ML17352B133

1994 Annual Radiological Environ Operating Rept Turkey Point Plant Units 3 & 4. W/950421 Ltr

ML17352B133
Person / Time
Site:	Turkey Point
Issue date:	12/31/1994
From:	Plunkett T FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-95-110, NUDOCS 9505020194
Download: ML17352B133 (84)

Text

RIG RITY

.ACCELERATED RIDS PROCESSING) 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

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 & Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

"1994 Annual Radiological Environ Operating Rept Turkey Point Plant Units 3 & 4." 950421 tr.

DISTRIBUTION CODE: IE25D COPIES RECEIVED:LTR TITLE: Environmental Monitoring Rept (per Tech Specs)

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RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 3 3 PD2-1 PD 1 1 CROTEAU,R 1 1 INTERNAL: ICE C5 ER 01 1 1 NRR/ADAR/PDLR 1 1 GR'2 D 1 1 RGN2 FILE 1 1 EXTERNAL: LITCO AKERS,D 1 1 NRC PDR 1 1 YO'I'E TO ALL"RIDS" RECIPIEYTS:

PLEASE HELP US TO REDUCE KVhSTE! CONTACT'I'IIE DOCL'IIEYTCOYTROL DESk, ROOXf Pl-37 IEXT. 04-o033 ) TO ELlhfIYATE)'OI.'R X'ANIL'l<OII DISTRI 8UTIOY LIS'I'S I'OR DOCL'5 I Ei'I'S YOL'OY"I'LTI'.D!

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0 APR 21 1ggg L-95-110 10 CFR 50.36b 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 1994 Annual Radiological Attached is the 1994 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 or comments regarding this information, please contact us.

Very truly yours, T. F. Plunkett Vice President Turkey Point Plant JEK Attachment cc: S. D. Ebneter, Regional Administrator, Region II, USNRC T. P. Johnson, Sr. Resident Inspector, USNRC, Turkey Point Plant 9505020194 94125i PDR 'DQCK 05000250 PDR R

an FPL Group company

1994 ANNUAL RADIOLOGICAL ENVIRONNENTAL OPERATING REPORT TURKEY POINT PLANT UNITS 3 L 4 LICENSE NOS. DPR-31, DPR-41 DOCKET NOS. 50-250, 50-251 Data submitted by: Florida DHRS Prepared by:

Reviewed by:

0 1994, ANNUAL RADIOLOGICAL'NVIRONMENTALOPERATING REPORT TURKEY POINT PLANT UNITS 3 & 4 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, 1994 Second Quarter, 1994 Third Quarter, 1994 Fourth Quarter, 1994 Results from the Interlaboratory Comparison ATTACHMENT C Program, 1994

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT UNITS 3 6 4 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 & 4, during the surveillance year, is well within the limits established by 10 CFR 50, Appendix I. The sampling period was from January 1, 1994 to December 31, 1994.

Additionally, supplemental samples collected by the State of Florida, HRS, do not indicate adverse trends in the radiological environment.

1994 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 . RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 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.

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 & 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.

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT UNITS 3 & 4

c. Surface water samples are'ollected 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.

Zah;La ~,

Zzln~ ~mazy. provides a summary for all specified P~qzam samples collected during the referenced surveillance period.

,Deviations from the sample schedule, missing data and/or samples not meeting the specified "A PRIORI" LLD, noted and explained in Tables 1A and 1B respectively.

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

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT UNITS 3 & 4 D.

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 Tz~~~, Land Limp Qaazus

~marx.

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.

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.

IZI. DISCUSSION AND INTERPRETATION OF RESULTS A.

The Annual Radiological Environmental Operating Report contains the summaries, interpretations and information required by the Turkey Point Units 3 & 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.

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT UNITS 3 6 4

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 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 sites T-81 and T-42. 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 1% 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. Food Products:

The results are consistent with past measurements; only naturally occurring radionuclides were detected.

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT UNITS 3 & 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 all locations. The maximum value is about 12% of the Table 3.12-2 reporting level. No other fission products were detected.

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 & 4, during the surveillance year, are well within "as low as reasonably achievable (ALARA) "

criteria established by 10 CFR 50, Appendix I.

Name of Facility Location of Facility (County, State) n, ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL SUMhGLRY i Docket No (s) .

, Reporting Period D Page 1 of 8 PATHWAY: DIRECT RADIATION SAMPLES COLLECTED: TLD UNITS: micro-R/hr Location with Highest Type and Lower Limit All Indicator Annual Mean Total Number of Locations C Control Locations of Analyses Detection'LLD) Mean (f) Distance & Mean (f)

Performed Range Direction Range Range Exposure 5.18 (74/74) NW-10 7. 62 (2/2) 6.05 (4/4)

Rate, 78 4.23 7.68 10 mi., NW 7.55 7. 68 6.04 6.05 Number of Nonroutine Reported Measurements = 0

Name of Facility Location of Facility PATHWAY: AIRBORNE D

P, ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

(County, State)

Docket No (s) .

Reporting Period SAMPLES COLLECTED: RADlOIODINE AND PARTICULATES UNITS: pCi/m Location with Highest Type and Lower Limit All Indicator Annual Mean Total Number of Locations C Control Locations of Analyses Detection'LLD) Mean (f) Distance & Mean (f)

Performed Range Direction Range Range

"'I, 260 0.024 <MDA <MDA Gross Beta, 260 0.0025 0.012 (205/208) T-52 0. 014 (26/26) 0.012 (52/52) 0.003 0.022 0.7 mi., W 0.006 0.022 0.005 0.022 Composite Gamma Isotopic, 20 Be 0.0052 0.1190 (16/16) T-58 0. 1316 (4/4) 0.1318 (4/4) 0.084 0.1433 1 mi., NW 0.1215 0.1433 0.1071 0.1551 210Pb 0.0112 (16/16) T-72 0.0121 (4/4) 0.0110 (4/4) 0.0065 0.0159 <1 mile, WSW 0.0081 0.0153 0.0077 0.0137 134C 0.00069 <MDA <MDA C 0.00066 <MDA <MDA Number of Nonroutine Reported Measurements = 0

~BLF~

ENVIRONMENTAL RADZOLOGZCAL MONZTORZNG PROGRAM ANNUAL

SUMMARY

Name of Facility Location of Facility 4, Docket No (s) .

, Reporting Period (County, State)

PATHWAY: WATERBORNE SAMPLES COLLECTED: SURFACE WATER UNZTS1 PCi/L Location with Highest Type and Lower Limit All Zndicator Annual Mean Total Number of Locations C Control Locations of Analyses Detection'LLD) Mean (f) Distance & Mean (f)

Performed Range Direction Range Range Tritium, 36 230 197 (11/24) T-81 206 (10/12) <MDA 112 299 6 mi., S 131 299 Gamma Zsotopic, 36 40< 279 (24/24) T-81 60 293 (12/12) 237 (11/12) 135 399 6 mi., S 231 399 133 338

<MDA <MDA F <MDA <MDA 58C <MDA <MDA 60Co <MDA <MDA Zn <MDA <MDA Zr-Nb <MDA <MDA 131 Z <MDA <MDA 134C

<MDA <MDA 137C

<MDA <MDA Ba-La <MDA <MDA Number of Nonroutine Reported Measurements = 0

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Docket No (s) .

