ML20097J455
| ML20097J455 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 09/14/1984 |
| From: | Kemper J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| OL, PROC-840914, NUDOCS 8409210254 | |
| Download: ML20097J455 (43) | |
Text
D Offcito Daco Celculctien Manu:1 Limerick Generating Station Units I and 2 j ;-
~'
, Philadelphia Electric Company Docket Mos. 50-352 C 50-353 O
~
B409210254 840914 m-PDR ADOCK 05000352 PDR SEP 141984
Tablo of Cantcnto t.
,y s
Eage
- Purpose
~I.
Liquid Pathway Dose Calculations A.
- Surveillance Requirement 4.11.1.1.2 3-8.
Surveillance Requirement 4.11.1.2 4
C.
Surveillance Requirement 4.11.1.3.1 5
III.
Gcseous Pat hway Dose Calculat ions A.
Surveillance Requirement 4.11.2.1.1 B.
Surveillance. Requirement 4.11.2.2 10 C.
Surveillance Requirement 4.11.2.3 13 D.
Surveillance Requirement 4.11.2.5.1 14 IV.
Nuclear Fuel Cycle Dose Assessment - 40 CFR 190 A.
Surveillance Requirement'4.11.4.1 16 B.
Surveillance Requirement 4.11.4.2 16 Calendar Year Dose Calculations A.
Unique Reporting Requirement 6.9.3.2 17 I.
Rtdiological Environmental Monitoring Program A.
Surveillance Requirement 4.12.1 17 II.
Effluent Radiation Monitor Setpoints 24 4
III. Beses 34
- X.
Liquid and Gaseous Effluent Flow Diagrams 39 f SEP 141984
,Purdbset 7T ho' purpose. o f t he Of f site Dose Calculat ion Manual is to
'catchlish met hodol ogi es and procedures for calculating dscos to individuals in areas at and beyond the SITE
'8OUNDARY due to radioactive ~
effluent from Limerick G:nsrating Station and establishing setpoints for redicactive-effluent monitoring instrumentation.
The
.rosults of t hese calculations are required to determine r ecepliance with Appendix A to Operating Licenses (numbers to be. assigned), ' "Tec hn i cal Specification and Bases for Lincrick Generating Station Units No. 1 and 2.
L l au l d - Pat hway Dose Calculations
.A.
Surveillance Reautrement 4.11.1.1.2 - Linuld Radwaste Release Comoliance wit h 10CFR20 L imit s Limerick. Generating Station Units 1 and 2 have one common di sc harge point for liquid releases under
- normal-circumstances.
In t he. event of heat exchanger leakage, additional release pat hways are possible through t he plant service water system and the RHR service water system.
Tre following calculat ion assures t hat t he redweste release limit s are met.
T he. f l ow rate of liquid redweste released f rom the site to areas at and beyond the SITE BOUNDARY shall be such t hat t he concentration of radioactive material af ter dilution shall be limited to the concentration i
specified in 10 CFR 20.106(a) for radionuclides other than the dissolved or entrained noble gases and 2x10-4 uCl/ml total activity concentration for all dissolved
-or entrained noble gases as specified in Tec hn i cal Specification 3.11.1.1.
Each tank of radioactive 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 l
follows:
l l
Determine a Dilution Factor hv
}{
l Dilution Factor =
uC1/ml i MPCI I
uCi/ml i = t he act ivity of each ident if ied gamma r
L emitter in uCl/ml l:
SEP 141984 P
+'-
e w-g y-
p--
wgp
-f.-eryy-9,-e
-6%
y-g--ytrum-r-*ps=m*g-e-y-ywg ay-F'v---tg1pf*--wpetie'+w WN-e mi rnumW WW WTI-N'*'=P**w-MM**f7=ts=ve-pe*F=---&Ne*NWWWWNW-*Br*195---
W-M
'MPCI : The MPC cp;cificd in 10 CFR 20, App:ndix B, Tcble II, Column 2 for rcdianuclidas othsr than dissolved or entrained noble gases or 2x10-4 uti/ml for dissolved or entrained nobic gases.
Any unidentified concentration is assigned an MPC value of 1X10-7 uC l.'m l.
Determine t he Maximum Permissible Release Rate with this Dilution Factor bv A
Release Rate (gpm)
B X Dilution Factor 1
A: The cooling tower blowdown volume which will provide dilution. Maximum flow rate is 10,000 gpm.
.B: margin of assurance which includes consideration of the maximum error in the activity setpoint and the maximum error in the flow setpoint and the possibility of multiple release pathways.
B.
Surveillance Reautrement 4.11.1.2 The primary method of calculating dose contributions from liquid effluents released to areas at or beyond the SITE BOUNDARY will be by using a computer-based calculational program developed using the equations and par meters of R.G.
1.109, Rev.
1, October, 1977 (see bases Note 4) for all organs and age groups.
The A values used for this calculation are located in the i
Appendix, Table 1.
Dose contributions from liquid effluents released to creas at and beyond the SITE BOUNDARY s hall 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.
[ At
[R [
C F
A l
D T
i i,
IC 1: 1 1
11 1,
t where:
D.
- the cumulat ive dose commitment to the total body or any organ, l', from liquid effluents in mrom f or the total t ime period m
{
At t
i=1 1
l l SEP 141984 l
B repsritd rotecco painto 3r *-
f a.
l Jkt '
t he l engt h o f t he Ith time period over which i
1 C
and F are averaged f or the liquid release, 11 1
in hou.s.
C
= t he a verage concent rat ion of radionuclide, i, il in uidiluted liquid effluent during time period Jht from any liquid release, (determined by the effluent sampling analysis program, Technical Specification Table 4.11.1.1-1), in uCi/ml.
the site related ingestion dose commitment A
IT f actor to the total body or organ,17, f or each radionuclide listed in Table II.A.I, in ersm-m1 per hr-uCl.
See Site Specific Data.ee the near field everage dilution factor for F
A C
during any liquid effluent release.
11 Defined as the ratio of the maximum undiluted liquid waste flow during release to the average flow f rom the discharge structure to the Schuylkill River.
I.C Survallianen Reautrement 4.11.t.3.1 Projected dose contributions f rom liquid ef fluents shall be calculated using the methodology described in Section II.B.
To estimate expected concentration of the various rcdlonuclides (C;g ) in the undiluted liquid effluent, t he duration of Ilquid release (At), and the near field average dilution factor (F ), the expected plant operating status y
chall be reviewed. If no operational changes are expected the same values as used which would ef fect Cg, Akt, or Fy to evaluate Section II.B may be used.
If any operational changes are expected during the the Fj following 31 days which could affect Cff, Jkt or values used shall be based on plant history. During the initial stages of plant operation, the values for Cff, tit,
as given in LG5 FSAR Section 11.2 and EROL Section end Ff 5.2 may be used.
i
- Soo Note 1 in Bases
. SEP 141984
4 TABLE II.A.1 9
LIQUID EFFLUENT INGESTION DOSE FACTORS (Decay Corrected)
A Dose Factor (mrem al per br-uci) i adlonuclide Total Body Bone 30-137 3.42x105 3.82x105 sc-134 5.79x105 2.98xt05 f-32 5.11xt0*
2.05x105 20-136 8.42x109 2.97x109 Bn-65
.3.32x109 2.31x109 Br-90 1.35x105 5.52x105
"-3 3.29xlO*8 e
c-24 1.35x102 1.35x102 1-131 1.16xt02 1.43xlO2 Os-60 5.70x102
?-133 1.23xlO' 2.3txtOi
- -55 1.06x102 6.61x102 ir-89 6.36x102 2.21x109 "c-1292 1.70x103 1.08x109
- n-54 8.34xlO2 8.34x102 Js-58 2.OOx102
'o-59 9.26x102 1.02x103
~c-13tm 3.88xlO2 9.53xlO2 s-140 1.33x101 2.03x102 e-132 1.21x103 1.99x103 OTE: The listed dose f actors are f or radionuclides that may be d;tected in liquid effluents and have significant dose esnsequences.
