ML19210B050
| ML19210B050 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/31/1978 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19210B047 | List: |
| References | |
| NUDOCS 7911010780 | |
| Download: ML19210B050 (17) | |
Text
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AN ACCEPTABLE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Program Requirements Environmental samples shall be lected and analyzed according to Table 1 at locations shown in Figure 1.
Analytical techniques used shall be such that the detection capabilities in Table 2 are achieved.
The results of the radiological environmental monitoring are intended to supplement the results of the radiological effluent monitoring by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measure-ments and modeling of the environmental exposure pathways.
Thus, the specified environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and for those radio-nuclides which lead to the highest potential radiation exposures of indivi-duals resulting from the station operation.
The initial radiological environ-mental monitoring program should be conducted for the first three years of commercial operation (or other period corresponding to a maximum burnup in the initial core cycle).
Following this period, program changes may be proposed based on operational experience.
The specified detection capabilities are state-of-the-art for routine environmental measurements in industrial laboratories.
The LLDs for I-131 in water, milk and other food products correspond to one quarter of the Appendix I (10 CFR Part 50) design objective dose-equivalent of 15 mrem /yr for atmospheric releases and 10 mrem /yr for liquid releases to the most sensitive organ and age group.
They are based on the assumptions given in Regulatory Guide 1.109, Rev 1.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons.
If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period.
All deviations from the sampling schedule shall be documented in the annual report.
The laboratories of the licensee and licensee's contractors which perform analyses shall participate in the Environmental Protection Agency's (EPA's)
Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck)
Program or equivalent program.
This participation shall include all of the 1 It may be necessary to require special studies on a case-by-case and site specific basis to establish the relationship between quantities of radioactive material released in effluents, the concentrations in environmental media, and the resultant doses for important pathways.
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7Po 7911010 MA i
determinations (sample medium-radionuclide combination) that are offered by EPA and that also are included in the monitoring program.
The results of analysis of these crosscheck samples shall be included in the annual report..
If the results of a determination in the EPA crosscheck program (or equivalent program) are outside the specified control limits, the laboratory shall investigate the cause of the problem and take steps to correct it.
The results of this investigation and corrective action shall be included in the annual report.
The requirement for the participation in the EPA crosscheck program, or similar program, is based on the need for independent chtcks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.
A census shall be conducted annually during the growing season to determine the location of the nearest milk animal and nearest garden greater than 50 sq. mcters (500 sq. ft.) producing broad leaf vegetation in each of the 16 meteorological sectors within a distance of 8 km (5 miles).2 For elevated releases as defined in Regulatory Guide 1.111, Rev.
1., the census shall also identify the locations of all milk animals, and gardens greater than 50 sq. meters producing bTo~ad leaf vegetation out to a distance of 5 km. (3 miles) for each radial sector.
If it is learned from this census that the milk animals or gardens are pre-sent at a location which yields a calculated thyroid dose greater than those previously sampled, or if the census results in changes in the location used in the radioactive effluent technical specifications for dose calculations, a written report shall be submitted to the Director of Operating Reactors, NRR (with a copy to the Director of the NRC Regional Office) within 30 days identifying the new location (distance and direction). Milk animal or garden locations resulting in higher calculated doses shall be added to the surveillance program as soon as practicable.
The sampling location having the lowest calculated dose may then be dropped from the surveillance program at the end of the grazing or growing season during which the census was conducted.
Any location from which milk can no longer be obtained may be dropped from the surveillance program after zBroad leaf vegetation sampling may be performed at the site boundary in a sector with the highest D/Q in lieu of the garden census.
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notifying the NRC in writing that they are no longer obtainable at that location.
The results of the land-use census shall be reported in the annual report.
The census of milk animals and gardens producing broad leaf vegetation is based on the requirement in Appendix I of 10 CFR Part 50 to "1dentify changes in the use of unrestricted areas (e.g., for agricultural purposes) to permit modifications in monitoring programs for evaluating doses to individuals from principal pathways of exposure." The consumption of milk from animals grazing on contaminated pasture and of leafy vegetation con-taminated by airborne radiciodine is a major potential source of exposure.