Location of Facility D F , Reporting Period n (County, State)

PATHWAY: WATERBORNE SAMPLES COLLECTED: SHORELINE SEDIMENT UNITS: pCi/kg, DRY Location with Highest Type and Lower of Limit All Indicator ,Annual Mean Tota1 Number Locations Control Locations of Analyses Detection'LLD) Mean (f) Dz.stance & Mean (f) b Performed Range Direction Range Range Gamma Isotopic, 6 Be 100 188 (4/4) T-42 210 (2/2) <MDA 109 224 <1 mi., ENE 196 224 K 140 428 (4/4) T-42 463 (2/2) 372 (2/2) 321 490 <1 mi., ENE 436 490 319 425 232Th 52 <MDA 40 (1/2) 226R T-42 49 580 (4/4) 716 (2/2) 110 (2/2) 386 778 <1 mi., ENE 655-778 108-111 23SU T-42 85 (2/4) 97 (1/2) <MDA 73 97 <1 mi., ENE Co <MDA <MDA Co 12 <MDA <MDA 134 C 14 <MDA <MDA 137C 12 <MDA <MDA Number of Nonroutine Reported Measurements = 0

Name of Facility Location of Facility ',

ENVIRONMENTAL RADZOLOGZCAL MONITORING PROGRAM ANNUAL

SUMMARY

(County, State) 4, Docket No (s) .

Reporting Period PATHWAY: INGESTION SAMPLES COLLECTED: CRUSTACEA UNITS: pCi/kg, WET Location with Highest Type and Lower Limit All Indicator ,Annual Mean Tota1 Number of Locations Control Locations of Analyses Detection Mean (f) Distance & Mean (f) b Performed (LLD) Range Direction Range Range Gamma Isotopic, 4 40K 1108 (2/2) T-81 130 1108 (2/2) 934 (2/2) 981 1236 6 mi., S 981 1236 904 964 226R T-81 20 206 (1/2) 206 (1/2) <MDA 6 mi., S

<MDA <MDA 59Fe 16 <MDA <MDA 58Co <MDA <MDA 60C 19 <MDA <MDA Zn 17 <MDA <MDA 134C

<MDA <MDA 137C

<MDA <MDA Number of Nonroutine Reported Measurements = 0

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Docket No (s) .

Location of Facility D Reporting Period (County, State)

PATHWAY: INGESTION SAMPLES COLLECTED: FISH UNiTS: pCi/kg, WET Location with Highest Type and Total Number Lower of Limit All Indicator ,Annual Mean Locations Control Locations of Analyses Detection Mean (f) Distance 6 Mean (f) ~

Performed (LLD) Range Direction Range Range Gamma Isotopic, 4 K 130 2670 (2/2) T-81 2670 (2/2) 2595 (2/2) 2464 2876 6 mi., S 2464 2876 2371 2819

'4Mn <MDA <MDA "Fe <MDA

$ 8Co

<MDA <MDA 60C 10 <MDA <MDA Zn 17 <MDA <MDA 134( <MDA 137C <MDA Number of Nonroutine Reported Measurements = 0

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Docket No(s).

Location of Facility , Reporting Period (County, State)

PATHWAY: INGESTION SAMPLES COLLECTED: BROAD LEAF VEGETATION UNITS: pCi/kg, WET Location with Highest Type and Total Number Lower of Limit All Indicator ,Annual Mean Locations of Analyses Performed Detection'ean (LLD) Range (f) D3.stance Direction Range Control Locations Mean Range (f) b Gamma Isotopic, 36 Be 71 1708 (24/24) T-40 1852 (12/12) 972 (12/12) 974 2976 3 mi., W 1107 2976 637 1501 K 100 3788 (24/24) T-41 3904 (12/12) 4035 (12/12) 2495 5148 2 mi., W/NW 2956 5049 3031 5711 1 37C 103 (23/24) T-41 135 (11/12) 30 (1/12) 14 236 2 mi., W/NW 39 236 1oPb 688 (2/24) T-40 688 (2/12) 307 (1/12) 636 739 3 mi., W 636- 739 131 I <MDA <MDA 134C

<MDA <MDA Number of Nonroutine Reported Measurements = 0

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Docket No.gs)

Location of Facility Fl (County, State)

Reporting Period 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 0

system background that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a real signal.

LLDs in this column are at time of measurement. in Attachment B for the individual samples have been corrected to the time of samplereported The MDAs 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.

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 & 4 ThRLZLlh Page 1 of 2 DEVIATIONS/MISSING DATA A) Pathway: Direct Exposure TLDs Location: N-7, 7 Miles North Date: 12/14/93 to 03/22/94 Deviation: Failure to provide continuous monitoring.

Description TLD reader failure during readout cycle.

of Problem:

Corrective Repair of TLD reader.

Action:

B) Pathway: Direct Exposure TLDs Location Quarter & Date of Missing Data NW-5 1 & 2, 12/14/93 to 6/8/94 NW-5 4, 9/22/94 to 12/7/94 NW-10 1, 12/14/93 to 3/22/94 NW-10 3, 6/8/94 to 9/22/94 WNW-10 2,3,&4, 3/22/94 to 12/7/94 Deviation: Failure to provide continuous monitoring.

Description TLDs were missing when collection was attempted.

of Problem:

Corx ective Replaced TLDs. Relocation of the replacements for Action: those prone to tampering has been somewhat successful.

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 & 4 XhEKF~ Page 2 of' DEVIATIONS/MISSING DATA C) Pathway: Airborne Radioiodines 6 Particulates, weekly sampling Location: T-58, 1 mile NW Dates: 07/19/94 to 07/25/94 and 07/25/94 to 8/3/94 Deviation: Failure to provide continuous monitoring.

Description Power source failure about one day into the first of Problem: sampling period; power restored about one day into the second sampling period.

Corrective Verified operability of sampling equipment upon Action: notification of power restoration.-

D) Pathway: Airborne Radioiodines 6 particulates, weekly sampling.

Location Sampling Period 0 Typ Sample T-72 <1 mi., WSW 7/19/94 to 7/25/94 88%

T-57 4 NW 8/3/94 to 8/10/94 88%

T-72 <1 mi., WSW 8/22/94 to 8/30/94 75%

T-72 <1 mi., WSW 12/6/94 to 12/13/94 89%

Deviation: Failure to provide continuous monitoring.

Description Suspected power interruptions during of Problem: sampling period, based upon integrated sample volume not meeting expectations.

Corrective Verified operability of the sampling Action: equipment; note, the sampling pumps self-start at the end of a power interruption.

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Zc 4 TABLE 1B ANALYSES WITH LLDs ABOVE TABLE 4.12-1 DETECTION CAPABILITIES 1/1/94 - 12/31/94 A) Analysis: Iodine 131 in weekly air filters.

Sampling Location: T-64 (Control Location), 22 miles NNE Sampling Period: 2/8/94 to 2/16/94 Required LLD: 0.07 pCi/m LLD Achieved: 2.49 pCi/m'ause:

Sample cartridge misplaced upon receipt at laboratory.

Cartridge discovered and analyzed 5/2/94. Long delay time precluded achieving required sensitivity.

HP3: 1/RADENVOP . PTN

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY> POINT PLANTi UNITS 3 Sc 4 TABLE 2 LAND USE CENSUS Distance to Nearest a b 6/94 Milk (c) 6/94 6/94 Sector Animal Residence Garden (d)

N L (e) 2.1/350 (g) 0 (f) 0 NE 0 ENE ESE SE SSE SSW SW WSW L L L 3.6/302 (h) 4. 3/303

3. 7/315 (i) L (g) 3.6/308 4.5/327 (i) 4.7/328 4.0/328 HP3: 1/RADENVOP . PTN

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Sc 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 2.1/350.

C. Potential milk animal locations.

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

L denotes that the'ector 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 Descri tion N 1.8/349 24-hour Security Staffing Building NW 3.5/304 24-hour Security Staffing NNW 4.5/327 Mobile homes used for field offices NNW 1.8/345 Security booth at park entrance

h. This house has been converted into a construction office The status of the goats identified at these locations are unknown. The property owners have been unresponsive to numerous attempts to discuss the animals.