T hese factors are deccyed for one day to cccount for the time between af fluent release and ingestion
- of fish by the maximum exposed individual, an adult.
i There is no bone dose factor given in R.G.
1.109 f or these nuclides.
l.
l SEP 141984
'II.
-Gaseoss Fathwav Dose Calculations IThe.controling receptor locat ions for the gaseous pat hway d3ce calculations are based on a land-use census perf.ormed in 1975 to 1976 which has been periodically updated. The p30t'recent update was in 1983.
A.
Surveillance Reautrement 4.11.2.1.1 The dose rate in areas at and beyond the SITE BOUNDARY due to radioactive materials released in gaseous I
effluents s hall be determined by the expressions below:
1.
Noble Gases The dose rate from radioactive noble gas releases shall be determined by either of two methods.
Method (a),
t he Isotopic Analysis Method, utilizes the results of noble gas analysis required by specification 4.11.2.1.1 and 4.11.2.1.2.
Met hod (b),
the Gross Release Method, assumes that all noble gases released are the most limiting nuclide-Kr-88 f or 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 t hat more accurately reflect actual releases.
a.
Isotopic Analysis Method
][(K (X/Q) 0 )
D TB 1
i v
Iv
](((L + 1.1M ) (X/Q) I D
=
s i
i i
v where:
The location is the site boundary, 790m HE f rom the vents.
This locetion results in the highest calculated dose to an individual from noble gas releases.
D
= total body dose rate, in mrom/yr.
TB D
= skin dose, in mrem /yr.
5
.y.
SEP 141984
.. K
- the totol brdy dato fcctor dus to gamma
~ 'l emissiena for occh id:ntificd nsblo gas rcdienuclida. V luss cro listad en Table III. A.1 and are taken f rom R.G.
1.109, in mrom/yr per uCi/m3 (X/4)
- 1.tx10-5 sec/m3; the highest calculated v'
annual average relative concentration for any area at or beyond the SITE BOUNDARY f or all vent releases (NE boundary).
9
- the releasw rate of noble gas redionuclide, iv 1,.in gaseous effluents from all vent releases determined by isotopic analysis averaged over one hour, in uCi/sec.
L
- the skin dose f actor due to beta emissions i
for each identified noble gas radionuclide.
Values are listed on Table III.A.1 and are taken from R.G. 1.109, in mrom/yr per uCl/m3 M
- t he ai r dose f actor due t o gamma emi ss ions i
for each identified noble gas radionuclide.
Values are ilsted on Table III.A.1 and are taken from R.G.
1.109, in mead /yr per uCl/m3 1.1
= unit conversion, converts air dose to skin dose, mrem /arad.
b.
Gross Release Method D
= K (X/0)
Q TB V
MV D
= (L + l.lM) (X/0) 9 s
NV where:
The location is the site boundary, 790m NE from the vents.
This location results in the highest calculated dose to en Individual form noble gas releases.
l D
z total body dose rate, in mrom/yr.
TB D
8 skin dose rate, in mres yr.
s X
- 1.47x109 mrom/yr per uCl/m3s t he total body dose factor due to gamma emissions for Kr-88 (Reg. Guide 1.109, Table B-1).
t
.g.
SEP 141984
.._,.~m-...,._--,,__._,_.~.,_,,.,__
m.--w
_m_,..-y.,
- (X/9)
= 1.1x10-5 3
ccc/o ; the highsct calculsted v.
cnnuel cv:rc;o roletiva canecntretien for cny ce co ct er b:yand the SITE BOUNDARY fer all vent releases (HE boundary).
h the gross release rate of noble gases in
-PV gaseous affluents from vent releases determined by gross activity vent monitors averaged over one hour, in uCi/sec.
L
- 9.73x103 mren/yr per Ci/m3; the skin dose factor due to beta emissions for Kr-87 (Reg.
Guide 1.109, Table B-4).
M
= 6.17x103 mrad /yr per uCi/m3; the air dose factor due to gamma emissions for Kr-87 (Reg. Guide 1.109, Table B-1).
2.
T he primary method of calculating dose contribution from Iodine-131, Iodine-133, tritium, and radioactive material in particulate form, other than noble gases, with half-lives greater than eight days will be
.y using a computer-based calculational program developed using the equat ions and parameters of R.G.
1.109, Rev.
1, October, 1977 (see bases Note 43 for all organs and age groups.
If t he computer model is not available, the dose contributions from Iodine-131, Iodine-133,
- tritium, and radioactive. materials in particulate form, other then noble gases, with half-lives greater t han eight days will be calculated using the equation below:
D
= (CF)
P IW h 1 T
i i v iv where :
The location is the site boundary, 762m ESE from the vents.
D
= do se rat e t o t he t hyro i d, in mrom/yr.
T CF
= 1.02; t he correction factor accounting for the use of lodine-131 and iodine-133 in lieu of all radionuclides released in gaseous effluents. SEP 141984
3 a
P
= 1.62x107 trem/yr p;r uCl/a ; the inhalct icn I-131 daco p;ramster for I-131 inhalct ion pst hway.
The d2so fcctor lo b 2sd en the critical individual organ, thyroid, and most restrictive age group, child. All values are from Reg.
Guide 1.109 (Tables E-5 and E-9).ee P
= 3.85x105 mrem /yr per uCl/m3; the inhalation I-133 dose parameter f or I-133 inhalat ion pat hway.
The dose f actor is based on the crit ical individual organ, t hyroid, and most rest rict ive age group, child. All values are from Reg.
Guide 1.109 (Tables E-5 and E-9) ee W
= 1.00x10-5 sec/m3; the highest calculated v
annual average relative concentration for any area at or beyond the SITE BOUNDARY for all vent rileases (NE boundary).
Q
= the release rate of lodine-131 and/or IV lodine-133 in gaseous effluents from all vent releases, determined by the ef fluent sampling and analysis paogram (Technical Specification Table 4.8.2) in uCl/sec.
- II.B Surveillance Reautrement 4.11.2.2 The air dose in areas at and beyond the SITE BOUNDARY due to noble gases released in gaseous effluents s hall be d;termined by t he expressions below.
The dose rate from radioactive noble gas releases shall be datermined by either of two methods.
Method (a),
the Icstopic Analysis Method, utilizes the results of noble gas cnalysis 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 tots! body dose and Kr-87 for skin oose.
Fsr normal operations, it is expected that method (a) will ha used.
- However, if isotopic release data are not cvollable method (b) can be used. Method (a) allows more sp; rating flexibility by using data t hat wore accurately roflect actual releases.
$0c Note 2 in Bases SEP 141984
't.O tar ~ gamma rcdictign
=o a)
Isotopic Analysis Method 3.17x10-e[ 'M (X/Q) e
'Dj i
,i v
Iv, where :
T he location 'is the SITE BOUNDARY, 762e ESE f rom the vents.
.This location results in the highest calculated gamma air dose from noble gas releases, where:
D
- . gamma air dose, in mrad.
y, 3.17x10-e :-
years per second.
M the air dose f actor due to gamma emissions i
for each identified noble gas radionucilde.
Values are IIsted on Table III.A.1 and are taken from R.G. 1.109 in mrad /yr per uCl/m3
.(X/0) c't.1xt0-5 sec/m3; the highest calculated V
average relative concentration from vent releases f or any area at or beyond the SITE BOUNDARY.
the release of noble gas radionuclides, 1, 4
=
IV in gaseous effluents from all vents as determined by isotopic analysis, in uCl.
Releases shall be cumulat ie,e over the
~
calendar quarter or year, as appropriate.
b.
Gross Release Met hod D
= 3.17x10-e (M (X/0) 4)
I v
v wh.re:
The location is t he SITE BOUNDARY 790m HE f rom the vents.
This location results in t he highest calculated gamma air dose from noble pas releases.
gamma air dose, in mrad.
D
=
y 3.17x10-e :
years per second.
