ML20078A531
| ML20078A531 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 06/30/1994 |
| From: | LONG ISLAND POWER AUTHORITY |
| To: | |
| Shared Package | |
| ML20078A520 | List: |
| References | |
| NUDOCS 9501250033 | |
| Download: ML20078A531 (100) | |
Text
7 O
SHOREHAM NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i
i ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT i
January 1,1994 to June 30,1994 i
i ISSUED BY RADIOLOGICAL CONTROLS DIVISION - LIPA ENVIRONMENTAL ENGINEERING DEPARTMENT - LILCO i
TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES 9501250033 950120 PDR ADOCK 05000322 R PDR
j TABLE OF CONTENTS l
- l
- PAGE l
. EXECUTIVE
SUMMARY
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 4
I. TH E PROG RAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 j A Obj e ctive s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 l
a m m* n *ren........................................ 6 ,
i 1
- 1. Aquatic Environment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 .
I l l 2. Atmospheric Environment . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 2
- 3. Terrestrial Environment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 l 4. Direct Radiation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 i
- C Q uality Assurance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 1
] D. Data intop sidan . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 j 1. G e n eral . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 1
1 3 i*
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- 2. Gamma lant@ Analyses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 4
i E. Dose As ses sment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 i
- F. Program Su mm ary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 )
i :
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l 3 11. RESULTS AND DISCUSSION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 1
l A Aquatic Environment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 4
l 1. Surface Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 1
l 2. Fi sh . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 1
1 i
- 3. Invertebrate s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 1
1
- 4. Se d im e nt . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 4
j R Atmospheric Environment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 1
^
- 1. Airborne Particulates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 4
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TABLE OF CONTENTS (cont.)
C Direct Radiation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 D. Dose Assessment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 III. CO N C LU SI ON S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 3 N. RE FERE N C ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 5 APPENDIX A - Radiological Environmental Monitoring Program Summary - 1994 . . . . . . . . . . . . . . . . . . . . 2 8 APPENDIX B - Sample Designation and Sampling Locations .... 34 I APPENDIX C - Data Tables . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 2 i
APPENDIX D - Analytical Procedures Synopsis . . . . . . . . . . . . . . . . 54 APPENDIX E - Summary of EPA Interlaboratory Compadsons ... 61 i APPENDIX F - REMP Sampling and Analytical Exceptions . . . . . . 88 APPENDIX G - SNPS Land Use Surveys . . . . . . . . . . . . . . . . . . . . . . 90 l APPENDIX H - Common and Scientific Names of Species Collected in the Radiological Environmental '
M onitoring Program . . . . . . . . . . . . . . . . . . . . . . . . . 9 2 l
O
LIST OF TABLES
]EL TITLE PAGE
- 1. Synopsis of the Shoreham Nuclear Power Station's l Radiological Environmental Monitoring Program for the Period January 1 through June 30, 1994 . . . . . . . . . . . . . . . . . . . . . . . . 1 2 1
l 1
Annendir A - Radiological Environmental Monitorina Prostram Summary 1994 A-1 SNPS REMP Summary Jan. I to Jun. 30, 1994 . . . . . . . . . . . . . . . . . . . 2 9 Annendir B Ramnle Deslanation and EmmnHas Locations B-1 Sample Locations Required by SNPS Offsite Dose Calculation Manual . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 6 B-2 Airborne Particulate Monitoring Stations . . . . . . . . . . . . . . . . . . . . . . . . 3 7 B-3 Waterborne Monitoring Stations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 7 B-4 Ingestion Monitoring Stations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 7 B-5 Direct Radiation Monitoring Stations . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 8 Appendir C - Data Tables Aquatic Environment i C-1 Concentrations of Tritium and Gamma Emitters
- in Surface Water Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 3 l
j C-2 Concentrations of Gamma Emitters in Fish Samples . . . . . . . . . . . . . . 44 j C-3 Concentrations of Gamma Emitters in Invertebrate Samples . . . . . . . 45 i
C-4 Concentrations of Gamma Emitters in Sediment Samples . . . . . . . . . 46 a
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IJST OF TABLES (cont.)
lEh TITLE PAGE Atmospheric Environment C-5 Concentrations of Gross Beta Emitters in Weekly Airborne Particulate Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 7 C-6 Concentrations of Gamma Emitters in Quarterly Composites of Airborne Particulate Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 9 Dimet Radiation C-7 Direct Radiation Measurements - Quarterly TLD Results. . . . . . . . . . 50 Lower Limits of Detection C-8 Typical LLDs Achieved for Gamma Spectrometry. . . . . . . . . . . . . . . . . 51 O C-9 LLDs and Reporting Action Levels Required by Offsite Dose Calculation Manual and 1994 Contract . . . . . . . . . . . . . . . . . . . . . 52 Appendix F REMP Sampling and Analytical Exceptions F-1 REMP Exceptions for Scheduled Fish Sampling and Analysis During 1994 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 9 tv !
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i.
I UST OF TABIES (coat.)
M TITLE PAGE j Appendix G i
i Appendix G SNPS Land Use Survers 90 i
i a
- Appendir H
) H-1 Common and Scientific Names of Species Collected i in th e REM P . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 93 i
j
{ UST OF FIGURES 1
i TITLE 1
l 1. Average Weekly Gross Beta Results in Airborne Particulates . . . . . . . 18 i
i 2. Comparison of Average Monthly Gross Beta Results in Airborne j Particulates (February 1977 - June 1994) . . . . . . . . . . . . . . . . . . . . . . 19
- 3. Comparison of Average TLD Results (February 1977 -
j J un e 19 9 4 ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1 4
J 1
i UST OF MAPS
! Appendix B - Sample Designation and Sampling Locations B-1 Shoreham Site Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 9 1
j B-2 On Site Sampling Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 0
! B-3 Off Site Sampling Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 i
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EXECUTIVE
SUMMARY
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l I EXECUTIVE
SUMMARY
In the long Island Power Authority (LIPA) letter to the NRC (LSNRC-2115), submitted November 4,1993, the LIPA requested an amendment to i Possession Only License No. NPF-82 for the Shoreham Nuclear Power l Station. The proposed amendment would eliminate all Technical l Specifications requirements as well as the requirements of the Non-l Radiological Environmental Protection Plan. The Radiological l
Environmental Monitoring Program was covered by the Technical 1 Specifications and hence would be terminated upon License Amendment by l the NRC. NRC Regulatory Guide 4.1, Proarnma For Monitorina Radioactivity j In The Environs of Nuclear Power Plants, indicates that if a facility can j demonstrate that either a particular set of isotopes and/or pathways no
- longer exist, or that even if they do exist, there is no measurable radiological j impact to the public, then these isotopes / pathways need not be sampled.
i To support the license amendment request and meet the
- requirements of Regulatory Guide 4.1 an analysis was prepared to estimate
{ the total available site source term after fuel disposal and bioshield wall
! decommissioning activities were completed. The estimate yielded an initial i value of less than 8 millicuries (which would be constantly decreasing during i the residual decommissioning activities). By the time License Amendment 11 to NPF-82 was approved and ready to be implemented, the site inventory
- had been further reduced to less than 1 millicurie.
The s retr ev i= tie = =v rue nac orrice or *=cie r teri i s retr lO And Safeguards Related to Amendment No.11 to Facility License No. NPF-82 Shoreham Nuclear Power Station Unit 1 (SNPS) Docket No. 50-322 states " ....the basis for finding the licensee's proposed changes are acceptable are: 1) all irradiated fuel will be removed and shipped off site: 2)
! all contaminated or activated systems will be decontaminated or dismantled i and removed, except for the structures and systems associated with the l SFSP Spent Fuel Storage Pool: 3) the radioactive material inventory other
) than sealed sources will be less than 8 millicuries: and 4) all remaining
! accident scenarios are bounded by accidents previously analyzed in the
- approved Defueled Safety Analysis Report (DSAR) and the approved
! Decommissioning Plan (DP)." <
! "This proposed amendment deletes from the Possession-Only IJcense l (POL) the requirements associated with the safe storage and handling of 3 irradiated fuel, the accompanying Appendix A ot SNPS Technical i Specifications, and Appendix B of SNPS Environmental Protection Plan i (non-radiological). This proposed amendment updates the SNPS POL to i reflect the status of the facility after irradiated fuel is removed from the site."
i "The amendment meets the eligibility criteria for categorical exclusior.
! set forth in 10 CFR 51.22(c) (9), and 10 CFR 51.22(c) (10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental i
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! assessment need be prepared in connection.with the issuance of this
' n amendment."
lV "In accordance with the NRC's regulations, the New York Official was notified of the proposed issuance of the amendment. The State Official had no comments on the proposed amendment."
- "Ihe NRC has concluded, based on the considerations above, that
- (1) {'
because the license amendment did not involve an increase in the i probability or consequences of accidents previously evaluated, or create the j possibility of a new or different kind of accident from any accident j previously evaluated, and does not involve a significant hazard and safety of i the public will not be endangered by operation in the proposed manner: (3) 2 such activities will be conducted in compliance with the NRC's regulations; and (4) the issuance of the amendment will not be inimical to the common j
- defense and security, or to the health and safety of the public."
t i Therefore, the Shoreham REMP has been terminated as of June 7, 1994 and this will be the final and last REMP report.
his last report summarizes the Shoreham Nuclear Power Station's
- (SNPS) Radiological Environmental Monitoring Program (REMP) final
! operations during the first half of 1994.
O The ob;ective of the SNeS REMe was to moniter the radiation ievei and the radioactivity concentrations in the plant offsite environs, and to ;
identify and measure those that were attributable to the operations and '
i, acuvities of the plant. If such plant-derived radiation level or radioactivity
! concentrations was found, then verification of the projections of amount of releases and resultant doses to the surrounding population, as made by models and methods contained in the plant's Offsite Dose Calculation Manual (ODCM), were reasonable, would have been done, i
i During the final, decommissioning phase of the plant, as well as in the i earlier operational phase, REMP did use the preoperational baseline data to j identify plant contributed radiation or radioactivities, and evaluated the !
effects of plant radioactive effluents, when detected, on the environment.
l The SNPS REMP was designed to comply with the plant's Technical l Specifications, ODCM and NRC Regulatory Guides as described in licensing i basis documents.
! The REMP data was acquired by sampling various media in the i environment which were then analyzed for radiation levels and/or radioactivity concentrations present. Media sampled within the aquatic environment in 1994 included surface water, fish, invertebrates (whelk, 4 lobsters, etc.) and sediment. The atmospheric environment was sampled iO i
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for airborne particulates until June. Direct radiation in the environment was O measured using TLDs.
Radioactivity in environmental media varies from sample to sample as well as geographically; therefore, a number of sam?l ing locations for each medium were selected using available meteorologican, land and water usage data. Sampling locations were designated as either indicator or control locations. The indicator locations were placed close enou,gh to Shoreham so that plant contributed radiation and radioactivity would M at their highest levels. The control sample locations were placed so that they would be beyond measurable influence of Shoreham and any other nuclear facillues.
An exception to this occurred at the onshore site for REMP location 13G2, at the entrance to Port Jefferson Harbor. During preoperational testing, aquatic samples revealed the presence of low levels of iodine-131. An investigation revealed that the iodine-131 was from area hospitals treating patients for thyroid carcinoma. Thereafter, until 1990 a second onshore aquatic background location was sampled at the entrance to Mt. Sinal Harbor.
A number of radioactivity analyses were performed on'each medium sampled. Not all samples underwent all types of radioanalyses; only those analyses appropriate lor the particular medium sampled were performed.
The analyses included gamma spectrometry, tritium concentration, gross beta and direct gamma radiation.
O In 1994, as the physical decommissioning effort at Shoreham reached completion under the Possession Only License (POL), REMP requirements contained in the Technical Specification were deleted (due to extremely limited site source term, less than 8 millicuries and decreasing) and the REMP was terminated.
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4 I. THE PROGRAM 4
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THE PROGRAM O The Shoreham Nuclear Power Station's (SNPS) Radiological Environmental Monitoring Program (REMP) was conducted in compliance with NRC Regulatory Guide 4.15, SNPS Technical Specification Section 6.7.4.b, and SNPS Offsite Dose Calculation Manual (ODCM) Section 3/4.12.