HP3:1/RADENVOP.PTN

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Ec 4 ATTACHMENT A KEY TO SAMPLE LOCATIONS HP3:1/RADENVOP.PTN

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Zc 4

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1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 & 4 KEY TO SAMPLE LOCATIONS

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANTi UNITS 3 & 4 Page 1 of 4 PATHWAY: DIRECT RADIATION SAMPLES COLLECTED: TLD SAMPLE COLLECTION FREQUENCY'UARTERLY Location" N-2 Convoy Point, Parking Area N-7 Black Point Marina Parking Lot N-10 Old Cutler Rd. approx. 196th Street NNW-2 East End North Canal Road NNW-10 Bailes Road & U.S. g1 NW-1 Turkey Point Entrance Road NW-5 Mowry Drive & 117th Avenue NW-10 Newton Road, North of Coconut Palm Drive WNW-10 Homestead Middle School W-1 On-Site, North Side of Discharge Canal W-5 Palm Drive & Tallahassee Road W-9 Card Sound Road, 0.6 mile from U.S. $ 1 WSW-8 Card Sound Road, 3.4 miles from U.S. $ 1 SW-1 On-Site near Land Utilization Offices SW-8 Card Sound Road, 5 miles from U.S. g1 SSW-5 On-Site, Southwest Corner of Cooling Canals SSW-10 Card Sound Road, west side of Toll Plaza S-5 On-Site, South East Corner of Cooling Canals S-10 Card Sound Road at Steamboat Creek SSE-1 Turtle Point SSE-10 Ocean Reef NNE-22 Natoma Substation "The location name is the direction sector approximate distance (miles)

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 & 4 Page 2 of 4 PATHWAY: AIRBORNE SAMPLES COLLECTED: RADIOIODINE AND PARTICULATES SAMPLE COLLECTION FREQUENCY: WEEKLY Approximate Location Direction Distance T-51 NNW Entrance Area to Biscayne National Park T-52 Florida City Substation Interim Alternate to T-51 T-57 NW SW 107th Avenue at Mowry Canal T-58 NW Turkey Point Entrance Road T-72 WSW Just before entrance to Land Utilization's access gate.

T-64 NNE 22 Natoma Substation

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 & 4 Page 3 of 4 PATHWAY: WATERBORNE SAMPLES COLLECTED: SURFACE WATER (OCEAN)

SAMPLE COLLECTION FREQUENCY: MONTHLY Approximate Location Direction Distance T-42 ENE Biscayne Bay at Turkey Point T-81 Card Sound, near Mouth of Old Discharge Canal T-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 Approximate Location Direction Distance T-42 ENE Biscayne Bay at Turkey Point T-81 Card Sound, near Mouth of Old Discharge Canal T-67 N, NNE 13-18 Near Biscayne Bay, Vicinity of Cutler Plant, North to Matheson Hammock Park

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 & 4 Page 4 of 4 PATHWAY: INGESTION SAMPLES COLLECTED: CRUSTACEA AND FISH SAMPLE COLLECTION FREQUENCY: SEMI-ANNUALLY Approximate Location Direction Distance

~9auz T-81 Card Sound Vicinity of Turkey Point Facility Cant~.

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 Approximate Location Direction Distance T-40 South of Palm Dr. on S.W. 117th Street Extension T-41 WNW Palm Dr., West of Old Missile Site near Plant Site Boundary Cant~:

N, NNE 13-18 Near Biscayne Bay, Vicinity of Cutler Park, North to Matheson Hammock Park

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 & 4 RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANYS TURKEY POINT SITE 1994 First Quarter, 1994 Second Quarter, 1994 Third Quarter, 1994 Fourth Quarter, 1994

RADIOLOGICAL SURVEILLANCE OF POHER AND LIGHT COMPANY'S

'LORIDA TURKEY POINT SITE First Quarter, 1994 Office of Radiation Control Florida Department, of Health and Rehabilitative Services

TURKEY POINT SITE Technical Specifications Sampling First Quarter, 1994 Sam le T e Col-lect-ion Fre enc Locations Number-of

1. Direct Radiation Quarterly 22 20

2. Airborne 2.a Air Iodines Weekly 5 65 2.b Air Particulates Weekly 5 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 1 4.a.2 Fish Semiannually 0 4.b Food Products 4.b.l Broadleaf Monthly Vegetation 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 12-14-93 Site Collection 03-22-94 N-2 5.64 + 0.16 N-7 N-10

~A) 5.28 + 0. 17 NNW-2 4.50 + 0.14 NNW-10 5.66 + 0.17 NW-1 4.68 + 0.25 NW-5 (B)

NW-10 (B)

WNW-10 6.41 + 0.17 W-1 6.69 + 0.18 W-5 (C) 4.89 + 0.15 W-9 4.88 + 0.15 WSW-8 5.25 + 0.16 SW-1 (C) 5.56 + 0.16 SW-8 4.97 + 0.16 SSW-5 5.07 + 0.16 SSW-10 (C) 5.42 + 0.18 S-5 4.91 + 0.21 S-10 5.58 + 0.15 SSE-1 (C) 4.91 + 0.17 SSE-10 5.76 + 0.16 NNE-22 6.04 + 0.18 (A) The results for site N-7 were lost due to malfunction of the dosimeter.

(B) The dosimeters for sites NW-5 and NW-10 were missing when t collection (C) This SSE-1 was attempted.

dosimeters at sites W-5, SW-l, SSW-10, S-10, and were found lying on the ground near where they had been deployed.

IODINE-131 IN WEEKL A R F L ERS Ci m Sam le Site Collection Date T51 T52 T58 T64 T72 01-04-94 <0. 02 <0.02 <0.02 <0.02 <0.02 01-13-94 <0.02 <0.03 <0.03 <0.03 <0.03 0~8M 4 01-25-94

<0 .04

<0; 04

<0 -03

<0.04

<0 -03

<0. 04

<0. 03~0<0.04

<0.04

-03 02-02-94 <0. 02 <0. 02 ,<0. 02 <0. 02 <0. 02 02-08-94 <0. 02 <0. 03 <0.02 <0. 02 <0. 03 02-16-94 <0. 03 (A) <0.03 <0.03 <2. 49 (B) <0. 03 02-22-94 <0. 02 <0.02 <0.02 <0. 02 <0. 02 (C) 03-01-94 <0. 01 <0. 02 <0.01 <0.01 <0.02 03-07-94 <0.02 <0.02 <0.02 <0.02 <0.02 03-17-94 <0.02 <0.02 <0.02 <0.02 <0.02 03-23-94 <0.02 <0.02 <0.02 <0.02 <0.02 03-31-94 <0.01 <0.01 <0.01 <0.01 <0.01 (A) The new filter being deployed at site T51 got mixed up with the old filter being collected at this site. Both. filters were sent in for analysis, and neither filter had any meas-urable activity.

'(B) This iodine filter cartridge for site T64 was accidentally left, in the shipping carton when these filters were received for analysis on 02-22-94. This oversight was not discovered due to the presence of the extra cartridge from site T51.

The misplaced .filter.-for site T64 was discovered on 05-02-94, when the carton had been reused to ship a later batch of air filters. This T64 filter was analyzed on 05-02-94, but the required sensitivity of <0.07 pCi/m3 could not be achieved due to,the long delay before. this. analysis was performed.

. (C) .At the beginning of this sampling interval, the equipment for site T72 was moved from a location inside a security fence to a more accessible location just outside the fence in the same general direction from and slightly closer to the nuclear generating units.

Supplementary air sample site T52 is now being temporarily used as a substitute for Technical Specifications site T57, which was destroyed by Hurricane Andrew.

