ML17353A648

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

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

Text

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

• Florida Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

1995 Annual Radiological Environmental Operating Rept for TPS units 3 6 4.

DISTRIBUTION CODE: IE25D COPIES RECEIVED:LTR 1 ENCL i SIZE:

TITLE: Environmental Monitoring Rept (per Tech Specs)

NOTES:

R ECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 3 3 PD2-1 PD 1 1 1 1 INTERNAL. 1 1 NRR/DRPM/PERB 1 1 RGN2 FILE 1 1 EXTERNAL: LITCO AKERSFD 1 1 NRC PDR 1 1 D

U E

N NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 10 gr l

~,

1'

NPR 83 Inaq L-96-094 10 CFR 550.36b U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:

Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 1995 Annual Radiological Environmental 0 eratin Re ort Attached is the 1995 Annual Radiological Environmental Operating Report for Turkey Point Units 3 and 4, as required by Technical Specification 6.9.1.3.

Should there be any questions, please contact us.

Very truly yours, R. J. Hovey Vice President Turkey Point Plant Attachment cc: S.'. Ebneter, Regional Administrator, Region IZ, USNRC T. P. Johnson, Senior Resident inspector, USNRC, Turkey Point Plant 9604260i9i 95i23i PDR ADOCK 05000250 R PDR an FPL Group company

1995 ANNUAL RADIOLOGICAL ENVIRONNENTAL OPERATING REPORT TURKEY POINT PLANT UNITS 3 & 4 LICENSE NOS. DPR-31, DPR-41 DOCKET NOS. 50-250, 50-251 Data submitted by: Florida DHRS Prepared by:

Reviewed by:

1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT - UNITS 3 Ec 4 TABLE OF CONTENTS DESCRIPTION PAGE Introduction Radiological Environmental Monitoring Program Discussion and Interpretation of Results Environmental Radiological Monitoring Program 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, 1995 Second Quarter, 1995 Third Quarter, 1995 Fourth Quarter, 1995 Results from the Interlaboratory Comparison ATTACHMENT C Program, 1995

1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT - UNITS 3 Ec 4 EXECUTIVE

SUMMARY

The data obtained through the Turkey Point Radiological Environmental Monitoring Program verifies that the levels of radiation and concentrations of radioactive materials in environmental samples are not increasing. These measurements verify that the dose or dose commitment to members of the public, due to operation of Turkey Point Units 3 6 4, during the surveillance year, is well within the limits established by 10 CFR 50, Appendix I. The sampling period was from January 1, 1995 to December 31, 1995.

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

1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT - UNITS 3 & 4 INTRODUCTION This report is submitted pursuant to Specification 6.9 of Turkey Point Units 3 & 4 Technical Specifications. The Annual Radiological Environmental Operating Report provides information, summaries and analytical results pertaining to the Radiological Environmental Monitoring Program for the calendar year indicated.

This report covers surveillance activities meeting the requirements of Unit 3 and Unit 4 Technical Specifications.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM A. ~Pur use The purpose of the Radiological Environmental Monitoring Program is to provide representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of members of the public resulting from station operation. The Radiological Environmental Monitoring Program also supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways.

B. Pro ram Descri tion The Radiological Environmental Monitoring Program (REMP) for the Turkey Point Plant is conducted pursuant to Technical Specifications 3/4.12 of Turkey Point Unit 3 E 4 Technical Specifications.

1. Sample Locations, Types and Frequencies:

a. Direct radiation gamma exposure rate is monitored continuously at 21 locations by thermoluminescent dosimeters (TLDs). TLDs are collected and analyzed quarterly.

b. Airborne radioiodine and particulate samplers are operated continuously at five locations. Samples are collected and analyzed weekly. Analyses include Iodine-131, gross beta, and gamma isotopic measurements.

0 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT - UNITS 3 8c 4

c. Surface water samples are collected from three locations. Samples are collected and analyzed monthly. Analyses include gamma isotopic and tritium measurements.

d. Shoreline sediment samples are collected from three locations coinciding with the locations for surface water samples. Samples are collected and analyzed semi-annually. Sediment samples are analyzed by gamma isotopic measurements.

e. Fish and invertebrate samples are collected from two locations coinciding with two of the locations for surface water samples. Samples are collected and analyzed semi-annually. Fish and invertebrate samples are analyzed by gamma isotopic measurements.

f. Broad leaf vegetation samplescollected are collected from three locations. Samples are and analyzed monthly. Broad leaf vegetation samples are analyzed by gamma isotopic measurements.

Attachment A provides specific information pertaining to sample locations, types and frequencies.

2. Analytical Responsibility:

Radiological environmental monitoring for the Turkey Point Plant is conducted by the State of Florida, Department of Health and Rehabilitative Services (HRS).

Samples are collected and analyzed by HRS personnel.

Samples are analyzed at the HRS Environmental Radiation Control Laboratory in Orlando, Florida.

CD Anal tical Results Table 1, Environmental Radicle ical Monitorin Procrram Annual ~Summar provides a summary for all specified samples collected during the referenced surveillance period.

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

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

1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT - UNITS 3 & 4 D. Land Use Census A land use census out to a distance of 5 miles radius from the Turkey Point Plant is conducted annually to determine the location of the nearest milk animal, residence, and garden producing broad leaf vegetation, in each of the sixteen meteorological sectors. A summary of the land use census for the surveillance year is provided in Table 2, Land Use Census

~Summaz No locations yielding a calculated dose or dose commitment greater than the values currently being calculated were identified by the land use census.

No locations yielding a calculated dose or dose commitment (via the same exposure pathway) 20% greater than locations currently being sampled in the radiological environmental monitoring program were identified by the land use census.

E. Interlaborator Com arison Pro ram The State of Florida HRS Environmental Radiation Control Laboratory participates in the Environmental Radioactivity Laboratory Intercomparison Studies Program conducted by the Environmental Protection Agency. Results from the Interlaboratory Comparison Program are provided in Attachment C.

III. DISCUSSION AND INTERPRETATION OF RESULTS A. Re ortin of Results The Annual Radiological Environmental Operating Report contains the summaries, interpretations and information required by the Turkey Point Units 3 6, 4 Technical Specifications. Table 1 provides' summary of the measurements made for the nuclides required by Technical Specifications, Table 3.12-2, for all samples specified by Table 3.12-1. In addition, summaries are provided for other nuclides identified in the specified samples, including those not related to station operation. These include nuclides such as K-40, Th-232, Ra-226, and Be-7 which are common in the Florida environment.

1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT - UNITS 3 & 4 B. Inter retation of Results

1. Direct Radiation:

The results of direct radiation monitoring are consistent with past measurements for the specified locations. The exposure rate data show no indication of any trends attributed to effluents from the plant. The measured exposure rates are consistent with exposure rates that were observed during the preoperational surveillance program. Direct radiation monitoring results are summarized in Table 1.

2. Air Particulates/Radioiodine:

Results of gross beta measurement are consistent with past measurements. No radioiodine was detected. The only identified isotopes are cosmic-ray produced Be-7 and naturally occuring K-40 and Pb-210 at levels consistent with past measurements.

3. Waterborne, Surface Water:

The results of radioactivity measurements in surface water samples are consistent with past measurements.

Tritium was reported as present in the surface water samples collected from site T-81. These results are consistent with the known subsurface interchange that occurs between the closed cooling canal and its surrounding waters, and the pressure gradients caused by the flow of aquifer subsurface waters in South Florida.

The highest reported tritium is less than 2% of the reporting value specified by Technical Specifications, Table 3.12-2.

4. Waterborne, Sediment:

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

5. Waterborne, Food Products:

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

1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT - UNITS 3 Sc 4

6. Broad Leaf Vegetation:

The results of radioactivity measurements are consistent with past measurements. Cs-137 was detected, as in the past, in samples collected from the indicator locations.

The maximum value is about 35% of the Table 3.12-2 reporting level, the average value is about 7% of the reporting level. No other fission products were detected.

C. Conclusions The data obtained through the Turkey Point Plant Radiological Environmental Monitoring Program verify that the levels of radiation and concentrations of radioactive materials in environmental samples, representing the highest potential exposure pathways to members of the public, are not being increased.

Additionally, supplemental to the Technical Specifications, sampling of the direct exposure, inhalation, and ingestion pathways, performed by HRS, does not show adverse trends in levels of radiation and radioactive materials in unrestricted areas. The measurements verify that the dose or dose commitment to members of the public, due to operation of Turkey Point Units 3 8 4, during the surveillance year, are" well within "as low as reasonably achievable (ALMS) criteria established by 10 CFR 50, Appendix X.

