ML17353A648

1995 Annual Radiological Environ Operating Rept for Turkey Point Plant Units 3 & 4. W/960423 Ltr

ML17353A648
Person / Time
Site:	Turkey Point
Issue date:	12/31/1995
From:	HOVEY R J FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-96-094, L-96-94, NUDOCS 9604260191
Download: ML17353A648 (105)

Text

{{#Wiki_filter:CATEGORY.: 1 REGULATOR INFORMATION DIS RI UTION OSTEM.(RIDE)gd,Z 43 ACCESSION NBR 9604260191 DOC.DATE: 95/1/31 NOTARIZED: NO DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH.NAME AUTHOR AFFILIATION

• Florida Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

1995 Annual Radiological Environmental Operating Rept for TPS units 3 6 4.DISTRIBUTION CODE: IE25D COPIES RECEIVED:LTR 1 ENCL i SIZE: TITLE: Environmental Monitoring Rept (per Tech Specs)NOTES: INTERNAL.R ECIPIENT ID CODE/NAME PD2-1 LA RGN2 FILE EXTERNAL: LITCO AKERSFD COPIES LTTR ENCL 3 3 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD2-1 PD NRR/DRPM/PERB NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 D U E N NOTE TO ALL"RIDS" RECIPIENTS: PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT.415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 10 gr l ~, 1' NPR 83 Inaq L-96-094 10 CFR 550.36b U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gentlemen: Re: Turkey Point Units 3 and 4 Docket Nos.50-250 and 50-251 1995 Annual Radiological Environmental 0 eratin Re ort Attached is the 1995 Annual Radiological Environmental Operating Report for Turkey Point Units 3 and 4, as required by Technical Specification 6.9.1.3.Should there be any questions, please contact us.Very truly yours, R.J.Hovey Vice President Turkey Point Plant Attachment cc: S.'.Ebneter, Regional Administrator, Region IZ, USNRC T.P.Johnson, Senior Resident inspector, USNRC, Turkey Point Plant 9604260i9i 95i23i PDR ADOCK 05000250 R PDR an FPL Group company 1995 ANNUAL RADIOLOGICAL ENVIRONNENTAL OPERATING REPORT TURKEY POINT PLANT UNITS 3&4 LICENSE NOS.DPR-31, DPR-41 DOCKET NOS.50-250, 50-251 Data submitted by: Prepared by: Reviewed by: Florida DHRS 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT-UNITS 3 Ec 4 TABLE OF CONTENTS DESCRIPTION PAGE Introduction Radiological Environmental Monitoring Program Discussion and Interpretation of Results Environmental Radiological Monitoring Program Annual Summary TABLE 1 Deviations/Missing Data TABLE 1A Analyses with LLDs Above Table 4.12-1 Detection Capabilities TABLE 1B Land Use Census TABLE 2 Key to Sample Locations ATTACHMENT A Radiological Surveillance of Florida Power and Light Company's Turkey Point Site First Quarter, 1995 Second Quarter, 1995 Third Quarter, 1995 Fourth Quarter, 1995 ATTACHMENT B Results from the Interlaboratory Comparison Program, 1995 ATTACHMENT C 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT-UNITS 3 Ec 4 EXECUTIVE

SUMMARY

The data obtained through the Turkey Point Radiological Environmental Monitoring Program verifies that the levels of radiation and concentrations of radioactive materials in environmental samples are not increasing. These measurements verify that the dose or dose commitment to members of the public, due to operation of Turkey Point Units 3 6 4, during the surveillance year, is well within the limits established by 10 CFR 50, Appendix I.The sampling period was from January 1, 1995 to December 31, 1995.Additionally, supplemental samples collected by the State of Florida, HRS, do not indicate adverse trends in the radiological environment. 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT-UNITS 3&4 INTRODUCTION This report is submitted pursuant to Specification 6.9 of Turkey Point Units 3&4 Technical Specifications. The Annual Radiological Environmental Operating Report provides information, summaries and analytical results pertaining to the Radiological Environmental Monitoring Program for the calendar year indicated. This report covers surveillance activities meeting the requirements of Unit 3 and Unit 4 Technical Specifications. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM A.~Pur use The purpose of the Radiological Environmental Monitoring Program is to provide representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of members of the public resulting from station operation. The Radiological Environmental Monitoring Program also supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways.B.Pro ram Descri tion The Radiological Environmental Monitoring Program (REMP)for the Turkey Point Plant is conducted pursuant to Technical Specifications 3/4.12 of Turkey Point Unit 3 E 4 Technical Specifications. 1.Sample Locations, Types and Frequencies: a.Direct radiation gamma exposure rate is monitored continuously at 21 locations by thermoluminescent dosimeters (TLDs).TLDs are collected and analyzed quarterly. b.Airborne radioiodine and particulate samplers are operated continuously at five locations. Samples are collected and analyzed weekly.Analyses include Iodine-131, gross beta, and gamma isotopic measurements. 0 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT-UNITS 3 8c 4 c.Surface water samples are collected from three locations. Samples are collected and analyzed monthly.Analyses include gamma isotopic and tritium measurements. d.Shoreline sediment samples are collected from three locations coinciding with the locations for surface water samples.Samples are collected and analyzed semi-annually. Sediment samples are analyzed by gamma isotopic measurements. e.Fish and invertebrate samples are collected from two locations coinciding with two of the locations for surface water samples.Samples are collected and analyzed semi-annually. Fish and invertebrate samples are analyzed by gamma isotopic measurements. f.Broad leaf vegetation samples are collected from three locations. Samples are collected and analyzed monthly.Broad leaf vegetation samples are analyzed by gamma isotopic measurements. Attachment A provides specific information pertaining to sample locations, types and frequencies. 2.Analytical Responsibility: Radiological environmental monitoring for the Turkey Point Plant is conducted by the State of Florida, Department of Health and Rehabilitative Services (HRS).Samples are collected and analyzed by HRS personnel. Samples are analyzed at the HRS Environmental Radiation Control Laboratory in Orlando, Florida.CD Anal tical Results Table 1, Environmental Radicle ical Monitorin Procrram Annual~Summar provides a summary for all specified samples collected during the referenced surveillance period.Deviations from the sample schedule, missing data and/or samples not meeting the specified"A PRIORI" LLD, if any, are noted and explained in Tables 1A and 1B respectively. Analysis data for all specified samples analyzed during the surveillance period is provided in Attachment B.