Samples from milk animals are considered a better indicator of radiciodine in the environment than vegetation.
If the census reveals milk animals are not present or are unavailable for sampling, then vegetation must be sampled.
The 50 sq. meter garden, considering 20% used for growing broad leaf vege-tation (i.e., similar to lettuce and cabbage), and a vegetation yield of 2 kg/m, will produce the 26 kg/yr assumed in Regulatory Guide 1.109, 2
Rev 1., for child consumption of leafy vegetation.
The option to consider the garden to be broad leaf vegetation at the site boundary in a sector with the highest D/Q should be conservative and that location may be used to calculate doses due to radioactive effluent releases in place of the actual locations which would be determined by the census.
This option does not apply to plants with elevated releases as defined in Regulatory Guide 1.111, Rev. 1.
Reporti g Requirement A.
An ual Environmental Operating Report, Part B, Radiological.
A report on the radiological environmental surveillance program for the previous calendar year shall be submitted to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) as a separate document by May 1 of each year.
The period of the first report shall begin with the date of initial criticality.
The reports shall include a summary (format of Table 3),
interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with operational controls, preoperational studies (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the station operation on the environment.
In the event that some results are not available the report shall be submitted noting the explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supple-mentary report.
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The reports shall also include the following:
a summary description of the radiological environmental monitoring program including sampling methods for each sample type, size and physical characteristics of each sample type, sample preparation methods, analytical methods, and measuring equipment used; a map of all sampling locations keyed to a table giving distances and directions from one reactor; the results of land use censuses; and the results of licensee participation in the Environmental Protection Agency's Environmental P.adioactivity Laboratory Interecm-parisons Studies (Crosscheck) Program.
B.
Nonroutine Radiological Environmental Operating Reports "If a confirmed 3 measured radionuclide concentration in an environ-mental sampling medium averaged over any quarter sampling period exceeds the reporting level given in Table 4, a written report shall be submitted to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) within 30 days from the end of the quarter.
If it can be demonstrated that the level is not a result of plant effluents (i.e., by comparison with control station or preoperational data) a report need not be submitted, but shall be discussed in the annual report. When more than one of the radionuclides in Table 4 are detected in the medium, the reporting level shall have been exceeded if:
concentration (1) concentration (2)
, ***, y reporting level (1) reporting level (2)
If radionuclides other than those in Table 4 are detected and are due from plant effluents, a reporting level is exceeded if the potential annual dose to an individual is equal to or greater than the design objective doses of 10 CFR Part 50, Appendix I.
This report shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous result.
aA confircatory reanalysis of the original, a duplicate, or a new sample may be desirable, as appropriate.
The results of the confirmatory analysis shall be completed at the earliest time consistent with the analysis, but in any case within 30 days.
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TABLE 1 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples
- Sampling and Type and frequency dnd/or Sample and locations Collection Frequency and Analysis AIRBORNE Radiciodine and Samples from 3 offsite locations (in Radioiodine Cannister:
Particulates different sectors) of the highest analyze weekly for calculated annual average ground-I-131 level D/Q.
h d
1 sample from the vicinity of a Continuous sampler Particulate Sampler:
community having the highest operation with sample Gross beta radio-calculated annual average ground-collection weekly or activity folloging level D/Q.
as required by dust filter change, composite loading, whichever is (bylocapion)forgamma more frequent isotopic quarterly 1 sample from a control location 15-30 km (10-20 miles) distant and d
in the least prevalent wind direction DIRECT RADIATION 2 or more dosimeters or one in-Monthly or quarterly Gamma dose monthly or strument for measuring and record-quarterly ing dose rate continuously to be placed at each of the same loca-tions as for air particulates, and at each of three additional offsite g
locations (different sectors) or W
highest calculated annual average ground-level X/Q.
tn O
C7s u
N N
TABLE 1 (Continued)
I Exposure Pathway Number of Samples
Sampling and Type and frequency a
dnd/or Sdmple and locations Collection Frequency of Analysis WATERBORNE Composite sample Gamma is topic analysis Surface 9 1 sample upstream one-month period *yer monthly.