Je 0

0

TABL 1 Pag 1 of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3 6 4 , Docket No(s) . 50-250 & 50-251 Location of Facility Dade Florida , Reporting Period Janua 1 - December 31 1995 (County, State)

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

Locations Mean (f)

Name'ean Distance Annual Mean 6

f Control Locations Mean (f) h Performed Range Direction Range Range Exposure 5.27 (80/80) NW-10 7. 62 (4/4) 5. 78 (4/4)

Rate, 84 4.37 - 8.16 10 mi., NW 7.27 8.16 5.14 - 6.04 Number of Nonroutine Reported Measurements = 0

TAB%1 Pag 2 of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3 & 4 , Docket No(s). 50-250 k 50-251 Location of Facility Dade Florida , Reporting Period Januar 1 - December 31 1995 (County, State)

PATHWAY: AIRBORNE SAMPLES COLLECTED: RADIOIODINE AND PARTICULATES UNITS:

pCi/m'ype Location with Highest Limit All Indicator Total and Number of Analyses Tower of Locations Mean (f )

Name'ean Distance Annual E

Mean f b Control Locations Mean (f)b Detection'LLD)

Performed Range Direction Range Range 131I 260 0.024 <MDA <MDA Gross Beta, 259 0.0025 0.012 (201/207) T-72 0.012 (51/52) 0.013 (52/52) 0.003 0.024 <1 mi., WSW 0.003 - 0.024 0.004 0.025 Composite Gamma Isotopic, 20

'Be 0.0052 0 '256 (16/16) T-58 0.1317 (4/4) 0. 1303 (4/4) 0.0904 0.1467 1 mi., NW 0 '99 0.1455 0.1043 0.1446 210pb 0.0116 (15/16) T-72 0. 0118 (4/4) 0. 0135 (4/4) 0.0098 0.0135 <1 mile, WSW 0.0105 0.0133 0.0116 0.0159 134Cs 0.00069 <MDA <MDA 137CS 0.00066 <MDA <MDA Number of Nonroutine Reported Measurements = 0

4 TAB%1 Pag 3 of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3 & 4 , Docket No(s). 50-250 & 50-251 Location of Facility Dade Florida , Reporting Period Janua 1 - December 31 1995 (County, State)

PATHWAY: WATERBORNE SAMPLES COLLECTED: SURFACE WATER UNITS: pCi/L 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)b Performed Range Direction Range Range Tritium, 36 230 144 (10/24) T-81 144 (10/12) <MDA 119 345 6 mi., S 119 345 Gamma Isotopic, 36 60 294 (24/24) T-81 246 (12/12) 181 (11/12) 40'Mn 86 347 6 mi., S 86 347 94 249

<MDA <MDA "Fe <MDA <MDA 58Co <MDA <MDA 60Co <MDA <MDA 6Szn <MDA <MDA ssZr-Nb <MDA <MDA 131 I <MDA <MDA 134CS <MDA <MDA 137 <MDA Cs <MDA 140B L <MDA <MDA Number of Nonroutine Reported Measurements = 0

0 0

TAB% 1 Pag 4 of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3 & 4 , Docket No(s). 50-250 E 50-251 Location of Facility Dade Florida , Reporting Period Janua 1 - December 31 1995 (County, State)

PATHWAY: WATERBORNE SAMPLES COLLECTED: SHORELINE SEDIMENT UNITS: pCi/kg, DRY Location with Highest Type and To'tal Number of Analyses Lower of Limit Detection'LLD)

AllLocations Indicator Mean (f)

Name'ean Dz.stance Annual Mean f Control Locations Mean (f)~

Performed Range Direction Range Range Gamma Isotopic, 6

'Be 100 408 (2/4) T-42 438 (1/2) 142 (1/2) 378 438 <1 mi., ENE 40K 140 369 (4/4) T-42 392 (2/2) 246 (2/2) 305 431 <1 mi., ENE 354 431 243 249 52 <MDA 55 (1/2) 226Ra 809 (4/4) T-42 860 (2/2) 110 (1/2) 645 965 <1 mi., ENE 754-965 238U 638 (1/4) T-42 638 (1/2) <MDA

<1 mi., ENE "Co <MDA <MDA 60Co 12 <MDA <MDA-n4Cs <MDA <MDA 137CS 12 <MDA <MDA Number of Nonroutine Reported Measurements = 0

TAB% 1 Pag 5 of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3 &. 4 , Docket No(s). 50-250 & 50-251 Location of Facility Dade Florida , Reporting Period Janua 1 - December 31 1995 (County, State)

PATHWAY: INGESTION SAMPLES COLLECTED: CRUSTACEA UNITS: pCi/kg, WET Location with Highest Type and To'tal Number of Analyses Lower of Limit Detection'LLD)

All Indicator Locations Mean (f)

Name'ean Da.stance Annual Mean f b Control Locations Mean (f)b Performed Range Direction Range Range Gamma Isotopic, 4 "K 130 1850 (2/2) T-81 1850 (2/2) 1552 (2/2) 1798 1901 6 mi., S 1798 1901 1317 - 1787 226Ra 20 641 (2/2) T-81 641 (2/2) <MDA 436 846 6 mi., S 436 846 "Mn <MDA <MDA "Fe 16 <MDA <MDA "Co <MDA <MDA 60Co 19 <MDA <MDA Zn 17 <MDA <MDA 134Cs <MDA <MDA l37Cs <MDA <MDA Number of Nonroutine Reported Measurements = 0

TAB 1 Pag 6 of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3 8 4 , Docket No(s). 50-250 E 50-251 Location of Facility Dade Florida , Reporting Period Janua 1 - December 31 1995 (County, State)

PATHWAY: INGESTION SAMPLES COLLECTED: FISH UNITS: pCi/kg, WET Location with Highest Type and To'tal Number of Analyses Lower of Limit Detection'LLD)

All Indicator Locations Mean (f)

Name'ean Dz.stance Annual Mean fb Control Locations Mean (f)D Performed Range Direction Range Range Gamma Isotopic, 4 40K 130 2409 (2/2) T-81 2409 (2/2) 2590 (2/2) 2198 2620 6 mi., S 2198 2620 2309 2870 "Mn <MDA <MDA "Fe 16 <MDA <MDA 58Co <MDA <MDA 60Co 10 <MDA <MDA Zn <MDA <MDA 134 CS <MDA <MDA 137CS <MDA <MDA Number of Nonroutine Reported Measurements = 0

tr

'0

0'AB%Name 1

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

of Facility Turke Point Units 3 &. 4 , Docket No(s).

Location of Facility Dade Florida , Reporting Period Janua 1 50-250 & 50-251

- December 31 1995 Pag 7 of 8 (County, State)

PATHWAY: INGESTION SAMPLES COLLECTED: BROAD LEAF VEGETATION UNITS: pCi/kg, WET Location with Highest Type and Total Number of Analyses Lower of Limit Detection'LLD)

All Indicator Locations Mean (f)

Name'ean Distance Annual E

Mean f Control Locations Mean (f)~

Performed Range Direction Range Range Gamma Isotopic, 36

'Be 71 2105 (24/24) T-40 2114 (12/12) 1235 (12/12) 688 3635 3 mi., W 1565 3408 699 1779 40K 100 4146 (24/24) T-41 4941 (12/12) 3943 (12/12) 2341 6175 2 mi., W/NW 3576 6175 3143 5511 137CS 74 (23/24) T-40 91 (11/12) <MDA 15 349 3 mi., W '15 349 210pb 827 (7/24) T-40 961 (3/12) 724 (1/12) 574 1141 3 mi., W 715 1141 131I <MDA <MDA 134 <MDA Cs <MDA Number of Nonroutine Reported Measurements = 0

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

SUMMARY

Name of Facility Turke Point Units 3 &. 4 , Docket No(s). 50-250 & 50-251 Location of Facility Dade Florida , Reporting Period Janua 1 - December 31 1995 (County, State)

NOTES

a. The LLD is an "a priori" lower limit of detection which establishes the smallest concentration of radioactive material95';in a sample that will ~ield a net count above system backqround that will be detected with probability with on y 5'-. probability of falsely conclucling that a blank observation represents a real signal.

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

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.

1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 & 4 TABLE 1A Page 1 of 2 DEVIATIONS/MISSING DATA A) Pathway: Direct Exposure - TLDs Location Quarter & Date (Sector, Dist. Miles) of Missing Data SW-1 1, 12/7/94 to 3/15/95 SW-8 1, 12/7/94 to 3/15/95 W-5 3, 6/7/95 to 9/13/95 SSW-10 4, 9/13/95 to 12/13/95 Deviation: Failure to provide continuous monitoring.

Description TLDs were missing when collection was attempted.

of Problem:

Corrective Replaced TLDs.

Action:

B) Pathway: Airborne - Radioiodines & particulates, weekly sampling.

Location Sampling Period 4 Typ Sample T-51 2 mi., NNW 3/21/95 to 3/28/95 97'o T-57 4 mi., NW 3/21/95 to 3/28/95 90%

T-57 4 mi., NW 12/7/95 to 12/12/95 96%

T-72 <1 mi., WSW 8/15/95 to 8/23/95 89%

T-72 <1 mi., WSW 8/23/95 to 8/29/95 96%

Deviation: Failure to provide continuous monitoring.

Description Suspected power interruptions during o f 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.