The REMP was developed in general accordance with the NRC Radiological Assessment Branch Technical Position (BTP), Rev.1, Nov. 1979, and findings in the Environmental Report (ER) Section 6.1.5. All samples were collected by personnel of the Long Island lighting Company (Environmental Engineering Department) or contractors hired for the collection of aquatic samples. A synopsis of the sampling program can be found in Table 1. Maps and a description of sampling locations appear in Appendix B.
During 1994 sample analyses were performed by Teledyne Browm Engineering of Westwood, New Jersey (referred to throughout the text as "the laboratory"), under contract to LIPA. A summary of analytical results appears in Appendix A and individual analysis results in Appendix C. Aquatic sample collections were performed by LILCO's Environmental Engineering Department and Energy & Environmental Analysts Inc. (EEA Inc.) under contract to LIPA.
A. Objectives O were:
The objectives of the radiological environmental monitoring program
- 1. Identify and measure plant generated radiation and radioactivity in the plant environs, and calculate associated potential doses to the surrounding population.
- 2. Verify the effectiveness of in plant measures used for controlling the release of radioactive materials.
- 3. Provide reasonable assurance that the predicted doses, based on effluent data and ODCM methodologies, have not been substantially underestimated and are consistent with applicable standards.
- 4. Comply with regulatory requirements and allowable limits, SNPS Technical Specifications and ODCM requirements, and provide records to document compliance.
- 5. Verification of negligible radiological impact throughout Shoreham's operational history.
B. Sample Collection O 1. ^9 tic z=vire me=t 6
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The a= tic ==vire==e=1 t the snes ite - ex mi ea dv analyzing samples of surface water, fish, invertebrates, and sediment.
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l Surface water samples were taken at three locations, including 13G2 -
i at the entrance to Port Je17erson Harbor, in May using a Niskin bottle.
! The samples were placed in new polyethylene bottles following three i rinses with the sample medium prior to collection. Samples of Winter Flounder (Pseudooleuronectes americanus), Windowpane (Scophthalmus aquosus), Sea Robin (Prionotus ggL), and Ilttle Skate 4 (Baia erinaceal were taken by trawl, sealed in plastic bags, frozen, and ,
j shipped to the laboratory for analysis. l Invertebrate samples of American Lobster 'lH o m a r u s americanus), and Channeled Whelk fBusvcon canaliculatal were col- ,
, lected by trawl. Channeled Whelk were also collected using pots. l i These invertebrate samples were sealed in plastic bags, frozen and 1 l shipped to the laboratory for analysis.
A beach sediment sample was also collected, sealed in plastic i bags, frozen and shipped to the laboratory.
I l 2. Atmospheric Environment l The atmospheric environment was examined by analyzing l airborne particulates collected on Gelman Type A/E filters using low l volume air samplers (approximately I cfm). The samplers used were 1 equipped with a vacuum recorder for sample volume correction to l ensure sample validity and to indicate any maintenance problems.
i When the sampler lost vacuum due to a leak, the vacuum level reading
! dropped to zero. Since this may occur without a corresponding loss of l electric supply the exact time of the maintenance problem was j evident on the vacuum recorder chart.
! Sample volumes were measured using dry gas meters and ,
l corrected for differences between the actual pressure seen by the i volume meter and the average atmospheric pressure. Sample volumes were corrected to standard pressure using average weekly barometric pressure (measured at LILCO's Environmental Engineering I
- Department, Melville) and air sampler vacuum readings. Time
- totalizers indicate the duration of time the sample was taken. .
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- 3. Terrestrial Environment ;
3 Due to the termination of routine REMP on June 7,1994, when 1 Ammendment 11 indicated that there was no further need for REMP j monitoring, the terrestrial environment was not sampled.
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- 4. Direct Radiation Direct radiation levels in the environs were measured with
- energy compensated calcium sulfate (CaSO4:Dy) TLDs, each containing four separate readout areas. The TLDs were annealed by LILCO prior ,
to placement in the field. After the quarterly collection, the TLDs !
were packaged and shipped to the laboratory for analysis along with a control dosimeter.
C Ouality Assurance Teledyne Isotopes has an extensive quality assurance program designed to ensure the precision and accuracy of the data generated.
An Interlaboratory Comparison Program is conducted with the Environmental Protection Agency (EPA). 'Ihe results of the Progrem
. analyses are listed in Appendix E. Participation in this program permits estimation of bias in the laboratory results from the deviation from the "known" value given, or by comparison with means of all participants. The laboratory's Quality Assurance Program for Radiological Monitoring is described in various publications (References 15, 16, 17).
Approximately 10 percent of the laboratory's total analytical effort is spent on quality control including process quality control, instrument quality control, intra- and inter-laboratory cross check, O and comprehensive data review. In addition, LIPA specifically required that two percent of its analyses be duplicated for further quality control cross check.
Additional information on the LIPA Quality Assurance Program is provided in LIPA NED 417004, Quality Assurance Program for Radio-logical Environmental Monitoring Program. Shoreham Nuclear Power Station.
D. Data Interoretation
- 1. General i
The analytical data generated during 1994 were routinely evaluated by the laboratory's project leader who served as liaison with Long Island Lighting Company's Environmental Engineering .
Department and LIPA's Nuclear Engineering Division. Several factors l nre important in the interpretation of the data. These factors are i discussed here to avoid repetition in sections that follow.
Within the data tables (Appendix C) an approximate 95 percent (12 sigma) confidence interval is supplied for those data points above the lower limit of detection (LLD). These intervals represent the range of values into which 95 percent of repeated analyses of the same l
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] sample would fall. Tables C-9 and C-10 present typical and required .
j 11Ds, respectively. l t
l Results for each type of sample were grouped according to the j analysis Arformed. Means and standard deviations of these results j are calcu:ated when applicable. The calculated standard deviations of grouped data represent sample rather than analytical variability. For these calculations any values below 11D are considered to be at the j LLD. As a result, the means are biased high and the standard j deviations are biased low. When a group of data is completely t i composed of LID values, averages are not calculated. j i
I Grab sampling is a useful and acceptable procedure for taking 1 j environmental samples of a medium in which the concentration of i radionuclides is expected to vary minimally with time or where
!' intermittent sampling is deemed sufficient to establish the -
radiological characteristics of the medium. 'Ihis method, however, is i only representative of the sampled medium for that specific location and instant of time. As a result, variation of radionuclide i concentrations in the samples will normally occur. Since these !
variations will tend to counterbalance one another, the es; traction of l
j averages based upon repetitive grab samples is valid. i i
- 2. Gamma Isotopic Analyses l
) SNPS ODCM Table 3.12.1-1 requires that analyses be performed .
j on all media for gamma emitting radionuclides which may be !
attributable to effluents from the plant. These analyses include i specific gamma emitters such as I-131, Cs-134. Cs-137 Ba-140, Mn-l 54, Fe-59, Co-58, Co-60, Zn-65, Zr-95 and Nb-95. Industry i experience suggests that these are the most likely radionuclides to i find their way into the environment from a BWR nuclear power plant.
Gamma spectroscopy is expected to identify most other nuclides which may be discharged when the LLDs for specified gamma emitters
! are met by this technique.
3 Tables 3.1 and 3.2 of the Shoreham Final Environmental Statement list the calculated liquid and gaseous effluents by j radionuclide in curies per year. These release rates assume normal j operation of the plant, including anticipated operational occurrences.
4 Those nuclides listed in Tables 3.1 and 3.2 which are not routinely j observable by gamma spectroscopy and which are not specifically-j analyzed in other ways fall into two categcdes:
1
! 1. Those radionuclides with half-lives on the order of hours or i minutes which cannot accumulate appreciably in the
! environment (Na-24, Cu-64, Zn-69m, Zn-69, Sr-91, Y-91m Y-j 92, Y-93, Tc-99m. Rh-103m, Rh-105, Rh-106 Te-129, Te-1 9
l- _ _ _ _ _ _ _ _ __ , , _ _ ,
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1 131m, Te-131,1-132,1-135. Ba-137m,' Pr-143 Cc-143, Pr-iO s
244 aa w-187).
- 2. Those radionuclides with no gammas (P-32, Fe-55), those j with a trivial percentage of their transitions going by gamma
- emissions (Y-91), or those with their primary gamma occurring at such a low energy and at such low abundance that
] it is not routinely observable in the presence of other gamma j activity (Nd-147). With only 10 pCi of Nd-147 calculated to be i released per year in Shoreham's liquid effluents in the j operational mode, the nuclide cannot be an important '
y contributor to dose.
E. Dose Assessment s '
j The methodology for determining doses is similar for all '
i pathways. Laboratory analyses from the REMP for each sample type l were compiled. Data from all locations taken on the same date were j averaged to obtain the most reliable approximation of the radioactivity concentration on that date for that sample type. The averages of all l dates are then taken to provide the best approximation of radioactivity j concentratit as for the year. ;
When an average value was obtained which represented a sample j medium or an exposure pathway, it was then used to calculate the i dose for the year. Additional information, such as the quantity of fish,
! vegetables, etc., consumed per year by the maximum exposed j individual is also needed to calculate the total dose (Reference 13).
I
! The dose due to direct radiation exposure was monitored by l TLDs. The laboratory results for TLDs were expressed in dose units
- directly and do not require any additional calculations.
4 The dose to the total body or to a specific organ was then calculated by the product of the radionuclide specific dose conversion j factor for its applicable exposure pathway, the environmental sample
- radionuclide concentration, and the ingestion or inhalation rate of the
! sample or medium of interest. For example, the following general l
! equation expresses this principle:
I
- Dose = Concentration X Quantity ingested X Dose factor (mrem /yr) per sample per year 4 l .
i The sample concentration is typically expressed in pCi/l or j- pCi/kg. For the ingestion pathway, the quantity ingested or consumed i per year is expressed in kg/ year or 1/ year. Finally, the dose conversion j factor is expressed in terms of mrem /pCi ingested or inhaled.
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1 F. Program Summary
' Tible 1 summarizes information on the REMP as performed during the period of this report, January 1 through June 30, 1994.
During this reporting period 190 separate analyses were performed on 176 environmental samples.
Appendix A stimmarizes the analytical results obtained from the SNPS REMP. The format used is that recommended in NRC Radiological Assessment Branch Technical Position (BTP), Rev.1 Nov. '
1979. Appendix B describes the sample coding system, which specifies sample type and relative locations at a glance. In addition, pertinent information on individual sampling locations, and maps which show their geographic location, are included.
Appendix C presents th:: analytical results -of the Shoreham Nuclear Power Station's Radiological Environmental Monitoring Program for the period January 1 through June 30,1994. Appendix D contains a synopsis of the analytical procedures used in the REMP.
Results of the EPA interlaboratory comparison program can be found in Appendix E. Appendix F lists the program exceptions for 1994. The REMP Land Use Census was not conducted in 1994 <'oe to Rev. I to the SNPS Offsite Dose Calculation Manual (ODCM) (Decu;nent O Change Nnhe No. 93X024) which revised the annual land use census requirement to every two years. Common and scientific names of species collected in the program are presented in Appendix H.
O 11
d [
v )
TABLE 1 SYNOPSIS OF Tile Silotti?lls M Nttri.EAll POWEli STATION'S IIAl)lOlI)GICAl, ENVIRONMENTAL MONITORING PitOGit/ M 1011 Tile PElttut) .lANilAltY I T11f1011Gl! .lilNI? 30.1994 SAMPl.E SAMPlJNG NtJMi1Elt ANALYSIS NUMBER TYPE FREQUENCY LOCATIONS ColJJr1EI) ANALYSIS FREQUENCY PERfT)RMED l
AqLeath; Eavtrotunegat Surface Water Semlannual 3 4 11-3 Semlannual 4 Gamma Semlannual 4 Fish Semlannual 3 14 Gamma Semlannual I4 Invertebrates Semlannual 3 6 Gamma Semlannual 6 Sediment - Beach Semlannual I I Gamma Semlannual i M
Atanssebeste Enytresuuseat Altborne Particulates Weekly 5 120 Gmes Beta Weekly 120 Gamma Quarterly 10 Direct Itseatten TLD Quartedy 18 36 Gamma Dose Quarterly 36
et e
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1 E METS AND DISCUSSION i
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13
i i
. RESULTS AND DISCUSSION l The analytical results for the reporting period of January 1 through j June 30, 1994, have been divided into three categories: aquatic,
! atmospheric, and direct radiation. The individual samples and analyses
! within each category display the unique radiological characteristics of that l type of environment. Analytical results of the REMP are summarized in
! Appendix A. The data for individual analyses are presented in Appendix C.
