SNRC-1807, Shoreham Nuclear Power Station Operational Radiological Environ Monitoring Rept 1990

Shoreham Nuclear Power Station Operational Radiological Environ Monitoring Rept 1990

ML20081E844
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	12/31/1990
From:	Leonard J LONG ISLAND LIGHTING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
SNRC-1807, NUDOCS 9105020226
Download: ML20081E844 (134)

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/E@@ ll LONG ISLAND LIGHTING COM PANY awateta w mamamp,} SHOREH AM NUCLEAR POWER STATION P.0, DOX 610, NORTH COUNTRY RO AD

• W ADING RIVER. N.Y.11792 JOHN D. LF.ON ARD, JR v1CE PRESIDENT OFHCE OF CORPORATE SERV 4CES ANO VICE PRESIDENT OFFICE OF NUCLE AA SNRC-1807 1

APR 2 9 991 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Radiological Environmental Monitoring Program Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322 Gentlemen:

Enclosed is a copy of the Shoreham Radiological Environmental Monitoring Program (REMP) Annual Report which provides detailed information for the full 1990 calendar year. Shoreham was in a defueled, non-operating condition during all of 1990. Shoreham's Technical Specification 6.9.1.6 requires this report to be submitted prior to May 1, 1991.

If you require additional information, please do not hesitate to contact me.

Very tru?.y yours,

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y' ((h td conard, Jr. / N Vicet President, Office /pf Corporate Services ansL/Vice President, Of'f' ice of Nuclear MAP /ab.

Enclosure cc: S. Brown T. T. Martin B. Norris 40l

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il il ll SHOREHAM NUCLEAR POWER STATION OPERATIONAL-ll L RADIOLOGICAL ENVIRONMENTAL ll MONITORING PROGRAM l

l ANNUAL REPORT

JANUARY 1 TO DECEMBER 31,1990 ISSUED BY NUCLEAR ENGINEERING DEPARTMENT ENVIRONMENTAL ENGINEERING DEPARTMENT il ,

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l SHOREHAM NUCLEAR POWER STATION OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1990 ANNUAL REPORT I JANUARY 1 to DECEMBER 31,1990 I

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l LONG ISLAND LIGHTING COMPANY and TELEDYNE ISOTOPES April 15,1991 I

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l TABLE OF CONTENTS PAGE E XE C U TIVE S U M MARY . . . . . . . .. .. .. .. .. . .. . . .. .. . . . . . . . . . . . . . . . . . . . . . .. ... .. . . . . .. .. .. .. . . . .. . . . . . . .. . . .. .. . .. .. . 1

1. 'IIIEPROGRAM............................................................................................................4 A. Ob,Jectives..............................................................................................................5

-g a S am pl e C 011 e c ti o n .. .. . . . . .. .. .. . . . .. .. .. .. . . . . .. . . . . . .. .. .. .. . . . . . . . . . . . . . . . .. . . .. . . . . . . . . . . . .. .. .. .. .. .. . .. .. . 6

1. Aquatic Envimnment. . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . 6 l 2. Atm osph eric Envimnm en t. . . . .. . . . . . .. . . . . . . .. . . . . . .. . . . . . .. . . . . .. . . . . . . . .. . . .. .. . . . .. .. ... . . 6

3. Tenestrial Envimnmen t. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 I 4. Direct Ra d i n t1on. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .!

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C Q u ali ty Ass u ran ce . .. . . .. . . . . . . . . . . .. . .. . . .. . . . . . . .. . . . . . . . . . . . . . .. . . .. . . . . . .. . . .. . . . . . . . .. . . . . . . .. . . . . . . .. . .. .. . 7 D. Data Interpre tation . . .. . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 l 1. Genera 1.........................................................................................................8

2. Gamma Isotopic Analyses. .. ... . . . .. ... .. .. .. .. . .. .. . .. . .. .. ... ..... . . .. ... . . . .. .. . .. .. . . . .. . . . . 8 E. D o s e As s e s s m e n t . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

F. Pro gr am S u mm ary . . . .. . . .. . . .. .. .. . . . .. . . . . . . .. . . .. . .. . . . . .. . . . . . . .. .. . . .. . . .. .. . .. . . . . .. .. . . .. .. . .. . . .. . I 1 I1. RE S U LTS AND D I S C U S S I O N . . . . . . . . . . . . . .. . . . . . . . . . .. . .. . . . . . . . . . . .. . . . . . . . . . .. .. . . . . . . . .. . . .. .. . . . . . .. . . 1 4 l A. Aquatic Envimnment. . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 5

1. Surface water. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

2. Fish.............................................................................................................15 g 3. Invertebmtes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

4. Sediment...................................................................................................16 l H Atmos ph ede Em'imnm en t. . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 6

1. Airbo rn e Parti c ul at e s ... .. .. .. ....... .. .. .. .... ... .. ...... .. . .. .. .. .. .. .. ..... .. ..... .......... .. 1 6

2. Airbam e lodine. . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . .

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l TABLE OF CONTENTS (Cont.)

I C. Temstrial Em'imnm ent. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 7 g 1. Milk.....................................................................................................17 l 2. Potable Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 8

3. Fo o d Pr od u e t s .. . .. .. .. . . . . . . . . . .. .. .. .. . . . .. .. . . .. .. .. . . . . . .. . . .. .. . . . . .. . . . . . . . .. .. . . . . . .. . . . 1 8 D.

I D i r e c t Ra d l a ti o n .. . . . .. . . .. .. . . .. . . . .. . . .. . . . . . . . . . . . .. .. . . . . .. . . .. . .. . . . . .. .. .. .. . .. . . .. . . . . . . .. .. . . . .. . 1 8 q

E. Dose Assessment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 9 I III, C O N C LU S l O N S . .. . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 5 l IV. RE FE RE N C E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . .. . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . 2 7 I APPENDIX 4 - Radiological Environmental Monitoring ......................... 30 Program Summary - 1990 I APPENDIX B - Sample Designation and Sampling Locations ............... 38 AP P E ND IX C - D a ta Tabl e s ... . . . . . . . . . . ... . . .. .. .. .. .. .. . . . .. . . .. . . . . . . . . . . . . . . . . . .. . .. .. .. .. .. .. . . . .. . .. . . 4 7 APPENDIX D - Analytical Procedures Synopsis ......................................... 7 2 APPENDIX E Summa:y of EPA Interlaboratory Comparisons ...........,86 APPENDIX F - REMP Sampling and Analytical Exceptjons ...............105 APPENDIX G - SNPS Land Use Surveys .....................................................,1 14 I APPENDIX H - Common and Scientific Names of Species..................121 Collected in the Radiological Environmental Monitoring Program AP PE ND IX I - 1 9 8 9 E rra ta . . . . . . . . .. .. . . . . . . . . . .. .. . . . .. . . .. .. .. . . .. . . . .. .. . . .. . . . .. .. .. . . . . .. . . ... . . .. . . 1 2 3 I

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LIST OF TABLES g PAGE N.(h TITLE I 1. Synopsis of the Shoreham Nuclear Power Stadon's .....................................12 Operational Radiological Environmental Monitoring Program I 2.

for the Period January 1 through December 31,1990 Summary of Dose Determinauon for 1990.......................................................24 Appendix A - Radiolocleal Environmental Monitoring Progam SummaJv 1990 A1 SNPS REMP Summary Jan. I to Dec. 3 1, 19 9 0 . .. .. .. . .. .. . . . . . . . .. ... . . .. . .. .. . . . .. . . .. . . . 3 1 g

Appendix B - Samnle Deslenation and Sampling Ix> cations

............ 4 0 B1 Sample Locations Required by SNPS Offsite Dose...........................

Calculadon Manual B2 Airborne Particulate and Airborne lodine Monitoring Stations............... 42 l B3 B4 Waterborne Monitodng Stations... ...... ........ . ....... ........................ . .... .. . . .... .. .. .. . ...... 4 2 1 n ge s ti o n M o nit o ri n g Stati o n s ................ ..................................................... .......... 4 2 B5 Diree t Radiation Mo nitorin g Statt on s ................................................................. 4 3 I Mendir C Data Tables.

Acuatic Environment I 90................... 48 C-1 Concentrations of Tritium Strondum-89 and Strontium I and Gamma Emitters in Surface Water Samples Concentradons of Strontium-89 and Strontium-90 and Gamma............ 4 9 C-2 Emitters in Fish Samples l

C-3 Concentrations of Stronuum 89 and Stf ontium-90 and Gamma............ 50 l C4 Emitters in Invertebrate Samples Concentrations of Strontium-89 and Strontium 90 and Gamma............ 51 Emitters in Sediment Samples I iii i

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ECL '"ITLE PAGE I I Atmospheric Environment 3

C5 Concentrations of Gross Beta Emitters in Weekly Airborne...................... 52 Particulate Samples e C-6 Concentrations of Strontium 89 and Strontium 90 and ........................... 5 5 Gamma Emitters in Quarterly Composites of Airborne Particulate Samples I C-7 Concentrations of Iodine-131 ?n Air Cartridge Samples.........................

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Terrestrial Environment i C-8 Concentrations of Iodine 131 in Milk Samples........................................... 6 0 C-9 Concentrations of Strontium-89 and Strontium 90 and Gamma......... 61 Emitters in Milk Samples C-10 Concentrations of Tritium. Iodine-131 and Gamma Emitters in......... 65 Potable Water Samples I C 11 Concentrations of Gamma Emitters and I 131 in ..................................... 6 6 Food Product Samples Direct Radiation C-12 Direct Radiation Measurements - Quarterly TLD Results........................ 67 Lower Limits of Detection

. C Typical LLDs Achieved for Gamma Spectrometry ........................................ 6 9 C-14 LLDs and Reporting Action Levels Required by Offsite .............................. 7 0 I Dose Calculation Manual and 1990 Contract I

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LIST OF TABLES (Cont.)

M TITLE PAGE Appendir F

( REMP Samo11nst and Analvtical Exceptions I F-1 REMP Exceptions for Scheduled Fish sampling...............................106 and Analysis During 1990

-3 F-2 REMP Exceptions for Scheduled Invertebrate Sampling..............107 l

• E and Analysis During 1990 l

1 I F-3 REMP Exceptions for Scheduled Airborne Particulates.................108 Sampling and Analysis During 1990

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l F4 REMP Exceptions for Scheduled Airborne Iodine............................109 I- Sampling and Analysis During 1990 i

F5 REMP Excepuons for Scheduled Milk Sampling..............................110 I and Analysis During 1990 F6 REMP Exceptions for Scheduled Food Products...............................111 Sampling and Analysis During 1990 F-7 REMP Exceptions for Scheduled Potable Water Sampling............112

,l and Analysis During 1990 F-8 REMP Exceptions for Scheduled Waterborne sediment...............113 ll from Shoreline Sampling and Analysis During 1990 Aenendir G I SNPS Land Use Survers l G-1 REMP 1990 Land Use Census Nearest Milk Animal ........................117 G-2 REMP 1990 Land Use Census Nearest Garden ..................................1 18 G-3 REMP 1990 Land Use Census Nearest Residence............................119 I Anoendir H O

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H-1 Common and Scientific Names of Species Collected.......................122 in the REMP v

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1. Average Weekly Gross Beta Results in Airborne Particulates................... 20 l 2. Comparison of Average Monthly Gross Beta Results in Airborne............ 21 Particulates (February 1977 - December 1990) l 3. Comparison of Average TLD Results (February 19 7 7 December 1990)

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I APPENDIX B SAMPLE DESIGNATION AND SAMPLING LOCATIONS I LIST OF MAPS B-1 Sh o r e h am S i t e to c a ti o n ... .. .. .. .. .. . . ... .. . . .. . . .. . . . . ... . . .. .. .. .. .. .. .. . . . .. . . . . .. . . .. . . . .. .. .. .. . . . . . . . .. . . . . . 4 4 B-2 On Si t e S ampl in g Loca tio n s ...... .... .. .. ... .. .. .. .... ..... .. .. .. .. .. ..... .... .. .. ...... ... .. .. .. .. .. .. . .. .. .. . 4 5 B-3 O ff Site Sam plin g Locatio n s .. .. .. .. .. .... ... .. .. .. .... .. ... .. ...... .. .. ..... .. .. .. .. .. .. .. . .. .. .. .. ... . ... . . . .. 4 6 I

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I EXECUTIVE

SUMMARY

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lI EXECUTIVE

SUMMARY

This report summarizes the Shoreham Nuclear Power Station's I (SNPS) Radiological Environmental Monitoring Program (REMP) for 1990.

Throughout 1990, the plant was in a defueled condition with all fuel rods removed from the reactor core, awaiting NRC approval of LILCO's request for l a Possession Only License (POL) and for transfer of the plant license to the Long Island Power Authority (LIPA). Consequently, the SNPS REMP scope was reduced from the level in effect prior to full power operation to the l normal Technical Specification scope (Sections 3/4.12 and 6.8.4.e). This reducuon began on January 1,1990.

I The objective of the operadonal REMP is to idenufy and measure plant related radioacuvity in the environment and calculate the potendal dose to the surrounding populauon. The operational phase uses the preoperational I baseline data to identify plant contributed radiation and evaluates the possible effects of radioacuve plant efnuents on the environment. The SNPS REMP is designed to comply with the plant's Technical Specificadons, Offsite Dose Calculation Manual (ODCM) and NRC Regulatory Guides.

The REMP data is acquired by sampling various media in the environment which are then analyzed for any radiauon present. Media I sampled within the aquade environment in 1990 included surface water, fish, invertebrates (squid, lobsters, etc.) and sediment. The atmospheric environment was sampled for airborne particulates and airborne lodine.

I Milk, potable water, and food products were obtained from the terrestrial environment. Direct radladon was measured using thermoluminescent dosimeters (TLDs).

I Radioacuvity in environmental media varies from sample to sample as well as geographically therefore, a number of sampling locadons for each l medium were selected using available meteorological, land and water use data. Sampling locations are designated as either indicator or control locations. The indicator locations are placed close enough to Shoreham so l that plant contributed radioactivity will be at its highest concentradon. The control sample locadons are placed so that they will be beyond measurable influence of Shoreham and any other nuclear facility. An exception to this I occurred at the onshore site for REMP location 13G2, at the entrance to Port Jefferson Harbor. During preoperadonal testing aquatic samples revealed the presence of low levels of lodine-131. An invesugauon revealed I that the lodine-131 was from area hospitals treaung padents for thyroid carcinoma. Thereafter, unul 1990 a second onshore aquatic background locadon was sampled at the entrance to Mt. Sinal Harbor.

