ML20214K491
ML20214K491 | |
Person / Time | |
---|---|
Site: | Farley |
Issue date: | 07/11/1986 |
From: | ALABAMA POWER CO. |
To: | |
Shared Package | |
ML20214K484 | List: |
References | |
PROC-860711, NUDOCS 8608210127 | |
Download: ML20214K491 (17) | |
Text
- _ _
INP-0-M-011
.O
', July 7, 1986 Revision 2 4
I h
ALABAMA POWER CCMPANY JOSEPH M. FARLEY NUCLEAR PIANT IMITS 1 AND 2 4
s S
. A F
E T ~
E O i T
E D
Approved:
[.0.
Technical Manager Date Issued: "7 - I l - 86 List of Effective Page Page Rev.
1,11 2 1-8 2 9-38 0 39,41,42,45-46, 1 49,50,52 1 40,43,44,47,48,51 2 ENV ODCW3 O
fDR609210127 860314 R ADOCK 05000348 PDR
~
FNP-0-M-Oll TABLE OF CatmNFS Page Table of Contents i
CDCM-Tech Spec. Cross Reference Table 11 Liquid Effluents 1
Gaseous Effluents 9 Noble Gases 17 Radioiodines and Radioactive Materials in Particulate Form 24 I
Dose Assessment for Environmental Radiation Standards 38
~
Radiological Environmental Monitoring #Locations 39 Determination of alarm trip Setpoints for Liquid Monitors 48 Determination of alarm trip setpoints for Gaseous Monitors 50 5
i Rev. 2' 1
I
, , - - - - - - - - ..n,-.n.. . . - . - - - - - , - . . - ....,,,,,.---,.,._,.,.-,,-,_-.,,,_,_,.-_._,,,,..--...,_..---.,---,,.,,--,.-,--!
PNP-0-M-011 CDCM-TECHNICAL SPECIFICATIONS
="*--=="=-"
O Radiological Effluent Technical Specification Dose calculation ODCM Section Methodology Page 3.3.3.10 Determination of Alarm Trip 48 Setpoints For Liquid Monitors 3.3.3.11 Determination of Alarm Trip 50 Setpoints For Gaseous Monitors 4.11.1.1.1 Liquid Effluents 1 4.11.1.1.2 Liquid Effluents 1 4.11.1.1.3 Liquid Effluents 1
. 4.11.1.2 Liquid Ef*1uents 1 4.11.1.3.1 Liquid Effluents 1 4.11.2.1.1 Noble Gases 17 i x 4.11.2.1.2 Gaseous Effluents 9
, 4.11.2.2 Noble Gases 17-23 4.11.2.3 Radiciodines and Radioactive 24-37 Materials in Particulate Form 4.11.2.4.1 Gaseous Effluents 9
, 4.11.4 Dose Assessment for Environmental 38 Radiation Standards 4.12.1 Radiological Environmental Monitoring 39-45 l 6.9.1.9 ODCM All 6.9.1.10 ODCM All 1
6.14 ODCM All 1
O 11 Rev. 2
PNP-0-M-011 l l
i Dose Calculation Due to Liquid Effluents 4.11.1.1.1 1 4.11.1.1.2 4.11.1.1.3 4.11.1.2 4.11.1.3.1 Liquid Effluents-Dose Calculations a
ne dose contributions for the total time period I atl 1-1 shall be determined by the following calculation and a cumulative summation-of these total body and any organ doses shall be maintained for each calendar quarter. tese dose contributions shall be calculated for all radionuclides measured in liquid effluents released to unrestricted area using the following expression:
m I at3 C i1 Fig]
D, = iI[A , 1-1 i
where: -
D, = The cumulative dose or dose connaitment to the total body or an organ T from the liquid effluents for the total time period m
O I at t, in mrem.
1-1 Atl = the length of the l'" time period over which C11 and F1 are averaged for all liquid releases, in hours.
