ML19031A733
| ML19031A733 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/31/1977 |
| From: | Public Service Electric & Gas Co, Radiation Machinery Corp |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| RMC-TR-77-02 | |
| Download: ML19031A733 (31) | |
Text
RMC-TR-77-02 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DECEMBER 11 TO DECEMBER 31, 1976 Prepared For PUBLIC SERVICE ELECTRIC AND GAS COMPANY By RADIATION MANAGEMENT CORPORATION MARCH 1977
RMC-TR-77-02 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM December 11 to December 31, 1976 Prepared for Public Service Electric and Gas Company By Radiation Management Corporation March 1977
SUMMARY
INTRODUCTION THE PROGRAM Objectives TABLE OF CONTENTS Sample Collection Data Interpretation RESULTS AND DISCUSSION CONCLUSIONS REFERENCES APPENDIX A - PROGRAM
SUMMARY
APPENDIX B - SAMPLE DESIGNATION & LOCATIONS APPENDIX C - DATA TABLES PAGE 1
2 2
2 3
4 5
8 9
11 17
- 25
SUMMARY
During the*period December 11 to December 31, 1976, Radiation Management Corporation participated in the Operational Radiological Environmental Monitoring Program conducted by Public Service Electric and Gas Company at Artificial Island, New Jersey. Salem Nuclear Generating Station (SNGS) Unit
- 1 became critical on December 11, 1976 thereby initiating the operational phase of the Radiological Environmental M:>nitoring Program (REMP).
This program was designed to identify and quantify concentrations of radioactivity in various environmental media and to quantify ambient radiation levels in the environs of Artificial Island.
During the operational phase, the program will monitor the operations of SNGS Unit #1, fulfill the requirements of.the SNGS Environmental Technical Specifications, and provid~ background data for SNGS Unit #2 and Hope Creek Generating Station. This report presents the results of radiachemical analyses of environmental samples and thermoluminescent dosimetry from the initial operational period of SNGS Unit#l, December 11 to December 31, 1976.
During the initial operational period 327 analyses were performed on 123 samples.
Due to the brief nature of the initial operational period, samples were limited to air particulates, air iodine, preci~itatibn, well water, potable water, milk, game and thyroid samples.
Thermolumfr1escent dosimeters were used to measure ambient -radiation.levels. A wide variety of radionuclides, both naturally occurring and man-made, were found in the above samples.
These nuclides were detected at levels similar to those
- found during the preoperational phase of this program and no significant differences were observed between indicator and control stations. Some media showed the after-effects of the Chinese nuclear test of September 26, 1976. It is concluded that the radi-0logical characteristics of the environment around Artificial Island were no:t affected by SNGS Unit #1 during its ini.tial operational period~
1
INTRODUCTION Radiation Management Corporation (RMC) has participated in the Artificial Island Radiological Environmental Monitoring Program (REMP) since January 1973.
RMC has previously reported results from the preoperational phase of the REMP fa~ 1973(1), 1974(2), and 1975(3).
On December 11, 1976, SNGS Unit #1 became critical thereby initiating the operational phase of the REMP.
This report covers the initial operational period of December 11, through December 31, 1976. It presents in detail the type and number of samples analyzed, the analyses performed and the data generated by RMC during the intitial operational period. Interpretation of the data and conclusions are presented.
Artificial Island is the future site of four nuclear power reactors.
Two of the *reactors.are part of the Salem Nuclear Generating Station. Unit #1 is a 1090 MWe pressurized water reactor.(PWR), and is operational presently.
Unit.#2, now under construction, will consist of an 1115 MWe PWR and is scheduled for operation in the spring of 1978.
The remai"ning two units will be part of the Hope Creek Generating Station.
Artificial Island.is.actually a man-made peninsula in the Delaware River resulting from the deposition of dredging spoils. It is located in Lower Alloways Creek Township, Salem County, New Jersey.
The site consists of a 220 acre plot which occupies the' southwest quarter of the 700 acre plot owned by Public Service Electric and Gas Company.
The environment around Artificial Island is characterized mainly by the Delaware River and Bay, extensive tidal marshes and grass lands. These land types make up approximately 85% of the land area within five miles of the site. l\\k>st of the remaining land is used for agricultural production. (4)
More specific information on the demography, hydrology, meteorology and land use characteristics of the local* area may be found in the Environmental Report (4), Environmental Statement (5) and the Final Safety Analy!?eS Report (Units 1 and 2) for SNGS (6).
THE PROGRAM In the operational phase of the REMP, the program was conducted in accordance with SNGS Environmental Technical Specifications. Radioanalytical data were collected for comparison with results of the preoperational phase.
Differences between these periods were examined statistically to determine whether any station effects exist. These observations were based on the magnitude and fluctuations of radioactivity levels determined in the pre-operational phase.
Objectives The objectives of the operational radiological environmental program are:
- 1.
To fulfill the obligations of the Radiological Surveillance-Environmental sections of the Environmental Technical Specifications for SNGS.
- 2.
To determine whether any statistically significant increase occurs in the concentration of radionuclides in critical pathways.
- 3.
To detect any buildup of long-lived radionuclides in the environment.
2
- 4.
Tb detect any change in ambient garrma radiation levels.
'5. To verify that radioactive releases are within allowable limits and that SNGS op~rations have no detrimental effects on the health and safety of the public or,on the environment.
This report provides information for the Public Service Electric and Gas Company, regulatory agencies and the public record toward these objectives.
