ML20198M024
| ML20198M024 | |
| Person / Time | |
|---|---|
| Issue date: | 08/09/1982 |
| From: | Congel F Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20198L994 | List: |
| References | |
| FOIA-97-455, RTR-NUREG-0472, RTR-NUREG-0473, RTR-NUREG-472, RTR-NUREG-473 NUDOCS 9801160172 | |
| Download: ML20198M024 (21) | |
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DISTRICUTlHN:
ClealIAl O AUG 3 1982 RAB R/T FJCongel tilluRANDUH TUR RA8 Staff TR0H Frank J. Congel, Chief Radiological Assessment Branch, OS!
SUBJECT:
INTER!H Ct%NGES IN THE IODEL rad!0 LOGICAL EFFLUENT TECHMCAL SPEClf! CATIONS (RETS)
It has been found appropriate to diange the Radiological Environnental Honitoring Section of the im', Al RETS by the incorporation of a number of sections of the Radiological Assessment Branch Technical Position, Revision 1, Novo-ber 1979.
These interim changes will be included in the next revision of NUREG-0472 and flVREG-0473.
The changes, as recorded on the enclosed sheets, should be used as guidance for the present and future RETs reviews for both ors and OLs.
Orideal den.d by r.J.c....
Frank J. Conpel, Chief Radiological Assesstaent Dranch Olvision of Systems Integration f
Enclosure:
As stated f
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R. stattson R. W. Inouston li. Gara111 D. Willis W. lleinko W. Pasciak l
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l7 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.) The radiologicti envirormental monitoring program th411 be conducted as specified in Table 3.121.
@PLICABillTY: At all times.
AC110N:
With the radiological ervironmental monitoring program not being a.
conducteo as specified in Table 3.lbl, in lieu of a Licensee Event Report, prepare and submit to the Commission, in the Annual Radio-logica*. Environmental Operating Report required by Specification 6.9.1.11, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence, Wlth the level of radioactivity as the result of plant effluents in b.
an erstronmental sampling medium at a specified location exceeding the reporting levels of Table 3.12 2 when averaged over any calendar quarter, in lieu of a Licensee Event Riport, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to A MEMBER Of THE PUBLIC is less than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2, and 3.11.2.3.
When more than one of the radionuclides in Table 3.12 2 are detected in the sampling medium, this report shall be submitted if:
concentration (1) concentration (2)
- > 1.0
+
reporting level (1) reporting level (2)
When radionuclides other than thoFe in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to A MEMBER Or THE PUBLIC is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.
This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report With milk or fresh leafy vegetab',e samples unavailable from one or I
c.
more of the sample locations required by Table 3.12-1, identify l
locations for obtaining replacement samples and add them to the radio-logical environmental monitoring program within 30 days.
The specific 4
PWR-STS-1 3/4 12-1 6/4/82
o RADIOLOGICAL ENVIRONMENTAL MONITORING locations from which samples were unavc11able may then be deleted In 11eu of a Licensee Event Report and from the monitoring program.6.9.3.12, identify the cause of the unavail-pursuant to Specificatiot ability of samples and identify the new location (s) for obtaining repit:.ement samples in the next Seetannual Radfonctive Effluent Releese Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
d.
SURVEILLANCE REQUIREMENTS The radiological environmental monitoring samples shall be collected l
4.12.1.1 pursuant to Table 3.12-1 from the specific locations given in the table and l
figure (s) in the ODCM and shall be analyzed pursuant to the requirements of i
Table 3.12-1, the detection capabilities required by Table 4.12-1, and the i
guidance of the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979.
Cumulative potential dose contributions for the current calendar 4.12,1.2 year from radionuclides detected in environmental samples shall be determined in accordance with the methodology and parameters in the 00CM.