1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT-UNITS 3&4 D.Land Use Census A land use census out to a distance of 5 miles radius from the Turkey Point Plant is conducted annually to determine the location of the nearest milk animal, residence, and garden producing broad leaf vegetation, in each of the sixteen meteorological sectors.A summary of the land use census for the surveillance year is provided in Table 2, Land Use Census~Summaz No locations yielding a calculated dose or dose commitment greater than the values currently being calculated were identified by the land use census.No locations yielding a calculated dose or dose commitment (via the same exposure pathway)20%greater than locations currently being sampled in the radiological environmental monitoring program were identified by the land use census.E.Interlaborator Com arison Pro ram The State of Florida HRS Environmental Radiation Control Laboratory participates in the Environmental Radioactivity Laboratory Intercomparison Studies Program conducted by the Environmental Protection Agency.Results from the Interlaboratory Comparison Program are provided in Attachment C.III.DISCUSSION AND INTERPRETATION OF RESULTS A.Re ortin of Results The Annual Radiological Environmental Operating Report contains the summaries, interpretations and information required by the Turkey Point Units 3 6, 4 Technical Specifications. Table 1 provides'summary of the measurements made for the nuclides required by Technical Specifications, Table 3.12-2, for all samples specified by Table 3.12-1.In addition, summaries are provided for other nuclides identified in the specified samples, including those not related to station operation. These include nuclides such as K-40, Th-232, Ra-226, and Be-7 which are common in the Florida environment. 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT-UNITS 3&4 B.Inter retation of Results 1.Direct Radiation: The results of direct radiation monitoring are consistent with past measurements for the specified locations. The exposure rate data show no indication of any trends attributed to effluents from the plant.The measured exposure rates are consistent with exposure rates that were observed during the preoperational surveillance program.Direct radiation monitoring results are summarized in Table 1.2.Air Particulates/Radioiodine: Results of gross beta measurement are consistent with past measurements. No radioiodine was detected.The only identified isotopes are cosmic-ray produced Be-7 and naturally occuring K-40 and Pb-210 at levels consistent with past measurements. 3.Waterborne, Surface Water: The results of radioactivity measurements in surface water samples are consistent with past measurements. Tritium was reported as present in the surface water samples collected from site T-81.These results are consistent with the known subsurface interchange that occurs between the closed cooling canal and its surrounding waters, and the pressure gradients caused by the flow of aquifer subsurface waters in South Florida.The highest reported tritium is less than 2%of the reporting value specified by Technical Specifications, Table 3.12-2.4.Waterborne, Sediment: The results are consistent with past measurements; only naturally occurring radionuclides were detected.5.Waterborne, Food Products: The results are consistent with past measurements; only naturally occurring radionuclides were detected. 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT-UNITS 3 Sc 4 6.Broad Leaf Vegetation: The results of radioactivity measurements are consistent with past measurements. Cs-137 was detected, as in the past, in samples collected from the indicator locations. The maximum value is about 35%of the Table 3.12-2 reporting level, the average value is about 7%of the reporting level.No other fission products were detected.C.Conclusions The data obtained through the Turkey Point Plant Radiological Environmental Monitoring Program verify that the levels of radiation and concentrations of radioactive materials in environmental samples, representing the highest potential exposure pathways to members of the public, are not being increased. Additionally, supplemental to the Technical Specifications, sampling of the direct exposure, inhalation, and ingestion pathways, performed by HRS, does not show adverse trends in levels of radiation and radioactive materials in unrestricted areas.The measurements verify that the dose or dose commitment to members of the public, due to operation of Turkey Point Units 3 8 4, during the surveillance year, are well within"as low as reasonably achievable (ALMS)" criteria established by 10 CFR 50, Appendix X. Je 0 0 TABL 1 Pag 1 of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3 6 4 , Docket No(s).50-250&50-251 Location of Facility Dade Florida , Reporting Period Janua 1-December 31 1995 (County, State)PATHWAY: DIRECT RADIATION SAMPLES COLLECTED: TLD UNITS: micro-R/hr Type and Total Number of Analyses Performed Lower Limit of Detection'LLD) All Indicator Locations Mean (f)Range Distance 6 Direction Range Location with Highest Annual Mean Name'ean f Control Locations Mean (f)h Range Exposure Rate, 84 5.27 (80/80)4.37-8.16 NW-10 10 mi., NW 7.62 (4/4)7.27-8.16 5.78 (4/4)5.14-6.04 Number of Nonroutine Reported Measurements =0 TAB%1 Pag 2 of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3&4 , Docket No(s).50-250 k 50-251 Location of Facility Dade Florida , Reporting Period Januar 1-December 31 1995 (County, State)PATHWAY: AIRBORNE SAMPLES COLLECTED: RADIOIODINE AND PARTICULATES UNITS: pCi/m'ype and Total Number of Analyses Performed Tower Limit of Detection'LLD) All Indicator Locations Mean (f)Range Distance E Direction Range Location with Highest Annual Mean Name'ean f b Control Locations Mean (f)b Range 131I 260 0.024<MDA<MDA Gross Beta, 259 Composite Gamma Isotopic, 20'Be 210pb 0.0025 0.0052 0.012 (201/207)0.003-0.024 0'256 (16/16)0.0904-0.1467 0.0116 (15/16)0.0098-0.0135 T-72<1 mi., WSW T-58 1 mi., NW T-72<1 mile, WSW 0.012 (51/52)0.003-0.024 0.1317 (4/4)0'99-0.1455 0.0118 (4/4)0.0105-0.0133 0.013 (52/52)0.004-0.025 0.1303 (4/4)0.1043-0.1446 0.0135 (4/4)0.0116-0.0159 134Cs 137CS 0.00069 0.00066<MDA<MDA<MDA<MDA Number of Nonroutine Reported Measurements =0 4 TAB%1 Pag 3 of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3&4 , Docket No(s).50-250&50-251 Location of Facility Dade Florida , Reporting Period Janua 1-December 31 1995 (County, State)PATHWAY: WATERBORNE SAMPLES COLLECTED: SURFACE WATER UNITS: pCi/L Type and Total Number of Analyses Performed Lower Limit of Detection'LLD) All Indicator Locations Mean (f)Range Distance&Direction Range Location with Highest Annual Mean Name'ean f Control Locations Mean (f)b Range Tritium, 36 Gamma Isotopic, 36 40'Mn"Fe 58Co 60Co 6Szn ssZr-Nb 131 I 134CS 137 Cs 140B L 230 60 144 (10/24)119-345 294 (24/24)86-347<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA T-81 6 mi., S T-81 6 mi., S 144 (10/12)119-345 246 (12/12)86-347<MDA 181 (11/12)94-249<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA Number of Nonroutine Reported Measurements =0 0 0 TAB%1 Pag 4 of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3&4 , Docket No(s).50-250 E 50-251 Location of Facility Dade Florida , Reporting Period Janua 1-December 31 1995 (County, State)PATHWAY: WATERBORNE SAMPLES COLLECTED: SHORELINE SEDIMENT UNITS: pCi/kg, DRY Type and ToŽtal Number of Analyses Performed Lower Limit of Detection'LLD) All Indicator Locations Mean (f)Range Dz.stance&, Direction Range Location with Highest Annual Mean Name'ean f Control Locations Mean (f)~Range Gamma Isotopic, 6'Be 40K 226Ra 238U"Co 60Co n4Cs 137CS 100 140 52 12 12 408 (2/4)378-438 369 (4/4)305-431<MDA 809 (4/4)645-965 638 (1/4)<MDA<MDA<MDA<MDA T-42<1 mi., ENE T-42<1 mi., ENE T-42<1 mi., ENE T-42<1 mi., ENE 438 (1/2)392 (2/2)354-431 860 (2/2)754-965 638 (1/2)142 (1/2)246 (2/2)243-249 55 (1/2)110 (1/2)<MDA<MDA<MDA-<MDA<MDA Number of Nonroutine Reported Measurements =0 TAB%1 Pag 5 of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3&.4 , Docket No(s).50-250&50-251 Location of Facility Dade Florida , Reporting Period Janua 1-December 31 1995 (County, State)PATHWAY: INGESTION SAMPLES COLLECTED: CRUSTACEA UNITS: pCi/kg, WET Type and ToŽtal Number of Analyses Performed Lower Limit of Detection'LLD) All Indicator Locations Mean (f)Range Da.stance&Direction Range Location with Highest Annual Mean Name'ean f b Control Locations Mean (f)b Range Gamma Isotopic, 4"K 226Ra"Mn 130 20 1850 (2/2)1798-1901 641 (2/2)436-846<MDA T-81 6 mi., S T-81 6 mi., S 1850 (2/2)1798-1901 641 (2/2)436-846 1552 (2/2)1317-1787<MDA<MDA"Fe"Co 60Co Zn 134Cs l37Cs 16 19 17<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA Number of Nonroutine Reported Measurements =0 TAB 1 Pag 6 of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3 8 4 , Docket No(s).50-250 E 50-251 Location of Facility Dade Florida , Reporting Period Janua 1-December 31 1995 (County, State)PATHWAY: INGESTION SAMPLES COLLECTED: FISH UNITS: pCi/kg, WET Type and ToŽtal Number of Analyses Performed Lower Limit of Detection'LLD) All Indicator Locations Mean (f)Range Dz.stance&Direction Range Location with Highest Annual Mean Name'ean f b Control Locations Mean (f)D Range Gamma Isotopic, 4 40K"Mn"Fe 58Co 60Co Zn 134 CS 137CS 130 16 10 2409 (2/2)2198-2620<MDA<MDA<MDA<MDA<MDA<MDA<MDA T-81 6 mi., S 2409 (2/2)2198-2620 2590 (2/2)2309-2870<MDA<MDA<MDA<MDA<MDA<MDA<MDA Number of Nonroutine Reported Measurements =0 tr'0 0'AB%1 Pag 7 of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3&.4 , Docket No(s).50-250&50-251 Location of Facility Dade Florida , Reporting Period Janua 1-December 31 1995 (County, State)PATHWAY: INGESTION SAMPLES COLLECTED: BROAD LEAF VEGETATION UNITS: pCi/kg, WET Type and Total Number of Analyses Performed Lower Limit of Detection'LLD) All Indicator Locations Mean (f)Range Distance E Direction Range Location with Highest Annual Mean Name'ean f Control Locations Mean (f)~Range Gamma Isotopic, 36'Be 40K 137CS 210pb 131I 134 Cs 71 100 2105 (24/24)688-3635 4146 (24/24)2341-6175 74 (23/24)15-349 827 (7/24)574-1141<MDA<MDA T-40 3 mi., W T-41 2 mi., W/NW T-40 3 mi., W T-40 3 mi., W 2114 (12/12)1565-3408 4941 (12/12)3576-6175 91 (11/12)'15-349 961 (3/12)715-1141 1235 (12/12)699-1779 3943 (12/12)3143-5511<MDA 724 (1/12)<MDA<MDA Number of Nonroutine Reported Measurements =0 0 TAB 1 Pa 8 of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3&.4 , Docket No(s).50-250&50-251 Location of Facility Dade Florida , Reporting Period Janua 1-December 31 1995 (County, State)NOTES a.b.C.d.The LLD is an"a priori" lower limit of detection which establishes the smallest concentration of radioactive material in a sample that will~ield a net count above system backqround that will be detected with 95';probability with on y 5'-.probability of falsely conclucling that a blank observation represents a real signal.LLDs in this column are at time of measurement. The MDAs reported in Attachment B for the individual samples have been corrected to the time of sample collection. Mean and range based upon detectable measurements only.Fraction of detectable measurements-at specified locations is indicated in parentheses (f).Specific identifying information for each sample location is provided in Attachment A.Results are based upon the average net response of two TLDs.(Thermoluminescent dosimeters). MDA refers to minimum detectable activity. 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3&4 TABLE 1A DEVIATIONS/MISSING DATA Page 1 of 2 A)Pathway: Direct Exposure-TLDs Location (Sector, Dist.Miles)SW-1 SW-8 W-5 SSW-10 Quarter&Date of Missing Data 1, 12/7/94 to 3/15/95 1, 12/7/94 to 3/15/95 3, 6/7/95 to 9/13/95 4, 9/13/95 to 12/13/95 Deviation: Description of Problem: Failure to provide continuous monitoring. TLDs were missing when collection was attempted. Corrective Action: Replaced TLDs.B)Pathway: Location Airborne-Radioiodines &particulates, weekly sampling.Sampling Period 4 Typ Sample T-51 T-57 T-57 T-72 T-72 2 mi., NNW 4 mi., NW 4 mi., NW<1 mi., WSW<1 mi., WSW 3/21/95 to 3/28/95 3/21/95 to 3/28/95 12/7/95 to 12/12/95 8/15/95 to 8/23/95 8/23/95 to 8/29/95 97'o 90%96%89%96%Deviation: Description o f Problem: Corrective Action: Failure to provide continuous monitoring. Suspected power interruptions during sampling period, based upon integrated sample volume not meeting expectations. Verified operability of the sampling equipment; note, the sampling pumps self-start at the end of a power interruption. 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3&4 TABLE 1A DEVIATIONS/MISSING DATA Page 2 of 2 C)Pathway: Location: Dates: Deviation: Description of Problem: Corrective Action: Airborne-Radioiodines E Particulates, weekly sampling T-57, 4 miles NW 11/27/95 to 12/7/95 Failure to provide continuous monitoring. Sampling station destroyed by abandoned car that was set on fire.Station destroyed about 22 hours into sampling period.Sampling, station replaced and power restored. 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Ec 4 TABLE 1B ANALYSES WITH LLDs ABOVE TABLE 4.12-1 DETECTION CAPABILITIES 1/1/95-12/31/95 The values specified in Table 4.12-1, Detection Capabilities, were achieved for all samples.

