ML20079J942
| ML20079J942 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 12/31/1983 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20079J932 | List: |
| References | |
| PROC-831231, NUDOCS 8401240460 | |
| Download: ML20079J942 (34) | |
Text
,, Offcito Does Calcclotier, 500001
~'
g 9
l Limerick Generating Station Units 1 and 2 Philadelphia Electric Company Docket Wos. 50-352 6 50-353 e
i i
t t
} .
O p
I t .
fN80A*oj$8l%,g,
_ _. _ _.. g l
REV.O 12/8 3
.- Tablo of ContCnto s
I. Purpose II. Liquid Pathway Dose Calculations A. Surveillance Requirement 4.11.1.1.2 i
B. Surveillance Requirement 4.11.1.2 C. Surveillance Requirement 4.11.1.3.1 III. Gaseous Pathway Dose Calculations A. Surveillance Requirement 4.11.2.1.1 B. Surveillance Requirement 4.11.2.2 C. Surveillance Requirement 4.11.2.3 D. Surveillance Requirement 4.11.2.4.1 IV. Nsclear Fuel Cycle Dose Assessment - 40 CPR 190 A. Surveillance Requirement 4.11.4.1 3
l B. Surveillance Requirement 4.11.4.2 V
T. Calendar Year Dose Calculations
.4 A. Unique Reporting Requirement 5.9.3.2 VI. Radiological Environmental Monitoring Program A. Surveillance Requirement 4.12.1 VII. Effluent Radiation Monitor Setpoints l
VIII. Bases L II . Liquid and Gaseous Effluent Flow Diagrams l
l l
f I
L i Rel.o 17-/83
I. ,,Purp*s7
~.
Tho purpo23 ef tho Offsit@ Des 2 Calcul3 tion Manuel in to fcatablich cethodolegies and precederse for calculating doses to individuals in areas at and beyond the SITE BOUNDARY due to radioactive effluent from Limerick Generating Station and establishing setpoints for radioactive effluent monitoring instrumentation. The results of these calculations are required to determine compliance with Appendix A to Operating Licenses (numbers to be assigned) , " Technical Specification and Bases for
)
Limerick Generating Stations Units No. 1 and 2.
i F II. Liquid Pathway Dose Calcuations A. S_urveillance Requirement 4.11.1.1.2 - Liquid Radwaste
' Release Compliance with 10CFR20 Limits l Limerick Generating Station Units 1 and 2 have one common discahrge' point for liquid releases. The following calculation assures that the radvaste release limits are met.
The flow rate of liquid radwaste released from the j site to areas at and beyond the SITE BOUNDARY shall be such that the concentration of radioactive material after dilution shall be limited to the concentration specified in 10 CFR 20.106 (a) for radionuclides other than noble gases and 2110-4 uCi/al total activity concentration for all noble gases as specified in Technical Specification 3.11.1.1. Each tank of ragioactive waste is sampled prior to release and is
. quantitatively analyzed for identifiable gamma emitters as specified in Table 4.11-1 of the Technical Specification. From this gamma isotopic analysis the maximum permissible release flow rate is determined as follows:
\
Determine a Dilution Factor by:
l Dilution Factor =
}{ uCi/al i MPC1 t - i
$. uti/ml i = the activity of each identified gamma 1
emitter in uCi/ml
}
l MPCi = The MPC specified in 10 CFR 20, Appendix B, l Table II, Column 2 for radionuclides other i than noble gases or 2110-* uCi/al for noble gases.
6
- . 90 '#
I ,,
D termine ths Mnximun Pernieciblo Roleae7 Rat 9 Mith this Dilution Factor by:
Rolcaco Rate (gpD) = __ A s
B X Dilution Factor A = The cooling tower blowdown volume which will provide dilution. Maximum flow rate is 10,000 gpa.
B = margin of assurance which includes consideration of the maximum error in the activity setpoint and the maximum error in the flow setpoint.
B. Surveillance Requirement 4.11.1.2 Dose contributions from liquid effluents released to areas at and beyond the SITE BOUNDARY shall be calculated using the equation below. This dose calculation uses as a minimum those appropriate radionuclides listed in Table II.A.1. These radionuclides account for virtually 100 percent of the total body dose and bone dose from liquid effluents.
[r a -
D T
=
i-A { At 1 iT i = 1 C
il F
1, where:
D Y
= the cumulative dose commitment to the total body or any organ, , from liquid effluents for the total time period a , in area p
i=1
{ 6t 1
At = the length of the 1th time period over which 1 C and F are averaged for the liquid release, il 1 in hours.
- C = the average concentration of radionuclide, i,
[ il in undiluted liquid effluent during time period ,
t from any liquid release, (determined by the effluent sampling analysis program, Technical j
specification Table 4.11.1.1-1, in uCi/al.
l A = the site related ingestion dose commitment iT f actor to the total body or organ,T , for each radionuclide listed in Table II.A.1, in j area-al per hr-uCi. See Site Specific Data.**
1 a,
co See Note 1 in Bases
.2.
REVO 12/85
~ F = the nazr field overnga dilution facter for 1 C during any liquid efflucnt rolsace.
il
. Defined as the ratio of tho caricun undiluted
, liquid vaste flow during release to the average flow from the discharge structure to the Schuylkill River.
II.C Surveillance Requirement 4.11.1.3.1 Projected dose contributions from liquid effluents shall be calculated using the methodology described in Section II.B.
t s
I .
I J
s o
'l 1
i e
I 4-
- I f
a REVo a/83. _ - _ . .
TABLE II.A.1 LIQUID EFFLUENT INGESTION POSE FACTORS .
(Dneny Correctod; A Dose Factor (area-al per hr-uci) iT Radionuclide Total Body Bone Cc-137 3.42x105 3.82x105 C3-134 5.79x105 2.98x105 P-32 5.11x10* 2.05x105 C2-136 8.42x10* 2.97x10*
zn-65 3.32x10* 2.31x10*
Sr-90 1.35x105 5.52x105 3.29x10-2
- E-3 Ba-24 1.35x102 1.35x102 I-131 1.16x102 1.40x102 5.70x102
[ 1.70x103 1.08x10*
F Te-129a an-54 8.34x102 8.34x102 2.00x102
- Co-58 F3-59 9.26x102 1.02x103 Tn-131a 3.88x101 9.53x102 B2-140 1.33x102 2.03x102 Te-132 1.21x103 1.99x103 L NOTE: The listed dose factors are for radionuclides that may be 3
detected in liquid effluents and have significant dose 1 conseguences. These factors are decayed for one day to account for the time between effluent release and ingestion of fish by the maximum exposed individual.
}
? O There is no bone dose factor given in R.G. 1.109 for these nuclides.