M 1.52xt09 mrad /yr per uCl/m3s the air dose factor due to gamma emissions for Kr-88 (Reg. Guide 1.109, Table B-1). SEP 141984
o (X/4)
= 1.tx10-5 cos/a3; the highest eclculcted V
annual cycrcg3 rolctivs etnccntrction frem vcnt rotecsce far cny creo et or beyond the SITE BOUNDARY.
the gross release of noble gas radio-9 y
nuclides in gaseous effluents from all vents, determined by gross activity vent monitors, in uCl.
Releases shall be cumulat ive over the' a.alendar quarter or year as appropriate, 2.
for beta radiation j
a.
Isotopic Analysis 3.17x10-']b N (X/Q) Q D
l,, i I v, v
where :
The location is the SITE BOUNDARY 790m HE f rom the vents. This location is the highest calculated gamma air dose from noble gas releases.
3.17x10-e : years per second.
N
= the air dose factor due to beta emissions i
for each identified noble gas radionuclide.
Values are listed on Table III.A.1 and are taken from Reg. Guide 1.109, in mrad /yr per uCl/m3 (X/4)
= 1.tx10-5 sec/m3s the highest calculated v
annual average relative concentration from vent releases for any area at or beyond the SITE BOUNDARY.
4
= the release of noble gas radionuclide, Iv I, in gaseous effluents from all vents as determined by isotopic analysis, in uCl.
Releases shall be cumulative over the calender quarter or year, as appropriate.
b.
Gross Release Met hod
- 3.17x10-8 N (X/0) e Dg v
v where:
T he location is t he SITE BOUNDARY 790m HE from the vents.
This location results in the highest calculated gemma air dose from noble gas releases. SEP 141984 o
9
,.~--,-,-_,v-,,,---,.c,,..
w e n, v -
,.e-,m-,w,,w~r w_ w w_mm,w,-p e--
o D a b tc cir does -in cred.
3.17x10-e : yacro per occznd.
N
= 1.03x104 mead /yr per uCl/m3; the air dose f actor due to beta emissions f or Kr-87 (Reg.
Guide 1.109, Table B-1).
(X/4)
= 1.1xl0-5 sec/m ; the highest calculated 3
v annual average relative concentration from vent releases f or any area at or beyond the SITE BOUNDARY.
9 the gross release of noble gas radionuclides v
in gaseous effluents from all vents determined by gross activity vent monitors, in uCl.
Releases shall be cumulative over the calender quarter or year, as appropriate.
II.C Surveillanen Reautrement 4.11.2.3 T he primary met hod of calculating dose to an Individual frcm Iodine-131.
Iodine-133,
- tritium, and radioactive materials in particulate form, other than noble gases, with half-Ilves greater than eight days in gaseous effluents released to areas at and beyond the SITE BOUNDARY, will be by using a computer-based calculational program developed using the equations and parameters of R.G.
1.109, Rev. I, Ostober, 1977 (see based Hote 4) for all organs and age getups.
If the computer model is not available, the following cxpression will be used:
D e 3.17 x 10-e (CF) ( 0.5) )[
R W 4 I
,1 v
I V, where:
Lozation is t he critical pathway dairy 1770m ESE from vcnts.
D critical organ dose, t hyrold, f rom all pat hways, in mrom.
3.17xl0-e : years per second.
CF s 1.00s t he correction f actor account ing f or the use of Iodine-131 and Iodine-133 in lieu of all radionuclides released in gaseous effluents.
0.5 fraction of lodine releases which are nonelemental. SEP 14 i>v,
9.51x1081=r (crem/yr) p:r uCi/ccc; the dico R,
=
I-131 fccter far Isdino-131.
The dsso fceter is b ssd an the critical individu:1 crg:n, thrysid, cnd most restrictive age group, infant. See Site Specific Data.*e R
= 8.13xlO'm2 (mrem /yr) per uCl/sec; the dose f actor I-133 factor for Iodine-133. The dose factor is based on the crit ical Individual organ, thyroid, and most restrictive age group, infant.
See Site Specific Data.ee W
= 1.82x10 *' met ers-z; (D/Q) for t he f ood v
pathway for vent releases.
4
- the release of Iodine-131 and/or Iodine-133 IV determined by the ef fluent sampling and analysis program (Technical Specificat ion Table 4.11.2.1.2-1) in uCl.
Releases shall be cumulat ive over the calender quarter or year, as appropriate.
(II.D Surveillance Reautrement 4.11.t,1,1 The projected doses from releases of gaseous effluents to crcas at and beyond the SITE BOUNDARY shall be calculated in accordance with the following sections of this manuals o.
gamma air dose - III.B.1 b.
beta air dose - III.B.2 c.
organ dose
- I!!.C The projected dose calculation shall be based on expected rolesses from plant operation.
The normal release pat hways rcsult in the maximum releases from t he plant.
Any alternative release pathways result in lower releases and t heref ore lower doses.
To estimate the expected releases of noble gases and redlolodines in gaseous effluents, the expected plant cp: rating status s hall be reviewed.
If no operational shanges are expected which would af fect t he magnitude or type of releases t he same values used to evaluate Sect ions III.B.1, III.B.2 and III.C may be used.
l If any operational c hanges are expected during the following 31 days which could af fect the magnitude or type of releases, the values used s hall be based on plant history. During the initial stages of plant operation t he values for releases expected as given in LGS FSAR Section 11.3 may be used.
500 Note 3 in Bases l L SEP 141984 1
e
. TABLE III.A.1 D0'SE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES
-Air #(MI) 7-Bodv##(KI)
'uclide
,$-air #(NI)
_[-Skin ##(LI) 1.93E-05 7.56E-05 r-83m 2.88E-04###
1
,r-85a 1.97E-03 1.46E-03 1.23E-03 1.17E-03
!r-85 f.95E-03 1.34E-03 1.72E-05 1.61E-05 (r-87 1.03E-02 9.73E-03 6.17E-03 5.92E-03 3r-88 2.93E-03 2.37E-03 1.52E-02 1.47E-02 3r-89 1.06E-02 1.01E-02 1.73E-02 1.66E-02 sr-90 7.83E-03 7.29E-03 1.63E-02 1.56E-02 00-131a f.IIE-03 4.76E-04 1.56E-04 9.15E-05
<C-133m 1.48E-03 9.94E-04 3.27E-04 2.51E-04
<0-133 1.05E-03 3.06E-04 3.53E-04 2.94E-04 C-135m 7.39E-04 7.llE-04 3.36E-03 3.12E-03
'c-135 2.46E-03 f.86E-03 1.92E-03 1.81E-03 c-137 1.27E-02 1.22E-02 1.5tE-03 1.42E-03
- c-138 4.75E-03 4.13E-03 9.21E-03 8.83E-03
\\r-41 3.28E-03 2.69E-03 9.30E-03 8.84E-03 enrad-m3 pCl yr Cemeen-m3 pCl yr
- CO2.88,E-04 s 2.88 x 10 *
- EFERENCE: Regulatory Guide 1.109, Revision I, October 1977 SEP 141984
V.-
A'.
Surveillance Reautrement 4.11.4.1 If t he doses as calculated by the equat ions in this manual do not exceed the limits given in Technical Specifications 3.11.1.2.a, 3.11.2.b.
3.fl.2.a.
3.11.2.2.b, 3.11.2.3.a. or 3.11.2.3.b by more t han two
. times,
. t he conditions of Technical Specification 3.11.4.2 have been met.
B..
Surveillance Reautrement 4.11.4.2 If t he doses as calculated by t he equat ions in this manual exceed t he limits given in Tec hn ical 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 t han two times, the maximum dose or dose commitment to a real individual shall be determined utilizing the met hodol ogy provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compilance with 10 CFR Part 50, Appendix I",
Revision I, October 1977. Any deviat ions f rom the methodology provided in Regulatory Guide 1.109 shall be documented in the Special Report to be prepared in accordance with Technical Specification 3.11.4.1.