A. Aquatic Et,ironment The aquatic environment in the vicinity of SNPS consists primarily of l Long Island Sound. The radiological characteristics were studied by analyzing samples of surface water, winter flounder, windowpane, sea robin, !
little skate, lobster, channeled whelk, and sediment. The samples were l collected by LILCO's Environmental Engineering Department and Energy &
Environmental Analysts Inc. (EEA Inc.) under contract to LIPA.
l
- 1. Surface Water (Table C-1) )
Semiannual surface water samples were taken at three locations and ;
analyzed for tritium. Gamma spectroscopy was also performed on all :
samples. l There was no detectable tritium in any surface water sample. This compares consistently with the 1993 tritium results, which were also all below the detection limit.
Naturally occurring potassium-40 was measured in all four semiannual ,
samples over three locations with an average of 241 pCi/l and a range :
l between 182 to 317 pCi/1, as compa'ed with 1993's average of 231 pCi/l and a range between 88.9 and 277 pCi/1. No other gamma activity above the detectable levels was measured in the four surface water indicator location samples as analyzed by gamma spectroscopy.
- 2. Fish (Table C-2)
Fourteen fish samples were collected at three locations and the edible portions analyzed for gamma emitters. Gamma spectrometry showed potassium-40 present in all samples with an average concentration of 3408 pCi/kg wet and a range between 2020 to 5860 pCi/kg wet, comparing with 1993's average of 3250 pCi/kg wet and a range between 1830 and 5390 pCi/kg wet. Cesium-137 was not detected in any samples during 1994.
This compares well with 1991 and 1990 when cesium-137 was detected in three fish samples.
o - 1 14
- 3. Invertebrates (Table C-3)
Six invertebrate samples, comprised of lobsters and whelk, were collected at three locations and analyzed for gamma emitters. Gamma spectrometry showed detectable levels of potassium-40 in all samples, ranging from 2330 to 3060 pC1/kg wet with an average activity of 2623 pCi/kg wet. These compare well to 1993's average potassium-40 activity of i 2805 pCi/kg wet and a range between 1640 and 3510 pCi/kg wet. :
horium-228 was not detected during 1994 and this compares favorably with the one measurement of thorium of 117 pCi/kg wet in a lobster sample in 1991. No cesium-137 activity was detected in 1994 samples, versus an l average of 33.8 pC1/kg wet out of two 1990 lobster samples.
- 4. Sediment Rable C-4)
One beach sediment sample was collected and analyzed for gamma ;
emitters. ne sample had a measurable activity of naturally occurring '
potassium-40 of 1760 pCi/kg dry. This is lower than the average concentration of potassium-40 of 2580 pCi/kg dry with a range of 2490 to 2670 pC1/kg dry measured in 1993. Thorium-228 was measured with an activity of 174 pCi/kg dry. His is higher than the average thorium i concentration of 95.0 pC1/kg dry with a range of 77.0 to 113 pCi/kg dry I measured during 1993. All other gamma emitters were below the lower ;
limits of detection. l l
B Atmosoheric Environment l The atmospheric environment in the vicinity of the SNPS was examined by analyzing samples of airborne particulates at five sampling locations. Airborne particulate filters were collected weekly until June 7, 1994 and analyzed for beta emitters. Quarterly composites from each station were analyzed for gamma emitters.
- 1. Airborne Particulates (Tables C-5 and C-6)
Beta-emitter concentrations ranged from 0.008 to 0.031 pCi/m3 with an annual average for the five sampling locations of 0.018 pCi/m3 Eable C-5). Of the 120 measurements none were below the gross beta detection limit, nominally 0.008 pCi/m3 Figure 1 shows the average weekly gross beta fluctuations in airborne particulates from all stations for 1994. Figure 2 represents the average monthly gross beta results in airborne paruculates from January 1,1977 through June 7,1994. ;
Results of gamma spectrometry (Table C-6) showed detectable levels of naturally occurring beryllium-7 in all ten samples. The average bery111um-7 activity in the quarterly analyses was 0.097-pCi/m3 with a range of 0.073 to 0.129 pCi/m3. Naturally occurring potassium-40 was observed in five samples with an average concentration of 0.012 pC1/m3 and a range 15
i l
1
- of 0.008 to 0.023 pCi/m3. Cesium-137 was not measured during 1994. All l other gamma emitters were below the lower limit of detection.
l I
C Direct Radiation frable C-7)
! Direct radiation measurements were taken quarterly at 18 locations during the first and second quarters of 1994, using CaSO4 :Dy thermoluminescent dosimeters CILDs). TLDs were used to detect radiation levels near ground level in the vicinity of the Shoreham site due to terrestrial and cosmic gamma ray emitters and possible SNPS contributed
! direct radiation. Figure 3 presents a comparison of average TLD results
/ from 1977 to 1994.
t l All TLD results presented in this repon have been normalized to
{
a standard month (30.4 days) to eliminate the apparent differences caused l by the variations in exposure period. The average of the quarterly I exposures of all 18 locations was 3.2 mR/ standard month which is the same
! as the average quarterly exposure of the 2 indicator locations only. This is j less than quanerly values 4.1 and 4.3 mR/ standard month, respectively, j measured during the preoperational years 1983 and 1984.
t l
Annual average results of all quarters at the same locations, as
! well as of all locations for each quarter, are given in Table C-7 with 95%
l confidence limits for the mean value, except for the average of all locations i and all quarters. For this last value, the 95% limits about any individual
- measurement, i.e.,11.2 mR/std. month, is given. The 95% interval for the j mean of all 18 locations for any single quarter is 3.5 i 1.0 mR/std. month, a versus that for the scan of all four quarters at any location at a value of 3.5 i O.73 mR/std. month.
l
)
D. Dose Assessment j Initially, all positive cor.centrations of radionuclides in indicator i samples, as shown in Appendix A, were considered for inclusion in the dose j calculation in an attempt to factor out as much of the contribution due to natural and man-made background radiation as possible, indicator and j control sample results were compared. If the control location results were i greater than those at the indicator location, the indicator sample results j were not included in the dose assessment.
1 i Since no radionuclide other than the naturally occurring j potassium-40 was found in all the waterborne and aquatic samples, surface 4 water from Long Island Sound was therefore, not considered in the dose I assessment. The dose due to standing on soil / sediment was not calculated I since this is accounted for in the direct radiation dose.
1 1
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i 16 i
1 Beryllium-7, potassium-40. radium-228 and thorium-228 are all naturally occurring isotopes and not likely to be produced as a result of the O operation of Shoreham, so they were excluded. Cesium-137 was not detected in any REMP samples during 1994. Therefore, after excluding these four naturally occurring isotopes identified and measured in all the 1994 REMP samples, there was nothing traceable to the Shoreham activities and the resultant doses are zero.
i Comparison of environmental concentrations found in 1994 shows I that they are consistent with those of 1983. For 1994, therefore, there is no discernible dose components other than those from natural sources in ;
the environment. l i
O iO i
i 17 j
i
(. - 5 - . - .D.
5 s 5 ,
~ '
. FIGURE 1 . ,
AVERAGE WEEKLY GROSS BETA RESULTS IN AIRBORNE PARTICULATES ,
- s' s .
,1000
- . . - . r ,
100 . . . _ . . . _ . . . . . _ . _ . _ _ . . _ _ . _ _ . _ _ . . . . . _ .
~ ~ - - '
E~'.l ~ ~ ~ ~ .. ._.
(D . . . _ . . ~ 2
' es __ . . . _ _
e
'10 ._ . . . - . - _ . . . . - . . .. -.
1 i i i i i
. Jan , , Feb Mar .' Apr .'May Jun-' . JiA .
o .
1994 L J
__ m.. . . _ _ _ _ _ _ . _ . _ _ _ _ _ . . . _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ . . _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ . _ _
4 r . - .
- 3 ,
FIGURE 2 , . -
t 4
COMPARISON OF AVERAGE MONTHLY GROSS BETA RESULTS IN AIRBORNE PARTICULATES ,
1000, .-
- ~ . ~:.~: . ~ ~'~ .
e 4
100.
~~
"3 . . .. :.:^~ :.~~
~; ~.:.. ' :.'~:...._.
s W --
Q <
9 ,
w 10- - - - - -
1 1/77_ 1/78 1/79 120 121 122 123 144 '125 r 126 L .
'J t
h h h
. ' t 9 FIGURE 2 (Cont.)- - -
COMPARISON OF AVERAGE MONTHLY GROSS BETA RESULTS IN AIRBORNE PARTICULATES
. s g % $
- s e e 1 ..sw,. . . . . . . . -
l 0 - . . . -.
. . . .. ..s.. , - <ae. .
.eh. .a m ...e--
4g*e.e.g.-wge+.e.mM**.ed
.f- q 100- -. _ ..-. .-
o _.
m a.
T id: 2 , _..
w....ws..-.
a es.-.. .e..we. e.
1 126 . 127 148 129 ISO 141 142: 143 '
1/94
. ( -)
. _ _ . _ ~ _. _ _. . _ __... _ _. _ . _ _ . . __ _ .__. _ _ _ ... _ __. _ . _ .. _ . _ ._ . _ _ _ _. _ .. _ __ _ _ .. _ _ . _ _ . ._.._. _ _ _ .. _ _ .. _ ._ ._ _ _
l h h n )
l L -
- . - 3 ,
FIGURE 3 . ' .
.: i COMPARISON OF QUARTERLY AVERAGE TLD RESULTS(1977-1988) ,
~
~' '
1'O
- g. .. _ . _ .
8 -
O '
8 .,
- 2 p 7 - -- .
, a w ,
~R 6 tc E
5 -
l 4 - --
1 i .
l l 3 - - - -- --
l t
i . \
(
l 2 . .
l 1/77 - 1/78 1/19 120 121 . 122 143 144 in 126- -127 ' ,
128 L
.4e elA u 4,44$ 44 A n. A4,h.E W.m4.h-Ah&a % an .S e th & Wa sh.ga.---aha h - L & A,EmhhW = 4 64 h h h b
, RGURE 3 (Cont.) , .
~
COMPARISON OF QUARTERLY AVERAGE TLD RESULTS (1988-1993) s 10 '
b b
f- 8-
?. .7 ._ . _ . . ..- - - . . . --
~
w E 8 - -
S - -- ---
4-3- - - - - - - - -- -
2 . , . .
128 228 328 428129'249 329 4/89180 240 380 440151241341441 ~ 142 242 lW2 442143 243 343 443144 244 A
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!. III. CONCLUSIONS 1
1 1
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4 I
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4 s
J i
- 23
i CONCLUSIONS
!O j The unit was defueled in August 1989, and has subsequently been in a
- non-operating condition. On February 29,1992, the Shoreham plant license was transferred from LILCO to LIPA. On June 11,1992, NRC issued LIPA a l i Decommissioning Order. The REMP operation continued through these l
- plant ownership and license changes into 1994 when it was terminated on l
} June 6,1994.
4
} Analyses of environmental samples collected during the first half 1994 show results consistent with those found during the preoperational years of j 1983 and 1984. In addition, comparison of results reveals little difference between indicator and control locations. Therefore, no isotopes could be identified as having originated from SNPS.
) Effect on the environment from two decades of atmospheric nuclear
! weapon testing ending in the early 80's and the Chernobyl accident in 1986 i has subsided noticeably in the past several years. This trend is evident j through the gradual disappearance of one of the leading indicators, cesium-
- 137, in all the SNPS REMP samples from 1990 to 1994, as is also supported by the lowering and leveling of annual TLD readings in recent years.