2.b AIR PARTICULATES . GROSS BETA" Ci m3 Sam le Site Collection Date T51 T52 T58 T64 T72 01-04-94 0. 008 + 0. 002'" 0.011 + 0.002 0.009 + 0. 002 0.012 + 0. 002 0.011 + 0.002 01-13-94 0.010 + 0 f001, 0.013 + 0.002 0.010 + 0.002 0.011 + 0;002 0.011 + 0.002 01-18-94 0.008 + 0;003 0.013 + 0.003 0.013 + 0.003 0.011 + 0.003 0.012 + 0.003 01-25-94 0.012 + 0.002 0.010 + 0.002 0.013 + 0.002 0.013 + 0.002 0.011 + 0.002 I

02-02-94 0.007 + 0. 002, 0.009 + 0.002 0.005 + 0.001 0.012 + 0.002 0.005 + 0.001 02-08-94 0.015 + 0;002 0.022 + 0.003 *0.013 + 0.002 0. 017 + 0.002 0-014 + 0.002 02-16 0.007 + 0)002 0.009 +. 0.002 *0.008 + 0.002 0.009 + 0.002 0.009 + 0.002 02-22-94 0.004 + 0.002 0.006 + 0.002 *0.006 + 0.002 0.007 + 0.002 (AO-006 + 0.002 03-01-94 0.010 + 0. 002! 0.009 + 0.002 *0.012 + 0.002 0.008 + 0.002 0.009 + 0.002 03-07-94 0.015 + 01002 0.018 + 0.002 0.014 + 0.002 0.013 + 0.002 0.011 + 0.002 03-17-94 0.014 + 0 (002, 0.017 + 0.002 0.015 + 0.002 0. 017' 0.002 0.015 + 0.002 03-23-94 0.014 + 0, 002,' 0.017 + 0.002 0.015 + 0.002 0.014 + 0.002 0.014 + 0.002 03-31-94 0.013 0 J002j 0.016 + 0.002 0.015 + 0.002 0.014 + 0.002 0.011 + 0.002 Means: 0.011 + 0 001:, 0.013 + 0.001 0.011 + 0.001 0 '12 + 0.001 0.011 + 0.001

• NRC split samples.

(A) At the beginning of this sampling interval, the equipment for site T72lwas moved from a location inside a security fence to a more accessible location just outside the fence in the same general direction from and slightly closer to the nuclear generating units.

Supplementary air sampl e site T52 is now being temporarily used as a substitu te for Technical Specifications site T57 which was destroyed by Hurricane Andrew.

II 2.b AIR PARTICULATES GAMMA SCANS OF UARTERLY COMPOSITES I

C i m3 First Qu arter, 1994 Sample Site Be- K-40 Cs-134 Cs-137 Pb-210 A T51 0.1289 0.0112 <0.0151 <0.0005 <0. 0007 0.0105 + 0.0022 T52 0. 1520 +. 0.0114 <0.0151 <0.0008 <0. 0007 0.0095 + 0.0026 T58 0.1323 + 0.0100 <0.0159 <0.0006 <0. 0008 0.0089 + 0.0025 T64 0.1551 + 0.0103 <0.0162 <0.0009 , <0.0008 0.013'7 + 0.0032 t

T72 0.1344 0. 0096 <0.0155 <0.0009 t <0.0008 0.0153 + 0.0027 (A) Pb-210 is a radionuclide which is often naturally present in air filter samples. Our gamma analyses in the past have often indicated the qualitative presence of Pb-210, but these results, were not reported because accurate measurement was not possible due to the low-energy cutoff of the detector used. With the recent acquisition of a new detector, we are now better able to quantify the measurement of Pb-210, and, beginning with th'is group of samples, ;we will be reporting the Pb-210 'results.

air

)

Supplementary sample site T52 is now being temporarily used as a substitu te for Technical Specifications site T57j, II which was destroyed by Hurricane Andrew.

3.a SURFACE WATER Ci l t

J

~ 'I Sample Collection Zr-95 Ba-140 Site Date H-3 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 T42 01-14-94 02-07-94

<130 288 + 46 <5 <5 <11 <6 <7 (A)

<8 <7 5 l J

<5 (B)

<6

<131 235 + 37 <5 <4 <9 <5 <9 <7 <6 ,

<5 <4 <7 03-24-94 112 + 43 232 + 31 <3 <4 <6 <5 <8 <6 <5 ~

<4 <4 <6 T67 01-14-94 <130 332 + 50 <5 <4 <9 <7 <10 <7 <8 <5 <5 <8 02-07-94 <131 275 + 40 <3 <4 I

<12 <5 <14 <6 <8, <5 <4 <8 03-24-94 <134 338 + 38 <4 <3 <8 <5 <7 <7 <6 <4 <4 <7 T81 01-14-94 131 + 42 240 + 38 <5 <4 <10 <6 <13 <7 <7 <5 <4 <5 J

02-04-94 238 + 44 342 + 41 <5 <4 <9 <5 <12 <8 -<6 <5 <4 <8

~ I 03-22-94 203 + 44 .295 + 31 <3 <4 <8 <5 <9 <7 <6 <4 <4 <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.

IJ I

~ '

I 3.b SEDIMENT Ci k dr wei ht Sample Collection I Site Date 'Be-7 K-4 0 Co-58 Co-60 Cs-134 Cs-137 Others J

T42 01-05-94 224 + (64 490 + 103 <15 <17 <17 <15 Ra-226: 778 + 29 U-235: 97 + 42 T67 01-07-94 <90 319 + 63 <8 <7 <10 <7 Ra-226: 108 + 10 T81 01-05-94 109 + 43 321 + 67 .<11 <11 <14 Ra-226: 386 + 18 Th-232 73 + 21 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 Collection attempts could not be scheduled in the first quarter. Efforts continue.

T81 03-02-94 1236 + 198 <'25 <25 <57 <24 <53 <29 <29 206 + 31 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 Collection attempts could not be scheduled in the first quarter. Efforts continue.

T81 First quarter collection attempts were not successful. Efforts continue.

ND  : Non-detectable.

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 01-14-94. 1616 + 82 4321 + 172 <16 <10 39 + 6 02-07-94 1617 + 88 2747 + 144 <14 <11 89 + 8 03-24-94 2153 + 90 4355 + 157 <14 <11 171 + 11 T41 01-14-94 1766 + 83 5049 + 189 - <15 <14 39 + 8 02-07-94 1440 + 83 3604 + 183 <15 <10 120 + 10 03-24-94 1698 + 74 4730 + 152 <13 <10 <13 T67 01-14-94 . 814 + 63 5711 + 200 <16 <11 <12 02-07-94 912 + 67 3566 + 168 <12 <9 <8 03-24-94 '70' 55= '617 + '122 <10 =

<8 30 + 6

RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE Second Quarter, 1994*

Office of Radiation Control Florida Department of Health and Rehabilitative Services

TURKEY POINT SITE Technical Specifications Sampling Second Quarter, 1994 Collection Locations Number of Sam le T e Fre uenc

1. Direct Radiation Quarterly 22 20

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: 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 954 confidence) for the true activity in the sample.

DIRECT RADIATION TLDs micro-R hour Sample Deployment 03-22-94 Site Collection 06-08-94 N-2 5.76 + 0. 18 N-7 4.97 + 0.16 N-10 5. 10, + 0. 17 NNW-2 4-.48 + 0.18 NNW-10 5.78 + 0.17 NW-1 4.94 '+ 0.20 NW-5 (A)

NW-10 7.68 + 0.23 WNW-10 (A)

W-1 6.59 + 0.20 W-5 4.51 + 0.14 W-9 4.80 + 0.15 WSW-8 5.12 + 0.16 SW-1 4.91 + 0.15 SW-8 5.06 + 0.15 SSW-5 4.73 + 0.14 SSW-10 4.85 + 0.15 S-5 4.75 + 0.15 S-10 6.35 + 0.17

'I SSE-1 4.72 + 0.14 SSE-10 5.66 + 0.18 NNE-22 6.05 + 0.19 (A) The dosimeters for sites NW-5 and WNW-10 were missing when collection was attempted.