9 9
4 REVO 12/g3
111... Gaseous Pathway Dose Calculations A. Surveillanco Requires *nt 4.11 2.1.1
- l
, The dose rate in areas at and beyond the SITE BOUNDARY !
due to radioactive materials released in gaseous l efiluents shall be determined by the expressions !
below: ,
Noble Gases
, j The dose rate from radioactive noble gas releases shall be determined by either of two methods. Method (a) , the Isotopic Analysis Method, utilizes the results of noble gas analysis required by specification 4.11.2.1.1 and 4.11.2.1.2. Method (D) ,
the Gross Release Method, assumes that all noble gases released are the most limiting nuclide-Kr-88 for total body dose and Kr-87 for skin dose.
For normal operations, it is expected that method (a) will be used. However, if isotopic release data are not available method (b) can be used. Method (a) allows more operating flexibility by using data that y more accurately reflect actual releases.
- a. Isotopic Analysis Method D =
k[(K (X/Q) Q )
TB i 1 V iv Ds =
)b[ (L + 1.1M ) (X/Q) ]
- s i i i V where: -
The location is the site boudary, 762a ESE from the vents. This location results in the highest calculated dose to an individual from noble gase releases.
4 D = total body dose rate, in arca/yr.
TB 1 -
1 D = skin dose, in area /yr.
! s
,1 1 K = the total body dose factor due to gamma I
i emissions for each identified noble gas N radionuclide. Values are listed on 3 Table B-1, R.G. 1.109, in area /ur per j- per uCi/m3
?
(X/Q) = 6.29x10-7 sec/m3; the highest calculated y annual average relative concentration for any
ersa et er bsycad tho SITE BOUNDARY for all vent rolcesos (ESE boundary) .
, 0 = the rolenco rate of noble gna radionuclido,
, iv i, in gaseous effluents from all vent releases determined by isotopic anlaysis averaged over one hour, in uCi/sec.
L = the skin dose factor due to beta emissions i for each identified noble gas radionuclide.
Values are listed on Table B-1, R.G. 1.109, ,
in ares /yr per uci/m3 M = the air dose f actor due to ganna emissions i for each identified noble gas radionuclide. i Values are listed on Table B-1, R.G. 1.109, in arad/yr per uti/m3 1.1 = unit conversion, converts air dose to skin dose, ares /arad.
- b. Gross Release Method
- e i'
D =K (X/Q) Q TB V NV ll 1
g D = (L.+ 1.15) (X/Q) 0 l
s NV where:
The location is the site boundary, 762m ESE from the
-l vents. This location results in the highest calculated dose to an individual form noble gas releases.
D = total body dose rate, in area /yr.
TB D = skin dose rate, in area yr.
s K = 1.47x10* aren/yr per uCi/m3; the total body dose factor due to gamma emissions for Kr-88 (Reg. Guide 1.109, Table B-1) .
(X/Q) = 6.29x10-7 sec/m3; the highest calculated t v annual average relative concentration for
!i any area at or beyond the SITE BOUNDARY for all vent releases (ESE boundary) .
{
6 REvo C/r
~
. Q a the gro23 relenco rato of noble gac33 in NV gcceous offlu:nto frca vant rolcacts dotorcincd by gross activity vent comitors nycraged over one hour, in uCi/sec.
L = 9.73x103 ares /yr per Ci/m*; the skin dose factor due to beta emissions for Kr-87 (Reg.
Guide 1.109, Table B-1) .
M = 6.17x103 mrad /yr per uCi/ma; the air dose 3
factor due to gamma emissions for Kr-87 (Reg. Guide 1.109, Table B-1) .
l
- 2. Iodine-131, iodine-133, tritium, and radioactive materials in particulate form, other than noble l gases, with half-lives greater than eight days:
D =
(CF) )[ P [ W Q ]
T i i v iv l-
- where
The location is the site boundary, 762m ESE from the j vents.
D = dose rate to the thyrod, in ares /yr.
T
[ CF = 1.02; the correction f actor accounting f or the use of iodine-131 and iodine-133 in lieu of all radionuclides released in gaseous effluents.
P = 1.62x107 ares /yr per uCi/m3; the inhalation I-131 dose parameter for I-131 inhalation pathway.
- The dose f actor is based on the critical individual organ, thyroid, and most restrictive age group, child. All values are from Reg.
t Guide 1.109 (Tables E-5 and E-9) .-
'l P = 3.85x106 area /yr per uCi/m3; the inhalation
. I-333 dose parameter for I-133 inhalation pathway.
- The dose factor is besed on the critical
? individual organ, thyroid, and most restrictive j age group, child. All values are from Reg.
j Guide 1.109 (Table E-5 and E-9) .
+
W = 5.27x10-7 sec/m3; the highest calculated
- y annual average relative concentration for any j area at or beyond the SITE BOUNDARY for all
- vent-releases (ESE boundary) .
9 I
l l
9 REV.o(2hs
Q = the rolenco rnto of iodino-131 in gac ous IV offluente froa all vsnt rolocena, detorcined l by the ef fluent saspling and ennlysis progros l
, (Technical Specification Table 4.8.2) in uCi/sec.
III.B Surveillance Requirement 4.11.2.2 The air dose in areas at and beyond the SITE BOUNDARY due to noble gases released in gaseous effluents shall be determined by the expressions below.
The dose rate from radioactive noble gas releases shall be determined by either of two methods. Method (a) , the Isotopic Analysis Method, utilizes the results of noble gas analysis required by specification 4.11.2.1.1 and 4.11.2.1.2, Method (b), the Gross Release Method, assumes that all noble gases released are the most limiting nuclide
- Kr-88 for total body dose and Kr-87 for skin dose.
For normal operations, it is expected that method (a) will be used. However, if isotopic release data are not available method (b) can be used. Method (a) allows more
- operating flexibility by using data that more accurately reflect actual releases.
l 1. . for ganna radiation I
- a) Isotopic Analysis Method Dy =3.17x10-ej{_n(xyg} g
- 1 1 V 1V<
where:
!, The location is the SITE BOUNDARY, 762a ESE from the vents. This location results in the highest calculated gamma air dose from noble gas releases.
where:
l
-Dy = ganza air dose, in arad.
3.17x10-e = years per second.
1 M = the air dose f actor due to gamma emissions i for each identified noble gas radionuclide.
Values are listed on Table B-1, Reg.
l? Guide 1.109 in arad/yr per uCi/m3 l-3 (X/Q) = 6.29x10-7 sec/m3; the highest calculated i
f V average relative concentration from vent releases for any area at or beyond the SITE BOUNDARY.
