ML17348A914

1990 Annual Radiological Environ Operating Rept Turkey Point Plant Units 3 & 4. W/910430 Ltr

ML17348A914
Person / Time
Site:	Turkey Point
Issue date:	12/31/1990
From:	Plunkett T FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-91-119, NUDOCS 9105070093
Download: ML17348A914 (92)

Text

ACCELERATED DISTRIBUTION DEMONSTPJ!!.TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR: 9105070093 DOC. DATE: 90/12/31 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 PLUNKETT,T.F. Florida Power 6 Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

"1990 Annual Radiological Environ Operating Rept Turkey Point Plant Units 3 6 4." W/910430 ltr.

DISTRIBUTION CODE: IE25D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Environmental Monitoring Rept (per Tech Specs)

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INTERNAL: AEO B 1 1 NRR/DREP/PRPB11 2 2 G FI 01 1 1 RGN2 DRSS/RPB 1 1 8 FILE 02 1 1 EXTERNAL EGGG SIMPSONFF 2 2 NRC PDR 1 1 R

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p pp .0. Box 029100, Miami, FL, 33102-9100 APR 80 1991 L-91-119 U.'. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. CD 20555 Gentlemen:

Re: Turkey Point Units 3 and 4 Docket: Nos. 50-250 and 50-251 1990 Annual Radiological Environmental 0 eratin Re ort This letter transmits the subject report in accordance with Technical Specification 6.9.1.3 for Turkey Point Units 3 and 4.

Should there be any questions on this information, please contact us.

Very truly yours, T. F. Plunkett Vice President Turkey Point Nuclear TFP/RJT/rjt Enclosure cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant 5'i05070093 5'01223i PDR AOOCK 05000250 PDR

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0 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT UNITS 3 & 4 TABLE OF CONTENTS DESCRIPTION PAGE Executive Summary Introduction Radiological Environmental Monitoring Program Discussion and Interpretation of Results Environmental Radiological Monitoring Program TABLE 1 Annual Summary Deviations/Missing Data TABLE 1A Analyses with LLDs Above Table 4.12-1 TABLE 1B Detection Capabilities Land Use Census TABLE 2 Key to Sample Locations ATTACHMENT A Radiological Surveillance of Florida Power ATTACHMENT B and Light Company's Turkey Point Site First Quarter, 1990 Second Quarter, 1990 Third Quarter, 1990 Fourth Quarter, 1990 Results from the Interlaboratory Comparison ATTACHMENT C Programs 1990

1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT UNITS 3 & 4 EXECUTIVE

SUMMARY

The data obtained through the Turkey Point Radiological Environmental Monitoring Program verifies the levels of radiation and concentrations of radioactive materials in environmental samples, is not increasing. These measurements verify that the dose or dose commitment to members of the public, due to operation of Turkey Point Units 3 & 4, during the surveillance year, is well within the limits established by 10 CFR 50, Appendix I.

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1990 e 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.

II'ADIOLOGICAL 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 tio The Radiological Environmental Monitoring Program for the Turkey Point Plant is conducted pursuant to Technical Specifications 3/4.12 of Turkey Point Unit 3 & 4 Technical Specifications.

1. Sample Locations, Types and Rrequencies:

a 0 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.

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1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT - UNITS 3 0 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 the 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.

C. Anal tical Results Table 1, Environmental Radicle ical Monitorin Procrram Annual ~summa 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 noted and explained in Tables lA and 1B respectively.

any, are Analysis data for all specified samples analyzed during the surveillance period is provided in Attachment B.

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1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT UNITS 3 fc 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

~summa 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) 204 greater than locations currently being sampled in the radiological environmental monitoring program were identified by the land use census.

E. Interlaborato 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'ISCUSSION AND INTERPRETATION OP RESULTS A. Re ortin of esults 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 a 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.

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1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATZNG REPORT TURKEY POINT PLANT - UNITS 3 0 4 B.'nter retation of Results

1. Direct Radiation:

The results for direct radiation monitoring are consistent with past measurements for the specified locations. The exposure rate data shows 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 isotope is cosmic-ray produced Be-7 and naturally occurring K-40 at levels consistent with past measurements.

3. Waterborne; Surface Water:

The results for 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 about 3% of the reporting value specified by Technical Specifications, Table 3.12-2 ~

4. Waterborne; Sediment, and Pood Products:

4.1 Sediment

'The results are consistent with past measurements; Cs-137 was detected in one sample collected at the control location. The result is about 18% of the table 4.12-1 LLD. No other fission products were detected.

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1990 0 ANNUAL RADZOLOGZCAL ENVZRONMENTAL OPERATZNG REPORT TURKEY POZNT PLANT. - UNZTS 3 fi 4

4.2 Food-Products

The results are consistent with past measurements. Mn-54 was detected in one sample collected at an indicator location; the result is about 154 of the table 4.12-1 LLD and is less than 0.14 of the table 3.12-2 reporting level. Cs-137 was detected in two samples collected at an indicator location; the maximum value is about 28%

of the table 4.12-1 LLD and is 2% of the table 3.12-2 reporting level. Again, the occasional extremely low level appearance of these nuclides is consistent with past measurements. No other fission products were detected.

5. Broad Leaf Vegetation:

The results for radioactivity measurements are consistent with past measurements. Cs-137 was detected, as in the past, in samples collected from all locations. The maximum value, occurring at the control location, is about 194 of the table 3.12-2 reporting level. No other fission products were detected.

C. Conclusions The data obtained through the Turkey Point Plant Radiological Environmental Monitoring Program verifies 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. The measurements verify that the dose or dose commitment to members of the public, due to operation of Turkey Point Units 3 & 4, during the surveillance year, are well within "as low as reasonably achievable (ALARA)"

criteria established by 10 CFR 50, Appendix I.

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4 TAB 1 Pa 1 of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Pacility Turke Point Units 3 & 4 , Docket No(s). 50-250 & 50-251 Location of Facility Dade Florida , Reporting Period Janua 1 - December 31 1990 (County, State)

PATHWAY: DIRECT RADIATION SAMPLES COLLECTED: TLD UNITS: MICRO R/hr Location with Highest All Indicator Type and Total Number of Analyses Lower of Limit Detection'LLD)

Locations Mean (f)

Name'ean Distance Annual Mean f Control Locations Mean (f)

Performed Range Direction Range Range Exposure 5. 6 (84/84) NW-10 7. 6 (4/4)

Rate, 84 4.5 7.8 10 mi., NW 7.3 7.8 Number of Nonroutine Reported Measurements = 0 HP3:1iRADENVOP.PTN

TAB 1 Pa 2 of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3 & 4 , Docket No(s). 50-250 6 50-251 Location of Facility Dade Florida , Reporting Period Zanua 1 - December 31 1990 (County, State)

PATHWAY: AIRBORNE SAMPLES COLLECTED: RADIOIODINE AND PARTICULATES UNITS: PICO Ci/M Location with Highest All Indicator Type and Total Number of Analyses Lower of Limit Detection Locations Mean (f)

Name'ean Distance Annual Mean f Control Locations Mean (f)

Performed (LLD) Range Direction Range Range

"'I, 260 0.024 <MDA <MDA Gross Beta, 260 0 '025 0. 010 (258/260) T-57 0.010 (51/52) 0.010 (52/52)

0. 003 0. 018 4 mi., NW 0.003 0.018 0.004 0.018 Composite Gamma Isotopic, 20

'Be 0. 0052 0. 092 (20/20) T-57 0.100 (4/4) 0.096 (4/4)

0. 074 0. 122 4 mi., NW 0.074 0.122 0-079 0.114 40K 0. 012 0. 011 (2/20) T-57 0. 011 (2/4) <MDA 0.011 0.011 4 mi., NW 0.011 0.011 0.00069 <MDA <MDA 137C 0.00066 <MDA <MDA Number of Nonroutine Reported Measurements = 0 HP3:1/RAOENVOP ~ PTN