Sample Collection In order to meet the stated objectives, an appropriate operational REMP was.
developed by RMC in cooperation with Public Service Electric and Gas Company.
The operational, REMP includes samples from the aquatic, atmospheric, and
- terrestrial environments and TLD's to measure ambient radiation. *samples of various media were selected to obtain data for the evaluation of the radiation dose to man and important organisms.
Sample types were based on (1) *established critical pathways for the transfer of radionuclides through the environment to man, and (2) experience gained during the preoperational phase.
Sampling locations were determined from site meteoro_logy, Delaware estuarian hydrology, local demography and land uses.
Sampling locations were divided into two classes-- indicator and control.
Indicator stations are those which are expected to.manifest station effects, if any* exist; control samples are collec~ed at locations which are believed-.
to be unaffected by station operations. Fluctuations in the levels of radio-nuclides and direct radiation at indicator stations ate evaluated with respect**
to analogous fluctuations at control stations, which are unrelated to station operation.
Indicator station data are* also evaluated relative to background characteristics established prior to station operation. Additional samples beyond those required by the environmental Technical Speci*fications Were collected and analyzed.
Although no aquatic samples were taken during this period, the aquatic portion
- of the REMP will include fish, prey fish, blue crabs, benthic*organisms, and sediment. All aquatic.samples will be collected by Ichthyological Associates and shipped to RMC.
The atmospheric environment w*as examined by analyzing air particulate filters, iodine cartridges, and precipitation. Air particulates were collected on Hollingsworth and Vose H-70-018 filters with low-volume air samplers (1 cfm).
Iodine was collected from air by adsorption on TEDA charcoal c~rtridges connected in series behind the air particulate filters. Air sample volumes were measured with calibrated dry-gas meters, corrected to standard temperature and pressure.* Pretipitation was collected on a 95 square-inch rain gauge.*
Samples were collected monthly and transferred to new polyethylene bottles.
The rain gauge was rinsed at collection with distilled water to include residual particulates in the precipitation samples.. Results of subsequent analyses
- were corrected for the increase in volume.
Tritium results were also corrected for the tritium content of the distilled water.
3.
The terrestrial environment was examined by analyzing samples of well water, potable water, milk, beef, game, and animal thyroid tissue. Monthly well a~d potable water samples were taken in new two gallon polyethylene bottles.
Separate raw and treated potable water samples were composited daily by personnel of the Salem Water Company.
The Salem Water Company draws its water from Laurel Lake and *adjacent wells, not expected to be influenced by SNGS liquid discharge. Milk samples were taken in new polyethylene bottles and shipped fresh.
Game, beef and thyroids were taken and shipped fresh to RMC.
Ambient radiation levels in the environs were measured with energy compensated Caso4(Tm), thermoluminescent dosimeters (TLDs).
Packets containing four TLDs each were placed on and around the Artificial Island site at various distances and were exposed on a monthly and quarterly basis.
The full operational program is described in Appencix A, as well as a description of the initial operational :phase.
App~ndix B describes the RMC coding system,
~hich specifies sample type and relative locations at a glance. Also in Appendix B, Table B-_1 gives the pertinent information on individual sampling locations,.while map~ B-1 and B-2 show their geographic locations.
Data *interpretation.
Radiation Management Corporation has an extensive quality assurance program
- designed to maximize confidence in the analytical procedures used.
The analytical methods and quality control procedures utilized in this program are described in an RMC publication (8). Approximately 20% of the total analytical effort is spent on quality control including process quality control; i.nstrument quality control, inter-laboratory cross-check analyses, and comprehensive data review.
The analytical data generated during the program also are.routinely evaluated by the RMC project leader who is the liaison with. Public Service Electri.c and Gas Company personnel. Several factors are important in the interpretation of the data. These factors are discussed here to avoid repetition in sections that follow.
Grab Sampl 1 ng is a usefu.l and acceptable procedure for taking environmental
_samples of a medium.in which th~ concentration of radionuc)ides is expected to vary slowly with time or where intermittent sampling is deemed sufficient_
to establish the radiological characteristics of the medium.
This method, however; is only representative of the sampled medium for that specific location*and instant of time.
As a result, variation in the radionuclide conceritrations of the samples will normally; occur. Since these variations will tend to counterbalance one another, the extraction of averages based upon repetitive grab samples is valid.
It is characteristic of environmental monitoring data that many results occur at or below the minfmum detectable level (MDL), as defined in reference.8.
For reporting and calculation.of averages, any result occurring at or below the minimum detectable 1 evel is consi der~d to _be at that level.
- Averag~s obtained using this.method are therefore biased high.
Within the data tables (Appendix C) an approximate 95% (+/-2 sigma) confidence interval is supplied for those data points above the minimum detectable level.
These intervals represent the range of values into which 95% of repeated analyses of the same sample would fall.
4
Results for each type of sample were qrouped according to the analysis performed.
Means and standard deviations of these results were calculated
- when appl i cab 1 e.: *The calculated standard deviations of grouped data represent sample rather than analytical variability.
For these calculations any values below MDL were considered to be at the MDL. *As a result, the means are biased high and the standard deviations are biased low.
When a group of data was composed of mainly (>50%) MDL values, averages -were not calculated.
RESULTS AND DISCUSSION The initial operational period of the Artificial Island REMP encompassed only 20 days. A limited number of samples could be taken (and analyses performed) during this short period making analysis of trends or environmental buildup difficult. The analytical results of the REMP are typically divided into four categories: Aquatic, Atmospheric, Terrestrial, and Direct Radiation.