Aside from these minute and residual radioactivities from past test fallout and the Chernobyl accident in the environment, expected normal lO i
l d casre"=a t di ct'vitr - = -e "rea i= asue =9'e ^9u tic ===9 te-were analyzed and reflected the normal background radiation found in the j environment. The atmospheric environment was sampled for airborne particulates and Figure I shows weekly gross beta results in airborne i particulates from Janua2y through June 1994. Figure 2 shows the average monthly gross beta results in airborne particulates from February 1977 to June 1994. Direct radiation levels were relatively low and approximately the i same at all locations. Figure 3 shows the average quarterly TLD results in mR/ standard month from January 1977 to June 1994.
i l
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Y i
l 24 i . . . .-
l l
I IV. REFERENCES I
25
1 i
l IV. REFERENCES iO i (1) Long Island Lighting Company, "Shoreham Nuclear Power Station.
l Environmental Report, Construction Permit Stage", December 1977.
( :
i (2) United States Atomic Energy Commission, Directorate of Licensing, !
j " Final Environmental Statement Related to Operation of Shoreham Nuclear Power Station", Docket No. 50-322, September 1972. l
- 1
- (3) long Island Lighting Company. "Shoreham Nuclear Power Station, )
j Updated Safety Analysis Report", ,
1 i (4) long Island ughting Company and Radiation Management Corporation.
l "Shoreham Nuclear Power Station Radiological Environmental j Monitoring Program - 1977 Annual Report", March 1978.
4 ,
(5) Long Island ughting Company and Radiation Management Corporation, i l
i "Shoreham Nuclear Power Station Radiological Environmental Monitoring Program - 1978 Annual Report", April 1979.
3 (6) long Island Lighting Company and Radiation Management Corporation, j "Shoreham Nuclear Power Station Radiological Environmental
{ Monitoring Program - 1979 Annual Report" June 1980.
I (7) long Island Lighting Company and Radiation Management Corporation.
O "Shoreham Nuclear Power Station Preoperational Radiological Monitoring Program - 1980 Annual Report", September 1981.
j (8) long Island Lighting Company and Radiation Management Corporation,
- "Shoreham Nuclear Power Station Preoperational Radiological Monitoring Program - 1981 Annual Report," October 1982.
l (9) Eisenbud, M., Environmental Radioactivity,2nd Ed.,1973.
(10) National Academy of Sciences, Radioactivity in the Marine j Environment, National Research Council, Washington, D.C.,1971.
i j (11) Long Island Lighting Company, Environmental Engineering Dept.,
Radiological Environmental Monitoring Program Procedures.
i (12) EA Science and Technology, Shoreham Protect Quality Assurance and
- Procedures Manual March 1985.
! (13) U.S. Nuclear Regulatory Commission Regulatory Guide 1.109, Rev.1-d 1977.
(14) Health Physics Journal, Vol. 38, No.4, April 1980.
(15) Teledyne Isotopes, " Nuclear Reactor Environmental Radiation O Monitoring Quality Control Manual", IWL-0032-361.
j 26 4
I IV. REFERENCES (Cont.)
!O ; (16) Teledyne Isotopes, " Quality Control Internal Controls and Audits, j Environmental Analysis Department" IWL-0032-365.
l (17) Teledyne Isotopes, " Quality Assurance Manual. Environmental Analysis i Department Compliance with 10CFR50 Appendix B and Reg. Guide ,
j 4.15", IWL-0032-395. j 1 (18) Long Island Lighting Co. and Teledyne Isotopes,1982 Radiological l j Environmental Monitoring Program Annual Report. j l
1 (19) Long Island Lighting Co. and Teledyne Isotopes,1983 Radiological l j Environmental Monitoring Program Annual Report. l j
j (20) Long Island Lighting Co. and Teledyne Isotopes,1984 Radiological j Environmental Monitoring Program Annual Report.
(21) Long Island Lighting Co. and Teledyne Isotopes,1985 Radiological j Environmental Monitoring Program Annual Report.
I i (22) Long Island Lighting Co. and Teledyne Isotopes,1986 Radiological j Environmental Monitoring Program Annual Report.
(23) Long Island Lighting Co. and Teledyne Isotopes,1987 Radiological Environmental Monitoring Program Annual Report.
t l (24) Long Island Lighting Co. and Teledyne Isotopes,1988 Radiological i Environmental Monitoring Program Annual Report.
l j (25) Long Island Lighting Co. and Teledyne Isotopes,1989 Radiological Environmental Monitoring Program Annual Report.
l
! (26) Long Island Lighting Co. and Teledyne Isotopes,1990 Radiological j Environmental Monitoring Program Annual Report.
(27) Long Island Lighting Co., Long Island Power Authority and Teledyne Isotopes, 1991 Radiological Environmental Monitoring Program Annual Report.
(28) Long Island Lighting Co., long Island Power Authority and Teledyne L Isotopes, 1992 Radiological Environmental Monitoring Program Annual Report.
! (29) Long Island Lighting Co., long Island Power Authority and Teledyne 1
Isotopes, 1993 Radiological Environmental Monitoring Program
- Annual Report.
~
O (30) Derueied saretv inalvsis Report (osaa). Rev. 4. ouiy see2.
(31) Decommissioning Plan Order, June 1992.
j 27
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j APPENDDEA 3
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
l 1994 1
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28 l
l O O O TAB 12 A-1 RADf0fACICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
j SHOREHAM NUCLEAR POWER STATION DOCKET NO. 50-322 l SUFIOLK COUNTY NEW YORK JANUARY I to JUNE 30.1994 l
l ANALYSIS AND IDWERIJMTT NUMBER OF MEDIUM OR PAT 1tWAY TUTAL NUMBER OF A111NDiLATOR IDCATIONSf31 IJ0 CATION WIDI filGHEST MEAN CONF 1tOLIDCAT10Nf31 NONROtmME SAMPLED OF ANALYSES DETECTION MEAN (21 NAME MEANI2) MEAN(2) IEEPORTED llDtfT OF MEASUREMENI) I'ERFORMED (1101 RANCE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS
( Ill surfmee Water H-3 4 100 -(0/3) N/A N/A -(0/l) 0 (pct /Ilter) - -
Gamma 4 K-40 60 229(3/3) 3Cl 0.1 ml NE 317(1/l) 275(1/11 0 (182-317) - -
y Cs- 137 4 -(0/3) N/A N/A -(0/ l) 0 1-131 7 -(0/3) N/A N/A -(0/1) O Mah camma 14 (pCl/kg wet)
K-40 300 3243(10/10) 13G2 13.2 ml W 3820(4/4) 3820(4/4) 0 (2020-4900) (2360-5860) (2360-5860)
Th-228 7 -(0/10) N/A N/A -(0/4) O Cs-137 5 -(0/10) N/A N/A -(0/4) 0 (Il The llDs quoted are the lowest actual 11Ds obtained in the lab for the various media during the reporting period lypical 11Ds were determined for each nucIlde as found on Tables C-9 and C-lo.
(2) Means calculated using detectable measurements only. Fractions of detectable menwrements In parentheses.
(3) Indicator and control locations are noted in Appendix H. Table Il-1.
O O O ..;
TABt2 A-1 tcme.1 i RADIOtDCICAL ENVIRONMENTAL MONITORING PROGRAM StfMMARY
- SHOREHAM NUCLEAR POWER STATION DOCKET NO. 50-322 SUITV(.K COUNTY, NEW YORK JANUARY I to JUNE 30.1994 ANALYSIS AND IDWER LIMIT NUMBER OF MEDIUM OR PATitWAY TUTAL NUMBER OF All INDICA 1DR IDCAT10NSf31 IDCATE)N WTT11 HKillEST MEAlt CONTROLIDCAT10N131 MONROUTINE SAM Pt.ED OF ANALYSES DETECTION MEAN 823 NAME MEAN(2) MEAN12) REPORTED (UNTT OF MEASUREMENT) I'ERFORMED lt1DI Ill itANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS AugustleInvertebrates Gamma 6 (pCl/kg wet)
Be-7 200 -(0/5) N/A N/A -(0/ l) 0 K-40 300 2668(5/5) 3Cl 2.9 ml NE 2745(2/2) 2400(1/1) 0 (2330-3060) (2680-2810) -
Cs-137 4 -10/5) N/A N/A -(0/1) O ta Th-228 7 -(0/5) N/A N/A -(0/1) 0 (1) The 11Ds quoted are the lowest actual LLDs obtained in flic lah for the varfous media during the reporting period. Typical 11Ds were determined for each nucitdc as found on Tables C-9 arwl C-10.
(2) Means calculated using detectable measurements only. Fractions of detectable measurerr.*nts in parentheses.
(3) Iruficator and control locations are noted in Appendix II. Tahic 11 1.
O O O .
TABt2 A-1 Icnni1 RADIOEDOICAL ENVIRONMENTAL MONt1DRING PROGRAM
SUMMARY
SHOREHAM NUCLEAR POWER STATION DOCKET NO. 50-322 SUF1GK COUN1Y. NEW YORK JANUARY I to JUNE 30.1994 ANALYSIS AND IIMFERIJMTT NUMBER OF MEIMUM OR PAT 11WAY TOTAL NUMBER OF A11 tNDICATDR IDCATIONSf31 IDCATION Wff11 IllGilEST MEAN CONTROLIDCA110NI38 NONROtff1NE SAMPLED OF ANALYSES DETECT 10N MEAN 121 NAME MFAN(21 MEANI21 REPORTED IUNTT OF MEASUREMENfl PERFORMED 111D1 Ill RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Sediment (Beach) Gamma l (pC1/kg dry)
K-40 900 1760(I/11 2A4 OA mi NNE 1760(I/1) -(0/0) 0 i
Cs-137 8 -(0/1) N/A N/A -(0/0) O e
Ra-226 200 -(0/1) N/A N/A -(0/0) 0 Th-228 60 174(1/l) 2A4 0.4 ml NNE 174(1/1) -(0/0) 0 (1) The 11Ds quoted are the lowest actual 11Ds obtained in the lah for the various media durtry the reporting parlod Typical LIDS were determined for each r uclide as found on Tables C-9 and C-10.
(2) Means calculated usity detectable measurements only. Fractions of detectable measurements in parentheses.
(3) Indicator and control locations are noted in Appendix B. Table 11-1.
O O ..
TABLE A-1 Itwe.1 RADIORDOICAL ENVHtONMENTAL RIOfMTORING PItOORAM SURERRARY SHOREHAM NUCl. EAR POWER STATION DOCKET NO. 50-322 !
SUFTOLK COUffiY. NEW YORK JANUARY l to JUNE 30.1994 4
ANALYSIS AND IDWER LIMfT NUMBER OF MEDIUM OR PAT 11WAY 1UTAL ftUMBER OF ALL MtDICATOR IJDCATIOftS31 IDCATIOie Wfnt HIGilEST AREAM CONTD06.lDCA"f10NES MONROUTINE ;
< SAMPLED OF ANALYSES DETECTION MEAN (21 MAME MFANt2l MFJuel2) REFORTED
~
luMfT OF MEASUREMEfrD PERFORMED ltIDI III ham;E DISTANCE AND DfRECTION RANGE RANGE MEASUREMENTS Airtierne Phrticulates Gross Beta 120 4 18.3(96/96) ' A2 0.2 ml NNE 18.5(24/24) 17.5(24/24) O !
(10 3pCI/m3) (7.5-31) (8.0-29) (8.1 -29) ;
Comma 10 Be-7 99.2(8/8) 3S1 0.1 ml NE 106.2(2/2) 88.5(2/2) 0 (72.7-I29) (94.3-1I8) (77.6-99.3)
K-40 4 12.4(5/8) 2A2 0.2 ml NME 15.5(2/2) -(0/2) 0 (8.22-22.8) (8.22-22.8) -
w Cs-134 0.4 -(0/8) N/A N/A -(0/2) O Cs-137 0.4 -(0/8) N/A N/A -(0/2) 0
. t d
i (1) Tne LLDs quoted are the lowest actual 11Ds obtained in the lah for the various media durlew the reporting period Typical LIDS were determined for each nuclide as found on Tables C-9 arw! C-10.
, (2) Means calculated using detectable measurements only. Fractions of detectable measuremerds in parentheses.
(3) Indicator nrwl control locations are noted in Apperwfix D. Table H-l.
u _ _- _ . _ . . _ - . ---_-____a._.--_ -.m____ _ _ _ _ _ _ _ _ - - - _ _ _ _ _ _ _ _ _ _ _ __
O O ..