1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 & 4 TABLE 1A Page 2 of 2 DEVIATIONS/MISSING DATA C) Pathway: Airborne Radioiodines E Particulates, weekly sampling Location: T-57, 4 miles NW Dates: 11/27/95 to 12/7/95 Deviation: Failure to provide continuous monitoring.

Description Sampling station destroyed by abandoned car that of Problem: was set on fire. Station destroyed about 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> into sampling period.

Corrective Sampling, station replaced and power restored.

Action:

1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Ec 4 TABLE 1B ANALYSES WITH LLDs ABOVE TABLE 4.12-1 DETECTION CAPABILITIES 1/1/95 12/31/95 The values specified in Table 4.12-1, Detection Capabilities, were achieved for all samples.

1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Ec 4 TABLE 2 LAND USE CENSUS Distance to Nearest a b 6/95 Milk (c) 6/95 6/95 Sector Animal Residence Garden (d)

N L (e) 2.j./350 (g) 0 (f) 0 0 NE 0 0 ENE ESE 0 0 0 SSE 0 L

SSW WSW L L 3.6/302 (11) 4. 3/303 L (g) 3 . 6/308 4.7/328 4. 0/328

1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Sc 4 TABLE 2 LAND USE CENSUS NOTES All categories surveyed out to 5 miles radius from the Turkey Point Plant.

The following format is used to denote the location:

distance (miles) /bearing (degrees)

For example, a residence located in the north sector at a distance of 2.1 miles bearing 350 degrees is recorded as 2.1/350.

Potential milk animal locations.

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

L denotes that the sector area is predominantly a land area unoccupied by the category type.

0 denotes that the sector area is predominantly an ocean area.

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

Sector Distance Descri tion N 1.8/349 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 This house has been converted into a construction office

lf 0

1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 & 4 ATTACHMENT A KEY TO SAMPLE LOCATIONS

1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 5: 4

"~ N-2 I Convoy Point 4NNW-2 " M@KPAYm =+ Pl%

I OUght OI7bClCOh

'C:

V J

C B

I I

S C

=e-4" A Y

N E

-41~ = A, ~$

A{. B:,

!NW-1 A {

{ " T-58 Y

'I

$ h' 'I ~

I T-71

~,.;==--. '$

Turkey Point

$ $ $ $ $ ~ $$ % $ $$

T-42 F~ 5((bt{a {0'h. p .L' AT

$ %$ $ $ $ ~ $ $$ $$ $ $$ $ oa t 2{ ~

T 72 l.

I

~ g B!

$ I I S

Y, N

E r ".Q-'W-1;-

Q TH SSE-1 A

Y I

Turtle Point

//". ~M Turkey Point Sampling Locations Plant Site Area

0 0

1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 &. 4 l I I, u i rrr NNE-22 T-64,12 miles 8 , T-67 4

SDA St tCt . N-10 I

Cull>>>

44>>

NNW-10 044ICI 5

NW-10 IAC\ICA

~ 4~ ~ >>tl 4> 4 AI4

> l. O.S OA CISCA>>l>S r>>A PIS rtrltfl>>4, 4 C II AlIQ>> AA

~

~ ~

Al

~

~ >> Jr A,>> AAAC

>>I WNW-10 >>C NW-5 T-57 T-52I T-40 I>>>>>l>>

l W-9 SSAC>Ct AA AO>>>> STASCI>>

5>>> Stt 5 WSW-Q, MODEL LAND'CANAL OAOS CO wO ~ 4 CA>>I~ AO I

I I ~ IA SW-8 SSW-5 S-5 r 4

T-81 ~

4 4 P$

C,'>>-" o P'i t

>>4 8 SSE-10 mI>

0g 5~

I >' ,I

~ ~ A>>VI> SAIC SSW-10/ I

((l S-10 Turkey Point Sampling Locations

1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Sc 4 ATTACHMENT A Page 1 of 4 PATHWAY: DIRECT RADIATION SAMPLES COLLECTED! TLD SAMPLE COLLECTION FREQUENCY: QUARTERLY Location"'ame Descri tion N-2 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 6 U.S. ¹1 NW-1 Turkey Point Entrance Road NW-5 Mowry Drive E 117th Avenue NW-10 Newton Road, North of Coconut Palm Drive WNW-10 Homestead Middle School On-Site, North Side of Discharge Canal W-5 Palm Drive & Tallahassee Road W-9 Card Sound Road, 0.6 mile from U.S. ¹1 WSW-8 Card Sound Road, 3.4 miles from U.S. ¹1 SW-1 On-Site near Land Utilization Offices SW-8 Card Sound Road, 5 miles from U.S. ¹1 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 Control Natoma Substation NNE-22

'"The location name is the direction sector - approximate distance (miles)

1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 R 4 ATTACHMENT A Page 2 of 4 PATHWAY: AIRBORNE 'I SAMPLES COLLECTED: RADIOIODINE AND PARTICULATES SAMPLE COLLECTION FREQUENCY: WEEKLY Approximate Location Direction Distance Name Sector Descri tion T-51 Entrance Area to Biscayne National Park T-57 SW 107th Avenue at Mowry Canal T-58 Turkey Point Entrance Road T-72 WSW Just before entrance to Land Utilization's access gate.

Control:

T-64 22 Natoma Substation

0 0

1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 & 4 ATTACHMENT A Page 3 of 4 PATHWAY: WATERBORNE SAMPLES COLLECTED: SURFACE WATER (OCEAN)

SAMPLE COLLECTION FREQUENCY: MONTHLY Approximate Location Direction Distance Name Sector miles Descri tion T-42 ENE Biscayne Bay at Turkey Point T-81 Card Sound, near Mouth of Old Discharge Canal Control:

-67 N, NNE 13-18 Near Biscayne Bay, Vicinity of Cutler Plant, North to Matheson Hammock Park SAMPLES COLLECTED: SHORELINE SEDIMENT SAMPLE COLLECTION FREQUENCY: SEMI-ANNUALLY Approximate Location Direction Distance Name Sector miles Descri tion T-42 ENE Biscayne Bay at Turkey Point T-81 Card Sound, near Mouth of Old Discharge Canal Control:

T-67 N, NNE 13-18 Near Biscayne Bay, Vicinity of Cutler Plant, North to Matheson Hammock Park

0 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 & 4 ATTACHMENT A Page 4 of 4 PATHWAY: INGESTION SAMPLES COLLECTED: CRUSTACEA AND FISH SAMPLE COLLECTION FREQUENCY: SEMI-ANNUALLY Approximate Location Direction Distance Name Sector miles Descri tion T-81 Card Sound Vicinity of Turkey Point Facility Control:

T-67 N, NNE 13-18 Near Biscayne Bay, Vicinity of Cutler Park, North to Matheson Hammock Park SAMPLES COLLECTED: BROAD LEAF VEGETATION SAMPLE COLLECTION FREQUENCY: MONTHLY Approximate Location Direction Distance Name Sector Descri tion 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

0 0

1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 9, 4 ATTACHMENT B RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE 1995 First Quarter, 1995 Second Quarter, 1995 Third Quarter, 1995 Fourth Quarter, 1995

RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE First Quarter, 1995 Office of Radiation Control Florida Department of Health and Rehabilitative Services

TURKEY POINT SITE Technical Specifications Sampling First Quarter, 1995 Collection Locations Number of Sam le T e Fre enc

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 3.b Shoreline Sediment Semiannually '3

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: 178

• Includes NRC split samples.

NOTE: Measurement results having magnitudes that are significantly above the background of the measurement system are reported as net values plus or minus a one-standard-deviation error term.

Measurement results that are not significantly above background are reported as "non-detectable" (ND) or as less than a Lower

=-

Limit of Detection (<LLD), which is an estimated upper limit (with at least 954 confidence) for the true activity in the sample.

DIRECT RADIATION TLDs micro-R hour Sample Deployment 12-07-94 Site Collection 03-15-95 N-2 6.28 + 0.30 N-7 5.68 + 0.30 N-10 5.38 + 0.29 NNW-2 5.32 + 0.35 NNW-10 5.72 + 0.29 NW-1 4.68 + 0.36 NW-5 (A) 5.25 + 0.30 NW-10 8.16 + 0.26 7.07 + 0.30 W-1 6.57 + 0.36 W-5 (A) 5.23 + 0.30 W-9 4.68 + 0.30 WSW-8 5.19 + 0.30 SW-1 (B),

SW-8 (B)

SSW-5 5.17 + 0.36 SSW-10 5.27 + 0.30 S-5 (A) 5.79 + 0.36 S-10 5.99 + 0.30 SSE-1 5.40 + 0.36 SSE-10 6.37 + 0.31 NNE-22 6.04 + 0.36 (A) The dosimeters for sites NW-5, W-5, and S-5 were found lying

'on the ground. Also, the wooden siren pole formerly used at site W-5 had been replaced with a concrete pole.

(B) The dosimeters .for sites SW-1 and SW-8 were missing when collection was attempted.