No samples from the aquatic environment were taken during this period.
The individual samples and analyses within each category display the unique radiological characteristics of that type of environment.
The analytical results for the REMP are summarized in Appendix A.
The data for individual samples are presented in Append1x C.
Atmospheric Environment The atmospheric environment in the vicinity of Artificial Island was e*xamined by analyzing samples of air particulates, air iodine, and precipitation~ -Air particulates and air iodine were collected at eight station. Precipitation was also collected at one of these locations - Salem Substation.
Air Particulates Weekly air particulate samples were analyzed for alpha and beta emitters.
Quarterly composites of the weekly samples from each station were analyzed for Sr-89 and* Sr-90.
Of the 8 weekly air particulate samples (two stations)*analyzed for alpha.
emitters, all showed detectable concentrations *. Therange of alpha activity was from 0.0008 to 0.013 pCi/cubic meter and averages 0.004 pCi/cubic meter.
Beta emitter concentrations ranged from 0.029 to 0.111 pCi/cubic meter with an average for the eight sampling stations (32 samples) of 0.057 pCi/cubic meter.
The results of all air particulate analyses did not differ from pre-operational results nor were any signigicant differences between indicator and control*
- stations observed.
Air Iodine Iodine cartridges were connected in series behind each of the air particulate filters for adsorption of gaseous iodine.
The adsorpticin media used in these cartridges was 11TEDA 11 impregnated §harcoal *. Qne sample showed detectable concentrations of I-131 (6.4 fCi/m ). This I-131 was not of SNGS origin since it was detected _at the background station 110 miles from.the site.
Precipitation Precipitation was collected continuously during the initial operational period at the Salem Township sampling location.
The concentration of H-3 in this samples was 197 pCi/l.
The concentration of alpha emitters was below MDL (1.5 pCi/l), while beta emitters were found at a concentration of 13 pCi/l.
Gamma analysis showed detectable levels no gamma emitters.
These nuclides were those typically found during the preoperational phase.
Results of analyses of the one available precipitation sample did not differ from preoperational results.
Terrestrial Environment The terres.trial environment in the vicinity of Artificial Island was examined by analyzing samples of well water, raw and treated potable water, milk, beef, game, and thyroid tissue.
Well Water Well Water samples were taken from an on-site (indicator) well and two off-site (control) wells. All well water samples were analyzed for H-3, alpha and beta activity, K-40 (atomic absorption), gamma emitters, and Sr-89 and Sr-~O.
Concentrations of H-3 were above MDL (80 pCi/l) in two of three samples with the background location showing the highest concentration. Alpha emitter concentrations were less than MDL (1.5 pCi/l) in all samples.
The concentrations of beta emitters averaged 5.7 pCi/l and ranged from <3.0 to 9.1 pCi/l. This beta activity was contributed mainly by K-40 which averaged 5.0 pCi/l, as determined by atomec absorption. Also, Sr-89 and Sr-90 were detected in one sample each (Sr-39 MDL-0.7 to 1.4 pCi/l; Sr-90 MDL-0.4 to 0.9 pCi/l).
Potable Water Both raw and treated water samples were taken at the Salem Water Company, the only drinking water processing plant in the vicinity of Artificial Island.
The raw water source for this plant is Laurel Lake (a tributary of the Delaware River) and severral adjacent wells.
Potable water samples were analyzed for H-3, alpha and beta activity, K-40 (atomic absorption), Sr-89 and Sr-90.,
and garrrna emitters.
The concentration of H-3 averaged 282 pCi/l for all analyses, with no significant differences between the raw and treated samples.
The alpha emitter concentrations were below MDL (1.5 pCi/l) in all samples.. Beta and K-40 concen-trations were lower than in the saline surface water, indicative of fresh water, with K-40 contributing less than 50% of the beta activity. Gross beta concentrations were less than MDL (3.4 pCi/l) for the two samples. The K-40 results were 1.3 pCi/l (raw) and 1.3 pCi/l (treated).
All samples were analyzed for Sr-89 and Sr-90, and gamma emitters.
The concentrations of Sr-89 and Sr-90 were at or below the. respective MDLs, which ranged from 0.9 to 1.2 pCi/l for Sr-89 and from 0.4 pCi/l for Sr-90 in all samples.
No gamma emitters were detected in any of these samples.
As during the preoperational phase, water treatment had no significant effect on any of the analytical parameters measured.
6
Milk Milk samples were taken from five local farms once during the initial operational period and were analyzed for I-131, gamma emitters, and Sr-89 and Sr-90.
I-131 was detected in the December 20 samples as was the case.
- This I-131 was probably the result of fallout from recent nuclear weapons test since the stations.
at which it was detected were all greater than 5 miles.from SNGS.
The highest concentration observed was at the background station 16.6 miles from SNGS.
Gamma spectrometry showed detectable concentrations of K-40 in all samples.
The average concentration was 1520 pCi/l for K-40.
These levels were not signi-ficantly different between stations or from preoperational values.
All Sr-89 values were below the MDL which ranged from 0.6 to 2.5 pCi/l.
The concentrat~on of Sr-90 exceed~d the MDL in 4 of the samples analyzed and averaged 0.9 pCi/l *.
Beef One beef sample was avilable during this period.
Gamma emitters detected were K-40, Cs-137, and Ra-226.
All other gamma emitters were below MDL..
Game Four game samples (2 muskrat, 2 deer) were taken during this period.
