L-95-113, 1994 Annual Radiological Environ Operating Rept St Lucie Plant Units 1 & 2

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1994 Annual Radiological Environ Operating Rept St Lucie Plant Units 1 & 2
ML17309A784
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 12/31/1994
From: Sager D
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-95-113, NUDOCS 9504250267
Download: ML17309A784 (90)


Text

PH.IC)R.I EV (ACCELERATED RIDS PROCESSING)

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9504250267 DOC.DATE: 94/12/31 NOTARIZED: NO FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power

& Light Co.

50-389 St. Lucie Plant, Unit 2, Florida Power

& Light Co.

AUTH.NAME AUTHOR AFFILIATION SAGER,D.A.

Florida Power &,"'Light Co.

RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000335 05000389

SUBJECT:

"1994 Annual Radiological Environ Operating Rept St Lucie Plant Units 1

& 2." W/950419 ltr.

DISTRIBUTION CODE:

IEZSD COPIES RECEIVED:LTR t ENCL I

SIZE:

0 +

TITLE: Environmental Monitoring Rept (per Tech Specs)

NOTES RECIPIENT ID CODE/NAME PD2-1 LA NORRIS,J INTERNAL: ACRS NRR/ADAR/PDLR RGN2 FILE EXTERNAL: LITCO AKERS, D COPIES LTTR ENCL 3

3 1

1 1

1 1

1 1

1 1

1 RECIPIENT ID CODE/NAME PD2-1 PD E CENTER 0

RG PB NRC PDR COPIES LTTR ENCL 1

1 1,

1 1

1 1

1 NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACTTHE DOCUMENTCONTROL DESK, ROOM PI-37 (EXT. 504-2083 ) TO ELIMINATEYOUR NAMEFROM DISTRIBUTIONLISTS I'OR DOCUMENTS YOU DON"I'EED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 12 ENCL 12

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c Florida Power & Light Company, P.O. Box 128, Fort Pierce, FL 34954-0128 April 19, 1995 L-95-113 10 CFR 50.4 10 CFR 50.36 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.

C.

20555 RE:

St. Lucie Units 1 and 2

Docket No. 50-335 and 50-389 Annual Radiological Environmental 0 eratin Re ort for Calendar Year 1994 The Attached report is being submitted pursuant to Technical Speci fication

6. 9. 1.8.

The Annual Radiological Environmental Operating Report provides information summaries and analytical results of the Radiological Environmental Monitoring Program (REMP) for the calendar year 1994.

Please contact us if there are any questions about this submittal.

Very truly yours, CW~~ ~

D. A. Sager Vice President St. Lucie Plant DAS/GRM cc:

Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Xnspector, USNRC, St. Lucie Plant O

r~ w)VU 9504250267 94i23i PDR ADOCK 05000335I, PDR an FPL Group company

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1994

..9504250267 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ST.

LUCIE PLANT UNITS 1 8<< 2 LICENSE NOS.

DPR-67, NPF-16 DOCKET NOS. 50-335, 50-389 Data Submitted By:

Florida DHRS Repor t Prepar ed:WZ+8 Repor t Reviewed:

t, 4

N f

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gh I

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ST.

LUCIE PLANT - UNITS 1 Ec 2

TABLE OF CONTENTS DESCRIPTION PAGE Introduction Radiological Environmental Monitoring Program Discussion and Interpretation of Results Environmental Radiological Monitoring Program Annual Summary, TABLE 1 Deviations/Missing Data TABLE 1A Analyses with LLDs Above Table 4.12-1 Detection Capabilities TABLE 1B Land Use Census TABLE 2 Key to Sample Locations ATTACHMENT A Radiological Surveillance of Florida Power and Light Company's St. Lucie Site First Quarter, 1994 Second Quarter, 1994 Third Quarter, 1994 Fourth Quarter, 1994 ATTACHMENT B Results from the Interlaboratory Comparison

Program, 1994 ATTACHMENT C NP3:1/RAOENVOP.PSL

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ST ~ LUCIE PLANT - UNITS 1 5: 2 INTRODUCTION This report is submitted pursuant to Specification 6.9.1.8 of St.

Lucie Unit 1 and St. Lucie Unit 2 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 1

and Unit 2

Technical Specifications.

II.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM A.

~Pur ose 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 for the St.

Lucie Plant is conducted pursuant to the St. Lucie Unit 1

and St. Lucie Unit 2 Offsite Dose Calculation Manual (ODCM)

Control 3i4.12.1.

1.

Sample Locations, Types and Frequencies:

a.

Direct radiation gamma exposure rate is monitored continuously at 27 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, 'ross

beta, and gamma isotopic measurements.

HP3:1/RAOENVOP.PSL

1 1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ST.

LUCIE PLANT - UNITS 1 Sc 2

c.

Surface water samples are collected from two locations.

Samples are collected and analyzed weekly and monthly respectively.

Analyses include gamma isotopic and tritium measurements.

Shoreline sediment samples are collected from two 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.

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 St. Lucie Plant is conducted by the State of Florida, Department of Health and Rehabilitative Services (HRS).

Samples are collected and analyzed by HRS personnel.

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

C.

Anal tical Results Table i, Environmental Radicle ical Monitorin

~pro ram Annual

~Summer 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.

HP3:1/RADENVOP.PSL (2)

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ST.

LUCIE PLANT - UNITS 1 R 2 D.

Land Use Census A land use census out to a distance of 5 miles radius from the St.

Lucie 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

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

E.

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.

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 Re ortin of Results The Annual Radiological Environmental Operating Report contains the summaries, interpretations and information required by the St.

Lucie Plant, ODCM.

Table 1 provides a

summary of the measurements made for the nuclides required by

ODCM, Table 4.12-1, 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, Ra-228, and Be-7 which are common in the Florida environment.

NP3:1/RADENVOP.PSL (3)

4

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ST.

LUCIE PLANT - UNITS 1

& 2 B.

Inter retation of Results Direct Radiation:

The results for direct radiation monitoring are consistent with past measurements for the specified locations.

The exposure rate data shows no indication of any trends attributed to effluents from the plant.

The measured exposure rates are consistent with exposure rates that were observed during the preoperational surveillance program.

Direct radiation monitoring results are summarized in Table 1.

2

~

Air Particulates/Radioiodine:

The results for radioactive air particulate and radioiodine monitoring are consistent with past measurements and indicate no trends attributed to plant effluents.

All samples for radioiodine yielded no detectable I-131.

Gamma isotopic measurements yielded no indication of any nuclides attributed to station operation.

The results for air particulate/radioiodine samples are consistent with measurements which were made during the preoperational surveillance program.

Air particulate and radioiodine monitoring results are summarized in Table 1.

3.

Surface Water:

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

Tritium was reported as present in one of the weekly samples collected from Site H-15 and one of the monthly samples collected at the control location, H-59.

The highest concentration, which was at the control location, was less than 1% of the reporting level specified by the Off-Site Dose Calcuation Manual, Table 3.12-2

~

No other nuclides attributed to station operation were detected.

Results for surface water samples are summarized in Table l.

