to ensure that the setpoints wotAd De conservatne vwth respect to quantity.
Example cunes are shcwn in Figure 10-5.
g:\\zior1-9wpf 104
l ZlON Revision 1.9 i
January 1997 10.1.3.5 WM Row Rates HVM flow rates are computed for 1(2)RT-PR25, ORE-0014 and 1(2)RIA-PR49 based on the number of operahng fans in the nmtored flow path.
((
F, x N Fu
=
P 1
(104)
Fu Total Rowin Monitored Row Path
[ cc/sec]
=
F, Row frorn fan iin path p.
[ cc/sec)
=
N Number d fans, in operation
=
The maxirnum flow for eed1 fan is used for setpoint calculations hum q this maxinues the flow, and therefore mininues the calojated nmtor senstivity whid1 is conservatne i
Pertinent data for the fans is provided in Table 102.
HVAC flows for the remaining ireLs are conservatnely fixed at upper bound values. They are listed below Marvtor Rowin oc/sec ORIA-PRio 6.61ES O-1(2)RE 0015 5.60E4 1RT-PR09A 1.65E6 (vent mode) 1.46E6 (rnru-purge mode) 1.46E7 (punje mode) 2RT-PROBA 4.35E6 (vent mode)*
4.11E6 (mirv-purge mode) 1.99E7 (purge-mode) 2.70E6 (roubne, hot lab only) 10.1.4 Allocabon of Effluents from Common Release Points Radioedne gaseous ef!Iuents released from the atooliary buildng niscellaneous ventilation system and the gas decay tanks are comprised of contributions from both units. Under nomrn operating conditions, it is dfficult to apportion the rr.rse.ctivity between tbs units. Consequently, allocation normeily is made evenly beteen talits.
' Row greater than Unit 1 due to " hot lab" hood exhaust fan flow.
g:\\ziari-9 wpf 10 5
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ZlON Ression 19 January 1997 10.1.5 Dose Projections for Entch Releases Projeded doses are calctiated before purgirg the un iniYivs d or venting the waste gas decay tanks. Per procedure, a representatne sanple is obtained and analyzed, and the total release is calculated. Prior to the release the projected I
dose rate (in mrenvyear) is calculated based on the assumption that the release is ax1tinuous for the entire year.
10.2 UQUID RELEASES 10.2.1
System Description
A sinpiified liquid waste processing diagram is prcNided in Figure 10-2. A simplified liquid effluent fkw dagram is provided in Figtse 103.
The liquid radaste tredunefit system is designed and installed to reduce radioactive liquid effluents by coileding the liquds, pnudng for retention or hoidup, and providng for treatment by datedizer for the purpose of reducing the total radioactivity prior to release to the erMronmert The system is desenbed in Section 11.1.3 of the Zion FSAR.
10.2.1.1 Lake Dscharge Tanks There are te lake dscharge tanks (GA and OB, 30,000 gallon capacty each) whid1 re ive liquid waste before discharge to Lake Mdigart 10.2.1.2 Turbine Btilding Fire Surrp The turbine buildng floor and equipment drain tanks recene turbine building waste whidi is released to the fire sung for processing by the waste water treatment facility and ultimate discharge into Lake Mdligan. The dsdiarge constitutes a low levei radioedive release 10.2.2 Radation Monitors 10.2.2.1 Lake Disdiarge Tank Monitors Monitors ORT-PR04 and ORT-PROS are used to monitor all releases from the lake dscharge tanks. On high alarm, the monitor automatically initiates dosure of a valve to prevent ftsther releases. The valve is located over 250 feet dcwnstream of the monitor to allow doeure prior to exmedng release lirrits. The rronitor setpoints are found by soMng Equation 105 for release setpoint P.
Pertinent ii su n =Uon on these iru &, s is provded in UFSAR Table 11.5-3.
10.2.2.2 Turbine E5ildng Fire Sunp Mxitor Nbnitor ORT-PR25 continuously monitors the dscharge line from the fire sunp pumps to the waste water treatment fadlity. On high alarm, the monitor automatically trips all of the fire surrp pumps, thereby contairing the liquid in the l
g:\\t10r1-95 104 I
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ZION Revsaan 1.9 1
January 1997 turbine tuidng. Ti'e rnorvtor setpoints are found by solving Equadon 10-5 for release setpoint P.
I Pertinent inivir-Gon on the rnorntor is provided in UFSAR Table 11.53.
10.2.3 Aarm and Trip Setpoints 10.2.3.1 Setpoint Calajation Alarm and trip setpoints of liquid effluent marvtors at the prinopal release points are established to ensure that the limts of the Technical Speafications and 10 CFR 20 are not exceeded in the unrestrided area. The monitor setpoints are found by solving Equation 10-5 for a consentabve nixture of radionudides found in IKpd effluents.
P s Kx(Cy(P/F)
(10-5)
P Release Setpoint
[pCi/rnL)
The alarm setpoint for radioaduty to be released in liquid effluents.
C, Maximum Pemissible COunsa6cn
[pCi/nt]
P Dlution Fkw Rate (gpm]
The fkw rate of the radwaste dilution strearn (condenser cooling veter).
P Dscharge Flow Rate
[gpm]
O The flow rate from the lake discharge tank or fire sunp as appropnate.
K Factor of ooneervaten K = 0.5 for lake discharge tank K = 1.0 for sump i
g'.\\z10ri-9 $
107
ZION Retision 1.9 January 1997 10.2.3.2 Dsdarge Ficw Rates G ;!
10.2.3.2.1 Lake Dsdarge Tank Dsdarge Row Rate i
Prior to each batch release, the water is recircuated, sampled, and analyzed.
The resdts of the analysis of the waste sanple detemine the disdarge rate of each batch as follows:
F
= (C,,y(P,JC)
(104)
P. Maximum Permtted Osdiarge Flow Rate
[gprn]
The maximum wn.a now rate from the lake dsdiarge tank.
[gpm}
1 F%
Actual Dlution Row Rate
[gpm]
The actual flow rate of the radeste dlution stream (based on punp curws).
C Sarmie Radoadmty Ceriziaiian
[pCi/mL]
The concentraban of radoachvityin the lake discharge tank based on rneasurements of a sarmle drawn from the C
has the same de6nition as in Equabon 10-5.
10.2.3.2.2 Tuttine Bdidng Fire Sur@ Dscharge Flow Rate This release path is a continuous dscharge Consequently, the release rate P in Equabon 106 is set equal to maximum design capaaty for the pumps on the emuent of the weste weler treatment fsclity.
10.2.3.3 Release Umts Release limts are deWned from 10 CFR 20.
10.2.3.4 Release U.xture The release nixture used for setpoint determnation is the worst case radionudide nix chosen on the basis of station isotopic analysis data reviewed for 1978.
gh10ri-9 wpf 104 O
ZION Reason 1.9 January 1997 10.2.3.5 Converson Fadors The converson factor for ORT-PR25 (fire surm monitor) is based on detector ll response curves for 1-131. The converson factors for monstar ORT-PR04 and ORT-PROS are bened on detector response cunes for Cs-137.
i l
10 2.3.6 Lxpd Dlution Flow Rates Dlution flow rates are computed bened on the number of operating purms in the i
flow path.
{ P,x M (10-7)
{
P
=
i Dlution Flow Rate (gpm) f P
=
P, Diulian Flow Rate from pur@ l
[gpm]
=
Nurrber of purms of type i operating l
N
=
Pertinent flow data for the purgs is prowded in Table 10e 1
10.2.4 Mombon of Efiluents from Common Rolesse Points i
3
\\
Radicadne liquid effluents rh from the lake discharge tank and turbine l
building fire sur@ are oorgneed of coninbubans from both units. Under normal i
operating condibons, it is difikult to apportion the radioedMty belmen the units.
i Copaswy swllly, allocaban is bened on the unit dedierge canal used for dlution.
l 10.2.5 Prgeded Concentrabons for Releases Projected concentrabons are cakulated before irutisting liquid discharges Per l
proomise, a representaine sarmie is obinned and analyaed and the prgected i
concentrabons are
- N using consenabve dilubon flows prior to release j
Rara ma the fire sump is a continuous r9ieene, it is sampled daily and isotopic l
erd,x are performed veeldy Domes due to liquid afRuents are calculated as required by the RETS 10.3 SOLIDIRCATION OF VMSTE/ PROCESS CONTROL PROGRAM
)
l The process control program (PCP) contains the sampling, analyss, and i
fomnulation determnebon by whid1 solidificaban of radioedive westes from liquid systems is ensured i
g:\\ziari-9wpf 10-9 I
I l
l
i ZION Revson 19 January 1997 Table 10-1 Assumed Cormosition of the Zon Station Noble Gas Effluent 1
Isotope Percent of Effluent Ar-41 1.92E-1 j
3 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 133rn 7.56E-1 Xe-133 8.36E1 Xe-135m 1.03E-1 Xe-135 8.79 l
Xe-137 1.0E-4 Xe-138 4.37E-3 l
Note:
Rwd on station isotopic release data aweraged over 7 years (1977 through June 1984).
g.h10r1-9 vgf 10-10 9
ZION Revision 1.9 January 1997 TABLE 102 HVAC EXHAUST FAN CAPACITIES
'O t)
- 1 Aux. Bda GA Exh. Fan 3.16 x 107 6.70 x 10' 4.020.000 l
OB Exh. Fan 3.16 x 10' 6.70 x 10' 4,020,000 OC Exh. Fan 3.16 x 10' 6.70 x 10' 4,020,000
- 2 Aux. Bida.