Flesh from all four samples was analyzed for gamma emitters while bones from the muskrats were analyzed for Sr-89 and Sr-90. Nuturally occurring K-40 was
- detected in all four samples ranging from 2.4 to 3.8 pCi/g.
In addition naturally occuring Ra-226 was observed in 3 of 4 samples and fission products ZrNb-95 and Cs-137 were present in 2 of 4 samples.
Muskrat bones showed no detectable Sr-89 (MDL 0.01 pCi/g) while Sr-90 was detected in both samples at approximately 0.1 pCi/g.
Thyroid Three thyroids, one beef and two deer, were taken during this period.
Two.
thyroids showed detectable concentrations of naturally occuring K-40.
All*
three thyroid samples showed detectable concentrations I-131 (maximum=
11 pCi/g); no other gamma emitters were detected in these samples.
The deer thyroids showed concentrations two orders of magnitude higher than the bovine thyroid. Since these samples were taken only four days after SNGS became operational, it is unlikely that this iodine was of SNGS origin.
The most probable explanation is that this I-131 was concentrated from atmopheric fallout due to the series of nuclear detonations by the Peoples Republic of China.
Unfortunately no thyroid samples were taken during the known fallout periods so no direct comparison was possible.
Direct Radiation Direct radiation measurements were made at 24 locations using Caso (Tm) thermoluminescent dosimeters.
During this period, 24 monthly and ~4 quarterly TLD packets were collected.
Each packet included four dosimeters for a total*
of 192 analyses~ These analyses resulted in an average dose rate of 5.74 mrads/
standard month for monthly TLDs, and 5.07 mrads/standard month for quarterly TLDs.
All TLD results presented in this report have been normalized-to a standard month (30.4. days) to eliminate the apparent differences caused by the variations>"*
in exposure periods.
The average annual dose from direct radiation in the environs of Artificial Island, computed from the monthly data, is 68 mrads, or 68 mrems assuming a quality factor of 1.
These results compare favorably to preoperational results.
7
CONCLUSIONS The Radiological Environmental Monitoring P*rogram for Salem Nuclear Generating Statiort at Artificial Island was conducted during the initial operational period in accordance with the SNGS Environmental Technical Specifications. The objectives of the program were met during this period.
The data collected shows that SNGS unit #1 was operated in compliance with Environmental Technical Specifications.
From the results obtained, it can be concluded that the levels and fluctuations of-radioactivity in environmental samples were as expected for an estuarine environment.
Ambient radiation levels were relatively low, averaging about 67 mrem/year.
The observation of the* fission product I-131 in a few samples was attributed to residual fallout from the September and November atmospheric weapons tests by the People's Republic of China.
No other unusual radiological characteristics were observed in the environs of Artificial Island.
The operation of SNGS Unit #1 had no descerhable-effect on the radiological characteristics of the environs of Artificial Island.
- 8
REFERENCES (1)
Radiation Management Corporation.
11Salem Nuclear Genera.ting Station -
Radiological Environmental Monitoring Program - 1973 11
- RMC-TR-74-09, 1974.
(2)
Radiation Management Corporation.
11Artificial Island Radiological Environmental Monitoring Program - 1974 Annual Report 11
- RMC-TR-75-04, 1975.
(3)
Radiation Management Corporation 11Artificial Island Radiological Environmental Monitoring Program - 1975 Annual Report 11
- RMC-TR-76-04, 1976.
(4)
Public Service Electric and Gas Company.
11Environmental Report, Operating License Stage - Salem Nuclear Generating Station Units 1 and 2, 11 1971.
(5)
United States Atomic Energy Commission.
11Final Environmental Statement -
Salem Nuclear Generating Station, Units 1 and 2 11 Docket No. 50-272 and 50-311, 1973.
(6)
Public Service Electric and Gas Company.
11 Final Safety Analysis Report -
Salem Nuclear Generating Station, Units 1 and 2 11 1972.
(7)
Ichthyological Associates, Victor Shular, Project Leader.
11An Ecological Study of the Delaware River in the Vicinity of Artificial Island 11 A
Series of Progress Reports since 1971.
(8)
Radiation Management Corporation.
11Radi at ion Management Corporation -
Analysis and Quality Control Program 11 RMC-TM-75-3, 1975.
(9)
Thomann, Robert V.
11 The Delaware River - A study in Water Quality Management 11, River Ecology and Man.
Academic Press, New York, 1972.
(10) United States Department of the Interior - Geological Survey.
11Monthly Water Resources Summary for Pennsyl vani a 11 January 1973 - March 1976.
(11) Bogen, Donald C. and George A. Welford, 111 Fallout Tritium' Distribution in the Environment 11, Health Physics lQ_, P. 203, February 1976.