RE\/.0 l1.l%
~
Q = the rolzcco cf noble gea rediensclidos, i, iY in gnsrous affluents free all vants ac detoroined by isotopic analysia, in uci.
, Releases shall be cumulative over the calendar quarter or year, as appropriate.
- b. Gross Release Method
.Dy = 3.17x10-s (M (I/0) Q v v D
where:
The location is the SITE BOUNDARY 762m ESE from the s vents. This location results in the highest
- calculated gamma air dose from noble gas releases.
Dy = gamma air dose, in urad.
3.17x10-8 = years per second.
M = 1.52x10* arad/yr per uCi/m3; the air dose factor due to gamma emissions for Kr-88 (Reg. Guide 1.109, Table B-1) .
(1/Q) = 6.29x10-7 sec/m3; the highest calculated j ,
V annual average relative concentration i
from vent releases for any area at or beyond the SITE BOUNDARY.
{
Q = the gross release of noble gas radio-
. v nuclides in gaseous effluents from all
, vents, determined by gross activity vent j monitors, in uCi. Releases shall be a cumulative over the calendar quarter or year as appropriate.
l
- 2. for beta radiation s
- a. Isotopic Analysis
- 3. -
D =3.17x10-8h N (1/0) Q
. i. i V iv, where:
N The location is the SITE BOUNDARY 762m ESE from the i vents. This location is the highest calculated gamma
/ air dose from noble gas releases.
A 3 3.17x10-8 = years per second.
4 N = the air dose f actor due to beta emissions i- for each identified noble gas radionuclide.
Velues are listed on Tablo B-1, Rag. Guide
.. 1.109, in cred/yr par uCi/cD.
, (X/Q) = 6.29x10-7 sec/03; the highest calculated y annual average relative cocentration from vent releases for any area at or beyond the SITE BOUNDARY.
Q = the release of noble gas radionuclide, iv i, in gaseous effluents from all vents as determined by isotopic analysis, in uC1.
Releases shall be cumulative over the calendar quarter or year, as appropriate.
- b. Gross Release Method D
p = 3.17x10-8 N (X/Q) Q v v where:
The location is the SITE BOUNDARY 762m ESE from the vents. This location results in the highest calculated gamma air dose from noble gas releases.
{ Dg
= beta air dose, in arad.
3.17x10-a = years per second.
j h = 1.03x10* mrad /yr per uCi/m3; the air dose factor due to beta emissions for Kr-87 (Reg.
i Guide 1.109, Table B-1) .
(X/Q) = 6.29x10-7 sec/m3; the highest calculated y annual average relative concentration from vent releases for any area at or beyond the SITE BOUNDARY.
Q = the gross release of noble gas radionuclides v in gaseous effluents from all vents determined by gross activity vent monitors, f in uCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.
III.C Surveillance Requirement The dose to an individual from Iodine-131, Iodine-133, tritium, and radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than eight days in gaseous effluents released to j areas at and beyond the SITE BOUNDARY shall be determined
, by the following expression:
)
D = 3.17 x 10-a (CF) (0.5) )[ R W Q I-I y IV,
'O REV O G/ir3
chara:
. Location in the critical pnthway dairy 17703 ESE froa
, vents.
D = critical organ dose, thyroid, from all pathways, in area.
3.17x10-* = years per second.
CF = 1.00; the correction f actor accounting for the use of Iodine-131 and Iodine-133 in lieu of all radionuclides released in gaseous effluents.
O.5 = fraction of iodine releases which are nonelemental.
R = 9.51x1011mr (area /yr) per uci/sec; the dose I-131 factor for Iodine-131. The dose factor is based on the critical individual organ, thryoid, and most restrictive age group, infant. See Site Specific Data.**
R = 8.13x10'a2 (aren/yr) per uCi/sec; the dose factor I-133 factor for Iodine-133. The dose factor is based on the critical individual organ, thyroid, and
. most restrictive age group, infant. See Site Specific Data.**
W = 3.93x10-10 meters-2; (D/Q) for the food v s pathway for vent releases.
r Q =
the release of Iodine-131 and/or Iodine-133 IV determined by the effluent sampling and analysis program (Technical Specification Table 4.11.2.1.2-1) in uCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.
III.D Surveillance Req uirerent 4.11.2.4.1 The projected doses from releases of gaseous effluents to
- areas at and beyond the SITE BOUNDARY shall be calculated
. in accordance with the following sections of this manual:
- a. ganna air dose - III.B.1
- b. beta air dose - III.B.2
- c. organ dose - III.C I6 C3 See Note 2 in Bases
" REVo \1/n
S
' ~
Tho projectcd deco calculaticn chs11 be based on expectsd rolcaca froa plant op:rction. Ths noreci ralssco pathuays rccult in the taxicuo relencas froD the plant. Any altsrnative rolenso pathways result in loest rolcases and therefore lower doses.
- IV. TOTAL DOSE A. Surveillance Requirement 4.11.4.1 If the doses as calculated by the equations in this manual do not exceed the limits given in Technical Specifications 3.11.1.2.a, 3.11.2.b, 3.11.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b by more than two times, the conditions of Technical Specification 3.11.4.2 have been met.
B. Surveillance Requirement 4.11.4.2 If the doses as calculated by the equations in this manual exceed the limits given in Technical Specifications 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b by more than two times, the maximum dose or dose commitment to a real individual shall be determined utilizing the methodology provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Releases of Reactor Efiluents for tho Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix
- I", Revision 1, October 1977. Any deviations from the methodology provided in Regulatory Guide 1.109 shall be documented in the Special Report to be prepared in accordance with Technical Specifice cion 3.11.4.1.
The cumulative dose contribution from direct radiation from the two reactors at the site and from radwaste storage shall be determined by the following methods:
Cumulative dose contribution from direct radiation =
Total dose at the site of interest (as evaluated by TLD measurement) -
Mean of background dose (as evaluated by TLD*s at background sites) -
Effluent contribution to dose (as evaluated above) .
This evaluation is in accordance with ANSI /ANS 6.6.1-
. 1979 Section 7. The error using this method is
- - estimated to be approximately 81 i
h
'L so m/s
i
, V.A Uniqu7 R9 porting Storir^m^nt (6-9 1.12) - Dose
. . calculations for the Radiation Dose Assessment Report Tho asce:ccont of radicticn docas for the rediction
, dose assessment report shall be performed utilizing the methodology provided in Regulatory Guide 1.109, j
" Calculation of Annual Doses to Man from Routine '
Releases of Reactor Effluents for the Purpose of 1 Evaluating Compliance with 10 CFR Part 50, Appendix !
I", Revision 1, October 1977. Any deviations from the methodology provided in Regulatory Guide 1.109 shall be documented in the radiation dose assessment report.