OD Exh. Fan 3.16 x 10' 6.70 x 10' 4,020,000 OE Exh. Fan 3.16 x 10' 6.70 x 10' 4,020,000 0F Exh. Fan 3.16 x 107 6.70 x 10' 4,020,000
- 1 Purae EA 1A Purge Fan 1.46 x 107 3.10 x 10' 1,860,000 18 Purge Fan 1.46 x 10' 3.10 x 10' 1,680,000 H2 Purge Fan 1A 1.70 x 105 3.60 x 102 21,600 H, Purge Fan 1B 1.75 x 10' 3.40 x 102 22,200
- 2 Pume Exh.
2A Purge Fan 1.65 x 107 3.50 x 10' 2,102,400 28 Purge Fan 1,72 x 107 3.65 x 10' 2,188,800 A(")
H Purge Fan 2A 1.82 x 105 3.85 x 102 23,100 2
H, Purge Fan 2B 1.75 x 108 3.71 x 102 22,260 Hot Lab Exh. 0A 1.50 x 10' 3.18 x 10' 191,000 Hot Lab Exh. OB 1.18 x 10' 2.51 x 10' 150.600 M sc. Exh.
Comp & Msc Exh. GA 2.81 x 10' 5.95 x 10' 357,000 Comp & Msc. Exh OB 2.81 x 10' 5.95 x 10' 357,000 Ser. Bdg.
Decon. Rrn Exh.
1.91 x 10' 4.04 x 10' 242,580 Welding Rrn Exh.
1.09 x 10' 2.30 x 10' 138,000 Sandblast Rrn Exh.
9.44 x 108 2.00 x 10' 120,000 Cave Exh.
6.14 x 108 1.30 x 10' 78,000 i
Mxhne Shop Exh.
1.42 x 10' 3.00 x 10' 180,000 l
l l
(b l
gk10ri-9 vgi 10 11
I ZION Re$ son 1.9 January 1997 I
TABLE 143 1
UQUID DILLITION FLON PUMP CAPACITIES PUNP Nt#EER OF PUMPS DILUTION FLON RUNNING CIRCULATING WATER 1
250,000 gpm CIRCULATING WATER 2
530,000 gpm CIRCULATING V%TER 3
640,000 gpm SERVICE WATER 1
13,500 gpm SERVICE WATER 2
27,000 gpm SERVICE VATER 3
40,500 gpm l
O g:\\z10r1-9wpf 10-12
~
ZION Revision 19 f
January 1997 i
Figure 10-1 Simphfied Gaseous Radwaste and Gaseous Emuent Flow Diagram i
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.5.
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r s==
espness m o UI N
V f
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m a s.
a m
=
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an e
4 e
p ggg age, 559 6 e
1 G
(NIFWTE SERE caarem ayung m i
aan eranom
= = = -
in
=.
T eas e RGENE 80-1
=
a=
. D ---------- J
[
ine s ensm.
--- G Sa@LFEO GASEOUS RADW4STE AND GASEOUS EFTLUENT FLOW DeAORAAA N I OF 2p l
10-13 g \\r10rt 9 v@f
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Chapter 12 Change Summary ODCM Revision 1.8, January 1997 Eagt Chance Descnotion 12-il Updated revision number, 12 1,2,13, Corrected typographical errors.
24,29,33, 36,40,46, 48,51 12 13 ACTION 15 - Remove requirement to daily venfy alignment of Auxiliary Building ventilation. This is consistent with other radiation mondors which require realignment of ventilation due to mondor inoperability. The daily venfication of the alignment (controlled by an out-of-service) is a task of no value.
12-22 Corrected Table 12.3 2 to reference applicable footnotes. Cunent sections of the table reference incorrect footnotes.
12-25 Revised wording to be consstent with NUREG-1301 and current ODCM methodology; indicated limits apply to effluents released from each unit, versus each site. Subsequently reduced the 16mits to one half of current values.
12-26 Revised last paragraph to indicate this section appises to effluents released from each unit at tfw site.
12-27 Revised wording to be consistent with NUREG-1301 and current ODCM methodology; indicated limits apply to effluents released from each unit, versus each site. Subsequently reduced the limits to one half of current values.
12-31 Revised wording to be consistent with NUREG-1301 and current ODCM methodology; indicated limits apply to effluents released from each unit, versus each site. The requirement had incorrecly been written to apply to the site.
12-33 Revised wording to be consistent with NUREG 1301 and current ODCM methodology; indicated limits apply to effluents released from each unit, versus each site. The requirement had incorrectly been wrttten to apply to the site.
v
I ZION Revision 18 Janurry 1997 O
SPECIAL NOTE I
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The requirements of the Technical Specifications shall take precedence over this chapter, should any i
differences occur.
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4 ZION Revision 18 January 1997 CHAPTER 12 REVISION 1.8 l
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ZION Rrvision 18 Jinuiry 1997 CHAPTER 12 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS (RETS)
TABLE OF CONTENTS PAGE 12.1 DEFINITIONS 12-1 12.2 INSTRUMENTATION 1.
Radioactive Liquid Effluent Monrtonng instrumentation 12-5 2.
Radioactive Gaseous Effluent Monitonng instrumentation 12-9 12.3 LIQUID EFFLUENTS 1.
Concenvabon 12-19 2.
Dose 12-25 3.
Liquid Radwaste Treatment System 12 27 12.4 GASEOUS EFFLUENTS 1.
Dose Rate 12-28 2.
Dose - Noble Gases 12-31 3.
Dose - l-131,1-133, Tntium, and Radioactive Material in 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.
Intertaboratory Companson 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) 12-52 4.
Major Changes to Liquid and Gaseous Radwaste Treatrnent Systems 12-53 l
g \\Z12ri-8 doc
ZION Revision 18 Jtnutry 1997 CHAPTER 12 1
i RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)
LIST OF TABLES PAGE 12.1 1 Surveillance Frequency Notations 12-4 12.2 Radioactive Liquid Emuent Monitoring instrumentation 12-6 12.2-2 Radioactive Liquid Effluent Monitoring instrumentation Surveillance 12-8 12.2-3 Radcactive Gaseous Emuent Monitoring instrumentation 12-10 12.2-4 Radioactive Gaseous Effluent Monitoring instrumentaten Surveillance 12 14 i
12.3-1 Allowable Concentration of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Emuents 12-21 12.3-2 Radioactive Liquid Effluent Sampling and Analysis Surveillance 12-22 12.4-1 Radioactive 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 Capabihties for Environmental Sample Analysis 12-45 g \\r12ri-8 doc 12-iv
_... _ - -.. -. - - -. ~.. - - - - -... - -
ZlON Revision 1 S Janutry 1997 i
4 l
12.1 l DEFINITIONS i-12.1.1-ACTION shell be that part of the sectens which presenbes remedial measures required under..
designated conditions.
12.1.2 A BATCH RELEASE is the discharge of hquid wastes of a discrete volume. Pnor to samchng for analyses, each batch shall be isolated and then thoroughly mixed to assure representative
-j sampling.
)
12.1.3 A CHANNEL CAllBRATION. shail be the adjustment, as necessary, of the channel Juch that it F
. responds with the necessary range and accuracy to known values of input. The CHANNEL I
CALIBRATION shall encompass the entire channel including the sensors (where possible),
i alarm interlock and/or inp functons and shall include the CHANNEL FUNCTIONAL TEST. The l
CHANNEL CAllBRATION may be performed by any senes of sequential, overlapping, or tot:f l
channel steps such that the entire channel is calibrated.
12.1.4 A CHANNEL CHECK shall be the quahtabve assessment of channel behavior during operation by observation. This determination shallinclude, where possible, comparison of the channel
{
indicaten and/or status with other indicatons 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 c:cse to the primary sensor (s) as pracbcable to venfy OPERABILITY, including all channel outputs, as appropnate.
- b. -
Logics-The applicaten of input signals, or the operabon of relays or switch contacts,'in all the combinatens required to produce the required decison outputs including the operaten of all ACTUATION DEVICES. Whert>
l prachcable, the test shall include the operaten 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 quantty of liquid sample is piepvik,nal to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representabve 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 inn. Sow during the release).