1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Ec 4 TABLE 2 LAND USE CENSUS Distance to Nearest a b Sector 6/95 Milk (c)Animal 6/95 Residence 6/95 Garden (d)N NE ENE L (e)0 (f)0 2.j./350 (g)0 0 0 ESE SSE SSW 0 0 0 0 L WSW L 3.6/302 (11)L (g)4.7/328 L 4.3/303 3.6/308 4.0/328 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Sc 4 TABLE 2 LAND USE CENSUS NOTES All categories surveyed out to 5 miles radius from the Turkey Point Plant.The following format is used to denote the location: distance (miles)/bearing (degrees)For example, a residence located in the north sector at a distance of 2.1 miles bearing 350 degrees is recorded as 2.1/350.Potential milk animal locations. Gardens with an estimated growing area of 500 square feet or more.L denotes that the sector area is predominantly a land area unoccupied by the category type.0 denotes that the sector area is predominantly an ocean area.Non-residential occupied buildings in these sectors include the following: Sector Distance Descri tion N 1.8/349 NW 3.5/304 NNW 4.5/327 NNW 1.8/345 24-hour Security Staffing Building 24-hour Security Staffing Mobile homes used for field offices Security booth at park entrance This house has been converted into a construction office lf 0 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3&4 ATTACHMENT A KEY TO SAMPLE LOCATIONS 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 5: 4 4NNW-2"~" M@KPAYm=+N-2 I Convoy Point Pl%I'C: OI7bClCOh OUght V J C I=e-4"-41~=A{.{~$A,!NW-1" T-58 B S I C A Y N E B:, A{YI I$hI~F~$%$$$$~$$$$$$$$$$2{l.T 72 I~g 5{{bt{a{0'h.T-71 ATt p.L'oa~'$~,.;==--.'$$$$$$~$$%$$$Turkey Point T-42 B!I I S.Q TH r".Q-'W-1;- SSE-1 Turtle Point Y, N E I A Y//".~M Turkey Point Sampling Locations Plant Site Area 0 0 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3&.4 l I I, u i rrr NNE-22 T-64,12 miles 8 , T-67 4 SDA St tCt I NNW-10 044ICI Cull>>>44>>.N-10 5 NW-10 IAC\ICA~4~~>l.O.S OA>>tl 4>4 A I 4 r>>A PIS CISCA>>l>S WNW-10 C~rtrltfl>>4, 4~~~r Al~>>J>>C NW-5 T-57 A,>>>>I II Al IQ>>AA AAAC T-52I l W-9 5>>>Stt 5 T-40 I>>>>>l>>SSAC>Ct AA AO>>>>STASCI>>WSW-Q, OAOS CO wO~4 CA>>I~AO MODEL LAND'CANAL SW-8 I SSW-5 I I~S-5 IA r 4 T-81~4>>>>4 P$P'i C,'>>-" t>>4 g 5~0 SSW-10/I S-10 Turkey Point Sampling Locations o 8 SSE-10 ,I I>'~~A>>VI>SAIC mI>((l 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Sc 4 ATTACHMENT A Page 1 of 4 PATHWAY: DIRECT RADIATION SAMPLES COLLECTED! TLD SAMPLE COLLECTION FREQUENCY: QUARTERLY Location"'ame Descri tion N-2 N-7 N-10 NNW-2 NNW-10 NW-1 NW-5 NW-10 WNW-10 W-5 W-9 WSW-8 SW-1 SW-8 SSW-5 SSW-10 S-5 S-10 SSE-1 SSE-10 Control NNE-22 Convoy Point, Parking Area Black Point Marina Parking Lot Old Cutler Rd.approx.196th Street East End North Canal Road Bailes Road 6 U.S.¹1 Turkey Point Entrance Road Mowry Drive E 117th Avenue Newton Road, North of Coconut Palm Drive Homestead Middle School On-Site, North Side of Discharge Canal Palm Drive&Tallahassee Road Card Sound Road, 0.6 mile from U.S.¹1 Card Sound Road, 3.4 miles from U.S.¹1 On-Site near Land Utilization Offices Card Sound Road, 5 miles from U.S.¹1 On-Site, Southwest Corner of Cooling Canals Card Sound Road, west side of Toll Plaza On-Site, South East Corner of Cooling Canals Card Sound Road at Steamboat Creek Turtle Point Ocean Reef Natoma Substation '"The location name is the direction sector-approximate distance (miles) 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 R 4 ATTACHMENT A Page 2 of 4 PATHWAY: AIRBORNE'I SAMPLES COLLECTED: RADIOIODINE AND PARTICULATES SAMPLE COLLECTION FREQUENCY: WEEKLY Location Name Direction Sector Approximate Distance Descri tion T-51 T-57 T-58 T-72 WSW Entrance Area to Biscayne National Park SW 107th Avenue at Mowry Canal Turkey Point Entrance Road Just before entrance to Land Utilization's access gate.Control: T-64 22 Natoma Substation 0 0 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3&4 ATTACHMENT A Page 3 of 4 PATHWAY: WATERBORNE SAMPLES COLLECTED: SURFACE WATER (OCEAN)SAMPLE COLLECTION FREQUENCY: MONTHLY Location Name Direction Sector Approximate Distance miles Descri tion T-42 T-81 ENE Biscayne Bay at Turkey Point Card Sound, near Mouth of Old Discharge Canal Control:-67 N, NNE 13-18 Near Biscayne Bay, Vicinity of Cutler Plant, North to Matheson Hammock Park SAMPLES COLLECTED: SHORELINE SEDIMENT SAMPLE COLLECTION FREQUENCY: SEMI-ANNUALLY Location Name T-42 T-81 Direction Sector ENE Approximate Distance miles Descri tion Biscayne Bay at Turkey Point Card Sound, near Mouth of Old Discharge Canal Control: T-67 N, NNE 13-18 Near Biscayne Bay, Vicinity of Cutler Plant, North to Matheson Hammock Park 0 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3&4 ATTACHMENT A Page 4 of 4 PATHWAY: INGESTION SAMPLES COLLECTED: CRUSTACEA AND FISH SAMPLE COLLECTION FREQUENCY: SEMI-ANNUALLY Location Name T-81 Direction Sector Approximate Distance miles Descri tion Card Sound Vicinity of Turkey Point Facility Control: T-67 N, NNE 13-18 Near Biscayne Bay, Vicinity of Cutler Park, North to Matheson Hammock Park SAMPLES COLLECTED: BROAD LEAF VEGETATION SAMPLE COLLECTION FREQUENCY: MONTHLY Location Name Direction Sector Approximate Distance Descri tion T-40 T-41 South of Palm Dr.on S.W.117th Street Extension Palm Dr., West of Old Missile Site near Plant Site Boundary Control: T-67 N, NNE 13-18 Near Biscayne Bay, Vicinity of Cutler Park, North to Matheson Hammock Park 00 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 9, 4 ATTACHMENT B RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE 1995 First Quarter, 1995 Second Quarter, 1995 Third Quarter, 1995 Fourth Quarter, 1995 RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE First Quarter, 1995 Office of Radiation Control Florida Department of Health and Rehabilitative Services TURKEY POINT SITE Technical Specifications Sampling First Quarter, 1995 Sam le T e Collection Fre enc Locations Number of 1.Direct Radiation Quarterly 22 20 2.Airborne 2.a Air Iodines 2.b Air Particulates 'Weekly Weekly 65 69*3.Waterborne 3.a Surface Water 3.b Shoreline Sediment Monthly Semiannually 3'3 4.Ingestion 4.a Fish and Invertebrates 4.a.l Crustacea 4.a.2 Fish Semiannually Semiannually 4.b Food Products 4.b.l Broadleaf Vegetation Monthly Total: 178*-Includes NRC split samples.NOTE: Measurement results having magnitudes that are significantly above the background of the measurement system are reported as net values plus or minus a one-standard-deviation error term.Measurement results that are not significantly above background are reported as"non-detectable" (ND)or as less than a Lower=-Limit of Detection (<LLD),.which is an estimated upper limit (with at least 954 confidence) for the true activity in the sample. DIRECT RADIATION-TLDs-micro-R hour Sample Site Deployment 12-07-94 Collection 03-15-95 N-2 N-7 N-10 6.28+0.30 5.68+0.30 5.38+0.29 NNW-2 NNW-10 5.32+0.35 5.72+0.29 NW-1 NW-5 NW-10 4.68+0.36 (A)5.25+0.30 8.16+0.26 7.07+0.30 W-1 W-5 W-9 WSW-8 6.57+0.36 (A)5.23+0.30 4.68+0.30 5.19+0.30 SW-1 SW-8 SSW-5 SSW-10 (B), (B)5.17+0.36 5.27+0.30 S-5 S-10 (A)5.79+0.36 5.99+0.30 SSE-1 SSE-10 5.40+0.36 6.37+0.31 NNE-22 6.04+0.36 (A)-The dosimeters for sites NW-5, W-5, and S-5 were found lying'on the ground.Also, the wooden siren pole formerly used at site W-5 had been replaced with a concrete pole.(B)-The dosimeters.for sites SW-1 and SW-8 were missing when collection was attempted. IODINE-131 IN WEEKLY AIR FILTERS-Ci m3 Collection Date T51 T57 Sam le Site T58 T64 T72.01.-05-95 01-11-95 01-17-95 01-23-95<0.02<0.01<0.01<0.03<0.01<0.03<0.01<0.01<0.01<0.01<0.01<0.03<0.02<0.01<0.01<0.03<0.01<0.01<0.01<0.03 02-01-95 02-06-95 02-13-95 02-21-95 02-28-95<0.02<0.01<0.02<0.01.<0.01<0.02<0.01<0.02<0.01<0.01<0.02<0.01<0.02<0.01<0.01<0.02<0.01<0.02<0.01<0.01<0.02<0.01<0.02<0.01<0.01 03-06-95 03-14-95 03-21-95 03-28-95<0.03<0.01<0.02<0.03<0.01<0.03<0.03<0.01<0.02<0.02(A)<0.02(B)<0.02<0.03<0.01<0.02<0.02<0.03<0.01<0.02<0.02 (A)-We believe a power outage.occurred during this sample.The ec{uipment is estimated to have run for 164 hours out of the 169 total hours for this sampling interval.(B)-We believe a power outage occurred during this sample.The equipment is estimated to have run for 170 hours out of the 189 total hours for.this sampling interval. 2.b AIR PARTICULATES -GROSS BETA-Ci m3-0 Collection Date 01-05-95 01-11-95 01-17-95 01-23-95 T51 0.005+0.002 0.015+0.002 0.010+0.002 0.018+0.003 T57 0.004+0.001 0.011+0.002 0.004+0.002 0.011+0.002 Sam le Site T58 0.008+0.002 0.012+0.002 0.007+0.002 0.015+0.003 T64 0.008+0.002 0.013+0.002 0.007+0.002 0.018+0.003 T72 0.006+0.002 0.017+0.002 0.011+0.002 0.012+0.002 02-01-95.02-06-95 02-13-95 02-21-95 02-28-95 0.016 0.015 0.008 0.004 0.011+0.002+0.003+0.002+0.001+0.002 0.017+0.014+0.009+0.005+0.012+0.002 0.003 0.002 0.001 0.002 0.017*0.011*0.015*0.005*0.011+0.002+0.003+0.002+0.001+0.002 0.018 0.018 0.014 0.007 0.013+0.002+0.003+0.002+0.002+0.002 0.018+0~013+0.012+0.006+0.011+0.002 0.003 0.002 0.001 0.002 03-06-95 03-14-95 03-21-95 03-28-95 0.008+0.002 0.010+0.002 0.009+0.002 (A0.017+0.002 0.005+0.002 0.012+0.002 0.007+0.002 (B0.014+0.002 0.007 0.009 0.011 0.014+0.002+0.002+0.002+0.002 0.006+0.002 0.011+0.002 0.010+0.002 0'17+0.002 0-005+0.002 0-011+0.002 0 009+0.002 0.016+0.002 Means: 0.011+0.001 0.010+0.001 0.011+0.001 0.012+0.001 0.011+0.001*-NRC split samples.(A)-We believe a power outage to have run for 164 hours (B)-We believe a power outage to have run for 170 hours occurred during this out of the 169 total occurred during this out of the 189 total sample.The equipment is estimated hours for this sampling interval.sample.The equipment is estimated hours for this sampling interval.2.b AIR PARTICULATES -GAMMA SCANS OF UARTERLY COMPOSITES -Ci m3 First Quarter, 1995 Sample Site Be-7 K-40 Cs-134 Cs-137 Pb-210 T51 T57 T58 T64 T72 0.1467 0.1589 0.1455 0.1446 0.1362+0.0100+0.0115+0.0102+0.0120+0.0094<0.0185<0.0173<0.0164<0.0163<0.0187<0.0007<0.0010<0.0007<0.0008<0.0008<0.0008<0.0009<0.0012<0.0009<0.0008 0.0104 0.0118 0.0100 0.0143 0.0133+,0.0026+0.0025+0.0023+0.0031+0.0027