TAB 1 Pa 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 1990 (County, State)

PATHWAY: WATERBORNE SAMPLES COLLECTED: SURFACE WATER UNITS: PICO Ci/LITER Location with Highest Type and Lower Limit All Indicator Annual Mean Total Number of- Locations Name Mean f Control Locations of Analyses Detection'LLD) Mean (f) Distance & Mean (f)

Performed Range Direction Range Range Tritium, 36 230 297 (6/36) T-81 297 (6/12) <MDA 121 910 6 mi., S 121 910 Gamma Isotopic, 36 40K 60 319 (36/36) T-81 3 60 ( 12/12) 277 (12/12) 200 450 6 mi., S 250 450 210 330

'4Mn <MDA <MDA 59Fe <MDA <MDA 5eC <MDA <MDA Co <MDA <MDA Zn <MDA <MDA Zr-Nb <MDA <MDA 131I <MDA <MDA 134C <MDA <MDA 137CS <MDA <MDA

>4oBa-La <MDA <MDA Number of Nonroutine Reported Measurements = 0 HP3:1/RAOEHVOP.PIN

TABL Pa 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 Facili.ty Dade Florida , Reporting Period Janua 1 December 31 1990 (County, State)

PATHWAY: WATERBORNE SAMPLES COLLECTED: SHORELINE SEDIMENT UNITS PICO Ci/Kg, DRY Location with Highest T

Total e and of Analyses Number Lower of Limit Detection'LLD)

All Indicator Locations Mean (f)

Name'ean zs ance

,Annual Mean f Control Locations Mean (f)

Performed Range Direction Range Range Gamma.

Isotopic, 6 "Be 100 365 (4/6) T-67 610 (1/2) 610 (1/2) 270 610 13-18 mi., N/NNE 40K 140 657 (6/6) T-67 1225 (2/2) 1225 (2/2) 220 1650 13-18 mi., N/NNE 800 1650 800 1650 (2/6) T-67 33 (2/2)

-(2/2) 137C 12 33 33 29-36 13-18 mi., N/NNE 29-36 29 36 52 104 (5/6) T-67 112 (2/2) 112 (2/2) 76 135 13-18 mi , N/NNE 100 124 100 124 226R 49 532 (6(64 T-42 688 (2/2) 363 (2/2)

<1 mi., ENE 655-721 298 427 1010 (1/6) T-67 1010 (1/6) 1010 (1/6) 13-18 mi, N/NNE 58CO <MDA <MDA Co 12 <MDA <MDA 134C 14 <MDA <MDA Number of Nonroutine Reported Measurements = 0 HP3: 1/RADENVOP. PIN

TAB Pa of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3 & i , Docket No(s). 50-250

& 50-251 Location of Facility Dade Florida , Reporting Period Janua 1 December 31 1990 (County, State)

PATHWAY: INGESTION SAMPLES COLLECTED: CRUSTACEA UNITS: PICO Ci/Kg, WET Location with Highest Type and Total of Analyses Number Lower of Limit Detection All Indicator Locations Mean (f)

Name'ean xs ance

,Annual Mean f Control Locations Mean (f)

Performed (LLD). Range Direction Range Range Gamma Isotopic, 4 40K 130 1875 (4/4) T-81 1960 (2/2) 1790 (2/2) 1840 2060 6 mi., S 1860 2060 1740 1840 226R 20 500 (4/4) T-81 837 (2/2) 163 (2/2) 156 1174 6 mi., S 500 1174 156 169 19 (1/4) T-81 19 (1/2) <MDA 6mi., S 228R 90 (2/4) T-81 117 (1/2) 62 (1/2) 61 117 6mi., S "Fe 16 <MDA <MDA "Co <MDA <MDA Co 19 <MDA <MDA Zn 17 <MDA <MDA 134CS <MDA <MDA 137C <MDA <MDA Number of Nonroutine Reported Measurements = 0 HP3: 1/RAOEHVOP. PTH

TABO1 Pa 6 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 Zanua 1 - December 31 1990 (County, State)

PATHWAY: INGESTION SAMPLES COLLECTED: FISH UNITS PICO Ci/Kg, WET Location with Highest Type and Total Number of Analyses Lower of Limit Detection'LLD)

All Indicator Locations Mean (f)

Name'ean zs ance

,Annual Mean f Control Locations Mean (f)

Performed Range Direction Range Range Gamma Isotopic, 4 40K 130 2366 (4/4) T-81 2480 (2/2) 2251 (2/2) 1870 3090 6 mi., S 1870 3090 2150 2352 137CS

(/) T-81 6 mi., S 30 18-42(2/2) <MDA 226R 18 70 (2/4) T-81 116 (1/2) 24 (1/2) 6 mi. S "Mn <MDA <MDA "Fe 16 <MDA <MDA "Co <MDA <MDA Co 10 <MDA <MDA Zn 17 <MDA <MDA

<MDA <MDA Number of Nonroutine Reported Measurements = 0 NP3:1/RAOENVOP.PIN

TAB 1 Pa of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

of Facility Turke Point Units 3 6 4 , Docket No(s). 50-250 &

'ame 50-251 Location of Facility Dade Florida , Reporting Period Janua 1 - December 31 1990 (County, State)

PATHWAY: INGESTION SAMPLES COLLECTED: BROAD LEAF VEGETATION UNITS: PICO Ci/Kg, WET Location with Highest Type and Lower of Limit All Indicator Locations

,Annual Mean f

Total Number Name Mean Control Locations of Analyses Detection Mean (f) zs ance Mean (f)

Performed (LLD) Range Direction Range Range Gamma Isotopic, 36 Be 71 1000 (36/36) T-41 1024 (12/12) 995 (12/12) 240 2130 2 mi., W/NW 550 1740 620 1580 40K 100 3376 (36/36) T-40 4413 (12/12) 2819 (12/12) 1381 5260 3mi., W 2490 5190 1381 5260 137C 139 (31/36) T-67 233 (8/12) 233 (8/12) 24 372 6 mi., S 24 372 . 24 372 131I <MDA <MDA 134C <MDA <MDA Number of Nonroutine Reported Measurements = 0 HP3:1/RADENVOP.PTR

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1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT g UNITS 3 & 4 TABLE 1 Page 8 of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Pacility Turke Point Units 1 & 2 Docket No.(s) 50-250 and 50-251 Location of Pacility Dade Florida (County, State)

Reporting Period Januar 1 - December 31 1990 NOTES

a. The LLD is an "a priori" lower limit of detection which establishes the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 954 probability with only 54 probability of falsely concluding 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.

b. Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (f).

c. Specific identifying information for each sample location is provided in Attachment A.

d. Results are based upon the average net response of two TLDs.

(Thermoluminescent dosimeters).

MDA refers to minimum detectable activity.

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1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANTi UNITS 3 TABLE 1A DEVXATXONS/MZSSXNG DATA A) Pathway: Airborne Locations: T-51 (2 miles NNW) and T-57 (4 miles NW)

Date: 10/2/90 to 10/15/90 Deviation: Failure to continuously provide air sampling at these locations.

Description Due to massive storms, there were power outages of Problem: to the areas in which these sample stations are located. The power was out for approximately the last four hours of the sampling period 10/2/90 to 10/9/90 and the first eight hours of the sampling period 10/9/90 to 10/15/90.

Corrective Verified equipment as operable upon notification Action: that power was restored.

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1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANTi UNITS 3 TABLE 1B ANALYSES WITH LLDs ABOVE TABLE 4 ~ 12-1 DETECTION CAPABILITIES 1/1/9 0 - 12/3 1/9 0 The values specified in Table 4.12-1, Detection Capabilities, were achieved for all samples.