12.1.8 DOSE EQUlVALENT l-131 shall be that concentration of I-131 (neroCurie/ gram) whbh alone would produce the same thyroid dose as the quantity and isotopic midure of I-131,1-132, I ",33, 1-134, and 1-135 actually present. The Thyroid Dose Conversion factors used for this calculation shall be those listed in Table ill 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.
12.1.9 MEMBER OF THE PUBLIC means any individual except when that individual is receiving an
. occupatonal dose.
)
g \\t12r1-8 doc 12-1
ZION R: vision 18 Januiry 1997 12.1.10 OCCUPATIONAL DOSE means the dose received by an individualin the course of employment in which the individual's assigned dutes involve exposure to radiation and/or radioactive matenal from licensed and unlicensed sources of radiation, whe*.her in the possession of the licensee or other person. Occupational dose does not include dose from background radiation, as a patient from medical practices, from voluntary participaton in medical research programs, or as a member of the public.
12.1.11 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified functon(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubncabon or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its functon(s) are also capable of performing their related support function (s).
i 12.1.12 OPERATING is defined as performing the intended function in the intended manner.
12.1.13 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.
j 12.1.14 An OPERATIONAL MODE (i.e., Mode) shall correspond to any one inclusive combination of core reactivity condition, power level, and a.'erage reactor coolant temperature specified in Table 1.1 of the Technical Specifications, when fuel assemblies are present in the reactor vessel.
12.1.15 The PROCESS. CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing 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 goveming the disposal of solid radioactive waste.
12.1.16 PURGE OR PURGING is the controlled process of discharging air or gas from a confinement to r.aintain temperature, pressure, humidity, concentration or other operating condition, in such a manner, that replacement air or gas is required to purify the confinement.
12.1.17 RATED THERMAL POWER shall be a total steady state reactor core heat transfer rate to the reactor coolant of 3250 MWt.
l 12.1.18 The REACTOR PRESSURE shall be in the pressure in the steam space of the pressurizer.
l 12.1.19 The SITE BOUNDARY chall be that line beyond which the land is not owned, leased or othesise controlled by the licensee.
12.1.20 SOLIDIFICATION shall be the conversion of radioactive liquid, resin and sludge wastes from liquid systems into a form that meets shipping and burial site requirements.
12.1.21 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
12.1.22 The SURVEILLANCE FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 12.1-1.
12.1.23 IHERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
g \\zi2ri-8 doc 12-2
ZION Rsvision 10 Januiry 1997 12.1.24 UNRESTRICTED AREA means an area, access to which is neither limited nor controlled by the t'
licensee.
b 12.1.25 VENTitATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream pnor to the release to the environment. Such a system is not considered to have any affect on noble gas effluents.
12.1.26 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 dunng venting. Vent, used in system names, does not imply a venting process.
12.1 27 WASTE GAS HOLDUP SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System off ases from the Reactor 1
Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
- V l
l g \\t12r14 doc 12-3
ZION Revision 18 January 1997 TABLE 12.1 1 SURVEILLANCE FREQUENCY NOTATIONS NOTATION FREQUENCY
- S (Shiftly)
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D
(Daily)
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W
(Weekly)
At least once per 7 days M
(Monthly)
Atleast once per 31 days O
(Quarterty)
Atleast once per 92 days SA (Semiannually)
Atleast 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 desenbed in Section 12.5.
gt12r1-8 doc W
ZION Rsvision 18 a
Jrnuary 1997 12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Effluent Monitonng instrumentation Ooerabihtv Reauirements 12.2.1.A The radioactive liquid effluent monitoring 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..
Aoolicability At all times.
Action 1.
With a radioactive lir.iuid efCuent 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 munitoring instrumentation channels inoperable, take the ACTION sfv.mn in Table 12.21.
Surveillance Reauirements 12.2.1.B.1 The setpomts shall be determined in accordance with procedures as desenbed in the ODCM.
12.2.1.B.2 Each radioachve liquid effluent monitoring instrumentation channel shall be demoastrated O.
CPERABLE by performanca of a CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 12.2-2.
p..
12.2.1.0 The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the release of radioactive matenals 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 /tnp 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.
9 12-5
ZION Revision 18 January 1997 TABLE 12 2-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE ACTION #
MODES 1.
Gross Activity Monitors Provdng Automatic Termnation of Release A.
Lake Discharge Tank (LDT) 1.
OR-PR04 See ACTION 1 1
All 2.
OR-PROS See ACTION 1 1
All B.
Turbine Bldg.
1.
OR-PR25 1
2 A!I 2.
Continuous Composite Sampler A.
Turbine Building Fire Sump 1
2 All 3.
Flow Rate Monitors A.
Lake Discharge Tank 1.
OF-WD63 1
3 All 2.
OF-WD67 1
3 All g u12r1-8 h 12-6 O
O O
ZION Rcvision 1.8 Januiry 1997 TABLE 12 2-1
. [h
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RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION (Cont'd) l 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 re; eases from 4
the tank may continue for up to 14 days, provided that prior to initiating the release:
i d
1.
At least two independent samples of the tank's contents are analyzed, in accordance with Section 12.2.1.B and l
2.
At least two technically qualified members of the facility staff independently venfy the release rate calculations and discharge flow path valving; Otherwise, suspend release of radioactive effluents via this pathway.
s 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.
1 ACTION 3 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 the flow rate is g
estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump curves may be used to estimate flow.
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g t:12ri-8 doc 12-7
ZION Revision 18 January 1997 TABLE 12.2-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION (1)
IEST(2) 1.
Gross Activity Monitors Providing Automatic Termnation Of Release A.
Lake Discharge Tank (LDT) 1.
OR-PR04 P
P R
O 2.
OR-PROS P
P R
Q B.
Turtune Bldg.
1.
OR-PR25 D(3)
M R
Q 2.
Continuous Composite Sampler A.
Turbine Building Fire Sump D
N/A N/A N/A 3.
Flow Rate Monitors A.
Lake Discharge Tank 1.
OF-WD63 D(3)
N/A R*
N/A 2.
OF-WD67 D(3)
N/A R*
N/A (1)
CHANNEL CALIBRATION shallinclude performance of a CHANNEL FUNCTIONAL TEST.
(2)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that any automatic isolation of this pathway occurs and that control room alarm annunciation occurs if any of the following conditions exist (if the capability is installed):
a) Instrument indicates levels above the alarm setpoints.
b) Circuit failure.
c) Instrument indcates a downscale failure.
d) Instrument controls not set in operate mode.
(3)
CHANNEL CHECK shall be made at least once daily on any day on which continuous, penodic, or BATCH RELEASES are made.
- Does not include flow sensor.
g m2n-a =
12-8
ZION Rsvision 18 Jinurry 1997 12.2.2 Radioactive Gaseous Emuent Monitonng instrumentation
(
Ooerability Reauirements 12.2.2. A The radioactive gaseous effluent monitonng instrumentation channels shown in Table 12.2 3 shall be OPERABLE with their alarm /tnp setpoints set in accordance with the method prescribed in the ODCM to ensure that the limits of Section 12.4.1.A are met.
Acolicability At all times, except as indicated in Table 12.2-3.
Action 1.
With a radioactive gaseous effluent monitoring instrumentation channel alarm /tnp 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 desenbed 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, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 12.2-4.
12.2.2.C The radioactrve 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.
e g\\z12r1 8 doc 12-9 O
ZION Rsv:sion 1.8 Jrnu*ry 1997 TABLE 12 2-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
)
MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE ACTION MODES
]
1.
Gas Decav Tank 1
A.
Gas Activity Monitor j
1.
OR-PR10 (Low gas-Channel 1) 1 5
All 2.
OR-PR10 (Mid gas-Channel 3) 1 5
All B.
Flow Rate Monitor 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 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 All 8
2.
2R-PR09A Gas 1
6', 78 All 3.
1R-PR40E (Channel 5) 1 6', 78 All 4.
2R-PR40E (Channel 5) 1 6', 7 All 2
B.
lodine Monitor 8
1.
1R-PR09B lodine 1
6', 7 All 8
2.
2R-PR09B lodine 1
6', 7 All 3.
1R-PR40C (Channel 3) 1 6', 7' All 8
4.
2R-PR40C (Channel 3) 1 6', 7 All
' Dunng VENTING
' During PURGING 0 V12ri-8 doc 12-10 1
I l
ZION Rsvision 18 Jtnutry 1997 TABLE 12.2-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION kJ (Cont'd)
MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE ACTION MODES 3.
Containment Purae or Vent C.
Particulate Monitor 2
1.
1R-PR09C Particulate 1
6', 7 All 8
2.
2R-PR09C Particulate 1
6', 7 All 2
3.
1R-PR40A (Channel 1) 1 6'. 7 All 8
4.
2R-PR40A (Channel 1) 1 6', 7 All 4.
Anviliary Buildino Ven*+ian and Miscellaneous Ventilation Stack A.