A number of radioanalyses were performed on each medium sampled.

All samples did not undergo all types of radioanalyses; only those analyses appropriate for the particular medium were performed. The analyses I included gamma spectrometry, stronuum-89 and -90, lodine-131, tridum, gross beta radiation and direct radiation.

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I Dose calculations for the SNPS environs were performed using g positive concentrations of radioactivity detected in the samples collected.

In all cases the calculated doses were similar to the background doses calculated for the previous years. Therefore, no environmental radioactivity was identifled as having originated from SNPS.

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I I. PROGRAM I

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THE PROGRAM The Shoreham Nuclear Power Station's (SNPS) Radiological Environ-I mental Monitoring Program (REMP) is conducted in compliance with NRC Regulatory Guide 4.15, lleensing commitments, LILCO's Updated Safety Analysis Report (USAR) 11.6, SNPS Technical Specification Section 6.8.4.e, I 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) 6.1.5.

I All samples were collected by personnel of the Long Island Lighting Company (Environmental Engineering Department) or biological contractors hired for the collection of aquaue 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 1990 sample analyses were performed by Teledyne Isotopes (TI) of Westwood, New Jersey (referred to throughout the text as "the labo-g ratory") under contract to LILCO. A summary of analytical results appears in g APpendix A and indMdual analysis results in Appendix C. Aquatic sample co!!ccuans were performed by Lilco's Environmental Engineering Department and Energy & Environmental Analysts Inc. (EEA Inc.) under l contract to LILCO.

A Objectives The objectives of the operational radiological environmental monitor-g ing program are:

1. Identify and measure radiation and radioactivity in the plant erwi-rons for the calculation of potential dose to the 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, have not been substantially underestimated and are I consistent with applicable standards.

4. Comply with regulatory requirements. SNPS Technical Spect-I fications and ODCM requirements, and provide records to document compliance.

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H Sample Collection l

1. Aquatic Environment The aquatic emdronment at the SNPS site was examined by ana-lyzing samples of surface water, fish, invertebrates, and sediment.

Surface water samples were taken at three locations in May and I October using a Niskin bottle. The samples were placed in new polyethylene bottles following three rinses with the sample medium prior to collection. Samples of Winter Flounder (Pseudopleuronectes I americanusl, Windowpane (Sconhthalmus acuosus), Searobin (Prionotus spn), Little Skate (Egla erinaceal and Fluke (Paralichthys dentatus) were taken by trawl, sealed in plastic bags, frozen, and I shipped to the laboratory for analysis.

Invertebrate samples of American Lobster (Homarus ameri-canus), Squid (Loligo pealett) and Channeled Whelk (Busycon canaliculata) were collected by trawl. Channeled Whelk were also collected using pots. These invertebrate samples were sealed in plas-l tic bags, frozen and shipped to the laboratory for analysis, Beach sediment samples were also collected, scaled in plastic

.g bags, frozen and shipped to the laboratory,

2. Atmospheric Emironment g

The atomspheric emironment was examined by analyzing air-borne paruculates collected on Gelman Type A/E filters using low I volume air samplers (approximately 1 cfm). Airborne lodine was collected by absorption on triethylenediamine (TEDA) impregnated charcoal cartridges, manufactured by Scott, which were connected in I series behind the airborne particulate filters. The samplers used were equipped with a vacuum recorder for sample volume correction to ensure sample validity and to indicate any maintenance problems.

I Should the sampler lose vacuum due to a leak the vacuum level reading will drop to zero. Since this may occur without a corresponding loss of electric supply the exact time of the maintenance proalem will be l evident on the vacuum recorder chart.

I Sample volumes were measured using dry gas meters and cor-rected for differences between the actual pressure seen by the volume meter and the average atmospheric pressure. Sample volumes are I corrected to standard pressure using average weekly barometric pres-sure (measured at En ironmental Engineering Department, Mehille) and air sampler vacuum readings. Time totalizers indicate the dura-tion of time the sample was taken.

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3. Terrestrial Environment The terrestrial environment was examined by analyzing samples of milk, potable water, and food products. When available, milk I samples were collected from three locations monthly, except during the pasture season (May through October) when the sampling was increased to twice a month. Milk samples were shipped on ice with I sodium bisulfite (NaHSO3) preservative added. Potable water was col-lected quarterly from three well locations. However, samples were unavailable from a fourth well 1352 presumably due to a change in the I water table. Food products consisting of vegetables and fruit were collected from area farm stands and shipped fresh to the laboratory.

I 4. Direct Radiation l Direct radiation levels in the environs were measured with energy compensated calcium sulfate (CaSO4 :Dy) TLDs, each containing four separate readout areas. The TLDs are annealed by LILCO prior to l placement in the field. TLDs were placed at each of 41 locations and exchanged on a quarterly cycle. These 41 units include 4 add!Uonal TLDs that were added in 1989 at various area schools to better I determine direct radiation levels at these sites. The units were then packaged and shipped to the laboratory for analysis along with a control dostmeter.

C Ouality Assurance

1. Teledyne Isotopes g

Teledyne Isotopes (TI) has an extensive quality assurance program designed to ensure the precision and accuracy of the data I generated. An Interlaboratory Comparison Program is conducted with the Environmental Protection Agency (EPA). The results of the Pro-gram analyses are listed in Appendix E. Participation in this program I- permits esumadon of bias in TI results from the deviation from the "known" value given, or by comparison with means of all participants.

The TI Quality Assurance Program for Radiological Monitoring is I described in various TI publications (references 15, 16, 17).

Approximately 10 percent of TI's total analytical effort is spent l on quality control including process quality control, instrument quality control, intra and interlaboratory cross-check, and comprehensive data review, in addition, LILCO specifically requires that two percent l of its analyses be duplicated for further quality control cross check.

Additional information on the LILCO Quality Assurance Program l 1s provided in NED 4170004, Quality Assurance Program for Radio-I l 1

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I l3 locical Environmental Monitorinc Procram. Shoreham Nuclear Power

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lE Etationi I D. Data Interpretation l 1. General The analyucal data generated during the program are routinely I evaluated by the TI project leader who is the liaison with Long Island Lighting Company's Emironmental and Nuclear Engineering Depart-ments. Several factors are important in the interpretation of the data.

I These factors are discussed here to avoid repettuon in secuons that follow.

I Within the data tables (Appendix C) an approximate 95 percent (t2 sigma) confidence interval is supplied for those data points above the lower limit of detection (LLD). These intervals represent the I range of values into which 95 percent of repeated analyses of the same sample would fall. Tables C-13 and C-14 present typical and required LLD's, respectively.

l Resulta for each type of sample were grouped eccording to the analysis performed. Means and standard deviations of these results are calcu ated when applicable. The calculated standard deviations of I grouped data represent sample rather than analyucal variability. For these calculations any values below LLD are considered to be at the LLD. .As a result, the means are biased high and the standard devia-l tions are biased low. When a group of data is composed of mainly LLD values, averages are not calculated.

l Grab sampling is a useful and acceptable procedure for taking environmental samples of a medium-in which the concentration of radionuclides is expected to vary minimally with time or where inter-I mittent sampling is deemed sufficient to establish the radiological characterisucs of the medium. This method, however, is only repre-sentative of the sampled medium for that specific location and instant I of time. As a result, variation of radionuclide concentrations in the samples will normally occur. Since these variations will tend to coun-terbalance one another, the extracdon of averages based upon repeti-uve grab samples is valid.

2. Gamma Isotopic Analyses SNPS ODCM Table 3.12.1-1 requires that analyses be performed on all media for gamma emitting radionuclides which may be I attributable to effluents from the plant. These analyses are in addition to requirements for specific gamma emitters such as I-131, Cs-134.

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Cs 137, Ba 140, Mn 54 Fe 59, Co 58, Co 60, Zn-65, Zr 95 and Nb-

95. industry experience suggests that these are the most likely radionuclides to find their way into the environment from a BWR lI nuclear- power plant, Gamma spectroscopy is expected to idenufy most other nuclides which may be discharged when the LLD's for specified gamma emitters are met by this technique.

Tables 3.1 and 3.2 of the Shoreham Final Environmental Statement list the calculated liquid and gaseous effluents by I radionuclide in curies per year. These release rates assume normal operation of the plant, including anticipated operational occurrences.

Those nuclides listed in Tables 3.1 and 3.2 which are not routinely l observable by gamma spectroscopy and which are not specifically analyzed in other ways fall into two categories:

I 1. Those radionuclides with half lives on the order of hours or minutes which cannot accumulate appreciably in the environ-I ment (Na-24, Cu 64, Zn 69m, Zn 69, Sr 91, Y-91m, Y 92, Y-93, Tc 99m, Rh 103m, Rh 105, Rh-106, Te 129. Te 131m, Te 131, I 132,1 135. Ba 137m, Pr 143, Cc 143, Pr-144 and W 187).

2. Those radionuclides with no gammas (P-32 Fe 55), those I with a trivial percentage of their transitions going by gamma emissions (Y 91), or those with their primary gamma occur-ring at such a low energy and at such low abundance that it is

-3 not routinely observable in the presence of other gamma 3 activity (Nd-147). With only 10 pCi of Nd-147 calculated to be released per year in Shoreham's liquid effluents, the nuclide cannot be an important contributor to dose.

E. Dese Assessment l The methodology for determining doses is similar for all pathways. Laboratory analyses from the REMP for each sam?le type are compiled. Data from all locations taken on the same c ate are I averaged to obtain the most reliable approximation of the radioactivity concentration on that date for that sample type. The averages of all dates are then taken to provide the best approximation of radioactMty l concentrations for the year.

When an average value has been obtained which represents a I sample medium or an exposure pathway, it can then be used to calculate the dose for the year. Additional informauon, such as the quantity of fish, milk, vegetables, etc., consumed per year by the I maximum exposed indMdual is also needed to calculate the total dose (reference 13).

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___-_m.__- - - _ _ _ _ ._ _. --i-w------ -.--

.I The dose due to direct radiadon exposure is monitored by TLDs, l The laboratory results for TLD's are expressed in dose units directly and do not require any additional calculations.

l The dose to the total body or to a specific organ is then calculated by the product of the radionuclide specific dose conversion factor for its applicable exposure pathway, the environmental sample I radionuclide concentration, and the ingestion or inhalation rate of the sample or medium of interest. For example, the following general equation expresses this principle:

I Dose = Concentration X Quantity ingested X Dose factor

.g (mrem /yr) per sample per year i

lg3 The sample concentration is typically expressed in pCl/l or pC1/kg. For the ingestion pathway, the quantity ingested or consumed er year is expressed in kg/ year or 1/ year. Finally, the dose conversion ctor is expressed in terms of mrem /pCl ingested or inhaled.

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,( F. Program summary Table 1 summarizes information on the REMP as performed g during the period of this report, January 1 through December 31, 1990. During this reporting period 1.153 analyses were performed on 823 environmental samples. Appendix A summarizes the analytical I 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 I coding system, which specifies sample type and relative locations at a glance. In addition, pertir at inlormation on individual sampling locations, and maps which show their geographic location, are

,I included. Appendix C presents the analytical results of the Shoreham Nuclear Power Station's Radiological Environmental Monitoring Program for the period January 1 through December 31, 1990.

Appendix D contains a synopsis of the analytical procedures used in I the REMP. Results of the EPA interlaboratory comparison program can be found in Appendix E. Appendix F lists the program exceptions for 1990, and Appendix G reports the land use surveys performed by I LILCO's Environmental Engineering Department during 1990 in the vicinity of the SNPS. Common and scientific names of species collected in the program are presented in Appendix H. Appendix 1 contains errata from the 1989 REMP Operating Report submitted in l_ May 1990.

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'M M M M M M M M M M M M M M M M M TABLE 1 SYNOPSIS OF'TIIE SilOREllAM NUC1 EAR POWER STATION'S OPERATIONAL HADIOIDGICAL ENVIRONMENTAL MONITOldNG PROGRAM FOR 111E PERIOD JANUARY I T11ROUCII DECEMBER 31.1990 SAMPLE SAMI~ LING NUM!!ER ANALYSIS NUMBER TYPE LOCATIONS CollEf!ED ANALYSIS FREQUENCY PERFORMED FREQUENCY Aquatic Environment Surfan Water Semlannual 3 6 1-131 Semtannual 6 11-3 Semiannual 6 Gamma Semiannisal 6 Sr-89 Semlannual 6 Sr-90 Semiannual 6 Fish Semlannual 3 27 Gamma Semlannual 27 Sr-89 Semlannual 27 Sr-90 Semlannual 27 Invertebrates Semiannual 3 15 Gamma Semiannual 15 l Sr-89 Semiannual 15

- Semiannual 15 ru Sr-90 l i

Settiment - Beach Semlannual 1 2 Gamma Semlannual 2 Sr-89 Sem1 annual 2 Sr-90 Semiannual 2 Atmospheric Environment Airborne Partleulates Weekly 5 264 Gross Beta Weekly 264 Gamma Quarterly 20 Sr-89 Quarterly 20 Sr-90 Quarterly 20 l

Airborne lodine Weekly 5 264 1-131 Weekly 264 l

i i

TABLE I (Cr>nt !

SYNOPSIS OF TIIE SIIOREllAM NUCIEAR POWER STAT 10FTS OPERADONAL RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM FOR 'IllE PERIOD JANUARY I T11ROUCII DECEMBER 31.1990 i

l SAMPtE SAMPLING NUMilER ANALYSIS NUMIJER l 'IYPE FREQUENCY IDCATIONS CO1JEMD AN U,YSIS FRF4)UENCY IEIFORMED l

l Terrestrial Environment l

Milk Ulweekly (1) 3 52 1-131 Utweekly (1) 52 Gamma Etweekly (1) 52 Sr-89 Montidy 33 Sr-90 Monthly 33 Potable Water Quarterly 3 11 Camma Quarterly II I-131 Quarterly 11 11-3 Quarterly 11

[ Forx1 Ihlucts Annual (2) 5 18 Camma AnnuaDy 18 I-131 AnnuaDy 18 Direct Radfauon

'ILDs Quarterly 41 164 Gamma Dme Qu sterly 164 (1) Milk is n>llected btweekly during the pasiure season (May through October) arxl monthly durink the nongrazing season.

(2) When milk samples are discontinued food product samples are collected monthly during harvest. If necessary, to comply with SNIS OIIstte Dose Calculauon Manual 3.12.1.