The cumulative dose contribution from direct radiation f rom the two reactors at the site and from 'radwaste storage shall be determined by the f ollowing methods:
Cumulative dose contribution from direct radiation c 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).
The method provided in the second paragraph above is used only to evaluate t he contribution from direct radiation dose.
T he direct radiation dose is then added to the dose or dose commitment determined in accordance with t he met hods in the first paragraph above to determine total dose f rom all pathways.
This evaluat ion is in accordance with ANSI /ANS 6.6.1-1979 Section 7.
T he error using this met hod is est imated to be approximately 4%. SEP 141984
- .A Unious Rooertina Renuirement (6.9.1.12) - Does calculations
- . for t he Radlemet ive Ef fluent Release Renort T he ' assessment of radiat ion doses f or t he radiat ion dose
.ccrossment report s hall be performed utilizing the
. cat hodology provided in Regulatory Guide 1.109, "Colculation of Annual Doses to Man from Routine Releases
.of Reactor' Effluents for the Purpose of Evaluating Crmpliance with 10 CFR Part 50, Appendix I",
Revision 1,
02tober 1977. Any deviat ions f rom t he methodology provided in Regulatory Guide 1.109 s hall be documented in t he radiation dose assessment report.
The meteorological condit ions concurrent with t he t ime of r lease of radioactive materials (as determined by sampling frequency of measurement) or approximate methods shall be us d as input to t he dose model.
The Radioactive Ef fluent Release Report shall be submitted within 60 days af ter January 1 of each year.
>I. A Surveillance Reautrement 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table VI. A. I f rom the locat ions shoun cn Figures VI. A.1, VI. A.2 and VI. A.3 and shall be analyzed pursuant to t he requirement s of Table 3.12-1 of the LGS Technical Specif icat ions.
II.A Surveillance Renuirement 4.12.3 Pursuant to Section 4.12.3 of t he LGS Technical Sp:cificat ions, t he laboratory performing t he radiological cnvironmental analyses s hall participate in an interleboratory comparison program which has been approved by the NRC.
This program is the Environmental Protect ion Agency's (EPA's) Environmental Laboratory Intercomparison Studies (cross c heck ) Program. Our participation code is CJ.
Participation includes all of t i.e determinations (campte. medium-redionuclide combination) t hat are of f ered by t he EPA and t hat are also included in t he monitoring prcgram.
The results of the analysis of these cross check samples will be included in t he Annual Radiological E.;vironmental Operating Report.
1 SEP 141984
e TABLE WI.A.1 R&DIOLOGICSL ENVIRONMENTAL MONITORING PROGRan E X POSW E E PATNut?
NWWSER OF SAMPLES AND STATION STATION DISTANCE sus #0B SAMPLE SAMPLE STATION NARE CODE SECTOR (MILES)
C0ftMENTS
- Street 40 LOCATIONS tal TLS sites were chosen in accordance Redsation tal INNER SING 10 CATIONS with timerick Generating Station's IS Evergreen E Senatoga Road 36S1 N
9.6 Technical Specifications Table 3.12-7.
Il Senatoga Bond 35%
NNE 9.6 Itea 1.
The inner ring and outer 33 Possue nellem Reed SSI NE 9.4 sing stations sewer all sesters.
43 ESS Training Canter TSt ENE 4.5 53 Eeen Reed 1933 E
e.5 The sentrol and spesial interest 69 EES Information Center 1939 ESE 0.5 stations provide information en
- 7) Longview Bead. SE Sester 1939 SE 0.6 yeyulatten centers and other special Site Boundary interest lesations.
83 Longview Road. SSE Sester 1632 SSE S.4 Site Soundary 93 Re11 read Track along 1831 S
9.3 Longvieu Road 103 Impounding Desia. SSU SISI SSN 0.5 Sester Site soundary 913 Transmission Teuer. Su 2332 SW 9.5 Seeter Site Boundary 129 USE Sector. Site Soundary 25St usu S.5 133 noteorelegical Tower 2 Site 2633 u
9.4 ft) Inr4 Sester Site Boundary 2959 WNW 0.5 153 Nu Sester Site soundary 32St NW 9.6 163 festeerstegical Temer 1 Site 3432 NNW 9.6 OWTER SING 10 CATIONS 13 singing Rock Substation 35F1 M
4.2 23 Eaughing Waters GSC 2Et NME 5.1
- 3) Neiffer Reed 4Et NE 4.6 43 Pheasant Road. Saee Fare 7El ENE 4.2 Site 53 Transatssion cerrader.
lett E
3.9 63 Trappe Substation ter3 ESE 5.5 73 Waugha Substation 13E9 SE 4.3 88 Pikeland substation 16Ft SSE 4.9
- 9) Shouden Substation 1991 3
3.6 ISS Sheeder Substation 20rt SSW 5.2 113 Petter's Mill Substation 1991 SW 3.9 128 Transmission Corrider.
2534 MSW 4.0 soffecker and Eoin Streets 133 Transassoien Corrider.
2003 u
3.8 W. Cedarville Road 143 Prince Street 29Et WNW 4.9 153 Pepter Substation 3932 NW 3.9 163 Torne11 Road 34Et NNW 4.6 SEP 141984
-/r-
.~ o
CONTROL ENS SPECIAL INTEREST
)
LeCOTIONS 13 Cinch SubsOcties (cont 201) 5N1 NE 25.4 23 Fattatema Landing Fi 13 6C1 EME 2.1 i
)
33 Reed Road 9C1 E
2.2 43 King Road 13C1 SE 2.9 53 Spring City substation 1531 SE 3.2
)
. 63 Linfield Substation 1731 5
1.6 73 Ellis Weeds Road test SSN 3.1 83 Lincola Substation 3131 Wu 3.8
)
5 LeCATIous
- 2. Althorne 13 Keen Reed 1953 E
0.5 (h) These stations provide for eeverage l
)
23 Les Informaties Center 1151 ESE 0.5 of the highest ammust ground level i
Redieiedine and 33 Leagviou Road 1951 SE 6.6 3/t. and a control location.
Radio-Particulates 43 King Reed 13C1 SE 2.9 iodine cartridges which have beem
)
(b) 53 2301 Market Street.
13N4 SE 28.8 tested for performance by the Philadelphia. FA (control) meaufacturer are used at all times
}
}
- 3. Waterberne (e) 9 LOCATIONS to) All surfose and drinking stations have
^
continuous samplers, i
Surface 13 Limerisk Intake (eentrol) 2451 USN 9.3 3
23 Linfield Bridge 1652 SSE 1.1 i
ereund 13 Les Information Center 1151 ESE e.5 1
23 South Seeter Farm Wear Site 18A1 3
1.0 i
)
Stinking 13 Phoeminv111e Mater Works 15r7 SSE 5.2 23 Fettstems Meter Authority 2SF3 MMu 5.9 j)
(eentrol) 3 33 Philadelphia suburban unter 15F4 SSE 7.8 1l company 43 Citizens Nome Water Company 16C2 SSE 2.4 i
)
Sediment Frea 13 Vincent Bam Pool Area 16C4 5
1.9 i
Shoreline
)
- 4. Ingestion 6 LOCATIONS
~
I Milk (d) 13 control Station 22F1 (d) Milk samples are taken free several 23 5C1 farms surrounding 165.
These farms 33 1031 include these with the highest dose 3
43 2531 potential from which samples are routinely available, as well as a j
oomtrol station.
The locations of the 5
)*
farms is not listed hereia due to a longstanding agreement with the faraeze inwelved. In return for being allowed
)
to sample and smalyse the milk. FEco has agreed met to divulge the location of l
the farms.
i
)
i
)
i
)
SEP 141984 l
3
-n-
P e
F a s ts tel il Niddle of %*acent peel 16CS SSR
- 1. 9 '
tel Two species of meeretienelly important upstreme to pageen Creek fish. sunfish and brown bullhead, will be sampled if available.
