ML20207C287
| ML20207C287 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 11/11/1998 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20207C270 | List: |
| References | |
| PROC-981111-01, PROC-981111-1, NUDOCS 9903080439 | |
| Download: ML20207C287 (75) | |
Text
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( LA CROSSE BOILING WATER REACTOR (LACBWR) i OFFSITE DOSE CALCULATION MANUAL i Prepared by: . A # 99~ Health Physics Review: li '/ /77 0 '/ H' Date ' Quality Assurance Review: MM-f /rJ*f[ Date ORC Approved: I/M #4 k /////[ff' [ Dste ' l l October 1998 Revision 5 l l I l s* Dairyland Power Cooperative h 3200 East Avenue South La Crosse, WI 54602-0817 9903000439 990219 PDR ADOCK 05000409 R PDR f-
B l 5 i Safety Analysis in Accordance with Decommissionina Plan and' Technical Specifications: 1 (1) Will the probability of occurrence or the consequences of an accident or \ malfunction of equipment important to safety previously evaluated eitherin 'l the Decommissioning Plan or FSAR be increased? NO Justification For Answer: ,
.The changes to the ODCM are administrative in nature and do not change i the intent, nor the requirements, of the ODCM.- The probability of i occurrence or the consequences of an accident or malfunction of equipment ;
necessary for SAFSTOR is not increased. Changes are as follows: l a). Table of Contents. Daae 1 insert section 3.4.which was inadvertently
- left out of Rev. 4 (identified in Audit 02-97-01, Open item C).
I b) Paoe 3 - add a definition for MPC as it applies to use at LACBWR. j c) Flaure 2.1 (oaae 9). Fiaure 2.4 (paae 23). and Table 2.1 (paae 25) - moved location in ODCM. Also removed short-lived isotopes no longer present at LACBWR due to SAFSTOR. d) Paoe 40 - change all monthly sampling and ana!ysis requirements for waste water to each discharge. Due to reduced liquid waste generation because of SAFSTOR, LACBWR does not require a monthly discharge of waste. e) Paoes 43 & 44 - remove reference to the Turbine Condenser monitor. Liquid waste discharges are not made if the Radwaste line monitoris not in service. The condenser monitor serves no function during SAFSTOR conditions.
-f) Table 3.3. pace 47 - change the minimum analysis frequency of the stack effluent gross alpha analyses from a quarterly composite to a weekly filter ' analysis, as is being done, to provide better alpha data.
f) Paae 49 - word correction: change particle to particulate (identified in j Audit C2-97-01, Open Item C). ; h) Paaes 1.6.8.10.12.13.14.15.16.17.19.20.21.24.26.27.28. !
- 29. 32, 36. 38. 42.45. 48.49. 50. 51. 57 - grammar corrections or format adjustments.
Note: ~ pages 60-69 are included only because of page renumbering. ODCM 1 of 2. Rev.5
- 4. . - . . _ - _ . - _ _ . _ _ _ . . _ _ . _ _ ._. __ _ . _ _ _ _ . . _ . _ . . _
I o l I Safety Analysis in Accordance with Decommissionino Plan and Technical Specifications: l i (2) is there a possibility of an accident or malfunction of a different type than l previously evaluated in the Decommissioning Plan or FSAR being created? NO Justification For Answer: These changes are administrative in nature and will not change the requirements of the ODCM. No new accident or malfunction will be created. (3) Is the margin of safety as defined in the Bases for any Technical Specifications reduced? NO Justification For Answer: The changes to the ODCM are administrative in nature only. All present requirements are being maintained. No margin of safety will be reduced. l 1 1 (4) Will the proposed change result in a significant environmentalimpact not i previously evaluated in the Environmental Assessment in support of the i August 7,1991, Decommissioning Order or the Final Environmental j Statement (FES) related to operation of LACBWR, dated April 21,1980 ' (NUREG-0191)? NO Justification For Answer: This is only an administrative change to an existing document. No requirement is reduced; no environmental impact will occur from this i change. l I ODCM 2 of 2 Rev.5
l TABLE OF CONTENTS O('__ j 1. I NTR O D U CTI O N . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . 1 O
- -1.1 P u rpo se . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 15 1.2 Definition s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 E
o. g 2. OFFSITE DOSE CALCULATIONS E o o 2.1 Compliance with the Limitations for Liquid Effluent Releases . . . . . . . . . 6
.h 2.2 Compliance with the Limitations for Gaseous Effluent Releases . . . . . . 13
% s-5 (
E e 3. RADIOACTIVE EFFLUENT CONTROL PROGRAM o b 3.1 Program Requirements . . . . . . . . . . .. .... .... . . ..... ........ 38 3.2 Liquid Effluents . . . . . . . . . . . . . . . 39 h .. .... . . .. . ...... . ... . 39 i ? 3.2.1 Sampling and Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . U 3.2.2 Liquid Effluent Release Limitation ................... ....... 41 T g_ _ 3.2.3 Liquid Effluent Instrumentation . . . . . . . . . ................. 43 s 3.3 Gaseous Eff!uents ............... ... ...... ...... ... ........... 46 : F[i ' s, 3.3.1 Containment Building Ventilation . . . . . . . . . . . . ... ... .. ... 46 46 g 3.3.2 Stack Effluent Sampling and Analyses . . . . . . . . . . . . .. ..... 3.3.3 Stack Effluent Release Limitation .. .. ........ .. ....... 48 : g a.% 3.3.4 Instrumentation ....... ..... .. ..... . ...... ... . .. 53 E 2 3.4 Total Dose to a Member of the Public .. ... .. ......... .... 57
% r . l e 4. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM e
2 e o E 4.1 Program Requirements . .. . . .. . .. . 60 5 4.2 REMP Description . . . . . . . . . . . . . . . . . . . ... . . ... 61
'8 z
- o 64
$ 63 4.3 REMP Lower Limits of Detection . . . .. . .........
5 yl 4.3.1 Calculation of Lower Limits of Detection .... .......... .. .... 65 O , e a 4.4 Interlaboratory Comparison Program ... . . . . 67 p1 a
' g b> 4.5 Reporting Requirements . .. . . . . . . .... . . .. 67 ODCM i Rev. 5
TABLE OF CONTENTS -(cont'd) h LIST OF TABLES ]
$1 o
I Q ! t 2.1. Infant Dose Factors P a(Inhalation) for H-3 and Particulate 1 F> Gaseous Release Monitor Alarm Setpoint Determinations . . . . . . . . . . . . . . 25 1
- j. 3.1 Radioactive Liquid Waste Sampling and Analysis Requirements l E for Batch Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40 1 0
D , 1 3.2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance l
$ Requirements .. . ................ ........ .............. .... ....... 44 E 3.3 Radioactive Gaseous Waste Sampling and Analysis . . . . . . . . . . . . . . . . . . . . 47 l 1
b
.@ ? 3.4 Rad' ioactive Gaseous Effluent Monit$ ring Instrumentation . . . . . . . . . . . . . . . . 55 O
~r.
I "
- 3.5 Radioactive Gaseous Effluent Monitoring lastrumentation Surveillance g ,
Requirements ... ........ .. ............. ...................... .. 56 , s; 1 S .
.!>A 4.1 Radiological Environmental Monitoring Program . . . . . . . . . . . . . . . . . . . . . . 62 h 4.2 Environmental Sample Analyses Lower Limits Values (LLD) ........... . 66 I' '
4
. 4.3 Reporting Levels for Radioactivity Concentrations in Environmental Q $ S a m p l e s . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . ....... 69 E
l I E z
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i; $ l e m B Z
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a ! 5
- W l l
ODCM ii Rev.5
._ - -- - . . .~ ..
TABLE OF CONTENTS -(cont'd) i /D kl LIST OF FIGURES y o lii (x 2.1 0 9 Liquid Release Monitor Alai.m Setpoint Determination .. ... ... . ...... 9 _ } a .. 2.2 Noble Gas (Kr-85) Release Monitor Alarm Setpoint Calculations ..... ... 17 l 1 I l E f E ,
~2.3 Noble Gas (Kr-85) Release Monitor Alarm Setpoint Summary ......... . 18 l o .$ i 8 2.4 H-3 and Particulate Gaseous Release Monitor Alarm Setpoint l j\ Determin a tion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . 23 eU o
ik 2.5 H-3 end Padiculate Gaseous Release Monitor Alarm Setpoint Summary 24 i i 1 b y y 2.6 Air Dose Commitment to a Member of the Public from Noble Gas O y (Kr-85) Release . . . . . . . . . . . . . . . . . . . . . . . . .. ..... . . .... 28 m- 1 ( i l E N
's !
E ; E LIST OF DIAGRAMS , k% a -
\
si ? j j 1.1 5 : Site Map, including Effluent Release Boundary . .. ... . ...... ..... q- . se e o
- 5 E
E z
.Y.! O m 3 E
w g z 1 a "! O_!5_ ODCM iii Rev,5
i b'
- 4
1.0 INTRODUCTION
1 1 O , t 1.1 Purpose (,/ The OFFSITE DOSE CALCULATION MANUAL (ODCM) contains the 5 I methodology and parameters used in (1) the calculation of offsite doses resulting from : g O I
$ radioactive gaseous and liquid effluents from LACBWR, and (2) the calculation of EN
$ ' gaseous and liquid effluent monitoring Alarm / Trip Setpoints. The ODCM also contains e I j b the Radioactive Effluent Controls and Radiological Environmental Monitoring Ek H_' ' Programs.
b
- i >
o T
- 1.2 Definitions p
b 5 I y N CHANNEL CAllBRATION E h j , A CHANNEL CAllBRATION shall be the adjustment, as necessary, of the I ' i channel output such that it responds with the necessary range and accuracy to known ii E J values of the parameter which the channel monitors. The CHANNEL CALIBRATION C shall encompass the entire channel including the sensor and alarm and/or trip , 2 e o { functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL h- CAllBRATION may be performed by any series of sequential, overlapping or total 3 2 . y@ channel steps such that the entire channel is calibrated. E id b ? E d BE n a 5 U ODCM 1 Rev.5
o, () , CHANNEL CHECK
\
g : A CHANNEL CHECK shall be the qualitative assessment of channel behavior
}
--S during operation by observation. This determination shall include, where possible, y :
e d comparison of the channel indication and/or status with other indications and/or status g g derived from independent instrument channels measuring the same parameter. 0.
*s E CHANNEL _ FUNCTIONAL TEST ii*
c fb A CHANNEL FUNCTIONAL TEST shall be: oEk
~{D T
- a. Analog channels - the injection of a simulated signal into the channel as 8 y closc to the sensor as practicable to verify OPERABILITY including alarm nnd/or trip functions and channel failure trips.
c b. Bistable channels - the injectivo of a real or simulated signal into the
>. sensor to verify OPERABILITY including alarm and/or trip functions.
E
- I , EFFLUENT F RELEASE '_50UNDARY g
a c l The Dairyland Power Cooperative property line within the 1109 ft. (338m) radius l _E EXCLUSION AREA is the EFFLUENT RELEASE BOUNDARY. (See Diagram 1.1.) l E ! E z i 8 5 Gi 8 Z . E a$ e m e 7 $
'v--
ODCM 2 Rev.5
EXCLUSION AREA ft The EXCLUSION AREA is defined as the area within an 1109 ft. (338m) radius Q ,
- frorn the centerline of the Containment Building. This was the area established per j
_s ' [
< J
)
10 CFR 100 as the EXCLUSION AREA for plant siting and operation, d. j MAXIMUM PERMITTED CONCENTRATION (MPC) E l 5 E The limiting liquid effluent concentration value 10 CFR 20, Appendix B, Table 2, E : jh Column 2. Ek o - MEMBER OF THE PUBLIC 2 W 8 4 L MEMBER OF THE PUBLIC shall mean an individual in a CONTROLLED or O __2 V UNRESTRICTED AREA. .However, an individual is not a MEMBER OF THE PUBLIC. f e N
% during any period in which the individual receives an occupational dose.