TABt2 A.1 Irms.)
RADIORDGICAL ENVIRONIltENTAL 300NITURING PROGRAllt SUREREARY SHOREllAM NUCLEAR POWER STATION DOCKET NO. 50-322 SUITOLK COUfffY. NEW YORK JANUARY 1 to JUNE 30.1994 ANALYSIS AND IDWER UMfT NUMBER OF MEDtUM OR PATIIWAY TOTAL NUMDER OF AlllNDICA1DR IDCATIONSf31 IDCATIDN Wint HIGHERE.NEAR CONTROLIDCAT10MI3 NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN (2) NAME MEANf21 MEANI21 RF,70RTED (UNTT OF MEASUREMENT 1 PERFORMED !!1D1 Eli HANGE DtSTANCE AND DIRECHON RANGE RANGE MEASUREMENTS t
Direct Radletion Gamma 36 (mR/ Standard month) Dose 1.5 3.22(32/32) 12A1 0.9 ml WSW 4.05(2/2) 3.28(4/4) 0 Quarterly (2.8-4.3) (3.8-4.31 (3.1-3.5) '
U i
(Il The LLDs quoted are the lowest actual LIDS obtained in the lah for the vartmas media during the reportinst period Typical 11Ds were determined for each nucIlde as found on Tables C-9 amt C-10.
(2) Means calculated using detectable measurements only. Fractions of detectabic measurements in parentheses.
(31 Indicator and control locations are noted in Apperwitx H. Table U-I.
__w.._.a.m.J _1.. 4 .._m., 4 _-_. +- eh.. ..a..,e__. 4#._ . _- . . . . - . - 4. _ . - . . , - - - _ - - . --a - _. _-- _ _ _ _ _ . _ _ _ . - - . -- _ _ _ _ _ _ _ _
' E i
I
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f i h
e a
4 1
1 3
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a i APPENDIX B
! SAMPLE DESIGNATION AND SAMPLING LOCATIONS i
4 1
)
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a l
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s
)
,i 34
+
.. , . _ . .__ -y .-
i APPENDIX B O Sample Designation IJPA's Radiological Environmental Monitoring Program (REMP) identifies samples i by a three part code. The first two letters are the power station identification code, in this case "SN". 'rhe next three letters are for the media sampled.
sw^ = Surface Water (long Island Sound) MLK = Cow Milk AQF = Fish (1) OMK = Goat Milk AGI = Invertebrates (1) PWA = Potable Water (ground water)
AQs = Sediment FPV = Food Products (1)
APT = Airborne Particulates FPF = Fruit AIO = Airborne lodine IDM = Immersion Dose frLD)
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 1/2 degrees centered about the reactor site. Sector one is divided evenly by the north axis, and other sectors are numbered in a clockwise direction, f.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 5-10 miles off site O A B
=
=
O-1 miles off site 1-2 miles off site F
G
=
= 10-20 miles off site
>20 miles off site i
C = 2-3 miles off site H = '
D = 3-4 miles off site The last number is the location numerical designation within each sector and zone, e.g.,1,2,3.....for example, the designation SN-SWA-3C1 would indicate a sample in the SNPS program SN, consisting of surface water SWA, which had been collected in the 22-1/2 degree sector centered on the northeast axis (3) between the site boundary and 2-3 miles off site (C). The number 1 indicates that this is sampling station No.1 in the designated area.
Sampling locations All sampling locations and specific information about the individual locations are given in Table B-1. Tables B-2 through B-5 list the sampling locations and media required by ODCM. l (1) A more specific means of classification will be noted in the comment section of each laboratory report for these samples. For example, AQI will be designated, in the sample description, as aquatic invertebrate. However, the comment section will specify the sample type by the generally accepted common name of the sample involved. In this case, clam, lobster, crab or other aquatic invertebrate would be listed in the comment section.
35
Maps B-1, B-2 and B-3 show the locations of 1994 sampling stations with respect to the site. These maps are tracings of portions oflarger maps pcepared by LILCO's Survey Division after an extensive land survey of REMP monitoring locations, j Additional information can be obtained by referring to the Site and Vicinity Map of 4
the Shoreham Nuclear Power Station (Map B-2), the map of Long Island and
, Connecticut Shore (Map B-3) and by contacting either LILCO's Environmental j Engineering Department or Survey Division.
TABLE B-1 Sample Locations Required By SNPS OfBste Dose Calculation Manual LOCATION SAMPLE i SECTOR CODE IDCATION TYPE
! N IS1 Beach east ofintake,0.3 mi. N IDM NE 3S1 Site Bounday,0.1 mi. NE APT,IDM
- ENE 4SI Site Boundary,0.1 mi. ENE IDM l
E 5S2 Site Bounday,0.1 mi. E IDM i ESE 6S2 Site Boundary 0.1 mi. ESE APT IDM S 9S1 Service Road. 0.2 mi. S IDM
! W 13S3 Site Boundary. 0.2 mi W IDM j WNW 14S2 St. Joseph's Villa, 0.4 mi. WNW IDM j NW 15S1 Beach west of intake, 0.3 mi. NW IDM NNW 16S2 Site Bounday,0.3 mi. NNW IDM i NNE 2A2 West rad of Creek Road. 0.2 mi. NNE APT,IDM NNE 2A4 Beach, 0.4 mi. NNE AQS SE 7A2 North Country Road,0.7 mi. SE IDM i SSE 8A3 North County Road. 0.6 mi. SSE IDM SSW 10A1 North Country Road,0.3 mi. SSW IDM SW 11A1 Site Boundary. 0.3 mi. SW IDM WSW 12A1 Meteorological Tower, 0.9 mi. WSW IDM i SE 7B1 Overhill Road, Wadi.ng River,1.4 mi. SE APT
- NE 3C1 Outfall area, aquatic location B-5. AQF,AQI, 2.9 mi. NE SWA l WNW 14C1 Outfall area, aquatic location SWA.AQF, B-4, 2.1 mi. WNW AQI
) SW C 11G1 MacArthur Substation,16.6 mi. SW AI T ,I D M
- WSW C 12G1 Central Islip Substation,19.9 mi. WSW IDM
- W C 13G2 Background aquatic location,13.2 mi. W SWA AQF,AQI l
4 O
l C Denotes Contro11ocation 1
36
4 i SAMPIE IDCK110NS REQUIRED BY SNPS OFFSITE DOSE CALCUIEllON MANUAL I
TABIE B 2 l
l Airborne Particulate Monitoring Stations 1
l Imcation Codes i NUREG-0473 $HOREHAM REMP Imcation Description
?
, A1 6S2 Site Boundary. 0.1 mi. ESE i A2 2A2 West end of Creek Road, 0.2 mi. NNE A3 SSI Site Boundary 0.1 mi., NE l A4 7B1 Overhill Road,1.4 mi. SE j l
j A5 11G1 MacArthur Subst' Mon,16.6 mi. SW I
TABLE B-S
]
- Waterborne Monitoring Stations j Imcation Codes j NUREG-0473 SHOREHAM REMP Imcation Description I
- WA1 13G2 Surface, background area,13.2 mi. W
- WA2 14C1 Surface, outfall area,2.1 mi. WNW WA3 3C1 Surface, outfall area,2.9 mi. NE I Wdl 2A4 Sediment, Beach, 0.4 mi. NNE l g
l TABLE B-4 l Ingestion Monitoring Stations I i
i Imcation Codes NUREG-0473 SHOREHAM REMP Lpeation Description
! Ib1 3C1 Fish and Invertebrates, outfall area,
! 2.9 mi. NE j lb2 14C1 Fish and Invertebrates, outfall area,
! 2.1 mi. WNW Ib3 13G2 Fish and Invertebrates, background, 3 13.2 mi. W i
i l l
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l 37 i
l 1
SAMPLE IDCAT10NS REQUIRED BY Q SNPS OFFSITE DOSE CALCULATION MANUAL V
TABIE B-5 Direct Radiation Monitoring Stations location Codes NUREG-0473 SHOREHAM REMP Jacation Description DR1 IS1 Beach east ofintake,0.3 mi. N DR2 2A2 West end of Creek Road,0.2 mi. NNE j DR3 3S1 Site Boundary,0.1 mi. NE DR4 4S1 Site Boundary,0.1 mi. ENE DR5 5S2 Site Boundary,0.1 mi. E DR6 6S2 Site Boundary,0.1 mi. ESE DR7 7A2 North Country Road,0.7 mi. SE DR8 8A3 North Country Road. 0.6 mi. SSE DR9 9S1 Service Road SNPS, 0.2 mi. S DRIO 10A1 North Country Road,0.3 mi. SSW DR11 11A1 Site Boundary,0.3 mi. SW DR12 12A1 Meteorological Tower, 0.9 mi. WSW DR13 13S3 Site Boundary,0.2 mi. W DR14 14S2 St. Joseph's Villa, 0.4 mi. WNW
- DR15 15S1 Beach west ofintake,0.3 mi. NW
] DR16 16S2 Site Boundary,0.3 mi. NNW
, DR30 12G1 Central Islip Substation,
- 19.9 mi. WSW j DR31 11G1 MacArthur Substation,16.6 mi. SW i ;
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APPENDIX C DATA TABLES d
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O O O .
TABLE C-1 CONCENTRA110NS OF *IRrT10M AND GAMMA EMITTERS
- IN SURFACE WATER SAMPLES Results in Units of pCI/I i 2 sigma IDCATION CODE COURCTION DATE H-3 1-131" K-40 Co-137 SN-SWA-3Cl 05/25/94 < 200 <7 317 i 40 <4 SN-SWA-13G2 (ct) 05/25/94 < 200 <6 275 i 42 <3 SN-SWA-14Cl 05/25/94 < 200 <6 189 i 27 <3 05/25/94 < 200 <7 182 i 41 <4 N
Awenge 241i132 i 2 s.d.
AB (dfer gamma emitters not Itsted were <llR typical Im are gven in Taldes C-8 and C-9.
I-131 by gamma spectrumcpy (ct) Denotes Control location.
_. . . . . . _ _ _ _ _ - . . .- .._ --_ _ _. . .-.. _... _.=__..__.m.- _.. .__ .._. m ..__. . _ _ . . . . .
O O O j TABLE C-2 CONCEffrRATIONS OF GAMMA EMtTTERS* IN FISH SAMPLES Results in Units of pct /kg twell i 2 sigena t
RACATION COELECTION DESCRIFFION K-40 Co-137 Th-228 CODE DATE SN-AQF-SCI 05/23/94 Llule Skate 2120 1 240 < 20 < 30 05/23/94 Sea Robin 4080 1 410 < 20 < 40 05/23/94 Windowpane 3570 1 360 < 20 < 30 05/23/94 Winter Flounder 3630 1 360 < 20 < 40 05/23/94 Little Skate 2020 i 200 < 10 < 20 SN-AQF-14C1 05/24/94 Little Skate 2130 1 210 < 20 < 30 05/19/94 Little Skate 2660 1 270 < 20 < 20 05/24/94 Sea Robin 4900 i 680 < 80 < 100 05/19/94 Winter Flounder 3790 1 380 < 20 < 30 05/24/94 Windowpene 3530 1 350 < 20 < 20 6
- SN-AQF-ISO 2 tell 05/16/94 Llule Skate 2360 1 240 < 20 < 30 05/16/94 Sea Robin 5860 i 950 < 100 < 200 05/16/94 Winter Flounder 3760 i 380 < 10 < 20 05/16/94 Windowpane 3300 i 330 < 20 < 30 Average i 2 s.d. 3408i 2215 a
i
- All other gamme emitters not listed were <LLD: typical 11Ds are sven in Tables C-8 and C-9.
(cll Denotes Control location.
O O O ..
TABLEC-3 CONCENTRATIONS OF GAMMA EMITTERS
- IN INVERTEBRATE SAMPLES Results in Units of pCI/kg twet) i 2 sigma i
IDCATION COLIJ!X: TION DESCRIPTION Be-7 K-40 Cs-137 Tit-228 CODE DATE SN-AQI-3Cl 05/23/94 Lobster < 200 2810 1 280 < 20 < 30 05/23/94 Lobster < 100 2680 1 270 < 20 < 20 SN-AQI-14C l 05/23/94 Whelk < 200 2460 1 260 < 20 < 40 05/24/94 lobster < 100 3060 i 310 < 20 < 30 05/24/94 Lobster < 100 2330 1 230 < 10 < 20
- SN-AQl-13G2 (cIl 05/16/94 lobster < 200 2400 i 240 < 20 < 30 Average 26231 500 1 2 s.d.