33 upsteem of ESS. Kate Street 39CS unas 3.2 Bridge to Wenever Street gradge (controll Feed Fredeets
- 1) ECS Information Center 1939 ESE S.5 (f) Feed produets are to be semples as Ef8 part ei the LES Technical Spesaf t-catica progree only af milk sampling-is met performed. The milk pathuay, which results in a higher menteue dose to humans them the wegetation pathuey.
As monitored at lesation meer the site, and as a better indicater them vegeta-tation semples.
In addition. me steps grown in the vicinity of LES are irrigated with unter in which liquid plant wastes have been discharged.
SEP14 884.
'M f
.\\.,.
1 19%
seem I\\'
- p. -
(
%e
/3651-12 34
- . 3;... -
M 32 si t., e:.,y.d. 9... :,, ; ' #p 6 *-.-
g$g'y
+
.%,3 t
N
.. -p
. p.-
/
..q SM' g.
~R 3
I M-s p
,.e
_. 2 es i
- . :.;'-;. 751,v
.....s.-
1,.
e
~
.s...
5
.c, s.. - ":,
1 Y
".d..';;.,...,.'..' -.
j
' ' 2 d,5 3 * <
v.
t-s
.\\
i,
- pos3, 1'
~,
g:
ea55.
e
,. r.iisi -
a-
- ,..., t...., ~ :
t c.
s..
. P.
e as st..,-
/ tish s'*.'3 ' 4. ;v.eQ.t.
x.
. \\e
- e
?:e_.._.e. e..w
\\ ;.-
- w.,.
..,.3..:..
.. i. e.,
y...-
w5i n.,-
.- i..
{
q;'. -,s'.
.:.u
,q.c......
t.
s LIMERICK GENERATING TTATION UNITS 1 AND 2 o.1 -tle s '
ENVIRONMENTAL SAMPLING STATIONS SITE BOUNDARY SEP 141984
-si-FIGURE VI.A.]
O 1
WD8tTM
$Y N
/< s; o
o e
'9/' 35 :
,s r
/
s v/
,e -
3y, 2rl ygwg N
4E "g
g 29El e7EI
5
,', {Ci m
I 3
g i2 -
l 80 6l a
e tc e tEl i
(
- =' i o r,igf l
sast conum
'a 3,
...,2 If' yh, \\
k 8
/
u,,
i f
2403
[
's ITDl q
19D1
$671 l d
l
\\
i f
Y l
Lie 4ERICK SENERATING STATMIN I
UMTS 1 AND 2
' 1,-i l v.s
, ENVIRONMENTAL SAMPLING STATIONS INTERMEDIATE DISTANCE SEP 141984 FICURE VI.A.2 l
l
up4Tk eng
,, g t
we T'
- a- { as-aNC g
4 4
ow, 1
.1
,4
%w
/
=.
/W Q$'
N x
- , s.
,i
.,a y -._
l l
p, >.$.
q?
\\
~ ~ ~
e sw e l3 M4 Y
rst
/
4 i
l t
2 I
f apr i
l i
se f
l 1
f I
i SO A
{
M 1
I LN8ERSE SENERATwo FTATION 45N751 Afe 3 ENVIRONMENTAL SAMPLING STATIONS DISTANT LOCATIONS SEP 141984
)
<o,.,%
{
resume v2.4.3
~83-t
- II, Effluent a-dimi ten nantier natmaint cateulallann d.
Llquid Effluents 1.
Redweste Discharge Line Radiation Monit or Monitor alarm setpoints will be determined in order to assure compliance wit h 10CFR20.
The setpoints will Indicate if the concentration of radienuclides in the liquid ef fluent at the site boundary is opproaching t he concentrations specified in 10CFR20, Appendlw B,
Table II, Column 2 for redienuelldes other t hen dissolved or entrained noble gases.
The setpoints will else assure t hat a concentrations listed on Technical
-Specification Table 3.11.1.1-1 for dissolved or entrained noble gases is not exceeded.
The fellowing method applies to liquid releases f rom t he plant via t he cooling tower blowdown line when determining t he high-high alarm setpoint for the Liquid Redweste Effluent Monitor during all operational conditlens. When t he high-high alarm setpoint is reac hed or exceeded, t he releases will be automatically terminated.
a.
The setpoint for t he Liquid Redweste Effluent monitor will be calculated as follows:
l)
Determine C t
j[C a O C s t
I xF C
i 8
MPC I
where:
C s sencontration at the liquid redweste discharge line t
mentter (prior to dilution to assure 10CFR20.106 limits are not emesededs uCl/se 2[C
- total sencontratten of liquid effluent diseberge I
prior to dilutlen with seeling tower blewdowns uCl/ec l
5 a mergin of safety faster including Fg uncertainty, to assure that the high-hleh alarm will terminate the diseherse before 10CFR20 limits are enceeded.
l [
SEP14 M4
- { 11'.. O sua cf the rctlO Cf the is;ltplo c : entrctl:7s MfC divided by t heir rcepect ivo MFC.
I D
a dilution f actor due to blowdown f rom the cooling towers calculated by dividing the total flew (cooling tower blowdown plus redweste discharge flow) by t he redweste discharge flow.
F s Ratio of MPC-welghted releases in the liquid I
redweste effluent monitor flow path divided by the total MPC-weighted liquid releasess
)[
release of flow path of interest MPC I_
Cl
}{ }{MPC all release flew paths I.
2)
Determine C.R.
C.R. s C t
E where C.R.
a t he calculated monitor count rate above background attributable to the radienuclides: CPS E
a t he detectlen efficiency of t he monitors uCl/cc/ cps.
3)
T he monitor high-hlgh alarm setpoint ebeve background should be set at the C.R. value.
b.
The mentter high-hlgh alarm setpoint will be calculated monthly.
The calculat ten will be based on Isotopes detected in the liquid redweste semple tanks during t he previous month.
If there were ne teetepes detected during the prevleus month t hen t he annual everage concentrations (ERCL Table 3.5-3) of those lestepes listed in Table !!.A.1 will be used to determine the setpoint. SEP 141984
If. the eciculcted c:tpoint is loss than tha cxisting acnitor cotpoint, the sotpsint will ba rcduced to ths n:w volus.
If ths calculated setpoint is. greater 'han the existing monitor setpoint, the setpoint may remain at t he lower value or increased to t he new value.
Monitor alarm i
2.
-Plant Service Water Monitor' setpoint will be determined in order to be able to identify and rectify any potential problem due to excessive leakage of heat exc hanger s.
This setpoint results in concentrat ions at the site boundary far below 10CFR20, Appendix B. Table II limits.
The service water side of the fuel pool heat exchangers is kept at higher pressure t han t he ' s hel l side to prevent potential radioactive contaminat ion of t he service water.
a.
The setpoint for t he Plant Service Water monitor will be calculated as follows:
II Determine C.R.
s C.R.
= Z x C.R.
s B
where:
the calculated monitor setp31nt count rate C.R.
s attributable to system leakage plus backgrounds CPM multiplier to establish monitor setpoint Z
=
count rate above background count rate monitor count rate attributable to background C.R.
B radiation; CPM b.
T he monitor high alarm setpoint will be calculated monthly. The calculat ion will be based aan t he background count rate during l
t he previous month.
If t he calculated h
setpoint is less t hen t he exist ing monitor setpoint, the setpoint will be reduced to l-t he new value. - If the calculated setpoint is~ ~g'reat er t han t he exist ing setpoint, the l
satpoint may' remain at the lower value or
~
increased at t he new valu'e'.
" Monitor alarm 3.
RHR Service Water Monitor '-
setpoints will be determined in order to be able to identify and~ rectify any potential problem due to excesstie leakage of he'a't exchsngers.
This
~
-t_ 3; i
SEP 141984 M
sh e
'L e
-e
- 1
-e
--ur--
.+.,%,,,_,c_,-o-w,,,-g.
..y...
g.g g
y.-,-.
cctpsint roculto in c:nc ntrct ions et the sito b;und:ry fcr balew 10CFR20, App:ndix B, Tcblo II limits.