1 I
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TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- Number of Representative Exposure Pathway Samples and Sampling and Type and Frequency and/or Sample Sample locations
- Collection Frequency
__o. Analysis 1.
DIRECT RASIATION 40 routine monitoring stations Quarterly Gamma o.se quarterly.
b (DRI-DR40) either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:
an inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY a;
(DRI-DR16);
Tu b
an outer ring of stations, one in each meteorological sector in the 6-to 8-km range from the site (OR17-0R32);
the balance of the stations (DR33-DR40) to be placed in special interest areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations.
This table presents an E
- The number, media,-frequency, and location of samples may vary from site to site. Local site characteristics R
acceptable minimum program for a site at which each entry is applicable.
must be examined to determine if pathways not covered by this table may significantly contribute to an 4 M M%
A%,,, y, o g i, individual's dose and should be included in the sampling program.
j U w h==e4 4,
a nt, M W q *( h g & Q A b d* *@ - h A tt, p p L. t -
it-Mf,1 v +4 te.otws.
s
d' T ABLE 3.12-1 (Continued)
RAC'211GICAt ENVIRONMENTAL MOM!10 RING PROGRAM
' 2, Number of J.
Representative Sampling and Type and Frequency CT Samples and Collection Frequency of Analysis Exposure Pathway Sample locations,,,
and/or Sample Radiotodine Cannister:
2.
AIRBORNE Continuous sampler 1-131 analysis weekly.
Samples f rom 5 locations ( Al-AS):
operation with sample Radiciodine and collection weekly, or Particulates 3 samples ( Al-A3) f rom close more frequently if to the 3 Slif BOUNDARY locations, required by' dust Particulate Sampler:
in different sectors, of the Gross beta radioactivity loading.
highest calculated 'nnual average analysis folloging groundlevel D/Q.
Gamma isotopic analysis, filter cnange; I sample (A4) from the vicinity of composite (by of a community having the highest location) quarterly.
calculated annual average ground-level D/Q.
t w
j 3:
1 sample A5 from a control
- j location, as for example 15-30 km 4
distant and in the least preva-1ert wind direction.
3.
WATER 80RME c==== isotopic analysis' Surface #
1 sample upstream (Wal)
Compositesampfeover 1-month period monthly. Composite for I sample downstream (Wa2) tritium analysis qu3rterly.
a.
Gamma isotopic' and tritium Quarterly Samples from 1 or ? sources analysis quarterly, b.
Groisnd (Wbl. Wbg), only if likely to be affected.
1-131 analysis on each Composite sampie 1 sample of each of 1 to 3 (Wcl -
over 7-week period composite when the dose 9
c.
Drinking when -131 analysis calculated for the consump-Wc3) of the nearest water o,
3:
supplies that could be is performed, monthly tion of the water is greater Com-affected by its distnarge.
composite ctherwise than 1 mrem per year.
posite for gross beta and N
1 sample from a control gamma isotopic analyses' location (Wc4).
monthly.
Composite for tritium analysis quarterly.
__~-a..
TABLE 3.12-1 (Continued)
RADIOLOGICAL ENY!RONMfMTAL MONITORING PROGRAM Number of Representative Exposure Pathway Samples and Sampling and Type and Frequency and/or Sample Sample Locations
- Collection Frequency of Analysis d.
Sediment I sample from downstream area Semiannually Gamma isotopic analysis' from.
with existing or potential semiannually.
shoreline recreational value (Wdi).
4.
INGESTION a.
Milk Samples from milking animals
'emimonthly when Gamma isotopic ^'and I-131 in 3 locations (Ia1 - Ia3) within onimals are on analysis semimonthly when 5 km distance having the highest pastere, monthly at animais are on pasture; dose potential.
If there are other times monthly at other times.
none, then, I sample from milking animals in each of 3 areas (Ia1 -
Ia3) between 5 to 8 km distant where doses are calculated to be g
greater than 1 arem per yr.
I sample from allking animals at a control location (la4)
(15-30 km distant and in the least prevalent wind direction).
b.
Fish and 1 sample of each commercially Sample in season, or Gamma isotopic analysis' Inverte-and recreationally important semiannually if they on edible portions.
brates species to vicinity of plant are not seasonal discharge area.
(Ib1 - Ib__).