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I I II. RESULTS AND DISCUSSION I

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I ll RESULTS AND DISCUSSION The analytical results for the reporting period of January 1 through l December 31,1990, have been divided into four categories: aquatic, atmo-spheric, terrestrial, and direct radiation. The individual samples and analy-ses within each category display the unique radiological characteristics of l that tyme of environment. Analytical results of the REMP are summarized in Appentix A. The data for indiddual analyses are presented in Appendix C.

I A. Aquatic Environment I The aquatic environment in the vicinity of SNPS consists primarily of Long ' Island Sound. The radiological characteristics were studied by analyzing samples of surface water, Winter Flounder, Windowpane, Searobin, Little Skate, Fluke, American Lobster, Squid, Channeled Whelk, and I sediment. The samples were collected by LILCO's Environmental Engineering Department and Energy & Environmental Analysts Inc. (EEA Inc.) under contract to LlLCO.

1. Surface Water (Table C-1) l Semiannual surface water samples were taken at three locations and were analyzed for tritium, gamma emitters, lodine 131, and strondum 89 and stronuum 90.

I There was no detectable tritium in any surface water sample. This compares favorably with the average tritium concentration of 3100 pCl/ liter l detected during 1989.

Naturally occurring potassium 40 was measured in all six semiannual l samples over three locauons with an average of 289 C1/1 and a range between 232 and 354 pCl/1. No other gamma activity a ove the detectable levels was measured in the six surface water samples as analyzed by gamma g spectroscopy.

Surface water samples were also analyzed for iodine 131, strontium-I 89, and strontium 90.

limits of detecuon.

None of these nuclides were observed within the

2. Fish Crable C 2)

Twenty seven fish samples were collected at three locations and the I edible portions analyzed for gamma emitters as well as for strontium 89 and strontium 90. Gamma spectrometry showed potassium 40 present in all but one sample with an average concentrauon of 4242 pCl/kg wet and a range I between 1990 to 10900 pCi/kg wet. Cesium 137 was detected in three I l

, 1,

I samples with an average acuvity of 34.6 pCl/kg wet and a range between 11.1 to 61.5 pCl/kg wet.

l 3. Invertebrates (Table C 3)

Fifteen invertebrate samples, comprised of lobsters, squid, and whelk, l were collected at three locations and analyzed for gamma emitters, strontium 89 and strontium 90. Gamma spectrometry showed detectable levels of potassium 40 in 14 of the 15 samp es, ranging from 2400 to 3910 l pC1/kg wet with an average activity of 3171 pCl/k wet. Cesium 137 was measured in two lobster samples with an average o 33.8 pC1/kg wet and a range of 18.1 to 49.4 pCl/kg wet.

I

4. Sediment (Table C 4)

Two beach sediment samples were collected and analyzed for strontium 89, strontium 90 and gamma emitters. No strontium 89 or I strondum 90 was detected. Both samples had measurable activides of naturally occurring potassium 40 with an average acuvity of 2300 pCl/kg dry and a range of 2220 to 2380 pCi/kg dry. Thorium 228 was measured in one sample with an acuvity of 113 pCl/kg dry. All other gamma emitters were I below the lower limits of detecuon.

H Atmospheric Environment The atmospheric environment in the vicinity of the SNPS was examined by analyzing samples of airborne paruculates and airborne lodine I at flve sampling locations. TEDA tmpregnated charcoal cartridges used to collect airborne lodine were collected weekly and analyzed by gamma spectrometry for todine-131. Airborne paruculate filters were collected l weekly and analyzed for beta emitters. Quarterly composites from each station were analyzed for gamma emitters, strontium 89 and strontium 30.

1. Airborne Particulates (Tables C 5, C 6, and C 7) l Beta emitter concentrations ranged from 0.003 to 0.033 pC1/m3 with an annual average for the five sampling locadons of 0.014 pC1/m3 (Table C-5). Of the 264 measurements two were below the detection limit.

l nominally 0.004 pC1/m3 Figure 1 shows the average weekly gross beta fluctuations in airborne particulates from all stations for 1990. Figure 2 represents the average monthly gross beta results in airborne particulates l from January 1,1977 through December 31,1990.

Results of gamma spectrometry (Table C 6) showed detectable levels l of naturally occurring beryllium 7 in all twenty samples. The average beryllium-7 activity in the quarterly analyses was 0.055 pCl/m3 with a range of 0.039 to 0.073 pCi/m3 (Both the lowest and the highest values occurred I

16

at control location 1101), Naturally occurring potassium 40 was observed in one sample with an actMty of 0.004 pC1/m3. All other gamma emitters were below the lower limit of detection, The radiostrontium analyses on the 20 quarterly composites showed no detectable levels of strontium 89 or strontium 90.

2. Airborne lodine (Table C 7)

Analytjenl results of the 264 weekly airborne iodine 131 samples were all below the lower limit of detection which ranged between <0.008 l and <0.5 pCl/m3, g C, nrrestrial Environment The terrestrial environment in the vicinity of the SNPS was examined I by analyzing samples of milk, food products, and potable water. Gamma spectrometry was performed on all samples. In addition, iodine 131, strontium 89 and strontium 90 analyses were performed on the milk I samples, while tritium and lodine 131 analyses were performed on the pota' ale water samples,

1. Milk (Tables C 8 and C 9) g All of the 52 monthly and semimonthly cow and goat milk samples 3 analyzed for lodine 131 were below the LLD which ranged between <0.2 M and <0.6 pCl/1. Naturally occurring potassturn 40 was observed in all the milk samples. The goat milk samples had an average measurement of 1688 I pC1/1 and a range of 1340 to 2090 pCl/1. The cow milk saraples had an average concentration of 898 pC1/1 with a range of 740 to 1000 pC1/l.

Cesium 137 was not detected in any of the 32 goat milk samples. Eleven of the 20 cow milk samples ha:1 detectable measurernents of cesium 137 with I an average of 10.2 pC1/1 and a range of 7.25 to 14.6 pCi/1.

All other gamma emitters, as well as strontium 89 were below the I detection limits. Strontjum 90 was observed in 13 of the 14 cow samples analyzed and 16 of the 19 goat milk samples. In the 13 cow rnilk samples, the average strontium 90 concentration was 6.7 pC1/1 with a range from 2.2 l to 17 pCi/1. For the 16 goat milk samples, the average strontjum 90 concentration was 1.8 pCi/l and the range was from 0.32 to 4.1 pCl/1. The actMues reported for strontium 90 are consistent with those found in cow and goat milk samples from 1983 to the present.

I 17

I

g 2. Potable Water Crable C 10)

Eleven potable water samples were collected at three locations I during 1990. All tritium results were below the lower limit of detection (100 pCl/l). No iodine 131 was measured above the lower limit of detection which was between <0.2 and <0.3 pC1/l. All other gamma emitters were below the lower limits of detection, except for one sample which showed I naturally occurring potassium-40 at a level of 104 pCl/l.

3. Food Products (Table C-11)

Eighteen human food products from local farms were analyzed, I including tomatoes, potatoes, cabbage, lettuce, carrots, peaches, strawberries, and corn. All samples contained naturally occurring potassium 40 with an average of 2315 pCl/kg wet and a range of 835 to I 3790 pCi/kg wet. Also naturally occurring beryllium-7 was observed in one control sample of lettuce with a concentration of 166 pC1/kg wet. All other gamma emitters were below the lower limits of detection. The samples l were also analyzed for lodine 131 by a radiochemical procedure. No activity was found. The detection limit varied from 4 to 20 pCi/kg wet.

I D. Direct Radiation fTable C-121 I Direct radiation measurements were taken quarterly at 41 locations using CaSO4:Dy thermoluminescent dostmeters (TLDs). TLDs were used to detect radiation levels near ground level in the vicinity of the I Shoreham site due to terrestrial and cosmic gamma ray emitters ar.d possible SNPS contributed direct radiation. Figure 3 presents a comparison of average TLD results from 1977 to 1990. All TLD results presented in I this report have been normalized to a standard month (30.4 days) to eliminate the apparent differences caused by the variations in exposure period. The average of the quarterly exposures of all 41 locations was 3.6 I mR/ standard month. This is less than quarterly values, respectively, measured during the preoperational years 1983 and 1984. Annual average results of all quarters at the same locations, as well as of all locations for each quarter, are given in Table C 12 with 95% confldence hmits for the I mean value, except for the average of all locations and all quarters. For this last value, the 95% limits about any individual measurement, i.e.,10.9 mR/std. month, is given. The 95% limits for the mean of all locations and I all quarters (N=164) are iO 07 mR/std. month about the sample mean of 3.6 mR/std. month for 1990.

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I

l E. Dose Assessment Tables 2 summarizes the results of the dose assessment l detenninations based on 1990 data.

In10 ally, all posidve concentradons of radionuclides in indicator sam-l ples, as shown in Appendix A, were considered for inclusion in the dose calculation. in an attempt to factor out as much of the contribution due to natural and man made background radiation as possible, indicator and I control sample results were compared. If the control locadon results were greater than those at the indicator locatJon, the indicator sample results were not included in the dose assessment, Surface water was not I considered as a significant human exposure pathway and therefore, not considered in the dose assessment: The dose due to standing on soll/ sediment was not calculated since this is accounted for in the cifrect I radiatJon dose. Also, aotable water was excluded from dose calcula' ions because it is not consic ered a pathway. (Since ground water drainage .s to the north, no water sources for drinking or irrigatjon can be affected.) In 1990. no radionuclide in the analysis category was detected above the lower limits of detection in any of the potable water samples. 1 Beryllium 7, potassium 40, radium 226. radium 228 and thorium 228 are all naturally occurring isotopes and not likely to be produced as a result of the operation of Shoreham, so they were excluded. The remaining postuve isotope, cesturn 137, could be produced as a result of plant I operation so it was included in the dose calculations, it should be noted that cesium-137 also exists in the environment as a result of atmospheric weapons tesung and the Chernobyl accident.

I Comparison of the results of the dose assessment of 1990 with those of the preoperadonal years 1983 and 1984, show similar results for all l three years. Doses calculated for 1983 were based on tngestion factors for the average individual, whereas the maximum individual ingestion factors l

)

were used in 1984 and 1990. This makes exact comparison of the results I difficult; however, the dose is directly proportional to the activity in the medium: in all cases considered, the concentrations found in 1990 are consistent with those of 1983.

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H1NOH CHv0Nv1S/eH 23

M M M M M M M M M M M M M M M M M M TABLE 2

SUMMARY

OF DOSE DElERENATION FOR 1900 pornwar TerrAL BOUT CWmCAI ORGAN TOTAL CRf7K:AE.

INEE FACTOR Drww. FACTUEt BODY DOME OprM D09E asoarr eemrTrVE RADi&ftPCtJDE ACTmTY QUANTTTT AGE GROtyt!g OR 112) IN REFDtt'BE ENCesTED(1) undts a/gC3 W/y(I fumh/yrJ 6=8lhuus/yrJ UNotsTEDK23 DNorsTr2*2 AquellG Z1tda Adult Cs-137 46.4 pCa/kg wet 21 krjyr 7.14 E-5 1.09 E-4 Itver G.96 E-2 7.39 E-3 Itver Chikt 6.9 ktfyr 4.62 E-5 3.27 E-4 lxane I.48 E-2 1.05 E-I bone ImrertetPrates Adult Cs-137 33.8 pct /kx wet 5 kyfyr 7.34 E-5 1.09 E-41rver 1.21 E-2 1.84 E-2 Ilver i

Child 1.7 kyfyr 4.62 E-5 327 E-4 bone 2.65 E-3 I.88 E-2 bone l

Compartwn of the 19% doe with thane of the , y..tlonal years 1983 and 1984 h no sW18 cant dt!Terenms.

(ll From Table E-5 max mum el Irvityklual. Reg. Guide 1.109.

(2) From Tables E-11. E.12. E-13 aruf E-14. Reg. Gukie 1.109.

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I I III. CONCLUSIONS I

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25 I

l CONCLUSIONS g The unit was defuled prior to 1990.

l Analyses of environmental samples show results consistent with those I found during the arcoperational years of 1983 and 1984. In addfuon, comparison of resu ts reveals little difference between indicator and control .

l locations. Therefore, no isotopes could be identifled as having originated from SNPS.

Sensitive indicators revealed minute quantlues of radioactive fallout I from the October 1980 atmospheric nuclear weapons test by the Peoples Republic of China and the Chernobyl accident in addition to radioactivity remaining from two decades of atmospheric testing.

l Aside from these anomalies in the environment, expected normal background radioacthity has been measured in REMP samples. Aquade and

'a terrestrial samples were analyzed and reflected the normal background I radiation round in the environment. The atmospheric environment was sampled for airborne weekly gross beta results in airborne paruculates from January through December 1990. Figure 2 shows the average monthly gross l beta results in airborne paruculates from February 197'7 to December 1990.

Direct radiadon levels were relauvely low and approximately the same at all locations. Figure 3 shows the average quarterly TLD results in mR/ standard l month from January 1977 to December 1990.

I I

'I I

I

!I

'I 1

I lg 26 lm 1

I il I

I I

I I

I I IV. RETERENCES I

I I

I '

I I

I I 27 1

I

l -

l IV. REFERENCES (1) Long Island Lighting Company. "Shoreham Nuclear Power Station.

Environmental Report, Construction Permit Stage" December 1977.

(2) United States Atomic Energy Commission, Directorate of Licensing

" Final Emironmental Statement Related to Operation of Shoreham Nuclear Power Station", Docket No. 50 322, September 1972.

I (3) Long Island Lighting Company. "Shoreham Nuclear Power Station, Updated Safety Analysis Report".

(4) Radiation Management Corporation. "Shoreham Nuclear Power I Station Radiological Emironmental Monitoring Program - 1977 Annual Report", March 1978.

I (5) Radiation Management Corporation. "Shoreham Nuclea: Power Stauon Radiological Emironmental Monitoring Program - 1978 Annual Report". April 1979.

I (6) Radiation Management Corporation. "Shoreham Nuclear Power Station Radiological Environmental Monitoring Program - 1979 Annual l Report", June 1980.

(7) Radiation Management Corporation. "Shoreham Nuclear Power Station Preoperational Radiological Monitoring Program - 1980 Annual Report". Septeinber 1981.

(8) Radiation Management Corporation "Shoreham Nuclear Power Station Preoperational Radiological Monitoring Program - 1981 Annual Report," October 1982.

(9) Eisenbud, M., Emironmental Radioacthitv. 2nd Ed.,1973.