4.

Waterborne Sediment and Food Products:

The results for radioactivity measurements in waterborne sediment, fish and crustacea samples are consistent with past measurements and with measurements made during the preoperational surveillance program.

There were no indications of any nuclides attributed to plant effluents.

Results for the waterborne sediment, fish and crustacea samples are summarized in Table 1

~

HP3:1/RADENVOP.PSL (4)

f,

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ST.

LUCIE PLANT - UNITS 1

& 2 5.

Broad Leaf Vegetation:

The results for radioactivity measurements in broad leaf vegetation are consistent with past measurements and with measurements made during the preoperational surveillance program.

There were no indications of any nuclides attributed to plant effluents.

Results for the broad leaf vegetation samples are summarized in Table 1.

C.

Conclusions The data obtained through the St. Lucie Plant Radiological Environmental Monitoring Program verifies that the levels of radiation and concentrations of radioactive materials in environmental

samples, representing the highest potential exposure pathways to members of the public, are not being increased.

The measurements verify that the dose or dose commitment to members of the public, due to operation of St.

Lucie Units 1

8 2, during the surveillance

year, are well within "as low as reasonably achievable (ALARA)" criteria established by 10 CFR 50, Appendix I.

HP3:1/RADEHVOP.PSL (5)

Pa of 8

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility St. Lucie Units 1

E 2

, Docket No(s).

50-335

&. 50-389 Location of Facility St. Lucie Florida

, Reporting Period Janua 1 - December 31 (County, State) 1994 PATHWAY:

DIRECT RADIATION SAMPLES COLLECTED:

TLD UNITS:

MICRO - R/hr Type and Total Number of Analyses Performed Lower Limit of Detection'LLD)

All Indicator Locations Mean (f)

Range Mean f b Distance Direction Range Location with Highest Annual Mean Name'ontrol Locations Mean (f)b Range Exposure

Rate, 102~

5.00 (98/98) 4.33 6.53 NW-10 10 mi.,

NW

6. 39 (4/4) 6.22 6.53
5. 51 (4/4) 5.29 5.70 Number of Nonroutine Reported Measurements

=

0 HP3:1/RADENVOP.PSL

4

of 8

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAT

SUMMARY

Name of Facility St. Lucie Units 1

E 2

, Docket No(s).

50-335

&, 50-389 Location of Facility St. Lucie Florida

, Reporting Period Janua 1 - December 31 (County, State) 1994 PATHWAY:

AIRBORNE SAMPLES COLLECTED:

RADIOIODINE AND PARTICULATES UNITS:

PICO Ci/M Type and Total Number of Analyses Performed Lower Limit of Detection'LLD)

All Indicator Locations Mean (f)

Range Distance 6

Direction Range Location with Highest Annual Mean Name'ean f b Control Locations Mean (f)b Range

"'I 258 0.024

<MDA

<MDA Gross

Beta, 258 Composite Gamma
Isotopic, 20 0.0025 0.012 (201/206) 0.003 0.078 H-08 6 mi.,

WNW 0.014 (52/52) 0.005 0.078 0.011 (51/52) 0.005 0.029

'Be 210pb 134Cs 137Cs 0.0052 0.00069 0.00066 0.1132 (16/16)

H-34 0.0799 0.1659 20.5 N

0.0120 (15/16)

H-8 0.0055 0.0161 6 mi.,

WNW

<MDA

<MDA

0. 1242 (4/4) 0.0990 0 '571
0. 01413 (4/4) 0.0113 0.0161
0. 1058 (4/4) 0 '824 0.1418 0. 0103 (4/4) 0.0089

- 0.0120

<MDA

<MDA Number of Nonroutine Reported Measurements

=

0 HP3:1/RADENVOP.PSL

T 1

of 8

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility St. Lucie Units 1

& 2

, Docket No(s).

50-335 E 50-389 Location of Facility St. Lucie Florida

, Reporting Period Janua 1

December 31 (County, State) 1994 PATHWAY:

WATERBORNE SAMPLES COLLECTED:

SURFACE WATER UNITS:

PICO Ci/LITER Type and Total Number of Analyses Performed Lower Limit of Detection'LLD)

All Indicator Locations

. Mean (f)

Range Mean f b Distance Direction Range Location with Highest Annual Mean Name'ontrol Locations Mean (f)"

Range Tritium, 64 Gamma

Isotopic, 64 "Mn "Fe ssCo 60Co 6sZn "Zr-Nb 131I 134Cs 137CS woBa-La 230 60 89 (1/52) 240 (52/52) 199 - 401

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA H-15 89 (1/52)

<1 mi., ENE/E/ESE H-15 240 (52/52)

<1 mi., ENE/E/ESE 199 - 401 92 (1/12) 320 (12/12) 200

- 404

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA Number of Nonroutine Reported Measurements

=

0 HP3: 1/RADENVOP. PSL

t)

Pa of 8

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility St. Lucie Units 1 6 2

, Docket No(s).

50-335

& 50-389 Location of Facility St. Lucie Florida, Reporting Period Janua 1 - December 31 1994 (County, State)

PATHWAY:

WATERBORNE SAMPLES COLLECTED:

SHORELINE SEDIMENT UNITS:

PICO Ci/Kg, DRY Type and Total Number of Analyses Performed Lower Limit of Detection'LLD)

All Indicator Locations Mean (f)

Range Distance 6

Direction Range Location with Highest Annual Mean Name Mean f b Control Locations Mean (f)

Range Gamma

Isotopic, 4

40K

>>6Ra "Co 60Co 134Cs 137Cs 140 52 12 14 12 789 (2/2) 361 1217 330 (2/2) 188 471 216 (1/2)

<MDA

<MDA

<MDA

<MDA H-15

<1 mi. ENE/E/ESE H-15

<1 mi. ENE/E/ESE H-15

<1 mi. ENE/E/ESE 789 (2/2) 361 1217 330 (2/2) 188

- 471 216 (1/2) 548 (2/2) 277 - 819 248 (2/2) 203 - 293 107 (2/2)68-146

<MDA

<MDA

<MDA

<MDA Number of Nonroutine Reported Measurements

=

0 HP3: 1/RADENVOP. PSL

Pa of 8

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility St. Lucie Units 1

& 2

, Docket No(s).

50-335 E 50-389 Location of Facility St. Lucie Florida, Reporting Period Janua 1 - December 31 (County, State) 1994 PATHWAY:

INGESTION SAMPLES COLLECTED:

CRUSTACEA UNITS:

PICO Ci/Kg, WET Type and To'tal Number of Analyses Performed Lower Limit of Detection'LLD)

All Indicator Locations Mean (f)

Range Location with Highest Annual Mean Name Mean f b Distance Direction Range Control Locations Mean (f)

Range Gamma

Isotopic, 4

40K 228Ra 226Ra "Mn "Fe 58Co 60Co Zn 4Cs 137Cs 130 16 19 17 1293 (2/2) 865 - 1721

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA H-15 1293 (2/2)

<1 mi., ENE/E/ESE 865 1721 1545 (2/2) 1340 1749 172 (1/2) 155 (1/2)

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA Number of Nonroutine Reported Measurements

=

0 HP3: 1/RADENVOP

. PSL

Pa of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility St. Lucie Units 1

& 2, Docket No(s).