8 1% ; i
$ OPERABLE-OPERABILITY l'
E a I , , , A system, subsystem, train, component or device shall be OPERABLE or have s E OPERABILITY when it is capable of performing its specified function (s) and when all ; 5 E )
" )
necessary attendant instrumentation, controls, a normal or an emergency electrical I cii Power source, cooling or seal water, lubrication or other auxiliary equipment that are l j z 8 l s's d required for the system, subsystem, train, component or device to perform its g z ;
] d function (s) are also capable of performing their related support function (s). l E
/~'T I @$ V i ODCM 3 Rev.5 i
r\ U __ SOURCE CHECK
~ A SOURCE CHECK shall be the qualitative assessment of channel response h .
t whdn'the channel sensor is exposed to a radioactive source. k , d o5 i M E a ( ' f! o1N L
$ T T
em = Le R
! 8 t
j 1 5= , E . s E o E n
\
E l 3z s8 ea is Z . E a!
- Oil l l' ODCM 4 Rev.5 f
l l
I I A-
'q ) Diagram 1.1 g
g SITE MAP INCLUDING EFFLUENT RELEASE BOUNDARY
~
j - , , W v o rMETEOROLOGICAL TOWER i
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! N . ' RELEASE < Mt.nouto EFFLUEtit DL5cstActc.E ad ',, \
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l ! l 1 l 2.0 OFFSITE DOSE CALCULATIONS E l o ' 2.1, Compliance with the Limitations for Llauld Effluent Releases 5 g/ a) To assure compliance with the limitations of Section 3.2.2.a, Radioactive Effluent g Control Program (RECP), the radioactivity monitor alarm setpoint is calculated for the 5 y monitor as a function of the maximum effluent flow rate and the minimum dilution flow .
.e
$ rate. The following equation is used to calculate setpoints:
E i e - e O ' af
' I')
i
% k( F + f )
e b b where: 1 e- 5 C = the effluent concentration limit implementing 10 CFR 20 for
.f g
)
s LACBWR, in pCi/ml.
. a = the setpoint (in CPS above background) of the radioactivity monitor n
y measuring the radioactivity concentration in the effluent line prior to i i 8 I * . dilution and subsequent release; the setpoint, which is inversely proportional to the volumetric flow of the effluent line (f) and l 0 proportional to the volumetric flow of the dilution stream plus the l 5 di effluent stream (F + f), represents a value which, if exceeded, could l 1B z
- j. f, $ result in concentrations exceeding the limits of 10 CFR 20.
i e w i 15 Z u a
$ g k = the conversion factor, cps per pCi/mt, for the liquid waste effluent a e
(
-s 5 monitor based upon most recent calibration of the monitor.
V I ODCM 6 Rev.5 l i I
4 f = the effluent line volumetric flow setpoint as measured at the radiation O__ k . monitor location, in gallons per minute. l w . O' __ F = the dilution stream (LACBWR & Genoa Station No. 3 [G-3] E , Condenser Cooling Water) volumetric fi w b gallons per minute. ] {/ l E 5") Since f << F, Equation 2.1 is satisfied when the following discharge line radioactivity 0-monitor setpoint is met: I
.h e -
a s; (2.2)
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LA
$ i Calculation of Instantaneous Allowable Release Rates U
T n V LACBWR's liquid radwaste is released in batches. In order to assess the E-
'5 L required radioactive liquid effluent line monitor setpoint, a, the following step-by-step a:
i 8" 3 %. method for obtaining data will be performed. The form presented in Figure 2.1 may be
$ 4 g i used as a worksheet for these calculations. The alarm setpoint calculation may be l 2
[ performed on an annual basis if the setpoint is determined to be sufficiently i conservative so as to prevent exceeding 0.5 MPC at the discharge point where MPC is w E the isotope weighted effluent concentration release limit for a typical LACBWR waste 5 batch based on 10CFR20, appendix B, Table 2, Col. 2 values.
!: 8s jE 1. Go to Figure 2.1 Enter the date on the form.
3 a$ d is r ODCM 7 Rev.5
) 2. Enter the concentration C, (pCi/ml) for each isotope i, in a typical LACBWR waste batch.
5 ' O
~ ' 3. .The values of f and F are determined and recorded at the top of
} i Figure 2.1. F is the minimum volumetric dilution flow rate during releases j
{ J ( p at the LACBWR - G-3 outfall which is equal to the LACBWR condenser 5
" cooling water flow rate plus the G-3 condenser cooling water volumetric j 4
j g( flow, in gallons per minute.- The value f is the maximum radioactive liquid b release flow rate (GPM) for the batches discharged during the period. A R o , _ value of 17 GPM is normally specified for f. b g O { g
- 4. The quantities I C,, and I C,/MPC, are determined and recorded.
1 O k The monitor conversion factor, k, determined at last primery calibration is V 5.
]
g s 3 s recorded on Figure 2.1, in cps (net) per pCi/ml.
' I 24 8 ,
} 6. The alarm setpoint, a (cps), with a 0.5 factor for conservatism, for the n- ,
$ monitor measuring radioactivity in the liquid effluent line is then !
$ s .
l determined by e R $ 0.5 kF ICi ('} 5 "fICi /MPC 3 8
- S
$ E d
18 5h Oe5 ODCM 8 Rev.5
1 l \ Figure 2.1 Q g, LIQUID RELEASE MONITOR O ALARM SETPOINT DETERMINATION
-, Date e
E Maximum Liquid Release Rate for Period, f= GPM
<, $i g Minimum Dilution Flow Rate for Period, F= GPM ,
5 o f4 y (T
- Nuclide 1 '
Average.Concentra-tion (in Tanks),L.
. MPCi (10 CFR Part 20,; Appendix B , C,/MPC,-
g C,(pCi/ml) ' . Table 2; Col. 2): E Co-60 3 E-06 I E Cs-137 1 E-06 Cs-134 9 E-07 l 0 ki Sr-90 5 E-07 d 1 E-04
>L
~
Fe-55 ; { F-
$ h Ici = IC
/MPCi =
! gbt
.L3 n -
f g Monitor Conversion Factor, k = I cps (net) s
- pCi/ml n $ cps above background o -
M a s 0.5 kF I C,
- I-m
<aiarm et ,,nt) f IC /MPCi i .
l?> z s8 IN 1 uaE g!5 _ ODCM 9 Rev.5
1 i Os i To demonstrate compliance with the limitations of Section 3.2.2.b, dose j v)_ _ b)
% 1 g T contributions are calculated at a maximum interval of once every calendar quarter for l 1
8 {q all radionuclides identified in liquid effluents released to unrestricted areas using the
._y methodology presented in NRC Regulatory Guide 1.109, Rev.1, October 1977. This ci j-(E methodology takes the form of the following general equation:
5 l 0 D,, = I(A,a $ Cij/Fj) (2.4) i i P1 B. '
?
e i 1 12 where.
.e w
h D. , = the cumulative dose commitment to the total body or any organ l l t of an individual in age group a, from the liquid effluents released
, h' E
Q in m batches, in mrem. Y ! n R %/ g N Cu = the total quantity of radionuclide i, released by batch j, in Ci. 5 0 , m-
,g A,8 = the site-related ingestion dose commitment factor to the total body l g \
g a z or any organ i of an individual in age group a, for each identified I s , principal gamma and/or beta emitter, in mrem-gal-min"-Cid g l F3 = the average dilution water flow rate during batch release j in E __ gallons / minute. E 1B z ie 8a Equation 2.4 requires the use of a dose factor A i, for each nuclide, organ and
$ E a v
e >- g g individual in age group a, which includes the factors which determine the ultimate dose p g $ (_) ODCM 10 Rev.5
h _ _ received such'ss pathway transfer factors (e.g., bioaccumulation factors), pathway
. lasage factors, ingestion dose factors and dilution factors. The following philosophy 3
and site-specific conditions determine the site-specific factors incorporated into the - liquid effluent dose calculation model: g 1. Liauid Dose Pathways 5 . S .Due to LACBWR's status as a fresh water site, there is no invertebrate pathway. The drinking water pathway is not included, since the nearest community which obtains its drinking water supply from the Mississippi River is h located at Davenport, Iowa, which is 195 miles downstream. The drinking water pathway represents < 0.01% of the dose to any organ. The irrigated foods
=- pathway is not included since the river water is not used for irrigation in this area C and the shoreline deposits pathway is insignificant for the Mississippi River. The
, p
] y -
only significant dose pathway is the dose commitment due to ingestion of fish C from the Mississippi River waters. O j h ' 2. Dilution
$k The liquid effluent flow from the waste tanks is diluted by the combined p - . total circulating water flow for condenser cooling at both LACBWR and G-3, For y offsite dose calculations, no dilution by the Mississippi River flow is considered.
j Also, under SAFSTOR conditions batch discharges of liquid effluent normally take place durir.g less than 35 hours per month (< 5% of the time). Therefore,
=- no fish in the river are continuously exposed to a radioactive environment 1
j . produced by LACBWR liquid effluent as assumed in the calculation of the _[ published bioaccumulation factors for fish. 5 2 z Based on the above site-specific criteria, the dose factor A,3 is defined as
.E o C $ follows:
a: m B z j A,3 = K, (UF,)(BF,)(DF, ). (2.5) E O 12
'ODCM' 11 .Rev.5 L
i fl where: w)_
? K, = a units conversion constant,5.03 E5 =
f a (1 E12 pCi/Ci x .2642 gall () / (8760 hrs /yr x 60 min /hr).
} '
[ UF, = fish consumption usage factor for an individual in age group a,, in kglyr.
}l s
a BF, = the bioaccumulation factor in fish for nuclide i, in pCi/kg per pCi/t.
~E E DF,3 = the ingestion dose factor for age group a, for nuclide i, in organ t in j b mrem /pCI. '
1% ; i Calculation of Dose Commitments from Liauid Effluents I L 5 Y O k The equations for this calculation have been formatted on a computer-based l F . s spreadsheet. ' The values of UF,, BF,, and DF,3 specified in NRC Regulatory Guide 1 1.109 Rev.1, October 1977, and the constant K, have' been entered on the [ l spreadsheet. s E y g , To perform the calculation the following information is entered in the appropriate __ cells of the spreadsheet for each liquid batch released during the period of interest:
$ h E 1. Date g 2. Release interval, hrs
]$ 3. Waste volume, gal
$- $ 4. Condenser cooling water flow rate, GPM z
- 5. Activity concentration of each isotope, i, in waste, pCi/ml.
{ _i E$ i $$ ODCM 12 Rev. 5
j_ The spreadsheet program will then calculate and display the total quarterly dose n in mrem to the total body and each organ of an individual in each age group. The
, b L y cumulative calendar year doses and the percentage of the limits set forth in g Section 3.2.2.b are also calculated. This spreadsheet will also print the data tables for J < ,
the liquid effluent section of the annual report. E i I O
.! 2.2 Compliance with the Limitations for Gaseous Effluent Releases )
E . , cr.' j g a) To assure compliance with the limitations of Section 3.3.3.a, alarm setpoints are o kk - established for the gaseous effluent monitor. These setpoints are calculated or j 1 checked annually, or as required by procedure, to confirm that the current setpoints are i n N set correctly for one- or two-stack blower operation.
$ k' J
p ! During SAFSTOR, the offgas treatment system from the condenser to the stack g 5 6! D is no longer in operation since the plant is shut down. The principal potential gaseous ._ .0 ! } ' release pathway is from the Containment Building ventilation exhaust system. The only
- a. ,
. $ noble gas potentially available for release from the facility is Kr-85. The irradiated fuel
$ r .
assemblies stored in the Fuel Element Storage Well(FESW) contain essentially all ; i c E the Kr-85 inventory. There is a very small potential for a Kr-85 release from the Waste I 4 y S l Treatment and Turbine Building ventilation exhaust systems. This would be possible
&Y only if FESW water containing Kr-85 were transferred to the Spent Resin Receiving
?z o
.m
$ $ Tank (SRRT) or the Waste Water Tanks (WWT). Activity in particulate form and H-3 0 Z can theoretically be released via any of these release pathways. There will be no E{
]
e O v
? 5 ODCM 13 Rev. 5 E
-() radiciodine (1-131,1-133) releases since they are no longer being produced and, since shutdown, any residual activity has decayed to insignificant levels.
n W Notile cases v The following mathematical relationships shall be used to implement the above k 5 l g requirements for noble gas (Kr-85) release alarm setpoints:
$ .T gh D = K Q (X/Q)(DF9) a:
j[ = K Q,F, (x/Q) (DFB) (2.6) o h .s Y D = K [1.11 Q(X/Q) DF + Q(x/Q)(DFS)) g = K Q,F, (x/Q)(1.11 DFY + DFS) (2.7) b b d where:
.O fs (Y = the dose rate in mrem /yr to the total body of an individual beyond the EFFLUENT RELEASE BOUNDARY due to Kr-85. This value is to be less 8% than 500 mrem /yr. l 1%
K= unit conversion constant,1E6 pCi/pCi. l
$ vs ,
F, =. volume flow rate in stack, cc/sec. Q= average Kr-85 release rate, pCi/sec. s E 8 g Q, = average Kr-85 release concentration, pCi/cc. g (x/Q) = atmospherc dispersion coefficient for instantaneous releases. (For the FAST alarm setpoint,6.05 E-5 sec/m is used, based upon Regulatory
? z Guide 1.3 criteria. For the SLOW alarm setpoint,3.90 E-6 sec/m is y 8
& si used, based upon actual historical monthly average x/Q values at the ti Z worst case receptor location.)