IODINE-131 IN WEEKLY AIR FILTERS Ci m3 Sam le Site Collection Date T51 T57 T58 T64 T72

.01.-05-95 <0. 02 <0.01 <0.01 <0. 02 <0.01 01-11-95 <0.01 <0.01 <0.01 <0.01 <0.01 01-17-95 <0.01 <0.01 <0.01 <0.01 <0.01 01-23-95 <0.03 <0.03 <0.03 <0.03 <0.03 02-01-95 <0. 02 <0.02 <0.02 <0. 02 <0.02 02-06-95 <0. 01 <0.01 <0.01 <0. 01 <0.01 02-13-95 <0.02 <0.02 <0.02 <0.02 <0.02 02-21-95 <0.01 <0.01 <0.01 <0.01 <0.01 02-28-95 .<0. 01 <0.01 <0.01 <0.01 <0.01 03-06-95 <0.03 <0.03 <0. 03 <0.03 <0.03 03-14-95 <0.01 <0.01 <0. 01 <0.01 <0.01 03-21-95 <0.02 <0.03 <0. 02 <0.02 <0.02 03-28-95 <0.02(A) <0.02(B) <0.02 <0.02 <0.02 (A) We believe a power outage. occurred during this sample.

The ec{uipment is estimated to have run for 164 hours0.0019 days <br />0.0456 hours <br />2.71164e-4 weeks <br />6.2402e-5 months <br /> out of the 169 total hours for this sampling interval.

(B) We believe a power outage occurred during this sample.

The equipment is estimated to have run for 170 hours0.00197 days <br />0.0472 hours <br />2.810847e-4 weeks <br />6.4685e-5 months <br /> out of the 189 total hours for. this sampling interval.

2.b AIR PARTICULATES GROSS BETA 0

Ci m3 Collection Sam le Site Date T51 T57 T58 T64 T72 01-05-95 0.005 + 0.002 0.004 + 0.001 0.008 + 0.002 0. 008 + 0. 002 0.006 + 0.002 01-11-95 0.015 + 0.002 0.011 + 0.002 0.012 + 0.002 0. 013 + 0. 002 0.017 + 0.002 01-17-95 0.010 + 0.002 0.004 + 0.002 0.007 + 0.002 0.007 + 0.002 0.011 + 0.002 01-23-95 0.018 + 0.003 0.011 + 0.002 0.015 + 0.003 0.018 + 0.003 0.012 + 0.002 02-01-95 0.016 + 0.002 0.017 + 0.002 0. 017 + 0.002 0.018 + 0.002 0.018 + 0.002

.02-06-95 0.015 + 0.003 0.014 + 0.003 *0.011 + 0.003 0.018 + 0.003 0 ~ 013 + 0.003 02-13-95 0.008 + 0.002 0.009 + 0.002 *0.015 + 0.002 0.014 + 0.002 0.012 + 0.002 02-21-95 0.004 + 0.001 0.005 + 0.001 *0.005 + 0.001 0.007 + 0.002 0.006 + 0.001 02-28-95 0.011 + 0.002 0.012 + 0.002 *0.011 + 0.002 0.013 + 0.002 0.011 + 0.002 03-06-95 0.008 + 0.002 0.005 + 0.002 0.007 + 0.002 0.006 + 0.002 0-005 + 0.002 03-14-95 0.010 + 0.002 0.012 + 0.002 0.009 + 0.002 0.011 + 0.002 0-011 + 0.002 03-21-95 0.009 + 0.002 0.007 + 0.002 0.011 + 0.002 0.010 + 0.002 0 009 + 0.002 03-28-95 (A0.017 + 0.002 (B0.014 + 0.002 0.014 + 0.002 0 '17 + 0.002 0.016 + 0.002 Means: 0.011 + 0.001 0.010 + 0.001 0.011 + 0.001 0.012 + 0.001 0.011 + 0.001

• NRC split samples.

(A) We believe a power outage occurred during this sample. The equipment is estimated to have run for 164 hours0.0019 days <br />0.0456 hours <br />2.71164e-4 weeks <br />6.2402e-5 months <br /> out of the 169 total hours for this sampling interval.

(B) We believe a power outage occurred during this sample. The equipment is estimated to have run for 170 hours0.00197 days <br />0.0472 hours <br />2.810847e-4 weeks <br />6.4685e-5 months <br /> out of the 189 total hours for this sampling interval.

2.b AIR PARTICULATES GAMMA SCANS OF UARTERLY COMPOSITES Ci m3 First Quarter, 1995 Sample Site Be-7 K-40 Cs-134 Cs-137 Pb-210 T51 0. 1467 + 0.0100 <0.0185 <0.0007 <0.0008 0.0104 +,0.0026 T57 0.1589 + 0.0115 <0.0173 <0.0010 <0.0009 0.0118 + 0.0025 T58 0.1455 + 0.0102 <0.0164 <0.0007 <0.0012 0.0100 + 0.0023 T64 0.1446 + 0.0120 <0.0163 <0.0008 <0.0009 0.0143 + 0.0031 T72 0.1362 + 0.0094 <0.0187 <0.0008 <0.0008 0.0133 + 0.0027

3.a SURFACE WATER Ci l I

'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 (A) (B)

T42 01-18-95 <136 297 + 28 <4 <3 <8 <5 <8 <6 <7 <4 <4 <5 02-08-95 <145 . 194 +'26 <4 <3 <8 <5 ~

<8 <7 <7 <4 <5 <5 03-09-95 <142 272 + )35 <3 <3 <11 <4 <6 <8 <12 <3 <4 <7 T67 01-19-95 <135 153 + '30 <3 <4 <8 <4 <7 <7 <10 <5

'5

<4 <5 02-09-95 <132 249 + 30 <4 <5 <7 <5 <6 <7 <6 <4 <5 03-09-95 <142 94 + 30 <4 <3 <5 <4 <7 <7 <12 <4 <4 <9 T81 01-18-95 186 + 45 256 + 32 <4 <4 <8 <4 '9 <6 <8 <4 <3 <5 02-08-95 345 + 47 265 + 32 <3 <4 <9 <6 <7 <7 <9 <4 <4 <4 03-09-95 175 + 46 270 + 31 <4 <5 <8 <5 <7 <8 <13 <4 <4 <5 (A) These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.

I (B) These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample.

0 0

3.b SEDIMENT Ci k dr wei ht Sample Collection Site Date Be-7 K-40 Co-58 Co-60 Cs-134 Cs-137 Ra-226 Th-232 T42 01-09-95 <204 354 + 72 <16 <13 <14 <16 965 + 19 ND T67- 01-12-95 <94 243 + 43 <8 <6 <8 <8 ND ND T81 01-09-95 <146 305 + 62 <12 <11 <11 <11 871 + 16 ND 4.a.l CRUSTACEA Blue Crab Ci k wet wei ht Sample Collection Site Date K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 First quarter attempts to collect this sample were not successful. Efforts continue.

T81 03-31-95 1901 + 177 <19 <24 <53 <23 <51 <25 <24 436 + 26 ND 4.a.2 FISH Mixed S ecies Ci k wet wei ht Sample Collection Site Date K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 02-09-95 2309 + 390 <54 <73 <151 <64 <128 <62 <60 ND ND T81 03-31-95 2198 + 192 <20 <20 <55 <24 <44 <22 <25 ND ND 4

ND Non-detectable.

lt 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 01-19-95 2314 + 94 3783 + 138 <19 <9 <15 ND 02-09-95 1806 + 86 3382 + 124 <21 <8 115 + 7 I 715 + 276 03-09-95 1618 + 72 2341 + 101 <19 <9 15+4 I ND T41 01-19-95 2880 + 90 5662 + 164 <17 <10 23+ 6 596 + 244'D W

02-09-95 2244 + 100 3576 + 154 <31 <10 42+7 03-09-95 688 + 63 5439 + 182 <24 71+ 9 ND T67 01-19-95 1186 + 60 3504 + 123 <15 <9 <9 ND 02-09-95 940 + 58 3143 + 117 <20 <9 <10 ND 03-09-95 1055 + 81 3947 + 143 <23 <10 ND ND Non-detectable.

RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE Second Quarter, 1995 Office of Radiation Control Florida Department of Health and Rehabilitative Services

TURKEY POINT SITE Technical Specifications Sampling Second Quarter, 1995 Collection Locations Number of Sam le T e Fre enc

1. Direct Radiation Quarterly 22 22

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 1 4.a.2 Fish Semiannually 0 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 95% confidence) for the true activity in the sample.

DIRECT RADIATION TLDs micro-R hour Sample Deployment 03-15-95 Sample Deployment 03-15-95 Site Collection 06-07-95 Site Collection 06-07-95 N-2 5.44 + 0.09 WSW-8 4.90 + 0.09 N-7 4.53 + 0.09 N-10 4.30 + 0.08 SW-1 4.75 + 0.09 SW-8 4.76 + 0.09 NNW-2 4.13 + 0.08 NNW-10 5.63 + 0.09 SSW-5 4.49 + 0.08 SSW-10 (A) 4.57 + 0.08 NW-1 4.72 + 0.09 NW-5 4.40 + 0.08 S-5 4.59 + 0.09 NW-10 7.58 + 0.10 S-10 5.45 + 0.09 WNW-10 6.14 + 0.09 SSE-1 (A) 4.76 + 0.09 SSE-10 5.69 + 0.09 W-1 6.23 + 0.09 W-5 5.08 + 0.09 NNE-22 5.98 + 0.09 W-9 4.63 + 0.09 (A) The dosimeters for sites SSW-10 and SSE-1 were found lying on the ground when they were collected.