Composite for h
I sample downstream tritium analyses quarterly Samplesfrom1or2scurgesonly Quarterly Gamma isotopic and h
Ground if likely to be affected tritium analysis quarterly Drinking 1 sample of each of 1 to 3 of Composite sample I-131 analysis on each the nearest. water supplies which over two week period' composite when the dose could be affected by its if I-131 anlysis is calculated for the con-discharge performed, monthly sumption of the water composite otherwise is greate{ than 1 mrem per year.
Composite for Gross p and gamma isotopic analyses monthly.
Compo-site for tritium analysis quarterly I sample from a control location Sediment from I sample from downstream area Semiannually Gamma isotopic analyses Shoreline with existing or potential semiannually recreational value INGESTION LD
[
Samples from milking animals Semimonthly when ani-Gamma isotopic and 1-131 Milk in 3 locations within 5 km mais are on pasture, analysis semimonthly when distant having the highest dose monthly at other times animals are on pasture; N
potentic1.
If there are none, monthly at other times.
co
- then, 1 :, ample from milking animals in each of 3 areas between 5 to 8 km distant where doses are calculated to be k
greater than I mrem per year
TABLE 1 (Continued) a Exposure Pathway Number of Samples Sampling and Type and frequency a
and'or Sample and Locations Collection Frequency of Analysis 3
Milk (cont'd)
I sample from milking animals at a control location (15-30 km distant and in the least prevalent wind direction)
Fish and I sample of each commercially and Sample in season, or Gamma isotopic Invertebrates recreationally important species semiannual)y.tf they are analysisonedill) in vicinity of discharge point not seasonal portions 1 sample of same species in areas not influenced by plant discharge j
Food Products 1 sample of each principal class At time of harvest Gamma isotopic of food products from any area analysis on edible which is irrigated by water in portion.
1-131 which liquid plant wastes have analysis on broad been discharged leaf vegetation 3 samples of broad leaf vegetation Monthly when available grown nearest offsite locations of highest calculated annual average ground-level D/Q if milk sampling is not performed 1 sample of each of the similar Monthly when available lll vegetation grown 15-30 km distant in the least prevalent wind direction LJ7 if milk sampling is not performed Ch Ch U
NW
TABLE I (Continued)
"The number, media, frequency and location of sampl ug may vary from site to site.
It is recognized that, at times, it may not be possible or practical to obtain samples of the media of choice at the most desired location or time.
In these instances suitable alternative media and locations may be chosen for the particular pathway in question and submitted for acceptance.
Actual locations (distance and direction) from the site shall be provided.
Refer to Regulatory Guide 4.1, " Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants."
Particulate sample filters should be analyzed for gross beta 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and b
thoron daughter decay.
If gross beta activity in air or water is greater than ten times the mean of control samples for any medium, gamma isotopic analysis should be performed on the individual samples.
' Gamma isotopic analysis means the identific ation and quantification of gamma-emitting radionuclides that may be dttributable lo the effluents from the facility.
ihe purpose of this sample is to obtain background information.
If it is not practical to establish control loca-d tions in accordance with the distance and wind direction criteria, other sites which provide valid background data may be substituted.
" Canisters for the collection of radioiodine in air are subject to channeling.
These devices should be carefully checked before operation in the field or several should be mounted in series to prevent loss of iodine.
I Regulatory Guide 4.13 provides minimum acceptable performance criteria for thermoluminescence dosimetry (ILD) systems used for environmental monitoring.
One or more instruments, such as a pressurized ion chamber, for measur-ing and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters.
for the purposes of this table, a thermoluminescent dosimeter may be considered to be one chip, and two or more chips in a packet may be considered as two or more dosimeters.
UIhe " upstream sample" should be taken at a distance beyond significant influence of the discharge.
The "down-stream" sample should be taken in an area beyond but near the mixing zone.