E >g - EE DFB = the total body gamma dose factor for exposure to a semi-infinite cloud of n V
! 5 Kr-85 = 1.61 E-5 mrem-m per pCi-yr. l ODCM 14 Rev.5
N th ' D' = the dose rate to the skin of an individual at or beyond the 'iFFLUENT RELEASE BOUNDARY due to Kr-85. This value is to be .ess than 3000
,, mrem /yr. l 5
O 1.11 = the ratio of the tissue to air energy absorption coefficients over the energy 4 ( - range of photons of interest. This converts dose (mrad) to dose 9 equivalent (mrem).
@ / DFY = the gamma air dose factor for exposure to semi-infinite cloud of Kr-85 =
d 1.72 E-5 mrad-m per pCi-yr. l l 5
. DFS = the skin beta dose factor for exposure to a semi-infinite cloud of ,
h Kr-85 = 1.34 E-3 mrem-m' per pCi-yr. l E - ) E V NOTE: Equations 2.6 and 2.7 incorporate the use of the semi-infinite plume j $h model. The model assumes receptor submersion in a plume of uniform concentration, which is semi-infinite in geometry, having as its only ? ~, O% boundary the ground plane. Que in the meteorology and topography at the La Crosse Site, the worst rr .or locations are a bluff 1300 m SSE
, k and a bluff 600 m ENE of the facility. At these locations the receptor is g f. submerged in the plume.
A b b E s
'g s Calculation of instantaneous Release Rate Monitor Setooints for Noble Gases (Kr-85) x %
$ Equations 2.6 and 2.7 are used to calculate the controlling instantaneous release rate setpoints for dose rates to the total body and skin of an individual due to e
I s Kr-85 for one- and two-blower operation.
- The DFB, DFYand DFS values for Kr-85 are multiplied by the appropriate yJQ w $
Q value, the conversion constants and the stack flow rate for one- or two-stack blower 5
. operation to obtain the values for TBF, SFG and SFB which are then inserted into the E o
'g g following equations to determine gaseous release monitor alarm setpoints, Q,:
E Q, (Whole Body) = I * ** YO (2.8) gg (TBF) n a $ V ODCM 15 Rev.5
_ . . ~ . . . __ _ _ _ _ _ -.__ _ _ 9'
= (3000 mrem /yr)
G(j O (Skin) (SFG + SFB) I') where: [S ~ TBF = (1E6) (x/Q) (DFB)(F,) SFG = (1.11E6)(x/Q)(DFY )(ps ) g- SFB = (1E6) (x/Q) (DFS)(F,) The smaller of the two values calculated is used for the setpoint. This instantaneous h s [ release rate setpoint is very conservative since it is the average release rate allowed U j l for a whole year. , E E g The following step-by-step procedure may be used in conjunction with the R o equations found on Figure 2.2 to calculate the instantaneous release rate limits for Kr-85 for one- or two-stack blower operation:
, h '
n y L
$: 1. On Figure 2.2, enter the date that the alarm setpoint calculation is performed.
B Note the appropriate value for x/Q. 3 q 2. E 8 s
- 3. Note the appr'opriate value of F, and the number of stack blowers
} operating for the condition being calculated. ;
n. r j -
- 4. Using the equations at the top of Figure 2.2, calculate the values of TBF, t s SFG and SFB for one- and two-blower operation and for all appropriate x/Q's, using the DFB, DFY and DFS values for Kr-85 listed on Figure 2.2.
g o g l S. Calculate the values of O, for each case. Select the smallest Q, value for each x/O which will become the FAST and SLOW alarm setpoints for the noble gas monitor.
- 6. The Q values (alarm setpoints) are tabulated on Figure 2.3.
b> b 0) E o l; NOTE: These alarm setpoints (Q,) will not need to be recalculated during SAFSTOR unless: (1) limits are changed, (2) x/Q values are changed, (3) dose factors are changed, or (4) volume flow rate in the stack n G ]ggx changes. a .5 ODCM 16 Rev.5
I Figure 2.2 > (] NOBLE GAS (KR.85) RELEASE MONITOR ALARM SETPOINT CALCULATIONS _fs o Galculation for Alarm Condition (FAST or SLOW) No. of Stack Blowers = F, =
~
x/Q = d Eauations: '
- h E TBF = (1E6)(x/Q) (DFB) (F,)
Y O SFG = (1.11 E6)(x/Q)(DF )(p ) j t 2 1 l j SFB = (1E6) (x/Q) (DFS) (F,) where: o (x/Q) = 6.05 E-5 sec/m or 3.90 E-6 sec/m' , (FAST) (SLOW) . L n k 3 8 1 DFB = 1.61 E-5 mrem-m h f P Ci-yr
. . . s DFY = 1.72 E-5 mRafm'
,8 s pCi-yr M i
% 3 DFS = 1.34 E-3 mrem-m ]
.0 w pCi-yr j g y
$ $ h l g F, = 1.65 E7 cc/sec or 3.304 E7 cc/sec :
y (1 blower) (2 blowers)
= mrem-cc TBF e Ci-yr E $
E + = mrem-cc SFG+SFB = pCi/yr l E
!3 8g Q,(whole body) = 500 mrem /yr TBF
= Ci/cc -
m m
*" Y' = pCi/cc Q,(skin) =
} >i (SFG + SFB) g v g3
-ODCM 17 Rev. 5
i l l I) Figure 2.3 '. V_
- ' . NOBLE GAS (Kr-85) RELEASE MONITOR l l Q ALARM SETPOINT
SUMMARY
(pCi/ccin stack effluent) E b 4
. FAST ALARM SETPOINT SLOW ALARM SETPOINT
! O.
1 BLOWER 2 BLOWERS 1 BLOWER 2 BLOWERS 8
- .!E l j WHOLE BODY 3.11 E-2 1.55 E-2 4.82 E-1 2.40 E-1 E 3, jV SKIN 2.21 E-3 1.10 E-3* 3.43 E-2 1.71 E-2*
o&k -
- g Since Kr-85's beta dose equivalent component is significantly higher than its gamma e s 3 dose component, the noble gas monitor alarm setpoints will always be based upon h
h- s the Q for skin dose. Since the alarm setpoints for 2 blowers are the most g. 5; s restrictive, they may be used for all operating conditions without exceeding the limits j g ~ ; l 8 for instantaneous release.
%.* s s !
fi 8 I s , e o E E z "8 o
.B $
$E u .i a $
5 C_!e_ ODCM 18 Rev. 5
r
' 4 l
' H-3 and Particulates s
E E The following mathematical relationship shall be used to implement the limitation , O - a
, __ for H-3 and Particulates with Tm > 8 days alarm setpoints:
1 9 1 . .. l De, = Ei Pi,Opi(x/Q) (2.10) e 3 f' where: N> -
- y De, = the dose rate to organ I of an individual at or beyond the i
a EFFLUENT RELEASE BOUNDARY, due to H-3 and particulates ! eU with half-lives greater than 8 days. This value is to be less than + 1500 mrem /yr. i o j P, = the dose parameter for organ T , for radionuclide i, for the
-{ inhalation pathway, in mrem-m per pCi-yr.
h __ h x/Q = the atmosphere dispersion coefficient in sec/m O=n release rate of nuclide i, in pCi/sec. i 5 ::
- e 8
- 1ACalculation of Release Limits for H-3 and Particulates i f ' with Half-Lives Greater than 8 days g f -
a 1 I g Since it is impractical to measure instantaneous release rates for radionuclides
. other than noble gases, the alarm setpoints for radionuclides other than noble gases 5 are expressed in terms of total accumulated activity on sample media for a specified sampling time, AT, which is monitored as pCi by the stack effluent monitor.
i I8 m e sm ; is z, G
-V ha m 5 . :
.ODCM 19 Rev.5 L I
d O V Equation 2.11 is used to calculate the release rate limit for all H-3 and ! padiculates with half-lives greater than 8 days. This equation is based on the dose 9 . rate to an infant due to inhalation of these radionuclides. - In accordance with O NUREG-0133, the infant will always receive the maximum dose rate. The atmospheric To 2 dispersion coefficients (x/Q) used are 6.05 E-5 sec/m for the calculation of the FAST
. , alarm setpoint and 3.9 E-6 sec/m' for the SLOW alarm setpoint.
E E I 8
.I Alarm Setooint Calculations for H-3 and Padiculates j with Half-Lives Greater than 8 days eh .E oEk 1500 mrem /yr 2'W -- OP ' E [P,(inhalation) x Rpi](x/Q)
A e w. ,A 8 -1. L 1 . where: _2 g s 0,,= the maximum allowed total release rate of a typical mixture of 5 E radionuclides in pCl/sec conservatively derived from the allowed annual m 8 1% average dose rate to organ T and very conservative x/Q. l l f 7 c t i
)
j - Rn= the ratio of the activity of nuclide i, to the total activity of all nuclides other x y;l _I than noble gases in a typical r.lixture being released.
- E
$ S x/O = the atmospheric dispersion coefficient as given above for FAST or SLOW M l alarm respectively, in sec/m*.
E l 3 5 B $ i lE o VM 5 V h i
- a. 5 ODCM 20 Rev.5
" -- ,n., y
i l l Resolution of the P,, term in Equation 2.11 yields:
~
P,, (inhalation) = (10' pCi/pCi)(BR)(DFA,',) (2.12) l where: l k' - > I DFA,,_ = the inhalation dose' factor for an infant, for the i* radionuclide, for l
' organ r, in mrem /pCi.
3-> k 'BRL = infant breathing rate, in m lyr, f d l 9 . . O To calculate the alarm setpoint in terms of total pCi deposited on filter or. ;
.E, . '
e cartridge sample media, the following equation is used: e
\
.g ' Lowest Op ' x AF
. Q := (2.13) gg. p, L where:
. % 1 5 f
{ - h 3 Oi = the activity in pCi (deposited on sample media in sample time AT) which initiates an appropriate alarm in the stack effluent monitor. .1 i g s Og, = pCi/sec E F, = stack flow rate, cc/sec h %s .
# .: AF = total flow through sample media (cc), in sample time AT, corrected to
' l
' stack gas conditions. AT is normally 7 days.
e f ii I - I
==
p
. g 1 The procedure outlined below is 'used to calculate the release limits for lii O
E radionuclides other than noble gases. This will be done at least annually. E
}> 6 us NOTE: This procedure is applicable for the determination of either FAST or E
- l
.1
- SLOW alarms by utilizing the appropriate value for x/O in the equation.
b ; kJ e a 5 a ! ODCM 21 Rev. 5 ; 1 i
+ - . . _ , - .-- -, _ _ , , . _ . _ , , , , . - . , , - - .
i
- 1. Start on Figure 2.4 Enter the date, the alarm setpoint being calculated ha__
FAST or SLOW) and the appropriate x/Q value to be used. O O
- 2. Enter the average release rate for the period, Opi, in pCi/sec, of each
} identified radionuclide. At the bottom of the form, compute and enter the sum IQpi .
i j 3. In the column labeled Rn , enter the ratio of the average period release ] h rate of nuclide i to the average total pe iod release rate, IQpi , f or the
\ period.
o h 4. For each organ t, as noted at the top of he form, calculate and enter the
-(
e* value of (x/Q) (fin) P,,(inhalation) for c.ach nuclide. Pa (inhalation) values 8 f are found on Table 2.1. At the bottom of the column, for each organ, g- enter the value of I Rei Pa (x/0) for that organ.