2.a IODINE-131 IN WEEKLY AIR FILTERS Ci m3 Sam le Site Collection Date T51 T57 T58 T64 T72 04-04-95 <0. 02 <0. 02 <0.02 <0.02 <0. 02 04-11-95 <0. 02 <0.03 <0.03 <0.02 <0. 02 04-17-95 <0. 02 <0.02 <0.02 <0.02 <0. 02 04-24-95 <0.02 <0.02 <0.02 <0.02 <0. 02 05-02-95 <0.02 <0.02 <0.02 <0.02 <0. 02 05-10-95 <0.01 <0.01 <0.01 <0.01 <0. 02 05-18-95 <0.01 <0.01 <0.01 <0.01 <0. 01 05-25-95 <0.02 <0.02 <0.03 <0.03 <0. 03 05-31-95 <0.02 <0.02 <0.02 <0.02 <0.02 06-06-95 <0.02 <0. 02 <0.02 <0.02 <0.02 06-13-95 <0.02 <0.02 <0.02 <0.02 <0.02 06-19-95 <0.04 <0.04 <0.05 <0.04 <0.05 06-27-95 <0.01 <0.01 <0.01 <0.01 <0.01

0 0'.b AIR PARTICULATES GROSS BETA Ci m3 Sam le Site Collection Date T51 T57 T58 T64 T72 04-04-95 0.016 + 0.002 0.018 + 0.002 0. 020 + 0. 002 0. 021 + 0.002 0. O18 + O. OO2 04-11-95 0.013 + 0.002 0.008 + 0.002 0.015 + 0.002 0. 012 + 0.002 0. 009 + 0. 002 04-17-95 0.010 + 0.002 0.014 + 0.003 0.020 + 0.003 0. 011 + O.Q02 0.016 + 0.003 04-24-95 0.021 + 0.003 0.017 + 0.002 0.022 + 0.003 0.022 + 0.003 0. 020 + 0. 003 05-02-95 0.009 + 0.002 0.012 + 0.002 0.009 + 0.002 0. 016 + 0. 002 0. 011 + 0. 002 05-10-95 0.010 + 0.002 0.013 + 0.002 *0.014 + 0.002 0.019 + 0.002 0. 012 + 0. 002 05-18-95 0.017 + 0.002 0.015 + 0.002 *0.018 + 0.002 0.012 + 0.002 0.020 + 0. 002 05-25-95 0.013 + 0.002 0.009 + 0.002 *0.015 + 0.002 0.014 + 0.002 0.014 + 0.002 05-31-95 0.010 + 0.002 0.013 + 0.002 *0.013 + 0.002 0.011 + 0.002 0.011 + 0.002 06-06-95 0.007 + 0.002 0.006 + 0.002 0.007 + 0.002 0.007 + 0.002 0. 009 + 0. 002 06-13-95 0.011 + 0.002. 0.010 + 0.002 0.012 + 0.002 0.018 + 0.002 0. 012 + 0. 002 06-19-95 0.005 + 0.002 0.011 + 0.002 0.006 + 0.002 0.010 + 0.002 0. 007 + 0. 002 06-27-95 0.009 + 0.002 0.010 + 0.002 0.012 + 0.002 0.011 + 0.002 0.011 + 0. 002 Means: 0.012 + 0.001 0.012 + 0.001 0.014 + 0.001 0.014 + 0.001 0.013 + O.OO1

• NRC split samples.

2 b AIR PARTICULATES GAMMA SCANS OF UARTERLY COMPOSITES Ci m3 Second Quarter, 1995 Sample Site Be-7 K-40 Cs-134 Cs-137 Pb-210 T51 0. 1214 + 0. 0095 <0.0159 <0.0010 <0.0007 0.0122 + 0.0025 T57 0.1160 + 0.0097 <0.0208 <0.0005 <0.0005 0.0123 + 0.0026 T58 0 ~ 1381 + 0 0101 F <0.0203 <0.0008 <0.0008 0.0135 + 0.0031 T64 0.1341 + 0.0110 <0.0182 <0.0010 <0.0009 0.0116 + 0.0028 T72 0.1145 + 0.0101 <0.0138 <0.0008 <0.0010 0.0105 + 0.0024

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 (B)

T42 04-12-95 <137 265 + 29 <3 <3 <7 <5 <7 <6 <7 <3 <4" '<5 05-10-95 <136 278 + 34 <3 <3 <9 <3 <9 <6 <6 <4 <4 06-16-95 <139 273 + 31 <4 <4 <8 <4 <9 <7 <10 <3 <4 <7 T67 04-14-95 <137 166 + 35 <4 <4 <7 <5 <8 <7 <6 <4 <4 <6 05-11-95 <136 226 + 34 <4 <4 <6 <4 <9 <6 <6 <5 <3 <5 06-16-95 <139 236 + 32 <4 <4 <8 <4 <11 <7 <10 <4 <4 <6 T81 04-13-95 <147 347 + 41 <4 <4 <6 <5 <8 <7 <8 <5 <5 05-11-95 201 + 45 238 + 30 <3 <4 <8 <4 <9 <6 <7 <3 <4 <5 06-15-95 149 + 45 266 + 35 <5 <4 <10 <4 <6 <8 <10 <3 <4 <7 (A) These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.

(B) These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample.

4.a.l CRUSTACEA Blue Crab Ci k wet wei ht Sample Collection Site Date K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65. Cs-134 Cs-137 Ra-226 Ra-228 T67 04-04-95 1787 + 189 <20 <19 <46 <27 <52 <22 <20 . ND ND 4.b.1 BROADLEAF VEGETATION Brazilian Pe er Ci k wet wei ht Sample Collection Site Date Be-7 K-4 0 I-131 Cs-134 Cs-137 T40 04-13-95 1842 + 73 3112 + 124 <14 <9 57+ 6

• 05-11-95 1671 + 73 2448 + 105 <14 <9 62+ 6 06-15-95 1469 + 91 3384 + 143 <18 <11- 74+ 9 T41 04-13-95 1689 + 81 5839 + 174 <17 <11 58+ 8 05-11-95 1632 + 83 6175 + 177 <18 <12 37+ 6 06-15-95 1133 + 75 4332 + 135 <22 <9 33+ 6 T67 04-14-95 1170 + 69 4080 + 141 <13 <10 <9 05-11-95 699 + 54 5511 + 157 <15 <9 <10 06-16-95 900 + 61 3823 + 134 <16 <8 <11

• NRC split sample. ND Non-detectable.

0 RADIOLOGICAL SURVEILLANCE OF FLORIDA POHER AND LIGHT COMPANY'S TURKEY POINT SITE Third Quarter, 1995 Office of Radiation Control Florida Department of Health and Rehabilitative Services

0 0

TURKEY POINT SITE Technical Specifications Sampling Third Quarter, 1995 Collection Locations Number of Sam le T e Fre enc Sam led Sam les

1. Direct Radiation Quarterly 22 21

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 4.a.2 Fish Semiannually 4.b Food Products 4.b.1 Broadleaf Monthly

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

0 DIRECT RADIATION TLDs (micro-R hour)

Sample Deployment 06-07-95 Site Collection 09-13-95 N-2 5.02 + 0 ~ 10 N-7 4.54 + 0.09 N-10 4.95 + 0.09 NNW-2 4.10 + 0.09 NNW-10 5.53 + 0.10 NW-1 4.50 + 0. 09 NW-5 4.53 + 0.09 NW-10 7.27 + 0.11 WNW-10 6.09 + 0.10 W-1 6.16 + 0.10 W-5 (A)

W-9 4.57 + 0.09 WSW-8 4.69 + 0.09 SW-1 4.87 + 0.10 SW-8 4.63 + 0.09 SSW-5, 4. 55. + 0.09 SSW-10 4.85 + 0.09, S-5 4.32 + 0.09 S-10 5 '7 + 0 ~ 10 SSE-1 (B) 4.91 + 0.10 SSE-10 5.55 + 0.10 NNE-22 5.14 + 0.09 (A) The dosimeter for site W-5 was missing when collection was attempted.