C,1 - the average concentration of radionuclide i in undiluted liquid effluent during time period at from any liquid release, in t
pCi/ml.
A, i
= the site related ingestion dose and dose commitment factor to the total body or organ T for each identified principal gamma j and beta emitter, in arenVhr per pCi/ml.
l Ai , = k,U,BF gDFi where:
k, = unit conversion factor,1.14 x 105 (year /hr).(ml/1).(pci/ Ci).
U, = adult fish consumption, 21 kg/yr.
BFi = the bioaccumulation factor in freshwater fish for each measured radionuclide i, in pCi/kg per pCi/ liter (Table 1).
- O 1 Rev. 2 l
l l
f FNP-0-M-011
= the dose conversion factor for nuclide i for adults, in DF' arenVpci (Table 2). ,
F3 = the near field average dilution factor for cu during any liquid effluent release. Defined as the ratio of the maximum undiluted liquid waste flow during release to the product of the average flow from the site discharge structure to unrestricted receiving waters times 5. (5 is the site specific applicable factor for the mixing effect of the discharge structure.)
For radionuclides not determined in each batch or weekly composite, the dose contribution to the current calendar quarter cumulative summation may be approximated by assuming an average monthly concentration based on the previous monthly or quarterly composite analyses.
/,
O O 2 Rev. 2 i
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- 0RNL-Private Communication
- Frekd, A.M., "A Model for the Approximate Calculation of Safe Rates of Discharge into Marine Environments, " Health Physics, Vol. 13, p. 749, 1967.
- 0btained from Regulatory Guide 1.109 (March, 1976) 3 Rev. 2 p , ,v--,-~-v---,----,.-r- - - - , ,
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l Note: 3.3 reans insuf*ictent nu Or nat - .e ::se 'ac :e is <l.;E 20.
- 0btained from Regulatory Guide 1.109 (March, 1976) 5 Gen. Rev. 2
FNP-0-M-011 TA8LE 2*'(Continued)
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. 3.ftE=49 0.0 t.53E-47 5.40E-45 52TE 125* 2.oAE-Ce (
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527E 127* 5.78E-06 2.37E-os S . 2.6 E-0 7 1.73E-06 2.75E-05 3.0 2.27F-45 '
527E 127 t. toe-47 3.45E-os 2.3mr-on a.tgg oS a.aAE 47 1.6 q. nae-o*
52f! 129* 1.15E-05 a.30E=ot 1.82E-ce 3. 4 5 E -0 5 a.40E-05 3.0 5.79E-05 527E 129 3. t SE -0 8 1.19E-49 7.66E-09 2,att-05 1.32E-47 3.0 2.37E-06 527E v31* t.7aE-46 9.37E of 7.66E-07 t.3aE-06 9. 55 E =o 6 1.3 9 . 3 0 E -4 5 52r! 131 1.97E*08 t.2aE-09 e.22E=0* 1. a 2 E -0 9 * .soE-18 1.0 2.956-04 527! 132 2.53E-05 1.s4E-oe 1.51E-06 1. 8 0 E -0 * '.58E-45 1.0 7.7tE-05 527E t33* a.63F-48 !.90E-99 s.aAE-on 1.32g10 } .57E-a7 1.6 a.17E o#
52rE 13e 3.2aE-08 2.13 E -0 4 1.30E-0* 2./)(- $ . 35E=o1 J.J 4.daE-0*
53I 12* 3.27E-06 2.StE-06 *.22E-06 7 ?I:y31 t.35E-os 3.0 -
- 3. 4 4F-0 7 13t t30 7.57E-07 2.2af-46 9.att-47 2 . t -d -o . J ,48 E-o s i.3 1.82E os
$31 131 a. toe-0e i . i n s -o s 3.ait-o* 4 5 E -4 5 1.32E-65 a.) 1.575-0e 532 132 2.03E-07 5.23E-07 1.431-47 7.15E-Gi ". hat-07 3.6 1.32E-o7 l
- 0btained from Regulatory Guide 1.109 (March, 1976) 6 Gen. Rev. 2
b s .