3.a SURFACE WATER-Ci l Sample Collection Site Date H-3 K-40 I'I Zr-95 Ba-140 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 (A)(B)T42 01-18-95<136 297+28<4<3 02-08-95<145.194+'26<4<3<8<5<8<6<7<8<5~<8<7<7<4<4<4<5<5<5 03-09-95<142 272+)35<3<3<11<4<6<8<12<3<4<7 T67 01-19-95<135 153+'30<3<4<8<4<7<7<10<5<4<5 02-09-95<132 249+30<4<5<7 03-09-95<142 94+30<4<3<5<4<7<7<5<6<7<6<12<4<4'5<4<5<9 T81 01-18-95 186+45 256+32<4<4<8 02-08-95 345+47 265+32<3<4<9<6<7<7<4'9<6<8<9<4<4<3<4<5<4 03-09-95 175+46 270+31<4<5<8<5<7<8<13<4<4<5 (A)-These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.I (B)-These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample. 0'0 3.b SEDIMENT-Ci k dr wei ht Sample Collection Site Date Be-7 K-40 Co-58 Co-60 Cs-134 Cs-137 Ra-226 Th-232 T42 01-09-95<204 354+72<16<13<14<16 965+19 ND T67-01-12-95<94 243+43<8<6<8<8 ND ND T81 01-09-95<146 305+62<12<11<11<11 871+16 ND 4.a.l CRUSTACEA-Blue Crab-Ci k wet wei ht Sample Collection Site Date K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 First quarter attempts to collect this sample were not successful. Efforts continue.T81 03-31-95 1901+177<19<24<53<23<51<25<24 436+26 ND 4.a.2 FISH-Mixed S ecies Ci k wet wei ht Sample Collection Site Date K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 02-09-95 2309+390<54<73<151<64<128<62<60 ND ND T81 03-31-95 2198+192<20<20<55<24<44<22<25 ND 4 ND ND-Non-detectable. 4.b.l BROADLEAF VEGETATION -Brazilian Pe er-Ci k lt wet wei ht Sample Site Collection Date Be-7 K-40 I-131 Cs-134 Cs-137;Pb-210 T40 01-19-95 02-09-95 03-09-95 2314+94 1806+86 1618+72 3783+138 3382+124 2341+101<19<21<19<9<8<9<15 ND 115+7 I 715+276 15+4 I ND T41 01-19-95 W 02-09-95 03-09-95 2880+90 2244+100 688+63 5662+164 3576+154 5439+182<17<31<24<10<10 23+6 42+7 71+9 596+244'D ND T67 01-19-95 02-09-95 03-09-95 1186+60 940+58 1055+81 3504+123 3143+117 3947+143<15<20<23<9<9<9<10<10 ND ND ND ND-Non-detectable. RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE Second Quarter, 1995 Office of Radiation Control Florida Department of Health and Rehabilitative Services