50-335

&, 50-389 Location of Facility St. Lucie Florida

, Reporting Period Janua 1 - December 31 (County, State) 1994 PATHWAY:

INGESTION SAMPLES COLLECTED:

FISH UNITS:

PICO Ci/Kg, WET Type and To'tal Number of Analyses Performed Lower Limit of Detection'LLD)

All Indicator Locations Mean (f)

Range Distance Direction Range Location with Highest Annual Mean Name'ean f

Control Locations Mean (f)

Range Gamma

Isotopic, 4

40K "Mn "Fe Co 60Co Zn 134 Cs 137CS 130 16 10 17 2044 (2/2) 1912 2176

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA H-15 2044 (2/2)

<1 mi., ENE/E/ESE 1912 2176 2827 (2/2) 2706 - 2948

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA Number of Nonroutine Reported Measurements

=

0 HP3:1/RADENVOP.PSL

Pa of 8

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility St. Lucie Units 1

E 2

, Docket No(s).

50-335

& 50-389 Location of Facility St. Lucie Florida

, Reporting Period Janua 1 - December 31 1994 (County, State)

PATHWAY:

INGESTION SAMPLES COLLECTED:

BROAD LEAF VEGETATION UNITS:

PICO Ci/Kg, WET Type and To'tal Number of Analyses Performed Lower Limit of Detection'LLD)

All Indicator Locations Mean (f)

Range Distance t Direction Range Location with Highest Annual Mean Name'ean f

b Control Locations Mean (f)

Range Gamma

Isotopic, 36

'Be "K

210pb 131 z 134 Cs 3~Cs 71 100 665 (24/24) 372 1228 2996 (24/24) 2052 5042 566 (3/24) 433 695

<MDA

<MDA

<MDA H-51 1 mi.,

N/NNW H-52 1 mi., S/SSE H-52 1 mi.,

S/SSE 739 (12/12) 372 1228 3326 (12/12) 2312 - 5042 695 (1/12) 669 (12/12) 516 - 788 2647 (12/12) 1339 - 4123

<MDA

<MDA

<MDA

<MDA Number of Nonroutine Reported Measurements

=

0 HP3:1/RADENVOP.PSL

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ST.

LUCIE PLANT, UNITS 1

& 2 TABLE 1 Page 8 of 8

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility St. Lucie Units 1

5; 2 Docket No.(s) 50-335 and 50-389 Location of Facility St. Lucie Florida (County, State)

Reporting Period Janua 1 - December 31 1994 NOTES a.

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

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 typically based upon the average net response of two TLDs. (Thermoluminescent dosimeters)

MDA refers to minimum detectable activity.

HP3:1/RADENVOP.PSL

J t

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ST.

LUCIE PLANT, UNITS 1 Ec 2

TABLE 1A DEVIATIONS/MISSING DATA Page 1 of 2 A)

Pathway:

Direct Exposure TLDs Location (Section 8 Approx Miles)

SW-2 SSW-10 SW-10 W-2 WSW-10 WNW-10 Date 12/7-93 3/15/94 12/7/93

- 3/15/94 3/15/94

- 6/7/94 6/7/94 9/20/94 6/7/94 9/20/94 9/20/94 12/6/94 Deviation:

Description of Problem:

Failure to provide continuous monitoring.

TLDs missing upong attempted collection.

Corrective Action:

Replaced missing TLDs.

B)

Pathway:

Location:

Date:

Deviation:

Description of Problem:

Corrective Action:

Airborne Particulates and Xodines H-30, 2 miles W

10/23/94 to 11/01/94 Failure to provide continuous air sampling.

Power failure, sample duration of 121 hours0.0014 days <br />0.0336 hours <br />2.000661e-4 weeks <br />4.60405e-5 months <br /> out of the 145 hour0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br /> sampling period.

Reestablished power upon discovery of outage.

HP3: 1/RADENVOP. PSL

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ST.

LUCIE PLANT, UNITS 1 Zc 2 TABLE 1A DEVIATIONS/MISSING DATA Page 2 of 2 C)

Pathway:

Location:

Date:

Deviation:

Description of Problem:

Corrective Action:

Airborne Particulates E Iodines H-14, 1 miles SE 10/25/94 to 11/21/94 Failure to provide continuous air sampling.

Extended power failure.

Power failed approxi-mately 3 days into the 10/24/95 to 11/1/94

, sampling period and was not restored until about 2

days into the 11/16/94'o 11/21/94 sampling period.

Restarted air sampling equipment upon power restoration.

HP3:1/RADENVOP.PSL

I P

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ST.

LUCIE PLANT, UNITS 1

& 2 TABLE 1B ANALYSES WITH LLDs ABOVE TABLE 4.12-1 DETECTION CAPABILITIES 1/1/94 - 12/31/94 The values specified in Table 4.12-1, Detection Capabilities, were achieved for all samples.

HP3: 1/RADENVOP. PSL

I

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ST.

LUCIE PLANT, UNITS 1 Ec 2

TABLE 2 LAND USE CENSUS Distance to Nearest a

b Sector 5/94 Milk (c)

Animal 5/94 Residence 5/94 Garden (d)

N NE ENE 0

(e) 0 ESE SE SSE SSW SW WSW 0

L (f)

L L

4.1/257 4.5/263 L

0 1.5/141 (g) 3.3/153 (g) 3.2/191 2.2/213 1.9/236 1.9/245

(}1) 1.9/260 2.3/281 3.5/304 L (g)

L 4.2/182 3.8/200 1.9/234 1.9/253 2.1/275 2.6/290 L

HP3:1/RADENVOP.PSL

0

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ST.

LUCIE PLANT, UNITS 1 Ec 2

TABLE 2 LAND USE CENSUS NOTES a.

All categories surveyed out to 5 miles radius from the St.

Lucie Plant.

b.

The following format is used to denote the location:

distance (miles) /bearing (degrees)

For example, a residence located in the southeast sector at a distance of 1.5 miles bearing 141 degrees is recorded as 1.5/141.

c.

Potential milk animal locations.

All locations specified have been verified to be not producing milk for human consumption.

d.

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

e.

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

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

g.

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

SSE

- Fire Station, 1.8/149 NNW - Lifeguard station at beach, 4.6/342 SE

- Lifeguard station at beach, 1.1/132 h.

Several residences in this sector are located approximately 1.9 miles from the St. Lucie Plant.

HP3: 1/RADENVOP. PSL

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ST.

LUCIE PLANT, UNITS 1 Sc 2

ATTACHMENT A KEY TO SAMPLE LOCATIONS HP3:1/RADENVOP.PSL

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=

V. (',AVi

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ST.

LUCIE PLANT, UNITS 1 k 2 H-32 10-MILES WNW-10 NW-10 Ft.