(10) National Academy of Sciences, Radioactivity in the Marine Environment, National Research Council, Washington, D.C.,1971.

ll (11) Long Island Lighting Company. Emironmental Engineering Dept.,

Radiological Emironmental Monitoring Program Procedures.

(12) EA Science and Technology Shoreham Profect Quality Assurance and ig Procedures Manual, March 1985.

3 I

g 2s

ll

{

l IV. REFERENCES (Cont.)

(13) U.S. Nuclear Regulatory Commission Regulatory Guide 1.109, Rev.1-1977.

g (14) Health Physics Journal, Vol. 38, No.4, April 1980.

(15) Teledyne Isotopes " Nuclear Reactor Environmental Radiation l Monitoring Quality Control Manual", IWL-0032 361.

(16) Teledyne Isotopes " Quality Control Internal Controls and Audits, I Environmental Analysis Department" IWL-0032-365.

I (17) Teledyne Isotopes " Quality Assurance Manual, Environmental Analysis Department Compliance with 10CFR50 Appendix B and Reg. Guide 4.15", IWL-0032 395.

(18) long Island Lighting Co. and Teledyne Isotopes,1982 Radiological Environmental Monitoring Program Annual Report.

I (19) long Island Lighting Co. and Teledyne Isotopes,1983 Radiological Environmental Monitoring Program Annual Report.

I (20) IAng Island Lighting Co. and Teledyne Isotopes,1984 Radiological Environmental Monitoring Program Annual Report.

(21) Long Island Lighting Co. and Teledyne Isotopes,1985 Radiological Environmental Monitoring Program Annual Report.

(22) Long Island Lighting Co. and Teledyne Isotopes,1986 Radiological g Environmental Monitoring Program Annual Report.

(23) Long Island Lighting Co. and Teledyne Isotopes,1987 Radiological l Environmental Monitoring Program Annual Report.

(24) 14ng Island Lighting Co. and Teledyne Isotopes,1988 Radiological I Environmental Monitoring Program Annual Report.

(25) Long Island Lighting Co. and Teledyne Isotopes,1989 Radiological I Environmental Monitoring Program Annual Report.

I I

a y

I I

I I

I-I I

I I APPENDIX A RADIOLOGICAL ENVIRONhENTAL

'40NITORING PROGRAM l

SUMMARY

1990 I

I I

I I

I I

w

E E E - E E E E E E E E E E E TABIE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SIIOREIIAM NUCIEAR POWER STKHON DOCKET NO. 50-322 SUFFOlK COUNTY. NEW YORK JANUARY I to DECEMBER 31.1990 ANALYSIS AND IDWER UMrr NUMBER OF MEDIUM OR PATTIWAY TUTAL NUMBER OF CONTRot,IOCA110N(3)

SAM Pt_ED A!l. INDIC'LIVR IDCATIO!GDI LOCATION WTT11 IIIGIIEST MEM NONROtmME OF ANALYSES DETECTION MEAN (2) NAME M EAN(2) MFAN(2) REPORTED (UNTTOF MEASUREMENil PERFORMED (11DI (11 RANCE DtSTANCE AND DIRECTION RANCE RANGE MEASUREMENTS surface Water II-3 6 100 -(0/4) N/A N/A -(0/2) 0 (pCl/ liter) -

Sr-89 6 1 -(0/4) N/A N/A -(0/2) 0 Sr-90 6 0.5 -(0/4) N/A N/A -(0/2) 0 j g Gamma G l f K-40 60 279(4/4) 3CI 2.9 mi NE 322(2/2) 309(2/2) 0 (232-354) (290-354) (278-339)

Flah Sr-89 27 0.7 -(0/I8) N/A N/A (pCl/kg wet) -

-(0/91 O Sr-90 27 0.6 -(0/18) N/A N/A -(0/9) O Gamma 27 I

K-40 300 4263(17/18) 3CI 2.9 mi NE 4734(8/9) 4202(9/9) 0 (2640-10900) (2820-10900) (1990-8890)

'Ih-228 7 -(0/ 38) N/A N/A -(0/9) O Cs-137 5 46.4(2/18) 3CI 2.9 mi NE G1.5(l/9) II.1(I/9) 0 (31.2-61.5) - -

(1) 'Ihe Il.Ds quoted are the kwest actual IJDe obtatned in the various media durtsst the reporting perkwl. W tlDs were determineti inr each maclide as found on '

C-13 arul C-14.

(2) Means calculated using detectable sw-umwnts ady. Frwtinew of detectable measurements in parentheaem I (3) Indicator and atrvd katsom are noted in Appermitt D. Table B-1.

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M M M M M M M M M M M TABIE A-1 tceti RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM SUMMART SIIOREllAM NUCLEAR POWER STATION DOCKET NO. 50-322 SUFTUIR COU? fly. NEW YORK JANUARY I to DECEMBER 31.1990 ANALYSIS AND IDWER UMfT MEDIUM OR PAT 1TWAY TUTAL NUMBER OF NUMitER OF SAM PtED M.L L*fRICATOR IJDCAT10NM31 IDCATTC'M #fT11 IDG1tm Mr>L1 EowTnotincATsoNpp NowuouTTNE OF ANALYSES DETTET10N MFAN (23 NAME M EANt21 MEANT 21 REPORTED (UNTT OF MEASUREMENTI PERFORMED (Ul4 411 RANGE DISTANCE AND DIRECT 1oM RANGE RANGE MEASUREMENTS Petable Water 11 3 II 100 -(0/8) N/A N/A (pCl/Itter) -

-(0/3) O  ;

- i I-13I 11 0.2 -(0/8) N/A N/A -(0/3) O y Gamma 1I K.40 50 104(1/8) 251 0.1 mi NNE 104(1/4)

-(0/31 0 Direct Radiation Ganma 164 (mR/Stamlard month) Dow 1.5 3.4G(140/140) 6Al O.7 mi ESE 4.53(4/4) 3.5af24 /24) O Quarterly (2.8-5.0) (4.2-5.01 (3.0-4.9) i

!II The LIDS quoted are tha lowest actual 11De obtatrwd in the various media during tlw rWing period. Typecal IIDe e determined few each mxBde as Inund ers '

C- 13 and C.14.

(21 Means takulated tssing detebi -- --.u, a, only. Fractinns of detectable measurements ers pah (3) E:witcater and mntrnl incations are reted in Appendix D. Table 11 1.

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O u .t

.= a 1:20 miles off site I The last number is the location numerical designadon 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 221/2 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 stauon No.1 in the designated area.

Sampling locations All sampling locations and specific informadon about the indMdual locations are I given in Table B-1. Tables B-2 through B d list the sampling locations and media required by Technical Specificadons.

k (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 descr!ption, as aquatic invertebrate. However, the I 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.

I I 39 l I

I Maps B 1, B 2 and B 3 show the locauons of 1990 sampling stations with respect l to the site. 'Ihese maps are tracings of portions oflarger maps prepared Survey Division after an extensive land survey of REMP monitoring ocations.

LILCO's Additjonal information can be obtained by referring to the Site and Vicinity Map of l 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 Engineering Department or Survey Division.

TABLE B 1 Sampling Locations Required By SNPS OfHste Dose Calculation Manual I SECTOR LOCATION CODE LOCA'nON SAhiPLE TYPE l

N IS1 Beach east ofintake 0.3 mi. N IDM(*)

NNE 2S1 Well, on site, 0.1 mi. NNE PWA(*)

NE 3SI Site Boundary,0.1 mi. NE APT (*), Al O (*),lD M (*)

I ENE E

4S1 5S2 Site Boundary,0.1 ml. ENE Site Boundary. 0.1 ml. E IDM(*)

IDM(*)

l i

ESE 6S2 Site Boundary. 0.1 mi. ESE A PT(*). AIO(*),lD M (*)

l S S

951 9S2 Service Road, 0.2 mi, S East Gate SNPS,0.3 m!. S IDM(*)

IDM(*)

W 13S2 Well, on site, 0.2 mi. W PWA(*)

I W WNW 13S3 14S2 Site Boundary, 0.2 mi. W St. Joseph's Villa 0.4 mi. WNW IDM(*)

IDM(*)

NW 15S1 Beach west of intake, 0.3 mi. NW IDM(*)

NNW 16S2 Site Boundary,0.3 mi. NNW IDM(*)

NNE 2A2 West end of Creek Road,0.2 ml NNE APT (*) AIO(*),lDM(*)

NNE 2A3 Residence 0.3 mi. NNE IDM(*),PWA I. NNE 2A4 Beach, 0.4 mi. NNE AQS(*)

ESE 6Al Sound Road,0.7 mi, ESE IDM(*)

I SE SSE SSW 7A2 8A3 10A1 North Country Road. 0.7 mi. SE North Country Road 0.6 ml. SSE North Country Road,0.3 mi SSW IDM(*)

IDM(*)

IDM(*)

SW Site Boundary,0.3 mi. SW I WSW ENE 11A1 12A1 4B1 Meteorological Tower, 0.9 mi WSW Little Flower Institute, Wading River, IDM(*)

IDM(*)

IDM 1.5 mi, ENT I ESE SE C 6B1 781 Remsen Road, Wading River.l.6 mi. ESE PWA Overh111 Road, Wading River,1.4 mi. A PT(*),

SE AIO(*),IDM(*)

I SE SE 7B3 7B4 Farm stand,1.7 ml. E Wading River Elementary School, FPV IDM Wading River,1.6 mi. SE l SSE 8B1 Farm stand 1.2 mi. SSE FPV(*),FPF I 40 I

l I

TABLE B-1 (Cont.)

LOCATION SAMPLE SECTOR CODE LOCAT10N 'nTE S 9B2 Shoreham Wading River High School, IDM Shoreham,1.2 mi. S WSW 12B2 Miller Avenue School, Shoreham,1.6 mi. IDM I W 13B1 WSW Briarcliff Road,1.9 mi W GMK(*)

NE 3C1 Outfall area, aquatic location B 5, AQF(*),AQl(*),

I E 502 2.9 ml. NE Farm 2.8 ml. E SWA(*)

FPV FPF(*)

WNW 14C1 Outfall area, aquaUe locadon SWA(*), AQ F(*),

I E 5D1 B-4, 2.1 mi. WNW Wildwood State Park, 3.4 mi E AQl(*)

IDM(*)

E 5D3 Wildwood State Park, 3.1 mi, E IDM I WSW 12D1 North Shore Beach Substauon 3.7 mt. WSW IDM(*)

I E ESE SE 5E2 6El Calverton, 4.5 mi. E LILCO ROW,4.8 mi. ESE Calverton, 4.9 ml. SE IDM(*)

IDM(*)

7El IDM(*)

I SSE S

8E1 9El Calverton, 4.4 ml. SSE Brookhaven National laboratory 5.0 mi. S IDM(*)

IDM(*)

I SSW SW W

10E1 11El 13E1 Ridge Substation,4.0 mi. SSW LILCO ROW,4.7 mi. SW 14ngview Ave. and Rocky Point Landing IDM(*)

IDM(*)

IDM(*)

Rd., 4.5 mi. W E C 5F2 Farm, 6.1 mi. E FFV E 5F3 I SSE SSW C

C 8F2 10F1 Farm, 7.8 ml. E Goat Farm,9.2 mi. SSW IDM(*)

Goat Farm, Wading River Rd.,9.5 mi. SSE GMK GMK(*)

ESE C GG1 Francis Court, Hampton Bays,19.0 mi, IDM(*)

I SSE C 8G1 ESE Wading River Rd.,10.1 mi. SSE IDM(*)

SSE C 8G2 Dairy Farm Center Moriches,10.8 mi. MLK(*)

SSE -

SW C 11G1 MacArthur Substadon,16.6 ml. SW APT (*), AIO( *),

l WSW C 12G1 CentralIslip Substadon,19.9 mi. WSW IDM(*)

IDM(*)

WSW C 12G2 Flowerfield Substauon,15.4 mi WSW IDM(*)

I W C 13G2 Background aquatic locadon,13.2 ml. W SWA(*)

AQF(*),AQl(*)

g WSW C 12H1 Farm,25.8 mi WSW FPV(*),FPF(*)

C Denotes Control Location I **

Denotes SNPS ODCM sampling locations and sample type.

BotUed Milk 41 I

REMP LOCATIONS REQUIRED BY SNPS OFFSITE DOSE CALCULATION MANUAL TABLE B-2 g Airborne Particulate and Airborne lodine Monitoring Stations Location Codes NUREG-0473 SHOREHAM REMP Lgpption Description g

A1 6S2 Site Boundary 0.1 mi, ESE I A2 A3 A4 2A2 3S1 7B1 West end of Creek Road,0.2 mi NNE Site Boundary,0.1 mi., NE Overhill Road,1.4 mi. SE A5 11G1 MacArthur Substation,16.6 ml. SW TABLE B-3 Waterborne Monitoring Stations I Location NUREG-0473 Codes SHOREHAM REMP Location Description WA1 Surface, backgrcund area,13.2 mi. W I WA2 WA3 13G2 14C1 3C1 Surface, outfall area,2.1 ml. WNW Surface, outfall area, 2.9 mi. NE Wbl 2S1 Potable Water, well on site, 0.1 ml. NNE I Wb2 Wdl 13S2 2A4 Potable Water, well on site, 0.2 mi, W Sediment, Beach, 0.4 mi. NNE TABLE B-4 Ingestion Monitoring Stations Location Codes NUREG-0473 SHOREHAM REMP Location Description Ia1 13B1 Goat Farm,1.9 mi. W Ia2 10F1 Goat Farm,9.2 mi. SSW I Ib1 8G2 3C1 Dairy (Cow),10.8 mi SSE Fish and Invertebrates, outfall area, 2.9 mi. NE Ib2 14C1 Fish and Invertebrates, outfall area.