FNP-0-M-011 N 2*(Continued) inc:.:sg sont t.:7tt Totar. nonT TIT 3cIn K::IrET I.1:NG GI-t11 53I 133 1.a3E-06 2.a4E-06 7.57E-07 4.77t=0a 4.31E-46 0.0 2.18E-06 531 134 1.06E-07 2.88E-07 1.03E-07 3.7aE-05 a.59E-07 0.0 2.51E-10 53! 135 a.a3E-07 t.17t=06 a.2*E-47 1. 51E =0 a t.56E-46 0.0 1.3tt=06 55G3 1339 2.13E-08 2.39E-08 2.30E-06 0.0 2. 3 8 E -4 8 3.43E-09 1. 5 4 E -0 4 55C3 13a 6.2?E-05 1.a8E-0a 1.2tE-09 0.0 a.50E-05 1.59E-05 2.59E-04 55CS 135 1.95E-05 t.50E 95 8.00E-46 n.n 6.32E-46 2.05E-06 2.2tE-07 55G3 13e 3.5tE-Oe 2.57E-05 1.35E-05 0.0 t.a3E-05 t.9eE-oe 2.92E-Ce 55C3 137 7. 9 8 E-0 5 1. 0 9E =0 a 7.15E-05 0.0 3.7tE-45 1.23E-05 2.10E-oe 55CS 138 5.52E-08 1.09E-97 5. ate =os 0.0 8.025-n8 7.92E-o9 a.e5E-t3 55G3 139 3. ate *06 5.J8E-08 L.35E-08 0.J a.07E-08 3.70E-09 0.0 568A 139 9.7tE-08 h.92E-11 2.$st-09 0.0 6.37E-tt 3.92E*11 1.72E*07 568A tuo 2.03E-05 ! . 55 E -4 9 1.3at-ot 0.0 9.68E-o* t. set =48 a.18E-05 5e8A tat 0.0 3.54E-11 1.59E-09 0.0 3.3tE-tt 2.02E-tt 2.221-17
. 568A ta2 2.13E-08 2.19E-tt 1.3at-49 0.0 1.55E-11 t.2aE-11 0.0 .
57tA too 2.50E-09 1.26E-09 3.3at-fo 0.0 0.0 0.0 9.25E-09 576A tat 3. tit-10 9.9tE-tt 1.e2E-11 0.0 0.0 0.0 1.18E-05 57bA ta2 1.2EE-10 S.42E-tt 1.a5E-11 0.0 0.0 0.0 a.25E-07 58CE tat 9.31E-49 6.3at-09 7. tee-to n.n 2. sat-o* o.0 2.a2E-05 58CE 143 .t.a5E-09 t.221-oe 1.35E-to 0.0 5.38F.-to n.0 a.56E-05 58CE tua a . 8 9 E -0 7 2.0aE-07 2.62E-08 0.0 1.2tE-47 0.0 1.65E-04 5989 143 8.2t!-o9 3.70E-09 a.57E-to 1.0 2.13E-09 9.0 a.03E-05 5989 taa 3.02E-tt 1.25E-11 1.53E-12 0.0 7.3eE-12 3.0 3.33E-18 5090 137 6.30F.-09 7.2SE-09 a.35E-to 0.0 a.25E-69 1.0 3.39E-05 t
6t8M 117 7.55E-08 7.10E-49 2.97E-49 0.0 1.3at-48 0.0 5.93E-06
!' 418" ta89 3.07E-04 7.964-09 6.Get-09 0.J 1.2tE-08 0.0 s . T aE =0 5 l
61PM ta8 7.tSE-09 1.19E-09 6.00E-10 0.0 2.25E-09 0.0 9.34F=05 6tPw tee t.52E-49 2.15E-to 9.79E-It 1.0 a.07E-to 0.0 a.03E-05 et** 151 a.91E-to 1.17E-to 5.92E-11 0.0 2.J4E-to 3.0 3.22E-45