PIERCE S-MILES ATLANTIC OCEAN W-Xo H-08 WNW-2 W-2 H-30 WSW-2 2-MILES ST.

LUCIE M ~~NT SSW-2 WSW 10 WQV PORT St.

LUCZE SW-5 S-5 SSE-5 SW-10 SSW-5 SSW-10 S/SSE-10 SE-10 St. Lucie Sampling locations S-10 a

STUART H-12 HP3:1/RADENVOP.PSL

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ST.

LUCIE PLANT, UNITS 1

& 2 ATTACHMENT A Page 1 of 4 PATHWAY:

DIRECT RADIATION SAMPLES COLLECTED:

TLD SAMPLE COLLECTION FREQUENCY:

QUARTERLY Location Name Direction Sector Approximate Distance miles Descri tion N-1 NNW-5 NNW-10 NW-5 NW-10 WNW-2 WNW-5 WNW-10

-2 5

-10 WSW-2 WSW-5 WSW-10 SW-2 SW-5 SW-10 SSW-2 SSW-5 SSW-10 S-5 S-10 S/SSE-10 SSE-5 SSE-10 SE-1 N

NNW NNW NW NW WNW WNW WNW W

W W

WSW WSW WSW SW SW SW SSW SSW SSW S

S SSE SSE SSE SE 5

9 6

10 3

5 10 2

5 9

2 5

10 2

5 10 3

6 8

5 10 10 5

10 1

A1A, North of Blind Creek South of Pete Stone Creek Coast Guard Station Indian River Dr., at Rio Vista Dr.

S.R.

68 at S.R.

607

'Cemetery South of 7107 Indian River Dr.

U.S.

1 at S.R.

712 S.R.

70, West of Turnpike 7609 Indian River Drive Oleander and Sager Street Interstate 95 at S.R.

709 8503 Indian River Dr.

Prima Vista at Yacht Club Del Rio at Davis Street 9207 Indian River Drive U.S.

1 at Village Green Dr.

Port St. Lucie Blvd. at Cairo Rd.

10307 Indian River Drive U.S.

1 at Port St. Lucie Blvd.

Pine Valley at Westmoreland Rd.

13179 Indian River Drive U.S.

1 at S.RE 714 Indian River Dr. at Quail Run Lane Entrance to Nettles Island Elliot Museum South of Cooling Canal Control:

H-32 19 University of Florida IFAS Vero Beach HP3: 1/RADENVOP. PSL

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ST.

LUCIE PLANT, UNITS 1

&, 2 ATTACHMENT A Page 2 of 4 PATHWAY:

AIRBORNE SAMPLES COLLECTED:

RADIOIODINE AND PARTICULATES SAMPLE COLLECTION FREQUENCY:

WEEKLY Location Name Direction Sector Approximate Distance miles Descri tion H-08 H-14 H-30 H-34 WNW SE W

N 6

1 2

0.5 FPL Substation, Weatherby Rd.

On-Site, Near South Property Line Power Line, 7609 Indian River Drive On-Site at Meteorology Tower Control:

12 FPL Substation, SR-76 Stuart HP3: 1/RADENVOP. PSL

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ST.

LUCIE PLANT, UNITS 1

& 2 ATTACHMENT A

~ Page 3 of 4 PATHWAY:

WATERBORNE SAMPLES COLLECTED:

SURFACE WATER (OCEAN)

SAMPLE COLLECTION FREQUENCY:

H-15 WEEKLY, H-59 MONTHLY Location Name Direction Sector Approximate Distance miles Descri tion H-15 ENE/E/SSE Atlantic

Ocean, Public Beaches East Side A1A Control:

H-59 S/SSE 10-20 South End, Hutchinson Island PLES COLLECTED:

SHORELINE SEDIMENT AMPLE COLLECTION FREQUENCY:

SEMI-ANNUALLY Location Name Approximate Direction Distance Descri tion H-15 ENE/E/ESE Atlantic Ocean Public Beaches East Side AlA Control:

H-59 S/SSE 10-20 South End, Hutchinson Island HP3:1/RADENVOP.PSL

It 1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ST.

LUCIE PLANT, UNITS 1 5:

2 ATTACHMENT A.

Page 4 of 4 PATHWAY:

INGESTION SAMPLES COLLECTED:

CRUSTACEA AND FISH SAMPLE COLLECTION FREQUENCY:

SEMI-ANNUALLY Location Name Approximate Direction Distance Descri tion H-15 ENE/E/ESE Ocean Side, Vicinityof St. Lucie Plant Control:

H-59 S/SSE 10-20 South End, Hutchinson Island PLES COLLECTED:

BROAD LEAF VEGETATION PLE COLLECTION FREQUENCY:

MONTHLY Location Name H-51 H-52 Direction Sector N/NNW S/SSE Approximate Distance Descri tion Off-site Near North Property Line Off-Site Near South Property Line Control:

H-59 S/SSE 10-20 South End, Hutchinson Island HP3: 1/RADENVOP. PSL

1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ST.

LUCIE PLANT, UNITS 1 6c 2

ATTACHMENT B 1994 RADIOLOGICAL SURVEILLANCE REPORTS First Quarter, 1994 Second Quarter, 1994 Third Quarter, 1994 Fourth Quarter, 1994 HP3: 1/RADENVOP. PSL

RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S ST.'LUCIE SITE First Quarter, 1994 Office of Radiation Control Florida Department of Health and Rehabilitative Services

ST.

LUCIE SITE Technical Specifications Sampling First Quarter, 1994 Samle T

e Collection Fre enc Locations Number of

1. Direct Radiation
2. Airborne 2.a Air Iodines 2.b Air Particulates Quarterly Weekly Weekly 27 25 65 69*
3. Waterborne 3.a Surface Water 3.b Shoreline Sediment Weekly Monthly Semiannually 13 33*
4. Ingestion 4.a Fish and Invertebrates 4.a.l Crustacea 4.a.2 Fish Semiannually Semiannually 2'2 4.b Food Products 4.b.1 Broadleaf Vegetation Monthly Total:

191

  • 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.

DIREC RADIATION

TLDs

m cro-R hour Sample Site Deployment 12-07-93 Collection 03-15-94 N-1 4.98

+ 0. 14 NNW-5 NNW-10 4.99

+ 0.15 4.94

+ 0.13 NW-5 NW-10 5.02

+ 0.15 6.22

+ 0.18 WNW-2 WNW-5 WNW-10 4.88

+ 0.14 4.99

+ 0.17 5;59

+ 0.17 W-2 (A) 6.23

+ 0.37 W-5 5.20

+ 0.16 W-10 5.06

+ 0.16 WSW-2 WSW-5 WSW-10 4.84

+ 0.15 5.26

+ 0.16 4'3

+

0'3 0

'SW-2 SW-5 SW-10 (B) 5.86

+ 0.15 4.87

+ 0.13 SSW-2 4.70

+ 0.13 SSW-5 5.19

+ 0.18 SSW-10 (B)

S-5 S-10 4.74

+ 0.14 4.91

+ 0.13 S/SSE-10 SSE-5 SSE-10 4.76

+ 0.14 4.69

+ 0.13 4.86

+ 0.13 SE-1 H-32 4.62

+ 0.14 5.36

+ 0.16 (A)

The empty holder for the dosimeter at site W-2 was found lying on the ground on 02-16-94.