\
j t 5. Go to Figure 2.5. Enter the date and the alarm setpoint being x determined. if 6. Using the equation at the top of Figure 2.5, calculate the release rate g '
}
I
- l
. limits, Op, , for each organ T.
__ l e 7. Select the lowest value of Og,, enter at the bottom of Figure 2.5 under 5 appropriate blower operation. Multiply the Og, r, umber times the total E sample flow through the sample media, cc, and divide this by the 18 y *d appropriate blower flow rate, cc/sec, to determine the 0, in pCi and use a z i these as alarm setpoints. y E o 25 V ODCM 22 Rev.5
~'
) [
-{v}
~
Health Pnysics Review Date Operations Reylew Com_ m. Approval Date , Prepared or Revised By Date LARRY L NELSON 3/10/98 h_! h(f 2//6 // t/-75'- gCMM #/////f ~
/ // /
Figure 2.4 Date H-3 AND PARTICULATE GASEOUS RELEASE MONITOR ALARM SETPOINT DETERMINATION Alarm being calculated (FAST or SLOW) x/Q sec/m2 * (x/Q) ReiPis(inhalation) *
- Nuclide i O,p Rn W Body Bone Liver Thyroid Kidney Lung GI-LLI H-3 Co40 Sr-90 Cs-134 Cs-137 Co-144 IQn= I=
i i
- For FAST alarm use 6.05 E-5 sec/m for x/O and for SLOW Alarm use 3.90 E-6 sec/m
** Pg(inhalation) values found in Table 2.1.
23 Rev. 5 ODCM
h (] Figure 2.5 H-3 AND PARTICULATE GASEOUS RELE/.oE
% MONITOR ALARM SETPOINT
SUMMARY
e k - l 8 N: k Calculation for (FAST or SLOW) alarm. 4
~
1500 mrem /yr 5 O* ~ Ii[Pis(inhalation) x Rpi x x/Q] E a 4 O g = maximum allowed total release rate, pCi/sec to meet dose rate limit to E organ T. 0' \ l
,[ t II (x/Q) Rei Pis(inhalation)* Og , (pCi/se:)
@> Whole Body j b Bone Liver O Thyroid
% Kidney e 4 Lung
,o j 4
(, 1 s GI-LLI , g s
- From Figure 2.4 s t-E. One-Blower Operation l Two-Blower Operation E4 l
} ~ . Lowest Qp, x AF
_~ Lowest Qp, x AF
$; 1.650E7 3.304E7 l
$ s where: l l Q= cc AF = corrected total flow through l uCi/sec x 3.304 E7 cc/sec sample media, cc l s E I pCi
=
o E " l ; Q= uCi/sec x cc l g 1.650 E7 cc/sec l l z I
] = pCi s 8 l ,
t e d I B
- I l e J
- P. >-
k_.g) h E
- a. 5 l
ODCM 24 Rev. 5
O Prepared or Revised By Data Her.ith Physics Fleview e-l Dats Operations Rsvjew Comm. Approval Data _ n LARRY L. NELSON 3/10/98 h J./M/g l // 'f-T ff/7//h
~
+////f6 "
.- i f // J Table 2.1 INFANT DOSE FACTORS P3(INHALATION) FOR H-3 AND PARTICULATE GASEOUS RELEASE MONITOR ALARM SETPOINT DETERMINATIONS in Units of mrem-m'/pCi-yr Nuclide . Whole Body Bone Liver Thyroid Kidney Lung GI-LLI H-3 .
6.47 E2 6.47 E2 6.47 E2 6.47 E2 6.47 E2 6.47 E2 CO-60 1.18 E4 8.02 E3 4.51 E6 3.19 E4 SR-90 2.59 E6 4.09 E7 1.12 E7 1.31 E5 CS-134 7.45 E4 3.96 ES 7.03 E5 1.90 ES 7.97E 4 1.33 E3 CS-137 4.55 E4 5.49 ES 6.12 E5 1.72 ES 7.13 E4 1.33 E3 CE-144 1.76 ES 3.19 E6 1.21 E6 5.38 E5 9.84 E6 1.48 ES Values in this table are derived from Tables E-5 and E-10 in App. E of NRC Regulatory Guide 1.109 Rev.1, October 1977.
- No data available.
ODCM 25 Rev.5
() b) To demonstrate compliance with the limitations of Section 3.3.3.b, dose g, % contributions are calculated for any Kr-85 released to unrestricted areas using the r o following expressions:
~
f DY (r,0) = 3.17 E-2 DFY Q [x/Q)(r,0) (2.14) g D" (r,0) = 3.17 E-2 DFs O [x/Q) (r,0) (2.15) E f 0 V where: B [p DY(r,0) = the dose commitment to the maximum individual due to the gamma radiation from Kr-85 at location (r,0), in mrad. 8 h DS (r,0) = the dose commitment to the maximum individual due to the oN beta radiation from Kr-85 at location (r,0), in mrad. g Q = the total release of Kr-85 in gaseous effluents for the release period, in pct. g 4 g _ $ 3.17 E-2 = pCi/pCi divided by sec/yr B [x/Q] (r,0) = the annual average atmospheric dispersion constant for long-8 % term releases at location (r,0), in sec/m . Since the collection j , of hourly meteorological data is no longer required or performed at the LACBWR site, a conservative value based on 3 y : E j historical site specific annual average x/O values will be used. I fi - This value is 1.82E-6 soc /m . I l e
- DFY gp,j gps = the gamma and beta air dose factors for exposure to a uniform semi-infinite cloud of Kr-85 in (mrad-m /pCi-yr). Numerical l l
,, g values are 1.72E-5 and 1.95E-3 respectively.
j o (Ref. NRC Regulatory Guide 1.109 Rev.1, October 1977.) E 3 8 s TE
.i eE ,- 3$
V-ODCM 26 Rev.5
- . . . . . . . . . , . . - . . ~ . . --
l a
.Qalculation of Gamma and Beta Air Dose Commitments l
n In accordance with the RECP, the gamma and beta air dose commitments are to l lii i O < be calculated once per calendar quarter and yearly. Equations 2.14 and 2.15 are used l to perform these calculations. Since the only noble gas that needs to be considered at i LACBWR is Kr-85, and since a conservative constant value is used forx /Q, these l d E equations reduce to: o ! T D7 = 9.923E-130 i l
$ DP = 1.125E-100 i !
o '. The following step-by-step procedure is used in conjunction with Figure 2.6 to l b I calculate the quarterly cumulative dose commitments due to Kr-85. g_2
,8 N 1. Go to Figure 2.6. Enter the Date. Enter the period covered by the ;
1 h s calculations. l
".0 - l
- c. s h f, 2. Enter the total Kr-85 activity released in the gaseous effluent during the l 5 a l
I N , period being considered, in pCi. 0= E 3. Calculate the dose commitments DY(r,0) and D"(r,0) due to Kr-85 using i o E the equations on Figure 2.6. x m 1
] $$
R
- 4. Calculate the percent of the current quarterly and annual release limits j@ ~ and enter on Figure 2.6.
J
'E >-
aE o ! $ V -- ODCM 27 Rev.5
I I') Dita Health Physics Riview l DIts Operations R;yiew Comm. Approv::1 Dat's
~Pmpared or Rivised By LARRY L. NELSON 3/10/98 je /h l //-Y-77 gWW/h e////FC i i // /
Figure 2.6 Date AIR DOSE COMMITMENT TO A MEMBER OF THE PUBLi0 FROM NOBLE GAS (Kr-85) RELEASE Release Period Total Kr-85 Act. Re: eased, O = uCi Dose Calculation for Release Period D7 = 9.923 E-13 Q = mrad D* = 1.125 E-10 Q = mrad Limits Gamma Beta Particle Calendar Quarter 5 5 mrad $10 mrad Calendar Year 510 mrad 520 mrad Current Air Dose Commitment Record for Calendar Year 1st Quarter 2nd Quarter 3rd QuarterJ 14th Quarter.J Calendar Year - i Beta Gamma Beta Gamma Beta Gamma Beta Gamma Beta Gamma Dose, mrad
% of Limit ODCM 28 Rev.5
! c) To demonstrate compliance with the limitations of Section 3.3.3.c, dose contributions are calculated for H-3, and particulates with half-lives greater than 8 days, 84 identified in gaseous effluents released to unrestricted areas using the methodology 4 9 ' presented in NRC Regulatory Guide 1.109, Rev 1, October 1977. This methodology 8 takes the form of the following general equation: E 5 0
$ D (r,0) = EE M!' W(r,0) Qi (2.16)
T Pi b$
$ where:
.g ,
e
& D (r,0) =the dose commitment to organ T of an individual in age group a, at O ' distance r in sector 0 from the release point, due to the release to the atmosphere of radionuclides other than noble gases, in mrem.
j s W(r,0)= the average dispersion parameter for estimating the dose to an
- d. individual at the receptor location (r,0), for the period of release, in g- s sec/m or m.2 as required by the characteristics of the exposure pathway.
e Q, = the total activity of each radionuclide i, other than noble gases, in 8% gaseous effluents for the release period of interest, in pCi. 3 x
= the dose conversion factor for exposure pathway P to organ t of an
{g M[, individual in age group a, for each identified radionuclide i. The units 2 i 5 ' of M[, are (mrem-m )/pCi or (mrem-m )/ Ci-sec) as required so that the product Ml, W(r,0) is mrem /pCi. S E o E n
;- Equation 2.16 may be expanded to the following form where each term is the incremental dose received via one of the three major dose pathways.
8 E '3 z tu yj D. (r, 0) = E DS (r,0) + D^, (r, 0) + D,?, (r, 0) (2.17) ax' ,--' 5 b-- ODCM 29 Rev.5
13 where the first term on the right is the external dose from direct exposure to activity V_
~ deposited on the ground plane, the second tenn is the dose from inhalation of f
8 radionuclides in air, and the third term is the dose from ingestion of foods contaminated j r by atmospheria releases of radionuclides. R 5 t Applying the methodology of NRC Regulatory Guide 1.109 Rev.1, equation 2.17 g [ is expanded as follows: g 3 Z M1 Qi(D/Q)(r,0) f e
~ D,, (r, 0) = (2.18) e,.
R o + E Ms Qi(x/0)(r,0)
+ E MU Qi(D/Q)(r,0) + (MP/1, Qi4 + My! QT ) (x/Q)(r,0) hs O-
- B + E My Qi(D/Q)(r,0) + (MPL Qi4 + M?", OT ) (x/Q)(r,0) s s i
8 h a
+ E M7 Qi(D/0)(r,0) + (M?E O54 + M?% OT ) (x/Q)(r,0) i
$. s . + E M,J Qi(D/Q)(r,0) + (M?h, O$4 + M?), OT ) (x/Q)(r,0)
S E 8 g where: g (x/Q)(r,0) = the annual average atmospheric dispersion factor for a receptor at the distance r in sector 0 from the release point, in sec/m' For E z the LACBWR in the SAFSTOR mode, the value for this term is y 0
& ;;j conservatively taken to be the largest historical (1983-1987) 3 z .
undecayed /undepleted z/O for a real receptor and is 1.82E 6
? d sec/m .
aE 55 O ODCM' 30 Rev.5 __ l
i l e (D/Q)(r,0) = 1.82E-9m.2. This is based on the relationship D/Q = V, x/Q
;- where V, = the deposition velocity in m/sec. V, is generally
< 1E-3m/sec for dry deposition of submicron aerosols which may be released from the LACBWR facility during SAFSTOR (Ref Q
a Whicker, F. W. and Schultz, V., Radioecology: Nuclear Energy D and the Environment, Vol ll, CRC Press, Inc., Boco Raton, E-> d Florida,1982. ] i { 1.0E6 Sr DFGa (1-e-%)/Ai and according to R.G.1.109 the g MR, = l dose to all internal organs (t) for all age groups (a) is taken to be j 4 g the same as the total body dose. o L j Mi =- 3.17E-2 BR,DFA, . i b l x E e and for the ingestion pathway (DV) for produce (non-leafy-vegetables, fruits, and { o grains) M,PV = 1.1 E2 DFlit, UY fg exp(-Astn)(r(1 - exp(-Aci te))/ YvAci + a b, Biv (1-exp(-Aitd))/ PAi) g >. E for all radionuclides except C-14 and H-3 O _2 U for C-14 g s M f. = 22 DFI,,,, U; fg p s; s for tritium E [N M?$ = 12 DFin, U;fg /H
$ for the ingestion pathway (Dm) for milk fe .