, 62SM 151 6. 9 t E-0 8 1.19E-08 2.56E-09 0.0 1.33E-05 0.0 5.25E-46 l 62S9 153 5.54F-to 7.16E-to 5.23E-tt 0.0 2.3?E-to 1.0 2.55E-05 63Eu 152 1.45E-07 a.est=06 3.91E-03 0.0 2.15E-07 0.0 2.5eE-05 63EU 15e 6.16E-07 7.57E-08 5.3*E-OS 0.0 3.62E-07 3.3 5.84E-05 63EU 155 9.6tE-08 1.22E 44 7.SME-09 0.3 5.baE-49 9.o e.s0E-og e3Eu 15s t.31E-08 1.06E=0S 1.7tE-49 0.n 7.39E-04 0.3 7.236-05 6573 160 2.70E-48 0.0 5.76E-49 0.3 1.4aE-05 0.0 3.33E-05 57a0 the* !.70E-47 S.3af-09 6.utE=o9 1.3 1.26E=o7 3.0 3.0 Tua til 4.32E-09 3.24E-09 3.deE-10 3.J 3.0 1.J J.3dE*01 7en 155 a.06E-07 1.35E-07 1.a2E-06 0.0 a.3 3.0 1.56E-05 7ad 197 1.03E-07 9 . 5 2 E -o n 3.02E-44 a.1 1.3 1.1 2.62E-05
$289 213 1.53E-02 a.38E-03 5.saE=0a 3.0 1.23E-42 3.0 5.42E-05 63SI 210 a.o2E-07 3.14 E -0 6 3.87E-06 1.0 3.5aE-05 3.3 a.75E-05 Sap 0 210 3.57E-0a 7.57E-os S.60E-45 1.3 2.52E-03 3.0 e.3eE-45
- 0btained from Regulatory Guide 1.109 (March, 1976) 7 Gen. Rev. 2
FNP-0-M-011
\
G81.E 2* (Cont inued).
3tXL3E 30NE IIVE1 It7tAL 30DY I1tT30.'3 E3 NET 8444 223 a.99E-03
!.CIG C*-t1I 7.66E-04 9.*5E=0a 0.0 2.17E-on 3.0 3.2tE-os 4844 22a 1.62E-03 3.90E=ot 3.23E-04 0.0 1.1tE-os 3.0 3.40E ca Sees 225 % 57E-4 3 7.79E-06 t.3tE-01 0.0 2.2tt-os 6.0 3.06E-os
$8M4 22e 3.J5f-ot 5.75E=ct 2.211-01 0.0 L.a3E-Ou 8824 225 1.12E-01 3.0 3.32E 04 3.12E-ot 1.2tE-01 0.0 S . S a E =o 5 0.0 5.6aE-05 S*4C 225 a.u1F=o4 6.07E=o6 2.e*E-07 0.0 5.*oE-47 S.0 a 07E-os
$94C 227 1 .88E-o3 2.48E-o# 1.ttE=os 0.0 4.03E-05 0.0 7.4*E-05 907M 227 1.37E-of 2.a8E-07 3.96E-47 0.0 1. ale-on 0.0 5.40E-0a 9efw 229 a.9eF=os S.att-46 1. 64 E =o s 0.0 a.67F=of 0.0 5.n3E-04 90im 229 A.JeE-03 1.21E-0a 3.95E-os 0.0 5.80E=ou 3.0 5.12E=os 907d 230 2.08E-03 1.tSE=os 5.76E-05 0.0 5.69E-os 3.s 6.02E-05 907d 232 1.50E=43 t.01E=os a.ozg-45 6.0 a.ieE-aa 0.0 1.2eE-os 90T* 23a 5.02E-08 4.72E-09 2.321-09 0.0 2.a7E=oA 3.0 1.13E=os Staa 33g a, gag-03 1.56E-os 1.htE=0a 0.0 0.0 0.0 6.27E=0a 9tpa 233 5.26F=0* 1.06E-69 8.29E-11 0.0 3.**E-o* 3.0 1.6aE-05