A new dosimeter was deployed here on 02-22-94 at a slightly different location in an attempt to reduce the frequency of vandalism being experienced here.

(B)

The dosimeters for site SW-2 and site SSW-10 were missing when collection was attempted.

2.a IODINE-131 IN WEEKLY AIR FILTERS

Ci m3 Collection Date H08 H12 Sam le Site H14 H30 H34 01-04-94 01-11-94 01-19-94 01-25-94

<0. 02

<0. 02

<0.02

<0.01

<0. 02

<0. 02

<0. 02

<0 ~ 02

<0. 02

<0. 02

<0. 02

<0.02

<0'2

<0.02

<0.02

<0.02

,<0.02

<0.02

<0.02

<0.02 02-02-94 02-08-94 02-,16-94 02-22-94

<0. 02

<0. 03

<0.01

<0.02

<0.01

<0.03

<0.01

<0.02

<0.01

<0.04

<0.01

<0.02

<0.01

<0.02

<0.01

<0.02

<0.01

<0.04

<0.01

<0.02 03-01-94 03-07-94 03-14-94 03-21-94 03-28-94

<0.01

<0.02

<0.02

<0.02

<0.01

<0.01

<0.02

<0.02

<0.02

<0.01

<0.01

<0.01

<0.01

<0.02

<0.01

<0.01

<0.01

<0.01

<0.02

<0.01

<0.01

<0.01

<0.02

<0.02

<0.01

2.b AIR PARTICULATES

GROSS BETA

Ci m3 0

Collection Date H08 H12 Sam le Site H14 H30 H34 01-04-94 01-11-94 01-19-94 01-25-94 02-02-94 02-08-94 02-16-94 02-22-94 03-01-94 03-07-94 03-14-94 03-21-94 03-28-94 0.

0 ~

0.

0 ~

0.

0.

0 ~

0 ~

0 ~

0 ~

0 ~

0.

0.

005

+

012

+

010

+

078

+

007

+

012

+

006

+

015

+

013

+

012

+

012

+

016

+

015

+

0.002 0.002 0.002 0.004 0.002 0.002 0.002 0.002 0 '02 0 '02 0.002 0.002 0.002 0.006

+

0.009

+

0.010

+

0.013

+

0.009

+

0.011

+

0.015

+

0.006

+

0.010

+

0.015

+

0.010

+

0.020

+

0.013

+

0.002 0.002 0.002 0.002 0.002 0.002 0.002 0.002 0'02 0.002 0.002 0'02 0.002 0.009

+

0.006

+

0.012

+

0.014

+

  • 0.009

+

  • 0.011 +
  • 0.009 +
  • 0.007 +

0.008

+

0.013

+

0.011

+

0.017

+

0.014

+

0. 002
0. 002 0.002 0.002 0.002 0.003 0.002 0.002 0 '02 0.002 0.002 0 '02 0.002 I

0.011 0.010 0.009 0.014 0.009 0.014 0.016 0.020 0 '09 0.011 0.011 0.016 0.014

+ 0'02

+ 0.002

+ 0.002

+ 0.002

+ 0.002

+ 0.002

+ 0 '02

+ 0.003

+

0 '02

+ 0 '02

+

0 '02

+ 0'02

+ 0 '02 0.008

+ 0.002 0.012

+ 0.002 0.010

+ 0.002 0.020

+

0.003'.010

+ 0.002 0.015

+ 0.003 0.011

+ 0.002 0.007

+ 0.002 0.009

+ 0.002 0.014

+ 0.002 0.012

+ 0.002 0.018

+ 0.002 0.016

+ 0.002 Means:

0.016

+ 0.001 0.011

+ 0.001

  • NRC split samples.

0.011

+ 0.001 0.013

+ 0 F 001 0.012

+ 0.001 2.b AIR PARTICULATES

GAMMA SCANS OF UARTERLY COMPOSITES

Ci m3 First Quarter, 1994 Sample Site H08 H12 H14 H30 H34 Be-7 0.1386

+

0. 1418

+

0. 1294

+

0.1659

+

0 ~ 1571

+

0.0102 0.0103 0.0090 0 '103 0.0095 K-40

<0. 0189

<0.0189

<0.0182

<0.0170

<0.0201 Cs-134

,<0.0006

<0.0007

<0.0007

<0.0009

<0.0008 Cs-137

<0.0010

<0.0009

<0.0005

<0.0008

<0.0007 Pb-210 A

0 ~ 0145

+ 0. 0031 0.0089

+ 0.0033 0.0137

+ 0.0033 0.0141

+ 0.0024 0.0151

+ 0.0030 (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 this group of samples, we will be reporting the Pb-210 results.

3.a SURFACE MATER

Ci l Sample Collection Site Date H-3 I

Zr-95

=Ba-140 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 (B)

H15 01-05-94

<135 401

+ 18

<2

<2 01-11-94

<134 259

+ 43

<5

<5 01-19-94

<130 292

+ 22

<2

<2 01-26-94

<129 276

+ 40

<4

<4

<4

<2

<11

<7

<4

<3

<12

<7

<4

<3

<13

<5

<4

<4

<10

<8

<3

<7

<2

<5

<2

<5

<2

<5

<2

<3

<2

<4

<2

<7

<4

<12 02-03-94 02-07-94 02-16-94 02-22-94

<131 234

+ 42

<4

. <4

<131 335

+ 48

<6

<4

<137 304

+ 42

<4

<3

<137 288

+ 31

<2

<3

<11

<7

<10

<9

<11

<6

<9

<8

<9

<5

<7

<6

<5

<4

<6

<4

<7

<8

<4

<3

<5

<5

<4

<3

<4

<4

<4

<3

<7

<9

<8

<6 03-02-94 03-08-94 03-15-94 03-22-94 03-28-94

<146

<135

<134

<134

<133 303

+ 44 206

+ 34 313

+ 36 119

+ 34 338

+ 36

<4

<3

<4

<3

<3

<4

<4

<5

<4

<3

<7

<6

<6'4

<9

<5

<7

<8

<9

<5

<8

<6

<8

<4

<5

<6

<7

<5

<7

<4

<4

<5

<4

<4

<4 1

<4

<4

<5

<4

<4

<6

<5

<6

<4

<5 H59 01-05-94

<135 343

+ 39

<4

<4 02-03-94 92

+ 43 200

+ 42

<4

<4 03-02-94

<135 320

+ 29

<3

<3

<7

<6

<6

<4

<6

<4

<4

<7

<7

<10

<8

<8

<7

<6

- <4

<4

<4

<3

<5

<5

<4

<6

<5

<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.

0 3.b SEDIMENT

Ci k dr wei ht Sample Collection

.Site Date Be-7 K-40 I

Co-58 Co-60 Cs-134 Cs-137 Ra-226 Th-232 H15*

02-07-94

<56 H59 02-09-94

<50

NRC split sample.