The meteorological conditions concurrent with the time of release of radioactive materials (as dete nined by i sampling frequency of measurement) or approximate methods shall be used as input to the dose model.
The Radiation Dose Assessment Report shall be submitted within 120 days after January 1 of each year in order to allow time for the calculation of radiation doses following publication of radioactive releases in the Radioactive Effluent Release Report.
There is a very short turnaround time between the determination of all radioactive releases and publication of the Radioactive Effluent Release l Report. This would not allow time for calculation of 1 , radiation doses in time for publication in the same report.
l
' VI.A Surveillance Requirement 4.12.1
- Th'e radiological environmental monitoring samples shall be collected pursuant to Table VI.A.1 from the locations shown on Figures VI.A.1, VI.A.2 and VI.A.3 and shall be analyzed pursuant to the requirements of Table 3.12-1.
l9 O
.l
/3
@El/O l')h3
l RA3ICLOGICAL'ENVIRONMONTAL BOZITORING PROGR13 l
EX POSURE PATHkAY NUMBER OF SAMPLES AND STATION STATION DISTANCE AND/OR SAMPLE SARPLE STATION NAME CODE- SECTOR (RILES) COMMENTS
- 1. Direct 40 LOCATIONS (a) TLD sites were chosen -in accordance.
Radiation (a) INNER RING LOCATIONS .
with Limerick Generating Station's
- 1) Evergreen & Sanatoga Road 3651 3 0.6 Technical Specifications table 3.12-7,
- 2) ' Sanatoga koad . 3S1 NME 0.6 Item 1. The inner ring and outer
- 3) Possua Hollow Road SSI ME 0.4 ring stations cover all sectors. -
- 4) LGS Training Center 7s t - ENE 0.5
- 5) Keen Road . 1051. E 0.5 The control and special interest
- 6) LGS Information Center 11S1 ESE 0.5 stations provide intornettom on
- 7) Longview Road, SE Sector 14S1. SE 0.6 population centers and other special Site Boundary interest locations. j
- 9) Railroad Track Along _1851 S 0.3 Longview Road
- 12) WSW Sector, Site Boundary 25S1 WSW 0.5-
- 13) neteocalogical Tower 2 Site 26S3 W 0.4
- 14) WNW Sector Site Boundary 29S1 WNW 0.5-
- 15) NW Sector Site Boundary 3251 NW 0.6
- 16) Meteorological Tower 1 Site 34S2 NNW 0.6 OUTER RING LOCATIONS
- 1) Ringing Rock Substation 35r1 N 4.2
- 2) Laughing Waters GSC 2E1 NME 5.1
- 3) Neiffer. Road 4E1 NE 4.6
- 4) Pheasant Road, Game Fara 701 ENE 4.2 Site
- 5) Transmission corrider, 10E1 E 3.9
- 6) Trappe Substation 10F3 ESE 5.5 I
- 7) Yaughn Substation 13E1 SE 4.3
- 8) Pikeland Substation 16F1 SSE 4.9
- 9) Showden Substation 19D1 S 3.6
- 10) Sheeder Substation 20F1 SSW 5.2
- 11) Porter's Hill Substation 24D1 SW 3.9
- 12) Transmission Corrider, 25D1 WSW 4.0 hofrecker and Kein Streets
- 13) Transmission Corrider, 28D2 W 3.8 W. Cedarville Road
- 14) Prince Street 29E1 WNW 4.9
- 15) Poplar Substation 31D2 NW 3.9
- 16) Yarnell Road 34E1 NMW 4.6 i
f*f G Q )'n*
L s - s 1 L J .s .>
- 1) Birch Sxbstetion 521 NE 25.8 .
- 2) Pottstora Landing Field C.C 1 ENE 2.1 9c1 .
- 3) Reed Road E 2.2 ,
- 4) King Road 13C1 SE 2.9
- 5) Spring City substation 15D1 SE . 3.2
- 6) Linfield Substation 17B1 S 1.6
- 7) Ellis woods Road 20D1 SSW 3.1
- 8) Lincoln Substation 31D1 NW 3.0 5 LOCATIONS
- 2. Airborne 1) Keen Road 1053 E 0.5 (b) These stations provide for coverage
- 2) LCS Information Center 11S1 ESE O .5 of the highest annual ground level Indiciodine and 3) Longview Road 14S1 SE 0.6 D/0, and a control location. Radio-Particulates 4) King Road .
13C1 SE 2.9 iodine cartridges which have been (b) 5) 2301 Market Street, 1384 SE 28.8 tested for performance by the Philadelphia, PA manufacturer are used at all times
- 3. W:terborne (c) 9 LOCATIONS (c) All surface and drinking stations have continuous samplers.
Stritce 1) Limerick Intake 2851 WSW 0.3 -
- 2) South Sector Fara Wear Site 18A1 S 1.0 Driaking 1) Phoenixville Water Works 15F7 SSE 5.2
- 2) Pottstown Water Authority 28F3 WWW 5.9
- 3) Philadelphia Suburban Water 15F4 SSE 7.8 Company a) Citizens Home water Company 1bC2 SSE 2.4 Sedicent From 1) Vincent Das Pool Area 16C4 S 1.9 Shoreline O. 11gsstion 6 LOCATIONS Rilk (d) 1) Control Station 22F1 (d) Bilk samples are taken f rom several f arms surrounding LGS. These farms
- 2) SC1
- 3) 9E1 include those with the highest dose
- 4) 17D1 potential from which samples are routinely available, as well as a control station. The locations of the farms is not listed herein due to a longstanding agreement with the farmers involved. In return for Leing allowed to sample and analyze the milk, PRCo has agreed not to divulge the location of the farms.
Fish (e) 1) Middle of Vincent Pool 16C5 SSE 1.9 (e) Two species of recretionally important fish, sunfish and brown bullhead, will Upstream to Pigeon Creek be sampled if available.
- 2) Upsteam of LGS, Kein Street 29C1 WNw 3.2 Bridge to Hanover Street Bridge RetO 12[83
Food Product 3 1)' LGS 1:1treation C;r.ter 1151 ESE 0.5 (f) Food prod: cts crs to be sarples c3 (f) part si th7 LGS Techtic31 Cpecifi- .
catiOO Pragr00 CCly if Cilk sa:Plitg is not pertorted. Th3 cilk pathway, .
which results in a higher nazione dose to humans than the vegetation pathway, is monitored at location near the site, and is a better indicator than vegeta-tation samples. In addition, no crops grown in the vicinity of lgs are irrigated with water in which liquid plaat vastes have been discharged. ,
i I
l e
i 1
e 16 r ,. an 1 ,
1 9
/
,.N w.er,
~
/
<9 ==m. <
ac=rw
( ', \!