- 92u 232 4.tuE-03 0.0 2.95E=oa o.0 f d.uTE-os 0.0 s . 72E-o 5 -
929 233 S.72E-os 3.0 5.2*E-05 040 2.0aE-os 3.0 6.27E=o5 920 23a 9.37E-44 0.0 5.t#E-05 0.0 t.seE-os S.o 6. tat-05 929 235 4.02E-os 0.0 4.SeE-05 0.0 1.87E=ou 0.0 7.81E-05 92U 236 8.02E oa 0.0 a.97E-05 0.0 1.*tE-os 0.0 5.76E-05 e2U 737 5.53F-OS 3.0 t.a7E=os 3.0 2.27E-07 1.0 1.*aE-os 42u 235 7.e7E=os 3.0 a.55E-05 0.0 1.75E=os 0.0 t.seE.ca 9348 237 1.3*E-03 1.20E=os 5.5*E-05 0.0 a. tee-04 3.0 7.9aE-05 93N8 239 t.37E-os 3.6st-to 2.11E-to 0.0 1.26E-o* S.0 1. alt-os 9348 238 1.29E-09 1.tSE-to 6.a4E-tt 0.0 3.65E-LQ 0.0 2.40E*05 9apu 238 6. 7 3F -o s 9.31E-45 1.67E-45 7.12E-05 0.0 a.0 7.30E-05
- a89 !38 7.60E-oa t.0ut-ou 1.89E-05 1.3 7.46E-oS 3.0 9.6ef=05 GaPU 240 7.56E-o# t.0aE=0s 1.88E-45 0.0 7.46E-05 0.0 3.75E-05 9aPU Zut 1. 5 e E -4 5 S.47E-07 3.33E-07 0.0 1.53E=ce 1.0 1.40E-06
- a89 2a2 7.22E-on o.e0E-of 1.7eE=os 4.0 7.54F-65 0.6 6.53E=os 9u84 2aa 4.e4E-48 1.tSE=os 2.13E=o5 0 . 0, 4.03E=o5 0.0 9.73E-05 95&M 2at 3.10E-os 2.79E-os 5.26E-05 0.0 3.4eE-on 0.0 7.22E-05 954w 2a2* 9.32E=on 2.7sF-os 5.a7E-45 0.0 a.SSE=on s.o s.3aE=o5 95a* 2u3 S.12E-os 2.13E-ca. 5.2aE-05 0.0 3.45E=ou 3.0 9.73E-05 96CM 2u2 t.54E oS t.aaE-oS 1.out-os 0.0 a.97E-os 3.0 7.92E-05 eeCu 2a3 3.u3E=os 2.stE-oa 3.77E-05 3.0 1.75E ou S.0 7.StE-05 l 9eCM 2aa 4.85d-os 2.07E*0s 2.SoE-05 0.0 1.3uC-cu 1.J 1.55i-o5 96C" 2u5 1.03E-o3 2.SSE-04 5.8tE-05 0.0 2.711-04 1.0 7.0aE-05 96CM 2ae t.02F-63 2.58E=ou 5.*oE-05 6.3 2.7tf-as a.3 s.stt-05 seC* 2a7 4.456-ou 2.83E-os 5.72E-05 0.0 2.e7E-os 3.0 a.0eE-05 96CM 2us e.27E-o3 2.33E-o3 a . 7 t E =o n 0.0 2.20E-03 0.0 1.47E-03 90C7 252 1.9eE-on 3.0 a.e5E-o6 3.0 0.0 3.0 2.SaE-oa
- 0btained from Regulatory Guide 1.109 (March, 1976) i 1
8 Gen. Rev. 2
O /'~'N ENP- 11 V -
TABLE 3.12-1 RADIOIDGICAL DNIi'ONMENTAL MCNI'IORING IDCATIONS EXPOSURE PATHWAY AND/OR SAMPLE SAMPLE IDCATIONS SAMPLE IDE!EIFICATICH
- 1. AIRBORNE .