I sample of same species in areas not (nfluenced by plant dis-charge (Ib10 - Ib__).
I Gamma isotopic analyses' c.
Food 1 sample of each principal class At time of harvest Products of food products from any area on edible portion.
that is irrigated by water in which liquid plant wastes have been discharged (Ici - Ic,_).
c 2
TABLE 3.12-1 (Continued)
?
. G RADIOLOGICAL ENVIRONMENTAL M0h1TORING PROGRAM Nurber of Representative Exposure Pathway Samples and Sampling and Type and Frequency and/or Sample-Sample Locations" Collection Frequency of Analysis c.
Food Samples of 3 different kinds Monthly when Gamma isotopic' and I-131 Products of broad leaf vegetation grown available analysis.
(cont'd) nearest each of two different offsite locations of highest predicted annual average ground-level D/Q if milk sampling is not performed (Ic10 - Icl3).
1 sample of each of the similar Monthly when Gamma isotopic' and 1-131 o
s br ad leaf vegetation grown available analysis.
15-33 km distant in the least 7
prevalent wind direc*. ion if milk sampling is not performed Ic20 - Ic23) l S
T 5
1
.y
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E 1AHL[ 3.12-1 (Continued) b 1ABLE NOTAll0N
- Specific parameters of distance and direction sector f rom the centerl
{
location in Tabla 3.12-1 in a l
description where peetinent, shall be provided for each and every samp eRefer to NUREG-0133, l'
l i
table and' figure (s) in the 00CM.
Specifications for Nuclear Power Plants." Octoben19J_8. and to Radiolog cait may not be possi Positions Revision 1. November 1979. (It is recognized th t, at times, i
time.
In these instances
, s ) ticabid to obtain samples of the media of choice at the most desired i
l athway in questien and appro-suitable alternative media and locations may be chosen for the part cu ar p In lieu ical environmental monitoring program.
W :.,
1 12, identify the cause of the unavall-il
- priate substitutions made within 30 days in the *ad o og of a Licensee Event Report and pursuant to Specification 6.9.. lacement samples in the next i
ability of samples and identify the new location (s) f or obtain ng repSealan i d figure (s) ar.d 3
na table'for the 00CM reflecting the new location (s).
ding dose rate One or more instruments, such as a pressurized ion chamber, for measuring and recor For the purposes of this dosimeters.
continuously may be used in place of, or in addition to, integratingtable b
h sphor; two or more phosphors in a 2
The number of direct radiation monitoring
~
packet are considered as two or more dosimeters.The 40 stations is not an absolate number.
t an ocean site, some sectors will 7
stations may be reduced according to geographical limitations; e.g., a direct radiation.
The freqency of analysis or
,I i l l
be nver water so that tte number of dosimeters may be reduced accord ng y.f the specific system u i;
readout for TLD systems will depend upon the characteristics oselected l
ll be described in the ODCM.
l Methodology to guarantee complete recovery of radiolodine sha C
i e
Deviations ars permitted from the required sampling schedule if spec mens arl una J
unobtainable due to hazardous conditions, seasona If specimens of automatic sampilng equipment arrJ other legitimatt reasons.are ffort shall be R
R made to complete corrective action prior to the enAl.1 deviations free the s in the
,,g,,,,,,,,,
period.
(2.p3 4.
p 1
C _g,c y
,,,;,p Rnnual itzf f
TABLE 3.17-1 (Continued) i 2
l i
7 TABLE NOTATION t
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. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more af ter If gross beta activity in air particulate samples
~
sampling to allow for redon and thoron daughter decay.is greater than ten times the yearly mean o on the individual samples.
I isotopic analysis means the identificatin and quantification of gamma-eeltting radionuclides
'cm===
that may be attributable to the effluents from the facility.
The The " upstream sample" shall be taken at a distaxe beyond significant influence of the discharge." Upstream" samples in
" downstream" sample shall be taken in an area beyond but near the alming zone.
Salt water shall be an estuery must be taken far enough upstream to he beyond the plant influence.
sampleo Only when the receiving water is utilized for recreational activities.