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1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT g UNITS 3 fi TABLE 2 LAND USE CENSUS Dista ce to earest a b 5/90 Milk (c) 5/90 5/9 0 Sector Animal Residence Garden (d)

N L (e) 2.1/350 (g) L NNE 0 (f) 0 NE 0 0 ENE 0 0 0 ESE 0 0 SE 0. 0 SSE 0 0 L (e)

SSW L SW L L L WSW L L

L 4. 0/229 L 3. 7/319 3. 8/305 NNW L (e) 4. 0/328 HP3:1/RADENVOP ~ PTN

1990 ANNUAL RADZOLOGZCAL ENVZRONMENTAL OPERATZNG REPORT TURKEY POZNT PLANT i UNZTS 3 Si 4 TABLE 2 LAND USE CENSUS NOTES a ~ All categories surveyed out to 5 miles radius from the Turkey Point Plant.

b. 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 F 1/350.

c ~ Potential milk animal locations.

d. Gardens with an estimated growing area of 500 square feet or more.

e. 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.

g, Non-residential occupied buildings in these sectors include the following:

Sector Distance N 1.8/349 24-hour Security Staffing Building 4.9/171 Small building/boat dock - not considered a residence NNW 4.5/327 2 mobile homes used for field offices NNW 1.8/345 Security booth at park entrance HP3:1/RADEMVOP ~ PTN

1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT g UNITS 3 0 4 ATTACHMENT KEY TO SAMPLE LOCATIONS HP3:1/RADENVOP.PTN

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1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT i UNITS 3 & 4 ATTACHMENT Page 1 of 4 SAMPLES COLLECTED 'LD PATHWAY: DIRECT RADIATION SAMPLE COLLECTION FREQUENCY: QUARTERLY Approximate Location Direction Distance Name Sector miles Descri tion N-1 N 1 Convoy Point N-5 N 6 North of Moody Drive N-10 N 12 Old Cutler Rd. at S.W. 87 Avenue NNW-1 NNW (1 Turkey Point Entrance Rd.

NNW-10 NNW 9 Burr Rd. at Hainlin Mill Dr.

NW/WNW-1 WNW 1 Turkey Point Entrance Rd.

NW-5 NNW 4 Dolan's Farm on Kings Hwy.

NW 10 Intersec Farm Lite & Coconut Palm

/WNW-5 W 5 Palm Dr. at Tallahassee Rd.

WNW-10 WNW 9 Homestead near Vehicle Inspect. Station W-1 W 1 On-Site near Cooling Tower W-10 W 10 Florida City near Fire Tower WSW-10 WSW 12 Old Hawk Missile Site, South of Florida City SW/SSW-1 SSW 1 On-Site near Land Utilization Offices SW-10 SW 10 U.S. 1 South of Florida City SSW/SW-5 SSW 5 On-Site, Southeast Corner of Cooling Canals SSW-10 SSW 10 At Card Sound Bridge S-5 S 5 On-Site, South End of Cooling Canals S-10 S 10 Card Sound Road at Steamboat Creek SSE/S-1 SSE 1 Turtle Point SSE-10 SSE . 8 Ocean Reef HP3:1/RAOEHVOP ~ PTN

1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANTg UNITB 3 8 4 ATTACHMENT A Page 2 of 4 PATHWAY: AIRBORNE SAMPLES COLLECTED RADIOIODINE AND PARTICULATES SAMPLE COLLECTION FREQUENCY: WEEKLY Approximate Location Direction Distance Name Sector Descri tio T-51 NNW 2 Homestead Bayfront Park T-57 NW 4 Tree Nursery on 316th Street T-58 NW 1 Turkey Point Entrance Road T-72 WSW <1 Turkey Point Boy Scout Camp Contro T-64 NNE 22 Natoma Substation HP3:1/RADENVOP.PTN

1990 e ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANTp UNITS 3 0 4 T ACHMENT Page 3 of 4 PATHWAY: WATERBORNE SAMPLES COLLECTED: SURFACE WATER (OCEAN)

SAMPLE COLLECTION FREQUENCY: MONTHLY Approximate Location Direction Distance Name S cto m les escri tio T-42 ENE (1 '- Biscayne Bay at Turkey Point LT-81 S 6 ,Card Sound, near Mouth of Old Discharge Canal

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'-6V 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 Approximate Location Direction Distance

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'T-42 ENE <1 Biscayne Bay at Turkey Point A1A T-81 S 6 Card Sound, near Mouth of Old Discharge Canal

'contr T-67 N, NNE 13-18 Near Biscayne Bay, Vicinity of Cutler Plant, North to Matheson Hammock Park HP3:1/RAOEHVOP.PTN

1990 ANNUAL RADZOLOGZCAL ENVZRONMENTAL OPERATZNG REPORT TURKEY POZNT PLANT@ UNZTS 3 fi 4 ATTACHME A Page 4 of 4 PATHWAY: INGESTION SAMPLES COLLECTED: CRUSTACEA AND FISH SAMPLE COLLECTION FREQUENCY: SEMI-ANNUALLY Approximate Location Direction .Distance Name Sector iles Descri tion T-81 Card Sound Vicinity of Turkey Point Facility Control:

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 Approximate Location Direction Distance Name Descri tio T-40 South of Palm Dr. on S.W. 117th Street Extension T-41 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 HP3:1/RADEHVOP.PTH

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1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANTi UNITS 3 TACHMENT B RADIOLOGICAL SURVEILLANCE OP FLORIDA POWER AND LIGHT COMPANYiS TURKEY POINT SITE 1990 First Quarter, 1990 Second Quarter, 1990 Third Quarter, 1990 Fourth Quarter, 1990 HP3:1/RADEHVOP.PTH

RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE First Quarter, 1990 Office of Radiation Control Florida Department of Health and Rehabilitative Services

TURKEY POINT SITE Technical Specifications Sampling First Quarter, 1990 Collection Locations Number of Sam le T e e e c

1. Direct Radiation Quarterly 21 42

2. Airborne 2.a Air Iodines Weekly 65 2.b Air Particulates Weekly 69*

3. Waterborne 3.a Surface Water Monthly 3.b Shoreline Sediment Semiannually

4. Ingesti'on 4.a Fish and Invertebrates 4.a.l Crustacea Semiannually 4.a.2 Fish Semiannually 4.b Food Products 4.b.l Broadleaf Monthly Vegetation Total: 201

• 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 got 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.

TURKEY POINT TECHNICAL SPECIFICATIONS SAMPLING First Quarter, 1990 DIRECT RADIATION - TLDs - (micro-R/hour)

Each result is the average net response of two dosimeters.

Sample Deployment: 12-19-89 Site Collection 03-13-90 N-1 6.5 a 0.3 N-5 6.2 a 0.3 N-10 5.6 a 0.3 NNW-1 6.4 + 0.3 NNW-10 6.5 s 0.3 NW/WNW-1 5.1 x 0.3 NW"5 5.5 t 0.3 NW"10 7.8 I 0.4 W/WNW-5 4.8 0.3 WNW-10 6.5 s 0.3 W-1 5.3 s 0.3 W-10 7.0 a 0.4 WSW-10 5.1 0' SW/SSW-1 5.1 0.3 SW-10 5.1 a 0.3 SSW/SW-5 6' + 0 '

SSW" 10 6.1 0.3 S-5 5.6 N 0.3 S-10 6.2 a 0.3 SSE/S-1 5.4 x 0.3 SSE-10 5.0 a 0.3 Notes:

(A) These results have been determined with the assumption that fading is negligible, although detailed testing to confirm this has not been completed.

(B) Testing to confirm compliance with NRC Reg. Guide 4. 13 and ANSI N545-1975 performance standards has not been completed.