--(B)=- The dosimeter-for-siCe-SSE-1 -was on the ground.

found'ying

4 IODINE-131 IN WEEKLY AIR FILTERS ( Ci m )

Sam le Site Collection Date T51 T57 T58 T64 T72 07-06-95 <0.01 <0;01 <0.01 <0.01 <0.01 07-12-95 <0 '2 <0. 02 <0 '2 <0.02 <0.02 07-17-95 <0.02 <0.02 <0.02 <0.02 <0.02 07-27-95 <0.01 <0.01 <0.01 <0.01 <0.01 08-02-95 <0. 02 <0.02 <0.02 <0.02 <0.02 08-07-95 <0. 02 <0.02 <0.02 <0.02 <0.02 08-15-95 <0 02

~ <0.02 <0. 02 <0 '2 <0.02 08-23-95 <0. 02 <0.02 <0. 02 <0.02 <0. 02 (A) 08-29-,95 <0. 02 <0:02 <0.02 <0.02 <0. 02 (B) 09-05-95 <0. 02 <0.02 <0.02 <0. 02 <0. 02 09-12-95 <0.01 <0.01 <0.01 <0.01 <0.01 09-19-95 <0.02 <0.02 <0.02 <0.02 <0.02 09-25-95 <0.02 <0.02 <0.02 <0.02 <0.02 (A) Electrical power was out at the end of this sample. The equipment is estimated to have run for 170 hours0.00197 days <br />0.0472 hours <br />2.810847e-4 weeks <br />6.4685e-5 months <br /> out of the 191 total hours for this sampling interval.

(B) Electrical power was out at the start of this sample. The equipment is estimated to have run for 138 hours0.0016 days <br />0.0383 hours <br />2.281746e-4 weeks <br />5.2509e-5 months <br /> out of the 144 total hours for this sampling interval.

0 2.b AIR PARTICULATES GROSS BETA (pCi m )

Sam le Site Collection Date ~ T51 T57 T58 T64 T72 07-06-95 0.016 + 0.002 0.013 + 0.002 0.014 + 0.002 0.016 + 0.002 0.016 + 0.002 07-12-95 0.007 + 0.002 0.003 + 0.002 0.009 + 0.002 0.015 + 0.003 0.013 + 0.002 07-17-95 <0.006 <0.007 0.006 + 0.002 0.005 + 0.002 0.008 + 0.002 07-27-95 0.004 + 0.001 0.005 + 0.001 0.008 + 0.002 0.008 + 0.001 0.005 + 0.001 08-02-95 0.008 + 0.002 0.011 + 0.002 *0.009 + 0.002 0. 012 + 0.002 0.007 + 0.002 08-07-95 08-15-95 0.024 0.012

+

+

0.003 0.002 0.023 0.014

+

+

0.003 0.002

• 0.012

• 0.016

+

+

0.002 0.002

0. 011 + 0.002 0.012 +'. 002

0. 017 + 0.002 0.014 + 0.002 08-23-95 0.020 + 0.002 0.015 + 0.002 *0.016 + 0.002 0.016 + 0.002 (A0.022 + 0.003 08-29-95 0.014 + 0.002 0.016 + 0.002

• 0.015 + 0.003 0.016 + 0.002 (B0.018 + 0.003 09-05-95 0.013 + 0.002 0.009 + 0.002 0.009 + 0.002 0.022 + 0.003 0.012 + 0.002 09-12-95 0.007 + 0.002 0.006 + 0.002 0 005 + 0.002 0. 010 + 0. 002 0.008 + 0.002 09-19-95 0.008 + 0.002 0.012 + 0.002 0.007 + 0.002 0.007 + 0.002 0.009 + 0.002 09-25-95 0.007 + 0.002 0.011 + 0.002 0-009 + 0.002 0.014 + 0.002 0.011 + 0.002 Means: 0.012 + 0.001'.012 + 0.001 0.010 + 0.001 0.013 + 0.001 0.012 + 0.001

• I NRC split samples.

(A) Electrical power was out at the end of this sample. The equipment is estimated

~to have run for 170 hours0.00197 days <br />0.0472 hours <br />2.810847e-4 weeks <br />6.4685e-5 months <br /> out of the 191 total hours for this sampling interval.

(B) Electrical power was out at the start of this sample The equipment is estimated to have run for 138 hours0.0016 days <br />0.0383 hours <br />2.281746e-4 weeks <br />5.2509e-5 months <br /> out of the 144 total hours for this sampling interval.

2.b AIR PARTICULATES GAMMA SCANS OF QUARTERLY COMPOSITES (pCi m )

Third Quarter, 1995 Sample Site Be-7 K-40 Cs-134 Cs-137 Pb-210 T51 0.1089 + 0.0097 <0.0164 <0.0011 <0.0009 0.0127 + 0.0026 T57 0.0954 + 0.0116 <0.0156 <0.0010 <0.0006 ND T58 0.0990 + 0.0096 <0.0181 <0.0010 <0.0007 0.0112 + 0.0026 T64 0.1043 + 0.0081 <0.0154 <0.0007 <0.0005 0.0123 + 0.0033 T72 0.0904 + 0.0085 <0.0196 <0.0011 <0.0007 0.0124 + 0.0025 ND Non-detectable.

'0 3.a SURFACE WATER (pCi/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 07-20-95 <152 218 + 31 <3 <3 <6 <4 <8 <5 <6 <4 <5 08-17-95 <144 254 + 25 <3 <4 <7 <4 <7 <7 <6 <3 <5 <8 09-06-95 <144 290 + 29 <4 <3'8 <4 <6 <7 <7 <3 <4 <5 T67 07-21-95 <152 225 + 13 <1 <1 <3 <2 <3 <3 <2 <2 08-18-95 <134 203 + 31 <4 <3 <6 <4 <8 <6 <5 <5 09-06-95 <144 186 + 25 <4 <4 <8 <4 <10 <7 <7 <4 <4 <5 T81 07-19-95 <152 271 + 32 <3 <3 <7 <4 <7 <7 <7 <5 <5 08-17-95 <153 195 + 33 <4 <4 <8 <5 <7 <5 <6 <4 <4 <2 09-06-95 <151 252 + 29 <4 <3 <10 <4 <7 <6 <8 <4 <6 (A) These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.

(B) These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample.

0 3

3.b SEDIMENT (pCi/k, dr wei ht)

Sample Collection Site Date Be-7 K-40 C0-58 C0-60 Cs-134 Cs-137 Others T42 07-20-95 438 + 69 431 + 89 <12 <15 <13 <15 Ra-226: 754 + 19 U-238 638 + 176 T67 07-18-95 142 + 37 249 + 45 <6 <4 <7 <7 Ry-226 110 + 7 Th-232: 55+ 8 T81 07'-19-95 378 + 68 386 + 60 <9 <11 <11 <12 Ra-226: 645 + 15 4.a.1 CRUSTACEA  ; Blue Crab (pCi k , wet wei ht)

Sample Collection Site Date K-4 0 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 07;21-95 1317 + 162 <16 <14 <35 <17 <37 <17 <19 ND ND

\

T81 Third quarter attempts to collect this sample were not successful. Efforts continue.

4.a.2 FISH Mixed Species (pCi/kg, wet wei ht) 1 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 Third quarter attempts to collect this sample were not successful. Efforts continue.~~

T81 Third quarter attempts to collect this sample were not successful. Efforts continue.

ND Non-detectable.

0 4.b.l BROADLEAF VEGETATION Brazilian Pepper (pCi/k , wet weight)

Sample Collection Site Date Be-7 K-40 3-131 Cs-134 Cs-137 Pb-210 T40 07-24-95 1686 + 80 5155 + 154 <13 <8 81+ 8 ND 08-17;95 2873 + 114 2820 + 122 <14 <10 100 + 10 1141 + 224 09-06-95 3408 + 99 3185 + 125 <26 <9 34 + 6 ND T41 07-24-95 2391 + 89 5096 + 159 <12 <9 74+ 6 ND 08-17-95 3252 + 102 3815 + 150 <18 <13 102 + 8 908 + 275 09-06-95 3635 + 108 4435 + 143 <20 <10 109 + 9 574 + 215 T67 07-21-95 1411 + 68 3858 + 137 <14 <10 <10 ND 08-18-95 1309 + 70 3535 + 128 <12 <9 <9 ND 09-06-95 1779 + 74 4746 + 146 <21 724 + 303 ND Non-detectable.

7

RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE Fourth Quarter, 1995 Office of Radiation Control Florida Department of Health and Rehabilitative Services

TURKEY POINT SITE Technical Specifications Sampling Fourth Quarter -1995 Collection Locations Number of Sam le T e Fre uenc

1. Direct Radiation Quarterly 22 21

2. Airborne 2.a Air Iodines Weekly 65 2.b Air Particulates Weekly 64

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: 171 NOTE: Measurement results having magnitudes that are significantly above the background of the measurement system are reported as net values plus or minus a one-standard-deviation error term.

Measurement results that are not significantly above background are reported as "non-detectable" (ND) or as less than a Lower Limit o f Detection (<LLD), which is an estimated upper imit (with at least 954 confidence) for the true activity in the l

sample.