2.a IODINE-131 IN WEEKLY AIR FILTERS Ci m3 Sam le Site Collection Date TSl T52 T58 T64 T72 r

04-07-94 <0. 02 <0.02 <0.02 <0.02 <0.02 04-14-94 <0. 01 <0. 01 <0.01 <0.01 <0.01 04-21-94 <0.02 <0.02 <0.02 <0.02 <0.02 04-27-94 <0.02 <0.02 <0.02 <0.02 <0.02 05-03-94 <0.02 <0. 02 <0.02 <0.02 <0.02 05-10-94 <0.01 <0. 01 <0.01 <0.01 <0.01 05-18-94 <0.02 <0.02 <0.02 <0.02 <0.02 05-25-94 <0.02 <0.01 <0.01 <0.02 <0.01 05-31-94 <0.02 <0.02 <0.02 <0.02 <0.02 06-07-94 <0.02 <0.02 <0.02 <0.02 <0.02 06-14-94 <0.02 <0.02 <0.02 <0.02 <0.02 06-20-94 <0.02 <0.02 <0.02 <0.02 <0.02 06-28-94 <0.02 <0.02 <0.02 <0.02 <0.02 Supplementary air sample site T52 is now being temporarily used as a substitute for Technical Specifications site T57, which was destroyed by Hurricane Andrew.

2.b AIR PARTICULATES GROSS BETA Ci m3 Sam le Site Collection Date T51 T52 T58 T64 T72 04-07-94 0. 019 + 0. 002 0.022 + 0.002 0.021 + 0.002 0. 018 + 0. 002 0.018 + 0.002 04-14-94 0. 013 + 0.002 0.021 + 0.002 0.017 + 0.002 0. 015 + 0. 002 0.016 + 0.002 04-21-94 0. 008 + 0.002 0.014 + 0.002 0.007 + 0.002 0.009 + 0.002 0-007 + 0.002 04-27-94 0. 007 + 0.002 0.006 + 0.002 0.007 + 0.002 0.008 + 0.002 0.006 + 0.002 05-03-94 0. 012 + 0.002 0.011 + 0.002 *0.011 + 0.002 0.009 + 0.002 0. 011 + 0.002 05-10-94 0 020 + 0.002

~ 0. 017 + 0.002 *0.015 + 0.002 0.016 + 0.002 0.019 + 0. 002 05-18-94 0. 018 + 0.002 0.019 + 0.002 *0.018 + 0.002 0..019 + 0.002 0.019 + 0.002 05-25-94 0. 007 + 0.002 0.015 + 0.002 P'0.013 + 0.002 0.006 + 0.002 0.011 + 0.002 05-31-94 (AO. 009 .+ 0.002 0.020 + 0.003 0.014 + 0.002 0.015 + 0.002 0.013 + 0.002 06-07-94 0. 012 + 0.002 0.011 + 0.002 0.012 + 0.002 0.012 + 0.002 0.014 + 0.002 06-14-94 0. 012 + 0;002 0.012 + 0.002 0.011 + 0.002 0.016 + 0.002 0.019 + 0.002 06-20-94 0. 008 + 0.002 0.006 + 0.002 0.012 + 0.002 0.010 + 0.002 0.007 + 0.002 06-28-94 0. 009 + 0.002 0.014 + 0.002 0.009 + 0.002 0.015 + 0.002 0.016 + 0.002 Means: 0.012 + 0.001 0.014 + 0.001 0.013 + 0.001 0.013 + 0.001 0.014 + 0.001

• NRC split samples.

(A) The holder with this particulate filter was found disconnected from the air hose. The surface of the filter also appeared to have been struck by raindrops. The darkness of the dust deposits on this filter was comparable to other sites. It appears that some-one had removed the filter holder during the latter part of this sampling interval and that they had attempted to replace it, but they were not able to unlock the cabinet to reconnect the air hose.

Supplementary air sample site T52 is now being temporarily used as a substitute for Technical Specifications site T57, which was destroyed by Hurricane Andrew.

4

-2. b AIR PARTICULATES GAMMA SCANS OF UARTERLY COMPOSITES Ci m3 Second Quarter, 1994 Sample Site Be-7 K-40 Cs-134 Cs-137 Pb-210 T51 0.1290 + 0.0099 <0.0154 <0.0009 <0.0007 0.0159 + 0.0028 T52 0.1071 + 0.0094 <0.0159 <0.0008 <0.0007 0.0089 + 0.0023 T58 0.1433 + 0.0100 <0.0177 <0.0009 <0.0005 0.0159 + 0.0042 T64 0.1343 + 0.0102 <0.0192 <0.0005 <0.0008 0.0135 + 0.0022 T72 0.1234 + 0.0100 <0.0198 <0.0009 <0.0007 0.0134 + 0.0035 Supplementary air sample site T52 is now being temporarily used as a substitute for Technical Specifications site T57, which was destroyed by Hurricane Andrew.

3.a SURFACE WATER Ci l Sample Collection Zr-95 Ba-140 Site Date H-3 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 04-22-94 <145 334 + 36 <4 <4 <8 <4 <9 <6 <6 <5 <4 <3 05-12-94 <.138 372 + 35 <4 <4 <8 <4 <8 <7 <12 <3 <5 <6 06-17-94 <142 350 + 33 <4 <4 <8 <4 <11 <6 <9 <5 <4 <4 T67 04-25-94 <130 236 + 30 <3 <3 <7 <3 <8 <6 <5 <5 <4 <3 05-12-94 <138 315 + 34 <4 <4 <9 <4 <7 <7 <11 <5 <4 06-16-94 <142 237 + 30 <4 <4 <8 <3 <7 <7 <7 <4 <3 <6 T81 04-22-94 241 + 44 312 + 33 <4 <4 <5 <4 <7 <6 <6 <5 <4 <5 05-12-94 124 + 44 399 + 36 <4 <3 <11 <5 <9 <8 <11 <4 <4 <7 06-17-94 270 + 48 312 + 32 <3 <4 <8 <4 <9 <6 <8 <3 <4 <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. 1 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 06-16-94 904 + 163 <22 <14 <43 <21 <48 <18 <22 ND 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 05-24-94 2819 + 334 <36 <40 <101 <46 <93 <40 <38 ND ND T81 06-22-94 2464 + 263 <24 <22 <53 <22 <59 <28 <26 ND ND 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 04-25-94 1656 + 77 5148 + 169 <10 <11 30+5

• 05-13-94 1199 + 75 4673 + 159 <25 <10 39+ 6 06-16-94 1755 + 75 2495 + 113 <17 <8 83+ 7 T41 04-25-94 1025 + 56 4119 + 140 <10 <9 78+8 05-13-94 1489 + 84 4184 + 148 <24 <11 69+8 06-16-94 1503 + 83 3510 + 138 <19 <11 166 + 9 T67 04-25-94 843 + 51 3031 + 116 <8 . <7 <10 05-13-94 1089 + 70 4483 + 157 <23 <11 <14 06-16-94 749 + 65 4651 + 155 <19 <11 <11

• NRC split sample. ND Non-detectable.

RADXOLOGICAL SURVEILLANCE OF FLORXDA POWER AND LXGHT COMPANY 'S TURKEY POINT SITE Third Quarter, 1994 Office of Radiation Control Florida Department of Health and Rehabilitative Services

TURKEY POINT SITE Technical Specifications Sampling Third Quarter, 1994 Collection Locations Number of Sam le T e Fre uenc

1. Direct Radiation Quarterly 22 19

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.1 Broadleaf Monthly Vegetation Total: 174

• 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 06-08-94 Site Collection 09-22-94 N-2 5.55 + 0.16 N-7 4.78 + 0.14 N-10 4.80 + 0.13 NNW-2 4.27 + 0.13 NNW-10 5.69 + 0.15 NW-1 4.50 + 0.13 NW-5 4.60 + 0.13 NW-10 (A)

WNW-10 (A)

W-1 5.67 + 0.15 W-5 4.23 + 0.12 W-9 4.51 + 0.13 WSW-8 4.58 + 0.13 SW-1 4.76 + 0.14 SW-8 4.78 + 0.13 SSW-5 4.54 + 0.14 SSW-10 4.82 + 0.14 S-5 4.47 + 0.13 S-10 (B)

SSE-1 4.77 + 0.13 SSE-10 5.79 + 0.16 NNE-22 6.05 + 0.16 (A) The dosimeters for sites NW-10 and WNW-10 vere missing when collection was attempted.