I Ib3 13G2 2.1 mi. WNW Fish and Invertebrates, background, 13.2 mi. W I Ic1 Ic2 8B1 6B21 Iacal Fann,1.2 mi. SSE I4 cal Farm,1.8 mi ESE Ic3 12H1 Background Farm. 25.8 mi. WSW I 42 I

I REMP LOCATIONS REQUIRED BY SNPS OFFSITE DOSE CALCULATION MANUAL TABLE B 5 g Direct Radiation Monitoring Stations Location Codes NUREG-0473 SHOREHAM REMP Location Description DR1 IS1 Beach east of intake, 0.3 ml. N I DR2 DRS DR4 2A2 3S1 4S1 West end of Creek Road. 0.2 ml Site Boundary, 0,1 ml. NE Site Boundary, 0.1 ml. ENE NNE DR5 5S2 Site Boundary. 0.1 ml. E I DR6 DR7 6S2 7A2 Site Boundary,0.1 ml ESE North Country Road,0.7 mi. SE DR8 8A3 North Country Road. 0.6 mi SSE I DR9 DR10 9S1 10A1 Service Road SNPS, 0.2 ml. S North Cour,try Road. 0.3 ml. SSW DR11 11A1 Site Boundary,0.3 ml. SW I DR12 DR13 12A1 13S3 Meteorological Tower, 0.9 ml. WSW Site Boundary,0.2 ml. W DR14 14S2 St. Joseph's Villa, 0.4 ml. WNW DR15 Beach west of intake, 0.3 mi. NW

(_ DR16 15S1 16S2 Site Boundary,0.3 mi NNW DR17 5E2 Calverton, 4.5 ml. E I DR18 DR19 DR20 6El 7El 8E1 LILCO ROW,4.8 ml ESE Calverton,4.9 ml. SE Calverton, 4.4 ml. SSE I DR21 DR22 9El 10E1 Brookhaven National Laboratory, 5.0 ml. S Ridge Substation,4.0 mi. SSW I DR23 DR24 11El 12D1 LILCO ROW. 4.7 ml. SW North Shore Beach Substation, 3.7 ml. WSW I DR25 DR26 13E1 5D1 Longview Ave. and Rocky Point Landing Rd. 4.5 mi W Wildwood State Park, 3.4 ml. E DR27 5F3 Dairy Farm,7.8 ml. E I- DR28 7B1 Overhill Road,1.4 mi. SE Flowerfield Substation, DR29 12G2 15.4 ml. WSW DR30 12G1 Central Islip Substation, 19.9 ml. WSW DR31 11G1 MacArthur Substation,16.6 mi. SW l DR32 DR33 8G1 6G1 Wading River Road,10.1 ml. SSE Hampton Bays Substation,19.0 ml. ESE DR34 6Al Sound Road,0.7 mi, ESE l DR35 DRS6 2A3 952 Nearest Residence. 0.3 ml. NNE East Gate SNPS,0.3 ml. S 43 j I

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I APPENDIX C

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DATA TABLES I ,

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TABIE C-1 CONCENTRATIONS OF 1RTIlUM. STRONI1UM-89* and -90 AND GAMMA EMTITERS" IN SURFACE WATER SAMPLES Results in Units of pCl/l i 2 sigru COf32CT10M DATE H-3 I-131"* Br-89* Sr-90 K-40 Co-137 LOCATION CODE

< 100 < 0.3 <1 < 0.6 290i44 <5 SN-SWA-3C l 05/24/90

< 200 < 0.3 <2 < 0.7 354 i40 <4 SN-SWA-3C l 10/15/90

< 200 < 0.2 <2 <1 2781 34 <3 SN-SWA-13G2 (c1) 05/24/90

< 200 < 0.3 <2 <1 339 42 <4 SN-SWA-13G2 (ci) 10/15/90

< 200 < 0.2 <2 < 0.7 238137 <3 SN-SWA-14C1 '05/24/99

< 100 < 0.3 <2 <1 232152 <3 SN-SWA-14C1 10/15/90 Average 289i101 1 2 s.d.

• Sr-89 results are corrected for decay to the sample stop date.

• • All other gamma emitters not listed were & typical Ellys are given in Tables C-13 and C-14.

• • • I-131 results determined by radiochemical analysis.

(ct) Denotes Control location l

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TABLE C-2 CONCFEIRATIONS OF STRONI1UM 89* AND -90 AND GAMMA EMITERS** LN FISil SAMIM Results in Units of pCl/kg (wet) i 2 sigma COLIECTION DESCRIPTION Br.89 Br-90 K-40 Co-137 Th-228 LOCATION CODE DATE Winter Flounder <1 <2 4430 1 440 <7 < 10 SN-AQF.3C1 05/16/90 <8 < 10 05/16/90 Windowpane <2 <1 3400 1 340 Sea Robin <2 <2 3880 1 390 < 20 < 30 05/16/90 <3 2820 1 260 <9 < IO 05/16/90 Uttle Skate <1

< 100 10/09/90 Sea Robin < 20 (a) <7 10900 2000 < 100 10/09/90 Windowpane <5 <2 3820 1 440 < 30 < 60 10/09/90 Uttle Skate <3 < 0.6 < 500 61.5121.5 < 40 Ruhe <4 < 0.8 4230 1 420 <20 < 40 10/09/90 <1 4390 1 440 < 20 < 40 10/09/90 Winter Rounder <3 Windowpane < 0.8 < 0.9 3810 i 380 < 10 < 20 SN-AQF-14C1 05/17/90 <2 4000 1 400 < 10 < 20 05/17/90 Winter Mounder <1 utile Skate <2 <1 2640 1 260 < 10 < 10 05/17/90 < 0.7 3820 1 380 < 10 < 20 05/17/90 Sea Robin < 0.8 10/1I/90 Windowpane <5 <3 5480 1 550 31.2 i 18.3 < 40 Muke <1 < 0.8 4130 1 410 < 10 < 20 r- 10/11/90 <5 4210 1 430 < 30 < 60 10/11/90 Sea Hobin <5 Winter Rounder <2 <1 3580 1 360 < 30 < 60 10/11/90 <2 2930 i 300 < 20 < 40 10/11/90 Uttle Skate <3 SN-AQF-13C2 (cIl 05/22/90 uttle Skate <3 <3 1990 1 200 < 20 < 20 Windowpanc <2 <1 3800 1 380 11.1 1 6.2 < 10 05/22/90 <1 4440 1 440 < 10 < 20 05/22/90 Sea Robin <1 Winter Mounder <2 <1 4240 1 420 <7 < 10 05/22/90 < 0.7 3650 i 370 < 30 < 40 10/10/90 Windowpane <2

< 20 (a) <6 8890i 1750 < 100 < 100 10/10/90 Sea Hobin Ruke <5 <3 2700 1 270 < 20 < 40 10/10/90 <1 3840 1 380 < 20 < 50 10/10/90 Uttle Skate <2 Winter Mounder <1 < 0.4 4270 1 430 < 20 < 30 10/10/90 ,

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• Sr-89 results are corrected for decay to the sample stop date.

• • All other gamma emitters not listed were <LLD: typimi 11D's are given in Tables C-13 and C-14.

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<5 <2 2380 1 270 < 300 113 i 16 < 10 SN-AQS-2A4 Beach 06/07/90

<2 <2 2220 1 320 < 400 < 50 < 30 SN-AQS-2A4 Beach 11/05/90 I

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TABIEC4 CONCENIRAT10NS OF GAMMA EMITIERS* AND STRONI1UM IN QUARTERLY COMPOSTIE OF AIRDORNE PARI 1CULATE SAMPLES Results in Units of 10-3 pC1/m3 12 sigma SECOND QUAITIER TlIIRD QUAlrTER FOURT11 QUAITTER AVERAGE LOCAT10M NUC1JDES FIRST QUARTER 1 2 e.d.

CODES 01/02/90 44/03/90 04/03/904Y7/03/90 07/(O/90 10/02/90 10/02/904I/02/91 Sr-89 < 0.5 - < 0.4 < 0.3 < 0.2 -

SN-AIT-2A2 Sr.90 < 0.09 < 0.05 ' < 0.1 < 0.03 -

52.7 i 6.5 60.9 i 6.1 57.016.6 59.316.3 57.517.1 Be-7 K-40 <8 <8 < 10 <9 -

Cs-134 < 0.4 < 0.3 < 0.5 < 0.4 -

Cs-137 < 0.6 < 0.4 < 0.5 < 0.4 -

Sr-89 < 0.6 < 0.2 < 0.4 < 0.2 -

SN.AIT-381 Sr-90 < 0.08 < 0.05 < 0.1 < 0.04 -

Be-7 51.7 i 5.8 56.215.6 49.015.5 49.116.7 51.5 i 6.7

< 10 < 20 <9 < 30 -

g K.40 Cs-134 < 0.6 < 0.5 < 0.4 < 0.7 -

Cs-137 < 0.5 < 0.5 < 0.4 < 0.8 -

Sr-89 < 0.6 < 0.3 < 0.2 < 0.2 -

SN-AIT-882 Sr-90 < 0.1 < 0.04 < 0.07 < 0.04 -

56.3 i 5.6 44.815.1 54.9 i 5.5 51.2 i 6.0 51.8

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Cs-134 < 0.5 < 0.4 < 0.3 < 0.5 -

Cs-137 < 0.5 < 0.5 < 0.4 < 0.5 -

• All other g mma emitters not listed were <LLD: typlal LLDs are found in Tables C-13 and C-14.

g g g m a m M M M M M M 'M M M M TABLE C-6 IcontJ CONCEN111AT10NS OF CAMMA EMITIERS* IN QUARTERLY COMPOSflE OF AIRBORNE PARTICULATE SAMPLES Results in Units of 10-3 pCI/m3 12 sigma 1DCAT10M NUCUDFS FIRST QUARTER SECOND QUARTER OODES TillRD QUARTER FOURIll QUARTER AVERAGEL 01/02/90 44/03/90 04/03/90 47/03/90 07/03/00-10/02/90 10/02/9041/02/91 1 2 e.d.

SN-AIT-7B1 Sr-89 < 0.2 < 0.4 < 0.4 < 0.2 -

Sr-90 < 0.04 < 0.04 < 0.2 < 0.03 -

lie-7 51.5 i 5.1 57.015.7 42.6 i 4.3 69.7 i 7.0 55.2122.7 K-40 <9 < 10 4.3212.47 <9 4.3212.47 Cs-134 < 0.3 < 0.5 < 0.3 < 0.4 -

Cs-137 < 0.3 < 0.4 < 0.2 < 0.4 -

SN-AIT-1101 Sr-89 < 0.2 < 0.3 < 0.5 < 0.2 -

(ct) Sr-90 < 0.06 < 0.05 < 0.2 < 0.03 -

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p Cs-134 < 0.4 < 0.4 < 0.4 < 0.9 -

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All other gamma emitters not listed were <lll): typical Il.Ds air found in Tables C-13 arxl C-14.

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g. g g g g M M M M M M M E E E E' E TABLE C-8 CONCE. VIVA 710NS OF IODINE-131 IN MILK SAMPLES Results in Units of pCI/lfteri 2 sigma IDCATION CODES COLIICTION DATES 8N.CMK-1381 SM-MLK.8C2 tell SM-CMK-8F2

! JANUARY 10. I1 < 0.4 < 0.2 JANUARY 24 < 0.4 FEBRUARY 06. 07. 08 < 0.2 < 0.2 MARCil 07. 08 < 0.1 < 0.1 APRIL 01, 04, 05 < 0.2 < 0.2 MAY 01, 02, 03 < 0.2 < 0.2 < 0.2 MAY 16.17 < 0.2 < 0.2 < 0.2 MAY 30, 31 < 0.2 < 0.4 JUNE 13.14 < 0.3 < 0.2 JUNE 26. 27. 28 < 0.2 < 0.1 < 0.1

$ JULY I1.12 < 0.4 < 0.4 < 0.5 JULY 25. 26 < 0.2 < 0.2 < 0.1 AUGUST 08. 09 < 0.2 < 0.4 < 0.5 AUGUST 22. 23 < 0.2 < 0.2 < 0.2 SEI7 EMBER 05. 06 < 0.2 < 0.2 < 0.2 SEI7 EMBER 19. 20 < 0.3 < 0.2 < 0.3 OCIOBER 01. 03. 04 < 0.4 < 0.3 < 0.2 OCTOBER 17.18 < 0.2 < 0.2 < 0.2 NOVEMBER 13. 14. 15 < 0.2 < 0.3 NOVEMBER 28. 29 < 0.2 < 0.2 DECEMBER 13.14 < 0.3 < 0.1 GMK Goat's Milk MILK Cow's Milk (cIl Denotes Control location

M -

M M- M M M M M M M ' -

M M M M M TABLE C-9 CONCENTRA110NS OF SIRONT1UM-89 AND -90 AND CAMMA EMTTIERS* IN MIllt SAMPLES Results in Units of pC1/ liter i 2 sigma LOCATION CODES COLLECTION DATES NUCLIDE SM-CMK-13B1 SM-MLK-8G2 teI) 8N-CMK-8F2 JANUAIN 10. I1 Sr-89 <3 <3 Sr-90 (a) i

< 0.4 -

2.2 1 0.8 K-40 1550 1 160 846 i 85 Cs-137 <4 10.1 i 3.8 JANUAIN 24. 25 . Sr-89 <3 Sr-90 2.5 i 1.3 K-40 998 i 100 Cs-137 <5 i

FEBRUARY 07. 08 Sr-89 <1 < 0.8 Sr-90 0.3G i 0.22 4.01 0.6 K-40 1500 i 150 852 i 85 Cs-137 <5 <5 C

MARCII 07. 08 Sr-89 < 0.9 <2 Sr-90 2.0 1 0.3 2.3 1 0.4 K-40 1780 i 180 938 i 94 Cs-137 <5 10.21 3.4 APRIL 01, 04. 05 Sr-89 <3 <4 Sr-90 2.1 1 0.3 17 i 1 K-40 1730 i 170 869 i 87 Cs-137 <4 <5 MAY 02. 03 Sr-89 (b) (b) (b)

Sr-90 (b) (b)

K-40 (b) 1600 i 160 811 1 81 1340 i 130 Cs-137 <5 8.721 3.02 <4

• Footnotes lacatetl at eral of table. I

I TABIE C- 9 tcont.)

CONCENIRAllONS OF STRONI1UM-89 AND -90 AND CAMMA EMnTERS* IN MILK S Results in Units of pCf/ liter i 2 s!pna IDCATION CODES SM-CMK-8F2 __

SM-MLK-802 (c0 NUCLIDE SN-CMK-13B1 COIJECT10M DATES

<5

<4 2 6 i 1.0

<3 9.2

• 2.6 Sr-89 1380 1 140 MAY 16.17 Sr -90 1.9 i 1.3 1000 i 100 1770 1 180 <4 K-40 <5

<4 Cs-137 (b)

(b) (b)

Sr-89 (b) 1540 1 150 MAY 30. 31 Sr-90 1790 i 180 <4 l K-40 <5 Cs-137 (b)

(b) (b)

Sr-89 (b) 1550 150 JUNE 13.14 Sr-90 861 i 86 <4 K-40 <4 Cs-137

$ <4

<5 2.8 1 0.3 Sr-89 <2 7.5 1 0.5 JUNE 26. 27. 28 2.0 1 0.4 16901 170 Sr-90 862 1 86 <5 K-40 1830 i 180 <4 Cs-137

<5 (b)

(b) (b)

Sr-89 (b) (b)

JULY 11.12 (b) 1590 i 160 835 i 83 Sr-90 <5 K-40 1700 i 770 <5 Cs-137 < ti

<2

<4 0.48 i 0.17 Sr-89 <3 4.7 1 0.3 JULY 25. 26 0.321 0.17 982 98 1640 i 160 Sr-90 <4 K-40 1790 1 180 <6 Cs-137 <5

• Footnotes located at emi of table.