TURKEY POINT SITE Technical Specifications Sampling Second Quarter, 1995 Sam le T e Collection Fre enc Locations Number of 1.Direct Radiation Quarterly 22 22 2.Airborne 2.a Air Iodines 2.b Air Particulates Weekly Weekly 65 69*3.Waterborne 3.a Surface Water 3.b Shoreline Sediment Monthly Semiannually 4.Ingestion 4.a Fish and Invertebrates 4.a.l Crustacea 4.a.2 Fish Semiannually Semiannually 1 0 4.b Food Products 4.b.l Broadleaf Vegetation Monthly 10*Total: 176*-Includes NRC split samples.NOTE: Measurement results having magnitudes that are significantly above the background of the measurement system are reported as net values plus or minus a one-standard-deviation error term.Measurement results that are not significantly above background are reported as"non-detectable" (ND)or as less than a Lower Limit of Detection (<LLD), which is an estimated upper limit (with at least 95%confidence) for the true activity in the sample. DIRECT RADIATION-TLDs-micro-R hour Sample Deployment 03-15-95 Site Collection 06-07-95 Sample Deployment 03-15-95 Site Collection 06-07-95 N-2 N-7 N-10 NNW-2 NNW-10 NW-1 NW-5 NW-10 5.44+0.09 4.53+0.09 4.30+0.08 4.13+0.08 5.63+0.09 4.72+0.09 4.40+0.08 7.58+0.10 WSW-8 SW-1 SW-8 SSW-5 SSW-10 (A)S-5 S-10 4.90+0.09 4.75+0.09 4.76+0.09 4.49+0.08 4.57+0.08 4.59+0.09 5.45+0.09 WNW-10 6.14+0.09 SSE-1 (A)4.76+0.09 SSE-10 5.69+0.09 W-1 W-5 W-9 6.23+0.09 5.08+0.09 4.63+0.09 NNE-22 5.98+0.09 (A)-The dosimeters for sites SSW-10 and SSE-1 were found lying on the ground when they were collected. 2.a IODINE-131 IN WEEKLY AIR FILTERS-Ci m3 Collection Date T51 T57 Sam le Site T58 T64 T72 04-04-95 04-11-95 04-17-95 04-24-95 05-02-95 05-10-95 05-18-95 05-25-95 05-31-95 06-06-95 06-13-95 06-19-95 06-27-95<0.02<0.02<0.02<0.02<0.02<0.01<0.01<0.02<0.02<0.02<0.02<0.04<0.01<0.02<0.03<0.02<0.02<0.02<0.01<0.01<0.02<0.02<0.02<0.02<0.04<0.01<0.02<0.03<0.02<0.02<0.02<0.01<0.01<0.03<0.02<0.02<0.02<0.05<0.01<0.02<0.02<0.02<0.02<0.02<0.01<0.01<0.03<0.02<0.02<0.02<0.04<0.01<0.02<0.02<0.02<0.02<0.02<0.02<0.01<0.03<0.02<0.02<0.02<0.05<0.01 0 0'.b AIR PARTICULATES -GROSS BETA-Ci m3 Sam le Site Collection Date T51 T57 T58 T64 T72 04-04-95 04-11-95 04-17-95 04-24-95 0.016+0.002 0.013+0.002 0.010+0.002 0.021+0.003 0.018+0.002 0.008+0.002 0.014+0.003 0.017+0.002 0.020+0.002 0.015+0.002 0.020+0.003 0.022+0.003 0.021 0.012 0.011 0.022+0.002+0.002+O.Q02+0.003 0.O18+O.OO2 0.009+0.002 0.016+0.003 0.020+0.003 05-02-95 05-10-95 05-18-95 05-25-95 05-31-95 0.009 0.010 0.017 0.013 0.010+0.002+0.002+0.002+0.002+0.002 0.012+0.002 0.013+0.002 0.015+0.002 0.009+0.002 0.013+0.002 0.009+*0.014+*0.018+*0.015+*0.013+0.002 0.002 0.002 0.002 0.002 0.016 0.019 0.012 0.014 0.011+0.002+0.002+0.002+0.002+0.002 0.011 0.012 0.020 0.014 0.011+0.002+0.002+0.002+0.002+0.002 06-06-95 06-13-95 06-19-95 06-27-95 0.007+0.002 0.011+0.002.0.005+0.002 0.009+0.002 0.006+0.002 0.010+0.002 0.011+0.002 0.010+0.002 0.007+0.002 0.012+0.002 0.006+0.002 0.012+0.002 0.007+0.002 0.018+0.002 0.010+0.002 0.011+0.002 0.009 0.012 0.007 0.011+0.002+0.002+0.002+0.002 Means: 0.012+0.001 0.012+0.001 0.014+0.001 0.014+0.001 0.013+O.OO1*-NRC split samples.2 b AIR PARTICULATES -GAMMA SCANS OF UARTERLY COMPOSITES -Ci m3 Second Quarter, 1995 Sample Site Be-7 K-40 Cs-134 Cs-137 Pb-210 T51 T57 T58 T64 T72 0.1214+0.0095 0.1160+0.0097 0~1381+0 F 0101 0.1341+0.0110 0.1145+0.0101<0.0159<0.0208<0.0203<0.0182<0.0138<0.0010<0.0005<0.0008<0.0010<0.0008<0.0007<0.0005<0.0008<0.0009<0.0010 0.0122+0.0123+0.0135+0.0116+0.0105+0.0025 0.0026 0.0031 0.0028 0.0024 3.a SURFACE WATER-Ci l Sample Collection Site Date H-3 Zr-95 Ba-140 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 (B)T42 04-12-95<137 265+29<3<3<7<5<7<6<7<3<4"'<5 05-10-95<136 278+34<3<3<9<3<9<6<6<4<4 06-16-95<139 273+31<4<4<8<4<9<7<10<3<4<7 T67 04-14-95<137 166+35<4<4<7<5<8<7<6<4 05-11-95<136 226+34<4<4<6<4<9<6<6<5 06-16-95<139 236+32<4<4<8<4<11<7<10<4<4<3<4<6<5<6 T81 04-13-95<147 347+41<4<4<6<5<8<7<8<5<5 05-11-95 201+45 238+30<3<4 06-15-95 149+45 266+35<5<4<8<4<9<6<7<3<10<4<6<8<10<3<4<4<5<7 (A)-These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.(B)-These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample. 4.a.l CRUSTACEA-Blue Crab-Ci k wet wei ht Sample Collection Site Date K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65.Cs-134 Cs-137 Ra-226 Ra-228 T67 04-04-95 1787+189<20<19<46<27<52<22<20.ND ND 4.b.1 BROADLEAF VEGETATION -Brazilian Pe er-Ci k wet wei ht Sample Site Collection Date Be-7 K-4 0 I-131 Cs-134 Cs-137 T40 T41 T67 04-13-95*05-11-95 06-15-95 04-13-95 05-11-95 06-15-95 04-14-95 05-11-95 06-16-95 1842+73 1671+73 1469+91 1689+81 1632+83 1133+75 1170+69 699+54 900+61 3112+124 2448+105 3384+143 5839+174 6175+177 4332+135 4080+141 5511+157 3823+134<14<14<18<17<18<22<13<15<16<9<9<11-<11<12<9<10<9<8 57+6 62+6 74+9 58+8 37+6 33+6<9<10<11*-NRC split sample.ND-Non-detectable. 0 RADIOLOGICAL SURVEILLANCE OF FLORIDA POHER AND LIGHT COMPANY'S TURKEY POINT SITE Third Quarter, 1995 Office of Radiation Control Florida Department of Health and Rehabilitative Services 0 0 TURKEY POINT SITE Technical Specifications Sampling Third Quarter, 1995 Sam le T e Collection Fre enc Locations Sam led Number of Sam les 1.Direct Radiation Quarterly 22 21 2.Airborne 2.a Air Iodines 2.b Air Particulates 3.Waterborne 3.a Surface Water 3.b Shoreline Sediment Weekly-Weekly Monthly Semiannually 5 5 6569*4.Ingestion 4.a Fish and Invertebrates 4.a.l Crustacea 4.a.2 Fish Semiannually Semiannually 4.b Food Products 4.b.1 Broadleaf-Vegetation Monthly Total: 177*-Includes NRC split samples.NOTE: Measurement results having magnitudes that are significantly above the background of the measurement system are reported as net values plus or minus a one-standard-deviation error term.Measurement results that are not significantly above background are reported as"non-detectable" (ND)or as less than a Lower Limit of Detection (<LLD),, which...is an estimated.upper limit~, (with at least 954 confidence) for the true activity in the sample. 0 DIRECT RADIATION-TLDs-(micro-R hour)Sample Site Deployment 06-07-95 Collection 09-13-95 N-2 N-7 N-10 5.02+0~10 4.54+0.09 4.95+0.09 NNW-2 NNW-10 4.10+0.09 5.53+0.10 NW-1 NW-5 NW-10 4.50+0.09 4.53+0.09 7.27+0.11 WNW-10 W-1 W-5 W-9 6.09+0.10 6.16+0.10 (A)4.57+0.09 WSW-8 SW-1 SW-8 4.69+0.09 4.87+0.10 4.63+0.09 SSW-5, SSW-10 S-5 S-10 4.55.4.85 4.32 5'7+0.09+0.09,+0.09+0~10 SSE-1 (B)4.91+0.10 SSE-10 5.55+0.10 NNE-22 5.14+0.09 (A)-The dosimeter for site W-5 was missing when collection was attempted. --(B)=-The dosimeter-for-siCe-SSE-1-was found'ying on the ground. 4 IODINE-131 IN WEEKLY AIR FILTERS-(Ci m)Sam le Site Collection Date T51 T57 T58 T64 T72 07-06-95 07-12-95 07-17-95 07-27-95<0.01<0'2<0.02<0.01<0;01<0.02<0.02<0.01<0.01<0'2<0.02<0.01<0.01<0.02<0.02<0.01<0.01<0.02<0.02<0.01 08-02-95 08-07-95 08-15-95 08-23-95 08-29-,95<0.02<0.02<0~02<0.02<0.02<0.02<0.02<0.02<0.02<0:02<0.02<0.02<0.02<0.02<0.02<0.02<0.02<0'2<0.02<0.02<0.02<0.02<0.02<0.02 (A)<0.02 (B)09-05-95 09-12-95 09-19-95 09-25-95<0.02<0.01<0.02<0.02<0.02<0.01<0.02<0.02<0.02<0.01<0.02<0.02<0.02<0.01<0.02<0.02<0.02<0.01<0.02<0.02 (A)-Electrical power was out at the end of this sample.The equipment is estimated to have run for 170 hours out of the 191 total hours for this sampling interval.(B)-Electrical power was out at the start of this sample.The equipment is estimated to have run for 138 hours out of the 144 total hours for this sampling interval.