- a. Particulate Indicator Stations. '
- River Intake Structure (ESE-0.8) PI - 0501 l South Perimeter (SSE-1.0) PI - 0701 Plant Entrance (WSW-0.9) PI - 1101 ,
North Perimeter (N-0.8) PI - 1601 Control Stations:
Blakely, Ga. (NE-15) PB - 0215 Dothan, Ala. (W-18) PB - 1218
- Neals Landing, Fl. (SSE-18) PB - 0718 l l Conmunity Stations:
Great Southern Paper Co. (SSE-3) PC - 0703 Ashford, AL. (WSW-8) s PC - 1108 Columbia, AL. (N-5) '
PC - 1605
- b. Radioiodine Indicator Stations:
- River Intake Structure (ESE-0.8) II - 0501 l South Perimeter (SSE-1.0) II - 0701 '
Plant Entrance (WSW-0.9) II - 1101 ,
North Perimeter (N-0.8) II - 1601 ,
Control Stations: 7 Blakely, Ga. (NE-15) IB - 0215 ;
Dothan, Ala. (W-18) IB - 1218 ,
- Neals Landing, Fl. (SSE-18) IB - 0718 I Cnmnnulity Stations: l
' Great Southern Paper Co. (SSE-3) IC - 0703 l }
l
- Nc? required.by Tech specs. Used as a spare station.
- Not required by Tech Specs. Used for comparison purposes with State of Ga. EPD. i 40 Rev. 2 DN ODCM/11 l
k .
TABLE 3.12-1 (con't)
EXPOSURE PATHWAY AND/OR SAMPLE SAMPLE IDCATIONS SAMPLE IDENTIFICATION
- 4. INGESTION A. Milk Indicator Station:
None Control Station:
Brooks-Silcox Dairy, Ashford, Ala. (WSW-10) MB - 1110
- b. Fish Indicator Station:
Smith Bend (River Mile-41)
Game Fish FGI Bottom Feeding Fish FBI Control Station:
Andrews Lock & Dam Reservoir (River Mile-47)
Game Fish s FGB Bottom Feeding Fish '
FBB
- c. Forage Indicator Stations:
South Southeast Perimeter (SSE-1.0) FI - 0701 North Perimeter (N-0.8) FI - 1601
I
- South Perimeter (S-1.0) FI - 0801
- Northeast Perimeter (NE-1.0) FI - 0201 Control Station:
Dothan, Alabama (W-18) FB - 1218
- Alternate forage plots.
43 Rev. 2 ENV ODCM/11
FNP-0-M-011 O .
J
- _ _oe_o_n_mq
+ r -
l
'! i 71-7s WAKE (Is l If X/Q = l.016 8
3 i
SEC/ M 14 2 W NE r, .
e : i-
+m
. . N ENE 3 -
- i 12 w
Mi< h 4 E
f";
. s ,
- -, -- e O *
~
[ 1 4
Md wSw 5 ...
. k gjg i.;;' t::=
)
q ,
. _[
'Q )
2 1. . . . . . . . -
7 N
l, l
m_ '/s ,
- k. 4 Y u __
_#A_ __ N__ _
~ '
4 FOR AGE SAMPLING A TLD SAMPLING
@ TLD. PARTICULATES S LODINE SAMPLING O -. - -
SCJlhE us FEET FIGURE 3.12-1 IN01CATOR SAMPLING LOCATIONS FOR AIRBORNE ENVIRONMENTAL RADBOACTIVITY AT THE FARLEY NUCLEAR PLANT.
u
'*
- RTP-0-M-011 I
ghastly
\ggN oi
/ !
is '
NNW NNE n 1 14 f 02 NE NW I
essa l
l ff ueLTom
" 03 is \ ENE WNw es 55
'l g -
s ww ' .