(B) The dosimeter from site S-10 was found at a boat ramp in the Card Sound area on 08-05-94. Xt was returned to site S-10 that same day. This dosimeter was missing again when collection was attempted on 09-22-94.

2.a IODINE-131 IN WEEKLY AIR FILTERS Ci m3 Sam le Site Collection Date T51 T57 T58 T64 T72 07-06-94 <0. 02 <0. 02 <0.02 <0.01 <0.02 07-11-94 <0.02 <0. 03 <0.03 <0.03 <0.02 07-19-94 <0.02 <0. 02 <0.02 <0.02 <0.02 07-25-94 <0.03 <0.03 <0. 06 (A) <0.03 <0.03(C) 08-03-94 <0.01 <0. 01 <0.02(B) <0.01 <0.01 08-10-94 <0.02 <0. 02 (D) <0.02 <0.02 <0.02 08-16-94 <0.02 <0. 02 <0.02 <0.02 <0.02 08-22-94 <0.03 <0. 04 <0.03 <0.03 <0.03 08-30-94 <0.02 <0. 02 <0.02 <0.02 <0. 03 (E) 09-07-94 <0.01 <0. 02 <0.02 <0.01 <0.01 09-13-94 <0.02 <0. 02 <0.02 <0.02 <0.02 09-19-94 <0.02 <0.02 <0.02 <0.02 <0.02 09-27-94 <0.01 <0.01 <0.01 <0.01 <0.01 (A) Electrical power was out at the end of this sample. The equipment is estimated to have run for 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> out of the 123 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 171 hours0.00198 days <br />0.0475 hours <br />2.827381e-4 weeks <br />6.50655e-5 months <br /> out of the 190 total hours for this sampl'ing interval.

(C) We believe a power outage occurred during this sample. The equipment is estimated to have run for 127 hours out of the 143 total hours for this sampling interval.

(D) We believe a power outage occurred during this sample. The equipment is estimated to have run for 152 hours0.00176 days <br />0.0422 hours <br />2.513228e-4 weeks <br />5.7836e-5 months <br /> out of the 171 total hours for this sampling interval.

(E) We believe a power outage occurred during this sample. The equipment is estimated to have run for 129 hours0.00149 days <br />0.0358 hours <br />2.132936e-4 weeks <br />4.90845e-5 months <br /> out of the 171 total hours for this sampling interval.

2.b AIR PARTICULATES GROSS BETA Ci m3 Collection Sam le Site Date T51 T57 T58 T64 T72 I

07-06-94 0.014 + 0.002 0.012 0.002 0.011 + 0.002 0. 013 + 0. 002 0. 009 + 0 002

~

07-11-94 0.016 + 0.002 0.012 0.003 0.011 + 0.003 0. 006 + 0. 002 0.009 + 0.002 07-19-94 0.020 + 0.002 0.020 0.002 0.021 + 0.002 0. 022 + 0. 002 0.018 + 0.002 07-25-94 0.013 + 0.002 0.008 0.002 (A) <0.039 0.009 + 0.002 (C0.012 + 0.002 08-03-94 0.015 + 0.002 0.010 0. 002 (B0.009 + 0.002 0. 013 + 0.002 0. 012 + 0. 002 08-10-94 0.005 + 0.002 (D0.007 + 0- 002 *0.006 + 0.002 0. 005 + 0.002 0. 010 + 0. 002 08-16-94 0.006 + 0.002 0.006 + 0-002 *0.008 + 0.002 0.006 + 0.002 0. 009 + 0 002

~

08-,22-94 0.010 + 0.002 <0 .00 7 *0.008 + 0.002 0. 010 + 0.002 0. 009 + 0 002

~

08-30-94 0.008 + 0.002 0.007 + 0.001 *0.010 +'.002 0. 007 + 0.002 (EO. 007 + 0. 002 09-07-94 0.009 + 0.002 0.010 0-002 0.009 + 0.002 0.010 + 0.002 0. 011 + 0. 002 09-13-94 0-012 + 0.002 0.007 0.002 0.009 + 0.002 0.009 + 0.002 0. 011 + 0.002 09-19-94 0.016 + 0.002 (F0.008 0.002 0.014 + 0.002 0.012 + 0 '02 0. 016 + 0.002 09-27-94 0.009 + 0.002 0.008 0.001 0 '11 + 0.002 0.012 + 0.002 0. 010 + 0.002 Means: 0.012 + 0.001 0.010 0.001 0.011 + 0.001 0.010 + 0.001 0.011 + 0.001

• NRC split samples.

(A) Electrical power was out at the end of this sample. The equipment is estimated to have run for 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> out of the 123 total hours for this sampling interval.

Also, the specified sensitivity of 0.01 pCi/m3 was not achievable due to the small air volume for this sample.

(B) Electrical power was out at the start of this sample. The equipment is estimated to have run for 171 hours0.00198 days <br />0.0475 hours <br />2.827381e-4 weeks <br />6.50655e-5 months <br /> out of the 190 total hours for this sampling interval.

(C) We believe a power outage occurred during this sample. The equipment is estimated to have run for 127 hours0.00147 days <br />0.0353 hours <br />2.099868e-4 weeks <br />4.83235e-5 months <br /> out of the 143 total hours for this sampling interval.

(D) We believe a power outage occurred during this sample. The equipment is estimated to have run for 152 hours out of the 171 total hours for this. sampling interval.

(E) We believe a power outage occurred during this sample. The equipment is estimated to have run for 129 hours0.00149 days <br />0.0358 hours <br />2.132936e-4 weeks <br />4.90845e-5 months <br /> out of the 171 total hours for this sampling interval.

(F) Fold marks and small holes were found in this particulate filter upon collection.

We suspect that someone tampered with this filter during this sampling interval.

4

2.b AIR PARTICULATES GAMMA SCANS OF UARTERLY COMPOSITES Ci m3 Third Quarter, 1994 Sample Site Be-7 K-40 Cs-134 Cs-137 Pb-210 T51 0.0993 + 0.0085 <0.0151 <0.0009 <0.0007 0.0085 + 0.0016 T57 0.0840 + 0 '095 <0.0153 <0.0009 <0.0009 0.0065 + 0.0020 T58 0.1215 + 0.0096 <0.0216 <0.0009 <0.0010 0.0108 + 0.0021 T64 0.1071 + 0.0093 <0.0166 <0.0007 <0.0008 0.0077 + 0.0024 T72 0.1056 + 0.0103 <0.0150 <0.0009 <0.0005 0.0081 + 0.0020

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

T42 07-20-94 <138 365 + 35 <4 <4 <9 <6 <7 <8 <7 <4 <4 <4 08-17-94 <134 291 + 35 <3 <4 <9 <5 <10 <7 <6 <4 <4 <4 09-15-94 <138 239 + 31 <4 <5 <10 <5 <8 <7 <9 <5 <4 <6 T67 07-22-94 <138 242 + 37 <4 <3 <7 <5 <8 <8 <7 <3 <3 <4 08-18-94 <134 133 + 26 <3 <3 <8 <4 <8 ~ <7 <10 <4 <5 <8 09-16-94 <138 171 + 27 <3 <4 <7 <5 <8 <7 <9 <3 <4 <8 T81 07-21-94 189 + 45 335 + 30 <3 <4 <8 <4 <6 <7 <7 <4 <4 <5 08-17-94 299 + 46 231 + 36 <4 <4 <9 <5 <8 <6 <11 <3 <4 <5 09-15-94 261 + 47 262 + 35 <3 <3 <9 <5 <9 <7 <11 <4 <3 <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.