I l ',
j A composite sample is one in which the quantity (allquet) of Ilquid sampled is proportional to the quantity.
of flowing liquid and in which the method of samp1 tog employed results in a spec I
4 of the llould flow.
ii very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obta n ng.
U a representative sample.
"Grounduater samples, hall be taken when this source is tapped for drinking or irrigation purposes in areas i tion.
where the hydraulic gradient or recharge properties are suitable for contam na The dose shall be calculated for the maximum organ and age group, using the methodology and paramete I
l the 000t.
If if harvest occurs more than one.e a year, sampilng shall be performed during each discrete harvest. Attentio l
harvest occurs continuously, sampling shall be monthly.
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tuborous and root food product
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TABLE 3.12-2 REPORTING LEVELS FOR RADICACTIVITY CONCENTRATIONS IN ENVIR08mCNTAL 5APttES Reporting Levels Water Airborne Particulate Fish Milk Food Products Analysis (pCl/2) or Gases (pci/m')
(pti/kg wet)
(pCl/t)
(pC1/kg. wet)
H-3 20.000*
30.000 Mn-54 1.000 10.000 fe-59 400 30.000 Co-58 1.000 10.000 Co-60 300 20.000 9
Zn-65 300 e
Ir-Mb-95 400 3
100 1-131 2
0.9 Cs-134 30 10 1.000 60 1.000 Cs-137 50 20 2.000 70 2.000 300 Ba-la-140 200 "For dr.~nking water samples. This is 40 U R Part 141 value.
If no drinking water pathway exists, a R
value of 30.000 pC1/2 may be used.
=
g y
f
)y tr n d.
0 0
eeg 5
8 l k 1
1 d/
eI SC P
(
s t)
Ct wdy org 0
0 0
Pk 6
6 8
/
d1 oC op F(
'S I
SY
)
L f
A 1
5 8
5 N
k/
1 1
1 li A
ic E
Mp L
E
(
M C
A
)
m S
D L
)
L L
t A
(
e T
M N
w r
sg 0
0 0
0 0
0
(
O h.
i 3
5 o
3 6
3 6
1 1
I 1
P M
T ik 1
2 1
2 2
O C
F/
V I
1 R
E I
T C
E p
r N
D
(
r f
I b
t F
B e
O A
o T
F T
I e
S M
t E
I a
s.
1 L
l )
u3 v
1 1
R cm i/
a L
E 1
W tl 8
O rC 7
5 6
0 0
0 a
A i
ap 1
P(
0 0
0 0
M es 0
C na N
rG O
e r
I tt o TC
=
lA y-E T
,v
)
d r/
4 0
5 0
5 0
5 I
5 8
5 ef 0
1 3
1 3
1 1
1 1
3 t
tC 0
L ap 2
'k d1(
0
~
a 4
0 t
1 X
s e
i b
5 4
7 y
s 4
9 8
5 b
1 3
3 a
s l
s 5
5 5
6 N
3 1
1 L
a o
3 1
i e
o n
r s
s 4
F C
Z Z
I C
C 8
n r
k A
g M s
[
N.NE
.1
~.0 s
J 4
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ItE 4.12-1 (Continued)
_o_
TABLE M)TATION -
"This list does not mean that only these nuclides are to be considered.
Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Rsdiological Environmental Operating Report pursuant-to Specificatior. 6.9.1.11.
Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.
The LLD is defined, for purposes of these specifications, as the smallest C
concentration of radioactive material in a sample that-will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falscly concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
4.66 sb MD =
exp(-Aat)
Y 2.22 V
E Where:
LLO is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume, is the standard deviation of the background counting rate or of stne counting rate of a blank sample as appropriate, as counts per b
- minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and at for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting Typical values of E. V, Y, and at should be used in the calculation, i
6/4/82 PWR-STS-1 3/4 12-11
l l
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TABLE 4.12-1 (Continued)
)
TABLE HOTAT10N It should be recognized that the LLD is defined as an a priori (before i
the fact) limit representing the capability of a measurement system and not as an a posteriori (6fter the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unschievable.