..< M. .
.s. fs *,
. . . ..- .<. /
' 36 51
\ J
'34 $ 2.ey. e. ~.
~3
. ,yp;, g, H,.': .
w s.- . .
- qN 32 51 t., .
. . +,
SSI f . ,
,\
.. ., My 't*
/ .
.s
\ -
a-
, .. 4 \ ..
Ss* i <
. 2931 . ,. ., , ,E
, . .;.. 751 ,
's
- s .
e 'e ' ','s. * *....,
g . . , , , ,".
w 4: ,. ,.
8
' i :c,+ .- . '"
~ 2t 53 ' -
9, soss,
\
k, r
>, pp , . .4.g '
.}
? Q.) .
. . cas,e llS i i e 25S I' t \
a> .,:
s . .J .
. s . .
i- s , . .
e z3 s2. /. .,,,3kI'"3*
, . fj- .
' \- "' '
/ s, Yl ,
j . y . . :. .:... .:. . i . .'.'.,:: ..
N' .y
. }. *
. ,, i. -[,ihr, , -
165 2'e l ,,.~ 'f .
4 t yy /
.c-}
\
l l
1 1
1.lMERICK GENERATING STATION UNITS 1 AND 2 1
ENVIRONMENTAL SAMPLING STATIONS SITE BOUNDARY l
l} FIGURE VI.A.1 (?.EV, o i')./?3
- m. . _ - m espaTw WM . k l i1
/s . o ,e h y
/ .
saw ,sg ,#
/ ,
/- i.c, -,
2c,
! s v i e% %
~ /, s, 4El , 'y 3:02 #
unapuca 7El 29El 5CI
' 'I ,
3
' ~ ~
iCI e ?Cl
- f El .
l .- iori ,s, 3 1 Al' #
SSs e / eloF3
' C 8' '3C l ,/
, , 11 ,
2 Di ,e i e ,
)
. , e 8 EC 3El 200 l
/ ,
< song 24DI , [
's,' ITDI ,
"V# I 39 p 3 ,
e +
B <
bi h
/ 'w s&,,, ssrs
\
LIMERfCK GENERATING STATSON UNITS 1 AND 2 1
ENVIRONMENTAL SAMPLING STATIONS INTERMEDI ATE DISTANCE i
/7 FIGURE VI. A.2 94\/. O I A/t2
. aree N081?k NNE hE s
u.
MI pa. { mJ. IT
... 9 j g FT.964asant i one ,
~ .
. . . g.. , ,
Mr / . 1*
% .re' ' . g
.. y x
~ ;r;* .:. . -
, ')
e' '
8* C e13H4
') ESE i
M SE h .
LiteERICK GENERATING STATMNe 83dIT31 AND 2 ENVIRONMENTAL SAMPLING STATIONS DISTANT LOCATIONS j 1
/9 FIGURE VI. A.3 REV.o#,[t3 2
r Vll. ,5fflu7nt Radiation Monitor Setpoint Calculationc 9
A. Liquid Effluente
- 1. Radwaste Discharge Line Radiation Monitor -
Monitor alara setpoints will be determined in order to assure compliance with 10CFR20. The setpoints will indicate if the concentration of radionuclides in the lig"*d effluent at the site boundary is approaching the concentrations
, specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. The setpoints will j also assure that a concentration of 2x10-* uci/al for dissolved or entrained noble gases is not exceed ed . The following method applies to liquid releases fro.! the plant via the cooling tower blowdown line when determining the high-high 4 alara setpoint for the Liquid Radvaste Effluent Monitor during all operational conditions. When the high-high alara setpoint is reached or exceeded, the releases will be automatically terminated.
- a. The setpoint for the Liquid Radvaste
! Effluent monitor will be calculated as
(; follows:
j 1. Determine C t
}
C =
2[C x D t i
- 3g C l 4 i l BPC where:
C = concentration at the liquid radwaste discharge line t monitor (prior to dilution to assure 10CFR20.106 limits are not exceeded.
j[C = total concentration of liquid effluent discharge i prior to dilution with cooling tower blowdown; uCi/cc 3 = nargin of safety factor to assure that the high-r high alara vill terminate the discharge before 9 10CFR20 limits are exceeded.
l {Ci
= sum of the ratio of the isotopic concentrations j MPC divided by their respective HPC.
l 2D REv.o t9.{t3
D a di10tica fccter dco to blecdcca frca tha cocling
. tocer; calculatcd by dividing the totcl flou (cooling toc:r blerdcan plus rodcacto dicchcrgs flow) by the rcdwanto dicchargo floc.
- 2) Determine C.R.
C.R.
- C t
E where:
C.R. = the calculated monitor count rate above background attributable to the radionuclides; CPS E = the detection efficiency of the monitor; uCi/cc/ cps.
- 3) The monitor high-high alarm setpoint above background should be set at the C.R. value.
- b. The monitor high-high alarm setpoint will be calculated monthly. The calculation will be based on isotopes detected in the liquid radwaste sample tanks during the previous month. If there were no isotopes detected during the previous month then the annual average concentrations (EROL Table 3.5-3) of those isotopes listed in Table II. A.1 will be used to determine the setpoint. It the calculated setpoint is less than the existing monitor setpoint, the setpoint will be reduced to the new value. If the calculated setpoint is greater than the existing monitor setpoint, the setpoint may remain at the lower value or increased to the new value.
B. Gaseous Effluents
- 1. North and South Stack Yent Radiation Monitors -
Monitor alarm setpoints will be determined in order to assure compliance with 10CFR20. The setpoints will indicate if th dose rate at or beyond the site boundary due to radionuclides in the gaseous effluent released from the site is approaching 500 ares /yr to the whole body and 3000 ares /yr to the skin from noble gases, or 1500 aren/yr to the thyrod from I-131 and I-133 (inhalation pathway only) . The alarm setpoint for the gaseous effluent radiation monitors will be calculated as follows:
2.1 RW.D 0./83
. Q. North Cnd S3Sth StGck YGat N3blo COD Chnntol
- 1) DGtorcino C
. t C = 2.12E-3 0 t t F
where:
]t C = the concentration at the vent noble gas radiation t monitor which indicates that the 10CFR20 dose rate limit at the site boundary has been reached; I l
uci/cc 2.12E-3 = unit conversion f actor to convert uCi/sec/CFM to uCi/cc.
0 = the total release rato of all noble gas radionuclides t in the gaseous effluent (uCi/sec) based on the lower of either the whole body exposure limit (500erea/yr) or the skin exposure (3000eres/yr) Q will be
- t calculated as shown in Attachment 1.