Gas Activity Monitor 1.
OR-0014 or 1
6 All 2.
6 All 3.
1R-PR49E (Channel 5) 1 13 All 4.
2R-PR49E (Channel 5) 1 13 All O-B.
lodine Monitor 1.
OR-PR12B 1
15 All 2.
1R-PR49C (Channel 3) 1 14 All 3.
2R-PR49C (Channel 3) 1 14 All C.
Particulate Monitor 1.
OR-PR12A 1
6 All 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 8 During Purging 9
g
ZION Rsymon 18 JInuiry 1997 TABLE 12.2-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (Cont'd)
MINIMUM i
CHANNELS APPLICABLE INSTRUMENT QPERABLE ACTION MODES 5.
Steam Generator Atmosoherie Relief and Safetv Valves j
A.
1R-PR58 1
10 1,2,3,7 i
B.
2R-PR58 1
10 1,2,3,7 i
C.
1R-PR59 1
10 1,2,3,7 O.
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.
Containrnent 1,
1R-PR40G (Channel 7) 1 10 1,2,3,4,7 2.
2R-PR40G (Channel 7) 1 10 1,2,3,4,7 3.
1R-PR40I (Channel 9) 1 10 1,2,3,4,7 4.
2R-PR401 (Channel 9) 1 10 1,2,3,4,7 B.
Miscellaneous Vent 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.
1R-AR04B 1
11 6
3.
2R-AR04A 1
11 6
4.
1R-AR048 1
11 6
- When purging during fuel handling operations gt12ri-a.d" 12-12
ZION Rsvision 1.8 Jtnuary 1997 1
TABLE 12 2-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (Cont'd)
TABLE NOTATIONS ACTION 5 -
With the number of chantiels OPERABLE less than the mmimum number requwed. the contents of the t it i
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 quairhed members of the facildy staff independently venfy the release rate calculations and decharge flow path valving; Otherwee, suspend release of radioactrve effluents via this pathway.
ACTION 6 -
Wdh the number of channels OPERABLE less than the minimum number requwed. effluent releases via this pathway may contmue 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 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s-ACTION 7 -
With the number of channels OPERABLE less than the minimum number requwed. and no redundant mondor OPERABLE in the flow path, vnmedetely suspend PURGING of radioactive efnuents via the pathway.
i i
ACTION 8 -
With the number of channels OPERABLE less than the mmwnum number required, effluent releases vm this
~
pathway may continue for up to 30 days, provided samples are contmuously collected with auxilary sampling equipment as required in Table 12.4-1.
ACTION 9 -
With the number of OPERABLE channels less than the minwnum number requwod, effluent releases vm the pathway may contmun provided the flow rate is eetwnsted at leset once por shdt while release is in progress..
ACTION 10 -
With the number of channels OPERA 8LE less than the mmwnum number requwed, restore the inoperable f
monitor to OPERA 8LE status within 30 days or estableh an allemate means of monitonng the parameter.
ACTION 11 -
With the number of OPERABLE channels less than the mmwnum number required, suspend vent and purge operatens and close each vont and purge valve providmg direct access from the contamment atmosphere to
(
the outside atmosphere or suspend the movement of nuclear fuel and reador components m the vicindy of the reactor, refuel.ng cavity, and transfer canal (contamment side).
ACTION 12 -
With the number of OPERABLE channels less than the mmir:n number requwod, effluent releases ve this pathway may contmue provided the effluent flow is bemg accounted for in the total plant ofRuont.
ACTION 13 -
With the number of OPERA 8LE channels less than the mmimum number requwod, restore the channel to OPERABLE status withm 30 days or conduct a station review to determine a plan of acten to restore the channel to OPERABLE status. EfRuont rolesse via the pathway may contmue provided grab samples are taken at least once por shdt and these samples are analyzed for gross actrvity withm 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 14 -
With the number of OPERABLE channels less than the mmwnum number required, restore the channel to OPERABLE status within 30 days or conduct a stabon revow to determine a plan of schon to restore the channel to OPERA 8LE status. Effluent release via the pathway may continue provided grab samples are conhnuously collected with auxiliary sampling equipment as requwed in Table 12.4-1.
ACTION 15-WIth the number of OPERABLE channels less than the mmwnum number required, Auxilary Building Cubicle venblabon shall be routed through the Auxiliary Buildmg ventitetson charcoal adsorber unds.
r P
i
ZION R:vison 18 January 1997 TABLE 12 2-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL CHECK CHECK CALIBRATION f1)
TEST (2) 1.
Gas Decav Tank A.
Gas Actrvity Monitor 1.
OR-PR10 (Low gas-Channel 1)
P P
R Q
2.
OR-PR10 (Mid gas-Channel 3)
P P
R O
B.
Flow Rate Monitor 1.
OF-WG03 P
N/A N/A O(5) 2.
Air Eiector Off-Gas A.
Gas Activity MonPa>r 1.
1R-0015 Gas D
M R
Q 2.
2R-0015 Gas D
M R
Q B.
Particulate / lodine Monitor 1.
1R-PR26 D
M R
Q 2.
2R-PR26 D
M R
Q u12r1-8 doc 12-14
O O
O
~
ZION Revissorf 18 January 1997 TABLE 12.2-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE (Cont'd)
CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CAllBRATION (1)
TEST (2) 3.
Containment Pume or Vent A.
Gas Activity Monitor i
1.
1R-PR09A D
M R
Q 2.
2R-PR09A D
M R
Q 3.
1R-PR40E (Channel 5)
D M
R O
i
'4.
2R-PR40E (Channel 5)
D M
R O
i B.
lodine Monitor 1.
1R-PR098 D
M R
O 2.
2R-PR09B D
M R
O 3.
1R-PR40C (Channel 3)
D M
R O
4.
2R-PR40C (Channel 3)
D M
R O
C.
Particulate Monitor 1.
1R-PR09C D
M R
O 2.
2R-PR09C D
M R
O 3.
1R-PR40A (Channel 1)
D M
R O
4.
2R-PR40A (Channel 1)
D M
R O
j t
t 6
L l
i g u12rt-8 dx 12-15
ZION Revision 18 January 1997 TABLE 12.2-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVElLLANCE (Cont'd)
CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION f1)
TEST (2) 4.
Anviliary BuiH% Ventilmtian and Miscellaneous Venhiabon Stack A.
Gas Activity Monitor 1.
OR-0014 Gas or D
M R
Q 2.
M R
Q 3.
1R-PR49E (Channel 5)
D M
R Q
4.
2R-PR49E (Channel 5)
D M
R Q
B.
lodine Monitor 1.
OR-PR-12B D
M R
O 2.
1R-PR49C (Channel 3)
D M
R Q
3.
2R-PR49C (Channel 3)
D M
R O
C.
Particulate Monitor 1.
OR-PR12A D
M R
Q 2.
1R-PR49A (Channel 1)
D M
R Q
i 3.
2R-PR49A (Channel 1)
D M
R Q
D.
Flow Rate Monitor 1.
1LP-084 D
N/A R
Q 2.
2LP-084 D
N/A R
O V12r1-8 doc 12-16
~
O O
O
~
ZION Revision.18 January 1997 -
TABLE 12.2-4 IMDIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE (Cont'd)
CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL l
lNSTRUMENT' CHECK CHECK CALIBRATION (1)
TEST (2) 5.
Steam Generator Atmosahenc Relief and Safety Valves 1.
1R-PR58 D
M R
Q 2.
2R-PR58 D
M R
Q 3.
1R-PR59 D
M R
Q 4.
2R-PR59 D
M R
Q 5.
1R-PR60 D
M R
Q 6.
2R-PR60 D
M R
O 7.
1R-PR61 D
M R
O 8.
2R-PR61 D
M R
O 6.
Accdent Monatonng l
A.
Containment t
1.
1R-PR40G (Channel 7)
N/A N/A R
Q 2.
2R-PR40G (Channel 7)
N/A N/A R
Q 3.
1R-PR401 (Channel 9)
N/A N/A R
Q 4
2R-PR401 (Channel 9)
N/A N/A R
Q B.
Miscellaneous Vent Stack 1.
1R-PR49G (Channel 7)
N/A N/A R
O 2.
2R-PR49G (Channel 7)
N/A N/A R
Q i
3.
1R-PR491(Channel 9)
N/A N/A R
O l
4.
2R-PR491(Channel 9)
N/A N/A R
Q C.
FuelHandling Area 1.
1R-AR04A D
M(3)
R O(4) 2.
1R-AR048 D
M(3)
R Q(4) 3.
2R-AR04A D
M(3)
R Q(4) 4.
2R-AR04B D
M(3)
R Q(4) i g u12rt-8 doc 12 17 i
m
ZION Rsvision 18 J;nuiry 1997 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 FUNCTIONAL TEST shall also demonstrate that any automatic isolation occurs; and that Control Room alarm 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.
j 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to commencing refueling operations.
j q
(5)
OPERABILITY test only.
l 1
O 3
g1212ri-8 doc 12-18
~ _ _. _. _ _ _ _ _.
f, ZION Revision 18 j
January 1997 4
1 12.3 LIQUID EFFLL'ENTS i
!~
12.3.1 Ccncentration
?