All other gamma emitters not listed were <LLD: typical 11Ds are sven in Tables C-8 and C-9.
(cIl Denotes Control location.
O O O ,
TABLE C-4 CONCENTRATIONS OF CAMMA EMITTERS
- IN SEDIMENT SAMPIES Results In Units of pct /kg (dry) i 2 sigma IDCATION SAMPLE COtl2CTf0N K40 Ra-228 Co-137 Th-228 CODE IDCATION DATE SN-AQS-2A4 Beach 06/07/74 1760 1 250 < 400 < 20 174 i 23 Average 1760 1 250 174 i 23 i 2 s.d.
y i All other gamma emitters not listed were <Ilb. typical ll,Ds are gven in Tables C-8 and C-9.
(ct) Denotes Control location.
. _ . _ . _ _ . ...__.m .__..m..___
_ _ _ - -__. ._.-m. _ _ . . _ _ _ - . . _ . . . -_ . _ _ . _ - . _ . _ . -. - .----m.... ...
O O O ..:
TABt2 C CONCENTRATIONS OF GROSS BETA EMITTERS IN WEEMLY AIRBORNE PARTICULATE SAMPLES Results in Units of 10-3 pCI/m3 i 2 shtma l
LOCATION CotNts cot 1ECTION DATES SN-APT-2A2 SN-AFT-381 SM-APT-GS2 SN APT.7BI SN APT-11G1 ATERAM (el)
- 2 e d. '
JANUARY _.Ri i
~
12/28/93-01/04/94 15 i 3 14 1 3 161 3 121 3 13 i 3 14 i 3 GI/04/94-01/11/94 19 i 3 20 i 3 191 3 20i 3 18 i 3 19 i 2 C1/11/94-01/18/94 241 4 231 4 24 i 4 28 i 4 24 i 4 251 4 ;
291 4 271 2 01/18/94-01/25/94 271 3 26 i 3 271 4 27 i 3 01/25/94-02/01/94 18 i 3 18 i 3 22 i 3 201 3 21 i 3 20 i 4 FEBRUART 02/01/94-02/08/94 29 i 3 261 4 31 i 4 26 i 4 28 i 4 28 i 4 02/08/94-02/15/94 24 i 3 251 4 221 3 221 3 22 i 3 23 i 3
$ 02/15/94-02/22/94 28 i 4 251 4 2614 24 i 3 29 i 4 26i 4 '
02/22/94-03/01/94 15 i 3 15 i 3 15 i 3 17 i 3 13 i 3 15 i 3 MLWC.H 03/01/94-03/08/94 21 i 4 211 4 21 i 4 22 i 4 18 i 3 '21 i 3 C3/08/94-03/15/94 25 i 4 18 i 4 16 i 3 211 4 17 i 3 19 i 7 C3/15/94-03/22/94 13 i 3 13 i 3 20 i 4 9.7 i 3 1 12 i 3 14 i 8 C3/22/94-03/29/94 19 i 3 16 i 3 12 i 3 15 i 3 15 i 3 15 i 5 Ant &
03/29/94-04/05/94 18 i 3 18 i 3 171 3 15 i 3 17 i 3 17 1 2 04/05/94-04/12/94 12 i 4 12 i 4 9.0 f 3.7 12 i 4 9 6 i 3.6 11 i 3 04/12/94-04/19/94 20 i 4 18 i 4 161 3 17 i 3 17 i 3 18 i 3 04/19/94-04/26/94 19 i 3 20 i 3 16 i 3 20 i 3 17 i 3 18 i 4 04/26/94-05/03/94 12 i 3 13 i 3 161 3 14 i 3 13 i 3 14 i 3 IcIl tenotes centrol Imatkm.
_ _ _ _ _ _ _ _ . . _ _ _ _ . _ . . _ . . . . ~ . _ _ . _ . . . . . _ . _ . . . _ . _ . _ . -
_. _.__..._-__ _ __ . ..-__ _ _ _. . _._... ..._m .. . .__m.._ _ _ _ _ _
TABt.E C-5 tews.1 CONCENTRA110NS OF GROSS BETA EMITTERS IN WEEKl.Y AIRBORNE PAR 11CUIATE SAMPLES Results in Units or 10-3 pC1/m3 i 2 sigma
! tocATioncoons cota.EcTson DATES sN-AFF.2A2 SN. AFT-381 SM-APT-682 SN. APT-751 SN. APT 1101 AVEstAGE (el) i 2 s.d.
i M
05/03/94-05/10/94 14 i 3 13 i 3 121 3 151 3 121 3 13 i 3 05/10/94-05/17/94 15 i 3 19 i 4 211 4 31 i 4 16 i 3 20 i 13 05/17/94-05/24/94 8.0 1 2.7 101 3 8.4 1 2.8 7.5 i 2.6 8.1 1 2.7 7.41 4.9 05/24/94-05/31/94 18 i 3 221 3 20 i 3 17 i 3 18 i 3 19 i 4 JUNE 05/31/94-06/07/94 12 i 3 12 i 3 121 3 13 i 3 12 i 3 12 i 1 06/07/94 06/14/94 18 i 3 19 i 4 19 i 4 17 i 3 211 4 19 i 3 A m ute is i 11 1s i to 1s i 11 1s i 12 17i 12 isi 11 i s .d.
(ct) Iknotes Contrul treaurws.
. . . . _ _.__>m. . __ . . _ _ . . _ _ . . ._m. _.
O O O .
TAB 12 C-e CONCENTRA'110NS OF CAMMA EMITTERS
- IN QUARTERLY COMPOSITE OF AIRBORNE PARTICULATE SAMPLES Results in Units or 10-3 pCl/m3 12 stena 10 .tT!Of* NUCl, IDES FIRST QUAPTER SECOND QUARTER AVERAGE 4'ocE3 12/2n/ss43/29/94 03/29/94 46/14/94 i 2 s.d.
i SN AM-2A2 Be-7 85.4 i 8.5 109i iI 97.2 i 33.4 K-40 8.22 i 4.I8 22.8 i 6.5 15.5120.6 Cs-134 < 0.4 < 0.7 Cs-137 < 0.4 < 0.6 SN-APT-351 Be-7 94.3 i 9.4 118 i 12 106 134 K-4 0 < 10 12.514.1 12.5 i 4.1 Cs.i34 < 0.5 < 0.4 Cs-137 < 0.6 < 0.6 s
'O SN-APT-SS2 Be-7 72.717.3 129i 13 101 i 80 K-40 8.34 i 4.53 10.015.0 9.17 i 2.4 Cs-134 < 0.6 < 0.4 Cs-137 < 0.6 < 0.5 SN-AIFT-7B1 Be 7 75.8 i 7.6 109iI1 92.4 i 47.0 K-40 <9 <9 Cs-134 < 0.5 < 0.4 Cs-137 < 0.6 < 0.4 SN-APT-1101 Be-7 77.6 i 7.8 99.3 i 10.7 88.5 i 30.7 (cl) K-40 <9 < 20 Cs-134 < 0.4 < 0.7 Cs-137 < 0.6 < 0.7 All other gamma emitters not IIsted werc <LLD: typtcal LLDs are found in Tables C-8 and C-9.
(ci) Denotes control location.
O O O ..
TABLE C.7 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS mR/stamfard month
- IDCATfoN FIRST GUARTER SECOND QUARTEft ANNUAL AVEstAGE coons 01/ce/osee/07/o4 04/07/o447/os/04 la)
SN-IDM. IS1 3.3 1 0.3 3.1 1 0.4 3.2 i 0.3 SN.lDM-3SI 3.1 i O.I 2.9 1 0.4 3.0 i 0.3 SN-IDM.4SI 3.4 i 0.1 3.5 1 0.1 3.5 i O.1 SN.lDM.5S2 3.4 i O.1 3.4 1 0.3 3.4 i O.0 SN.lDM.6S2 3.4 1 0.0 2.9 i 0.2 3.2 i O.7 SN-IDM 9SI 2.9 i 1.2 3.4 i 0.3 3.2 i O.7 SN.lDM- 13S3 3.4 i 0.2 2.8 i 1.0 3.1 1 0.9 SN-IDM-14S2 3.0 1 0.1 2.9 i 0.3 3.0 i O.1 SN.lDM-1SSI 2.9 1 0.I 2.9 i 0.2 2.9 i 0.0 u, SN.lDM-16S2 3.3 i O.2 3.2 1 0.6 3.3 i O.1 SN.lDM.2A2 3.0 i 0.I 2.8 i 0.3 2.9 i 0.3 SN.lDM-7A2 3.2 1 0.1 3.4 i 0.1 3.3 i 0.3 SN-IDM.8A3 3.3 1 0.2 3.0 1 0.5 3.2 1 0.4 SN.lDM- 10A1 3.2 i 0.1 3.3 1 0.7 3.3 i O.1 SN-IDM- 11 A1 3.3 i 0.4 3.2 1 0.2 3.3 i 0.1 SN.lDM- 12A1 3.8 i 0.2 4.3 1 0.3 4.1 1 0.7 SM-IDM- 1 IG1 (ct) 3.5 1 0.2 3.3 1 0.2 3.4 i 0.3 SN-IDM-12G1 (ct) 3.2 i O.1 3.1 1 0.2 3.2 1 0.1 4
Averag M 3.3 i O.5 3.2 i 0.7 3.2 i O.6 (c)
De standard month = 30.4 days.
(a) De i Ilmits given in this column define a 95% confidence interval for the mean of the four quarterly results at that location.
(b) The i limits given in this row define a 95% confidence Interval for the mean of all locanons for that quarter.
(c) The i limits gtven here define a 95% confidence interval for a measurement at any location during any quarter in 1994.
(cIl Denotes Control location
1 l
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s' % fr TABt2 C-9 LLDs AND REPORTING ACTION LEVELS REQUIRED HYODCM AND 1994 CONTRACT SABEFIE TTFE
^
Unita creas meta M S_ Mn-84 Ca se Fe4B Osee Em48 Gr-8BIII AT9808FffERIC Air Sample 11D* ODCM pct /m3 0 01 - - - - - - -
11 0 Contract 0 01 - - - - - - 0.005 RAL** ODCM - - - - - -
RAL Contract I - - - - - - 0.1 j AGUATIC F1sh and 11D ODCM pct /hg - - 130 - - 130 280 -
Invertebrate 11D Contract twet) - - 130 130 280 130 280 5 (21 Aquatic 11antst21 RAL ODCM - - 30.000 - - 10.000 20.000 -
RAL Contract - - 30.000 30.000 10.000 10.000 20.000 20(21 WATER Surface 11D ODCM pct /l 4 3.000 15 - - 15 30 -
llD Contract - 3.000 15 15 30 15 30 10 RAL ODCM - 30.000 1.000 - - 300 300 -
RAL Contract - 30.000 1.000 1.000 400 300 300 20 tit N Came I2I Softs llD ODCM pCI/kg - - - - - - - -
11D Contract (dry) - - - - - - - 5 RAL ODCM - - - - - - - -
RAL Contract - - - - - - - 80 SEDIRRENT Sediments 11D ODCM pct /kg - - - - - - - -
LID Contract Idryl - - - - - - - 5 RAL ODCM - - - - - - - -
RAL Contract - - - - - - - 80 DUtBCf RADIATIOft TtD 11D ODCM - - - - - - - -
IlD Contract 1.5 mR/std. month - - - - - - - -
RAL Contract - - - - - - - -
Note: See fontnotes at end d tahk.
, .mm ..-mm___ _.m_._ _.-.....__.m. - . . . _ . ~ . - _ - _ . . _ _ - _ . . .-._.m., - . . . ~ ._ _ - -___ ._ _ _ _ _ m . .m _- .- _ . _ . _ _ . _ . .
e TABLE C-9 Ocore.)