2.b Collection Date~T51 AIR PARTICULATES T57 GROSS BETA-(pCi m)Sam le Site T58 T64 T72 0 0.013+0.002 0.003+0.002<0.007 0.005+0.001+0.002+0.003+0.002+0.002+0.002 0.011 0.023 0.014 0.015 0.016 0.009+0.002 0.006+0.002 0.012+0.002 0.011+0.002 144 total hours to have run for 138 hours out of the 07-06-95 0.016+0.002 0.014+0.002 07-12-95 0.007+0.002 0.009+0.002 07-17-95<0.006 0.006+0.002 07-27-95 0.004+0.001!0.008+0.002 08-02-95 0.008+0.002*0.009+0.002 08-07-95 0.024+0.003*0.012+0.002 08-15-95 0.012+0.002*0.016+0.002 08-23-95 0.020+0.002*0.016+0.002 08-29-95 0.014+0.002*0.015+0.003 09-05-95 0.013+0.002 0.009+0.002 09-12-95 0.007+0.002 0 005+0.002 09-19-95 0.008+0.002 0.007+0.002 09-25-95 0.007+0.002 0-009+0.002 Means: 0.012+0.001'.012 +0.001 0.010+0.001 I*-NRC split samples.(A)-Electrical power was out at the end of this sample.~to have run for 170 hours out of the 191 total hours (B)-Electrical power was out at the start of this sample 0.016+0.002 0.015+0.003 0.005+0.002 0.008+0.001 0.016+0.002 0.013+0.002 0.008+0.002 0.005+0.001 0.012 0.011 0.017 0.016 0.016+0.002+0.002+0.002+0.002+0.002 0.007 0.012 0.014 (A0.022 (B0.018+0.002+'.002+0.002+0.003+0.003 0.022+0.003 0.010+0.002 0.007+0.002 0.014+0.002 0.012+0.002 0.008+0.002 0.009+0.002 0.011+0.002 0.013+0.001 0.012+0.001 The equipment is estimated for this sampling interval.The equipment is estimated for this sampling interval.2.b AIR PARTICULATES -GAMMA SCANS OF QUARTERLY COMPOSITES -(pCi m)!Sample Site Be-7 K-40 Cs-134 Third Quarter, 1995 Cs-137 Pb-210 T51 T57 T58 T64 T72 0.1089+0.0097 0.0954+0.0116 0.0990+0.0096 0.1043+0.0081 0.0904+0.0085<0.0164<0.0156<0.0181<0.0154<0.0196<0.0011<0.0010<0.0010<0.0007<0.0011<0.0009<0.0006<0.0007<0.0005<0.0007 ND 0.0127+0.0026 ND 0.0112+0.0026 0.0123+0.0033 0.0124+0.0025 Non-detectable. '0 3.a SURFACE WATER-(pCi/l)Sample Collection Site Date H-3 Zr-95 Ba-140 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 (A)(B)T42 07-20-95<152 08-17-95<144 09-06-95<144 218+31<3<3<6 254+25<3<4<7 290+29<4<3'8<4<4<4<8<5<6<7<7<6<6<7<7<3<3<4<5<4<5<8<5 T67 07-21-95<152 08-18-95<134 09-06-95<144 225+13<1<1 203+31<4<3 186+25<4<4<3<6<8<2<4<4<3<3<2<8<6<10<7<7<5<4<4<2<5<5 T81 07-19-95<152 271+32<3<3<7<4<7<7<7<5<5 08-17-95<153 195+33<4<4<8<5<7<5<6<4<4<2 09-06-95<151 252+29<4<3<10<4<7<6<8<4<6 (A)-These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.(B)-These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample. 0 3 3.b SEDIMENT-(pCi/k, dr wei ht)Sample Collection Site Date Be-7 K-40 C0-58 C0-60 Cs-134 Cs-137 Others T42 07-20-95 438+69 431+89<12<15<13<15 Ra-226: U-238 754+19 638+176 T67 07-18-95 142+37 249+45<6<4<7<7 Ry-226 Th-232: 110+7 55+8 T81 07'-19-95 378+68 386+60<9<11<11<12 Ra-226: 645+15 4.a.1 CRUSTACEA;Blue Crab-(pCi k , wet wei ht)Sample Collection Site Date K-4 0 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 07;21-95 1317+162<16<14<35<17<37<17<19 ND ND\T81 Third quarter attempts to collect this sample were not successful. Efforts continue.4.a.2 FISH-Mixed Species-(pCi/kg, wet wei ht)K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 1 Sample Collection Site Date T67 Third quarter attempts to collect this sample were not successful. T81 Third quarter attempts to collect this sample were not successful. Ra-226 Ra-228 Efforts continue.~~ Efforts continue.ND-Non-detectable. 0 4.b.l BROADLEAF VEGETATION -Brazilian Pepper-(pCi/k , wet weight)Sample Collection Site Date Be-7 K-40 3-131 Cs-134 Cs-137 Pb-210 T40 07-24-95 08-17;95 09-06-95 1686+80 2873+114 3408+99 5155+154 2820+122 3185+125<13<14<26<8 81+8 ND<9 34+6 ND<10 100+10 1141+224 T41 07-24-95 08-17-95 09-06-95 2391+89 3252+102 3635+108 5096+159 3815+150 4435+143<12<18<20<9 74+6 ND<13 102+8 908+275<10 109+9 574+215 T67 07-21-95 08-18-95 09-06-95 1411+68 1309+70 1779+74 3858+137 3535+128 4746+146<14<12<21<10<9<10<9 ND ND 724+303 ND-Non-detectable. 7

RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE Fourth Quarter, 1995 Office of Radiation Control Florida Department of Health and Rehabilitative Services TURKEY POINT SITE Technical Specifications Sampling Fourth Quarter-1995 Sam le T e Collection Fre uenc Locations Number of 1.Direct Radiation Quarterly 22 21 2.Airborne 2.a Air Iodines 2.b Air Particulates Weekly Weekly 65 64 3.Waterborne 3.a Surface Water 3.b Shoreline Sediment Monthly Semiannually 4.Ingestion 4.a Fish and Invertebrates 4.a.l Crustacea 4.a.2 Fish Semiannually Semiannually 4.b Food Products 4.b.1 Broadleaf Vegetation Monthly Total: 171 NOTE: Measurement results having magnitudes that are significantly above the background of the measurement system are reported as net values plus or minus a one-standard-deviation error term.Measurement results that are not significantly above background are reported as"non-detectable" (ND)or as less than a Lower Limit o f Detection (<LLD), which is an estimated upper l imit (with at least 954 confidence) for the true activity in the sample.