4
)
i.
Ooerability Reauirements i~
)
12.3.1.A.1 The concentration of radioactive material released from the site to UNRESTRICTED AREAS (see Zion Station OOCM Annex, Appendix F, Figure F 1) shall be limited to 10 l
times the concentrations specified in Appendix B, Table 2, Column 2 to 10CFR20.1001-i-
20.2402, for radionuclides other than dissolved or entrained noble gases. For dissolved 4
j or entrained noble gases, the concentrations shall be limited to the values listed in Table 12.3-1.
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.
k Aoolicabihty At all times.
I i
AGilQD 1.
With the concentration of radioactrve materials released from the site to i
UNRESTRICTED AREAS exceeding the limits specified in Section 12.3.1.A, j
immediately decrease the release rate of radioactive materials and/or increase j
the dilution flow rate to restore the concentration to within the above limits.
Surveillance Raouirements i
12.3.1.B.1 The radioactivity content of each batch of radioactive liquid waste shall be determined j
prior to release by sampling and analysis in accordance with Table 12.3-2. The results of
- d pre-release analyses shall be used with the calculational methods in the ODCM to assure
)
1 that the concentration at the point of release is maintained within the limits of Section 12.3.1.A.
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 limi:s 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 concentrations at 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.
o v12r1.s =
$219
ZION Rtvision 18 Januiry 1997 Bases 12.3.1.C This SeeJon 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 the 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 outside 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 e
ZION Revision 1.8 JInuary 1997 TABLE 12.3-1 k
ALLOWABLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID EFFLUENTS NUCLIDE A(mci /mh*
Kr-85m 2 X 10" Kr-85 5 X 10" Kr-87 4 X 10
Kr-88 9 X 10
Ar-41 7 X 10
Xe-131m 7 X 10" Xe-133m 5 X 10" Xe-133 6 X 10" Xe-135m 2 X 10" Xe-135 2 X 10"
- 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.
ZION Rivision 18 J!nu ry 1997 TABLE 12.3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE MINIMUM ANALYSIS LOWER LIMIT '"'
LIQUID RELEASE SAMPLING FREQUENCY TYPE OF OF DETECTION TYPE FREQUENCY ACTMTY ANALYSIS (LLD)(pCi/ml)
A. Lake Discharge Prior to Each Release Prior to Each Pnncipal Gamma SE-7 Tank (c)
Release Emitters (e) l l131 1E-6 P
M Dissolved and 1E-5 One Batch /M(c)
Entrained Gases (Gamma Emitters) l P
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 1E-5 Entrained Gases (Gamma Emitters)
Continuous (d)
M Tntium 1E-5 Composite (b) i 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 Release Principal Gamma SE-7 Tank i
Emitters (e)
I l-131 1E-6 P
Composite (b)
Gross Alpha 1E-7 g \\z12rt-a. doc 12 22
--.--.._.----.-~----_.~.-.---.--s.--
ZION Ravision 18
.Jinuity 1997 TABLE 12.3-2 TABLE NOTATIONS b
RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE b
(Cont'd) a.
' The LLD is the smallest concentration of radioactive matenal 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 =
4.68 g A E
- V a 2.22 Y + exp (-lat)
Where:
LLD is the lower limit of detection as defined above in picoCuries (pCi) per unit mass or
- volume, s,is the square root of the background counting rate or of the counting rate of a blank sample as appropnate (as counts per minute),
A is the number of gamma rays emitted per disintegration for gamma rey radionuclide aralysis (A = 1.0) for gross alpha, strontium, and tntium measurement.
E is the counting efficency (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 radioactrve decay constant for the particular radionuclide, and l
At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental sample).
The value of s used in the calculation of the LLD for a detecbon system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropnate) rather than on an unvenfied theoretically predicted variance. In calculating the LLD for a radionuclide determ:ned 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 one FWHM (FullWidth at Half Maximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radionuclide.
gv12ri-8 m 12-23
ZlON Rsvision 18 Januiry 1997 TABLE 12 3-2 TABLE NOTATIONS 1
RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE (Cont'd)
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 i
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 CQMPOSITE SAMPLE is one in which the quantity of liquid sampled is proportional to the i
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 l
t 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 l
batch discharged, and (2) a monthly record of radionuclides discharged (isotope and quantity)is maintained.
A BATCH RFL FASE is the discharge of liquid wastes of a discrete volume. Prior to sampling for c.
analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.
d.
A CONTINUOUS RFLFASE 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.
The principal gamma emitters for which the LLD specification applies exclusively are the following e.
radionuclides: Mn 54, Fe-59, Co-58, Co-60,2n-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 shifL e
~.
ZION Rev;sion 18 January 1997 1
m 12.3.2 Dose i
Ooerabihty 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 l
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 l
and to less than or equal to 5 mrem to any organ, and I
2.
During any calendar year to less than or equal to 3 mrem to the total body and to l
j less than or equal to 10 mrem to any organ.
Acolicability: At all times.
action I
1.
With the calculated dose from the release of radioactive materials in liquid 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 j
THE PUBLIC from all uranium fuel cycle sources is limited to less than or equal to j
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 from 1
q the Commission to permit releases which exceed the 40CFR Part 141 or 190
[d 4
Standard. The radiation exposure analysis shall use methods prescribed in the I
ODCM.
Surveillance Reauirements 12.3.2.B Cumulative dose contnbutions from liauid 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.
g-\\t12ri-8 doc j g.25
%d
~
~
ZION RT; vision 1.8 Jrnuiry 1997 Bases 12.3.2.C This Section is provided to implement the requirements of Sections ll.A. Ill.A and IV.A of Appendix 1,10CFR 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 1 to assure that the releases of radioactive materialin liquid effluents will be kept "As Low As is Reasonably Achievable". Also, for fresh water sites with dnnking 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 appropnate 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 materi&ls in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109; l
Calculation of Annual Doses to Man from Routine Releases of Radioactive Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix l, 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", Apnl 1977.
This Section applies to the release of liquid effluents from each unit at the site. For l
shared radwaste treatment systems, the liquid effluents from the shared systems are proportioned among the units sharing the system.
1 1
)
g \\zi2r1-8. doc 12-26
_ _ _. ~ _ _ _ _.. _ _ _. _. _. _ _ _. _. _ _ _ -.. - _ - -... _ _. _.. _ _. - _
ZION.
Revision 18
{
January 1997 f
,(
12.3.3 Liquid Radwaste Treatment System i
Ooerability Reauirements l
12.3 3.A The Liquid Radwaste Treatment System shall be OPERABLE.* The appropnate portions of the system shall be used to reduce the radioactive materials in liquid wastes pnor to their discharge when the projected dose due to liquid effluent releases from each unit to UNRESTRICTED AREAS (see Zion Station ODCM Annex, Appendix F. Figure F-1)
~
j would exceed 0.06 mrem to the total body or 0.20 to any organ in a 31 day penod.
f t
j
- The liquid Radweste Treatment Systeri shall be considered 1
OPERABLE, if liquid waste can be held up and/or discharged within applicable hmits.
i Aophcabihty At all times.
t Ij Achon 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 l
the above limits, retum the system to OPERABLE status and place the appropriate portions of the system in use.
i j.
Survamance R==irements i
i 12.3.3.B Doses due to liquid releases from the site to UNRESTRICTED AREAS, shall be projected j
at least once per 31 days in accordance with the methodologies and parameters of the ODCM when the Liquid Radweste Treatment System is not being fully utilized.
4 n==
12.3.3.C The OPERABILITY of the Liquid Radweste 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 radioachve materials in liquid effluents will be kept "As Low As is Reasonably Achievable". This Sechon implements the requirements of 10CFR Part 50.36a, General Design Criterion to of Appendix A to 10CFR Part 50 and the design objechve given in Sechon ll.D of Appendix i to 10CFR Part 50.
The specified limits goveming the use of appropnate porbons of the Liquid Radwaste Treatment System were specified as a 2% frachon of the dose design objectives set forth in Seebon ll.A of Appendix 1,10CFR Part 50, for liquid effluents.
j g \\r12ri-8. doc g
12-27 V
1
ZION Rsv: tion 18 Januiry 1997 12 4 GASEOUS EFFLUENTS 12.4.1 Dose Rate Ooeratina Recuirements 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 mremlyr to the skin, and
~
2.
For lodine-131, lodine-133, trrtium and all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem /yr to any organ.
Aeolicability: 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 presenbed 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.