LLDs AND REPORTING ACTION LEVELS REQUIRED BY ODCM AND 1994 CONTRACT jasialut2 TTPE 17 elta er eeI80 Er.95 Mb 95 I-131I81 CoISS ht*F Ba-148 Im-149 WATER ,
6 Surface LLD OOCM pct /l - - - - 15 18 - -
IJD Contract 2 30 15 15 ISI 15 18 - 15 M RAL OOCM - - - - 30 50 - -
r RAL Contract 20 40019 - 20 30 50 - 200 III l
ATMOSPRERIC Air Sample llD ODCM pC1/m3 - - - - 0.05 0.08 - -
IJD Contract 0.001 - - 0.07 0.05 0.06 - -
RAL OOCM - - - - 10 20 - -
i RAL Contract 0.1 - -
0.9 10 20 - -
l AgUATIC ptsh and 11D OOCM pCi/kg - - - - 130 150 - -
Invertebrate 11D Contract twett 5 125 - - - 130 150 - -
$ Aquatic I1antst2) RAL ODCM RAL Contract 20 (21 1.000 1.000 2.000 2.000 Sotts llD ODCM PCl/kg - - - - - - - -
Lim contract Idryl 5 - - - 150 180 - -
RAL Contract 80 - - -
1.000 2.000 - -
SEINREENTS Sedhnents llD DOCM pCI/kg - - - - ISO 180 - -
LID contract Idry) 5 .
- - 150 180 - -
RAL Contract MO - - - 1.000 2.000 - -
l
- Imwer IJmet of Detection
- Reporting Action level (1) Sr-89 data remained In contract for spedal requent cases le.g. Termination Sewvey) only.
125 There are no ODCM requerements for gune or aquatic plants. Fish contract llDs asul HAls for spunma spectrometry apply to gusae. Except for Sr-89/90. Ash contract LLDa and RAlm forspumna w .-., at name numertral value but in dINereset unitn II.e. pCI/kg dryl. apply to aquatic plants. Sr-50/9011De and RAls for aquatic plants are 30
^ ^
pC3/kgIdryl and 45 pO/kgIdryl. mu m ., .
13 Sr-90 and I.131 by rarmachemistry remnened in contract for special requegt canre (e.g. Termination Surveyl ordy.
(4) Reporting level inr total Zr-95 plus Nh-95.
15l For non41rtnkenet water thway.
181 BA/IA-140 eamhaned .
(7) %,eg level for hetal Be-140 plus 14 140.
---___--_-._-.--______--_---amme ,m---_ - - --- ._ -- - -- - - . _ ,
1 1
i 1
i I
e 1
i i
e i
i i
I 1
1 i
e i,
APPENDR D f
- ANALYTICAL PROCEDURES SYNOPSIS I
1 i
i ANALYTICAL PROCEDURES SYNOPSIS Appendix D is a synopsis of the analytical procedures performed during ,
, 1994 on samples collected for the Shoreham Nuclear Power Station
} Radiological Environmental Monitoring Program. All analyses have been )
l mutually agreed upon by long Island Power Authority and Teledyne Brown !
) Engineering and include those recommended by the NRC Regulatory Guide ;
4.8, BTP, Rev.1 November 1979.
i 1
l
- ANALYSIS TITIE EArnE 4
j Gross Beta Analysis of Air Particulate Samples . . . . . . . . . . . . . . . . . . . . . . . . . 56 i
j Analysis of Samples for Tritium (liquid Scintillation) . . . . . . . . . . . . . . . . . . . 57 l
i
- Gamma Spectrometry of Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 58 Milk and Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 58 1
1 Dried Solids other than Soils and Sediment . . . . . . . . . . . . . . . . . . . . . 58 i F1sh.......................................................58
- O i Soils and Sediments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 58 l Airborne Particulates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 58 i
Environmental Dosimetry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60
{
4
)
i h
t i
l l
1 J
I iO s
l J
- i i
l
! GROSS BETA ANALYSIS OF AIR PARTICUIATE SAMPLES I
i'
, Airborne Particulates i
l After a delay of five or more days, allowing for the radon-222 and l radon-220 (thoron) daughter products to decay, the filters are counted in a gas-flow proportional counter. An unused air particulate filter, supplied by i the customer, is counted as the blank.
- Calculations of the results, the two sigma error and the lower limit of detection (LLD)
4
! RESULT (pC1/m3) = ((S/T) - (B/t))/(2.22 V E) 1
) "IWO SIGMA ERROR (pC1/m3) = 2((S/T2) + (B/t 2))1/2/(2.22 V E) i LLD (pCi/m3) = 4.66 (B/t/T)1/2/(2.22 V E)
)
- O
- where
l
! S = Gross counts of sample including blank
. B = Counts of blank l E = Counting efficiency l T = Number of minutes sample was counted i t = Number of minutes blank was counted l V = Sample aliquot size (cubic meters) l i
1 iO 4
56
~
i, l
i l
! AMALYSIS OF RAMPIES FOR TRITIUM 1
f (IJquid Scintillation) ;
i l M l l Ten milliliters of water are mixed with 10 ml of a liquid scintillation I
) " cocktail" and then the =ivhare is counted in an automatic Mqidd ::ttillator. l i
1 l
Calculation of the results, the two sigma error and the lower limit ;
- detection (LLD) in pCi/l
- l
} l 1 RESULT = (N-B)/(2.22 V E) i 4
4 TWO SIGMA ERROR = 2((N + B)/At)1/2/ (2.22 V E)
! Lw = 4.66 (B/At)1/2/(2.22 V E )
1 2
where: N = the gross cpm of the sample B = the background of the detector in cpm
- l 2.22 = conversion factor changing dpm to pCi j V = volume of the sample in ml l E = efBelency of the detector l l At = counting time for the sample i
4 j
i i
i 1
4 i
)
I O
4 j 57
i i
i
! GAMMA SPECTROMETRY QF RAMPLES
!O i Milk and Water I
i A 1.0 liter Marinelli beaker is filled with a representative aliquot of the i sample. He sample is then counted for approximately 1000 minutes with a-shielded Ge(Li) detector coupled to a mini-computer-based data acquisition J system which performs pulse height analysis.
Dried Solids other than Snlis and Sediments
) A large quantity of the sample is dried at a low temperature, less than 100 C. As much as possible (up to the total sample) is loaded into a tared 1-l liter Marinelli and weighed. The sample is then counted for approximately j
j 1000 minutes with a shielded Ge(L1) detector coupled to a mini-computer-
) based data acquisition system which performs pulse height analysis.
4 ll Esh As much as possible (up to the total sample) of the edible pordon of l
j the sample is loaded into a tared Marinelli and weighed. The sample is then
! counted for approximately 1000 minutes with a shielded Ge(LI) detector ,
l coupled to a mini-computer-based data acquisition system which performs I
pulse height analysis.
Soils and Sediments l
! Soils and sediments are dried at a low temperature, less than 100 C.
} The soil or sediment is loaded fully into a tared, standard 300 cc container I and weighed. De sample is then counted for approximately six hours with
! a shielded Ge(Li) detector coupled to a mini-computer-based data l acquisition system which performs pulse height analysis.
1 l Airborne Particulates 4 ;
i i
- The thirteen airborne particulate filters for a quarterly composite for l l each field station are aligned one in front of another and then counted for at i least six hours with a shielded Ge(Lt) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.
4 58
J A mini-computer software program defines peaks by certain changes l in the slope of the spectrum. The program also compares the energy of
- j. each peak with a library of peaks for isotope identification and then
! performs the radioactivity calculation using the appropriate fractional i
gamma ray abundance, half life, detector efficiency, and net counts in the peak region. The calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/ volume of pC1/ mass: i RESULT = (S-B)/2.22 t E V F DF)
TWO SIGMA ERROR = 2(S+B)1/2/(2.22 t E V F DF)
LI.D = 4.66(B)1/2/(2.22 t E V F DF) where: S = Area, in counts, of sample peak and background (region of spectrum of interest)
B = Background area, in counts, urder sample peak, determined by a linear interpolation of the O representative backgr unds n either side of the peak t = length of time in minutes the sample was counted 2.22 = dpm/pCi E = detector efficiency for energy of interest and geometry of sample V = sample aliquot size (liters, cubic meters, kilograms, or grams)
F = fractional gamma abundance (specific for each emitted gamma)
DF = decay factor from the mid-collection date to the counting date O -
59
l l 1
l i
j ENVIRONMENTAL POSIkETitY
]O j
Teledyne Brown Engineering uses a CaSO 4 :Dy thermoluminescent dosimeter (ILD) which the company manufactures. '1his material has a high j light output, negligible thermally induced signal loss (fading), and negligible
- self dosing. The energy response curve (as well as all other features) l satisfies NRC Reg. Guide 4.13. Transit doses are accounted for by use of .
j separate TLDs.
! Following the field exposure period the TLDs are placed in a Teledyne I
l Isotopes Model 8300. One fourth of the rectangular TLD is heated at a time and the measured light emission (luminescence) is recorded. The TLD is
( then annealed and exposed to a known Cs-137 dose; each area is then read
! again. This provides a calibration of each area of each TLD after every field l use. The transit controls are read in the same manner.
Calculations of results and the two sigma error in net milliroentgen (mR):
l RESULT D = (D3 +D2 +D3 +D4 )/4 l
TWO SIGMA ERROR = 2((D3 -D)2+(92 -D)2+(93 0)2+(94.p)2)/3)1/2 i
j WHERE: D1 = the net mR of area 1 of the TLD, and similarly for i D2, D 3, and D4 D1
- Il K/R1-A 1
- 11
= the instrument reading of the field dose in area 1 i
l K = the known exposure by the Cs-137 source i
j R1 = the instrument reading due to the Cs-137 dose on area 1 i
i A = average dose in mR, calculated in similar manner j as above, of the transit control TLDs
! D = the average net mR of all 4 areas of the TLD.
i i
!O i
j 60 i
)
m m, _m.
j I
i 4
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i I
i 1 APPENDIX E
SUMMARY
OF EPA INTERLABORATORY COMPARISONS 1
I i
8 r
i
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]
1 4
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i 0
f 1
l 5
t 4
i i
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t i 61
}
EPA INTERIABORATORY COMPARISON PROGRAM Teledyne Brown Engineering participates in the EPA Interlaboratory Comparison Program to the fullest extent possible. That is, Teledyne participates in the program for all radioactive isotopes prepared and at the maximum frequency of availability. In this section trending graphs (since 1981) and the 1994 data summary tables are presented for isotopes in the various sample media applicable to the Shoreham's Radiological Environmental Monitoring Program. The footnotes of the table discuss investigations of problems encountered in a few cases and the steps taken to prevent reoccurrence.
O l
O 62
-a em, ,a-.- - ~ .
-s - - - -- --
i J
EPA INTERLABORATORY COMPARISON PROORAM 1994 i Environmental
- Collecuon Teledyne
- Date Media Nuclide EPA Result (a) Isotopes Result (b) Deviation (c)
J l 01/14/94 W ater Sr-89 25.0 i 5.0 24.00 i 1.00 -0.35 Sr-90 15.0 1 5.0 15.67 i 1.53 0.23 e
l 01/28/94 W ater Gr-Alpha 15.0 1 5.0 21.67 1 0.58 2.31 (d)
] Gr-Beta 62.0 1 10.0 72.33 i 3.79 1.79 1
02/04/94 W ater I-131 119.0 1 12.0 110.33 1 0.00 -1.30 l l 02/11/94 Water Ra-226 19.9 i 3.0 21.00 1 1.00 0.64 j Ra 228 14.7 1 3.7 15.67 i 1.53 0.45
- 03/04/94 W ater H3 4936.01 494.0 4833.33 1 152.75 -0.36 i
04/19/94 Water Gr Beta 117.0 1 18.0 102.67 1 6.43 -1.38 i
Sr-89 20.0 5.0 19.00 i 1.00 -0.35 Sr-90 14.0 1 5.0 13.00 0.0) -0.35 CW 20.0 5.0 23.67 i S.21 1.27 i Cs 134 34.0 5.0 34.00 1.73 0.00
- Cs-137 29.0 t 5.0 34.00 1 2.35 1,73
- Gr-Alpha 86.0 22.0 78.00 3.00 -0.63
- Ra-226 20.0 3.0 15.67 1.53 -2.50 (e)
Ra-228 20.1 5.0 15.33 0.58 -1.65
~
i 06/17/94 W ater Ra-226 15.0 2.3 15.33 0.58 0.25 l Ra 228 15.4 1 3.9 16.33 1.53 0.41 i
l Footnotes:
l (a) EPA Results-Expected laboratory precision (1 sigma). Units are pct / liter for water and milk j except K is in mg/ liter. Units are total pC1 for air particulate filters.