M m'M M M M M M m W M M .. M M M TABLE C- 9 (contI CONCENITIA'I1ONS OF STRONHUM-89 AND -90 AND GAMMA emf 1TERS* IN MILK SAMPLES Results in Units of pC1/Ilter i 2 sigrna I.OCATION CODES NUCLIDE SN-GMK-13B1 SM-MIE-8G2 (cQ BM-CMK-8F2 COLLECTION DATES Sr-89 (b) (b) (b)

AUGUST 08. 09 (b)

Sr-90 (b) (b) 1900i 190 909 i 91 1690 i 170 K-40 <4 Cs-137 <4 <4

<3 <3 <3 AUGUST 22. 23 Sr-89 0.8510.23 Sr-90 0.7G i 0.26 8.5 i 0.4 K-40 1710 i 170 95Gi 9G 1880i 190 Cs-137 <4 11.a i 4.2 (c) <5 Sr-89 (b) (b) (b)

SEI'IEMBER 05. 06 (b) (b)

Sr-90 (b) 1730 i 170 918 i 71 1690 i 170 K.4 0 <5 C Cs-137 <G 8.621 3.44 (c)

<4 <2 <4 )

SEI7EMUER 19. 20 Sr-89 < 0.9  ;

Sr-90 <1 < 0.5 K-40 1970 1 200 985 i 99 1530 i 150  !

Cs-137 <5 14.61 3.9 (c) <5 i

OCTOBER 01. 03, 04 Sr-89 (b) (b) (b)

Sr-90 (b) (b) (b) 1920 i 190 740 i 74 1660 i 170 K-40 <4 Cs-137 <4 7.25 i 3.69 (c)

• Footnotes k>cateti at emi of table.

M M M -M M M M M M M M _. M M M M- .

TABLE C- 9 (cont.)

CONCENTRA'I1ONS OF STRONI1UM-89 AND -90 AND CAMMA EMTITERS* IN MIIE SAMI1ES Results in Units of pCf/ liter i 2 sigma IDCATION CODES Coll.ECT10M DATES NUCLIDE SM-CMK-13B1 SM-MLK-8G2 (d) BN-CMK-8F2 OCTOBER 17.18 Sr-89 <2 <4 <3 Sr-90 1.3 i O.2 7.6 i O.4 3_3 i O.3 K-40 1730 i 170 893 i 89 1820 i 180 Cs-137 <3 12.5 i 3.0 (c) <4 NOVEMBER 14.15 Sr-89 <5 <3 Sr-90 8.9 1 0.5 4.1 i O.7 K-40 955 i 95 1410 i 140 Cs-137 9.671 3.96 <5 NOVEMBER 28. 29 Sr-89 <3 <3 E 1.3 1 0.3 3.0 i O.4 Sr.90 K-40 1510 i 150 877 i 8.8 Cs-137 <5 9.711 3.95 DECEMBER 13.14 Sr-89 <3 <5 Sr-90 2.1 1 0.3 9.4 i O.7 K-40 2090 1 210 873 1 87 Cs-137 <4 9.19 i 3.49

• All other gamma emitters not listed were <IlD: typical Illys are ghren in Tables C-13 ami C-14.

GMK Coat's Milk MLK Cows Milk.

(a) No goat milk available during the winter due to kkkiing.

(b) Strontium analysis performed once a month.

(c) Result confirmed by recount.

(c!) Denotes Control location

M M M M M m m m m M mm M m M' M TABIE C-10 CONCENTRATIONS OF TRTITUM. IODINE-131 AND GAMMA EMITTERS" IN PC7 TABLE WATER Hesults in Units of pCI/ liter i 2 sigma LOCATION COLIECTION CODES DATE H-3 I-131* K-40 Cs-137 Th-228

< 200 < 0.2 < 90 <4 <8 FWA-2S E 03/14/90 <4 < 12 06/21/90 (a) < 100 < 0.1 104 i62

< 100 < 0.1 < 100 <5 <8 09/13/90 <3 <7 12/06/90 < 200 < 0.1 < 60 06/21/90 < 100 < 0.1 < 60 <3 <7 ENA-BR1(b) <4 <7 (ct) 09/13/90 < 200 < 0.1 < 60

< 100 < 0.1 < 100 <5 <8 12/06/90 u,

< 100 < 0.3 < 50 <4 <6 PWA-2A3 03/14/90 <4 <6 06/21/90 < 100 < 0.1 < 60

< 200 < 0.1 < 90 <5 <8 09/13/90 <G 12/06/90 < 100 < 0.1 < 50 <3

• Iodine-131 results are mrrected for decay to sample stop date. Determined by ra<llochemical analysis.

• • All other gamma emitters not listed were <LLD: typical LIDS are found in Tables C-13 and C-14.

(c!) Denotes Contml location (a) Analyzed by Clean liarbors Inc Braintree. MA. San >ple was forwarded to Clean f{ arbors by mistake.

(b) March 14.1990 sample was not collected at this locauon due to owner's absence from the site.

M M M M g g g m e e m m- ' m m M M -

TABIE C-11 CONCENITIA110NS OF CAMMA EMTTIERS* AND I-131 IN FOOD PRODUCT SAMPLES Results in Units of pCI/kg (wet) i 2 simia COLLECTION DATE K-40 I-131" Cs-137 Be-7 LOCATION CODE SAMPLE TTPE

<7 <8 < 70 SN-FPV-5C2 Tomatoes 08/09/90 2840 1 280

<7 < 60

<7 SN-FPV-SC2 Corn 08/09/90 2480 i 250 Peaches 08/09/90 1460 1 150 <4 <5 < 40 SN-FPF-5C2 <4 < 10 < 100 SN-FIL5C2 Cabbage 08/09/90 1540 i 150 Potatoes 08/09/90 3670 1 370 <7 <6 < 60 SN-FPV-5C2

<8 < 10 < 90 SN-FPF-6B21 Strawberries 06/18/90 1110 i 120

<6 < 50 Tomatoes 08/16/90 1770 i 130 < 10 SN-FPV-6B21 06/18/90 2140 1 210 < 10 < 10 < 100' SN-FPF-8BI Strawberries <8 < SO Tomatoes 08/08/90 2270 1 230 <6 SN-FPV-8 BI < 100 08/08/90 2660 1 270 <9 < 10

$ SN-FPV-Bill Corn Cam >ts 08/08/90 3790 1 300 <7 <9 < 80 SN-FPV-8H I < 100 SN-FIL8BI Cabbage 08/08/90 2530 1 750 <5 < 10 08/08/90 3490 1 '350 <9 <6 < 50 SN-FPV-8BI Potatoes 08/15/90 2240 1 220 < 20 <7 < 70 SN-FPV-12111 (et! Tomatoes Strawberries 06/18/90 835 i 108 < 10 <8 < 60 SN-FPF-12112 (c!! <6 < 50 SN-FPV-12112 Tomatoes 08/08/90 1290 1 130 < 20 Stringbeans 08/08/90 2330 1 230 <8 < 10 < 100 SN-FPV-12112 <5 <7 1661 59 SN FIL12112 lettuce 08/08/90 3230 1 320 23151 1728 166 i 59 Average i 2 s.d.

• All other gamma emitters not listed were <LLD; typical LLD's are given in Tables C-13 and C-14.

• * !-131 by Rad:ochemistry (ci) Denotes Control location

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M M m W M M M M M MM M M M M M M M TABLE C-10 (ConL) 11D's AND REPORTING ACTION LEVELS - 1990 REQUIRED BY ODCM AND CONTRACT aAurtz TTrE a _ _ _ _ za Unies ora-a n.es ses as.-s4 C.we F.as C mo 2.es Rrms arme AtasonriestIC/ AIRBORNE Air Samg4e IJD* Tech S. gC/m 3 0 01 - - - - - - - -

eld Cwtract G.Ol - - - - - - -

RAL** Tech S. - - - - - - - -

.000t HAL Contract 1 - - - - - - -

O1 AQUATIC Fish IlD Teth S. gC/M - -

130 130 28 9 130 2re - -

Invertebrate / IJD Contract (wrt) - -

130 130 28io 130 2*4 5 Algae RAL Tech S. -

30. fin 0 30.000 30.000 10.000 20.On0 - -

RAL Contract - -

30.000 30.ono 10.000 30,000 20.000 -

20 WATDtBOWtNE Pot able llD Tech S. 30/I 4 3.ono 15 15 30 15 Surfare 30 - -

llD Cortract 4 200 15 15 30 15 30 Prectp.

10 RAL Tech S. -

30.000 1.000 10n0 400 300 300 - -

RAL Contract 50 30.000 1.ono 1.000 400 300 300 -

20 TutRESTRIAL .

~2

- Fewwi IlD Tech S. gCS/kg - - - - - - - -

thwhsets IlD Contract  !=t) - - - - - - - - -

HAL Tech S. - - - - - - - - -

RAL Contract - - - - - - - -

EsIIK MtIk IlD Tech S. gC1/1 - - - - - - - - -

uD Contract - - -

RAL Tech S. - - -

5 RAL Contract - - - - - - - -

20 santorT/sous Sedicients 11D Tech S. gC /kg - - - - - - - -

Sotta IJD Centract (dry) - - - - - - - -

S RAL Tech S. - - - - - - - - -

RAL Contract - - - - - - - - 80 NOWE2 GAS tlD Tech S. 30/m3 - - - - - - - - -

uD Contract - - - - - - -

25 -

RAL Tech S. - - - - - - - - -

RAL Contract - - - - - - - - -

DERECT llD Tech S. - - - - - - - - -

RADtATION tlD Csweract 1.5 mR/ sed. mmth - - - - - - - - -

TLD tower Itmit <4 detectior Regwwttng action Irvel 2

- w n sm a re s n, M--n e 4 mm 4m- Mw A-b"n-~a-A4'Me+4d ea n-- us w AsaM A K-o---4*J6- an A M*Amden& A M 4 Mes-M&R-- =AABA-- >*A- ne'",wo,4s4aAMA-*mde on4-aw- as 4 d e, A -e- s AJmb,4. 61 iI l

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I l I APPENDIX D ANALYTICAL PROCEDURES SYNOPSIS I

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I ANALYTICAL PROCEDURES SYNOPSIS I Appendix D is a synopsis of the analytical procedures performed on samples collected for the Shoreham Nuclear Power Station's Radiological I Environmental Monitoring Program. All analyses have been mutually agreed upon by Long Island Lighting Company and Teledyne isotopes and include l those recommended by the USNRC Branch Technical Position, Rev.1.

November 1979.

I ANALYSIS TITLE }% @

l G ross Be ta Analysis of Samples. .. .. . . . .. .. .. . .. .. . .. . . . . . . . . . . . . . . . ... . . . . . . . . . . . . . . . . . . .. . . .. . . . . . .. . . . . . .. . . . 7 4 I Air bo rn e Pa rtJ c u 1 a t e s . .... .. .. . ... .. ... .. .. . . .. . . .. .. . . . . . . . . . .. .. . . ... .. .. .. . . .. . . .. .. . . . . . . . . . .. ..

A n aly si s o f S am ple s fo r Tri ti u m ........ ............... ............... .................... ...... ............... 7 7 g Water.......................................................................................................................77 An alysis of Sam ples for S tron tiu m 89 and -90 .................................................. 7 8 l To tal W a t e r' . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

M11k.........................................................................................................................78 So i l an d Se d i m e n t .. .. .. .. . .. . .. . . ... .. .. .. .. .. .. . . ... .. .. .. .. .. .. .. .. . . . . . . . . . .. . . .. .. . .. . . .. .. . . .. .. .. ... .

O r g a ni c So l i d s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Air Paniculates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

l An alys is of Sam ples for 1 odin e- 131............................. ........................ ...... ......... .... 8 2 Milk or Water. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

G am m a S pe c tro m e try o f Sam pl e s ........................................................................... 8 3 Milk and Water. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Dried Solids oth er than Soils and Sediment .......................................... 8 3 l Fish.........................................................................................................................83 So il s an d Se d i m e n t s .. .. .. .. .. .. .. .. ... .. .. .. .. . . . . . .. .. .. .. .. . . .. .. . .. .. .. .. < .. .. . . . . . .. .. .. .. .. .. .. ... . . .. 8 C h arcoal C artri d ge s (Air I od in e) ........... .................... ......... .. ........................ 8 3 Airbo rn e Parti c ul a t e s . . ... . ... . . .. .. ... . . . . . . . . . . . . . . .. . .. . . .. . . . . .. . . . . . .. .. .. .. . . .. ... . . . . . . .. . . .. .. . .. .. .

Environnr:n tal Dosime try. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 5 I 73 I

I

'I DETERMINATION OF GROSS BETA ACTIYlTY IN WATER SAMPLES 1.0 [ETJRODUCTION I The procedures described in this secuon are used to measure the overall radioactMty of water samples without identifying the radioacuve species present. No chemical separadon techniques are involved.

One liter of the sample is evaporated on a hot plate. A smaller volume may be used if the sample has a significant salt content as l measured by a conductivity meter. If requested by the customer, the sample is filtered through No. 54 filter paper before evaporation.

l removing particles greater than 30 microns in size.

I After evaporaung to a small volume in a beaker, the sample is rinsed into a 2 inch diameter stainless steel planchet which is stamped with a concentric ring pattern to distribute residue evenly. Final evaporadon to I dryness takes place under heat lamps.

l Residue mass is determined by weighing the planchet before and after mounung the sample. The planchet is counted for beta actMty on g an automauc propordonal counter. Results are calculated using empirical self absorption curves which allow for the change in effective counung efficiency caused by the residue mass.

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L 2.0 DETECTION CAPABilfrY I.

Detection capability depends upon the sample volume actually l represented on the planchet, the background and the efficiency of the counting instrument, and upon self absorpuon of beta particles by the g mounted sample. Because the radioactive species are not identified, no decay corrections are made and the reported activity refers to the counting time.