361

+ 54

<6 277

+ 40

<7

<7

<8

<7

<8

<7

<7 188

+ 11 203

+ 11 ND 68

+ 15 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 Ce-134 Ce-137 Ra-226 Ra-228 H15 02-16-94 1721

+ 249

<20

<25

<44

<37

<61

<34

<23 H59 02-08-94 1749

+ 190

<21

<20

<39

<30

<45

<22

<28 ND ND ND 172

+ 33 4.a.2 FISH

H15:

Shee shead H59:

S anish Mackerel

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 H15 02-07-94 2176

+ 320

<24

<31

<50

<41

<74

<34

<37 ND ND H59 02-08-94 2948

+ 242

<14

<18

<48

<29

<49

<26

<23 ND ND ND Non-detectable.

P I

0

4.b.1 BROADLEAF VEGETATION

Man rove

Ci k wet wei ht Sample Collection Site Date Be-7 K-4 0 I-131 Cs-134 Cs-137 H51 01-05-94 372

+ 50 2576

+ 128

<13 02-03-94 745

+ 57 2052

+ 131

<9 03-02-94 803

+ 61 2365

+ 117

<10

<10

<10

<11

<10

<8

<9 H52 01-05-94 525

+ 61 3612

+ 165

<15

<13

<9 02-03-94 03-02-94 658

+ 65 557

+ 53 2891

+ 167

<10 2312

+ 130

<11

<11

<10

<12

<12 H59 01-05-94 569

+ 54 2669

+ 130

<13

<11

<10 02-03-94 03-02-94 653

+ 57 2216

+ 134

<10 788

+ 70 2186

+ 110

<9

<11

<8

<11

<9

RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER 'AND LIGHT COMPANY '

ST.

LUCIE SITE Second Quarter, 1994 Office of Radiation Control Flarida Department of Health and Rehabilitative Services

ST.

LUCIE SITE Technical Specifications Sampling Second Quarter, 1994 Sam le T e

Collection Fre uenc Locations Sam led Number of Sam les

1. Direct Radiation Quarterly 27 26
2. Airborne 2.a Air Iodines 2.b Air Particulates Weekly Weekly 65 69*
3. Waterborne 3.a Surface Water 3.b Shoreline Sediment Weekly Monthly Semiannually 13 3

0

4. Ingestion 4.a Fish and Invertebrates 4.a.1 Crustacea 4.a.2 Fish Semiannually Semiannually 4.b Food Products 4.b.l Broadleaf Vegetation Monthly Total:

185

  • 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 03-15-94 Site Collection 06-07-94 N-1 4.99

+ 0.14 NNW-5

,NNW-10 NW-5 NW-10 5.11

+ 0.16 4.97

+ 0.15 5.08

+ 0.17 6.44

+ 0.17 WNW-2 WNW-5 WNW-10

~ 4.98

+ 0. 14 4 '5

+ 0.14 5.51

+ 0.16 W-2 W-5 W-10 WSW-2 WSW-5 WSW-10 5.61

+ 0.18 5.08

+ 0.14 5.08

+ 0.14 5.09

+ 0.17 4.94

+ 0.15 4.41

+ 0.15 SW-2 SW-5 SW-10 (A)

SSW-2 SSW-5 SSW-10 4.60

+ 0.16 5.95

+ 0.18 4.71

+ 0.16 5.12

+ 0.16 4.95

+ 0.15 S-5 S-10 4.80

+ 0.14 5.06

+ 0.17 S/SSE-10 SSE-5 SSE-10 4.58

+ 0.14 4.78

+ 0.15 5.03

+ 0.17 SE-1 4.43

+ 0.14 H-32 5.69

+ 0.15 (A)

The dosimeter for site SW-10 was missing when collection was attempted.

2.a IODINE-131 IN WEEKLY AIR FILTERS

Ci m3 Sam le Site Collection Date HOS H12 H14 H30 H34 04-05-94 04-11-94 04-21-94 04-26-94

<0.01

<0.02

<0.02

<0.02

<0.

01'0.02

<0.02

<0.02

<0. 01

<0. 02

<0.02

<0.02

<0.01

<0.02

<0. 02

<0.02

<0. 01

<0. 02

<0.02

<0.02 05-02-94 05-10-94 05-17-94 05-24-94

<0. 02

<0. 01

<0. 03

<0.01

'0.01

<0.01

<0.03

<0.01

<0. 01

<0.01

<0.02

<0.02

<0.02

<0.01

<0.03

<0.01

<0.01

<0". 01

<0. 02

<0. 02 06-01-94 06-06-94 06-14-94 06-20-94 06-27-94

<0.02

<0.02

<0.02

<0.03

<0.01

<0. 02

<0.02

<0.02

<0.03

<0.01

<0.02

<0.01

<0.03

<0.02

<0.01

<0.02

<0.02

<0.02

<0.03

<0.01

<0. 02

<0.01

<0.03

<0.02

<0.01

2.b AIR PARTICULATES

GROSS BETA

Ci m3 Collection Date H08 H12 Sam le Site H14

. H30 H34 04-05-94 04-11-94 04-21-94 04-26-94 05-02-94 05-10-94 05-17-94 05-24-94 0.047

+ 0.

0.014

+ 0.

0.012

+ 0.

0.006

+ 0.

0.015

+ 0.

0.023

+ 0.

0.023

+ 0.

0.016

+ 0.

003 002 002 002 002 002 003 002 0.029

+ 0.002 0.010

+ 0.002 0.010

+ 0.002

<0.007 0.012

+ 0.002 0.013

+ 0.002 0.020

+ 0.002 0.014

+ 0.002

0. 023

+ 0. 002 0.014

+ 0.002 0.010

+ 0.002 0.006

+ 0.002 0.012

+ 0.002

  • 0.018 + 0.002
  • 0.017

+ 0.002

  • 0.017

+ 0.003 0.030 +,0.002 0.017

+ 0.002 0.009

+ 0.002 0.009

+ 0.002 0.015

+ 0.002 0.021

+ 0.002 0.025

+ '0.003 0.021

+ 0.002 0.021

+ 0-002

0. 016

+ 0. 002 0.010

+ 0.002 0.009

+ 0.003

0. 014

+ 0. 002

0. 013

+ 0. 002 0.020

+ 0.002 0.018

+ 0.003 06-01-94 06-06-94 06-14-94 06-20-94 06-27-94 0.023 0.006 0.012 0.005 0.018

+

Q.

+

Q.

+

Q.

+

Q.

+ 0.

002 003 002 002 002 0.015

+

0.007

+

0.009

+

0.012

+

0.017

+

0.002 0.003 0.002 0.002 0.002

  • 0.018

+

0.006

+

0.014

+

0.008

+

0.015

+

0. 002
0. 002 0:002 0.002 0.002
0. 017

<0.

0.014 0.006 0.013

+ 0. 002 007

+ 0. 002

+ 0.002

+ 0.002

0. 013

<0

0. 013 0.009 0.014

+ 0. 002

.005

+ 0.002

+ 0.002

+ 0.002 Means:

0.017

+ 0.001 0.014

+ 0.001 NRC split samples.