Ci m3 Sam le Site Collection Date T51 T57 ~58 T64 T72 01-02-90 <0.02 <0.02 <0.02 <0. 02 <0.02 01-09-90 <0.02 <0 '2 <0.02 <0. 02 <0.02 01-16-90 <0.03 <0.03 <0.03 <0. 03 <0.03 01-23-90 <0.02 <0 '2 <,0. 02 <0. 02 <0.02 01-30-90 <0.02 <0.02 <0.02 <0. 02 <0.02 02-06-90 <0.02 <0.02 <0.02 <0.02 <0.02 02-13-90 <0.03 <0.03 <0 '3 <0.03 <0.03 02-20-90 <0.02 <0.03 <0 '2 <0.02 <0.02 02-28-90 <0.03 <0.03 <0.03 <0.03 <0.03 03-06-90 <0.03 <0.03 <0.03 <0 '2 <0.03 03-13-90 <0.02 <0.02 <0.02 <0.02 <0.02 03-19-90 <0.04 <0.04 <0 '3 <0.03 <0.04 03-26-90 <0.03 <0.03 <0.03 <0.03 <0.03

5 1

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~

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2.b AIR PARTICULATES GROSS BETA Ci m3 Collection Sam le Site Date T51 T57 T58 T64 T72 01-02-90 0. 014 + 0.002 0.012 + 0.002 0.008 + 0.002 0.012 + 0.002 0. 015 + 0.002 01-09-90 0.009 + 0.002 0.007 + 0.002 0.004 + 0.001 0.008 + 0.002 0.007 + 0.002 01-16-90 0.019 + 0.002 0.018 + 0.002 0.017 + 0.002 0.009 + 0.002 0.016 + 0.002 01-23-90 0.006 + 0.002 0.005 + 0.002 0.006 + 0.002 0.007 + 0.002 0.008 + 0.002 01-30-90 0.007 + 0.002 0.003 + 0.001 0.006 + 0.002 0.004 + 0.001 0.008 + 0.002 02-06-90 0.005 + 0.001 0.006 + 0.002 *0.004 + 0.001 0.004 + 0.001 0.003 + 0.001 02-13-90 0.006 + 0.002 0.007 + 0.002 *0.005 + 0.001 0.004 + 0.001 0.005 + 0.002 02-20-90 0.007 + 0.002 0.009 + 0.002 *0.006 + 0.002 0.006 + 0.002 0.006 + 0.002 02-28-90 0.012 0.002 0.010 + 0.002 *0.010 + 0.002 0.009 + 0.002 0.009 + 0.002 03-06-90 0.008 + 0.002 0.008 + 0.002 0.009 + 0.002 0.007 + 0.002 0.008 + 0.002 03-13-90 0.012 + 0.002 0.011 + 0.002 0.015 + 0.002 0.010 + 0.002 0.013 + 0.002 03-19-90 0.004 + 0.002 0.006 + 0.002 0.004 + 0.002 0.006 + 0.002 0.007 + 0.002 03-26-90 0.013 + 0.002 0.016 + 0.002 0.013 + 0.002 0.013 + 0.002 0.014 + 0.002 Means: 0.009 + 0.001 0.009 + 0.001 0.008 + 0.001 0.008 + 0.001 0.009 + 0.001

• NRC split samples.

GAMMA SCANS OF UARTERLY COMPOSITES Ci m3 2.b AIR PARTICULATES First Quarter, 1990 Sample Site Be-7 K-40 Cs-134 Cs-137 T51 0.100 + 0.008 <0. 012 <0.0007 <0.0006 T57 0.106 + 0.008 0.011 + 0.004 <0.0008 <0.0007 T58 0.106 + 0.009 <0.012 <0.0009 <0.0007 T64 0.102 + 0.008 <0.013 <0.0007 <0.0006 T72 0.113 + 0.009 <0.015 <0.0008 <0.0007

3.a SURFACE WATER Ci l Sample Collection Zr-95 Ba-140 Site Date H-3 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 1-131 Cs-134 Cs-137 Ls-140 (A) (5)

T42 01-11-90 <150 350 + 30 <2 <7 <2 <3 <6 <5 <7 <3 <3 <5 02-19-90 <130 330 + 40 <4 <9 <5 <5 <10 <7 <9 <5 <4 <6 03-19-90 <160 340 + 40 <3 <10 <4 <5 <7 <6 <8 <4 <3 <8 T67 01-11-90 <150 250 + 40 <4 <10 <4 <3 <7 <8 <11 <4 <7 02-19-90 <130 240 + 40 <3 <10 <4 <5 <9 <6 <9 <3 <4 <9 03-19-90 <160 210 + 40 <4 <11 <4 <8 <11 <8 <9 <3 <3 <6 T81 01-12-90 220 + 50 360 + 50 <4 <11 <4 <4 <9 <9 <9 <5 <4 <8 02-19-90 910 + 60 390 + 40 <4 <14 <4 <4 <10 <5 <8 <4 <4 <7 03-19-90 <180 380 + 50 <3 <12 <5 <4 <8 <9 <9 <4 <4 <8 (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.

n L

3.b SEDIMENT Ci k d wei ht Sample Collection Site Date Be-7 K-4 0 Co-58 Co-60 Cs-134 Cs-137 Others T42 01-11-90 <130 430 + 80 <11 <14 <12 <12 Ra-226: 721 + 25 T67 01-10-90 <210 1650 + 140 <12 <16 <15 36 + 7 Ra-226: 298 + 24 Th-232: 100 + 27 U-238: 1010 + 110 T81 01-12-90 300 + 50 490 + 90 <10 <12 <14 Ra-226: 615 + 22 Th-232: 135 + 46 4.a.1 CRUSTACEA Blue Crab Ci k wet wei ht Sample Collection Site Date K-40 ~n-54 ~Fe-5 Co-58 Co-60 Zn-65 Ca-134 Ce-137 Ra-226 T67 01-10-90 1840 + 120 <9 <27 <10 <13 <23 <11 <8 156 + 9 T81 01-26-90 2060 + 170 ~

<16 <51 <19 <20 <37 <20 <19 500 + 32 4.a.2 FISH Mixed S ecies Ci k wet wei ht Sample Collection Site Date K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 T67 03-29-90 2150 + 120 <9 <28 <12 <12 <25 <9 <11 24 + 7 T81 01-26-90 3090 + 200 <16 <45 <18 <15 <39 <17 18 + 8 116 + 12

b. BO we we'ample Collection

~Ste Date e 7 ~I- 3 Ce-134 Ce-137 T40 01-11-90 820 + 60 3850 + 150 <14 <10 <10 02-19-90 490 + 60 4590 + 200 <15 <12 24 + 6 03-19-90 630 + 60 5150 + 200 <15 <13 24 + 7 T41 01-11-90 990 + 70 3760 + 160 <18 <10 177 + 10 02-19-90 560 + 70 3570 + 170 <15 <12 141 + 10 03-19-90 650 + 60 2760 + 130 <12 <9 93+ 7 T67 01-11-90 700 + 60 4240 + 180 <19 <11 <13 02-19-90 970 + 70 2290 + 140 <16 <11 40+ 7 03-19-90 1200 + 70 2620 + 150 <11 <10 <12

RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY '

TURKEY POINT SITE Second Quarter, 1990 Office of Radiation Control Florida Department of Health and Rehabilitative Services

)

TURKEY POINT SITE Technical Specifications Sampling Second Quarter, 1990 Collection Locations Number of Sam le T e Fre uenc

1. Direct Radiation Quarterly 21 42

2. Airborne 2.a Air Iodines Weekly 65 2.b Air Particulates Weekly 69*

3. Waterborne 3.a Surface Water Monthly 3.b Shoreline Sediment Semiannually

4. Ingestion 4.a Fish and Invertebrates 4.a.l Crustacea Semiannually 4.a.2 Fish Semiannually 4.b Food Products 4.b.l Broadleaf Monthly 10*

Vegetation Total: 195

• - 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.