i I . MR,* = 1.1E2 DFi g UT Fmi OF exp(--Ai tr)(fp fs (1 -- exp(-At tn)) + exp(-Aiin )) x (r(1-exp(-Xeit.))NyAci + Bw(1 -exp(-Aito))/PAi)
@ $ for all radionuclide except C-14 and H-3 i
O g M 7, = 22DFI,e US FmiOr p(exp(-Autt)) for C-14
]5 83 M?" = 12DFi g U* Fmi Or exp(-ATtr)/H for tritium o E
'E ,
ae /~'- E $ d ODCM 31 Rev.5 I 1
rm Q for the ingestion pathway (DM) for meat j
- Mfou = 1.1E2 DFli. UY Fn Qrexp(-Ait.)(f pf.(1 -exp(-Aitn)) + exp(-Aitn) )
g x (r(1-exp(-1a t.))/Yv1a+Bw(1 - exp(-lit3))/PAi)
-- for all radionuclides except C-14 and H-3
~
s { MW. -'= 22 DFli4.UY Fn4 Or p(exp(-As4t.)) for C-14 for tritium l M?". = - 12 DFir. UI FtrQrexp(-Art.)/H 0 g for the ingestion pathway (DL) for leafy vegetables: g x e I j { Mfo' = 1.lE2DFlioU[f,exp(-Aith)(ql -- exp(-Aet ))/YvAr,+Biv(1 - exp(-A,te))/Pli ) e~ OE%__ for all radionuclides except C-14 and H-3. L
&. ' for C-14 E
0 si MP4, = 22DFIi4 Uff,p for tritium h- . Myh = 12DFIToU[f,/H
- N
$ kThe values used for the various parameters in the abovs equations are those z
recommended in NRC Regulatory Guide 1.109, Rev.1, for the maximum exposed Si individual. 1
-- Parameter Dimensions Description / Source Q $ 1.0E6 pCi/ Ci E
DFG3 mrem-m 2/pCi-hr from table E-6 in R.G. z l 0 DFA,m mrem /pCiinhaled from table E-7 thru E-10 in R.G.
".l E El j *; DFA i4w mrem /pCiinhaled from table E-7 thru E-10 in R.G.
E R$ e O j V _f $__ ODCM 32 Rev.5 1 u
l I s Parameter Dimensions Description / Source _ _t I
. DFArw mrem /pCiinhaled from table E-7 thru E-10 in R.G.
u .. O DFI,w mrem /pCiingested from tables E-11 thru E-14 in R.G. DFInu mrem /pCiingested from tables E-1, thru E-14 in R.G.
)
5 gg DFIrw mrem /pCiingested from tables E-11 thru E-14 in R.G. 23
}\
Sr = 0.7 dimensionless attenuation factor accounting for R. i
]
~
shielding by residential structures 5 8 gj ( hr- radiological decay constant for L e v nuclide i, hk
== ta = 1.31x105 hr period of long-term buildup for k activity in soil (nominally 15 yrs)
E d 3.17x1J2 pCi-yr/pCi-sec g__ N BR, inhalation rate for age group a. y m3 /yr I Nt Table E-5 in R.G. E
.g g Q 1.1x102 pCi-yr/ Ci-hr l E
kg/yr consumption rate of produce for j fg U7 individual in age group a. Table E-5 , I N , of R.G. l I i
. f, = 0.76 dimensionless fraction of produce ingested that is l
{ $ grown in garden of interest. l 5 t,, hr time delay between harvest of s vegetation or crops and ingestion. i 1B z y @ =0 for pasture grass by animals E Gi
- z for stored feed by animals
.; = 2160 a $x C $$
v __ ODCM 33 Rev.5
^ t f
J : Parameter . Dimensions - Description / Source ,
for leafy vegetables by man V
.' = 24 g .
t = 1440.. . for produce by man ; i
> /
fraction of deposited activity - g 1 r- = 0.2 .' dimensionless g retained on crops, leafy vegetables, ; or pasture grass.
= A, + Ar . d the effective removal rate constant' i 1e, - hr k for radionuclide i from crops. l E 1 j Ar =.0021 hr 4 removal rate constant for activity on j E plant or leaf surfaces by weathering >
1 (~ to 14 day half-life) : o l t, hr period of crop, leafy vegetable, or pasture grass exposure during g o g growing season. i G -k N
= 720 for grass-cow-miik-man painwey
.bt s
' = 1440 for crop / vegetation-man pathway
[ Y, kg/m2 agricultural productivity (measured i j - in weiweight) E
= 1
= 0.7 for grass-cow-milk-man pathway f 1 4,
N
- 2.0 for produce or leafy vegetables g l E
ingested by man pCi/kg in vegetation per pCi/kg in B. dimensionless soil for nuclide i. Table E-1 in R.G. E E 8
$ $ P~ = 240 kg/m 2 effective surface density of soil (dry i a: w .
g z weight) a E > ,
& @ 22 pCi-pr-m 3/ Cl-kg-sec n e
-Y) h_$ _
ODCM- 34 Rev.5 ;
)
l
._ .._..- -~-. .._._.__ _ . _ _. _ ._ _.._..._....._._. .__..__ ___ _ __ _ _.
( k
. Parameter Dimensions Description / Source I
' the ratio of the total annual release
- f. y p dimensionless
! lii s time for C-14 to the total annual time [. during which photosynthesis occurs with the condition that p<_1.0 E
/ = 1.0 for continuous C-14 releases.
i $
^
pCi-g-yrlpCi-kg- sec {] 5 n 12 average absolute humidity of the I ! $E H = 8.0 g/m i atmosphere at location (r,0) i, U'" liters /yr consumption rate of milk for
& 3 individual in age group a. Table E-5 0 -._
of R.G. o k F, day /l factor for estimation of activity of s nuclide i in milk from that in animal 8 feed (pCi/l in milk per pCi/d ingested n f by the animal) Table E-1 in R.G. V -
' Og - = 50 kg/ day feed or forage consumption rate
.)
? O (wet weight) by milk cow or beef j cattle 3 % .i, - = 48 hr
. transport time from animal g g g f feed-milk-man.
3hf I ,. = 0.5 dimensionless fraction of the year that animals graze on pasture.- f, = 1.0 dimensionless - fraction of daily feed that is pasture 3 $
. when the animal is on pasture 8 @
_g __ UP ' kglyr consumption rate of meat & poultry for individual in age group a. Table ! z
] o E-5 of R.G. .;
.y Ed !
l BZ . 3 a$ I
&E5 ODCM .35 Rev. 5
_ 7. . V __ Parameter Dimenuions Description / Source yFn day /kg factor for estimation of activity of lii nuclide iin meat from that in animal feed (pCi/kg in meat per pCi/ day ingested by the animal) Table E-1 in j R.G. O k , t, = 480 hr average time from slaughter of meat - animal to consumption of meat 4 5 o j, UE kglyr consumption rate of leafy vegetables for individualin age
.f group a. Table E-5 in R.G.
y
,$ \ f,
= 1'0 dimensionless fraction of leafy vegetables grown in Eb garden of interest.
O&% s b j Calculations of Dose Commitments due to Gaseous Release other than Noble Gases n v _ _:: in accordance with the RECP, the maximum commitment to a MEMBER OF THE 5 DPUBLIC from H-3 and all radionuclides in particulate form with half-lives greater than 8 68 days shall be determined at least quarterly. S /, g j , To perform this calculation Eq 2.18 has been formatted on a computer-based spreadsheet. The quantity in curies of each nuclide (i) released to the atmosphere
- E g o from the LACBWR facility during the calendar quarter is entered in the appropriate cell M
-- of the spreadsheet. The spreadsheet orogram calculates and displays the total m
j $ quarterly dose in mrem to the total body and each organ of an individual in each of 5 3 3 E four age groups and the cumulative calendar year dose to the total body and each v -i l
$ $ organ. It also determines the maximum exposed organ (and its dose) for each age /"~N $
I () -- i
)
i ODCM 36 Rev. 5 i l 1
l-
- ex V -
group each quarter and the dose to the maximum exposed organ in all age groups. j l l g ' The quarterly and cumulative calendar year doses to the maximum exposed organ are E
- compared to the limits and the relation in terms of percent of the limit is displayed. The 1 -_
l j maximum incremental organ dose received through each of the three major pathways is I 1
< also determined for each age group each quarter. ;
E. I , e - l 0 i g L i E ' E
.o E.
E i O
~5 !
c i'
- 8 1 >L-s l' %
s l f a:
,UN R
i f E I a E 1 l I : I o E l 8 B ! l E i E z , m o R $ E E
-)
E >.; - l 1E ! 5 C, l ODCM 37 Rev.5
i
- 3.0 RADIOACTIVE EFFLUENT CONTROL PROGRAM y
b < N 3.1 Proaram Requiremente s ! The Radioactive Effluent Control Program (RECP) shall conform to the guidance g
<l p of 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses E4 0 '
to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably E
- s. 9 g achievable. This program shall establish the requirements for monitoring, sampling ;
E K( e G and analysis of radioactive gaseous and liquid effluents released from LACBWR to o bk% ensure the concentrations in effluents released to areas beyond the EFFLUENT ! RELEASE BOUNDARY conform to 10 CFR Part 20 Appendix B, Table 2, Columns 1 lii 8 Y and 2. It shall provide limitations on the annual and quarterly dose commitment to a
=
O - MEMBER OF THE PUBLIC from radioactive effluents in conformance with Appendix 1 5 ? I tof 10 CFR Part 50. x 8 . 1N The limitations of operability of gaseous and liquid monitoring instrumentation, g E I E h including surveillance test and setpoint determination in accordance with Section 2.0, f Offsite Dose Calculations, will be included in this program. J' Requirements for the Containment Building Ventilation System, including 5 filtration and elevated stack release of exhausted air is included in Section 3.3.1. b 5 ' i E $ I $ u&E E q e bi ODCM 38 Rev.5
in accordance with provisions of 40 CFR 190, the restrictions and surveillance [ C requirements for total dose to any MEMBER OF THE PUBLIC from all LACBWR lii , O
~ related sources and dose pathways are presented in Section 3.4. l
_m
~
!l!
i ; g 3.2 Llauld Effluents s O ' 3.2.1 Samplina and Analysis
.5 k B i E All liquid effluent releases at LACBWR will be in batch form. A batch l
.E d _.
lii V release is the discharge of liquid wastes of a discrete volume. Prior to sampling i h for analysis, each batch shall be isolated and then thoroughly mixed, to assure : h g y representative sampling. The radioactive content of each batch of radioactive o T i
~ liquid waste to be discharged shall be determined prior to its release, as per the .!
h3 following table: g s i i 5 4 z . e a fi 3 , (
=
o E E Z
,3 8 E Gi is Z
l? # 4 E-E ' n'u_! 5 _ ODCM 39 Rev.5
, s i
,w-.. -
, , ,r
l 1 .f% U -- Table 3.1 , i s
$ RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS REQUIREMENTS U I FOR BATCH RELEASES l 3
e k s s ....a......... _;. . . . . . . . . . ...a . ? SAMPLING L : . . . _ MINIMUML ANALYSIS;FREQUENC.Y: p jiTYPE OF ACTIVITY. ANALYSIS.." L :FREQUENCYU , E 8 1. Principal Gamma emitters *) Prior to discharge Each discharge y f 2. Dissolved and entrained gases (gamma emitters) Prior to discharge Each discharge l
- 3. Tritium Prior to discharge Each discharge j E
- 4. Gross Alpha Prior to discharge Each discharge !
o l I S. Sr-90 and Fe-55 Beta emitters Prior to discharge Quartedy Composite (*) h w (a) A composite sample is one made up of individual samples which are proportional to g 4i the quantity of liquid waste disenarged and in which the method of sampling ('N _
's employed results in a specimen which is representative of the liquid release.
'O N (b) The principal gamma emitters for which the LLD specification will apply are exclusively )
.! s the following radionuclides: Co-60, Cs-134, and Cs-137. This list does not mean that i
' l j only these nuclides are to be detected and reported. Other peaks which are g measurable and identifiable, together with the above nuclides, shall also be identified y% and reported.
$ (c) Methods of calculating the Lower Limits of Detection (LLD) shall be contained in plant l j procedures and are calculated in accordance with criteria of NUREG-0473, Rev. 2.