" Upstream" samples in an estuary must be taken far enough upstream to beyond the plant influence.
g hGenerally, salt water is not sampled except when the receiving water is utilized for recreational activities.
Composite samples should be collected with equipment. (or equivalent) which is capable of collecting an aliquot at time intervals which are very short (e.g., nourly) relative to the compositing period (e.g., monthly).
W 3 Groundwater samples should be taken when this source is tapped for drinking or irrigation purposes in areas where O
the hydraulic gradient or recharge properties are suitable for contamination.
O k Ihe dose shall be calculated for the maximum organ and age group, using the methodology contained in Regulatory u
Guide 1.109, Rev.
1., and the actual parameters particular to the site.
v4 lit harvest occurs more than once a year, sampling should be performed during each discrete harvest.
If harvest c
occurs continuously, sampling should be monthly.
Attention should be paid to including samples of tuborous and root iood products.
TABLE 1 (Continued)
Note:
In addition to the above guidance for operational monitorin0. the following material is supplied for guid-ance on preoperational programs.
Preoperational Environmental Surveillance Program A Preoperational Environmental Surveillance Program sho. tid be instituted two years prior to the institution of station plant operation.
The purposes of this program are:
g 1.
To measure background levels and their variations along the anticipated critical pathways in the area surrounding the station.
2.
To train personnel 3.
To evaluate procedures, equipment and techniques lhe elements (sampling media and type of analysis) of both preoperational and operational proorams should be essen-tially the same.
The duration of the preoperational program, for specific media, presented ', the following table should be followed:
Duration of Preoperational Sampling Program for Specific Media 6 months 1 year 2 years iodine in milk (while
. milk (remaining analyses)
. fishandinvertebratesll)
. direct radiation airborne iodine
. airborne particulates animals are in pasture)
. surface water food products
. groundwater
. sediment from shoreline t>7 drinking water Ch Ch U
Cr4
TABLE 2 Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD)
Airborne Particulate Water or Gas Fish Milk Food Products Sediment Anaysis (pCi/1)
(pCi/m )
(pCi/kg, wet)
(pCi/l)
(pCi/kg, wet)
(pCi/kg, dry) 3 c
-2 gross beta 2
i x 10 3H 330 54 130 Mn 15 59 260 fe 30 58,60Co 15 130 652n 30 260 bZr-Nb 10 d
131 d
-2 d
25 '*
1 0.5 7 x 10 0.8 134,137
-2 Cs 15 1 x 10 130 15 80 150 Os 140 os Ba-La 15 15 6
U N
TABLE 2 NOTES aAcceptable detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.
bTable 2 indicates acceptable detection capabilities for radioactive materials in environmental samples.
These detection capabilities are tabulated in terms of the lower limits of detection (LLDs).
The LLD is defined, for purposes of this guide, as the smallest 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 falsely con-cluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66 s b LLD =
E V 2.22 exp(-Aat)
Y where LLD is the lower limit of detection as defined 7. Dove (as pCi per unit mass or volume) s is the standard deviation of the background counting rate or of bthe counting rate of a blank sample as appropriate (as counts per 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
? is the fractional radiochemical yield (when applicable)
A is the radioactive decay constant for the particular radionuclide at is the elasped time between sample collection (or end of the sample collection period) and time of counting The value of Sg used in the calculation of the LLD for a particular measure-ment system sh0uld be based on the actual observed variance of the back-ground counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicated variance.
In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background should include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples).
Typical values of E, V, Y and at should oe used in the calculation.
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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 a posteriori (af ter the fact) limit for a particular measurement."
C LLD for drinking water.
d 131 LLDs for 1 in water, milk and other food products correspond to one-quarter of the Appendix I (10 CFR Part 50) design objective dose equivalent of 15 mrem / year for atmospheric releases and 10 mrem /yr for liquid releases to the most sensitive organ and age group using the asssumptions given in Regulatory Guide 1.109, Rev. 1.
'LLD for leafy vegetables.
U or a more complete discussion of the LLD, and other detection limits, see tiie following:
(1) HASL Procedures Manual, HASL-300 (revised anntally).