B.aSes 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 wi3 be within the annual dose limrts of 10CFR Part 20.1301. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the 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 airbome releases, the stack is considered a ground level release.
e
ZION Rsvision 18 Januity 1997
+
TABLE 12.41 RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM
%-./
LOWER LIMIT MINIMUM TYPE OF OF
- GASEOUS RELEASE SAMPLING ANALYSIS ACTIVITY DETECTION TYPE FREQUENCY FREQUENCY ANALYSIS (LLD) Ci/cc A. Gas Decay Tank Grab Sample Prior to Prior to Each Noble Gases Each Release Release Pnncipal Gamma 1 E-4 l
Emitters (d)
- 8. Containment Vent Prior to Each Release Prior to Each Noble Gases 1 E-4 and Purge (a)
Release Phipl Qm Emitters (d)
Tritium 1E4 C. Continuous Grab (b)
Monthly Noble Gases 1 E-4 Principal Gamma Vent Stack for both Emitters (d)
(2) units Tritium 1 E-6 Continuous (b)
Weekly 1-131 1E-12 (Charcoal Sample) 1-133 1E.10 (Charcoal Sample)
Continuous (b)
Weekly (c)
Particulate 1E-11 Principal Gamma Emitters (d)
Composite Quarterly Sr-89 Particulate 1 E-11 Sr-90 Particulate 1E-11 Gross Alpha 1E-11 Continuous (f)
N.A.
Noble Gases, 1E-6 I
Noble Gas Monitor mma l
)
l g u12ri-8 doc 12-29
ZION R, vision 1.8 Jznutry 1997 TABLE 12.4-1 TABLE NOTATIONS RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM (Cont'd)
Should a shutdown, startup or power change greater than 50% occur which could alter the a.
mixture 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.
The particulate filter (s) shall be saved for a quarterly composite analysis for Sr-89 and Sr-90.
c.
d.
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 for gaseous emissions, and Mn-54, Fe-59, Co-60, Zn-65, Co-58, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. Other peaks which are measurable and identifiable by gamma-ray spectrometry, together with the above nuclides, shall 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.
e.
The LLD is def;ned in Notation a of Table 12.3-2.
f.
Refer to Table 12.2-3 for required actions when the noble gas rnonitor is not in service.
O e
l s
ZION Rsvtsion 18 JInuiry 1997 12.4.2 Dose - Noble Gases Ooerability Raouirements 12.4.2. A The air dose due to noble gases released in gaseous effluents from each unit to areas at l
or beyond the SITE BOUNDARY (see Zion Station ODCM Annex, Appendix F. Figure F-1) thall be limited to the following-1.
During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and 2.
During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
Acolicability: At all times Action 1.
With the calculated air dose from gaseous effluents exceeding the above limits, define the corrective action (s) to be taken to ensure that future i
i 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 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 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 fuel cycle sources (including all effluents pathways and direct
)
radiation) are less than the 40 CFR Part 190 Standard.
Surveillance Reauirements 1
12.4.2.B Cumulative dose contributions for the current calendar quarter and current calendar year l
for noble gases shall be determined in accordance with the methodologies and parameters of the ODCM at least once every 31 days.
1 I
gut 2rt-a. doc 12-31
ZION RIvision 18 Jinurry 1997 Bases 12.4.2. C This Section implements the requirements of Sections ll.B. Ill.A and IV.A of Appendix 1.
10CFR Part 50. The Operability Requirements implement the guides set forth in Section ll.B 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 ! to assure that the releases of radioactive materialin gaseous effluents will be kept "As Low As is Reasonably Achievable". The Surveillance Requirements implement the requirements in Section Ill.A of Appendix 1 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 4
_. _..--. _ _ m
_ _ _... _ _ _ _._,_m ZION Revision 1.8 J-' "
Janutry 1997 l
12.4.3 Dose - l-131,1 133, Tntium, and Radioactive Material in Particulate Form i
Onerabihtv Paa"i'amants i
t i
12.4.3.A '
The dose to a MEMBER OF THE PUBLIC from l-131,1-133, tntium, and all radionuclides i
in particulate form with half-lives greater than 8 day in gaseous effluents released from i
each unit to areas at or beyond the SITE BOUNDARY (see Zion Station ODCM Annex, l
i
' Appendix F, Figure F-1) shall be limited to the following:
4 j
1.
During any calendar quarter: Less than or equal to 7.5 mrem to any organ, and i
l t
j 2.
During any calendar year: Less than or equal to 15 mrom to any organ.
l Aoolicacihty At all times.
Action 5
t With the calculated dose from the release of lodine-131, lodine-133, tntium and i
all radionuclides in particulate form with half-lives greater than 8 days in gaseous
[
effluents exceeding twice the iimits of Section 12.4.3.A:
i i _
1.
Limit subsequent releases such that the dose or dose commitment to a l
MEMBER OF THE PUBLIC from all uranium fuel cycle sources to less than or equal to 25 mrom to the total body or organ (except the thyroid which is limited to less than or equal to 75 mrom) over 12 consecutive i
months.
I i
2.
Prepare an analysis which demonstrates that radiation exposures to all l
b MEMBERS OF THE PUBLIC from ali uranium fuel cycle sources V
(including all effluent pathways and direct radiation) are less than the 40CFR Part 190 Standard. Otherwise, request a variance from the Commission to permet release which exceeds the 40CFR Part 190 Standard. The radiation exposure analysis shall use the methods presenbod in the ODCM.
Sure :"mca Parui. a:-
12.4.3.B 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 greater than
.]
8 days shall be determined in accordance with the methodologies and parameters in the i
ODCM at least once per 31 days.
I
.l gv12ri-a doc C
12-33
ZION Rrvis"on 18 Jrnuary 1997 Bases 12.4.3 C This Section implements the requirements o" Sections ll.C, Ill.A arid IV.A of Appendix 1, 10CFR Part 50. The Operability Requirements are the guides set forth in Section ll.C 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 assures that the releFeis of radioactive materials in gaseous effluents will be kept "As Low As is Reasc,aably Achievable". The ODCM calcalation methods specified in the Survenilance Requirements implement the requirements in Section Ill.A of Appendix 1 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 appropnate pa"hways is unlikely to be substantially underestimated. The release rate specifications for radioiodines, radioactive materialin 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 development of these calculations are: 1) individual inha!ation of airbome radionuclider, 2) dispostion of radionuclides onto green leafy vegetat'on with subsequent consumption by raan, 3) deposition onto grassy areas where tralk animals and meat producing animals graze with consumption of the milk and meat by man.
O
,2 3,
ZION Rsvision 18
. ~.
Janutry 1997 12.4.4 Gaseous Radwaste Treatment System
(
Ooerabiltty Reauirements 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 releases of radioactivity 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.
0.2 mrad to air from gamma radiabon, or 2.
0 4 mrad to air from beta radiation, or 3.
0.3 mrem to any organ.
- The installed VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be considered OPERABLE by meetings Section 12.4.1, 12.4.2 and/or 12.4.3, as applicable Anchcabihty At all times.
Action With the Gaseous Radweste Treatment System inoperable for more than 30 days or with radioactive gaseous 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 Ramkaments 12.4.4.B Doses due to gaseous releases from each unit to areas at or beyond the SITE
- BOUNDARY shall be projected at least once per 31 days in accordance with the methodologes and parameters in the ODCM when the Gaseous Radwaste Treatment Systems are not being fully utilized.
Ranma 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 appropnate porbons of this system be used when specifed provides reasonable assurance that the releases of radioactive materials in gaseous efCuents will be kept "as low as is reasonably achievable". This section implements the requirement of 10CFR50.36a, General Design Cnterion 60 of Appendix A to 10CFR50 and the design objective given in Sechon ll.D of Appendix i to 10CFR50. The specifed limits goveming the use of appropnete portions of the Gaseous Radwaste Treatment System were specified as a 2% fracbon of the dose design objectives set forth in Section 11.B and ll.C of Appendix 1,10CFR50, for gaseous effluents.
g u12ri-8 doc 12-35
ZION Revision 1.8 January 1997 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Monttoring Program Ooerabilrty Reauirements 12.5.1.A The Radiological Environmental Monitoring Program shall be conducted as specified in Table 12.5-1.
Aoolicability: At all times.
A._,,ct.io_rt 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 desenption of the reasons for not conducting a program as required and the plans for preventing a recurrence.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction l
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 j
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 sampaing schedule shall be desenbed in the Annual Radiological Environmental Operating Report.
2.
With the level of radioactMty 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 to the Commission within 30 days a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to 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 art 1ual dose i
to a LIEMBER OF THE PUBLIC from all radionuclides is equal to or greater than i
the calendar year limits of Section 12.3 2,12.4.2, or 12.4.3. This report is not required if tne measured level of radioactMty was not the result of plant effluents; however, in such a event, the condition shall be reported and desenbod 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.
gv12r18 =
12-36
I 1
ZION Rcvision 18 Jrnuiry 1997 i
[
3.