F = anticipated maximum vent flow rate; CFM
- 2) Determine the noble gas channel j alara setpoint (S )
N S = 0.50 C N t where:
. 0.50 = margin of safety factor to assure that the site boundary limit is not exceeded due to the simultaneous releases from other vents.
- b. North and South Stack Yent Iodine Channel
- 1) Determine C t
C = 2.12E-3 Q t t F
y where:
C = the concentration at the vent iodine radiation t monitor which indicates that the 10CFR20 dose rate limit at the site boundary has been reached; 22 REv'o I2/83
- CCi/cc.
2.12E-3 = unit co2voretion f actor to conysrt uCi/ cec /CFM to
}, uti/cc.
0 = the total release rate of radioiodines in the t gaseous effluents (uci/sec) Q will be t
calculated as shown in Atthchment 1.
F = maximum antcipated vent flow; CFM.
- 2) Determine the iodine channel alara setpoint (S )
I
- S = 0.50 C I t where
0.50 = nargin of safety f actor to assure that the site boundary limit is not exceeded due to simultaneous releases from other vents.
- 2. The monitor alarm setpoints will be calculated monthly. These calculations will be based on isotopic analysis of releases made during the previous month. If there were no isotopes detected during the previous month then isotopic concentrations calculated from the expected annual average noble gas and iodine-131 and 131
. isotopic release rates (EROL Table 3.5-6) will be used to determine the setpoint. If any calculated setpoint is less than the existing monitor setpoint, the setpoint will be reduced to the new value. If the calculated setpoint is greater than the existing value, the setpoint may remain at the lower value or increased to the new value.
Due to the fact that I-131 and I-133 comprise 98.5% of the total dose based on expected annual average releases (LGS FSAR Table 11.3-1) and particulates contribute a minor fraction of the
~
total dose, a particulate channel setpoint will not be calculated for purposes of the ODCM.
- 3. Containment Purge Isolation
- a. Monitor alara setpoints will be determined for the North Stack Vent Wide Range Gas Monitor to initiate closure of the containment purge supply and exhaust lines in the event that high radioactivity O REVO89./83
roloases cro detected. The setpoint will be
.. determined to alarn and isolate containnent in the event that 10CFR20 dose rates at the site boundary are approached or exceeded.
a The setpoint for the Wide Range Gas Monitor will be calculated as follows:
- 1) Determine C t
C = 2.12E-3 0 t t F
i where:
C = the concentration at the Wide Bange Gas Radiation t Monitor which indicates that the 10CFR20 dose rate limit at the site boundary has been reached; uCi/cc 2.12E-3 = unit conversion f actor to conver t uCi/cc/CFM to
! uCi/Sec.
i i Q = the total release rate of all noble gas radionuclides
- in the gaseous effluent (uci/sec) based on the lower l of either the whole body exposure limit (500aren/yr)
- or the skin exposure limit (3000nren/yr) .
F = maximum anticipated vent flow rate; CFM.
- 2) Deterei.ne the Wide Range Gas Monitor trip setpoint (S )
- S = 0.50 C
)
N t I
where:
0.50 = nargin of safety factor to assure that the site i boundary limit is not exceeded.
1
- b. Prior to containment purge and venting, the
- monitor setpoint will be recalculated. The calculations will be based on the noble gases detectcd by isotopic analysis of the
, containment atmosphere. If the calculated y setpoint is less than the existing monitor setpoint, the setpoint will be reduced to the new value. If the calculated setpoint
. is greater than the existing value, the j setpoint may remain at the lower value or
- increased to the new value.
- 4 gw.o (2/es
ATTACHMENT 1 0 Calculations t
- 1. 0 = 500 t(whole body) (X/Q) f,KS , ,
Y 1 1 where:
0 = the total release rate of all noble gas t radionuclides in the gaseous effluent; uCi/sec.
(X/Q) = 6.29x10-7sec/m3; the highest calculated v annual average relative concentration for an area at or beyond the site boundary for all vent relesae (ESE boundary) .
, K = whole body gamma dose f actors due to noble i gases (f rom Reg. Guife 1.109, Table B-1) .
S = the fraction of the total radioactivity in the i gaseous effluent comprised by noble gase
( radionuclide "i".
- 2. Q = 3000 t (skin) (X/Q) ]' (L _ + 1.1M ) S v i i i i i
{K/Q) = 6.29x10-7sec/m3; the highest calculated v annual average relative concentration for an area at or beyond the site boundary for all vent rolesae (ESE boundary) .
K = beta skin dose factor due to noble gases i (from Reg. Guide 1.109, Table B-1) .
. M = air dose factor due to noble gases i (f rom Reg. Guide 1.109, Table B-1) .
S- = the fraction of the total radioactivity in the i gaseous effluent comprised by noble gase radionuclide "i".
- 3. Q = 1500 t (thyroid) (X/Q) d }I P 1A 1, , ,
i
' gEv. o #2
- z. _ _ _ _ _ _ __-__- _ _ _ _ _ _ _ _ _ _ _ -
.thsras Q = tho total relensa rato of radioicaines
, t in the gasocus afflunnt; uci/=sc.
(X/Q) =-S.27x10-7sec/m3; the highest calculated d annual average depleted concentration for an area at or beyond the site boundary for all vent relesae (ESE boundary).
P = inhalation dose factor for child thyroid for i radioiodines arem-m3/uCi-sec.
A = the fraction of the total radioactivity in the i gaseous effluent (iodine channel) comprised by radionuclide "i".
it is
?
1
+
l i
b
?
t Ab
@EV.O (2(?5
VII. , BASES Sita Sp*cific Data foto' 1: Liquid dose factors, A , for section III. A vere 1
developedusing the following site specific data.
The liquid pathways involved are drinking water and fish. The maximum exposed individual is an adult.
A = (U /D +U x BF ) K x DF i w w F i O i a = 730 liters per year; maximum adult usage of v drinking water (Reg . Guide 1.109, Table 3-5) .
D = 85; average annual dilution at Phoenixville Water w Authority intake.
U = 21 kg per year; maximum adult usage of fish (R eg .
F Guide 1.109, Table E-5) .
BF = bioaccumulation f actor for nuclide, i, in f resh-i water fish. Reg. Guide 1.109, Table A-1, except P-32 which uses a value of 3.0E03 pCi/kg per pCi/ liter.
K =. 1.14 x105 (10 6 pCi/uci x 10a ml/kg x 8760 hr/yr) j 0 units conversion factor.