T he follawing cathsd cpplics to liquid releases f rom the plant to the spray pond when determining the high-high alarm setpoint f or the RHR Service Water Monitor during all operational conditions. When the high-high alarm setpoint is reached or exceeded, the releases will be automatically terminated.
s.
The setpoint for the RHR Service Water monlior will be calculated as follows:
1)
Determine C.R.
C.R. : Z x C.R.
S B
wh3re:
C.R.
= the calculated monitor count rate above background S
attributable to system leakage plus background; CPM Z
= multiplier te establish monitor setpoint count rate above background count rate.
C.R.
- monitor count rate attributeble to background B
radiation; CPM E
- the detection ufficiency of the monitor; uCi/cc/ CPM.
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 t he background count rate during the previous month.
If the calculated setpoint is less then the existing monitor setpoint, the setpoint will be reduced to t he new value.
If the calculated setpoint is greater t han 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 Vent Radiation Monitors -
Monitor alarm setpoints will be determined in order to assure compliance with 10CFR20.
The setpoints will indicate if the dose rate at or beyond the site boundary due to radionuclides in the gaseous ef fluent released from the site is SEP 141984
appracching 500 crem/yr to t he wholo bsdy and i
3000 crcm/yr to the skin frca nsblo gasos, or l
1500 crem/yr to the thyroid f rcm I-131 cnd I-133 (inhalat ion pat hway only).
The alarm setpoint for t he gaseous ef fluent radiat ion monitors will be calculated as follows:
a.
North and South Stack Vent Noble Gas Channel 1)
Determine C t
C = 2.12E-3 0 t
t F
where C
the concentrat ion,at the vent noble gas radiat ion t
monitor which indicates that the 10CFR20 dose rate limit at the site boundary has boere reached; uCi/cc 2.12E-3 : unit conversion factor to convert uCi/sec/CFM to uCi/cc.
9
- the total re'. ease rate of all noble gas radio-t nuclides in the gaseous ef fluent (uci/sec) based on the lower 9f either the whole body exposure limit (500mres./yr) or the skin exposure (3000mrom/yr) Q will be calculated as shown t
-in Attachment 1.
F
= anticipated maximum vent flow rate; CFM 2)
Determine the noble gas channel alarm setpoint (S )
N S : VF C i
N i t where:
t l
= fraction of total gaseous releases on an MPC-I-
I weighted basis for the previous month that are i
f rom the release point of interest;
(
e.g. nort h went releases l
releases from all plant release points I
l l
l-
, SEP 141984
- p.
b.
M2rth cnd $suth Stcck Vcnt Icdins Channal
.p-1)
Dstcraino C t
C = 2.12E-3 e t
t F
wh re:
C
= t he concentrat ion at the vent fodine radiation
+
t
- monitor which -indicates that the IOCFR20 dose rate limit at the site boundary has been reached; uCi/cc.
4 2.12E-3 = unit converstion factor to convert uCi/sec/CFM to uCl/cc.
9
- the total release rate of radiolodines in t he t
gaseous effluents (uci/sec) Q will be t
calculated as shown in Attachment 1.
F-
- maximum antcipated vent flow; CFM.
2)-
Determine the lodine channel alarm setpoint (S )
I l
5 : VF C I
i t
where:
'VF
- fraction of lodine releases on an MPC-I weighted basis for the previous month that are f rom the release point of interest;
- e.g. nort h vent releases releases from all plant j
release points 2.
The monitor alarm setpoints will be calculated
. mont hly.
These calculat ions will be based on isotopic analysis of releases made during t he previous-' month.
If t here were no isotopes detected during the previous month then isotopic concentrations calculated from t he expected annual average noble gas and lodine-131 and 133 l
. isotopic release rates (ER0L Table 3.5-6) will be used to determine t he setpoint.
If any l
calculated setroint is less t hen t he existing l
monitor setpoint, the setpoint will be reduced to t he new value.
If t he calculated setpoint is greater than t he exist ing value, the setpoint may i
i l
l l SEP 141984
remain ct the lew:r volus or inccces:d to th) nsw voluo.
Due to the fact t hat 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 f ract ior of the total
- dose, a particulate channel setpoint will not be calculated for purposes of the ODCM.
3.
-Containment Purge Isolation a.
Monitor alarm setpoints will be-determined f or the North Stack Vent Wide Range Gas Monitor to initiate closure of the containment purge supply and ex haust lines in the event t hat high radioactivity releases are detected. The setpoint will be determined to alarm and isolate containment in the event that 10CFR20 dose rates at the site boundary are approached or. exceeded.
The setpoint for the Wide Range Gas Monitor will be calculated as follows:
1)
Determine C t
1 C
= 2.12E-3 Q t
t F
where :
C-
= t he concentrat ion at the Wide Range Gas Radiat ion i
Monitor which indicates that the 10CFR20 dose I
rate limit at the site boundary has been reached; uCl/cc 2.12E-3
= unit conversion factor to convert uCi/cc/CFM to uCi/sec.
L 9
the total release rate of all noble gas. radionuclides I
in the gaseous ef fluent (uCl/sec) based on the lower p
of either the whole body exposure limit (500 mrem /yr) or the skin exposure limit (3000 mrem /yr).
F
= maximum anticipated vent flow rate; CFM.
l l-2)
Determine the Wide Range Gas Monitor trip setpoint (S )
S
I t l
l-i SHEP 141984
whero:
IP -
+e
- frcction of totcl g:accus relcases an en MPC-VF; I
weighted basis previous month t hat are f rom the release point of interest; e.g. nort h vent releases releases from all plant release points b.
Prior to containment purge and venting, the
. monitor setpoint will be recalculated.
The calculations will be based on the noble gases detected by isotopic analysis of the containment atmosphere.
If the calculated setpoint is less than the existing monitor
- setpoint, the setpoint will be reduced to the new value.
I f t he celculated setpoint is greater t han the existing value, the setpoint may remain at the lower value or increased to the new value.
I l
I l
i:
i l SEP 141984 i
l
?
ATTACHMENT 1 Q Celculations t
Q
=
500
-t(whole body)
(X/Q)
KS v
i i whore:
0
- the total release rate of all noble gas t
radionuclides in the gaseous ef fluent; uCi/sec.
(X/Q)
= 1.1x10-5sec/m3; the highest calculated v
annual average relative concentration for an area at or beyond the site boundary f or all vent releases (NE boundary).
K
= whole body gamma dose factors due to noble i
gases listed on Table III.A.1 (from Reg.
Guide 1.109, Table B-1).
t S
- .the f ract ion of the total radioactivity in the i
gaseous effluent comprised by noble gas radionuclide "i".
4 3000 t(skin)
(X/Q)
][(L + 1.1M )S v
i i
i i
(X/Q)
- 1.tx10-5sec/m ; the highest calculated 3
v annual average relative concentration for an area at or beyond the site boundary for all
~
vent releases (NE boundary).
L
- beta skin dose factor due to noble gases, i
listed on Table III.A.1 (from Reg. Guide 1.109, Table B-1).
l M
= air dose factor due to noble gases, i
listed on Table III.A.1 (from Reg.
Guide 1.109, Table B-1).
- S
- the f raction of the total radioactivity in the i
gaseous effluent comprised by noble gas radionuclide "i".
Q
=
1500 f ( t hyro i d) -
(X/Q) j[P A d
i i f SEP 14 1984 l
l
[
~. - -
wherof
.4
- the totcl rolcsso rato of radioicdinas t'
in the gaseous ef fluent; uCi/sec.
(X/Q)
': 1.0x10-5sec/m3; the highest calculated i
I d.
annual average depleted concentration for an area at or beyond the site boundary f or all vent releases (HE boundary).
P
= inhalat ion dose f actor for child thyroid f or i
radiolodines mrem m /uCl yr; 1.62xt0x107 3
for I-131 and 3.85x106 for I-133 A
- the f raction of the total radioactivity in the i
gaseous ef fluent (iodine channel) comprised by radionuclide "i".
l f
i l
r I SEP 141984
i l
I II.