If the sample type or sampling location (s) required by Table 12.5-1 become(s) permanently unavailable, identify suitable alternative sampling media for the i
pathway of interest and/or specific locat,ons for obtaining replacement samples and add them to the Radiological Environmental Monitonng Program as soon as l
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 j
including a revised figure (s) and table reflecting the new location (s) with 1
supporting information identifying tne cause of the unavailability of samples and justifying the selection of new location (s) for obtaining samples.
l Surveillance Raamraments 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 --
l capabilities required by Table 12.5-3.
12.5.1.C The Radiological Environmentai Monitoring Program required by this section provides representative measurements of radiation and of radioactive matenals in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This j
monitoring program implements Sechon IV.B.2 of Appendix l to 10CFR50 and thereby supplements the radiological effluent monitoring program by venfying that the measurable 1
f concentrabons of radioactive matenais and levels of radiation are not higher than i
expected on the basis of the effluent measurements and modeling of the environmental
]
exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective for at least 3 years of commercial operation.
Following this period, program changes may be initiated based on operational expenence.
The required detecten capabilities for environmental sample analyses are tabulated in terms of the lower limits of detecten (LLD). The LLDs required by Table 12.5-3 are considered optimum for routine environmental measurements in industrial laboratones. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement.
Detailed discussion of the LLD, and other detecten limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Cume LA., " Limits for Qualitative Detecbon and Quantitative Determination-Application to Radiochemistry," Anal. Cham 40.
586-93 (1968), and Gartwell, J.K., "Detecten Limits for Radioanalytical Counting
' Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
o u12r1.s e 12-37 k
l
ZION Revision 18 Janurry 1997
)
Interoretations 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 taken from river, takes, or reservoirs (not well water) which is used for drinking. Since Lake Michigan has no designated downstream or upstream direction, two dnnking water locations (one north /one south) within 10 kilometers shall be sampled as dnnking water indicator locations, and two other locations (one north /one south) beyond 10 kilometers shall be j
sampled as controllocations.
O'
,2 3, g
.~ -....
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O 1
.I ZION Revision 18 January 1997,
TABLE 12.5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i
EXPOSURE! PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND FREQUENCY OF AND/ OR SAMPLE AND SAMPLE LOCATIONS"'
FREQUENCY ANALYSIS
- 1. Arborne Samples from a total of eight locahons:
Continuous sampier operation Radiciodine Canister-Radiosodine and with particular sample collection 1-131 analysis bweekg on near field l
Partculates
- a. Indicator-Near Field weekly (or more frequently if and control samples 8
required due to dust loading), and Four samples from locations within 4 km (2.5 radioachve canister collection Partculate Samoler:
l mi)in different sectors.
beweekly Gross beta analysis following weekly i
filter change *and gamma isotopic
- b. Indicator-Far Field analysis
- quarterly on composite filters by location on near field Three additional locations within 4 to 10 km samples.*
[
(2.5 to 6.2 mi) in different sectors.
[
- c. Control One sample from a control location within 10 to 30 km (6.2 to 18.6 mi).
E t
L l
t h
L I
I L
g u12rt-8 doc 12-39
[
I
ZION Revison 18 January 1997 TABLE 12.5-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND FREQUENCY OF AND/ OR SAMPLE AND SAMPLE LOCATIONS"8 FREQUENCY ANALYSIS
- 2. Direct Radiabon"'
Forty routine monitoring stations either with a Quarterly Gamma dose on each TLD quarterly.
thermoluminescent dosimeter (TLD) or with one instrument for measunng dose rate continuously, placed as follows:
- a. Indcator-Inner Ring (100 Senes TLD)
One in each meteorological sector, in the general area of the SITE BOUNDARY 0.1 to 1.5 mi);
- b. Indicator-Outer Ring (200 Series TLD)
One in each meteorological sector, within 4.8 to 10 km (3.0 to 6.2 mi); and
- c. Other One at each Airbome location given in pcrt 1.a. and 1.b.
The balance of the TLDs to be placed at special interest locations beyond the Restricted Area where either a MEMBER OF THE PUBLIC or Commonwealth Edison employees have routine access.
{
(300 Series TLD)
- d. Control One at each Airbome controllocation given in part 1.c.
g v12r1-8 d*
12-40 O
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. -,.. ~ -.
. - -........ =.
[
t i
ZION Revision 18.'
.. January 1997 l TABLE 12.5-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l
EXPOSURG PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND FREQUENCY OF i
ANDIOR SAMPLE AND SAMPLE LOCATIONS"'
FREQUENCY ANALYSIS
- 3. Waterborne
- a. Drinking *8
- a. Indicator Weekly grab samples Gross beta and gamma isotopec i
analyses"' on monthly composite; One Sample from each community drinking trihum analysis on quarterly water supply that could be affected by the composite.
i stahon discharge within 10 km (6.2 mi) downstream of discharge
- b. Control
- a. Control Weekly grab samples Gross beta and gamma isotopic Sample *'
analyses") on monthly composite;
[
One sample upstream of discharge tntium analysis on quarterly composite.
- c. Sediment
- a. Indicator Semiannually.
Gamma isotopic analysis"'
semiannually.
At least one sample within 10 km (6.2 mi) of discharge i
a.In W
- d. Cooling Water Samples Weekly grab samples Gross beta analysis weekly; inhum i
- b. D=Je#
analysss on quarterly composite.
i t
5 a
i L
g \\z12rt.8 doc gg4j i
h
ZION Revision 18 January 199 TABLE 12.5-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND FREQUENCY OF AND/ OR SAMPLE AND SAMPLE LOCATIONS"'
FREQUENCY ANALYSIS
- 4. Ingestron
- a. Indicator Biweekly
- when animals are on Gamma isotopic'*3and 1-131* analysis pasture (May through October),
biweekly
- when animals are on pasture
- a. Milk'78 Samples from melking animals from a maximum of monthly at other times (November (May through October), monthly at other three locations within 10 km (6.2 mi) distance.
through April).
times (November through Apni).
- b. Control One sample from melking animals at a control location within 15 to 30 km (9.3 to 18.6 mi).
- b. Fish
- a. Indicator Two times annually.
Gamma isotopic analysis on edible portions.
Representative samples of commerdEJy and recreationally important speces in discharge area.
- b. Control Representative samples of commeroaily and recreationally important speces not infk:enced by plant discharge.
- c. Food Products
- a. Indicator Annually Gamma isotopic'*' analysis on each sample.
Two representative samples from the pnncipal food pathways grown in each of two major quadrants (over land) within 10 km (6.2 mi):
At least one root vegetable sample"*3 At least one broad leaf vegetable (or vegetatxm)"")
- b. Control Two representative samples sirrular to indcator samples grown within 15 to 30 km (9.3 to 18 6 rru).
g u12rt-8 doc 1M2 O
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- - -_.~ -. -.
-. -. -.. _ ~
t
. ZION Revision 18
[
January 1997 TABLE 12.5-1 (Continued)
. RADIOLOGICAL ENVIRONIENTAL ISONITORING PROGRARE TABLE NOTATIONS i
(1)
Specdc pei. / ;s of distance and owection from the centerkne of the medpoent of the two unsts and addehonal desenption where perhnent, shall be
[
provided for each and every sample Incahan in Table 1.1-1 of the ODCM Stabon Annexes. Refer to NUREG-0133," Preparation of Radiologecal Effluent Technscal Speedcahons for Nuclear Power Plants," October 1978, and to Radiologscal Assessment Branch Technical Posshon, Revision 1 November 1979.
(2)
Far field samples are analyzed when the respechve near field sample results are inconsistent with previous measurements and radioachvity is j
confirmed as having its origin in awbome elRuents from the station, or at the descrebon of the Rathahnn Protechon Director.
l (3)
Arbome particulate sample filters shah be analyzed for gross beta radioachwity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after samphng to allow for radon and thoron f
daughter decay if gross beta achwity in air perhenamaa samples is greater than 10 times the yearly mean of control samples, gamma isotopec l
analysis shall be performed on the indudual samples l
(4)
Gamma sootopec analysis means the idenhficahon and quantificahon of gamma emstbng radionuchdes that may be attnbutable to the effluents from I
the stabon.
(5)-
One or more instruments, such as a pressunzed ion chamber, for measunng and recording dose rate continuously may be used in place of, or in addebon to, integrahng dosameters Film badges shah not be used as doswneters for measunng dwect radiahon The 40 locations is not an absolute j
number The number of direct radiahon monstonng stabons may be reduced accui&q to geographecal lwnstations; e g, if a stabon is adpacent to a lake (i e. Zion), some sectors may be over water thereby reducing the number of dosaneters which could be placed at the indicated destances The.
frequency of analysis or readout for TLD systems will depend upon the charactensbcs of the specific system used and should be selected to obtaen
[
ophmum dose informahon with mwwnal fading (6) ~
Refer to Sechon 12.5.1.D for interpretabon on the apphcabshty of " downstream" and
- upstream
- If no communsty dnnking water supply exists l
within 6.2 miles of the discharge, surface water sarnphng shall be performed j
i (7)
If milking animals are not found in the desagnated indicator locahons, or the owners dechne to parbespate in the REMP, all melk samphng may be I
disconhnued l
l (8)
Biweekly refers to every two weeks.
j
?