(b) Teledyne Results - Average i one sigma. Units are pC1/ liter for water and milk except K is in
! mg/ liter. Units are total pCi for air particulate filters.
(c) Normalized deviauon from the known.
i s (d) There appears to be variation in self-absorption matrix. The EPA confirms that the f composition of their tap water from Lake Mead, varies seasonally which can cause variation in alpha beta results. No corrective acuon required at this time since results are within t 3 i sigma control limits.
(e) No specific or apparent reason found. Data sheets verified and detector efficiencies i calibrated. Will exert extra care in making dilutions and using correct sample type on concentrauon of acids. Will check future samples to see if a pattem develops.
- O October 6.1994 63 1
O O O .;
EPA CROSS CHECK PROGRAM GROSS ALPHA IN AIR PARTICULATES (pg.1 of 1) oo 4
80 -
g >
UcL 40 - -
- {
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0 - -
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l l
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1981 1982 1983 1984 1985 1988 1987 1988 1989 1990 1991 1992 1993 1994 n 71 3 Sigma o EPA i 3 S'pa l
O O O <
EPA CROSS CHECK PROGRAM GROSS BETA IN AIR PARTICULATES (pg.1 of 1) 160 4
4 .
~
140 -
I I,
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3 "
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,, 2, i E t ., < > q i <
i ,[ j, <
i g, ,
40 -
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j i .
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5 0l -
1981 1982 1983 1984 1985 1988 1987 1988 1989 1990 1991 1992 1993 1994 1
- Sr2!V89 EPA test invalid.
e Tl 3 Sigma
- EPAi3 Syna
O O O .
a EPA CROSS CHECK PROGRAM STRONTIUM-90 IN AIR PARTICULATES (pg.1 of 1) 80 so -
i Q 4o . < > < - -
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) , ,
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. . . . - . - . . - _ _ , . . . . - . - . . - ~ . . . - . - - . - - - . . -- . . - _ - - - - - -...-. _-- -
O O O .
EPA CROSS CHECK PROGRAM CESIUM-137 IN AIR PARTICULATES (pg.1 of 1) 80 80 - , ,
j i
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-4 -
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< l. .
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(< l ,
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0 -- - -
4
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1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 a TI i 3 sigma o EPA i3 sigma 4
EPA CROSS CHECK PROGRAM STRONTIUM-89 IN MILK (pg.1 of 1) 100 go .
i i t l I 80 -
l
= ,,
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1981 1982 1983 1984 1985 1988 1987 1988 1989 1990 1991 1992 1993 1994 i
a Tl 3 sigma o EPA i3 sigma
O O O .
EPA CROSS CHECK PROGRAM STRONTIUM-90 IN MILK (pg.1 of 1) 80 l , , .
' '\ ' -
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i 1 1 4a .
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f q ,
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l
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1981 1982 1983 1984 1985 1988 1987 1988 1989 1990 1991 1992 1993 1994 i
n TI 3 sigma o EPA 13 sigma i
i
-. .. . . _ . . . - . - . . - - - - . - . ~. . - -_. .-. .
i i
1 I
EPA CROSS CHECK PROGRAM POTASSIUM-40 IN MILK (pg.1 of 1) 2800 2400 -
i 4
1 y . . .
4
- l 2000 , ,
1800 .
= ,
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, , s i o i 94ag t i s i . ..
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1200 1000 800 - - -
800 .
1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 o TIi3 sigma o EPA 13 sigma i
.i.
- i
?
I EPA CROSS CHECK PROGRAM IODINE-131 IN MILK (pg.1 of 1) 180 .
4 I 140 -
l l
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. 120 - , .
1 1 j@ = l lll
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- o gl ' ' '
,(E g g ,,
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l . . , ,
j 1981 1982 1983 1984 1985 1988 1987 1988 1989 1990 1991 1992 1993 1994 a TIi 3 sigma o EPA 13 sigma l
l l
l .
i r
l l
~
EPA CROSS CHECK PROGRAM CESIUM-137 IN MILK (pg.1 of 1) 100 i
l 80 -
si i ,
,e ,, . I . .
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i, ,
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- g *
[ W
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5 5
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5
- 5 5 5
- 5 ' t 1981 1982 1983 1984 1985 1988 1987 1988 1989 1990 1991 1992 1993 1994 o Tii 3 sigma e EPA 13 sigma I
- . . . . - . . . - . . . ~ . . . . . . _.~ ... _ _ .-. _ . _ _ .~ - ....- _ . - ........ ..- -- . ~ .. ..... - - . . . - . - - - . - - . . . . - _ - - - . . ~ . - .
I i
ei l
! EPA CROSS CHECK PROGRAM GROSS ALPHA IN WATER (pg.1 of 1) 180 j 180 - i 140 -
120 -
100 - -
<> g b <>
, 80 - 1 1 < ,
E h
y <
" U i 60
- l l -
L a E< > ,I i i l i i l 4 > l l
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l ,, ; ,
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l g jl ' - 1 1 i l l
l ,
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1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 !
I e TI i 3 Sigma o EPA i 3 Swjma 6
I 5
+
l 4
l
" - - ' - ' ^ ^ ^
a 4.h A Ju. 4s t-A. -w E A . w.4544 Amm a h-4 & Mw atmm =,. m A d@A. 444. dL 4.444.h. shu.4 A A..@-h nh t W ee t N ALawC'-'- . &Ahensk .. 4 4.L h &4&dh. 6 *%-4tM-he 44M W M EMA.A4A h Medt.. 4 4 .m Ae4 ahmW A. mis h
- A. A m m = h =amG.L A4 m_ &_.
O O O .
EPA CROSS CHECK PROGRAM ,
GROSS BETA IN WATER (pg.1 of 2) ,
im -
i l i
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, , o 140 - t - -
9
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0 -
i
' L I - w g y g g w g w 1981 1982 1983 1984 1985 1986 i
lD Tli3 sigma
- EPA 13 sigma
O O O .
EPA CROSS CHECK PROGRAM GROSS BETA IN WATER (pg. 2 of 2) eso ,
220 -
180 -
5 140 -
I
~
- = , , < >
q 5
\ 5 ~
~
g . . q
- ' ' ' ' ' E l g' ,
,o . .
+.
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b , , t, l E E E E
- g w w g w w g w w g w 1988 1987 1988 1989 1990 1991 1992 1993 1994 1995 l5 Tli3 Sigma o EPA i3 Sigme l
t .
l I
i i
l EPA CROSS CHECK PROGRAM TRITIUM IN WATER (pg.1 of 2) !
i 5000 l l !
I
, t l
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j 4000 - .
, n . ,
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a < ..
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t 1
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1981 1982 1983 1984 1985 o Tli 3 sigme o EPA 13 supme
?
4 i
m as-E5w.4% am Ar-- .. gM-w -b. am . Ammas &. h W A ,a,M 46 6.E a a u i 4. Aes A m 4.eaga, SSGh6=&--ben.4 h" - " 146ahEha. -W MW & MD =AM .S s e4&h44AMm &- 4W h 4b A k DJ Am h aush% man s. &&ah4 M.Ag n 4 a> EL AA a wh & aba w as ,,3.4 4.k A6 M A a W4 h4hhm O m E.A4ahahA&-h Ah. 4-2 A4 A-C 4 4
I EPA CROSS CHECK PROGRAM TRITIUM IN WATER (pg. 2 of 2)
- 18000 l
14000 -
i E .,
, E
. 12000 -
10 M -
t I 6
2 sooo -
[ ,,
i I a i N 2 ,, E N o
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6000 - <
l l l 4
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i j I -
<, g < g -
g
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w w w g y w g w g g v g w w g w g y w g y w g 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 l e Tli3 %
- EPA 13 Sigma v
i
_.. _. .__ _._..._...._ _._ _ ___ _____ _ __._ _ _ - - _ ~._.._.. _ . _ _ _ __._. -- - __.._ _ _
i i
I EPA CROSS CHECK PROGRAM IODINE-131 IN WATER 160 -
i 140 -
120 -
a l l <> I I l l
' t -
100 - - .
E ,
< i i ..
80 - ' '
1 1 e .
y U l ~
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, g.. o o
, o ,
40 - <
i l
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y y o .
20 .
< > D< > -
l >
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"o n ti n 0 - - -
-20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995
, a a Tl 13 Sigma e EPA t 3 Sigms j ,
r 5
I
-. - - .- -. _ . - .~ _.. _. - - . - .- - - .. .. - - - - - ._ -
. ~ . _ _ ~ . - -
- - . . . . - . . . . . - . . - . . . . - . . . . . . . ~ .
O i
EPA CROSS CHECK PROGRAM '
COBA1.T-60 IN WATER (pg 1 of 2) t
~
I L l 100 i
< i 80 - , ,
\
i < l , ,
- < i
>i i 80 - -
i m.
.e.
y 2 40 -- < -
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1981 1982 1983 1984 1985 1986 1G87 1988 4
e Tli3 sigma o EPA 13 sigma i
u 9
1
~ . - - _ . . . _ _ _ - . _ _ . . _ - _ _ _ . _ _ _ . _ _ _ _ _ _ _ . _ _ _ . - . - _ - - -___-- - - - ----_ - - - - + - . -_ - _ - __ - - _ _ _ _ _-_ - -
m.....__._._.._.._..._.....-_...____.__._._.-_.--.~.....___._.._m...___.._.__.____ _ _ . . . . _ _ . _ _ . . _ _ _ _ .
O O 3 c EPA CROSS CHECK PROGRAM COBALT-60 IN WATEFI (pg. 2 of 2) 100 go .
l l 80 .
' '1 1 ,,
i l 1
m.
- >i l oo i i ' -
o 40 - <
'l l , l 6a.
i
't i i il l , 1 1 - - < >, ,
,, < > < ,tr , ,
20 - i ' '
>E i 'E t' -
< i
,j l >f ,1-
, ,E ,
0 -
4
-20 , , . .
1988 1989 1990 1991 1992 1993 1994 1995 a Tii 3 Sigma o EPAi 3 Segme b
i EPA CROSS CHECK PROGRAM CESIUM-134 IN WATER (pg.1 of 2) 100 90 - ,
I "
80 - '
- n. t
.o.
1 i
l '-
3 2 m . . . < <- -
O
- - 1
< i . , .
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g
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f l ., I m .
0 - - { .~
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1 i APPENDIE F
,i REMP SAMPLING AND ANALYTICAL EXCEPT10NS i
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! TABLE F-1 l l }
l REMP Exceptions for Scheduled i Fish Sampling and Analysis During 1994 1
l Date of Reason (s) for ,
Imcation Description Sampling IAss/ Exception SCI Bluefish 05/23/94 Bluefish were not present 13G2 05/16/94 during sampling.
14C1 05/19/94 14C1 05/24/94 l
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APPENDIX G 4
SNPS LAND USE SURVEYS i
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'lte REMP Land Use Census was not conducted in 1994 due to Revision 1 to the SNPS ODCM (Document Change Notice No. 93XO24) which revised the annual land use census requirement to every two l
j years. .
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- I 1________ _ _ _ . . . _ _ _ ._ _ _ . _ _ _ _ .
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O APPENDIX H COMMON AND SCIENTIFIC NAMES OF SPECIES COLLECTED IN THE REMP ll O
O 92 n.., ., , -,
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4 i
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! TABLE H-1 i
lO
'I COMMON AND SCIENTIFIC NAMES OF SPECIES COLLECTED IN 'IEE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i
i Common Name Scientific Name i
fish 1
i Winter Flounder Pseudopleuronectes americanus Windowpane Sconhthalmus. acuosus
{ Searobin Prionotus ADD-i Little Skate Baia erinacea i
4
- Invertebrates l American kbster Homarus americanus i
1 Channeled Whelk Busvcon canaliculata
!O 4
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i 1
1
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93
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