(2) Currie, L.
A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968).
(3) Hartwell, J.
K., " Detection Limits for Radioisotopic Counting Techniques," Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).
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TABLE 3 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL
SUMMARY
Name of Facility Docket No.
Location of Facility Reporting Period (County, State)
Medium or Type and Lower Limit All Indicator Location with Highest Controllocatgons Number of L cation Annual Mean Mean (f)
Nonroutine Pathway Sampled Total Number of Mean(f)g Mean (f)b Range Reported a
Name (Unit of of Analyses Detection Measurement)
Performed (LLD)
Range Distance &
Range Measurements Direction Air Particu 3) lates (pCi/m Gross p 416 0.01 0.08(200/312) Middletown 0.10 (5/52) 0/08 (8/104) 1 (0.05-2.0) 5 miles 340 (0.08-2.0)
(0.05-1.40) y-Spec. 32 137 0.01 0.05 (4/24)
Smithville 0.08 (2/4)
<LLD 4
Cs (0.03-0.13) 2.5 miles 160* (0.03-2.0) 131 0.07 0.03 (2/24)
Podunk 0.05 (2/4) 0.02 (2/4) 1 g
(0.01-0.08) 4.0 miles 270 (0.01-0.08)
Fish pCi/kg (wet weight) y-Spec. 8 137 130
<LLD
<LLD 90 (1/4) 0 Cs 134 130 CD 6
6 0
g Cs 60, 130 120 (3/4)
River Mile 35 See Column 4
<LLD 0
(90-200)
[h See Table 3, note b.
m Mean and range based upon detectable measurements only.
Fraction of detectable measurements at specified locations is indicated in parentheses.
(f)
'u' Note:
The example data are provided for illustrative purposes only.
c U1
TABLE 4 REPORTING LEVELS FOR NONROUTINE OPERATING REPORTS Reporting level (RL)
Broad Leat Water Airborne Particulate Fish Hilk Vegetation Analysis (pCi/l) or Gases (pCi/m )
(pCi/Kg, wet)
(pCi/l)
(pCi/Kg, wet) h 3
4 H-3 3 x 10 3
4 Mn-54 1 x 10 3 x 10 2
4 Fe-59 4 x 10 1 x 10 3
4 Co-58 1 x 10 3 x 10 2
4 Cc-60 3 x 10 1 x 10 2
4 Zn-65 1 x 10 2 x 10 2
Zr-Nb-95 4 x 10 g
2 1-131 2
0.9 3
1 x 10 3
3 Cs-134 30 10 1 x 10 60 1 x 10 3
3
~
Ln Cs-137 50 20 2 x 10 70 2 x 10 Cs 2
2 Ba-La-140 2 x 10 3 x 10
._~
CA I
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Metropolitan Edison Cotapany cc:
G. F. Trowbridge, Esquire Shaw, Pi ttman, Potts & Trowbridge 1800 M Street, N.W.
Washington, D.C.
20036 GPU Service Corporation Richard W. Heward, Project Manager Mr. T. Gary Brouahton, Safety and Licensing fianager 250 Cherry Hill Road Parsippany, New Jersey 07054 Pennsylvania Electric Company Mr. R. W. Conrad Vice President, Generation 1001 Broad Street Johnstown, Pennsylvania 15907 Miss Mary V. Southard, Chairman Citizens for a Safe Environment P. O. Box 405 Harrisburg, Pennsylvania 17108 Government Publications Section State Library of Pennsylvania Box 1601 (Education Building)
Harrisburg, Pennsylvania 17126 1566 337 Y
Figure 1 (This figure shall be of a suitable scale to show the distance and direction of each monitoring station.
A key shall be provided to indicate what is sampled at each location.)
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UNITED STATES I
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NUCLEAR mEQULATomV COMMISSION WASHINGTON, D. C. 20555 u.s. nucksan macuLaTony OPPICI AL SUSINESS C # "" ' 0 "
gM PEN ALTY PO R PalVATE USE, $300 LJ d
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