9
APPENDIX A 11
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERA TI NG STA TI ON DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY DECEMBER 11, 1976 to DECEMBER 31, 1976 ANALYSIS AND LOWER LIMIT NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATIONS NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN**
NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT)
PERFORMED (MDL)
RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Surface Water*
Edible Fish*
Blue Crabs*
Prey Fish*
Zooplankton*
Aquatic Sediment*
Benthos*
Air Particulates Alpha 8
0.4 3.6 (4/4) 16El 4.1 mi. NNW 3.6 (4/4) 4.7 (4/4) 0
( 10-3 pCi/m3) 0.8-9.8 0.8-9.8 1.1-13
.Beta 32 5.0 5.6 (28/28) 2F2 8. 7 mi. NNE 83 ( 4/ 4) 60 (4/4) 0 29-111 40-111 50-79 Air Iodine I-131 24 2.0 (0/20)
( 1/4) 0
<2. 9-64
( 10-3 pCi/m3)
,_. Precipitation Alpha 1
1.5
-.(0/1) 0 w
(pCi/l)
Beta 1
3.0 13 ( 1/ 1) 0 H-3 1
80 197 (1/1) 0 Ga nm a 1
(0/ 1)
(0/1) 0 Well Water Alpha 3
1.5 (0/2)
(Oil) 0 (pCi/l)
Beta 3
3.0
- 4. 0 ( 1/2) 5Bl 3.5 mi. E 5.1 (1/1) 9.1 (1/1) 0 3.0-5.1 H-3 3
80 127 (1/2) 4S2. Site Well 174 (1/1) 236 (1/1).
0 80-174 Sr-89 3
1.5 (0/2)
- 1. 4 (1/ 1) 0 Sr-90 3
0.8 0.6 (1/2) 4S2 Site Well 0.9 (1/1)
(0/ 1) 0 0.4-0.9 K-40 3
6.0 3.0 (2/2) 5Dl 3. 5 mi. E 3.3 (1/1) 8.9 (1/1) 0
. 2.8-.3.3
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY DECEMBER 11, 1976 to DECEMBER 31. 1976 ANALYSIS AND LOWER LIMIT NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATIONS NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN**
NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT)
PERFORMED (MDL)
RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS
. Gatm1a 3
Ra-226 1.0
- 1. 4 ( 1/2) 452 Site Well
- 1. 9 (1/1)
- 2. 2 (1/ 1) 0
- 1. 0-1. 9 Potab1e Water A1pha 2
1.5
- (0/2)
No contro1 0
- ~aw, Treated location (pCi/l)
Beta 2
3;0 (0/2) 0 H-3 2
80.
282 (2/2) 2F3 Raw Water 372 ( 1/1) 0 192-372 Sr-89 2
1.0
- 1. 0 (2/2) 2F3 Treated 1.15 (1/1) 0 0.9-1.2 Sr-90 2
- 1. 0 d.4 ( 1/2) 2F3 Raw Water 0.4 (1/1) 0 0.4-0.4 K-:40 2.
6.0 1.3 (2/2)
- o.
1.3-L3 Garrma 2
(2/2) 0
.f:>
Mi1k I-131 5
0.05 0.1 (2/4) 15Fl 5.2 mi. NW
- 1. 5 (1/1) 0.2 (1/1) 0 (pCi/1) 0.03 -
Sr-89 5
2.0 (0/4)
(0/1) 0 Sr-90 5
0.05
- 1. 0 (3/4) 2Fl 5.0 mi. NNE
- 1. 0 (1/1)
- o. 9 (1/1) 0
- o. 5-1. 0 Gamma 5
K-40 10 1500 (4/4) 14Fl 5.5 mi. WNW 1600 (1/1) 1600 (1/1).
0 1300-1600 Fruits or Vegetation*
Fooder Crops*
Beef Ganma 1
(pCi/g)
K-40 0.1 2.8 (1/1)
No control 0
location Cs-137 4.0 0.01 (1/1) 0 Ra-226 10 0.01 (1/1) 0
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY DECEMBER 11, 1976 to DECEMBER 31, 1976 ANALYSIS AND LOWER LIMIT NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATIONS NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN**
NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT)
PERFORMED (MDL)
RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Game Sr-89 2
0.01 0.08 (1/2) 3El 4.1 mi. NE 0.16 (1/1) 0 (pCi/g) 0.01-0.16 Sr-90 2
0.01 0.04 (1/2) 3El 4.1 mi. NE
- o. 08 (1/1) 0
- 0. 01-0. 08 Garrma 4
K-40 2.8 (3/3) 3El 4.1 mi. NE 3.5 (1/1) 3.8 (1/1) 0 2.4-3.6 ZrNb-95 30 0.02 (2/3) 3El 4.1 mi. NE
- o. 03 (1/1) 0.01 (1/1) 0 0.01-0.03 Cs-137 10 0.01 ( 1/3) 3El 4.1 mi. NE 0.02 (1/1)
- o. 02 (1/1)
- 0. 03 (1/ 1) 0 0.01-0.02 Thyroid Garrma 3
,_. (pCi/g)
K-40 3.3 ( 1/2) 3El 3.5 mi. NE 4.0 (1/1) 3.6 (1/1) 0 CJ1 2.4-4.0 I-131 6.0
- 1. 9 ( 2/2) 3El 3.5 mi. NE 3.8 (1/1) 11 (1/1) 0 0.1-3.8 Direct Radiation Garrma 192 5.3 (40/40) llFl 5.2 mi. SW 6.4 (2/2) 5.1 (8/8) 0 (mrem/std month)
Dose 3.84-6.73 5.4-6.3 Part of preoperational program and future operational programs.
Mean cauculated using MDLs only when 50% of measurements were > MDL.
Fraction of detectable measurements in parentheses.
APPENDIX B 17
APPENDIX B Sample Designation RMC identifies samples by a three part code.
The first two letters are the power station identification code, in this case 11SA 11 The next one to three letters are for the media sampled.