3.b SEDIMENT Ci k dr vei ht Sample Collection Site Date K-40 Co-58 Co-60 Cs-134 Cs-137 Ra-226 Th-232 T42 07-20-94 196 + 40 436 + 66 <12 <10 <11 <10 .655 + 22 ND T67 07-21-94 <75 425 + 45 <7 <7 <7 <8 111 + 19 40 + 11 T81 07-21-94 224 + 52 463 + 61 <9 <13 <12 <10 503 + 20 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 We vere not able to schedule attempts to collect this sample. Efforts continue.

T81 We were not able to schedule attempts to collect this sample. Efforts continue.

4.a.2 FISH Mixed S ecies Ci k vet vei 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 We were not able to schedule attempts to collect this sample. Efforts continue.

T81 We were not able to schedule attempts to collect this sample. Efforts continue.

ND Non-detectable.

I 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 Pb-210 T40 07-22-94 1499 + 66 2978 + 122 <14 <8 61+ 7 ND 08-18-94 2103 + 89 3549 + 135 <19 <11 56+7 ND 09-16-94 2444 + 86 3517 + 124 <22 <8 178 + 8 739 + 252 T41 07-22-94 1232 + 63 2956 + 119 <14 <10 187 + 9 ND 08-18-94 1640 + 78 4781 + 161 <24 <11 95 + 7 ND 09-16-94 1892 + 81 3083 + 126 <23 <9 236 + 10 ND T67 07-22-94 878 + 55 3812 + 127 <12 <8 <8 ND 08-18-94 881 + 63 4430 + 164 <20 ND 09-16-94 1036 + 67 4365 + 140 <20 <9 <8 ND ND Non-detectable.

RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE Fourth Quarter, 1994 Office of Radiation Control Florida Department of Health and Rehabilitative Services

TURKEY POINT SITE Technical Specifications Sampling Fourth Quarter, 1994 Collection Locations Number of Sam le T e Fre uenc

1. Direct Radiation Quarterly 22 20

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: 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 95% confidence) for the true activity in the sample.

DIRECT RADIAT10N TLDs micro-R hour Sample Deployment 09-22-94 Site Collection 12-07-94 N-2 5.58 + 0.17 N-7 5.18 + 0.18 N-10 4.86 + 0.16 NNW-2 4.66 + 0.16 NNW-10 5.77 + 0.18 NW-1 4.95 + 0.16 NW-5 (A)

NW-10

\

7.55 + 0.23 WNW-10 (A)

W-1 6.52 + 0.21 W-5 4.84 + 0.16 W-9 4.75 + '0.15 WSW-8 4.87 + 0.16 SW-1 4.87 + 0.17 SW-8 4.99 + 0.16 SSW-5 4.72 + 0.15 SSW-10 5.00 + 0.18 S-5 4.56 + 0. 15 S-10 5.57 + 0.17 SSE-1 4.82 + 0.17 SSE-10 5.85 + 0.18 NNE-22 6.05 + 0.21 (A) The dosimeters for sites NW-5 and WNW-10 were missing when collection was attempted.

2.a IOD1NE-131 IN WEEKLY AIR FILTERS Ci m3 Sam le Site Collection Date T51 T57 T58 T64 T72 10-04-94 <0.03 <0.03 <0. 03 <0. 03 <0.03 10-12-94 <0.02 <0.02 <0. 02 <0. 02 <0.02 10-18-94 <0.03 <0.04 <0.03 <0.03 <0.03 10-25-94 <0.02 '<0. 02 <0.02 <0.02 <0.02 11-01-94 <0.02 <0. 02 <0. 02 <0. 02 <0.02 11-08-94 <0.02 <0.02 <0.02 <0. 02 <0.02 11-16-94 <0.04 <0.04 <0.04 <0. 04 <0.04 11-22-94 ,<0. 02 <0.02 <0.02 <0.02 <0.02 11-28-94 <0. 03 <0.04 <0.03 <0.04 <0.03 12-06-94 <0.02 <0.02 <0.01 <0. 02 <0.02 12-13-94 <0.01 <0.01 <0.01 <0.01 <0.01(A) 12-21-94 <0.03 <0.03 <0.03 <0.03 <0.03 12-28-94 <0.02 <0.02 <0.02 <0.03 <0.02 (A) We believe a power outage occurred during collection of this sample. The .equipment is estimated to have run for 148 hours0.00171 days <br />0.0411 hours <br />2.44709e-4 weeks <br />5.6314e-5 months <br /> out of the 167 total hours for this sampling interval.

2.b AIR PARTICULATES GROSS BETA Ci m3 Collection Sam le Site Date T51 T57 T58 T64 T72 10-04-94 0. 008 + 0. 002 0.006 + 0.001 0.009 + 0.002 0.010 + 0.002 0.008 + 0.002 10-12-94 0. 009 + 0. 002 0.007 + 0.002 0.007 + 0.002 0.011 ~ 0.002 0.010 + 0.002 10-18-94 0.009 + 0.002 0.014 + 0.003 0.007 + 0.002 0.009 + 0.002 0.012 + 0.002 10-25-94 0.017 + 0.002 0.017 + 0.002 0.022 + 0.002 0.017 + 0.002 0.019 + 0.003 11-01-94 0.009 + 0.002 0.006 + 0.002 0.015 + 0. 002 0. 013 + 0. 002 0. 012 + 0.002 11-08-94 0.014 + 0.002 0.016 + 0.002 *0.014 + 0. 002 0.015 + 0. 002 0.013 + 0.002 11-16-94 <0.004 0.005 + 0.001 *0.006 + 0. 001 0.007 + 0.002 0.005 + 0.001 11-22-94 0.008 w 0.002 0.008 + 0.002 *0.005 + 0.002 0.008 + 0.002 0.006 + 0.002 11-28-94 0.014 + 0.002 0.012 + 0.002 *0.015 + 0.002 0.011 + 0.002 0.015 + 0.002 12-06.-94 0.006 + 0.002 0.003 + 0.001 0.004 + 0.001 0.005 + 0.001 0.005 + 0.001 12-13-94 0.007 + 0.002 0.008 + 0.002 0.013 + 0.002 0.011 + 0.002 (A0.005 + 0.002 12-21-94 0.010 + 0.002 0.009 + 0.002 0.012 + 0.002 0.013 + 0.002 0.010 + 0.002 12-28-94 0.015 + 0.002 0.013 + 0.002 0.016 + 0.002 0.015 + 0.002 '.015"+ 0.002 Means: 0.011 + 0.001 0.010 + 0.001 0.011 + 0.001 0.011 + 0.001 0.010 + 0.001

• NRC split samples.

(A) We believe a power outage occurred during collection of this sample. The equipment is estimated to have run for 148 hours0.00171 days <br />0.0411 hours <br />2.44709e-4 weeks <br />5.6314e-5 months <br /> out of the 167 total hours for this sampling interval.