DF = dose conversion factor for nuclide, i, for adults i in total body or bone, as applicable. Reg. Guide 1.109, Table E-11, except P-32 bone which uses a value of 3.0x10-6 The data for D was taken from data published in Limerick Generating Station Units 1 and 2 Environmental Report Operating License Stage, Volume 3. All other data except P-32 BF and DF were used as given in Reg. Guide 1.109, Revision 1, October 1977. The P-32 BF and DF were used in accordance with information supplied in Branagan, E. F.,
Nichols, C. R., and Willis, C. A., "The Importance of P-32 in Nuclear Reactor Liquid Effluents", NRC, 6/82.
Esto 2: To develop constant R for section III.C, the following site specific data were used-G H (D/Q) = K*Q (0 ) F xrx (DFL ) f (1-f ) -Ait j i F ap a i a p se f l
A+>
i w I
p K' = 106pci/uci unit conversion factor i
27 gv.oa/n1 l
Q = 6Kg/ day; goat's consuoption rate I
. U = 330 1/yr; yearly milk consumption by an infant ap A = 9.97 x 10-7 sec-1 decay constant for I-131 i
n A = 5.73 x 10-7 sec-2 decay constant for removal w of activity in leaf and plant surfaces.
- F = 6.0 x 10-2 day / liter, the stable element a transfer coefficient for I-131.
n r = 1.0 fraction of deposited radioiodine retained in goat's feed grass.
DFL = 1.39x10-2mren/pci - the thyroid ingestion dose i factor for I-131 in the infant.
8
^
f = 0.75; the fraction of theyear the goat is on n p pasture (average of all f arac f = 0.0; the fraction of goat feed taa: is stored s feed while the goat ison pasture (average of all f arms) .
Y = 0.7 Kg/m2 - the agricultural productivity of p pasture feed grass.
t = 2 days - the transport time from pasture to goat, l
f to milk, to receptor.
The pathway is the grass-goat milk ingestion pathway.
These data were derived from data published in Limerick Generating Station Units 1 and 2 Environmental Report Operating Stage, Volume 3. All other data were used as j given in Reg. Guide 1.109, Revision 1, October 1977.
- Similar data were used to develop the constant R for I-133.
! Surveillance Requirement 4.11.1.2 Liquid Pathway Dose Calculations The equations for calculating the doses due to the actual release
. rates of radioactive materials in liquid effluents were developed J
from the methodology provided in Regulatory Guide 1.109, t
"Celculation of Annual Doses to Man from Routine Releases of
! C actor Effluents for the Purpose of Evaluating Compliance with a 10CFRPart 50, Appendix I", Revision 1, October 1977 and NUREG-j 0133 " Preparation of Radiological Effluent Technical Spacifications for Nuclear Power Plants". October 1978.
l n acv o a/n
Surveillance Requireeent 4.11.2.1.1 and 4.11.2.1.2 - Dose Noble Gases The pguations for calculating the doses due to the actual release pates of radioactive noble gases in gaseous effluents were developed f rom the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance Uith 10 CFR Part 50, Appendix I", Revision 1, October 1977, NUREG-0133 " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", October 1978, and Regulatory Guide 1.111, " Methods for Estinating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases
- from Light-Water-Cooled Reactors," Revision 1, July 1977 with site specific dispersion curves and disperion methodology. The specified equations provide for determining the air doses in creas at and beyond the SITE BOUNDARY based upon the historical average atmospheric conditions.
The dose due to noble gas release as calculated by the Gross R21 ease Method is much more conservative than the dose calculated by the Isotopic Analysis Method. Assuming the release rates j given in Limerick Generating Station Units 1 and 2 Environmental Enport Operating License Stage, Volume 3, the values calculated by the Gross Release Method for total body dose rate and skin dose rate are 4.8 times and 3.25 times, respectively, the values calculated by the Isotopic Analysis Method.
1
-l The model Technical specification LCO for all radionuclides and i radioactive materials in particulate from and radionuclides other than noble gases requires that the instantaneous dose rate be loss than the equivalent of 1500 area per year. For the purpose of calculating this instantaneous dose rate, thyroid dose from e iodine-131 and iodine-133 through the inhalation pathway will be used. Since the expected annual releases presented in LGS FSAR Table 11.3-1 indicate that iodine-131 and iodine-133 releases I have the major dose impact this approach is appropriate. The
.value calculated is multiplied by 1.02 to account for the thyroid dose from all other nuclides. This allows for expedited analysis
. nnd calculation of compliance with the LCo.
Surveillance Requirement 4.11.2.2 and 4.11.2.3 - Dose Noble Gases The equations for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents were developed f rom the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CPR Part 50, Appendix I", Revision 1, October 1977, MUREG-0133 " Preparation of Radiological Effluent Technical specifications for Nuclear Power Plants", October 1978, and R3gulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-cooled Reactors", Revision 1. July 1977 with site specific dispersion curves and dispersion methodology. The
- 28 aev o a/n
cpecified equntions provide for doteroining the cir doses in Cr200 et and b2 yond the SITE BOUNDARY baned upon the historical ovcrago atrospheric conditions.
Th'$ dose due to noble gas releases as calcalated by the Gross Release Method is much more conservative than the dose calculated by the Isotopic Analysis Method. Assuming the release rates giv n in Limerick Generating Station Units 2 and 3 Environmental Report Operating License Stage, Volume 3, the values calculated by the Gross Release Method for total body dose rate and skin dose rate are 4.8 times and 3.7 times, respectively, the values calculated by the Isotopic Analysis Method.
Doa,, Iodine-131, Tritium, and Radioactive Material in 3 ' Particulate Fora The equations for calculating the doses due to the actual release rates of radioiodines, radioactive material in particulate form, cnd radionuclides other than noble gases with half-lives greater then 8 days were developed using the methodology provided in
, C:gulatory Guide 1.109, " Calculation of Annual Doses to Man from
' Routine Releases of Reactor Effluents for the Purpose of 4 Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 0 1, October 1977, NUREG-0133, " Preparation of Radiological
! Effluent Technical Specifications for Nuclear Power Plants",
fOctober1978,andRegulatoryGuide1.111,"MethodsforEstinating
- Atmocpheric Transport and Dispersion of Gaceous Effluents in 8 Csutine Releases from Light-Water-Cooled Reactors", Revision 1,
! Jaly 1977 with site specific dispersion curves and dispersion 6 csthodology. These equations provide for determining the actual dcats based upon the historical average atmospheric conditions.