AI
= Air Iodine FPV
= Food Products, Various AP
= Air Particulates GM
= Game AQS
= Sediment ID
= Immersion Dose (TLD)
E
= Soil M
= Milk ECH
= Hard Shell Blue Crab PW
Potable Water; (PWR
=Soft Shell Blue Crab PWT
= treated)
- ESB
= Benthos RW
= Rain Water ESF = Edible Fish SW
= Surface Water ESP
= Prey Fish THB
= Bovine Thyroid ESZ = Zooplankton v
= Fodder Crops FPB
= Beef WW
= Well Water The last four symbols are a location code based on direction and distance from the site.
Of these, the first two represent each of the sixteen angular sectors of 22.5 degrees centered about the reactor site. Sector one is divided evenly by the north axis and other sectors are numbered in a clockwise direction; i.e., 2=NNE, 3=NE, 4=ENE, etc.
The next digit is a letter which represents the radial distance from the plant:
s = On-site location E = 4~5 miles off-site A = 0-1 miles off-site F = 5-10 miles off-site B = 1-2 miles off-site G = 10-20 miles off-site c = 2-3 mil es off-site H = >20 miles off-site D = 3-4 miles off-site The last number is the station numerical designation within each sector and zone; e.g., 1,2,3,..* For example, the designation SA-WW-501 would indicate a sample in the SNGS program SA, consisting of well water (WW), which had been collected in the 22.5 degree sector centered on east axis (5), at a distance of 3 to 4 miles off-site (D).
The number 1 indicates that this is sampling station #1 in the designated area.
19
- raw, l:oii
Sampling Locations All Samplfog locations and specific information about' the individual locatjons are given in table B-1.
Maps B-1 and B-2 Show the locations of sampling stations with respect to the site.
TABLE B-1 STATION STATION CODE LOCATION lSl
- 0.5 mi. No~ vent; meteorological tower 2Sl 1575 ft.- NNE of vent 4S2 Site well #5 ENE *of Vent 5Sl l~O ~i. ~of vent; site access road 6Sl 0.2 mi. ESE of vent; observation platform SAMPLE TYPES ID AP,AI WW
_ ID,AP,AI ID,E 7Sl 0.12 mi. SE of vent; station personnel gate ID lOSl llSl llAl 12Cl 5Dl lODl llDl 14Dl 2El 3El 0.14 mi*. SSW of vent; site shoreline 0.09 mf. SW of vent; site shoreline
- 0.2 mi. SW of vent; outfall area 2.5 mi. WSW of vent; west bank of Delaware river 3.5 mi. E of vent; local farm
- 3. *g mi. SSW of vent; Taylor's Bridge Spur 3.5 mi. SW of Vent 3.4 mi. WNW of vent; Bay View, Delaware 4.4 mi. NNE of vent; local farm 4.1 mi. NE of vent; local farm
- 20.
SW,ESF,ESP, ECH,ECS,ESB, AQS SW,ESF,ESP, ECH,ECS,ESB, AQS 1 D, V,E ~WW, AP,FP ID,AP,AI,E
'GM ID ID,FPV,E ID,THB,FPV, WW,GM,FPB
TABLE B-1 (CONT.)
7El 4.5 mi. SE of vent; 1 mi. W of Mad Horse SW,ESF,ESP, Creek.
ESB,AQS
- 13El' 4.2 mi. W of vent; Diehl House Lab ID 15E2 4~1 mi. NW of vent; local.farm M
16El
- 4.1 mi. NNW of. vent; Port Penn ID,AP,AI,E
. lFl 5.8 mi. N of vent; Fort Elfsborg ID,AP,V,E 1F2 7.1 ~i~ N of vent; midpoint of Delaware SW,ESP,ESB River 2Fl **
5.0 mi. NNE of vent; local farm E;V,M 2F2 8.7 mi. NNE of vent; Salem substation ID,AP,AI, RW,E,M 2F3 8.0 mi. NNE of vent; Salem Water Company PWR,PWT 5Fl 8.0 mi. E of vent GM 5F2 7.0 mi. E of vent; local farm M
6Fl 6.4 mi. ESE of vent; Stow Neck Road ID 7F2 9.1 mi. SE of vent; Bayside, New Jersey ID llFl 5.2 mi. SW of vent; Taylor's Bridge*,
ID Del aware 13El 9.8 mi. W of vent; Middletown, Delaware ID 14Fl 5.5 mi. WNW of vent; local farm V,M,FPB,THB 15Fl 5.2 mi. NW of vent; local farm V,M 16Fl 6.9 mi. NNW of vent; C & D Canal SW,ESB,ESP, AQS lGl 13 mi. N of vent; local farm FPV 1G2 12 mi. N of vent; local farm FPV 3Gl 17 mi. NE. of vent; local farm ID,E,V,M 2Hl 34 mi. NNE of vent; RMC, Phila.
ID 3Hl 32 mi. NE of vent; National Park, N.J.
ID 3H3 110 mi. NE of vent; Maplewood Laboratories ID,AP,AI,E 3H4 18 mi. NE of vent; local fann FPV 21
0 S.CAU OF l,'llLES MAP 8-1
- ON SITE SAMPlJNG LOCATIONS ARTIFICIAL ISLAND -
1976 22
MAP B-2 OFF SITE SAMPLING LOCATIONS ARTIFICIAL 10 9
o.E:E::E::c::'~:=:;:::::~=:;;;;=;;~3======~4[::::=::=~
SCALI OF MILIES ISLAND
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1976
APPENDIX C 25
TABLE NUMBER C-1 C-2 C-3 C-4 C-5 C-6 C-7 DATA TABLES Data tables below present the analytical results of the 1976 Artificial Island Radiological Environmental Monitoring Program for the period of December 11 to the end of the year.