2.b AIR PARTICULATES GAMMA SCANS OF UARTERLY COMPOSITES Ci m3 Fourth Quarter, 1994 Sample Site Be-7 K-40 Cs-134 Cs-137 Pb-210 T51 0.1140 + 0.0119 <0.0172 <0.0011 <0.0010 0. 0118 + 0. 0030 T57 0.0907 + 0.0092 <0.0167 <0.0009 <0.0008 0. 0118 + 0. 0028 T58 0.1294 + 0.0107 <0.0180 <0.0005 <0.0007 0.0115 + 0.0038 T64 0.1308 + 0.0122 <0.0147 <0.0008 <0.0007 0.0092 + 0.0030 T72 0.1087 + 0.0099 <0.0196 <0.0006 <0.0008 0.0115 + 0.0029

3.a SURFACE MATER Ci l Sample Collection Zr-95 ~

Ba-140 Site Date H-3 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 (A) (B) t T42 10-17-94 <134 172 + 27 <4 <4 <5 <4 <8 <6 <7 <4 <4 11-09-94 <137 177 + 24 <4 <4 <8 <4 <6 <6 410 <4 <4. <7 12-14-94 <136 135 + 26 <4 <4 <9 <4 <8 <7 <6 <4 <4 <5 T67 10-17-94 <134 141 + 25 <4 <4 <6 <3 <7. <7 <7 <4 <4 <4 11-09-94 <142 <63 <3 <3 <7 <4 <7 <7 <11 <5 <3 <5 12-15-94 <136 192 + 30 <4 <4 <8 <3 <7 <5 <6 <5 <4 <4 T81 10-17-94 101 + 43 280 + 17 <2 <2 <4 <2 <4 <3 <3 <2 <2 <3 11-07-94 <137 258 + 32 <3 <3 <8 <5 <6 <8 <13 <4 <4 <8 12-15-94 <136 252 + 35 <4 <4 <9 <5 <8 <7 <8 <4 <4 <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.1 CRUSTACEA Blue Crab Ci 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 I

T67 10-18-94 964 + 226 <28 <28 <70 <19 <64 <29 <28 ND ND T81 10-07-94 981 + 128 <17 <22 <53 <26 <46 <19 <28 ND 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 'a-228 T67 10-18-94 2371 + 209 <21 <22 <46 <22 <42 <23 <23 ND ND T81 11-07-94 2876 + 262 <23 <35 <51 <33 <66 <26 <28 ND ND 4.b.1 BROADLEAF VEGETATION Brazilian Pe er Ci k wet wei ht Sample Collection Site Date Be-7 K-40 I-131 Cs-134 Cs-137 Pb-210 T40 10-19-94 2084 + 83 2715 + 119 <11 <9 14+ 4 636 + 228

• 11-09-94 1107 + 80 2657 + 129 <42 <10 81+ 7 ND 12-15-94 2976 + 94 4909 + 161 <17 <12 40+ 6 ND T41 10-19-94 974 + 67 3936 + 136 <11 <9 177+ 9 ND 11-09-94 1329 +.81 3554 + 131 <47 <10 112 + 7 ND 12-15-94 2769 + 107 3336 + 125 <16 <10 147 + 8 ND T67 10-19-94 1455 + 34 3152 + 58 ,<5 <4 <5 307 + 126 11-09-94 637 + 64 4007 + 139 <45 <9 <8 ND 12-15-94 1501 + 77 3597 + 134 <15 <12 <10 ND

• NRC split sample. ND Non-detectable.

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 & 4 RESULTS FROM THE INTERLABORATORY COMPARISON PROGRAM 1994

FLORIDA DEPT. OF HRS - EPA INTERLABORATORY CROSS-CHECK PROGRAM DATA January through June, 1994 Media Nuclide Collection EPA Units Normal. Mean of N.D.K. Action Mon Day Yr Known Range Analyses Level WATER Alpha 01 28 94 15 pCi/L 0.591 16.33 0.46 WATER Beta 01 28 94 62 pCi/L 0.354 65.00 0.52 WATER Co-60 06 10 94 50 pCi/L 0.354 50.33 0.12 WATER Zn-65 06 10 94 134 pCi/L 0.091 145.00 1 47

~

WATER Ru-106 06 10 94 252 pCi/L 0.213 196.00 -3.88 1 WATER Ba-133 06 10 94 98 pCi/L 0.059 83.33 -2.54 WATER Cs-134 06 10 94 40 pCi/L 0.236 37.67 -0.81 WATER Cs-137 06 10 94 49 pCi/L 0.118 54.33 1.85 WATER H-3 03 04 94 4936 pCi/L 0.005 4957.67 0.08 WATER I-131 02 04 94 119 pCi/L 0.148 115.00 -0.58 WATER Sr-89 01 14 94 25 pCi/L 0.591 20.00 1 73

~

WATER Sr-90 01 14 94 15 pCi/L 0.354 11.67 -1.15 NOTES:

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.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.

ACTION LEVEL:

Cause: Problem with Ruthenium-106 standard.

Corrective Action: See attached letter from Dr. George Dilbeck.

,s(p S4r<

S'

~~ UNITED STATES ENVIRONMENTALPROTECTION AGENCY OFFICE OF RESEARCH AND DEVELOPMENT

~< okapi< ENVIRONMENTALMONITORING SYSTEMS LA8ORATORY LAS VEGAS P,O. 8OX 93478 LAS VEGAS. NEVADA 89193-3478 (702/798 2100- FTS 545.2100)

Dear Participant:

The Radiation Quality Assurance Program has been experiencing problems vith the Ruthenium-106 currently used in the Performance Evaluation (PE) Studies and in the Standards Distribution Program. If these problems can be satisfactorily resolved, this analyte vill once again be placed into this PE Study. If the problems cannot be resolved, the Ruthenium-106 vill be replaced.

Formal vritten notice vill be given to all participants that are enrolled in the Gamma in Vater PE Study before the Ruthenium-106 is reintroduced or replaced. At that time; nev calibration standards vill be available to all participants in the Gamma- in Mater PF Study.

Sincerely,

~ George Dilbeck Chemist Performance Evaluation Program Radioanalysis Branch (RSA-RADQA)

r FLORIDA DEPT. OF HRS EPA XNTERLABORATORY CROSS-CHECK PROGRAM DATA" July through December, 1994 Media Nuclide Collection EPA Units Normal. Mean of N.D.K. Action Mon Day Yr Known Range Analyses Level FIL'gER Alpha '08 26 94 35 pCi/F 0.000 37.00 0.38 FILTER Beta 08 26 94 56 pCi/F 0.000 61.00 0.87 FILTER Cs-137 08 26 94 15 pCi/F 0.000 16.00 0.35 FILTER Sr-90 08 26 94 20 pCi/F 0.118 17.33 -0.92 MILK I-131 09 30 94 75 pCi/L 0.148 73.33 -0.36 MILK Cs-137 09 30 94 59 pCi/L 0.118 62.67 1.27 MILK K 09 30 94 1715 mg/L 0 '20 1726.00 0;22 MILK Sr-89 09 30 94 25 pci/L 0.000 22.00 -1. 04 MILK Sr-90 09 30 94 15 pCi/L 0.000 15 00 F 0.00 WATER Alpha 07 22 94 32 pCi/L 0.517 45.00 2.81 WATER Alpha 10 28 94 57 pCi/L 0.253 61.67 0 '8 WATER Beta 07 22 94 10 pCi/L 0.000 15.00 1.73 WATER Beta 10 28 94 23 pCi/L 0.000 30.00 2.42 WATER Co-60 11 04 94 59 pCi/L 0.118 60.67 0.58 WATER Zn-65 11 04 94 100 pCi/L 0.236 108.33 1.44 HATER Ba-133 11 04 94 73 pCi/L 0.338 66.00 -1.73 WATER Cs-134 11 04 94 24 pci/L 0.236 23.00 -0.35 HATER Cs-137 11 04 94 49 pCi/L 0.118 53,67 1.62 WATER H-3 08 05 94 9951 pCi/L 0.149 9985.33 0.06 WATER I-131 10 07 94 79 pCi/L 0.222 77.33 -0.36 WATER Sr-89 07 15 94 30 pCi/L 0.591 30.67 0.23 WATER Sr-90 07 15 94 20 pCi/L 0.236 20.00 0.00 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.D.K.: Normalized deviation of the mean from the known value, as defined in EPA-600/4-81-004.

NDP: No data provided. No'ata 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.

I

'I