Y j
- a. . essaa I
N1 A A aswono . os is " CSE
-wsw -
NL g 55
""""d \ '
!- a =
Jannu 5
os of i I
saw sat j Y
f e we e i a . o
& TkB Sa6 FIGURE' 3.12-41. COMMUNITY (tNotCATOR E) SAMPLING LOCATIONS FOR AIR 80RNC RA010ACilVITY IN THC FARLEY NUCLEAR PLANY AREA.
47 Rev. 2 i
,
- FNP-0-M-Oll 3.3.3.10 Deter'mination of AlarnVIrip Setpoints for Liquid Monitors
.- R-18 Trip setpoint will be calculated based on manufacturers single isotope activity response curves for the detector being used according to the following expression; 4=K (F,+F,)
F, where:
4 K = monitor meter response (cpa) corresponding to the source activity (pciAal) calculated as measured monitor meter response taken from the calibration curve given by the manufacturer.
F, = liquid radwaste tank release flow rate (gpa) i
. F, - dilution water flow rate (gpm) 2 R-23A and R-23B Trip setpoints will be determined from; I -
- 1. During initial startup the trip setpoint will be taken from the manufacturers single isotope activity response curves for the detector being used. Setpoints will be less than
- 1. or equal to the count rate (cpm) corresponding to 1 X 10-,
pCiAnl in the effluent stream.
- 2. After sufficient data is accumulated to permit a calibration against act al representative effluent these monitor trip setpoints n.ay be calculated from the following expression; i
4 = h(x) + K (cpm) where:
l K = The zero intercept on the manufacturers curve obtained by taking the difference between the (cpm) actual response of the detector to the measured pCi/ml.
h(x) = the function which generates the manufacturers curve such to count rate corresponding that 14 X =0 1 fcpm) pCiAnl as measured in the effluent stream.
- l 1 v 48 Gen. Rev. 2 1
l
. . _ _ _ , - . _ . _ - . . . - , . . _ - . _ _ _ . _ _ . _ _ . . . . . _ . _ . . , _ _ _ __._, _,._._,_ _ - . - . . , . _ _ . - . . ~ . . _ - - ,
.,.m . . . ,_ . . _ . . . . . . . . . . . . _ _ . . . . . . _ . _ . . _ _ _ . . _ _ . . . . _ . . . . _ . ._. . . _. ..
FNP-0-M-011 Mi = air dose, factor due to gamma emissions for O identified noble gas isotope 1 (arad/yr per peiAn')
from Table 3 The actual monitor setpoints will be adjusted for a lower (thus more conservative) count rate based on the worst isotope release-dose rate Q as follows and need not be changed, except based,on reaportioning of allotted release fraction from operating experience as mentioned above.- From Table 3, Kr-89 would be the most restrictive isotope in either the total body or skin dose restrictions. Assuming that the total release consists of Kr-89, the skin dose equation is more restrictive than the whole body dose equation, and the release-dose rate limit would be calculated as:
Q, = 3000 mrenVyr F,
, (X/Q),10; pci/pci* F* (L,+1.1M,), and Q,, = 6.9x10',pci/sec (F,) .
- Q , - 4.3x10' pCi/sec (F,)
Based on maximum flow rate and conservative.
detector efficiency, the monitor setpoints s, (cpm) may be calculated as follows:
S, = Q, + b,,where
- (c)(f,)
b = monitor background count rate (cpm) l c= gross monitor calibration factor (pciAnl per l net cpm) -
= u+ m, where u= isotope concentration ( C1/ml) in the monitor at time of grab sample calibration (Noble gas
! release rate calculations)
! f, = maximum effluent flow rate (ml/sec) a= net monitor reading (cpm) at time of grab sample calibration (release rate calculations) l l
!O 51 Rev. 2 h
-. ,..,._-...-,_.._,___,.,-.._,._..___,__.____.-.r....,..... , _ . . . , , , , . . _ , . - _ _ _ . . _ _ _ _ - - _ _ . - . .