- 11111, 4
i Site Soocific Data f
sto la Liquid dose factors, A, for section III.A were 1.
developed using.the f ollowing site specific data.
The liquid pathways involved are drinking water and fish. The maximum exposed individual is an adult.
. U /D + U x BF ) K x DF
(
A
=
IT w w F
i 0
1-730 liters per year; maximum adult usage of U~
=
w drinking water-(Reg. Guide 1.109, Table 3-5).
85; average annual dilution at Phoenixville Water D.
=
.w Authority intake.
21 kg per years maximum adult usage of fish (Reg.
.U
=
F
' Guide 1.109, Table E-5).
bloaccumulation factor for nuclide, 1,
in fresh-BF :-
1
-water fish.
Reg. Guide 1.109. Table A-1, except P-32 which uses a value of 3.0E03 pCl/kg per pCi/ liter.
1.14x105(10' pCl/uci x 103ml/kg x 8760 hr/yr)
K
=
0.
units conversion factor.
dose conversion factor for nuclide,
- l. for adults DF =
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-s prem/pcl ingested.
The. data for D was taken f rom data published in Limerick
.G:nerating Station Units I and 2 Environmental Rooort
[-
Doeratina License Staae, Volume 3.
All ot her. data except
(
P-32 BF and DFi were used as given in ' Reg.
Guide 1.109, l
Ravision 1, October 1977. A P-32 BFI value was taken f rom
-Kthn, B. and K..S. Turgeon, "The Bloaccumulat ion Factor f or Phosphorus-32 in Edible Fish Tissue", HUREG-CR-1336, March, 1980. A P-32 DF value was taken from Limits for Intakes of
.Radionuelldes hv' Workers, International Commission on
[
R diological Protection ICRP Publication 30, Supplement to l
Pcrt 1,
1979.
l
!!sto 2:-
To develop constant.P f or Sect ion III. A, t he I-131
}.
following data were used:
=
K' (BR) (DFA)
l
.106'pCl/ucis unit canvorsion fceter K',
=
g.
3
- 3700 m / yrs child's inhalat ion rato.
BR =
4.39x10-3 mrem /pcis the thyroid inhalat ion DFA =
I-131 dose fa. tor for I-131 in t he child.
The pat hway i s ' t he Inhalat ion pat hway f or a child. All values are taken from Regulatory Guide 1.109, Revision 1, October 1977.
Note 3:
To develop constant R f or sect ion III.C. the f ollowing site specific data were used:
0' R
(D/0) : K't (U ) F x r x (DFL )
f (1-f ) Ett i
F ap m
i a o
se f
K +A Y
I w p
K'
=
10'pCl/uCl unit conversion factor G
=
6Kg/ days goat's consumption rate F
U.
=
330 1/ yrs yearly milk consumption by an infant op 7J.
=
9.97 x 10-7 sec-' decay constant for I-131; i
9.48x10-6 for I-133.
pL
=
5.73 x 10 7 sec-8 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.
c.
1.0 fraction of deposited radiolodine retained in goat's feed grass.
DFL =
1.39x10-2mree/pCi - t he t hyroid ingest ion dose i
factor for I-131 in t he inf ant s 3.31x10-3 mrem /
pCl for I-133.
f 0.75 t he f ract ion of t he year t he goat is on p
-pasture (average of all farms).
f'
=
0.03 t he f ract ion of goat f eed t hat is stored s
f eed while t he goat is on pasture (average of all farms).
0.7 Kg/m2 - t he ogricultural productivity of Y
p pasture feed grass.
- t 2 days - t he t ran spo r t t ime f rom pas t ure t o goat,
f to milk, to receptor. SEP 141984
._.-,.-,-..,.,..-...__-,_.,,.,_,.m--.-_,
.,.-.,,.-.,_,...,.m.
,---.m,--m.
_c..-..,----.
- T he p t hw y is the gress gzct milk ingsst ien pat hway.
Thase d2tc wuro d2rivsd f rem dato publishsd in Limerick
' Generating Station Units 1 and 2 Environmental Reoort Doeratina Staae, Volume 3.
All other data were used as given in Reg.
Guide 1.109.
Revision 1.
October 1977.
Similar data were used to develop the constant R f or 1-133.
Nate 4:
The methodology described herein will be implemented via computer codes. These codes have been verified as documented in:
1.
G.A.
Tec hno lo gi e s, RM-2tA Comoutational Models, Document No. E-115-1241, June 1984.
2.
G.
A.
Tec hnolog ies, Meteoroloalcal Monitorina.
Disclav and Renort ina Svst em/RM-214. Document No.
0375-9032, January, 1984.
Surveillance Reauirement 4.11.1.2 Llauld Pathwav Dose Calculations The equat ions f or calculat ing the doses due to the actual release rates of radioactive materials in liquid effluents were developed from the met hodo l o gy provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Men from Routine Releases of Reactor Effluents f or the Purpose of Evaluating Compliance with 10CFRPart 50, Appendix I",
Revision 1, October 1977 and HUREG-0133
" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants". October 1978.
Surveillance Reautrement 4.11. 2.1.' t and 4.11.2.1.2 - Done Noble Gases The equations for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents were developed from t he met hodo lo gy provided in Regulatory Guide l.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I",
Revision 1,
October 1977, I
NUREG-Ol33
" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants",
October 1978, and Regulatory Guide 1.111.
" Methods for Estimating A t mo sp her i c Trarsport and Dispersion of Gaseous Effluents in Routine Releases from L i ght -Wat er-Cool ed 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 t he historical cverage atmospheric condit ions.
T he dose due to noble gas release as calculated by the Gross
^ Release Method is much more conservative than the dose calculated by t he Isotopic Analysis Met hod.
Assuming the release rates given in Limerick Generating Station Units I and 2 Environmental
'Renort omeratina tiennse Simes, Volume 3, t he values calculat ed
, SEP 141934
.-,-,-w-
--.w..c-r-.,,----,-+,--,-c.,~...m, v--.-----w
--.www---p-,.,--w
- ,--,-e.-,ee.,--ee,-.,-v-... -+ww
- by the Grecs Rolocsa M2thod f ar totcl brey diso reto end skin
+
,, dbss= rcto cro 4.8 t imss cnd 3.25 t imes, respsct ivoly, t he vcluss
- ,-, calculated by the Isotepic Analysis M2th3d.
+
Far ' t he Gross Release Met hod, Kr-87 and Kr-88 are used f or t he -
limiting skin and total body dose factors respectively, due to helf life consideratiors.
Kr-89, t he nuclide wit h t he highest dise: factors per Regulatory Guide 1.109 Table B-1 has a half-life
.of '3.2 minutes while.tte half-Ilves of Kr-87 and Kr-88 are 76 l
- oinutes and 2.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> respect ively. T heref ore, by the t ime t hat
~
gaseous effluents have been transported offsite, Kr-89 will have
-.d:cayed enough so t hat Kr-87 'and Kr-88 are ef f ect ively the most limiting nuclides.
T he model Technical '5pecificat ion LCD f or all radienuclides and rcdloactive materials in particulate form and radionuclides other t hari noble gases requires t hat the instantaneous dose rate be 1:ss than the equivalent of 1500 mrom per year.
For t he purpose of-calculating. this instantaneous dose rate, t hyroid dose f rom isdine-131 and iodine-133 through the inhalation pathway will be used.
Since the expected annual releases presented in LG5 FSAR
'Tchte 11.3-1 Indicate t hat lodine-131 and lodine-133 releases have t he major. dose impact this approach is appropriate. The v=lue calculated is multiplied by 1.02 to account for the thyroid dese' f rom all ot her nuclides. This allows for expedited analysis end. calculation of compliance with the LCO.
l Surveillanes Reapirement 4.11.2.2 and 4.11.2.3 - Done Noble Gases i
l The equations for calculating the doses due to the actual release rctos of radioactive noble gases in gaseous effluents were
- daveloped.from' t he 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 CFR Part 50, Appendix I",
Revision I,
October 1977, NUREG-0133
" Preparation of Radiological Effluent Techn ical Specifications for Nuclear Power Plants",
October 1978, and R5gulatory Guide 1.111, 9 Met hods for Estimat ing Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases
'from L i ght -Wat er-Coo led Reactors". Revision 1.