DIRECT RADIATION-TLDs-(micro-R/hour) Sample Deployment 09-13-95-Site==--Collection -.12-13-95 N-2 N-7 N-10 5.57+0.11 4.63+0.11 4.75+0.10 NNW-2 NNW-10 4.46+0.11 5.66+0.11 NW-1 (A)6.67+0.12 NW-5 4.77+0.11 NW-10 7.46+0.12 WNW-10 6.29+0.12 W-1 W-5 W-9 6.29+0.12 4.75+0.11 4.73+0.11 WSW-8 4.76+0.10 SW-1 SW-8 4.81+0'0 4.60+0.10 SSW-5 SSW-10 S-5 S-10 4.52+0.11 (>)4.37+0.10 5.61+0.11 SSE-1 SSE-10 4.45+0.10 5.73+0.11 NNE-22 5.97+0.11 (A)-The result for site NW-1 is statistically high compared to the long-term average of 5.03 micro-R/hr there.This corre-sponds to a dose of approximately

3.6 millirem

more than would be expected at this site during this deployment inter-val.Although this location is along the plant entrance road where shipments of radioactive materials would pass by, no specific explanation for this elevated reading is known.t (B)-The dosimeter for site SSW-10 was missing when collection was attempted.

2.a IODINE-131 IN WEEKLY AIR FILTERS-Ci m Sam le Site'Collection Date T51 T57 T58 T64 T72 10-04-95 10-11-95 10-19-95 10-25-95 10-31-95<0.01<0.02<0.02<0.02<0.02<0.01<0.02<0.02<0.02<0.02<0.01<0.02<0.02<0.02<0.02<0.02<0.01<0.02<0.02<0.02<0.01<0.02<0.02<0.02<0.02 11-06-95 11-13-95 11-20-95 11-27-95<0.02<0.02<0.02<0.01<0.02<0.02<0.02<0.01<0.02<0.02<0.02<0.01<0.02<0.02<0.02<0.01<0.02<0.02<0.02<0.01 12-07-95 12-12-95 12-19-95 12-28-95<0.01<0.04<0.02<0.02<0.02<0.01<0.07(A)<0.01<0.02(B)<0.03<0.02<0.02<0.01<0.03<0.03'<0.01<0.01<0.04<0.02<0.01 (A)-Electrical power was out at the end of this sample.A car had been backed against this utility pole and had been set afire.The fire had damaged the utility pole, and one of the wires was down.The equipment is estimated to have run for 22 hours out of the 197 total hours for this sampling interval.(B)-Electrical power was out at the start of this sample.The equipment is estimated to have run for 134 hours out of the 139 total hours for this sampling interval.

2.b AIR PARTICULATES -GROSS BETA-(pCi m)Sample Site Collection Date 10-04-95 10-11-95 10-19-95 10-25-95 10-31-95 11-06-95 11-13-95 11-20-95 11-27-95 T51 0.007+0.002 0.004+0.002 0.007+0.002<0.006 0.012+0.002 0.013+0.002 0.018+0.002 0.014+0.002 0.018+0.002 T57 0.008+0.002 0.004+0.002<0.005<0.005 0.013+0.002 0.009+0.002 0.020+0.002 0.020+0.002 0.016+0.002 T58 0.006+0.001 0.007+0.002 0.004+0.001 0.006+0.002 0.015+0.002 0.018+0.002 0.014+0.002 0.020+0.002 0.015+0.002 T64 0.004+0.002 0.006+0.001 0.007+0.002 0.007+0.002 0.015+0.002 0.015+0.002 0.015+0.002 0.015+0.002 0.018+0.002 T72 0.007+0.001 0.007+0.002 0.003+0.001<0.007 0.010+0.002 0.016+0.002 0.015+0.002 0.017+0.002 0.020+0.002 12-07-95 12-12-95 12-19-95 12-28-95 Means: 0.013+0.002 0.017+0.003 0.011+0.002 0.021+0.002 (A)(B0.014+0.003 0.007+0.002 0.020+0.002.0.013+0.001 0.013+0.001 0.015+0.002 0.024+0.003 0.007+0.002 0.024+0.002 0.013+0.001 0.016+0.002-0.019+0.002 0.013+0.003 0.025+0.002 0.013+0.001 0.015+0.002 0.021+0.003 0.009+0.002 0.018+0.002 0.013+0.001 (A)-Electrical power was out at the end of this sample.A car had been backed against this utility pole and had been set afire.The fire had damaged the utility pole, and one of the wires was down.The particulate filter and its holder were missing when collection was attempted.(B)-Electrical power was out at the start of this sample.The equipment is estimated to have run for 134 hours out of the 139 total hours for this sampling interval.2.b AIR PARTICULATES -GAMMA SCANS OF QUARTERLY COMPOSITES -(Ci/m)Fourth Quarter, 1995 Sample Site Be-7 K-40 Cs-134 Cs-137 Pb-210 T51 T57 T58 T64 T72 0.1398+0.0100 0.1191+0.0091 0.1443+0.0104 0.1382+0.0105 0.1348+0.0123<0.0186<0.0167<0.0139<0.0135<0.0152<0.0011<0.0007<0.0005<0.0008<0.0006<0.0006<0.0008<0.0009<0.0008<0.0007 0.0112 0.0105 0.0098 0.0159 0.0109+0.0030+0.0029+0.0039+0.0029+0.0028

3.a SURFACE WATER-(pCi 1)Sample Collection Site Date H-3 Zr-95 Ba-140 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 T42 10-12-95<140 (A)222+30<3<4<8<5<8<7<6<3 (B)I ,<4<6 11-08-95<145 162+30<4<4<8<3<7<7<7 12-08-95<155 175+27<3<4<7<5<7<6<8<4<5<4<4<6<5 T67 10-13-95<14'0 174+28<3<4<9<3<7<6<7<4<4<5 11-09-95<145 146+30<4<4<7<5<7<5<8<3<4<6 12-08-95<149 117+24<4<3<7<4<8<7<9<3<3<7 T81 10-12-95<140 86+29<3<3<6<4<7<6<6 11-08-95 119+46 242+29<4<4<8<4<8<6<7 12-08-95 260+50 259+31<5<4<7<4<8<6<9<4<4<3<4<4<4<5<5<6 (A)-These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.(B)-These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample. (o/ 4.a.1 CRUSTACEA-Blue Crab-(pCi/kg, wet wei ht)Sample Collection Site Date K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226: Ra-228 T81 12-19-95 1798+192<25<25<61<30<49<26<26 846+32'D 4.a.2 FISH-(T67: Snapper)(T81: Mixed Species)-(pCi kg, wet weight)Sample Collection Site Date K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 12-01-95>2870+15714<15<37<18<31<15<15 T81 12-18-95 2620+74<6<7<15<7<14<7<7 ND ND ND ND 4.b.l BROADLEAF VEGETATION -Brazilian Pepper-(Ci k , wet wei ht)K-40 Sample Collection Site Date Be-7 I-131 Cs-134 Cs-137'b-210 T40 T41 T67 10-12-95 11-09-95 12-08-95 10-12-95 11-09-95 12-08-95 10-13-95 11-09-95 12-08-95 2171+87 2946+94 1565+80 2737+93 1996+78 877+57 1191+67 1500+81 1678+87 3830+141 2753+112 4010+134 5220+153 5047+147 4653+150 3539+128 3482+141 4145+148<17<15<21<15<15<19<12<17<22<10<9<10<8<8<11<8<11<10 349+12 52+6 62+7 90+8 31+6 31+6<9<12<10 ND 1027+304 ND 831+280 ND ND ND ND ND ND-Non-detectable. (o 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3&4 ATTACHMENT C RESULTS FROM THE INTERLABORATORY COMPARISON PROGRAM 1995