TURKEY POINT TECHNICAL SPECIFICATIONS SAMPLING Second Quarter, 1990 DIRECT RADIATION TLD's micro-R hour Each result is the average net response of two dosimeters.

Sample Deployment 03-13-90 Site Collection 06-13-90 N-1 6.6 + 0.3 N-5 5.8 + 0.3 N-10 5.5 + 0.3 NNW-1 5.8 + 0.3 NNW-10 5.9 + 0.3 NW/WNW-1 4.9 + 0.3 Nw-5 5.3 + 0.3 Nw-10 7.6 + 0.4 W/WNW-5 4.9 + 0.3 WNW-10 6.5 + 0.3 W-1 5.2 + 0.3 W-10 6.8 + 0.4 WSW-10 4.9 + 0.3 Sw/SSW-1 4.7 + 0.2 Sw-10 4.8 + 0.3 SSW/SW-5 5.8 + 0.3 SSW-10 5.6 + 0.3 S-5 4.9 + 0.3 S-10 5.4 + 0.3 SSE/S-1 4".9 + 0.3 SSE-10 4.8 + 0.3 Notes:

(A) These results have been determined with the assumption that fading is negligible, although detailed testing to confirm this has not been completed.

Testing to confirm compliance with NRC Reg. Guide 4.13 and ANSI N545-1975 performance standards has not been completed.

IODINE-131 IN WEEKLY AIR FILTERS Ci m3 Sam le Site Collection Date T51 T57 T58 T64 T72 04-03-90 <0.02 <0.02 <0.02 <0 02

~ <0.02 04-10-90 <0.03 <0.03 <0.03 <0.03 <0.03 04-17-90 <0 '2 <0.02 <0.02 <0.02 <0.02 04-24-90 <0.02 <0.02 <0.02 <0.02 <0.02 04-30-90 <0.02 <0.03 <0.03 <0.02 <0.03 05-08-90 <0.02 <0.02 <0.02 <0.02 <0.02 05-14-90 <0 '4 <0.04 <0.04 <0.03 <0.03 05-21-90 <0.03 <0.02 <0.03 <0.02 <0.02 05-29-90 <0.02 <0.02 <0.03 <0.02 <0.02 06-05-90 <0.02 <0.02 <0.02 <0.02 <0.02 06-12-90 <0.02 <0.02 <0.02 <0.02 <0.02 06-18-90 <0.02 <0.02 <0.02 <0.02 <0.03 06-26-90 <0.02 <0.03 <0.03 <0.03 <0.03

2 b AIR PARTICULATES GROSS BETA Ci m3 Collection Sam le Site Date T51 T57 T58 T64 T72 04-03-90 0. 007 + 0.001 0.008 + 0. 002 0.007 0.001 0.008 + 0.002 0.007 + 0.001 04-10-90 0.009 + 0.002 0.014 + 0.002 0.012 0.002 0.008 + 0.002 0.011 + 0.002 04-17-90 0.010 + 0.002 0.010 + 0.002 0.008 0.002 0.009 + 0.002 0.008 + 0.002 04-24-90 0.015 + 0.002 0.012 + 0.002 0.012 0.002 0.015 + 0.002 0.014 + 0.002 04-30-90 0.016 + 0.002 0.011 + 0.002 *0.014 0.002 0.011 + 0.002 0.013 + 0.002 05-08-90 0.014 + 0.002 0.013 + 0.002 *0.012 0.002 0.016 + 0.002 0.012 + 0.002 05-14-90 0.007 + 0.002 0.009 + 0.002 *0.008 0.002 0.011 + 0.002 0.008 + 0.002 05-21-90 0.008 + 0.002 0.012 + 0.002 *0.009 0.002 0.012 + 0.002 0.007 + 0.001 05-29-90 0.013 + 0.002 0.013 + 0.002 0.012 0.002 0.008 + 0.001 0.010 + 0.001 06-05-90 0.011 + 0.002 0.008 + 0.002 0.008 0.001 0.010 + 0.002 0.011 + 0.002 06-12-90 0.007 + 0.002 0.005 + 0.001 0.005 0.001 0.005 + 0.001 0.009 + 0.002 06-18-90 0.009 + 0.002 0.012 + 0.002 0.007 0.002 0.008 + 0.002 0.011 + 0.002 06-26-90 0.010 + 0.002 0.009 + 0.002 0.010 0.002 0.008 + 0.001 0.010 + 0.002 Means: 0.010 + 0.001 0.010 + 0.001 0.010 0.001 0.010 + 0.001 0-010 + 0.001

• NRC split samples.

2.b AIR PARTICULATES GAMMA SCANS OF UARTERLY COMPOSITES Ci m3 Second Quarter, 1990 Sample Site Be-7 K-40 Cs-134 Cs-137 T51 0.103 + 0.010 <0.018 <0.0013 <0.0008 T57 0.122 + 0.012 <0.018 <0.0011 <0.0010 T58 0.100 + 0.010 <0.021 <0.0009 <0.0007 T64 0.090 + 0.010 <0.015 <0.0012 <0.0010 T72 0.093 + 0.010 <0.014 <0.0013 <0.0009

3.a SURFACE WATER Ci l Sample Collection Zr-95 Ba-140 Site Date H-3 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-$ 37 La-140 (A) (B)

T42 04-13-90 <150 380 + 50 <4 <8 <4 <5 <10 <6 <7 <4 <5 05-11-90 <190 390 + 50 <3 <8 <4 <5 <10 <8 <7 <4 <5 <5 06-15-90 <150 380 + 50 <4 <8 <4 <6 <9 <7 <5 <5 <4 <8 T67 04-13-90 <150 280 + 40 <4 <11 <4 <4 <11 <7 <7 <4 <4 <4 05-11-90 <190 330 + 50 <3 <10 <4 <5 <11 <8 <8 <4 <4 <6 06-15-90 <150 300 + 40 <4 <11 <4 <4 <10 <6 <6 <5 <4 <6 T81 04-13-90 <150 450 + 50 <4 <11 <4 <4 <11 <9 <11 <4 <5 <5 I

05-11-90 <190 370 + 40 <4 <10 <3 <5 <10 <8 <8 <4 <4 <4 06-15-90 260 + 50 380 + 40 <3 <9 <5 <5 <11 <7 <8 <4 <5 <9 (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.b.l BROADLEAF VEGETATION Brazilian Pe er Ci k wet wei ht Sample Collection Site Date Be-7 K-40 I-131 Cs-134 Cs-137 T40 04-13-90 990 + 70 4620 + 190 <29 <12 143 + 10

• 05-11-90 520 + 40 4660 + 140 <12 <9 51+ 5 06-15-90 240 + 30 2490 + 100 <9 <6 22+ 4 T4 1 04-13-90 860 + 80 2900 + 150 <30 <13 197 + 11 05-11-90 550 + 50 2860 + 150 <16 <10 106 + 8 06-15-90 940 + 70 2400 + 130 <13 <9 160 + 9 tI T67 04-13-90 1030 + 80 2870 + 170 <25 <9 <13 05-11-90 800 + 70 5140 + 200 <19 <14 <13 06-15-90 620 + 60 5260 + 190 <16 <11 24 + 5

• NRC split sample.

RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE Third Quarter, 1990 Office of Radiation Control Florida Department of Health and Rehabilitative Services

0 TURKEY POINT SITE Technical Specifications Sampling Third Quarter, 1990 Collection Locations Number of Sam le T e Fre uenc

1. Direct Radiation Quarterly 21 42

2. Airborne 2.a Air Iodines Weekly 65 2.b Air Particulates Weekly 69*

3. Waterborne 3.a Surface Water Monthly 3.b Shoreline Sediment Semiannually

4. Ingestion 4.a Fish and Invertebrates 4.a.l Crustacea Semiannually 4.a.2 Fish Semiannually 4.b Food Products 4.b.l Broadleaf Monthly Vegetation Total: 200

• 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 Each result is the average net response of two dosimeters.