July 1977 with site. specific dispersion curves and dispersion methodology.
The specified equations provide--for determining the air doses in creas at and beyond t he SITE BOUNDARY based upon ' t he historical cverage atmospheric conditions.
'The dose due to - noble gas releases as calculated by the Gross R0 lease Met hod is much more conservat ive t hen t he dose calculat ed by t he Isotopic Analysis Met ho d.
Assuming the release rates given in-Limerick Generating Station Units 2 and 3 Environmental i
Resort eneratine - ticense Staae, Volume 3, the values calculated t.
. by t he Gross Release Met hod _ f or total body done rate and skin dase rate are 4.8 times and 3.7 times, respectively, the values calculated by the Isotopic Analysis Method.
-3'-
SEP 141954
- Done, Indine-131.
- Tritium, and Radioactive Material in
,farticulate Form a
The equat ions f or calculat ing t he doses due to t he actual releans rates of1radiolodines, radioactive material in partleulate form,
-cnd radionuclides other than noble gases with half-Ilves greater than 8 days were developed using the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from j
Routine-Releases of Reactor Effluents for the. Purpose of 1
Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision I,
October 1977, HUREG-0133, " Preparation of Radiological
. Effluent Tec hnical Specifications for Nuclear Power Plants",
October 1978, and Regulatory Guide 1.111. " Methods for Est imat ing At mo sp her i c 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 met hodol ogy.
These equations provide for determining the actual doses based upon the historical average atmospheric condit ions.
Compliance with t he
'It CFR 50 Ilmits for radiolodines, radioactive materials in particulate form and radionuclides other than noble gases with half Ilves greater than eight days is to be determined by calculat ing t he t hyroid dose from iodine-131 and lodine-133 -releases.
Since the lodine-131 and lodine-133 dose cccount s f or 99.97 percent of t he total dose to t he t hyroid, the value calculated is not increased.
l SEP 141984 i
. _ _ _ _ _ _. _ _ ~.,. -. _.
q l
s i : g:i n;. :m
- i gr.
I IT i
M Q.
td CD l
iI I!ll~lj'i i
i I
I'I.g 11 lI,i l
i ii i
I III i Il li i i
~~~
e
'I n,,i
!i R
'I: ii:
g,g,;;
==
m ai I
7 '7~ L ' g7:
-@-1 H
VC)C),C).C). (20
(
i!!,
3,,
c J
o,,
ti;ir c
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ I :_ ',. i 5E
__i_
I n g,g_ _ _ - a g;_ - _ - - _
ig c
ira,)iI!',
j,g l
g o
o o
o o o
o o
g 8
8 ggg,jg e
e W
W W
L
-M-}--
E i
g
_ k(
k j
l
-4M s
g gh gg gbgg tb
.b i.Igli i
1 i
11 'il-
.t l i i
1 I
i i
i li i
l
o-yi I i n.i EE n
i ur s-g
58 U
=
El9
=E mE E-
.,*. u a
En v
=
es m
EE ~.
32~
- e a:-
t =
ee=
5 e-t E-2 E
a EE W
w o
55 1..
~E E
((n I
l33 gg3
~
I E E8g gag gm I-i ag_
9 9
E!
I
(
(-
o o
o E
l*a
~
5-I
=E I
o e
m.I I " "e o
m I:g s--
a db t
k g"I
=
.=-
E
-i l
E.
Sh
~
,,zu 3
I 3
3I a-g.g o
5
_E=
=
s
=
le E
.=
==
x, l5 n
o o
e s
as s
l i
i i
\\
b
(
(
o o
o a
o o
e s
=
s z
i
=e l
Il l
E II i
l I
I Il
[s II s
y uI ff a
~
~
1 I
E c
we E=.
[I e
5:
a l
-I as 3
.a
.g ::
En I.,
a E-t t
t t
t t
Q l
I i
!=
-8 m
5e
=
=
==
1.g
~g g,
5 ;=
ia-55 e,
==
gs e=
=
E 5R l
l l
l l
y$'&*"%*"'gld-jjp556 5
1
,G f} @ f f a
~
l
- .., j Nag
. \\, '
h," '
y i$
a[
~
~
'\\
s, b2 ?
.M 0$[ESN "=';;;,ay='tw(,7 *I
.g. %y; g=
a 5.
',8
$265 Vi-
- g g g% n
.s m::.
g,..
s-w w
e.
]) % '.
wE A'eIs'ASe I;%
h.c,&'
3 7, 'l~ %' y
\\f :gl)[y N
h lf
-m.
..p- %
} }
t-l,
.m f.~
,'D
~9s s
-71 \\
"\\:
,1 f
.c
_l
\\o
'\\
re
,ylr.' :),
,\\
Nhb 3g
+
1 MAP DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND l
LIQUID EFFLUENTS FIGURE IX.A3
~4 8-SFP 1 A 1994 I
r v.
y PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET
' P.O. BOX 8699 PHILADELPHIA PA.19101 SEP 141984 (215)841-4502 WIC E-PR ESID E NT Enosmaansne ano nessancn,
Mr. A. Schwencer, Chief Docket Nos.: 50-352 Licensing Branch No. 2 50-353 Division of Licensing U. S. Nuclear Regulatory Ccmission Washington, D.C.
_20555 9
Subject:
Limerick Generating Station, Unit 1 and 2 Revision of Offsite Dose Calculation Manual (ODCM)
Reference:
1)
Telecopy, R. E. Martin to T. Robb, dated 9/6/84 2)
PECo and NRC Telecon dated 9/10/84 File:
00VT 1-1 (NBC)
Dear Mr. Schwencer:
In accordance with discussions in the reference conference call, the Limerick ODCM has been revised and is included as Attachment 1.
During the conference call, Philadelphia Electric Canpany cmmitted to supply as an Appendix to the ODCM, the cmputer model dose parameters for the various age groups and organs for sections II.B, III.A.2, and II.C of the' ODCM.
'Ihis Appendix will be supplied by October 22, 1984.
Sincerely,
.:2 N.
I
~JWB/dg/09068403 Attachment Copy to: See Attached Service List 1
J
E:
Q.& <-
- f#
cc: Judge Lawrence Brenner (w/ enclosure)
Judge Peter A. Morris
.(w/ enclosure)
Judge Richard F. Cole (w/ enclosure)
' Judge Christine N. Kohl.
(w/ enclosure)~
dudge Gary J. Edles (w/ enclosure)
Judge Reginald L. Gotchy (w/enclosu e)
Troy B. Conner, Jr., Esq.
(w/ enclosure)
Ann P. Hodgdon, Esq.
(w/ enclosure)
Mr. Frank R. Romano (w/ enclosure)
Mr. Robert L.' Anthony (w/ enclosure)
(w/ enclosure)
Ms. Maureen Mulligan -.
(w/ enclosure)
Charles W. E11Iot, Esq.
Zori G. Ferkin,' Esq.
(w/ enclosure)
.Mr.' Thomas Gerusky (w/ enclosure)
Director, Penna. Emergency (w/ enclosure)
Management Agency.
Angus R. Love, Esq.
(w/ enclosure)
David Wersan, Esq.
(w/ enclosure)
Robert J. Sugarman, Esq.
(w/ enclosure)
Martha W. Bush, Esq.
(w/ enclosure) c Spence W. Perry, Esq.
(w/ enclosure)
Jay M. GutIerrez, Esq.
(w/ enclosure)
Atomic Safety & Licensing' (w/ enclosure)
Appeal Board Atomic Safety & Licensing (w/ enclosure).
Board Panel Docket & Service Section (w/ enclosure)
Mr. James Wiggins
.(w/ enclosure)
Mr. Timothy R. S. Campbell (w/ enclosure)
-