DIRECT RADIATION TLDs (micro-R/hour)

Deployment 09-13-95 Sample Site == Collection .12-13-95 N-2 5.57 + 0.11 N-7 4.63 + 0.11 N-10 4.75 + 0.10 NNW-2 4.46 + 0.11 NNW-10 5.66 + 0.11 NW-1 (A) 6.67 + 0.12 NW-5 4.77 + 0.11 NW-10 7.46 + 0.12 WNW-10 6.29 + 0.12 W-1 6.29 + 0.12 W-5 4.75 + 0.11 W-9 4.73 + 0.11 WSW-8 4.76 + 0.10 SW-1 SW-8 4.81 4.60

+ 0 '0

+ 0.10 SSW-5 4.52 + 0.11 SSW-10 (>)

S-5 4.37 + 0.10 S-10 5.61 + 0.11 SSE-1 4.45 + 0.10 SSE-10 5.73 + 0.11 NNE-22 5.97 + 0.11 (A) The result for site NW-1 is statistically high compared to the long-term average of 5.03 micro-R/hr there. This corre-sponds to a dose of approximately 3.6 millirem more than would be expected at this site during this deployment inter-val. Although this location is along the plant entrance road where shipments of radioactive materials would pass by, no specific explanation for this elevated reading is known.

t (B) The dosimeter attempted.

for site SSW-10 was missing when collection was

2.a IODINE-131 IN WEEKLY AIR FILTERS Ci m Sam le Site

'Collection Date T51 T57 T58 T64 T72 10-04-95 <0. 01 <0.01 <0.01 <0. 02 <0. 01 10-11-95 <0. 02 <0.02 <0.02 <0. 01 <0. 02 10-19-95 <0.02 <0.02 <0.02 <0. 02 <0. 02 10-25-95 <0.02 <0.02 <0.02 <0.02 <0.02 10-31-95 <0.02 <0.02 <0.02 <0.02 <0.02 11-06-95 <0. 02 <0.02 <0.02 <0.02 <0. 02 11-13-95 <0.02 <0.02 <0.02 <0.02 <0. 02 11-20-95 <0.02 <0.02 <0.02 <0.02 <0. 02 11-27-95 <0.01 <0.01 <0.01 <0.01 <0. 01 12-07-95 <0.01 <0.07(A) <0.01 <0.01 <0.01 12-12-95 <0.04 <0.02(B) <0.03 <0.03 <0.04 12-19-95 <0.02 <0.02 <0.02 <0. 03 <0.02 12-28-95 <0.02 <0.02 <0. 01 '<0. 01 <0.01 (A) Electrical power was out at the end of this sample. A car had been backed against this utility pole and had been set afire. The fire had damaged the utility pole, and one of the wires was down. The equipment is estimated to have run for 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> out of the 197 total hours for this sampling interval.

(B) Electrical power was out at the start of this sample. The equipment is estimated to have run for 134 hours0.00155 days <br />0.0372 hours <br />2.215608e-4 weeks <br />5.0987e-5 months <br /> out of the 139 total hours for this sampling interval.

2.b AIR PARTICULATES GROSS BETA (pCi m )

Sample Site Collection Date T51 T57 T58 T64 T72 10-04-95 0.007 + 0.002 0. 008 + 0. 002 0.006 + 0.001 0.004 + 0.002 0.007 + 0.001 10-11-95 0.004 + 0.002 0.004 + 0.002 0.007 + 0.002 0.006 + 0.001 0.007 + 0.002 10-19-95 0.007 + 0.002 <0.005 0.004 + 0.001 0.007 + 0.002 0.003 + 0.001 10-25-95 <0.006 <0.005 0.006 + 0.002 0.007 + 0.002 <0.007 10-31-95 0.012 + 0.002 0.013 + 0.002 0.015 + 0.002 0.015 + 0.002 0.010 + 0.002 11-06-95 0.013 + 0.002 0.009 + 0.002 0.018 + 0.002 0.015 + 0.002 0.016 + 0.002 11-13-95 0.018 + 0.002 0.020 + 0.002 0.014 + 0.002 0.015 + 0.002 0.015 + 0.002 11-20-95 0.014 + 0.002 0.020 + 0.002 0.020 + 0.002 0.015 + 0.002 0.017 + 0.002 11-27-95 0.018 + 0.002 0.016 + 0.002 0.015 + 0.002 0.018 + 0.002 0.020 + 0.002 12-07-95 0.013 + 0.002 (A) 0.015 + 0.002 0.016 + 0.002 0.015 + 0.002 12-12-95 0.017 + 0.003 (B0.014 + 0.003 0.024 + 0.003 -0.019 + 0.002 0.021 + 0.003 12-19-95 0.011 + 0.002 0.007 + 0.002 0.007 + 0.002 0.013 + 0.003 0.009 + 0.002 12-28-95 0.021 + 0.002 0.020 + 0.002 . 0.024 + 0.002 0.025 + 0.002 0.018 + 0.002 Means: 0.013 + 0.001 0.013 + 0.001 0.013 + 0.001 0.013 + 0.001 0.013 + 0.001 (A) Electrical power was out at the end of this sample. A car had been backed against this utility pole and had been set afire. The fire had damaged the utility pole, and one of the wires was down. The particulate filter and its holder were missing when collection was attempted.

(B) Electrical power was out at the start of this sample. The equipment is estimated to have run for 134 hours0.00155 days <br />0.0372 hours <br />2.215608e-4 weeks <br />5.0987e-5 months <br /> out of the 139 total hours for this sampling interval.

2.b AIR PARTICULATES GAMMA SCANS OF QUARTERLY COMPOSITES Ci/m

( )

Fourth Quarter, 1995 Sample Site Be-7 K-40 Cs-134 Cs-137 Pb-210 T51 0.1398 + 0.0100 <0.0186 <0.0011 <0.0006 0.0112 + 0.0030 T57 0.1191 + 0.0091 <0.0167 <0.0007 <0.0008 0.0105 + 0.0029 T58 0.1443 + 0.0104 <0.0139 <0.0005 <0.0009 0.0098 + 0.0039 T64 0.1382 + 0.0105 <0.0135 <0.0008 <0.0008 0.0159 + 0.0029 T72 0.1348 + 0.0123 <0.0152 <0.0006 <0.0007 0.0109 + 0.0028

3.a SURFACE WATER (pCi 1)

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)

I T42 10-12-95 <140 222 + 30 <3 <4 <8 <5 <8 <7 <6 <3 ,<4 <6 11-08-95 <145 162 + 30 <4 <4 <8 <3 <7 <7 <7 <4 <4 <6 12-08-95 <155 175 + 27 <3 <4 <7 <5 <7 <6 <8 <5 <4 <5 T67 10-13-95 <14'0 174 + 28 <3 <4 <9 <3 <7 <6 <7 <4 <4 <5 11-09-95 <145 146 + 30 <4 <4 <7 <5 <7 <5 <8 <3 <4 <6 12-08-95 <149 117 + 24 <4 <3 <7 <4 <8 <7 <9 <3 <3 <7 T81 10-12-95 <140 86 + 29 <3 <3 <6 <4 <7 <6 <6 <4 <4 <5 11-08-95 119 + 46 242 + 29 <4 <4 <8 <4 <8 <6 <7 <4 <4 <5 12-08-95 260 + 50 259 + 31 <5 <4 <7 <4 <8 <6 <9 <3 <4 <6 (A) These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.

(B) These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample.

(o

/

4.a. 1 CRUSTACEA Blue Crab (pCi/kg, wet wei ht)

Sample Collection Site Date K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226

'D Ra-228 T81 12-19-95 1798 + 192 <25 <25 <61 <30 <49 <26 <26 846 + 32 4.a.2 FISH (T67: Snapper) (T81: Mixed Species) (pCi kg, wet weight)

Sample Collection Site Date K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 12-01-95 > 2870 + 15714 <15 <37 <18 <31 <15 <15 ND ND T81 12-18-95 2620 + 74 <6 <7 <15 <7 <14 <7 <7 ND ND 4.b.l BROADLEAF VEGETATION Brazilian Pepper ( Ci k , wet wei ht)

Sample Collection Site Date Be-7 K-40 I-131 Cs-134 Cs-137 'b-210 T40 10-12-95 2171 + 87 3830 + 141 <17 <10 349 + 12 ND 11-09-95 2946 + 94 2753 + 112 <15 <9 52+6 1027 + 304 12-08-95 1565 + 80 4010 + 134 <21 <10 62+7 ND T41 10-12-95 2737 + 93 5220 + 153 <15 <8 90+8 831 + 280 11-09-95 1996 + 78 5047 + 147 <15 <8 31+ 6 ND 12-08-95 877 + 57 4653 + 150 <19 <11 31+ 6 ND T67 10-13-95 1191 + 67 3539 + 128 <12 <8 <9 ND 11-09-95 1500 + 81 3482 + 141 <17 <11 <12 ND 12-08-95 1678 + 87 4145 + 148 <22 <10 <10 ND ND Non-detectable.

(o 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 & 4 ATTACHMENT C RESULTS FROM THE INTERLABORATORY COMPARISON PROGRAM 1995

FLORIDA DEPT. OF HRS EPA INTERLABORATORY CROSS-CHECK PROGRAM DATA January through June, 1995 Media Nuclide Collection Mon Day Yr EPA Known Units Normal.