TABLE TITLE Concentrations of Alpha and Beta Emitters in Air Particulates Concentration of Iodine-131 in Filtered Air Concentrations of Alpha, Beta, Tritium, Strontium-89 and-90, Potassium-40, and Gamma Emitters in Precipitation, Well Water, and Potable Water Concentrations of Strontium-89 and-90, I-131 and Gat1111a Emitters in Mi 1 k Concentrations of Strontium-89 and-90 and Gamma Emitters in Beef, Game, and Thyroid Samples Direct Radiation Measurements Monthly(December) and Quarterly Typical MDL 1s for Ganrna Spectrometry 27 PAGE 28 29 30 31 32 33 34
TABLE C-1 CONCENTRATIONS OF ALPHA AND BETA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma SAMPLE*
PERIOD NUCLIDE SA-AP-2Sl SA-AP-5Sl SA-AP-5Dl SA-AP-lODl SA-AP-16El SA-AP-lFl SA-AP-2F2 SA-AP-3H3 12-06-76 Alpha 0.8+/-0.5
- 1. 7+/-0. 7 to 12-13-76 Beta 53+/-7 75+/-9 71+/-8 61+/-6 64+/-7 64+/-7 81+/-6 79+/-8 12-13-76 Alpha 2.4+/-0~9 3.0+/-0.9 to 12-20-76 Beta 62+/-8 55+/-7 64+/-8 58+/-8 65+/-9 67+/-7 111+/-14 60+/-8 12-20-76 Alpha 1.2+/-0.8 1.1+/-0.8 to 12-27-76 Beta 35+/-7 39+/-6 42+/-6 43+/-6 38+/-6 46+/-6 99+/-13 53+/-7 12-27-76 Alpha 9.8+/-3.l 13+/-4 to 1-03-77 Beta 29+/-6 48+/-7 44+/-6 52+/-6 42+/-6.
42+/-7 40+/-7 50+/-7 N
AVERAGE Beta 45+/-31 54+/-31 55+/-29 54+/-16 52+/-28 55+/-25 83+/-62 60+/-26 00 Sampling period may differ by 1 day.
~----------------------------
~
............ ------------------------------~-
r.:i l..O SAMPLE
. PERIOD SA-AI-2Sl 12-07"'.' 76 to
<3.8
- . 12-13..;76 12.-13-76 to
<2.6 12-20-76 12-20-76 to
<3.6 12-25-76 12-28-76 to
<3.6 1-03-77 TABLE C-2 CONCENTRATIONS OF IODINE-131 IN FILTERED AIR Results in Units ~f 10-3 pCi/m3 STATION NO.
SA-AI-5Sl SA-AI-lODl SA-AI-16El
<5.2
<2.5
<3.8
<2.7
<2.8
<5.7
<3.0
<2.5
<3.1
<3.1
<2.2
<2.7 Low flow rate resulted in high MDL.
SA-AI-2F2 SA-AI-3H3
<62*
<4.5
<4.9
<5.1
<4.4
<2.9
<3.4 64+/-3. 7
w 0
TABLE C-3 CONCENTRATIONS OF ALPHA, BETA, TRITIUM, STRONTIUM-89 AND-90, POTASSIUM-40, AND GAMMA EMITTERS IN PRECIPITATION, WELL WATER, AND POTABLE WATER Results in Units of pCi/l +/- 2 sigma MEDIUM AND STATION NO.
Precipitation SA-RW-2F2 Well Water SA-WW-4S2 SA-WW-501 SA-WW-3El Potable Water SA-PWR-2F3 SA-PWT-2F3 SAMPLING PERIOD 12-07-76 to 1-03-77 12-13-76 12-13-76 12-13-76 12-01-76 to 12-31-76 12-01-76 to 12-31-76 ALPHA BETA H-3
<1. 5 13+/-4 197+/-80
<1.5
<3.0 174+/-72
<1. 5 5.1+/-2.5
<80
<1.5 9.1+/-2. 8 236+/-72
<1.5
<3.4 372+/-75
<1.8
<3.3 192+/-73 K-40 analyzed by atomic absorption spectroscopy.
Insufficient volume to perform analysis.
Sr-89
<0.6
<0.4 1.4+/-0.4 0.9+/-0.4 1.2+/-0.3 Sr-90 K-40*
0.9+/-0.3 2.8+/-0.3
<0.4 3.3+/-0.3
<0.5 8.9+/-0.9 0.4+/-0.3 1.3+/-0.1
<0.4
- 1. 3+/-0.1 Ra-226
<30
- 1. 9+/-1. 2
<1.0 2.2+/-1.3
<0.9
<0.9
w I-'
TABLE C-4 CONCENTRATIONS OF STRONTIUM-89 AND-90, I-131 AND GAMMA EMITTERS IN MILK STATION NO.
SAMPLING
. START DATE SA-M-2Fl 12-19-76 SA-M-14Fl 12-19-76 SA-M-15Fl 12-19-76 SA-M-5F2 12-19-76.
SA-M-3Gl 12-19-76 Results in Units of pCi/l +/- 2 sigma SAMPLING STOP DATE 12-20-76 12-20-76 12-20-76 12-20.;. 76 12-20-76 Sr-89
<0.6
<1.4
<2.5
<O. 7
<0.9 Sr-90
- 1. 0+/-0. 3 0.7+/-0.6
<1.6
- o. 5+/-0. 3
- 0. 07+/-0. 04 1300+/-130
<O. 04 1600+/-160 0.15+/-0.05 1500+/-150
<0.03 1600+/-160
- 0. 20+/-0. 05 1600+/-150
w N
TABLE C-5 CONCENTRATIONS OF STRONTIUM-89 AND-90 AND GAMMA EMITTERS IN BEEF, GAME AND THYROID SAMPLES STATION NO.