Sample Deployment 06-12-90 Site Collection 09-19-90 N-1 6.4 + 0.3 N-5 6.0 + 0.3 N-10 5.5 + 0.3 NNW-1 6.3 + 0.3 NNW-10 6.1 + 0.3 NW/WNW-1 4.9 + 0.3 NW-5 5.5 + 0.3 1

NW-10 7.6 + 0' W/WNW-5 4.8 + 0.3 WNW-10 6.4 + 0.3 W-1 5.1 + 0.3 W-10 6.5 + 0.3 WSW-10 4.5 + 0.2 SW/SSW-1 4.6 + 0.2 SW-10 4.7 + 0.2 SSW/SW-5 5.8 + 0.3 SSW-10 5.9 + 0.3 S-5 5.1 + 0~3 S-10 6.0 + 0.3 SSE/S-1 5.7 + 0.3 SSE-10 4.9 + 0.3

0 2.a IODINE-131 IN WEEKLY AIR FILTERS Ci m3 Sam le Site Collection Date T51 T57 T58 T64 T72 07-03-90 <0.03 <0.03 <0.03 <0.03 <0.03 07-10-90 <0.02 <0.02 <0.02 <0.02 <0.02 07-18-90 <0.02 <0.02 <0.02 <0.02 <0.02 07-23-90 <0.03 <0.03 <0.03 <0.03 <0.03 07-31-90 <0.02 <0.02 <0.02 <0.02 <0.02 08-07-90 <0.03 <0.03 <0.03 <0.03 <0.03 08-14-90 <0.02 <0.03 <0.03 <0.02 <0.02 08-22-90 <0.03 <0.03 <0.03 <0.03 <0.03 08-28-90 <0.04 <0.04 <0.04 <0.04 <0.04 09-04-90 <0.03 <0.03 <0.03 <0.03 <0.03 09-11-90 <0.03 <0.03 <0.03 <0.03 <0.03 09-18-90 <0.02 <0.02 <0.02 <0.02 <0.02 09-24-90 <0.02 <0.03 <0.03 <0.02 <0.02 3

2.b AIR PARTICULATES GROSS BETA Ci m3 Collection Sam le Site Date T51 TS7 T64 T72 07-03-90 0.010 + 0.002 0.012 + 0.002 0.011 + 0.002 0.010 + 0.002 0. 009 + 0. 002 07-10-90 0.008 + 0.002 0. 013 + 0.002 0. 012 + 0.002 0.007 + 0.002 0.012 + 0.002 07-18-90 0.010 + 0.002 0. 010 + 0.002 0.010 + 0.002 0.011 + 0- 002 0.011 + 0.002 07-23-90 0.009 + 0.002 <0 .007 <0 .006 0.009 + 0. 002 0.009 + 0. 002 07-31-90 0.010 + 0. 002 0. 010 + 0.002 0.009 + 0.002 0. Oll + 0. 002 0.011 + 0. 002 08-07-90 0.011 + 0. 002 0. 012 + 0.002 *0.007 + 0.002 0-012 + 0 ~ 002 0-008 + 0. 002 08-14-90 0.007 + 0.002 0.009 + 0.002 *0.008 + 0.002 0.009 + 0.002 0- 007 + 0. 002 08-22-90 0.015 + 0.002 0.013 + 0.002 *0. 017 + 0.002 0.014 + 0. 002 0 014 +

~ 0. 002 08-28-90 0.013 + 0.002 0.013 + 0.002 *0.009 + 0.002 0.009 + 0.002 0.011 + 0. 002 09-04-90 0.006 + 0.002 0.006 + 0.002 0.004 + 0.002 0.007 + 0.002 0.004 + 0.001 09-11-90 0.009 + 0.002 0.013 + 0.002 0.013 + 0.002 0.012 + 0.002 0. Oll + 0. 002 09-18-90 0.007 + 0.002 0.011 + 0.002 0.008 + 0.002 0. 011 + 0. 002 0 ~ 013 + 0. 002 09-24-90 0.006 + 0.002 0.005 + 0.002 0.009 + 0.002 0.007 + 0-002 0-010 + 0. 002 Means: 0. 009 + 0. 001 0. 011 + 0. 001 0. 010 + 0. 001 0 ~ 010 + 0. 001 0.010 + 0.001

• HRC split samples.

2.b AIR PARTICULATES GAMMA SCANS OF UARTERLY COMPOSITES Ci m3 Third Quarter, 1990 Sample Site Be-7 K-40 Cs-134 Cs-137 T51 0.081 + 0.008 <0.016 <0.0006 <0.0007 T57 0.074 + 0.007 0.011 + 0.004 <0.0007 <0.0007 T58 0.093 + 0.007 <0.021 <0.0007 <0.0009 T64 0.079 + 0.006 <0.017 <0.0008 <0.0006 T72 0.083 + 0.008 <0.014 <0.0008 <0.0007

3 a SURFACE HATER Ci 1 Sample Collection Zr-95 Ba-140 Site Date H-3 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 (B)

T42 07-11-90 <170 360 + 50 (4 <11 <4 <5 <9 <8 <6 <5 <3 <5 08-20-90 <120 34Q + 40 <4 <9 <4 <3 <8 <7 <3 <5 09-19-90 <130 230 + 40 <4 <8 <4 (4 <9 (7 (5 <4 <4 <5 T67 07-13-90 <170 300 + 40 <3 <8 <4 <4 <10 <6 <7 <4 <3 08-17-90 <120 250 + 40 <4 <10 <3 <5 <11 <7 (7 <4 <4 <6 09-18-90 <130 290 + 40 <4 <11 <4 <5 <4 <8 T81 07-11-90 140 + 60 430 + 40 <4 <9 <4 <4 <7 <8 <8 <5 <5 <7 08-16-90 130 + 40 230 + 40 <4 <9 <4 <4 <12 <6 <6 <5 <5 <6 09-12-90 <140 410 + 40 <5 <11 <4 <5 <8 <8 <12. <4 (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 samp3.e.

4 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 07-11-90 280 + 50 350 + 80 <11 <11 <10 <9 655 + 14 76 + 18 T67 07-12-90 610 + 70 800 + 100 <15 <15 <12 29 + 7 . 427 + 13 124 + 17 T81 07-11-90 270 + 50 220 + 70 <7 <11 <11 <8 476 + 12 84 + 13 4.a.1 CRUSTACEA Blue Crab Ci k wet wei ht Sample Collection Site Date K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 08-10-90 1740 + 170 <19 <36 <16 <16 <37 <15 <19 169 + 14 62 + 24 T81 08-07-90 1860 + 160 19 + 5 <54 <19 <18 <45 <21 <18 1174 + 21 117 + 25 4.a.2 FISH Mixed S ecies Ci k wet wei ht Sample Collection Site Date K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 Third quarter attempts to collect this sample were not successful. Efforts continue.

T81 08-08-90 1870 + 540 <48 <117 <40 <63 <116 <49 42 + 16 ND ND ND Non-detectable.