The minimum detectable level (MDL) for water samples is nominally 1.6 picoeuries per liter for gross beta at the 4.66 sigma level (1.0 pCi/l at the 2.83 sigma level), assuming that I liter of sample is used and that h gram of sample residue is mounted on the planchet. These figures are based upon a counting Ume of 50 minutes and upon representauve values l of counung efficiency and background of 0.2 and 1.2 cpm, respecuvely, g The MDL becomes significantly lower as the mount weight decreases because of reduced self absorpuon. At a zero mount weight, the 4.66 sigma MDL for gross beta is 0.9 picoeuries per liter. These I

values reflect a beta counung efficiency of 0.38.

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I GROSS BETA ANALYSIS OF SAMPLES Air Particulates I After a delay of five or more days, allowing for the radon 222 and g radon 220 (thoron) daughter products to decay, the filters are counted in a l gas flow proportional counter. An unused air particulate filter, supplied by LILCO, is counted as the blank.

I Calculations of the results, the two sigma error and the lower limit of detection (LLD)* I RESULT (pCi/m3) ((S/T) - (B/t))/(2,22 V E)

I

=

'IWO SIGMA ERROR (pC1/m3) = 2((S/T2 ) + (B/t 2))1/2 (2.22

/ V E)

LLD (pC1/m3) = 4.66 (B1/2)/(2.22 V E t) l where:

S = Gross counts of sample including blank B = Counts of blank E = Counting efficiency g

T = Number of minutes sample was counted t Number of minutes blank was counted I

=

V = Sample aliquot size (cubic meters)

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I ANALYS!S OF SAMPLES FOR TRITIUM Water l Approximately 2 ml of water are converted to hydrogen by passing the water, heated to its vapor state, over a granular zinc conversion column g heated to 400' C. The hydrogen is loaded into a one liter proportional detector and the volume is determined by recording the pressure.

The proportional detector is passively shielded by lead and steel and an electronic, anticoincidence system provides additional shleiding from cosmic rays.

l l

Calculation of the results, the two sigma error and the lower limit detection (LLD) in pCi/l: 1 RESULT =

2(3.234) TN VN(C o V)

B)/(CN S  !

'IWO SIGMA ERROR =

2(3.234) TN VN(E)1/2 /(CN V)

S l 12 =

3.3 (3.234)TN VN(E)1/2 /(CN V)S where: TN = tritium units of the standard 3.234 = conversion factor changing tritium units to pC1/1 I VN = volume of the standard used to calibrate the efficiency of the detector in psia I Vs = volume of the sample loaded into the detector in psia CN = the net epm of the standard of volume VN l OG B

=

the gross epm of the sample of volume Vs

the background of the detector in cpm l At E

= counting time for the sample S/T2 + B/t2 I

I I 77 I

ANALYSIS OF SAMPLES FOR STRONTIUM 80 AND 90 Water '

Stable strondum carrier is added to 1 liter of sample and the volume is reduced by evaporadon. Strontium is precipitated as Sr(NO3)2 using l nitric acid. A barium scavenge and an iron (ferric hydroxide) scavenge are performed followed by addluon of stable yttrium carrier and a minimum of 5 g day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re precipitated as oxalate. The yttrium oxalate is mounted on I a nylon planchet and is counted in a low level beta counter to infer Sr 90 activity. Strontium-89 actMty is determined by precipitating SrCO3 rora f the sample after yttrium separadon. This precipitate is mounted on a nylon l planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counung.

I hillh l Stable strontium carrier is added to 1 liter of sample and the sample is first evaporated, then ashed in a muffle furnace. The ash is dissolved and l stronuum is precipitated as phosphate, then is dissolved and precipitated as SrNO3 using fuming (90%) nitric acid. A barium chromate scavenge and an I fron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and I re precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr 90 actMty.

l Strondum 89 is determined by precipitating SrC03 from the sample after yttrium separadon. This precipitate is mounted on a nylon planchet and is l covered with an 80 mg/cm2 aluminum absorber for low level beta counting.

Soil and Sediment The sample is first dried under heat lamps and an aliquot is taken.

ll i

Stable stronuum carrier is added and the sample is leached in hydrachloric acid. The mixture is filtered and stronuum is precipitated from the 11guld g portion as phosphate. Strondum is precipitated as Sr(NO3)2 using fuming

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78

I (90& nitric acid. A barium chromate scavenge and an iron (ferric l hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for yttrium l Ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet I and is counted in a low level beta counter to infer Sr 90 actMty. Strontium-89 activity is determined by precipitaung SrC03 from the sample after yttrium separadon. This precipitate is mounted on a nylon planchet and is I covered with an 80 mg/cm2 aluminum absorber for low level beta counting.

l- Organic Solids I A wet pordon of the sample is dried and then ashed in a muffle furnace. Stable strontium carrier is added and the ash is leached in hydrochloric acid. The sample is filtered and strondum is precipitated from the liquid poruon as phosphate. Strontium is precipitated as Sr(NO3) using fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, l followed by addtuon of stable yttrium carrier and a minimum of 5 days period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, g dissolved and re precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer I strontium 90 actMty. Stronuum 89 actMty is determined by precipitaung SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum l absorber for low level beta counting.

l Air Particulates I Stable strondum carrier is added to the sample and it is leached in nitric acid to bring deposits into soludon. The mixture is then filtered and the filtrate is reduced in volume by evaporadon. Stronuum is precipitated l as Sr(NO3 )2 using fuming (90%) rdtric acid. A barium scavenge is used to remove some interfering species. An iron (ferric hydroxide) scavenge is l performed, followed by addition of stable yttrium carrier and a 7 to 10 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, g dissolved and re precipitated as oxalate. The yttrium oxalate is mounted on I 79 I

a nylon planchet and is counted in a low level beta counter to infer stron-l tium 90 activity. Strontium 89 activity is determined by precipitating SrC03 from the sample after yttrium separation. This precipitate is g mounted on a nylon planchet and is covered with 80 mg/cm2 aluminum absorber for low level beta counting.

Calculations of the results, two sigma errors and lower limits of detection (LLD) are expressed in activity of pC1/ volume or pC1/ mass:

RESULT Sr 89 = (N/Dt DC'UA)/(2.22 V Y3 DFSR 89 ESR 89)

M'O SIGMA ERROR Sr 89 = 2((N/Dt+D C +D A )/ot)1/2/(2.22 V Y3 DFSR 89 ESR 89I LLD St 89 = 4.00((DC+DA)/ot)1/2 (2.22

/ V YS DFSR 89 ESR 39)

RESULT Sr 90 = (N/At D)/(2.22 V Y1Y2DF IF E) l M'O SiOMA ERROR Sr 90 = 2((N/At+D)/At)1/2/ (2.22 Y Y1 Y2DF E IF))

LLD Sr 90 = 4.66(D/ot)1/2/(2.22 V Y1Y2IF DF E)

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I g where: N = total counts from sample (counts) at = counting time for sample (min) l BC u background rate of counter (epm) using absorber configuration 2.22 = dpm/pCi V = volume or weight of sample analyzed

background addition from Sr 90 and ingrowth of Y 90 BA BA

0.016 (K) + (K) EY/ abs)(IG Y 90) l Ys = chemical yield of f.tmntium DF SR 89 = decay factor from the mid collectjon date to the counting l ESR 89 =

date for SR 89 cfficiency of the counter for SR 89 with the 80 mg/cm.sq.

g aluminum absorber K = (Not - BC)Y 90 /(Ey.go IFy.go DFy. goy 1) l DFY 90 = the decay factor for Y 90 from the " milk" time to the mid count time g Ey.go = cfficiency of the counter for Y 90 IFy.go = ingrowth factor for Y 90 from scavenge time to milking time IGY-90 = the ingrowth factor for Y 90 into the strondum mount from the " milk" time to the mid count time 0.016 = the efliciency of measuring SR 90 through a No. 6 absorber EY/ abs

= the efficiency of counting Y-90 through a No. 6 absorber B = background rate of counter (cpm) g Yi = chemical yield of yttrium Y2 = chemical yield of stronuum DF = decay factor of yttrium from the radiochemical milking time to the mid count time E = efficiency of the counter for Y 90 IF = ingrowth factor for Y 90 from scavenge time to the radio-

l. chemical milking time I 81 I

ANALYGIS OF SAMPLES FOR IODINE-131 Milk or Water I 'INvo liters of sample are first equilibrated with stable lodide carrier. A batch treatment with anion exchange resin is used to remove lodine from the I sample. Tne lodine is then stripped from the resin with sodium hypochlorite soluuon, is reduced with hydioxylamine hydrochloride and is extracted into carbon tetrachloride as free iodine. It is then back extracted as iodide into I sodium bisulfite solutJon and is precipitated as palladium iodide. The sodium bisulfite soludon and is precipitated as palladium lodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level I beta counting. The chemical yield is corrected by measuring the stable iodide content of the milk or the water with a specific lon electrode.

I Calculations of results, two sigma error and the lower limit of detection (LLD) in pCl/l:

g RESULT =

(N/At B)/(2.22 E V Y DF)

TWO SIGH 1A ERROR =

2((N/ot+B)/6t)1/2 (2.22

/ E V Y DF) l LLD = /

= 4.66(B/At)1/2 (2.'22 E V Y DF) where: N = total counts from sample (counts)

At = counung time for sample (min)

B = background rate of counter (cpm) 2.22 = dpm/pCi l V = volume or weight of sample analyzed Y = chemical yield of the mount or sample counted DF = decay factor from the collecdon to the counting date I E = efficiency of the counter for 1-131, corrected for self absorpuon effects by the formula Es(exp 0.0061M)/(exp-0.0061Ms)

I E =

Es = efficiency of the counter determined from an I 131 standard mount Ms = mass of Pdl2 on the standard mount, mg g M = mass of PD12 on the sample mount, mg I s:

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g _ GAMMA SPECTROMETRY OF SAMPLES Milk and Water A 1.0 liter Marir.ellt beaker is filled with a representauve aliquot of the sam ale. The sample is then counted for approximately 1000 minutes with a shie ded Ge(L1) detector coupled to a mini-computer based data acquisition system which performs pulse height analysis.

l Dried Solids Other Than Solls and Sediments A large quanuty of the sample is dried at a low temperature, less than l 100'C. As much as possible (up to the total sample) is loaded into a tared 1-liter Marinelli and weighed. The sample is then counted for approximately 1000 minutes with a shielded Oc(LI) detector coupled to a mini computer-l based data acquisluon system which performs pulse height analysis, ne As much as possible (up to the total sample) of the edible portion of the sample is loaded into a tared Marinelli and weighed. The sample is then I counted for approximately 1000 minutes with a shielded Ge(L1) detector coupled to a mini computer based data acquisition system which performs pulse height analysis.

Soils and Sediments I 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 and weighed. The sample is then counted for approximately six hours with a shielded Ge(L1) detector coupled to a mini computer-based data acquisition system which performs pulse height and analysis.

Charcoal Cartridges (Air Iodine)

I Charcoal cartridges are counted up to five at a time, with one positioned on the face of a Ge(L1) detector and up to four on the side of the l Ge(Li) detector. Each Ge(LI) detector is calibrated for both oosidons. The detection limit for I-131 of each charcoal cartridge can ae determined (assuming no positive I-131) uniquely from the volume of air which passed l through it. In the event I-131 is observed in tne initial counting of a set, each charcoal cartridge is then counted separately, posidoned on the face of the detector.

Air Partfeulate I The thirteen airborne particulate filters for a quarterly composite for each field station are aligned one in front of another and then counted for at least six hours with a shielded Ge(L1) detector coupled to a mini-computer-g based data acquisition system which performs pulse height analysis.

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I g A mini computer software program defines peaks by certain changes 3 in the slope of the spectrum, The program also compares the energy of 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 pC1/ volume of pCl/ mass:

I RESULT = (S B)/(2.22 t E V F DF)

I TWO SIGMA ERROR = 2(S+B)1/2 /(2.22 t E V F DF)

LLD = 4.66(B)1/2 /(2.22 t E V F DF) where: S = Area, in counts, of sample peak and background I (region of spectrum of interest)

B = Background area, in counts, under sample peak, l determined by a linear interpolation of the representative backgrounds on either side of the peak I t = length of time in minutes the sample was counted l 2.22 E

=

=

dpm/pC1 detector efficiency for energy of interest g and geometry of sample V = sample aliquot size (liters, cubic meters, kilograms, or grams) g F = fractional gamma abundance (specific for each emitted gamma) g DF = decay factor from the mid collection date to the counting date I

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!I ENVIRONMENTAL DOSIMETRY I

Teledyne isotopes uses a CaSO 4 :Dy thermoluminescent dosimeter I (TLD) which the company manufactures. This material has a high light output, negligible thermally induced signal loss (fading), and negligible self dosing. The energy response curve (as well as all other features) satisfies NRC Reg. Guide 4.13. Transit doses are accounted for by use of separate l TLDs.

Following the field exposure period the TLDs are placed in a Teledyne 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 I 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 use. The transit controls are read in the same manner.

Calculations of results and the two sigma error in net milliroentgen (mR):

RESULT = D = (D +D2 +D3 +D4 )/4 TWO SIGMA ERROR = 2((Dt -D)2+(D2 -D)2+(p3 .D)2+(D4 -D)2)/3)1/2 I WHERE: D1 = the net mR of area 1 of the TLD, and similarly for D2, D 3, and D4 l D1 =

1 1 K/R1-A

= the instrument reading of the fiele, dose in area 1 I 11 K = the known exposure by the Cs-137 source l R1 = the instrument reading due to the Cs-137 dose on area 1 A = average dose in mR, calculated in similar manner I as above, of the transit control TLDs D = the average net mR of all 4 areas of the TLD.

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I I APPENDIX E SUhBIARY OF EPA INTERLABORATORY COMPARISONS I

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US EPA INTERLABORATORY COMPARISON PROGRAM 1990 g (ENVIRONMENTAL)

Collection Teledyne Date Media Nuclide EPA Result (a) Isotopes Result (b) 10/31/89 I Lab Perf.