FLORIDA DEPT.OF HRS-EPA INTERLABORATORY CROSS-CHECK PROGRAM DATA January through June, 1995 WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER Alpha Bet.a Co-60 Zn-65 Ba-133 Cs-134 Cs-137 H-3 I-131 Sr-89 Sr-90 Media Nuclide Collection Mon Day Yr 01 27 95 01 27 95 06 09 95 06 09 95 06 09 95 06 09 95 06 09 95 03 10 95 02 03 95 Ol 13 95 01 13 95 EPA Known 5 5 40 76 79 50 35 7435 100 20 15 Units pCi/L pci/L pCi/L pCi/L pci/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L Normal.Range 0.236 0,236 0.236 0.517 0,148 0.000 0.354 0'93 0'18 0.354 0.236 Mean of Analyses 5.00 7.33 39.00 82.67 74.33 47.00 37.67 7355.00 97.00 14.33 10.33 N.DE K'ction Level 0.00 0.81-0.35 1.44-1.01-1.04 0.92-0.19-0.52-1.96-1.62 NOTES: Normal.: N.D.K.: NDP: NA: Normalized range.As defined in"Environmental Radioactivity Laboratory Xntercomparison Studies Program Fiscal Year 1981-1982", Environmental Monitoring Systems Laboratory, U.S.Environmental Protection Agency, P.0.Box 93478, Las Vegas, Nevada, 89193-3478. EPA-600/4-81-004, February, 1981.Normalized deviation of the mean from the known value, as defined in EPA-600/4-81-004. No data provided.No data was provided to EPA for inclusion in their report.Not available. Report containing this data has not yet been received from EPA, Las Vegas. FLORIDA DEPT OF HRS-EPA INTERLABORATORY CROSS-CHECK PROGRAM DATA July through December, 1995 FILTER FXLTER FILTER FXLTER MILK MILK MXLK MILK MILK WATER WATER HATER WATER WATER WATER WATER HATER WATER WATER WATER WATER HATER Alpha Beta Cs-137 Sr-90 I-131 Cs-137 K Sr-89 Sr-90 Alpha Alpha Beta Beta Co-60 Zn-65 Ba-133 Cs-134 Cs-137 H-3 X-131 Sr-89 Sr-90 Media Nuclide Collection Mon Day Yr 08 25 95 08 25 95 08 25 95 08 25 95 09 29 95 09 29 95 09 29 95 09 29 95 09 29 95 07 21 95 10 27 95 07 21 95 10 27 95 11 03 95 11 03 95 11 03 95 11 03 95 11 03 95 08 04 95 10 06'5 07 14 95 07 14 95 EPA Known 25 86.6 25 30 99 50 1654 20 15 27.5 51.2 19.4 24.8 60 125 99 40 49 4872 148 20 8 Units pCi/Fil pCi/Fil pCi/Fil pCi/Fil pCi/L pCi/L mg/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pci/L pCi/L pCi/L pCi/L pCi/L pCi/L Normal.Range 0.141 0.396 0.000 0.709 0.295 0.000 0.306 0.945 0.945 0.231 0.120 0.567 1.413 0.236 0.409 0.059 0.118 0.354 0.039 0,591 0.118 Mean of Analyses 28.30 79'7 28.00 21.33 98.67 53.00 1687.33 12.00 16.00 23.33 24.90 23.60 32.97 60,33 134.67 92.67 37.33 54.00 148.67 8.00 9.33 N.D.K.Action Level 0.91-1.22 1.04-3.00 1-0.06 1'4 0.70-2077 0.35-1.05-3.56 2 1.45 2.83 0.12 1.29-1.10-0.92 1.73 NDP 0.08-4.16 3 0.46 NOTES: Normal.: Normalized range.As defined in"Environmental Radioactivity Laboratory Xntercomparison Studies Program Fiscal Year 1981-1982", Environmental Monitoring Systems Laboratory, U.S.Environmental Protection Agency, P.O.Box 93478, Las Vegas, Nevada, 89193-3478. EPA-600/4-81-004, February, 1981.N.D.K.: Normalized deviation of the mean from the known value, as defined in EPA-600/4-81-004. NDP: No data provided.No data was provided to EPA for inclusion in their report.NA: Not available, Report containing this data has not yet been received from EPA, Las Vegas.ACTXON LEVEL: (1)Cause: Chemical recoveries too low and inconsistent. Corrective Action: Try to improve recovery and consistency. (2)Cause: Please see attached note from EPA.Corrective Action: Try EPA's suggestions. (3)Cause: Insufficient number of counts on sample.Corrective Action: Count samples more time.

VNITED STATES ENVIRONMENTAL PROTECTION AGENCY NATIONAL EXPOSURE RESEARCH LABORATORY .P.O.BOX 93478 i LAS VEGAS, NV 89193.3478 OFFICE OF RESEARCH AND DEVELOPMENT A note regarding the Gross Alpha portion of the October 27, 1995 Gross Alpha-Beta in Water Performance Evaluation Study: Both the July 1995 and October 1995 Gross Alpha-Beta in Water Performance Evaluation (PE)Studies showed a significant difference between the grand average and the known value for the gross alpha.This strongly implies there is bias in the method.Our research indicates that matrix differences between the salt solids used to prepare the calibration curve and the salts in the sample are the source of the bias.The attached figure illustrates the changes in efficiency due to salt composition and nuclide energy.The bottom curve was prepared with serial dilutions of laboratory tap water.Laboratory tap water is also used to add variable amounts of dissolved solids to the'E gross alpha/beta study samples.The second curve was prepared with serial dilutions of sodium sulfate solution.The top curve was prepared the same way as the second curve.except that Am-241 was used as the alpha emitter.All the usual precautions apply.The curves reflect the efficiencies for our counter;the curves in the figure are illustrative only;and lastly, results for your laboratory may be different than shown in the figure.At zero mass all the curves converge to the extent that the bias would not be noticeable in a PE study.As the mass of solids increases, the difference between the two Th-230 curves becomes pronounced. For sample masses between 30 and 40 mg, typical range for a 200 mL sample of the July 1995 or October 1995 study, the difference is between 50 to 70 percent.To address the bias, we are recommending the procedure used in our laboratory. To a'olume of sample equal to that used for analysis (100-150 mL)add 120 pCi of Th-230.Acidify the sample with 20-40 mL of concentrated nitric acid and evaporate by the procedure attached to the PE study report sheet.The volume of PE,sample provided is sufficient to prepare triplicate 150 mL samples and duplicate spiked samples.Count the spikes until approximately 1600 counts above background are acquired to a maximum of 200 minutes.Background in this case will be that of the PE samples.Subtract the average count rate of the triplicate samples from the average count rate of the spikes and calculate the efficiency. Use this efficiency to calculate the concentration of gross alpha in the PE sample.RecycledtRecyctaote ~panted vntn vegetattte oil Based Inks on ttxt,e Recycted papet (40e'ostconsutner) 4 k A'n alternate procedure. After counting the triplicates, redissolve/reslurry the solids of two of the samples in the planchet with dilute nitric acid (3-6M).Add the spike, mix well, redry and count the spikes.This technique, though simple on the surface, requires sufficient care so as not to lose sample volume, and that the Th-230 is thoroughly incorporated into the dissolved salts.We recommend this only for laboratories with a high degree of confidence in the analyst's ability to prepare the spikes by this technique. You may use more or less spiked activity if you choose.The recommended activity of the spike and the maximum count time were determined to provide 5 percent precision at 95 percent confidence for the spike at an efficiency as low as 3 percent.For higher efficiencies the count time will be much shorter than 200 minutes.Additionally, we recommend several practice runs to gain experience with the technique you choose.So, why not send out our laboratory tap water and have the participating laboratories prepare a curve?The tap water supplied to our laboratory varies in dissolved salt composition. This was observed during our verification of the July 1995 PE sample.Our QC samples showed a 40 percent bias when samples and spikes were quantified using a calibration curve.Repeat measurements demonstrated the bias was consistent and not due to analyst error.Therefore, preparing a curve with water from our laboratory does not guarantee that the bias will be eliminated. Collectively these procedures are single point calibration techniques and are not prohibited by the approved methods.The curve concept was introduced in recognition of the variable dissolved solids of water in given geographical areas.If you have any questions or comments please call Stephen Pia at 702 798-2102. 0~'i ALPHA ATTENUATION CURVES FOR RADQA TENNELEC GP COUNTER 0.2500.0.2250 0.2000 0.1750 V 0.Am-241 sulfa 30 ss h-2 tes ystem ulfa te system TH-230 nitr ate syst em 0.1500 0.1 250 0.1 000 0.0750 0.0500 0.0250 0.0000 V 0 0""""'0 0.10 20 30, 40 50 60 70 80 90 100110120 Mg RESIDUAL SOLIDS EQUATION: Y=Ao+A(X+A2X.+A X Th-230 sulfate Ao=0.2 I 99.A=-2.914E-3 1 A2=1.8422E-5 A3=-4.4449E-8 Th-230 nitrate 0.2016-4.495 E-3 3.9 I8E-5-1.154E-7 v 0~Ig (e E'}}