In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.11.
dLLD for drinking water samples.
3( ~
4 m,
tG Luo 4 y = 4 ~.,.
g, S
e PWR-STS-I 3/4 12-12 6/4/02
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i-I e-TABLE 4.12-1 (Continued)
TABLE NOTATION It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be Occasionally background fluctuations, achieved under routine conditions.
unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.11.
l dLLD for drinking water samples. N ~ C% 4 M,
i tt, LL.D 4 p -
4 eg.
p 6/4/02 3/4 12-12 PWR-STS-I
RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION A land use census shall be conducted and shall identify within a 3.12.2 distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest (F c,r (500 ft ) producing broad leaf vegetation.
2 8
garden" of greater than 50 melevated releases as defined in Regulatory Guide 'i.111, the land use census shall also identify within a distance of 5 km (3 miles) the locations in each of the 16 meteorological sectors of all milk animals and all gardens of greater than 50 m2 producing broad leaf vegetation.
APPLICABILITY:
At all times.
ACTION:
With a land use census identifying a location (s) that yields a calcu-lated dose or dose commitment greeter than the values currently being a.
calculated in Specification 4.1'.2.3, in lieu of a Licensee Event Report, identify the new location (s) in the next Semiannual Radioactive Ef fluent Release Report, pursuant to Specification 6.9.1.12.
With a land use census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) b.
20 percent greater than at a location from which samples are cur-rently being obtained in accordance with Specification 3.12.1, add the new location (s) to the radiological environmental monitoring l
The sampling location (s), excluding the program within 30 days.
control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program af ter (October 31) of the year in which this land use :ensus was conducted.
In lieu of a Licensee Event Report and pursuant to Specification 6.9.1.12, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s),
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
c.
SURVE1LLANCE REQUIREMENTS The land use census shall be conducted during the growing season at 4.12.2 least once per 12 months using that information that will provide the best results, such as by a door-to-door-survey, aerial survey, or by consulting The results of the land use census shall be local agriculture authorities. included in the Annual Radiological Environmental Op l
Specification 6.9.1.11.
I
- Broad laaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different direction sectors Specifications with the highest predicted D/Qs in lieu of the garden census.
l for broad leaf vegetation sampling in Table 3.12-1.4c shall be followed, including analysis of control samples.
6/4/82 3/4 12-13 PWR-STS-1 l
1.'c RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 1NTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION Analyses shall be performed on radioactive materials supplied as part 3.12.3 of an'interlaboratory Comparison Program that has been approved by the Commission.
APPLICABILITY: At all times.
ACTION:
With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission a.
in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.11.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable, b.
i l
SURVEILLANCE REQUIREMENTS A summary of the results obtained as part of the above required 4.12.3 Interiaboratory Comparison Program and in accordance with the methodology and parameters in the ODCM shall be included in the Annual Radiological 11.
aental Operating Report pursuant to Specification 6.9.1.
i Env' i
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L 6/4/82 i
3/4 12-14
-PWR-STS-!
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3/4.12 RA010 LOG 1 CAL ENVIRONMENTAL MONITORING BASES i
l 3/4.12.1 MONITORING PROGRAM The radiological environmental monitoring program required by this specification provides representative measurements of radiation _and of radio-active materials in those exposurt pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation.
This monitoring program implementsSection IV.B.2 of Appendix ! to 10 CFR Part 50 and thereby supplements the radiological affluent monitoring program by verifying that the measurable i
}
concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of-the environmental exposure pathways.
The initially specified monitoring program will be effective for at least the first three years of commercial operation.
Following this period, program changes may be initiated based on operational experience.
The required detection capabilities for environmental sample analyses are-tabulated in terms of the lower limits of detection (LL0s).
The LL0s required by Table 4.12-1 are considered optimum for routine environmental measurements in industrial laboratories.