I % , Q 5i The results of pre-release analyses shall be used in accordance with the Offsite , [ Dose Calculations methodology to assure that the concentration at the point of 1B z j y release is maintained within the limits specified in this RECP. E z _J a $ e A b) ! $ ODCM 40 Rev.5
, . . _ _ . . _ . . . - . . ._ _ _ . . ~ _ . . _ _ _ _ . . _ . . _ _ _ _ . _ . _ _ . _ _ . _ . . _ _ . . . _ . _ . . _ . _ . _ . .
l s I i- . 3.2.2 ' Liouid Effluent Release Limitation , 1
) a) Concentration - the concentration of radioactive material released in k liquid effluents at any time to areas beyond the EFFLUENT RELEASE i l
4 { ' BOUNDARY shall be limited to concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2, for radionuclides other than d .
, dissolved or entrained noble gases. For dissolved or entrained noble -
gases, the concentration shall be limited to 6E-4 Ci/mi total activity g concentration. E E U If the concentration of radioactive material released beyond the O .
== EFFLUENT RELEASE BOUNDARY exceeds the above limits, restore the
$ D >
concentration to within the above limits without delay. O fO - This limit is provided to ensure that the concentration of radioactive s
.$ +
t
- materials released in liquid waste effluents from the site will be less than n: i the concentration levels specified in 10 CFR Part 20, Appendix B, l
- n. T' -
g Table 2, Column 2. The concentration limit for dissolvdd or entrained
. , T f * '
. noble gases is based upon the assumption that Kr-85 is the controlling ~
=_ :
, g radioisotope and its MPC in air (submersion) was converted to an lii o O
E equivalent concentration in water using the methods described in ' E _ international Commission on Radiological Protection (ICRP) ' E 8 i g $ Publication 2.
$E '
E >.J b h Oa ,
.ODCMl 41 . Rev. S '
g r
l (. b) Dose - the dose or dose commitment to a MEMBER OF THE 3 % PUBLIC from radioactive materials in liquid effluents released to areas I a N q beyond the EFFLUENT RELEASE BOUNDARY shall be limited to: w k Calendar Quarter Calendar Year E o 51.5 mrem total body $ 3 mrem total body 5 5 mrem to any organ 510 mrem to any organ v 5 ,, The cumulative dose contribution from liquid effluent shall be E determined at least once per calendar quarter in accordance with f O Section 2.0, Offsite Dose Calculations. If this calculated dose exceeds
. k the above limits, prepare and submit to the Commission, within 30 days, a 3 S
.I. Special Report which identifies the cause(s) for exceeding the limit (s) and O .
s defines the corrective actions which have been or will be taken to assure that subsequent releases shall be in compliance with the above limits.
.l % $ [ This limit is provided to implement the requirements of Sections ll.A, l I
5 Ill.A, IV.A and Annex of Appendix 1,10 CFR Part 50. The dose calculations in Section 2.0 implement the requirement in Section Ill.A of l 2 E 8 g Appendix 1 that conformance with the guides of Appendix l be shown by g calculational procedures based on models and data, such that the actual
.f o exposure of an individual through appropriate pathways is unlikely to be e a g z substantially underestimated.
E $. aE g!5 ODCM 42 Rev. 5
1 r 3.2.3 Liauid Effluent instrumentation The following radioactive liquid effluent monitoring instrumentation lii O
% channels shall be OPERABLE, with their alarm setpoints set to ensure that the E limits of Section 3.2.2.a are not exceeded, at all times when releasing liquid
" i
<,, radioactive effluents. !
l E 5 3 U
- Liquid Radwaste Effluent Line Monitor
.$. l g
and E
- i 8 \
- Liquid Radwaste Effluent Line Flow Meter.
- 5
. g . o The alarm setpoints for this monitor will be determined and adjusted using b l g y methodology in Section 2.0, Offsite Dose Calcule'. ions.
* ?
n s The radioactive liquid effluent instrumentation is provided to monitor the B s 1 - releases of radioactive materials in liquid effluents during actual or potential E l E releases of liquid effluents with the alarm setpoints set to ensure that the alarm EL }< I l h will occur prior to exceeding the limits of 10 CFR Part 20. 4
??
b $ % . _ a) Surveillance Reauirements - each radioactive liquid effluent 1 y$ monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL 5 FUNCTIONAL TEST, and CHANNEL CAllBRATION operations at the 3 z
's 8 E
O { frequencies shown in the following table. j l E >- tg ; Av__2 5 ) i ODCM 43 Rev.5
. _ _ _ .__ , _ . _ . _ . _ . _ _ . _ . _ . _ . . _ _ _ . ~
. 1
- .p Table 3.2 :
N RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION _ _4 SURVEILLANCE REQUIREMENTS f n> k - E ldYUE,< U. ..i " ' ' , si / "m j Channeli , , 43 11nstrument8 i h4 [; AChanneld " iSourcel P TChanneln ' g d F6nctional! i c i y I J ' fig M , NChsckfr, a[ Checks M ~ YiTesti ' " {CalitkatiorW > [ 1 g> Liquid Radwaste ' . Prior to Prior to Quarterly . Atleast once h!
- discharge discharge (See Note 1) per 18 months Effluent Line Monitor.
(See Note 4) (See Note 3) Q Liquid Radwaste (See Note 2) N/A N/A At least once O E% ) Effluent Line Flow per 18 months ! (See Note 5)
-Q A Meter l 2 s E I NOTES- f s
P - L (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room g s alarm annunciation occurs if any of the following conditions exist: )
- Instrument indicates measured levels at the alarm setpoint. l
> q
+ Instrument in'd icates a downscale (circuit failure) failure..
E 8% d 1 [~ [(2) ~ CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours on days in f p g 1 which continuous, periodic, or batch releases are made, e p I. b , '(3) The CHANNEL CAllBRATION shallinclude the use of a known liquid radioactive source positioned in a reproducible geometry with respect to the sensor. The source will have the gamma emitting radionuclide mixture and activity concentration !
' which would normally be measured by the channel during batch discharges.- 1 e $
b$ a (4)- Background radiation may be used for the source check. (5) ' The CHANNEL CALIBRATION will be in accordance with plant procedures. E z
.e o 3
oc w 4 g Z 3 >>- 1 EE s ! 5 ODCM~ 44 Rev.5
# o
l l O_. b) correciive aciien i 8 N (1) With the Liqdd Radwaste Effluent Line Monitor channel alarm / trip-point setpoint less conservative than that required by ~ W , j Section 3.2.2(a), immediately suspend the release or change the fO ., setpoint so that it is acceptably conservative. ! i k (2) With the Liquid Radwaste Effluent Line Monitor NOT 4 m ! $ OPERABLE, or if its alarm setpoint is found to be less conservative than required, suspend release of liquid radioactive effluent without ', ~5. es delay. Effluent releases may be resumed without the Liquid ! 8 - Radwaste Effluent Line Monitor OPERABLE, provided that at least
- ]
i h two independent samples are analyzed and that at least two ! g technically qualified members of the staff independently verify the j m
.g s release rate calculations. If the monitor is not operable for more
!2.
S f' than 30 continuous days, explain in the next Annual Effluent is 2 i s , Report. s E (3) With the flow meter not OPERABLE, effluent releases via E E _E this pathway may cortaue provided the flow rate is estimated at l 87 . z least once per 4 hours during actual releases.
]
, 8 e a is Z
E a$ p 2 s : V j ODCM 45 Rev. 5
3.3 Gaseous Effluents ,
.('/)
I 6S o 3.3.1 Containment BuUdino Ventilation ' Q 4 Normal air discharge from LACBWR is made as an elevated stack 7-k release. Air is swept through the Turbine and Containment Building and then ! 4 , j
, discharged out the stack. Whenever the Containment Ventilation dampers are ;
O ', g open, the air from the Containment Building shall be discharged through a set of p E HEPA particulate filters to reduce the amount of radioactive particulates being ! 8 i released to the environment. This filtration of the Containment Building l Ventilation System exhaust implements the requirements of 10 CFR Part 50.36a, s General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design a Y objectives given in Section ll.D of Appendix I to 10 CFR Part 50. d , h y j 4 , With Containment Building Ventilation System exhaust being discharged
&k
#N without filtration, prepare and submit to the Commission within 30 days a Special !
A G i l Report which discusses the circumstances and what action will be taken to "i! u i , prevent a recurrence. m E5 3.3.2 Stack Effluent Samplina and Analyses E E z The radioactive gaseous discharge from LACBWR will be sampled and s 8 E III analyzed as per the fo: lowing table. B Z E s aE
/m l$
ODCM 46 Rev. 5
t q Table 3.3 I RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS o
} Releasef J Sampling; , , , .. Minimum,Analy + . . . Type of: .
dType) Li requency 4 Frequericyl Activity Analysis (H g ,
" . Stack Continuous M Weekly (*) Particulate Sample Principal Gamma Emitters M a
lo Effluent Continuous M Quarterly Particulate Sample Sr-90 Composite . 3 , Continuous M Weekly (*) Particulate Sample Gross Alpha m
$ k Continuous (b) Noble Gas Monitor Noble Gases Gross Beta j h and Gamma Monthly Monthly H-3 M
, ~% g h NOTES: o i 4 (a) The filter sample shall be changed at least weekly, and filter analyses shall be g-- completed within seven (7) days. [ (b) The ratio of the sample flow rate to the sampled stream flow rate shall be known for
'5 D the time period covered by each dose or dose rate calculation.
- k
.0 4 (c) The principal gamma emitters for which the LLD specification applies exclusively s, ? are the following radionuclides: Mn-54, Co-60, Zn-65, Cs-134, Cs-137, and Ce-144
$ h for particulate emissions. This list does not mean that only these nuclides are to be ;
E 3 considered. Other gamma peaks that are identifiable and measurable, together j 4 with those of the above nuclides, shall also be analyzed and reported in the ,
* . annual Radioactive Effluent Release Report, l
. (d) When upper cavity is flooded or FUEL HANDLING is being performed, stack tritium g g grab samples will be taken at least once per seven (7) days.
O C (e) Lower Limits of Detection (LLD) are determined in accordance with plant
~["- procedures and are calculated in accordance with criteria of NUREG-0473, m Revision 2. ;
u z i
.8 o E $
o W . 1B Eh g2 5 ODCM 47 Rev. 5 c_
(~') 3.3.3 Stack Effluent Release Limitation tj__ k
;. ) a) instantaneous Dose Rate - the dose rate due to radioactive materials 8 '
released in gaseous stack effluents to areas beyond the EFFLUENT
} RELEASE BOUNDARY shall be limited to:
e "
% {
d N + The dose rate limit for noble gases shall be 5 500 mrem / year to the E 8 total body and 5 3000 mrem / year to the skin. 5 L y + The dose rate limit for H-3 and for all radionuclides in particulate z . E form with half-lives greater than 8 days shall be 51500 mrem / year e to any organ. o c b, The dose rate due to noble gases in gaseous stack effluents shall be 8 Y l r~. 4 determined to be within the above limits in accordance with Section 2.0, b - y s Offsite Dose Calculations. x t
.g g The dose rate due to H-3 and for all radioactive materials in k
i particulate form with half-lives > 8 days in gaseous stack effluents shall
$ s ,
be determined to be within the above limits in accordance with Section 2.0, Offsite Dose Calculations, by obtaining representative o g samples and performing analyses in accordance with the sampling and g analysis program specified in Table 3.3.
!5
> (O
$ El if the dose rate (s) exceeds the above limits, without delay decrease l B Z
?> d the release rate to within the above limit (s).
EE o u ODCM 48 Rev. 5
)
i O This instantaneous dose rate limit is provided to ensure that the dose rate at any time at the EFFLUENT RELEASE BOUNDARY from ' 3 gaseous effluents from LACBWR will be within the annual dose limits of 3 10 CFR Part 20 for unrestricted areas. The annual dose limits are the - k j 4 doses associated with the concentrations of 10 CFR Part 20, Appendix B, E, j E Table 2, Column 1. These limits provide reasonable assurance that j 4 g radioactive material discharged in gaseous effluents will not result in the e .,
\
j exposure of an individual in an unrestricted area, outside the EFFLUENT E h Q RELEASE BOUNDARY to annual average concentrations exceeding the
-E limits specified in Appendix B, Table 2 of 10 CFR Part 20. For individuals
- D l d Y who may at times be within the EFFLUENT RELEASE BOUNDARY, the occupancy of the individual will be sufficiently low to compensate for any .