SA-FPB-3El SA-GM-1101 SA-GM-3El SA-GM-3El SA-GM-5Fl SA-THB-3El SA-THD-3El SA-THD-5Fl SAMPLING DATE 12-16-76 12-13-76 12-12-76 12-15-76 12-15-76 12-15-76 12-16-,76 12-15-76 Results in Units of pCi/g (wet) +/- 2 sigma Sr-89*
Sr-90*
K-40 ZrNb-95 I-131 Cs-137 2.8+/-0.3
<0.01
<0.01 0.01+/-0.01
<0.01
<0.01 2.6+/-0.3 0.01+/-0.01
<0.01
<0. 01 0.16+/-0.03 0.08+/-0.02 2.4+/-0.2 0.03+/-0.01
<0.01
<0.01 3.5+/-0.4
<0.01
<0.01
- 0. 02+/-0. 01 3.8+/-0.4
<0.01
<0.01
- 0. 5+/-0.1
- 2. 4+/-1.1
<0.1 0.07+/-0.04
<0.1
<4.0
<0.3 3.8+/-0.4
<O. 3 3.6+/-0.4
<0.2 11+/-1
<0.3 Sr-analyses on skelatal portions of muskrat samples only.
Units in pCi/kg (dry).
Ra-226 0.01+/-0.01 0.02+/-0.01
- 0. 01+/-0. 01
<0.01 0.03+/-0.01
<0.1
<0.7
<0.5
TABLE C-6 DIRECT RADIATION MEASUREMENTS - MONTHLY (DECEMBER) AND QUARTERLY Results in Units of mrem/standard month*
DECEMBER QUARTERLY STATION NO.
11-29-76 to 12-27-76 9-28-76 to 12-27-76 SA-ID-2Sl 5.16+/-0.35 4.82+/-0.33 SA-ID-5Sl 4.86+/-0.16 4.84+/-3.68 SA-ID-6Sl 5.76+/-0.37 4.90+/-0.13 SA-ID-7Sl 6.15+/-0.79 5.47+/-0.23 SA-ID-lOSl 5.80+/-0.32
- 4. 96+/-0. 28 SA-ID-llSl 4.74+/-0.32 4.11+/-0.46 SA-I D-501 5.39+/-0.36 4.33+/-0.34 SA-ID-lODl
- 6. 73+/-0.28 5.63+/-0.07 SA-I D-14Dl 6.22+/-0.52 5.29+/-0.29 SA-I D-2El 5.74+/-0.97 5.23+/-0.65 SA-ID-3El 5.71+/-0.37 5.36+/-0.42 SA-ID-13El 5.94+/-0.47 5.17+/-0.31 SA-ID-16El 6.14+/-0. 77 5.17+/-0.41 SA-ID-lFl 5.82+/-0.50 5.11+/-0.41 SA-ID-2F2 4.82+/-0.29 4.27+/-0.31 SA-ID-5Fl 5.84+/-0.22 4.68+/-0.27 SA-ID-6Fl 5.08+/-0.37 4.48+/-0.23 SA-ID-7F2 4.58+/-0.37 3.84+/-0.12 SA-ID-llFl 6.72+/-0.53 6.07+/-1.12 SA-ID-13Fl 5.85+/-0.41 5.18+/-0. 55 SA-ID-3Gl 6.30+/-0.80 5.42+/-0.60
-I SA-ID-2Hl 5.79+/-0.22 5.65+/-0.37 SA-ID-3Hl 6.30+/-0.33 6.02+/-1.30 SA-ID-3H3 6.24+/-0.30 5.67+/-0.73 AVERAGE
- 5. 74+/-1. 20
- 5. 07+/-1.15 Standard month = 30.4 days.
33
NUCLIDE Na-22 K-40 Cr-51 Mn-54 Co-58 Fe-59 Co-60 Zn-65 ZrNb-95 Mo-99 Cu RuRh-106 Ag-110m Te-129m I-131 Te-132 I-133 Cs-134 Cs-136 Cs-137 BaLa-140 Ce-144 Ra-226 Th-232 PRECIPITATION
( p Ci I 1 )
9 200 100 20 20 40 20 40 20 100 80 20 300 10 10 20 20 20 20 20 100 30 60 TABLE C-7 TYPICAL MDL'S FOR GAMMA SPECTROMETRY WELL/POTABLE WATER (pCi/l) 0.2 7
3 0.5 0.5 1
0.6 1
0.4 4
2 0.4 7.
0.4 0.3 0.5 0.5 0.7 0.5 0.6 3
0.9 2
MILK (pCi/l) 0.8 10 2
2 4
2 5
2 10 7
2 30 2
1 2
2 3
2 2
10 4
6 BEEF (pCi/kg) 10 20 3
3 7
4 8
3 20 10 3
' 40
- 2.
2 2
3 4
3 10 10 GAME (pCi/kg) 20 20 4
4 10 6
10 4
30 20 4
60 3
3 4
4 6
4 4
20 7
10 THYROID (pCi/kg) 20 200 40 40 80 40 80 30 300 200 20 500 20 40 40 50 40 50 200 70 100