It should be recognized that the LLO is defined as an a priori (before the fact) limit representing the capa-bility of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement, Detailed discussion of the LLO, and other detection limits, can he found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A.. " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968), and Hartwell, J.
K., " Detection Limits for Radioana.lytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-5A-215 (June 1975).
PWR STS-1 8 3/4 12-1 6/4/82
_m
'e 3/4.12 RADIOLOGICAL.-ENVIRONMENTAL MON 1TORING I
i BASES A
J/4.12.2 LAND USE CENSUS
' This specification is~ provided to ensure that changes in the use _ of areas p
at and beyond the SITE SOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results ofJthis census.
The best information from the door-to-door survey, f rars eerVA1 survey or from consulting with local agricultural euthorities shall be usedi This census satisfies the requirements of Section IV 8.3 of Appen-dix ! to'10 CFR Part 50.
Restricting the census to' gardens of greater than 50 m2 provides assurance that significant exposure pathways via: 1eafy vege-tables =will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child.
To determine this minimum garden size, the following assumptions were made:
- 1) 20% of the
. garden was used for growing broad leaf vegetation (i.e., similar to lettuce 8
and cabbage), and 2) a vegetation yield of 2 kg/m.
3//
1NTEP!.ABORATORY=COMPARISONPROGRAM requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accu-racy of the measurements of radioactive material in environmental sample matrices are performed as part nf the quality assuranct program for environ-mental _ monitoring in order to demonstrate that the results are reasonably valid for-the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.
I I
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k PWR-STS B 3/4.12-2 6/4/82
ADMIN 151NM 1vt t0NTROLS
-}.
N ANNUAL RADIOLOGICAL,ENVIRONMENTAt OPERATING REPORT
- Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous eslandar year shall be submitted p 6.9.1.11 The initial report shall be submitted prior to May 1 to May 1 of each year.
of the year following initial criticality.
l The Annual Radiological Environmental Operating Reports shall include summa interpretations, and an analysis of trends of the results of the radiological includino a compar-environmental surveillance activities for the report period,Qyropriatf, and I
ison[Jilh7e6irirational studles, with operational controls ~
with previous environmental surveillance reports, and an assessment of theThe repo observed impacts of the plant operation on the environment.als The Annual Radiological Environmental Operating Reports shal) include 'he re cf analysis of all radiological.environmenta) samples and of all environmental radiation measurements taken during the period pursuant to the locations spec L
fled in the Table and Figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table iti the Radiological Assessment Branch Technical Position, Revision 1, November 197 In the event that some individual results are not available for inc the report, the report shall be submitted noting and explaining the reasons for The missing data shall be submitted as soon as possible the missing results.
in a supplementary report.
a summary description of the The reports shall also include the following:
radiological environmental monitoring program; at least two legible maps **
l covering all-sspling locations keyed to a table giving distances aind directions l
from the centerline of one reactor; the results of licensee discussion of all analyses in which the LLD required by Table 4.12-1 was not
~
how. hM kW %'ll. -.- y,-2 + r 4 '
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'A single submittal may be made for a multiple unit station.
- 0ne map shall cover stations near the site boundary; a second shall include
-the more distant stations, i
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l 6.10 ' RECORD RETENTION for the duration of the Unit
.6.10.2' The following records sha11 be retained i
Operating License:
Records of analyses required by the radiolo of
- n.
This should include procedures the analysis at a later date. effective at specified tie:s and QA i
/f procedures were followed.
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1 6.14 0FF51TE 00$f CAtCULATION MANUAL (ODCM)
The ODCM shall be approved by the Commission prior to implementation.
6.14.1 6.14.2 Licensee initiated changes to the ODCM:
Shall be submitted to the Commission in the Semiannual Radioa Ef fluent Release Report for the period in whien the change (s) was 1.
made effective. This submittal shall contain:
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supple-a.
mental information.
Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaivations justifying the change (s);
A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; b.
and Documentation of the f act that the change has been reviewed and l
f found acceptable by the (URG).
.c.
Shall become effective upon review and acceptance by the (URG).
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