[] ( increase in the atmospheric diffusion factor above that for the EFFLUENT m E RELEASE BOUNDARY. The specified release rate limits restrict, at all I i times, the corresponding gamma and beta dose rates above background
=
2 I s to an individual at or beyond the EFFLUENT RELEASE BOUNDARY to
~
5 500 mrem / year to the total body or 1o 5 3000 mrem / year to the skin. 2 e 5 l These release rate limits also restrict, at all times, the corresponding h organ dose rate above background to an individual via the inhalation l
] z pathway to 51500 mrem / year.
3 8 {' E Ei g z , j aE OM ODCM 49 Rev.5 l
I 1 i
.rsg V
b) Dose from Noble Gas - the air dose to a MEMBER OF THE PUBLIC k O due to noble gases released in gaseous effluents to areas beyond the EFFLUENT RELEASE BOUNDARY shall be limited to: E E 4t Calendar Quarter s g 5 5 mrad from gamma radiation o ! j 510 mrad from beta particulate radiation t e
$ b Calendar Year
$h X 510 mrad from gamma radiation o \
520 mrad from beta particulate radiation S i 5 ? The cumulative dose contributions shall be determined at least once per (3 U/ - N calendar quarter in accordance with Section 2.0, Offsite Dose i t
& Calculations.
8 4, m With the calculated air dose from radioactive noble gases in i is I s . gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a Special Report which identifies the 2 I 5 l cause(s) for exceeding the limit (s) and defines the corrective actions g which have been taken or will be taken to reduce the releases of iB z y 8 radioactive noble gases in gaseous effluents so that the cumulative dose E Gi z during each subsequent quarter and the dose for the calendar year will be j e >- l within the above limits. {E Vi ! i ODCM 50 Rev. 5 1
g
-/ g
, E This limit is provided to implement the requirements of Sections 11.B, s% lli.A, and IV.A of Appendix 1,10 CFR Part 50. The dose calculations in h%
-1.x the ODCM implement the requirements in Section Ill.A of Appendix I that E conformance with the guides of Appendix l is to be shown by calculational
@ f 'i s procedures based on models and data such that the actual exposure of 5
an individual through the appropriate pathways is unlikely to be
}
r4 sk substantially underestimated. E b b[._ o c) Dose from Radionuclides other than Noble Gases - the dose to a MEMBER OF 'HE PUBLIC from H-3, and all r adionuclides in particulate g e w j form with half-lives greater than 8 days, in gaseous effluents released to n 4 (j - areas beyond the EFFLUENT RELEASE BOUNDARY shall be limited to: m b D g Calendar Quarter x
.g 4 5 7.5 mrem to any organ 2
n.
@ Calendar Year 515 mrem to any organ e
C e The cumulative dose contributions shall be determined at least once per 8 g g calendar quarter in accordance with Section 2.0, Offsite Dose v Calculations.
.) h u a
(~'; &a x5 G' ODCM 51 Rev.5
p With the calculated dose from the' release of H-3 and all
- radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit
] f to the Commission within 30 days a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions which EI f ! have been taken or will be taken to reduce these releases in gaseous effluents during remaining quarters so that the cumulative dose during -
each subsequent quarter and during the calendar year will be within the
)Q
']
\ above limits.
. This limit is provided to implement the requirert snts of Sections ll.C, 3 >
lll.A, IV.A and Annex of Appendix 1,10 CFR Part 60. The ODCM n $ y - calculational methods specified in the surveillance requirements s l implement the requirements in Section Ill.A of Appendix I that 8x conformance with the guides of Appendix I be shown by calculational
}n. y
[ { procedures based on models and data such that the actual exposure of I w ' an individual through appropriate pathways is unlikely to be substantially
-=
. g underestimated.
! -M E
5 E d O 'U5 i I ODCM 52 Rev.5 i 1
l l i i I 3 3.34 Instrumentation jg The radioactive gaseous effluent monitoring instrumentation channels q shown in Table 3.4 shall be OPERABLE with their alarm and/or trip setpoints set I __ [ E ' i g to ensure that the limits of Section 3.3.3a are not exceeded. The stack nobi' : i
' gas ' instrumentation alarm setpoint will be determined and adjusted in j d i accordance with the methodology and parameters in Section 2.0, Offsite Dose l Y
.5 l Calculations. j E !
.e f(\
o - The radioactive gaseous effluent instrumentation is provided to monitor l
]
and control, as applicable, the releases of radioactive materials in gaseous { > : j effluents during actual or potential releases of gaseous effluents. The only g _ 3 significant noble gas remaining is Kr-85. The alarm setpoints for these
.l g
N i instruments shall be set to ensure that the alarm will occur prior to exceeding the
" k limits of 10 CFR Part 20.
h 5 N 5 ' a) Gaseous Effluent Instrumentation Surveillance Reauirements - i Each radioactise gaseous effluent monitoring instrumentation channel g g shall be demonstrated OPERABLE by performance of the CHANNEL 8 $ M . CHECK, SOURCE CHECK, CHANNEL FUNCTIONAL TEST, and i
'" CHANNEL CAllBRATION operations at the frequencies shown in i
$ $ Table 3.5. !
m m i E5 z E >-
&E rb
! 5 ODCM' 53 Rev, 5 s
y- , ,-.: - g , ,c-
e , t i O-
~'
b) forrective Action l i. i,' ' _ n . (1)L With a radioactive gaseous effluent monitoring instrumenta- i . tion channel alarm and/or trip setpoint less conservative than that
< r required, declare the channel inoperable or change the setpoint so ,
i , I i that it is acceptably conservative. h l I
- .5 1 g'-
a: (2). With less than the minimum number of radioactive gaseous
- l g ' effluent monitoring instrumentation channels OPERABLE, take the l I
l
- , h L
ACTION required by Table 3.4. Exert best efforts to return the ! (
- I ' . ki instruments to OPERABLE status within 30 days and, if un- '
lii o > I 1 successful, explain in the next Annual Radioactive Effluent i _ 2 (N. Releese Report why the inoperability was not corrected in a timely I
- s. ~
g manner. 1 L 2 a i 5* 1 5 .. l a o n E z .i -
".I o )
4 $ I a: w g z l J ! 9 E >- E e 4 E
- a. _
.ODCM 54 Rev.5
-[
Table 3.4 V_V . s S RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION , i o
~
MINIMUM i INSTRUMENT CHANNELS APPLICABLE OPERABLE CONDITIONS ACTION ki[5
- 1. Reactor Containment Building E! Ventilation Monitor System E *
- a. Particulate Activity Monitor 1 A 8
{ A
- b. Gaseous Activity Monitor 1
- c. Sampler Flow Rate Measuring 1 B E ,
$ Device
'8 E
k '
- 2. Stack Monitor System
- a. Gaseous Activity Monitor 1 C
, b. Particulate Activity Monitor 1 D ,
c , " B 3 y Sampler Flow Rate Measuring
- c. 1
- Device .
)
h-
- When Containment Building Ventilation System is in operation.
g }'
** At all times, unless attemate monitoring is available L
m
.l3N ACTIONS:
R
$ With the number of channels OPERABLE less than required by the Minimum g A.
2 Channels OPERABLE requirement, effluent releases through this pathway may I % . continue as long as a stack monitor is OPERABLE; otherwise, secure the Containment Building Ventilation. B. With the number of channels OPERABLE less than required by the Minimum e $ Channels OPERABLE requirement, effluent releases via this pathway may continue bj @ o provided the flow rate is estimated at least once per 24 hours. E C. With the number of channels OPERABLE less than required by the Minimum
'S z . Channels OPERABLE requirement, effluent releases via this pathway may continue
$ @ provided the Containment Building Gaseous Activity Monitor is OPERABLE; id iIl otherwise, secure the Containment Building Ventilation.
3 z Wsth the number of channels OPERABLE less than rege' red by the Minimum . yj D. Channels OPERABLE requirement, effluent releases v!a this pathway may continue l gm p
- y. _ _
2
} provided continuous collection of samples with auxiliary sampling equipment is initiated within 12 hours.
I i l ODCM 55 Rev.5
l Table 3.5 ) h_ RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ] 3
" - SURVEILLANCE REQUIREMENTS .
l 5 .
.i CHANNEL i CHANNEL M f
INSTRUMENT CHANNEL - SOURCE - FUNCTIONAL -
'QHECK CHECK TEST - CAllBRATION i l
- 1. Reactor Containment Building l Ventilation Monitor System '
MONTHLY QUARTERLY AT LEAST ONCE j o' a. Particulate Activity Monitor DAILY W PER 18 MONTHS ; j I
> i k, b. Gaseous Activity Monitor ' DAILY . MONTHLY QUARTERLY AT LEAST ONCE e
W PER 18 MONTHS ] 8 iM c. Sampler Flow Rate Measuring Device DAILY MONTHLY QUARTERLY AT LEAST ONCE-
# PER 18 MONTHS l
l
==
n lii k 8
- 2. Stack Monitor System o > - a. _ Noble Gas' Activity Monitor DAILY - MONTHLY QUARTERLY AT LEAST ONCE A PER 18 MONTHS g k
'V g,3 h b. Particulate Activity Monitor DAILY N/A QUARTERLY AT LEAST ONCE A PER 18 MONTHS s 5 lll: ' N/A QUARTERLY AT LEAST ONCE Sampler Flow Rate DAILY
@ %g c. @ PER 18 MONTHS ~ ,
89 Measuring Device 1 g :j* NOTES:
@ (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of y, 5 this pathway, and control room alarm annunciation occurs if any of the following
- conditions exist:
== ' a. Instrument indicates measured levels at or above the alarm setpoint.
. - b. Instrument indicates a downscale failure (provides control room annunciation alarm
$ $ only).
O c. Instrument indicaies' a circuit failure (provides control room annunciation alarm only). 5 Im
'(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:
38 a. Instrument indicates measured level above the alarm setpoint on one channel, j $ b. Instrument indicates a failure by a Low Flow and Low Count Rate signal. a: tu g z (3) The CHANNEL FUNCTIONAL TEST shall also demonstrate that the control room local yy alarm occurs if the flow instrument indicates measured levels below the minimum and/or above the maximum alarm setpoint. gg (4) The' CHANNEL CAllBRATION shall be conducted in accordance with plant procedures. ODCM- 56 Rev. 5
' ~w v ,n<
3.4 Total Dose to a Member of the Public fa)__ g The dose equivalent to any MEMBER OF THE PUBLIC due to release of O' radioactivity and radiation, shall be limited to $ 25 mrem to the total body or any organ 5 (except the thyroid, which is limited to 5 75 mrem) over a period of one calendar year. h With the calculated doses from the release of radioactive materials in liquid or ' OI
,[ gaseous effluents exceeding twice the calendar year dose limits specified in Sections ,
E
- 3.2.26, 3.3.3b, or 3.3.3c, a determination should be made, including direct radiation 5 bi li from reactor containment and radioactive waste storage tanks to determine if the above ,
o b limits have been exceeded. If these limits have been exceeded, prepare and submit a g Special Report (including an analysis which estimates the radiation exposure to a O E g _
$ MEMBER OF THE PUBLIC for the calendar year) to the Director, Nuclear Reactor LJ g N Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555, within 5
m 8 g 30 days, which defines the corrective action to be taken to reduce subsequent releases fs 1 to prevent recurrence of exceeding these limits. If the release condition resulting in the j 1 excess has not already been corrected, the Special Report shall include a request for a I % va'riance in accordance with the provisions of 40 CFR 190. Submittal of the Special y $ ' Report is considered a timely request, and a variance is granted until staff action on the E request is complete. ET E 5
- s E
a $x o I $ u -- ODCM' 57 Rev.5
(~ (),/ Cumulative dose contributions from liquid and gaseous effluents shall be 4 A determined quarterly and annually in accordance with Section 2.0, Offsite Dose l lii O Calculations. s < E g , Cumulative dose contributions from direct radiation from the reactor containment l l or radioactive waste storage tanks shall be determined once per year in accordance 8 with Section 4.0, Radiological Environmental Monitoring Program. g , s 3 5 1 f ' This requirement is provided to meet the dose limitations of 40 CFR 190. ! _E Whenever the calculated doses from plant radioactive effluents exceed twice the o L design objective doses of Appendix 1, a Special Report will be submitted which S. N D l 1 8 describes a course of action which should result in the limitation of dose to a real ( - individual for 12 consecutive months to within the 40 CFR 190 limits. f& s For conservatism, for compliance with this limit, the maximum total dose to any 13 s MEMBER OF THE PUBLIC will be assumed to be the sum of the maximums from each
$ dose pathway even though the actual maximally exposed individual for each of the i s pathways could not be the same person.
sE
$ l The maximum potential dose to a MEMBER OF THE PUBLIC from direct
[ radiation from the containment and radioactive waste storage tanks is determined by B z y @ TLD dosimeters located at various locations around the perimeter of the LACBWR E Ei ti Z
? d lE n a 5
'% ) ODCM 58 Rev.5
I (J -
' access controlled area and the EFFLUENT RELEASE BOUNDARY for the ]
' l n
g ' environmental monitoring program. For compliance with this limit, the actual maximum { I __ possible exposure to an actual MEMBER OF THE PUBLIC from direct radiation may be - w .