0.014

+ 0.001 0.016

+ 0.001 0.014

+ 0.001 2.b AIR PARTICULATES

GAMMA SCANS OF UARTERLY COMPOSITES

Ci m3 Sample Site Be-7 Second Quarter, 1994 K-40 Cs-134 Cs-137 Pb-210 H08 H12 H14 H30 H34 0.1203

+ 0.0084 0.1075

+ 0.0096 0.1121

+ 0.0115 0.1051

+ 0.0083 0.1209

+ 0.0095

<0.0171

<0.0183

<0.0167

<0.0186

<0.0161

<0.0007

<0.0010

<0.0010

<0.0007

<0.0010

<0.0009

<0.0009.

<0.0008

<0.0008

<0.0005 0.0161

+

0.0096

+

0.0101

+

0.0128

+

0.0096

+

0.0023 0.0024 0.0026 0.0027 0.0028

3.a SURFACE WATER

Ci l Sample Collection Site Date H-3 Zr-95 Ba-140 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 I-131 Cs-134-Cs-137 La-140 H15 04-05-94

<132 04-12-94 89

+ 42 04-21'-94

<130 04-26-94

<136 319

+ 33

<4 280

+ 32

<4 310

+ 39

<4 327

+ 36

<4

<3

<4

<3

<3

<9

<8

<9

<7

<5

<6

<5

<5

<8

<7

<8

<7 (A)

<5

<6

<7

<4

<8

<5

<6

-<5

<4

<4

<4

<4

<4

<4

<4 (B)

<5

<5

<3

<6 05-03-94 05-09-94 05-17-94 05-24-94 05-31-94

<140

<138

<137

. <137

<137 286

+ 32 352

+ 35 333

+ 36 373

+ 34 340

+ 37

<4

<3

<3

<4

<4

<4

<4

<4

<4

<4

<9

<7

<8

<8

<8

<5

<6

<5

<5

<4

<8

<9

<9

<8

<8

<7

<8

<6

<6

<6

<4

<5

<8

<4

<4

<5

<4

<4

<4

<4

<4

<4

<4

<4

<8

<6

<6

<8

<7 06-07-94 06-13-94 06-21-94 06-27-94

<138

<138

<142

<142 334

+ 35 353

+ 36 347

+ 35 339

+ 37

<4

<4

<4

<3

<3

<4

<4

<5

<7

<6

<9

<5

<4

<4

<4

<9

<5

<5

<9

<6

<4

<5

<6

<4

<9

<5

<4

<4

<5

<4

<3

<4

<4

<4

<4

<6

<7

<8

<9 H59 04-12-94

<132 404

+ 34

<3

<4

<7

<5

<9

<6

<5 05-03-94

<140 326

+ 33

<3

<4

<6

<5

<7

<6

<4 06-01-94

<138 248

+ 40

<4

<4

<7

<4

<8

<8

<6

<3

<4

<3

<4

<3

<4

<6

<8

<3 (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

I BROADLEAF VEGETATION

Man rove

Ci k wet wei ht Sample Collection Site Date Be-7 K-40 I-131 Cs-134 Cs-137 Pb-210 H51 04-12-94 710

+ 57 2445

+ 118

<8 05-03-94 538

+ 59 2860

+ 120

<8

<9

<8

<10

<6 ND ND 06-01-94 488

+ 35 2150

+ 89

<6

<7

<7 433

+ 192 H52 04-12-94 673

+ 61 3359

+ 151

<11 05-03-94 662

+ 67 3867

+ 155

<10 06-01-94 421

+ 44 3587

+ 144

<10

<12

<10

<12

<9 ND 695

+ 286 ND H59 04-12-94 588

+ 47 1339

+ 93 05-03-94 516

+ 50 1506

+ 89

<8

<8

<9

<7

<9

<8 ND ND 06-01-94 656

+ 47 3074

+ 121

<9

<8

<7 ND ND Non-detectable.

RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S

,ST.

LUCIE SITE Third Quarter, 1994 Office of Radiation Control Florida Department of Health and Rehabilitative Services

ST.

LUCZE SITE Technical Specifications Sampling Third Quarter,.1994 Sam le T e

Collection Fre uenc Locations Sam led Number of Sam les

1. Direct. Radiation Quarterly 27 25
2. Airborne 2.a Air Iodines 2.b Air Particulates Weekly Weekly 65 69*
3. Waterborne 3.a Surface Water 3.b Shoreline Sediment
4. Ingestion 4'.a Fish and Invertebrates 4.a.l 'Crustacea 4.a.2 Fish Weekly Monthly Semiannually Semiannually Semiannually 13 33*

4.b Food Products 4.b.1 Broadleaf Vegetation Monthly Total:

191

  • 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 06-07-94 Site Collection 09-20-94 N-1 4.83

+ 0.13 NNW-5 NNW-10 NW-5 NW-10 4.86

+ 0.15 4.78

+ 0.12 4.85

+ 0.16 6.53

+ 0.19 WNW-2 WNW-5 WNW-10 4.82

+ 0.14 4.77

+ 0.15 5.51

+ 0.17 W-2 W-5 W-10 (A) 4.92

+ 0.16 4.89

+ 0.15 WSW-2 WSW-5'SW-10 SW-2 SW-5 SW-10 4.78

+ 0.15 5.00

+ 0.15 (A) 4.49

+ 0.12 5.59

+ 0.16 4.84

+ 0.15 SSW-2 SSW-5 SSW-10 4.64

+ 0.16 5.00

+ 0.15 5.04

+ 0.13 S-5 S-10 4.62

+ 0.13 4.83

+ 0.16 S/SSE-10 SSE-5 SSE-10 4.51

+ 0.13 4.60

+ 0.12 4.78

+ 0.13 SE-1 H-32 4.44

+ 0.13 5.70

+ 0.15 (A)

The dosimeters for sites W-2 and WSW-10 were missing when collection was attempted.

r A

0 e

2.a IODINE-131 IN WEEKLY AIR FILTERS

Ci m3 Collection

- Date H08 H12 Sam le Site H14 H30 H34 07-05-94 07-12-94 07-19-94 07-26-94

<0. 01

<0.02

<0.01

<0.03

<0.01

<0.02

<0.01

<0.03

<0.01

<0.02

<0.01

<0.02

<0.01

<0.02

<0.01

<0.02

<0. 01

<0.02

<0.01

<0.02 08-04-94 08-12-94 08-17-94 08-26-94 08-30-94

<0.02

<0.01

<0.01

<0.01

<0.03

<0.02

<0.01

<0.01

<0.01

<0.03

<0.02

<0.01

<0.02

<0.02

<0.02

<0.02

<0.02

<0.02

<0.03

<0. 02

<0. 02

<0.01

<0.01

<0,02

<0.02 09-06-94 09-13-94 09-20-94 09-28-94

<0'. 01

<0.01

<0.02

<0.01

<0.01

<0.01

<0.02

<0.01

<0.01

<0.01

<0.02

<0.01

<0. 01

<0.01

<0.02

<0.01

<0.01

<0.01

<0.02

<0.01

2.b AIR PARTICULATES

GROSS BETA

Ci m3 Collection Date H08 H12 Sam le Site H14 H30 H34 07-05-94 07-12-94 07-19-94 07-26-94 0.011