4 ~ b. 1 BROADLEA VEGET TION Brazi 'an Pe e C' wet wei ht Sample Collection Site Date Be-7 K-40 1-131 Cs-134 Cs-137 T40 07-13-90 1200 + 80 4450 + 180 <16 <11 270 + 13 08-17-90 1210 + 80 4110 + 180 <14 <13 51+ 8 09-18-90 2130 + 100 4560 + 190 <16 <12 42 + 8 T41 07-13-90 1160 + 70 2470 + 140 <13 <10 252 + 12 08-17-90 1070 + 70 2530 + 140 <11 <10 153 + 10 09-19-90 1740 + 80 3180 + 140 <15 <9 75+ 7 T67 07-13-90 1330 + 80 1730 + 120 <14 <12 264 + 13 08-17-90 1280 + 80 1970 + 140 <15 <10 372 + 15 09-18-90 740 + 70 1530 + 110 <17 <9 329 + 13

RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE Fourth Quarter, 1990 Office of Radiation Control Florida Department of Health and Rehabilitative Services

4 f

-%4

TURKEY POINT SITE 0 Technical Specifications Sampling Fourth Quarter, 1990 Collection Locations Number of Sam e T e Fre uenc

1. Direct Radiation Quarterly 21 42

2. Airborne 2.a Air Iodines Weekly 65 2.b Air Particulates Weekly 69*

3. Waterborne 3.a Surface Water Monthly 3.b Shoreline Sediment Semiannually

4. Ingestion 4.a Fish and Invertebrates 4.a.l Crustacea Semiannually 4.a.2 Fish Semiannually 4.b Food Products 4.b.l Broadleaf Monthly 10*

Vegetation Total: 196

• 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 Each result is the average net response of two dosimeters.

Sample Deployment 09-19-90 Site Collection 12-18-90 N-1 6.5 + 0.3 N-5 5.8 + 0 '

N-10 5.6 + 0.3 NNW-1 5.9 + 0.3 NNW-10 6.2 + 0.3 NW/WNW-1 5.1 + 0.3 NW-5 5.6 + 0.3 NW-'10 7.3 + 0.4 W/WNW-5 4.7 + 0.2

.WNW-10 6.1 + 0.3 W-1 5.0 + 0.3 W-10 6.3, + 0.3 WSW-10 4.7 + 0.2 SW/SSW-1 4.5 + 0 '

SW-10 4.5 + 0 '

SSW/SW-5 5.5 + 0.3 SSW-10 5.7 + 0.3 S-5 5.0 + 0.3 S-10 5.4 + 0.3 SSE/S-1 5.2 + 0.3 SSE-10 4.8 + 0.3

1, 0

IODINE-131 IN WEEKLY AIR FILTERS Ci m3 Sam le Site Collection Date T51 T57 T58 T64 T72 10-02-90 <0.03 <0.03 <0.03 <0.03 <0.03 10-09-90 <0.03(A) <0.03(B) <0.03 <0.03 <0.03 10-15-90 <0.04(C) <0.04(D) <0.04 <0.04 <0.04 10-23-90 <0.02 <0. 02 <0. 02 <0.02 <0.02 10-30-90 <0.03 <0. 03 <0.03 <0.03 <0.03 11-05-90 <0.05 <0.05 <0.05 <0.05 <0.05 11-14-90 <0.02 <0.02 <0.02 <0.02 <0.02 11-20-90 <0.04 <0.04 <0.04 <0.04 <0.04 11-26-90 <0.02 <0.02 <0.03 <0.02 <0.02 12-03-90 <0.02 <0.02 <0.02 <0.02 <0.02 12-12-90 <0.05 <0.05 <0.05 <0.04 <0.05 12-18-90 <0.03 <0.03 <0.04 <0.03 <0.03 12-26-90 <0.04 <0.04 <0.04 <0.04 <0.04 (A) Electrical power was out at the end of this sample due to storms. The equipment is estimated to have run for 165 hours0.00191 days <br />0.0458 hours <br />2.728175e-4 weeks <br />6.27825e-5 months <br /> out of the 168 total hours for this sampling interval.

(B) Electrical power was out at the end of this sample due to storms. The equipment is estimated to have run for 166 hours0.00192 days <br />0.0461 hours <br />2.744709e-4 weeks <br />6.3163e-5 months <br /> out of the 169 total hours fox this sampling interval.

(C) Electrical power was out at the start of this sample due to storms. The equipment is estimated to have run for 134 hours0.00155 days <br />0.0372 hours <br />2.215608e-4 weeks <br />5.0987e-5 months <br /> out of the 143 total hours for this sampling interval.

(D) Electrical power was out at the start of this sample due to storms. The equipment is estimated to have run for 135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br /> out of the 143 total hours for this sampling interval.

0 p

)'

E I

2.b AIR PARTICULATES GROSS BETA Ci m3 Collection Sam le Site Date T51 T57 T58 T64 T72 10-02-90 0. 013 + 0. 002 0.010 + 0.002 0.010 + 0. 002 0. 014 + 0.002 0.015 + 0. 002 10-09-90 (A0.009 + 0.002 (B0.009 + 0.002 0.008 + 0.002 0.010 + 0.002 0.008 + 0. 002 10-15-90 (C0.008 + 0.002 (D0.007 + 0.002 '

0.006 + 0.002 0.007 + 0.002 0.004 + 0. 002 10-23-90 0.012 + 0.002 0.009 + 0.002 0.009 + 0.002 0.008 + 0.002 0.009 + 0.002 10-30-90 0.018 + 0.002 0.018 0.002 0.017 + 0.002 0.018 + 0.002 0.017 + 0.002 11-05-90 0.014 + 0.002 0.017 + 0.002 *0.013 + 0.002 0.017 + 0.002 0.011 + 0.002 11-14-90 0.011 + 0.001 0.017 + 0.002 *0.014 + 0.002 0.013 + 0.002 0.013 + 0.002 11-20-90 0.009 + 0.002 0.012 + 0.002 *0.014 + 0.002 0.014 + 0.002 0.013 + 0.002 11-26-90 0.015 + 0.002 0.014 + 0.002 *0.013 + 0.002 0.013 + 0.002 0.016 + 0.002 12-03-90 0.008 + 0.002 0.009 + 0.002 0.008 + 0.002 0.010 + 0.002 0.010 + 0.002 12-12-90 0.011 + 0.002 0.010 + 0.002 0-012 + 0.002 0.013 + 0.002 0.013 + 0.002 12-18-90 0.011 + 0.002 0.010 + 0.002 0.010 + 0.002 0.008 + 0.002 0.009 + 0.002 12-26-90 0.010 + 0.002 0.006 + 0.001 0.012 + 0.002 0.011 + 0.002 0.011 + 0.002 Means: 0.011 + 0.001 0.011 + 0.001 0.011 + 0.001 0.012 + 0.001 0.011 + 0.001

• NRC split samples.

(A) Electrical power was out at the end of this sample due to storms. The equipment is estimated to have run for 165 hours0.00191 days <br />0.0458 hours <br />2.728175e-4 weeks <br />6.27825e-5 months <br /> out of the 168 total hours for this sampling interval.

(B) Electrical power was out at the end of this sample due to storms. The equipment is estimated to have run for 166 hours0.00192 days <br />0.0461 hours <br />2.744709e-4 weeks <br />6.3163e-5 months <br /> out of the 169 total hours for this sampling interval.

(C) Electrical power was out at the start of this sample due to storms. The equipment is estimated to have run for 134 hours0.00155 days <br />0.0372 hours <br />2.215608e-4 weeks <br />5.0987e-5 months <br /> out of the 143 total hours for this sampling interval.

(D) Electrical power was out at the start of this sample due to storms. The equipment is estimated to have run for 135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br /> out of the 143 total hours for this sampling interval.