.g determined from maximum possible exposure times relative to the continuous exposure
< Y d dose measured by the TLD's. Conservative maximum possible exposure times will be 5
{ 3 determined by actual observation of the areas of interest by LACBWR management i
& , ,. and/or security personnel.
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() - 4.0. RADIOLOGICAL ENVIRONMENTAL MONITORING J ? PROGRAM u : O t
;;; 4.1 Proaram Requirements e I R j
< j The Radiological Environmental Monitoring Program (REMP) shall conform to E,
the guidance of Appendix l to 10 CFR Part 50. The REMP shall provide the require- l h l 8
- g. ments for monitoring, sampling, analyzing, and reporting radiation and radionuclides in a: 1 E the environment resulting from the LACBWR facility and/or its effluents. These h
% requirements have been established to ensure the measurements of radiation and of 6 radioactive material in potential exposure pathways to MEMBERS OF THE PUBLIC are ,
1 s i 8 y performed. Various environmental samples will be taken within the area surrounding i O E L^CBwa end in seiected controiied or becxoround iocetions. An interieberetorv ! (
.f (Comparison Program shall be established to ensure that independent checks on the 1
,g gprecision and accuracy of the measurements of radioactive material in the
!1 S environmental sample matrices are performed as part of the Quality Assurance iii i s Program for environmental monitoring. ]
s= @o The radiological monitoring program required by this specification provides O Y
" measurements of radiation and of radioactive materials in those exposure pathways E and for those radionuclides, which lead to the highest potential radiation exposures of
'8 z s8
& d individuals resulting from plant effluents. This monitoring program theory supplements Z l 15 .
] d the radiological effluent monitoring program by verifying that the measurable EE 7 2 5 concentrations of radioactive materials and levels of radiation are not higher than (d l ODCM 60 Rev.5 ,
l
- n. - . . - _. .. . . . _. . - - -_ _ - . -
l O expected on the basis of the effluent measurements and modeling of the environmental t/_ e s . exposure pathways. 3 - The requirement for participation in an Interlaboratory Comparison Program is
's provided to ensure that independent checks on the precision and accuracy of the l measurements of radioactive materialin environmental samples are performed to j 0(g demonstrate that the results are reasonably valid.
5 E g 4.2 REMP Description b Radiological environmental monitoring samples will be collected and analyzed in L g i accordance with Table 4.1. The specific sample locations are listed in HSP-03.1. u T
- d. Section 3 of the Health and Safety Procedures (HSP's) shall contain procedures to g y provide specific guidance to the HP technicians in the collection and analysis of each j t a: environmental sample.
h % E o. x s 5 h o 5 E ,
? z 9 8 e d g z t
~
g $ v ODCM 61 Rev.5
, ~. .. OJ Prepared or Rtvised By Data Hesith Physics R: view -
. . .O Data Operations R; view Comm. Approval Dats O" _
LARRY L; NELSON 3/10/98 h_h / y(N//4 si <
//-V-fy -
87fM G M //////C -
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Table.43 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway - Number of ' Sampling and Collection . . and/or Sample : Samples W Frequency Type and Frequency cf Analysis
.(1) Analyze each filter for gross beta I. AIRBORNE Three (3) Continuous operation PARTICULATES - . of sampler with ' radioactivity > 24 hours following filter ;
sample collection as . change. Perform gamma isotopic analysis ' required by dust on each sample when gross beta activity is - loading, but at least > 10 times the control sample (La Crosse).
. weekly.
- (2) A composite of particulate filters from each ;
location will be gamma analyzed at least - !
' once per quarter. :
i~ ;
- 2. DIRECT ' Eight (8) - Atleast 1) Gamma dose'- at least semi-annually. *
[ RADIATION 'at least 2 monitors semiannually. j at each location. j
- 3. WATERBORNE Two (2) Monthly.= 1) Gamma isotopic analysis monthly on each i j _
sample. j F (River Water) 2). Tritium analysis on composite sample from each location quarterly. r
~
I-(A) Exact sample locations are listed in HSP-03.1. ODCM 62 Rev. 5 j i !
('h V VO O y Prepared or Revised By Date Health Physics Review Date Operations Review Comm. Approval Date LARRY L. NELSON 3/10/98 h # f M //ZI // 4/--97 f/ h _ /f/p/95
/ Talille /.1 -(cont'd)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Sampling and and/or Sample Samples W . Collection Frequency Type and Frequency of Analysis
- 4. RIVER Two (2) Semi-annually. (1) Gamma isotopic analysis on each SEDIMENT sample.
- 5. INGESTION
- a. Fish One (1) sample of two At least semi-annually. (1) Gamma isotopic analysis of the (2) different species in edible portions of each sample.
area important as a recreational or commercial species.
- b. Milk One (1) At least monthly when (1) Gamma isotopic analysis on each animals are on pasture sample.
(May thru October). t
- c. Vegetation One (1) At time of harvest. (1) Gamma isotopic analysis of the edible portion of each composite -
sample. (A) Exact sample locations are listed in HSP-03.1. ODCM 63 Rev.5
-..n_-.. - _ - . . . _ _ - - - _ - . . - _ _ - _ - - - _ _ _ _ _ _ _ . _ - _ - - _ _ _ _ - - - - . - - _ ~ - - _ - _ _ - . . - . - - - _ - - - - - - - - - _ - _ _ - - , , _ . . - - _ _ _- - _ _ _ _ . _ _ . _ - - _ - _ _ _ . _ - - - - . . - _ _ - - - . - . _ . - _ - . _ _ . . . . -
4.3 REMP Lower Limits of Detection (LLD)
\
g Ny The sampling techniques and counting equipment used for the analysis of O _'; samples collected as requirements of the REMP will meet LLD's calculated in w accordance with criteria of NUREG-0473, Rev. 2. LACBWR's LLD's are calculated g E 9 as follows and are essentially the same as those found in NUREG-0473, Rev. 2. E E-8i Table 4.2 lists these values.
.$ Il a ,
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x > g . s g 1 fi a z s , S E o S Ps E" z
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l e ai l ! 8 Z . E Y aE O!5 l i- ODCM 64 Rev, 5
-.--...._.m . . _ _ _ _ . . - . , _ _ , .. . .,
Propefed or Reveed By - Date _ Health Physics Review Date Operations Review Comm. Ay,,ieval Date
/r /N/fg:>
~
.< LARRY L. NELSON 3/10/98 Jh --- i /L JZpC // 8/ - 9 7 f/fd4#_h_
.c. .f 11.- 1
~4.3.1 ' Calculation of Lower Limits of Detection: .
~
The LLb is the smallest concentration of radioactive material in a sampie 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):
. '4.66 S3 LLD.= ' . E x V x 2.22 x Y x Exp (-AAt)
~
WHERE: LLD is the priori lower limit of detection as defined above (as picocurie per unit mass or volume).~ _
'S y is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute). l
.i E is the counting efficiency (as counts per gamma).
V. is the sample size (in units of mass or volume). f
~
2.22 is the number of transformations per minute per picocurie. l l
.. i Y is gamma abundance for isotope of interest.
i t A is the radioactive decay constant for the particular radionuclide. : l.
-is the elapsed time between sample collection (or end of the sample collection period) and time j At of counting.
t ODCM 65 Rev.5
,~ q ,,.
' ]
(.b Prepared or Revised By Date . Health Physics Review Date Operations Reyiew Comm. Approval Qate LARRY L. NELSON 3/10/98 h%_ & /jfl/M //- 8/- 97 g7/fujg% W //////gp ( / V // / Table 4.2 ENVIRONMENTAL SAMPLE ANALYSES LOWER LIMITS OF DETECTION VALUES (LLD) Sample Type Water Airborne Particulate Fish Milk Sediment Analysis pCi/i or Radiciodine (pCi/m ) (pCi/Kg, Wet) (pCill) (pCi/Kg Dry) Gross Beta 6 1 E-2 H-3 3500(2000)* Mn-54 ' 15 130 Co-60 15 130 Zn-65 30 260 Cs-134 15 5 E-2 130 15 150 Cs-137 18 6 E-2 150 18 180
- For drinking water.
66 Rev. 5 ODCM
/*
- 4.4 Interlaboratory Comparison Proaram An Interlaboratory Comparison Program will be established to ensure that the q ,
g-> analyses being performed to comply with the REMP is accurate. A suitable offsite k laboratory will be used to supply NIST traceable or equivalent standard spiked sample v l media for analysis. The offsite laboratory will supply a report to DPC of the comparison 8 g results. The Interlaboratory Comparison Program will be conducted annually. The i E . results of this comparison will be included in the Annual Radiological Environmental 8 i - Monitoring Report. R . o ' i N
, w 4.5 Reportina Requirements b h' An Annual Radiological Environmental Monitoring Report shall be p) a)
g submitted to the Administrator of the Regional Office of the NRC. This report 3 3 s E % , shall include summarized and tabulated results, including interpretations and '
.l %
analysis of data trends, of environmental samples taken _during the previous { - c 3 y calendar year. In the event that some results are not availabie for inclusion with x % _ _J the report, the report shall be submitted noting and explaining the reasons for j $ .the missing results. The missing data shall be submitted as soon as possible in o 5 , a supplementary report. ciE The report shall also include the following: a summary description of the 3z , s E Radiological Environmental Monitoring Program, a map of all sampling locations
.J E g keyed to a table giving distances and directions from the plant, the results of the Ee (3
v E 5 ODCM 67 Rev. 5
i V{
-d 3 Interlaboratory Comparison Program, and a discussion of all analyses in which l i
I the LLD was not achievable. l O t
~
le b) With the REMP program not being conducted as specified in Table 4.1,
, k prepare and submit to the Commission, in the Annual Radiological E!
$ Environmental Monitoring Report, a description of the reasons for not conducting o ,
. the program as required, analysis of the cause of unexpected results, and the j E%
g plans for preventing a recurrence.- '
.2 V g ,
o E$ With the Interlaboratory Comparisons not being performed, report the l c) Ry , corrective actions taken to prevent a recurrence to the Commission in the l i s> , i Radiological Environmental Monitoring Report. l pv 1
, d) With radiological environmental sample analysis in excess of the
$y reporting levels listed in Table 4.3, when averaged over any calendar quarter, g s s prepare and submit to the Commission a Special Report within 30 days, with a J' s
]e (, description of the reasons for exceeding these reporting levels.
== '
m 5 8 5 , 5 , 3 8 e s m w B Z _i ae 0 $ (v3 ODCM 68 Rev.5
j')/_ s _ Table 4.3 9 q h Reporting Levels for Radioactivity Concentrations 5 in Environmental Samples n
. Water Airborne. Particulate Fish * * - Milk -
k : ,. t. . . .. ;
' pCl/mY " pCi/kg (wet) pCill '
l FAnalysis lpCill . E
$ H-3
~
20,000 - - -
) Mn-54 1,000 - 30,000 -
-4 x
l E Co 300 - 10,000 l e k Zn-65 300 - 20,000 - o k-
- 30 10 1,000 60
[* Cs-134 e j S. Cs-137 50 20 2,000 70' l l s
- e -
l 5 E 8 r g l E I l S U E E n I g E z
.e o x $
C w is Z E la a $ O _!x_ 5 ODCM 69 Rev.5
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