Range Mean of Analyses N.DE K 'ction Level WATER Alpha 01 27 95 5 pCi/L 0.236 5.00 0.00 WATER Bet.a 01 27 95 5 pci/L 0,236 7.33 0.81 WATER Co-60 06 09 95 40 pCi/L 0.236 39.00 -0.35 WATER Zn-65 06 09 95 76 pCi/L 0.517 82.67 1.44 WATER Ba-133 06 09 95 79 pci/L 0,148 74.33 -1.01 WATER Cs-134 06 09 95 50 pCi/L 0.000 47.00 -1.04 WATER Cs-137 06 09 95 35 pCi/L 0.354 37.67 0.92 WATER H-3 03 10 95 7435 pCi/L 0 '93 7355.00 -0.19 WATER I-131 02 03 95 100 pCi/L 0 '18 97.00 -0.52 WATER Sr-89 Ol 13 95 20 pCi/L 0.354 14.33 -1.96 WATER Sr-90 01 13 95 15 pCi/L 0.236 10.33 -1.62 NOTES:

Normal.: Normalized range. As defined in "Environmental Radioactivity Laboratory Xntercomparison Studies Program Fiscal Year 1981 1982 ", Environmental Monitoring Systems Laboratory, U. S. Environmental Protection Agency, P. 0. 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.

FLORIDA DEPT OF HRS EPA INTERLABORATORY CROSS-CHECK PROGRAM DATA July through December, 1995 Media Nuclide Collection EPA Units Normal. Mean of N.D.K. Action Mon Day Yr Known Range Analyses Level FILTER Alpha 08 25 95 25 pCi/Fil 0.141 28.30 0.91 FXLTER Beta FILTER Cs-137 08 08 25 25 95 95 86.6 25 pCi/Fil pCi/Fil 0.396 0.000 79 '7 28.00

-1.22 1.04 FXLTER Sr-90 08 25 95 30 pCi/Fil 0.709 21.33 -3.00 1 MILK I-131 09 29 95 99 pCi/L 0.295 98.67 -0.06 MILK Cs-137 09 29 95 50 pCi/L 0.000 53.00 1 '4 0.70 MXLK K 09 29 95 1654 mg/L 0.306 1687.33 MILK Sr-89 09 29 95 20 pCi/L 0.945 12.00 -2077 MILK Sr-90 09 29 95 15 pCi/L 0.945 16.00 0.35 WATER Alpha 07 21 95 27.5 pCi/L 0.231 23.33 -1.05 WATER Alpha 10 27 95 51.2 pCi/L 0.120 24.90 -3.56 2 HATER Beta 07 21 95 19.4 pCi/L 0.567 23.60 1.45 WATER Beta 10 27 95 24.8 pCi/L 1.413 32.97 2.83 WATER Co-60 11 03 95 60 pCi/L 0.236 60,33 0.12 WATER Zn-65 11 03 95 125 pCi/L 0.409 134.67 1.29 WATER Ba-133 11 03 95 99 pCi/L 0.059 92.67 -1.10 HATER Cs-134 11 03 95 40 pci/L 0.118 37.33 -0.92 WATER Cs-137 11 03 95 49 pCi/L 0.354 54.00 1.73 WATER H-3 08 04 95 4872 pCi/L NDP WATER X-131 10 06'5 148 pCi/L 0.039 148.67 0.08 WATER Sr-89 07 14 95 20 pCi/L 0,591 8.00 -4.16 3 HATER Sr-90 07 14 95 8 pCi/L 0.118 9.33 0.46

NOTES:

Normal.: Normalized range. As defined in "Environmental Radioactivity Laboratory Xntercomparison Studies Program Fiscal Year 1981 1982", Environmental Monitoring Systems Laboratory, U. S. Environmental Protection Agency, P. O. Box 93478, Las Vegas, Nevada, 89193-3478.

EPA-600/4-81-004, February, 1981.

N.D.K.: Normalized deviation of the mean from the known value, as defined in EPA-600/4-81-004.

NDP: No data provided. No data was provided to EPA for inclusion in their report.

NA: Not available, Report containing this data has not yet been received from EPA, Las Vegas.

ACTXON LEVEL:

(1) Cause: Chemical recoveries too low and inconsistent.

Corrective Action: Try to improve recovery and consistency.

(2) Cause: Please see attached note from EPA.

Corrective Action: Try EPA's suggestions.

(3) Cause: Insufficient number of counts on sample.

Corrective Action: Count samples more time.

VNITED STATES ENVIRONMENTALPROTECTION AGENCY NATIONALEXPOSURE RESEARCH LABORATORY

. P.O. BOX 93478 i LAS VEGAS, NV 89193.3478 OFFICE OF RESEARCH AND DEVELOPMENT A note regarding the Gross Alpha portion of the October 27, 1995 Gross Alpha-Beta in Water Performance Evaluation Study:

Both the July 1995 and October 1995 Gross Alpha-Beta in Water Performance Evaluation (PE) Studies showed a significant difference between the grand average and the known value for the gross alpha. This strongly implies there is bias in the method.

Our research indicates that matrix differences between the salt solids used to prepare the calibration curve and the salts in the sample are the source of the bias.

The attached figure illustrates the changes in efficiency due to salt composition and nuclide energy. The bottom curve was prepared with serial dilutions of laboratory tap water. Laboratory tap water is also used to add variable amounts of dissolved solids to the

'E gross alpha/beta study samples. The second curve was prepared with serial dilutions of sodium sulfate solution. The top curve was prepared the same way as the second curve

.except that Am-241 was used as the alpha emitter. All the usual precautions apply. The curves reflect the efficiencies for our counter; the curves in the figure are illustrative only; and lastly, results for your laboratory may be different than shown in the figure.

At zero mass all the curves converge to the extent that the bias would not be noticeable in a PE study. As the mass of solids increases, the difference between the two Th-230 curves becomes pronounced. For sample masses between 30 and 40 mg, typical range for a 200 mL sample of the July 1995 or October 1995 study, the difference is between 50 to 70 percent.

To address the bias, we are recommending the procedure used in our laboratory. To a

'olume of sample equal to that used for analysis (100-150 mL) add 120 pCi of Th-230.

Acidify the sample with 20-40 mL of concentrated nitric acid and evaporate by the procedure attached to the PE study report sheet. The volume of PE,sample provided is sufficient to prepare triplicate 150 mL samples and duplicate spiked samples. Count the spikes until approximately 1600 counts above background are acquired to a maximum of 200 minutes. Background in this case will be that of the PE samples. Subtract the average count rate of the triplicate samples from the average count rate of the spikes and calculate the efficiency. Use this efficiency to calculate the concentration of gross alpha in the PE sample.

RecycledtRecyctaote ~ panted vntn vegetattte oil Based Inks on ttxt,e Recycted papet (40e'ostconsutner)

4 k

A'n alternate procedure. After counting the triplicates, redissolve/reslurry the solids of two of the samples in the planchet with dilute nitric acid (3-6M). Add the spike, mix well, redry and count the spikes. This technique, though simple on the surface, requires sufficient care so as not to lose sample volume, and that the Th-230 is thoroughly incorporated into the dissolved salts. We recommend this only for laboratories with a high degree of confidence in the analyst's ability to prepare the spikes by this technique.

You may use more or less spiked activity ifyou choose. The recommended activity of the spike and the maximum count time were determined to provide 5 percent precision at 95 percent confidence for the spike at an efficiency as low as 3 percent. For higher efficiencies the count time will be much shorter than 200 minutes. Additionally, we recommend several practice runs to gain experience with the technique you choose.

So, why not send out our laboratory tap water and have the participating laboratories prepare a curve? The tap water supplied to our laboratory varies in dissolved salt composition. This was observed during our verification of the July 1995 PE sample. Our QC samples showed a 40 percent bias when samples and spikes were quantified using a calibration curve. Repeat measurements demonstrated the bias was consistent and not due to analyst error. Therefore, preparing a curve with water from our laboratory does not guarantee that the bias will be eliminated.

Collectively these procedures are single point calibration techniques and are not prohibited by the approved methods. The curve concept was introduced in recognition of the variable dissolved solids of water in given geographical areas.

Ifyou have any questions or comments please call Stephen Pia at 702 798-2102.

0~

'i

ALPHA ATTENUATIONCURVES FOR RADQA TENNELEC GP COUNTER 0.2500

.0.2250

.Am-241 sulfa tes ystem 0.2000 V

0 h-2 30 ss ulfate system 0.1750 TH-230 nitrate syst em 0.1500 V 0.1 250 0

0.1 000 0

0.0750 """"'0 0.0500 0.0250 0.0000

0. 10 20 30, 40 50 60 70 80 90 100110120 Mg RESIDUAL SOLIDS EQUATION: Y = Ao + A(X+ A2X. + A X Th-230 sulfate Th-230 nitrate Ao = 0.2 I 99. 0.2016 A1 = -2.914E-3 -4.495 E-3 A2 = 1.8422E-5 3.9 I8E-5 A3 = -4.4449E-8 -1.154E-7

0 ~

Ig v

(e E

'