4 2 b A AR CU CA 0 Fourth Quarter, 1990 Sample Site Be-7 K-40 Cs-134 Cs-137 T51 0. 1016 + 0. 0108 <0.0165 <0.0010 <0.0009 T57 0.0988 + 0.0108 <0.0152 <0.0008 <0.0008 T58 0.0829 + 0.0119 <0.0180 <0.0009 <0.0009 T64 0.1141 + 0.0109 <0.0174 <0.0009 <0.0009 T72 0.0843 + 0.0127 <0.0191 <0.0009 <0.0009

3.a SURFACE WATER Ci l Sample Collection Zr-95 Ba-140 Site Date H-3 K-40 Mn-54 Pe-59 Co-58 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 (A) (B)

T42 10-15-90 <130 333 + 40 <5 <10 <4 <5 <9 <7 <8 <5 <4 <6 11-16-90 <137 219 + 40 <4 <9 <4 <5 <9 <7 <10 <5 <4 <6 12-14-90 <136 200 + 35 <4 <10 <5- <6 <8 <7 <11 <5 <5 T67 10-15-90 <130 308 + 39 <5 <9 <4 <4 <7 <8 <8 <5 <4 <8 11-16-90 <175 249 + 34 <5 <12 <4 <5 <9 <6 <9 <4 <5 <8 12-14-90 <137 314 + 34 <4 <10 <4 <4 <8 <8 <12 <5 <6 T81 10-12-90 <140 361 + 38 <4 <9 <4 <3 <11 <7 <10 <5 <3 <10 11-16-90 <175 313 + 40 <4 <10 <4 <4 <8 <8 <10 <4 <4 <8 12-14-90 121 + 45 250 + 42 <4 <11 <5 <5 <8 <7 <11 <5 (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.2 FISH Mixed S ecies Ci k wet wei ht Sample Collection Site Date K-40 Mn-54 Fe-59 Co-58 Co-60 T67 10-,08-90 2352 + 158 <13 <37 <10 <14 Zn-65 Cs-134 Cs-137

<26 <14 <12 4.b.l t

BROADLEAF VEGET ON B azi 'an e er Ci k wet wei ht Sample Collection Site Date Be-7 K-40 1-131 Cs-134 Cs-137 T40 10-12-90 2121 + 109 5190 + 202 <29 <13 84+ 9

• 11-16-90 982 + 68 4204 + 165 <22 95+ 8 12-14-90 569 + 51 5085 + 165 <12 <10 30+ 6 T41 10-12-90 1415 + 98 3218 + 162 <26 <14 117 + 9 11-16-90 882 + 67 2808 + 140 <23 <12 69+ 7 12-14-90 1466 + 81 2301 + 118 <14 <10 67+ 7 T67 10-12-90 1580 + 83 1381 + 96 <22 <8 270 + 11 11-16-90 930 + 70 2304 + 122 <21 208 + ll 12-14-90 759 + 65 2494 + 123 <15 <9 352 + 13

• NRC split sample.

1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT i UNITS 3 0 4 ATTACHMENT C RESULTS PROM THE INTERLABORATORY COMPARISON PROGRAM 1990 HP3:1/RADEHVOP.PTH

C E

4

FLORIDA DEPT OF HRS EPA INTERLABORATORY CROSS-CHECK PROGRAM DATA January through June, 1990 Media Nuclide Collection EPA Units Normal. Mean of N.D;K. Action Mon Day Yr Known Range Analyses Level FILTER Alpha 03 30 90 5 pCi/F 0.118 5.33 0. 12 FILTER Beta 03 30 90 31 pCi/F 0.118 28.33 -0. 92 FILTER Cs-137 03 30 90 10 pCi/F 0.000 11.00 0. 35 FILTER. Sr-90 03 30 90 10 pCi/F 0.788 8.33 -1. 92 MILK I-131 04 27 90 99 pCi/L 0.354 98.00 -0. 17 MILK Cs-137 04 27 90 24 pCi/L 0.000 25.00 0. 35 MILK K 04 27 90 1550 mg/L 0.379 1536.67 -0. 30 MILK Sr-89 04 27 90 23 pCi/L 0.000 22.00 -0.35 MILK Sr-90 04 27 90 23 pCi/L 0 000 F 21.00 -0.69 WATER Alpha 01 26 90 12 pCi/L 0.118 10.33 -0.58 WATER Alpha 05 11 90 22 pCi/L 0.492 15.67 -1.83 WATER Beta 01 26 90 12 pCi/L 0.000 12.00 0.00 WATER Beta 05 11 90 15 pCi/L 0.236 19.00 1.39 WATER Co-60 02 09 90 15 pCi/L 0.118 15.67 0.23 WATER Co-60 06 08 90 24 pCi/L 0.118 25.67 0.58 WATER Zn-65 02 09 90 139 pCi/L 0.211 139.67 0.08 WATER Zn-65 06 08 90 148 pCi/L 0.197 153.00 0.58 WATER Ru-106 02 09 90 139 pCi/L 0.464 138.00 -0.12 WATER RQ-106 06 08 90 210 pCi/L 0.056 206.00 -0.33 WATER Ba-133 02 09 90 74 pCi/L 0.169 73.00 -0.25 WATER Ba-133 06 08 90 99 pCi/L 0.295 96.33 -0.46 WATER Cs-134 02 09 90 18 pCi/L 0.118 17.33 -0.23 WATER Cs-134 06 08 90 24 pCi/L 0.000 24.00 0.00 WATER Cs-137 02 09 90 18 pCi/L 0.236 18.00 0. 00 WATER Cs-137 06 08 90 pCi/L 0.118 25.67 0.23 WATER H-3 02 23 90 25'976 pCi/Z 0.225 5143.33 0.58 WATER H-3 06 22 90 2933 pCi/L 0.165 3033.33 0.49 WATER Sr-89 01 12 90 25 pCi/L 0. 236 21.33 -1.27 WATER Sr-89 05 04 90 '7 pCi/L 0. 118 7.67 0. 23 WATER Sr-90 01 12 90 20 pCi/L 0. 394 18.33 -1. 92 WATER Sr-90 05 04 90 7 pCi/L 0 000

~ 7.00 0. 00 NOTES:

Normal.: Normalized range. As defined in "Environmental Radioactivity Range Laboratory Intercomparison 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.

FLORIDA DEPT. OF HRS - EPA INTERLABORATORY CROSS-CHECK PROGRAM DATA July through December, 1990 Media Nuclide Collection EPA Units Normal. Mean of N.D.K. Action Mon Day Yr Known Range Analyses Level FILTER Alpha 08 31 90 10 pCi/F 0.236 12.33 0. 81 FILTER Beta 08 31 90 62 pCi/F 0.118 59.33 -0.92'.69 FILTER Cs-137 08 31 90 20 pCi/F 0.000 22.,00 FILTER Sr-90 08 31 90 20 pCi/F 0.473 15.33 -1.62 MILK I-131 09 28 90 58 pCi/L 0.295 58.33 0.10 MILK Cs-137 09 28 90 20 pCi/L 0.236 21.00 0. 35 MILK K 09 28 90 1700 mg/L 0.188 1744.33 0. 90 MILK Sr-89 09 28 90 16 pCi/L 1.345 21.00 1. 73 MILK Sr-90 09 28 90 20 pCi/L 0.709 8.67 -3. 93 WATER Alpha 09 21 90 10 pCi/L 0.000 10.00 0. 00 WATER Beta 09 21 90 10 pCi/L 0.000 14.00 1.39 WATER Co-60 10 05 90 20 pCi/L 0.118 21.33 0. 46 WATER Zn-65 10 05 90 115 pCi/L 0.197 119.00 0.58 WATER Ru-106 10 05 90 151 pCi/L 0.630 153.67 0.31 WATER Ba-133 10 05 90 110 pCi/L 0.054 105.67 -0.68 WATER Cs-134 10 05 90 12 pCi/L 0.118 11.33 -0.23 WATER Cs-137 10 05 90 12 pCi/L 0.236 13.00 0.35 WATER H-3 10 19 90 7203 pCi/L 0. 255 5656.33 3 72

~

WATER I-131 08 10 ,90 39 pCi/L .0. 098 40.67 0. 48

~ ~

J g~

I t y V

NOTES:

Normal.: Normalized range. As defined in "Environmental Range Radioactivity Laboratory Intercomparison 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.DE 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.

ACTION LEVEL:

Cause: Erroneously over estimated chemical recovery of strontium carrier.

Corrective Action: Try to improve purity of isolated strontium carrier.

(2) Cause: Incorrect counting efficiency used in calculation.

Corrective Action: Double check all parameters used in the calculation.