Cocpliance with the 10 CFR 50 limits for radioiodines, a radioactive materials in particulate form and radionuclides other then noble gases with half lives greater than eight days is to be j dstcrained by calculating the thyroid dose from iodine-131 and isdine-133 releases. Since the iodine-131 and iodine-133 dose ccesunts for 99.97 percent of the total dose to the thyroid, the valuo calculated is not increased.
l 30 REV o I&S
., ., - e m
a e
FLOOR DRAIN SU8 SYSTEM ,
eneu t-u
- WASTE T AGE fleen omAte SAMPLE M me.1 e- Te Come $Yennel TE Fleen enAIII enveELL a nE ACien teCL CulrS pelt I > COLLECTies TE )
envwtLL a ntACien teCt suers uesT 2 y
TuneemE EmCL Sutet DesY t Tuneemt EeCL Sutes gelf 2 I
e FLeen enApg y
A 3 Fleen en%Ie eERIIe 4 >
fleelt MAas 3AaIPLE TE se. t )
5
, Ceme nEFUtiles TE SIEE SussP , sg i natWA8TE S ef f 5AS EeCL 5GMP floen enAle 14 95 teuer enam samrtE Ts atCvCtt * )
sonst u l nCute m n
- to wAsitstuostTa [ To Fleen onAm met nise u + steweewsamt
- To IvarenAfon TE envWELL & af ACTen f eCL SWIIPS Nat? I y envWtLL & nE ACTE 9 ESCL SURIPE Unti 2 STE Aas Leet enAss self1 l
un E Ct n o -Em .S nAeWAITE & eFFGAS teCL SM T.t
> Co LECT Ig U) E TE Cees $ Ten TE evtaf teW & EeWIP enAm fitTEn EeWIP enate otti:3 -
To wae87 enact TK Fleen onaas 3AartE 7K es.1 MCvCLE g,,,,,,,, .deser enase nWCU PisasE SEtanaten oECAuf Case PWASE SEPARATen of CAST 8885E IE
_ { g,ygg yg )
l nE ACien WEtt SEAL asPT5at MAas L To waste stueet TK f
~
INIff a To teUIP enAIG 9PtsT nEste TK nE ACien WEtt OEAL nsPT5M onAm WWIT 2 w- Cenesse rtsf rutt Cass oAssessou r--------------------------------------------- TeCoeLeeresEn i 8
L Aenemy onAm Ta evaartes ! CHEMICAL WASTE SUBSYSTEM ** n stoweeneimE g L A.se.s,av enAas sAartt is e.vEntien To Fle i
, . ,C. ,e on- -C--
,W C me
-1 Cmu,e,neeenase, me a ,
""8""'"en Ev .T -
i
, -um E n-4e--. .e.n. ,. i ,E. A,0.,en
===n E e e nu -m .-
.4.se.e ,, i ,,,,,,,e,,,,,,, . ,,,, ,,
,,,,m,, o i
5 CamCAt er.u n ) i m.e.T esu CA,ss.Cia"e*u.e's"'
mTEn ,1 C
u E,un,onAm e-e,mun.o.w eeu . C Ase A.s.I i -
.e.Aen. -
. = Cose .on i
,no-T im ou- o-- i E.A,so i
.e,. i Co. ,e eu.u -C-i 6 - - - - - - - - - - - - - - - - - - - - - - - - LA_
Cao eenge-t- - T,I -
i t . CeeCEm m n ogoeE o i
"'" ""'" e": =" " '
WeiIBAlei SNeP AnE A Suer
- ----------------- a anywf LL CmLLEe mAits enAes assie14 I CouTaet noeu CmtLEe mATEn enase n- LAument enAm Tu )
Come rto CEtt Costme Cost enau serfs 1 a a LAumnv enAm avenAm - Te CeeUse TeWEn SteWesse nE ACien EeCL PEnsemeEL SIIeWEn /\
getTS t & 2 LAgesav enAle Qt7 )
nasonsis EuCL PEnscenEt seeWt t , ,,,,,,, y LAUNDRY DRAIN SUBSYSTEM P
- STRE AM NUtstLRS REFLECT eATCH PROCESSHIG 0F CHEMICAL NOTE:lNFORRIAT10N ON STRE AM NURSeERS II ASTE VI A THE FLOOR DR AIN SUtSYSTEM (SEE STCTION 11.2.2.1.3) BDENTIFIED eY 13 GIVEN IN T Acte O. - **lNSTALLATION OF THIS PORTION OF THE CHEMichiWASTE SueSYSTEM ellLL NOT et CORAPLETED F1R INITIAL PLANT OPERATION.
1122 FIGunE Ne .I nEv0 M3 I
e-cu d
5 MC d I M N lR 4
-?
'l %
y)%Idi!,
F h h~P~.! :I ;f N 8
I:
.!{l ] l: . ..
g j i i.h) 7h*l j = -
.=
-e ! N'I '
SET 3 ) bp C ,~ [C= Us[ E! -W ?C -
~*
h .k
- ' I'.h f ;I< -
g
!i +
i 7 .y a/ & ]%.. _. . -,7 ,
l-A 7mc .' o-t ll4 y$@fa= g: 4 g.!
U$. [sh_Nd , l
. (L 1,[~
ilN '
.*I~ ') r-1 1 !!! !
l-
"g; F .-
~7 'a .
- ?" =:: [g .
- - - - gj gny iigta t - -
o 1qq, !.
- w:
.#P. g co ;i ul *
. ! J._Ji $ s *
--i 'j -! .l Ie I i.is-- .
kiY 1 iW>iki13 l> 1 p..
i I i ,
I i
h ';M; l@gi;,g , <
i
.". 4,,it IE inkikip i 4:.- j i l l l g.
j y ,a, -
1 ea _J i i , i ; _ ,, .
l '
b hjg
" j g
--:_la. ,y y. 3 i e m
- c. , mr.
. i. j ; ; m . , :+-- -
k N hk 1.,.! ! l',I e ---
[ Y p. l'- ....
.L< , t .e gi e J.'iQ.t! !u 91 Pib. !
lb 4;i t i 9 f;'l 6 i _
l r II H Id 4: id .
^$[ -~'" -!T ,,1 T~~
i I:l
',ijj>$gr%. f -i@---!m E I1 ,Mr. " hT f g J
k i== Q "
l
(!h . .
i i 1
h=j% k +t 'd 3,'
Ug Joaf 7a,,
-3'
.:ii ,, . +
.+ f3 a, s
p ,
i >r ;,n_ e.
- g,. 3 ,
~ E[dD(.z-r gig = = r.
l .;
s i t
-q%r 6- "!M
,g~@
l . II
< f ri lEli d2 i
,r.i (
~I,l U1 r tp iY y . .
i -
li F i,gy,j id [Ilyf I 7J i".54 il da l1lI ~j (' %# j; "M q 1 G Rt r, ;., '-
i
-~ ~C
~ '
~ ~~ f i g!.. 1I rI 18
^ b* !
_. }
G l 15 u Gi
$ !. ( s s .
"Al
_ Ime n )_ "A m %i 'l ' I. I. I. f l
l 31 ) Ra/ o -rt/a3 k (
. _ _ _ __