Water Sample A Gr Alpha Ra 226 Ra 228 49.00 i 8.40 i 4.10 i 12.00 1.30 0.60 42.33 i 9.20 1 4.00 1 5.77 0.46 0.50 I Sample B Gr Beta Sr 89 32.00 1 15.00

• 5.00 5.00 30.33 i 15.00

• 0.58 3.46 Sr 90 7.00 i 1.50 7.00

• 0.00 I Cs 134 Cs 137 5.00 1 5.00 1 5.00 5.00 5.33 i 7.00 1 1.15 0.00 I 11/10/89 Water Ra 226 Ra 228 8.70 i 8.57

• 1.30 1.40 8.47 i 8.57 1 0.49 1.46 01/12/90 Water Sr 89 25.00 1 5.00 24.00 i 1,73 Sr90 20.00 i 1.50 19.67 i 2.52 01/26/90 Water Gr-Alpha 12.0 1 5.0 10.00 1 1,73 Gr Beta 12.0 1 5.0 12.33 i 1.53 02/09/90 Water Co 60 15.00 i 5.00 15.00 1 3.46 I

Zn 65 139.00 i 14.00 131.33 1 9.07 Ru 106 139.00 1 14.00 113.67 1 4.04 (c)

Cs 134 18.00 1 5.00 15.33

• 2.31 Cs 137 I Ba 133 18.00 1 74.00 1 5.00 7.00 19.33 i 66.00 1 3.21 3.46 02/23/90 Water H3 4976.00 i 498.00 4900.00 i 100.00 03/09/90 Water F3 226 4.9 i 0.7 4.73 1 0.47 Ra 228 12.7 1 1.9 13.00 1 1,00 03/30/90 Air Filter Gr-Alpha 5.0 1 5.0 6.33 i 0.58 Gr Beta 31.0 1 5.0 31.67 1 0.58 I St90 Cs 137 10.0 i 10.0 1.5 5.0 9.33 1 10.67 i 0.58 1.15 04/17/90 Water Gr Alpha I (Lab Perf)

Sample A Ra 226 Ra 228 90.0 1 5.0

• 10.2 1 23.0 0.8 1.5 79.33 1 5.67 i 9.37 i 2.89 0.15 1.44 Sample B Gr Beta 52.0 1 5.0 53.33 i 1.53 Sr 89 10.0 1 5.0 10.67 i 1.15 Sr90 10.0 i 1.5 9.67 1 0.58 Cs 134 15.0 1 5.0 12.67 1 1.53 I Cs 137 15.0 i 5.0 16.33 1 1.15 Footnotes at end of table.

e,

US EPA INTERLABORATORY COMPARISON PROGRAM 1000 (Cont.)

I (ENVIRONMENTAL)

I Collection Date Media Nuclide EPA Result (a)

Teledyne Isotopes Result (b) 04/27/90 Milk Sr 89 23.0 1 5.0 24.67 i 1.53 Sr90 23.0 1 5.0 24.00 1 0.00 1131 99.0 1 10.0 89.67 i 3.21 Cs 137 24.0 1 5.0 27.33 1 2.52 K 1550.0 i 78.0 1483.33 i 75.06 I 05/04/90 Water Sr.89 Sr 90 7.0 1 7.0 1 5.0 5.0 6.67 1 6.67 i 0.58 0.58 05/11/90 Water Gr Alpha 22.0 i 6.0 16.00 i 1.03 Gr Beta 15.0 1 5.0 17.00 i 1.00 I 06/08/90 Water Co 60 Zn 65 Ru 106 24.0 1 148.0 i 210.0 5.0 15.0 21.0 25.33 1 148.67 1 196.00 i 2.52 3.06 20.66 I Cs 134 Cs 137 Ba 133 24.0 1 25.0 1 99.0 i 5.0 5.0 10.0 23.67 i 24.67 1 93.00 1 2.89 2.08 6.08 06/22/90 Water H3 2933.0 1 358.0 2900 i 100.00 07/13/90 Water Ra 226 12.1 i 1.8 11.37 i 0.60 Ra 228 5.1 1 1.3 4.20 1 0.75 08/10/90 Water I131 39.0 1 6.0 36.00 1 3.00 08/31/90 Air Filter Gr Alpha 10.0 i 5.0 16.00 i 1.00 (d)

Gr Beta 62.0 i 5.0 63.33 1 1.53 I Sr90 Cs 137 20.0

• 20.0 1 5.0 5.0 18.00 i 18.33 i 1,00 3.21 09'14/90 Water Sr 89 10.0 1 5.0 8.67 1 0.58 Sr90 9.0 1 5.0 9.0 i 1.00 I 09/21/90 Water Gr Alpha Gr Beta 10.0 1 10.0 1 5.0 5.0 11.00 i 11.00 i 1.00 1.00 I

I I rootnotes at end or tadie.

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I US EPA INTERIABORATORY COMPARISON PROGRAM 1000 (cont.)

(ENVIRONMENTAL)

Collection I Date Media Nuclide EPA Result (a)

Teledyne Isotopes Result (b)

I 09/28/90 Milk Sr89 Sr90 1131 16.0 i 20.0 1 58.0 i 5.0 5.0 9.0

• 15.33 i 2.65 (e) 0.58 6.0 54.67 i 1.53 I Cs 137 K

20.0 1 1700.0 i 5.0 85.0 23.00 i 1710.00

• 1.73 65.51 10/15/90 Water Co 60 20.0 i 5.0 21.00 i I Zn 65 Ru 106 115.0 i 151.0 i 12.0 15.0 115.00 i 142.00 i 1.00 11.53 8.66 l

1 Cs 134 12.0

• 5.0 11.00 i 0.00 I Cs 137 Ba 133 12.0 i 110.0 i 5.0 11.0 16.33 i 94.67 i 2.52 5.13 (f)

I 10/30/90 Lab Perf. Gr Alpha 62.00 i 16.00 57.00 i I Water Sampic A Ra 226 Ra 228 13.6 1 5.0 i 2.0 1.3 12.67 i 4.87 i 1.00 1.27 0.23

=

I Sample B Gr Beta Sr 89 Sr90 53.0 1 20.0

• 15.0 5.0 5.0 5.0 51.00 1 19.00 1 14.33 1 2.31 3.61 0.58 I Cs 134 Cs 137 7.0 1 5.0 i 5.0 5.0 9.00 1 7.67 i 0.00 1.15 10/19/90 Water H3 7203.0 1 720.0 7133.33 1 251.66 lI 11/09/90 Water Ra 226 7.4 i 1.1 7.27 i 0.38 Ra 228 7.71 1.9 7.57 0.32 1

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1 I US EPA INTERLABORATORY COMPARISON PROGRAM 1990 (Cont.)

(ENVIRONMENTAL)

I Footnotes:

I (a) EPA Results Expected laboratory precision (1 sigma). Units are pCl/ liter for water and milk except X is in mg/ liter. Units are total pCi for air particulate filters.

(b) Teledyne Results . Average i one sigma. Units are pCl/ liter for water and milk except K is in mg/ liter. Units are total pCi for air particulate filters.

(c) No apparent cause for the low results were found. Three aliquots of the r> ample were counted on three separate detectors. The results of all three were similar. The calibration I curve fit is good (0.997). Ruthenlutn 100 was obtained from the EPA. Results of spikes were acceptable. Subsequent cross checks from the EPA did not exceed two normalized standard deviations. No additional follow.up is necessary, but we will continue to monitor the results. New calibrations were completed in March,1991.

(d) The EPA deposit occupies a smaller area than our calibration planchet and hence has a higher counting efficiency. No further corrective action is required, since our calibration standard better represents an air particulate filter.

(e) Incomplete removal of calcium, lead to erroneously high strontium yields More care is being taken in the strontium nitrate and strontium sulfate precipitation steps to ensure a I final volume of at least 20 ml in the strontium sulfate step. Reanalysis of internal QC samples produced good results after implementing the corTective action.

I (O There is no apparent reason for the deviation between the EPA and Teledyne Isotopes values. Other isotopes in the sample were measured accurately. The calculations were reviewed and activities calculated from other Da.133 gamma rays. Results were reproduced as reported.

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1lle and in the Shoreham Record Retrieval System. Environmental Engineering identifies nearest residences by utilizing both aerial photography and visual confirmatJon. This year's census was I conducted in November and December. Table G 3 lists the nearest residence in each meteorological sector. I I I I I I I I I I I 116 I I TABLE G-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 1990 Land Use Census l Nearest Milk Animal (within 8 km)* ( Sector 1 Direction N Lpeation Area within sector is long Island Sound 2 NNE None r 3 NE None 1 4 ENE None g 5 E None l 6 ESE None 7 SE None ' 8 SSE None il l l 9 S None g 10 SSW None i 11 SW Shoreham - Wading River Middle School l Randall Road, Shoreham 12 WSW None l 13 W C.B. Pocle residence, Briarcliff Road, Shoreham

l. 14 WNW None 15 NW Area within sector is Long Island Sound 16 NNW Area within sector is Long Island Sound ll l

l SNPS ODCM Pan 1. Secuon 3/4.12.2 l 117 I TABLE G 2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 1990 land Use Census k Nearest Garden (> 50m2 within 8 km)* Sector Garden Code # Location & Direction g 1 - Area within sector is Long Island Sound 2 - Nonc 3 - None l 4 4A10 (5A13 on map) Mistano, Little Bay Road, Wading Ryer, 4642' ENE of SNPS I 5 5A11 Loggia, Little Bay Road, Wading River, 3978' E, of SNPS. I 6 7 6A12 Punda, Sound Ave., Wading PAer, 4343' ESE of SNPS. 7B12 Muller, Dogwood Dr., Wading River. l j 6823' SE of SNPS 8 8A14 Pierzchanowsid, Randall Road, Wading (8B1) River 5191' SSE of SNPS ) 9 9B14 Smith, Randall Road, Wading River, g 6027' S of SNPS. 10 10A15 Pierce, Defense Hill Road, Shoreham, , 5000' SSW of SNPS [ 11 11B31 Marcott, Jomarr Road, Shoreham 7246', SW of SNPS i ! 12 12B31 Murtash, Harvard Road, Shoreham,  ! l 6401' SW of SNPS 13 13B22 Connoly, Valentine Road, Shoreham,

4893' W of SNPS h 14 -

None f 15 - Area within sector is.Long Island Sound 16 - Area within sector is Long Island Sound SNPS ODCM Part 1. Section 3/4.12.2 118 l-1 IL TABLE G-3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 1990 Land Use Census Nearest Residence (within 8 km)* Sector Direction location 1 N Area within sector is Long Island Sound 2 NNE Thurber-Creek Road, Wading River, 1503' from SNPS S NE Creek Road, Wading River,1916' from SNPS (First house east of Field and Tennis Club), 4 ENE Hughes-Creek Road, Wading River, 3444' from SNPS (fifth house west of Riverhead I- Town Beach) 5 E Peterson-Sound Road, Wading River, 3598' l_ , from SNPS 6 ESE - Bartow-Sound Road, Wading River, 2917' l 7 from SNPS SE Larsen-North Country Road and Thomas l 8 SSE Drive, Wading River, 3304' from SNPS North Country Road, fourth house west of -E Pheasant Run, Wading River, 2588' from E' SNPS I 9 S Fugelsang- 20 Long Bow, Wading River, 3839' from SNPS 10 I SSW 16 Defense Hill Road, Wading River, 4877' from SNPS 11 SW 170 North Country Road, Wading River, I 1632' from SNPS 12 WSW Gildea-Valentine Road, Shoreham, 5557' from SNPS 13 W Brice, 55 Valentine Road, Shoreham, 4620' l

• SNPS ODCM Part I, Secuon 3/4,12.2 from SNPS I 119 I

TABLE G 3 (cont.) .g Sector Direction Incation 14 WNW St. Joseph's Villa, Wading River, 2178' from SNPS 15 NW Area within sector is Long Island Sound 16 NNW Area within sector is Long Island Sound I I I I I I I I I I I I  :

• SNPS ODCM Part 1. Section 3/4.12.2 120 I

l l t l l3 lI lg APPENDIX H i COMMON AND SCIENTIFIC NAMES OF  ! 'l SPECIES COLLECTED IN THE REMP l l lI LI - 1 I 121 TABLE H 1 COMMON AND SCIENTIFIC NAMES OF SPECIES COLLECTED IN THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Common Name Scientific Name Elah 1 Winter Flounder Pseudopleuronectes americanus l Windowpane Ecophthalmus aquosus 1 Searobin Prionotus spp. l Little Skate Baia erinac.ca Fluke

l. Parallchthys dentatus I

I Invertebrates American Lobster Homarus americanus Squid Loligo pealell Channeled Whelk Busvcon canaliculata II l l 1 I 122 __ .________/_-__-_-_-___--___-_-_____ .I !I I I I I~ I I APPENDIX I 1989 ERRATA I I I I I I I I 123 I m m M M M M m W m m m m m m M Revised 1989 Annual Report Data RADIGIEGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SIIOREfIAM NUCLEAR POWER STATION DOCKET NO. 50-322 SUFFOlK COUN'IY. NEW YORK JANUARY I to DECEMBER 31.1989 ANALYSIS AND IDWER IJMrF NUMi1ER OF MEDIUM OR PAT 11WAY 1UTAL NUMBER OF All. INDICATOR IDCAT10NSf31 IDCATION WTT1f IllCitEST MEAN CONTROf.IDCAT10N(3) NONROUTINE OF ANALYSES DETECTION MEAN (2) NAME MEAN(2) MEAN(2) RETORTED SAMPLED MEASUREMENTS (11D) (1) RANCE DISTANCE AND DIRECTION RANCE RANCE (UNTT OF MEA.PJREMENIl PERfDRMED sett Sr-90 10 0.9 22.5(4/9) 8A3 0.6 mi SSE 35(1/1) -(0/I) O l (pCi/kg dry) (15-35) - -

Gamma 10 K-43 900 3492(9/9) 5F3 7.8 mi E 7060(1/1) 7060(I/1) O g (1800-6400) - -

u Cs- 137 10 252(7/9) 8A3 0.6 mi SSE 532(l/1) 169(I/1) O (37.7-456) - -

Ra-226 300 83315/9) 5F3 7.8 ml E 1620(1/1) 1620(1/1) 0 (604-1180) - -

Th-228 60 527(9/9) 5F3 7.8 mi E I300(l/1) 1300(l/1) O

-(256-947) - -

(1) The 11Ds quoted are the lowest actual IlDe obtained in :tw= vartenss media during the repcuttrg sustod. tral llDs were detennined for each ruxhde as found on Tables C-20 and C-21.

(2) Means calculated ueng detectalde measurements only. IYactione c4 deteriatAc u.;w. ...c ..:s in parent .

(3) trutrator arut control locations a.T ruded in Appendix 11. Table B- 1.

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