(9) 1-131 analysis means the analyhcal separation and counting procedure are specific for this radionuclide.
j (10)
One sample shall consist of a volume / weight of sample large enough to fiH contractor specified container.
i l
g u12r1-8 m jp_43 t
~.
ZION Revison 1.8 January 1997 TABLE 12.5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES
- WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS ANALYSIS (pCill)
OR GASES (pCi/m*)
(pCi/kg, wet)
(pCi/I)
(pCi/kg, wet)
H-3 20,000"'
Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co40 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2*
0.9 3
100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 (1)
For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/l rnay be used (2)
If no drinking water pathway exists, a value of 20 pCill may be used.
- This table contains reporting levels for analyses beyond the requirements of Table 12.5-1.
g u t2r14 e 12-44 O
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ZION Revison 1.8 January 1997 TABLE 12.5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS"3 LOWER LIMIT OF DETECTION (LLD)*'8 AIRBORNE FOOD WATER PARTICULATE FISH MILK PRODUCTS SEDIMENT ANALYSIS (pCi/I)
OR GASES (pCi/m')
(pCi/kg, wet)
(pCi/l)
(pCi/kg. wet)
(pCAg, dry)
Gross Beta 4
0.01 1000 H-3 200 Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn45 30 260 Zr-Nb-95 15 l-131(6) 1/15"'
O.07 100 0.5/5"'
60 Cs-134 15 0.01 100 15 60 150 Cs-137 18 0.01 100 18 80 180 Ba-La-140 15 15 i
i g V12r14 doc 12-45
ZION Revision i 8 Janusry 1997 TA LE 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 S, + 3/t.
LLD =
(E)(V)(2.22)(Y) (exp (-ut))
4.66 S.
LLD -
(E)(V) (2.22) (Y)(exp (-Mt))
Where: 4.66 S n 3/t, LLD = the "a priori" Lower Limit of Detection (picoCuries per unit mass or volume),
s,
= the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate (counts per minute),
5taICounts t6
=
E
= the counting efficiency (counts per disintegration),
V
= the sample size (units of mass or volume),
,2.22 = the number of disintegrations per minute per picocurie, Y
= the fractional radiochemical yield, when applicable, A,
= the radioactive decay constant for the particular radionuclide (sec"),
t.
= counting time of the background or blank (minutes), and g \\z12r1-8 doc jg.4g
ZION Rsvis:on 18 Jtnuiry 1997 TABLE 12.5-3 (Continued)
DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS Q
TABLE NOTA flONS U
At = the elapsed time between sample collection, or end of the sample collection penod, and the time of counting (sec).
Typical values of E, V, Y, and At should be used in the calculation.
4 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 e
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 l
may render these LLDs unachievable. In such cases, the contnbuting factors shall be j
identified and described in the Annual Radiological Environmental Operating Report.
l (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 pCi/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.
r 9
g u12rt-e doc 12-47 f
ZION Revision 18 s,
Januiry 1997 12.5.2 LAND USE CENSUS Ooerability Reauirements 12.5.2.A A Land Use Census shall be conducted and shallidentify within a distance of 10 km (6 2 mi) the location, in each of the following meteorological sectors, A, J K, 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.
Aeolicability: At all times.
Action 1,
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 monitorir.; 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 locahon(s) with information supporting the change in sampling locations.
The nearest industrial facility shall also be documented if closer than the nearest residence.
Surveillance Raouirements 12.5.2.8 The Land 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 l
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.
This census satisfies the requirements of Section IV.B.3 of Appendix i 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.
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ZION Revision 18 e #
Janu:ry 1997 12.5.3 INTERLABORATORY COMPARISON PROGRAM Ooerability Reauirements l
12.5.3. A Analyses shall be performed on radioactive materials supplied as part of an interfaboratory companson program that correspond to samples required by Table 12.5.1.
Anolicabiktv: 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 Operatirig Report.
i Surveillance Reauirements 12.5.3.8 A summary of the results obtained as part of the above required interlaboratory comparison program shall be included in the Annual Radiologul Environmental Operating Report.
Bases 12.5.3.C The requirement for participation in an interlaboraiory comparison program 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 Sechon IV.B.2 of Appendix 1 to 10 CFR Part 50.
O 1
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I
ZION Rtvision 10 e
Jrnuary 1997 12.6 REPORTING REQUIREMENTS 12.6.1 Annual Radiolooical Environmental Ooeratina Recort*
Routine Annual Radiological Environmental Operating Report covenng the operation of the Unit (s) dunng the previous calendar year shall be submitted prior to May 15 of each year. The Annual Radiological Environmental Operating Report shallinclude summanes, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including, as found appropriate, a companson of preoperational studies with operational controls or with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.
The Annual Radiological Environmental Operating Report shallinclude the results of all 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 summanzed and tabulated results of these analyses and measurements in the format of the table in the Radiological 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 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 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 sample measurements that exceed the reporting levels of Table 12.5-2 but are not the result of plant effluents; discussion of all analyses in which the LLD required by Table 12.5-3 was not achievable; results of the Land Use Census required by Section 12.5.2; and the results of licensee participation in an intertaboratory 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, atmosphenc stability, and precipitation (if measured), or in the form of joint frequency distnbutions 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.
A single submittal may be made for a multiple unit station.
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v ZION Revision 1.8 l
January 1997 l-i i
The Annual Radiological Environmental Operating Report shtll also include an assessment of I
the radiation doses due to the radioactive liquid and gaseous effluents released from the Unit or Station dunng the previous calendar year. This report shall also include an assessment of i
radiation doses to the most likely exposed MEMBER OF THE PUBLIC from reactor releases i'
and other nearby uranium fuel cycle sources, including doses from primary effluent pathways i
and direct radiation, for the previous calendar year. The acsessment of radiation doses shall l
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 Radiametive Effluent R-'---- Renort" l
Routine Annual Radioactive Effluent Release Reports covering the operation of the unit during I
the previous calendar year of operation shall be submitted no longer than 12 months since the j.
previous report pursuant to 10CFR50.36a.
1-The Annual Radioactive Effluent Release Reports shallinclude a summary of the quantities of radioactive liquid and gaseous affluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, *Mossunng, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materialin Liquid and Gaseous Effluent from Light-Water-Cooled i
Nuclear Power Plants," Revision 1, June 1974, with data sumfr.arized on a quarterly basis l
l following the format of Appendix B thereof i
j The Annual Radioactive Effluent Release Report shall include a list and description of j
unplanned releases of radioactive matonalin liquid effluents from the site to UNRESTRICTED AREAS and of unplanned releases of radioactive matenal in gaseous effluents from the site to j
i areas at or beyond the SITE BOUNDARY dunng the reporting penod 1
The Annual Radioactive Effluent Release Report shall include any changes made during the j
reporting period to the Process Control Program as well as any major changes to Liquid,
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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, I
respectively; and description of the events leading to liquid holdup tanks or gas storage
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tanks exceeding the limits of Technical S mc4.c.nen 3.11 (ITS 5.5.10) or 3.12 (ITS 5.5.10),
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4 "A single submittal may be made for a multiple unit station. The submittal should combine those sections -
that are comrnon to all units at the station; however, for units with separate radweste systems, the l
submittal shall specify the releases of radioactive material from each unit.
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ZION Revision 1 B Janutry 1997
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12.6.3 Offsite Dose Calculation Manual (ODCM) 9 12.6.3.1 Changes to the ODCM.
a Shall be documented and records of reviews performed shall be retained as 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 anahses 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 i 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.
c.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shallindicate the date (e.g.,
month / year) the change was implemented.
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_.m ZION Ravision 18 j g JInuary 1997 12.6.4 Maior Chanaan to Liouid and C==us Radwaste Treatment Svstems*"
Licensee-instiated major changes to the Radwaste Treatment Systems (liquid and gaseous).
a.
Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation -
was reviewed by the Onsite Review and investigative Function.
The discussion of each change shall contain:
1)
A summary of the evaluation that led to the i
determination that the change could be made in
- accordance with 10 CFR 50.59;
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2)
Sufficient detailed informaton to totally support the reason for the change without benefit of additional and supplementalinformation; 3)
A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems.
i 4)
An evaluation of the change which shows the predicted releases of radioactive matenals in liquid and gaseous j
- effluents that differ from those previously pred' ted in the c
License application and amendments thereto; 5)
An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC and to the general population that differ from those previously
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estimated in the License application and amendments thereto; A
6)
A comparison of the predicted releases of radioactive matenais, in liquid and gaseous effluents, to the actual releases for the penod 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 8)
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.
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