+ 0.002 0.011

+ 0.002 0.020 +,0.002 0.010

+ 0.002 0.013

+ 0.002 0.008

+ 0.002 0.022

+ 0.002 0.010

+ 0.002

0. 012

+ 0. 002 0.010

+ 0.002 0.013

+ 0.002 0.009

+ 0.002 0.010 0.011 0.013 0.008

+

p

+

Q

+

p

+

Q

.002

.002

.002

.002

0. 013

+ 0. 002

0. 014

+ 0. 002 0.022

+ 0.003 0.006

+ 0.002 08-04-94 08-12-94 08-17-94 08-26-94 08-30-94 0.011

+

0.008

+

0.011

+

0.009

+

0.007

+

0.002 0.002 0.002 0.002 0.003

0. 011
0. 006

. 0.008

0. 007
0. 012

+ 0.002

+ 0.002

+ 0.002

+ 0.001

+ 0.003

  • 0.010 +
  • 0.004

+

  • 0.011 +
  • 0.006

+

0.014

+

0.002 0.001 0.002 0.002 0.003 0.010 0.004

<0 0.009 0.006

+

Q

+

p

.007

+

p

+

Q

.002

.001

.002

.003 0.009 0.007 0.009 0.008 0.008

+ 0. 002

+ 0. 001

+ 0.002

+ 0.002

+ 0.002 09-06-94 09-13-94 09-20-94 09-28-94 0.008

+ 0.002 0.008

+ 0.002 0.014

+ 0.002 0.009

+ 0.002

0. 007

+ 0. 002 0.006* + 0.002 0.011

+ 0.002 0.011

+ 0.002 0.007

+ 0.002 0.009

+ 0.002 0.011

+ 0.002 0.013

+ 0.002

0. 008
0. 006
0. 015
0. 009

+

Q

+ p

+ p

+

p

.002

.002

.002

.002

0. 009

+ 0. 002 0.010

+ 0.002 0.011

+ 0.002 0.010

+ 0.002 Means:

0.011

+ 0.001 0.010

+ 0.001 NRC split samples.

0.010

+ 0.001 0.009

+ 0.001 0.010

+ 0.001 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 H08 H12 H14 H30 H34 0.0799 0.0916 0.0824 0.0844 0.0990

+ 0.0102

+ 0.0097

+ 0.0083

+ 0.0089

+ 0.0082

<0.0140

<0.0159

<0.0141

<0.0181

<0.0111

<0.0010

<0.0008

<0.0005

<0.0009

<0.0006

<0.0007

<0.0007

<0.0005

<0.0006

<0.0007 0.0146 0.0120 0.0106 0.0081 0.0055

+ 0.0021

+ 0.0029

+ 0.0024

+ 0.0025

+ 0.0024

r

3.a SURFACE WATER

Ci l Sample Collection Site Date H-3 Zr-95 Ba-140 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 H15 07-06-94

<140 07-13-94

<139 07-19-94

<138 07-27-94

<152 316

+ 31 339

+ 34 301

+ 30 335

+ 33

<3

<3

<3

<3

<3

<3

<4

<3

<7

<7

<5

<6

<4

<4

<3

<4

<6

<9

<6

<7 (A)

<6

<5

<5

<5

<3

<4

<3

<4

<3

<4

<3

<4

<3

<4

<3

<4 (B)

<7

<9

<4

<8, 08-04-94 08-12-94 08-18-94 08-26-94 08-31-94 09-07-94 09-14-94 09-21-94 09-28-94

<132

<132

<134

<134

<134

<131

<131

<138

<138 326

+ 34 322

+ 36 316

+ 32 339

+ 35 291

+ 33 326

+ 36 328

+ 38 385

+ 26 330

+ 38

<3

<3

<3

<4

<4

<4

<3

<3

<3

<4

<4

<4

<4

<4

<2

<3

<4

<4

<7

<6

<7

<8

<6

<8

<7

<5

<8

<5

<5

<4

<5

<5

<5

<5

<3

<5

<8

<6

<5

<6

<7

<5

<7

<6

<4

<9

<6

<5

<8

<7

<4

<8

<8

<6

<7

<6

<5

<6

<5

<3

<7

<7

<6

<3

<3

<3

<4

<4

<4

<4

<3

<4

<3

<4

<4

<3

<4

<3

<4

<3

<4

<7

<5

<8

<6

<9

<4

<10

<7

<4 H59 07-06-94

<140 339

+

14

<1

<1

<3

<2

<3

<2

<2 08-04-94

<132 349

+ 35

<4

<4

<5

<4

<9

<6

<5 09-07-94

<131 336

+ 35

<3

<4

<7

<5

<10

<8

<7

<1

<4

<4

<4

<4

<2

<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.

1

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 H59 08-18-94

<81

NRC split sample.

H15*

08-18-94

<93 1217

+ 83

<9 819

+ 76

<7

<10

<10

<12

<10

<11 471

+ 11 216

+ 17

<10 293

+ 10 146

+ 16 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 H15 08-31-94 865

+ 150

<20

<17

<38

<26

<38

<22

<16 ND ND H59 09-06-94 1340

+ 184

<16

<19

<38

<21

<38

<20

<18 155

+ 17 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 H15 08-18-94 1912

+ 172

<14

<20

<36

<23

<39

<16

<18 ND ND H59 09-07-94 2706

+ 263

<23

<26

<51

<29

<50

<29

<26 ND ND ND Non-detectable.

I

4.b.l BROADLEAF VEGETATION

Man rove

Ci k wet wei ht Sample Collection Site Date Be-7 K-40 I-131 Cs-.134 Cs-137 H51

" 07-06-94 721

+ 59 3474

+ 141

<10

<9

<9 08-04-94 09-06-94 621

+ 46 1228

+ 86 3093

+ 113

<7 3008

+ 169

<13

<8

<13 (7

<12 H52 07-06-94 518

+ 81 5042

+ 198

<13

<13

<14 08-04-94 09-06-94 646

+ 55 615

+

62 3883

+ 148 2394

+ 133

<10

.<11

<11

<13

<8

<11 H59 07-06-94 772

+

62 2587

+ 128

<10

<11

<11 08-04-94 09-07-94 644

+ 48 4123

+ 133

<8

<10 778

+ 65 2502

+ 134

<12

<12

<9

<12

RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S ST.

LUCIE SITE Fourth Quarter, 1994 Office of Radiation Control Florida Department of Health and Rehabilitative Services

ST.

LUCXE SXTE Technical Specifications Sampling Fourth Quarter, 1994 Sam le T e

Collection Fre uenc Locations-Number of

1. Direct Radiation Quarterly 27 26
2. Airborne 2.a Air Xodines 2.b Air Particulates Weekly Weekly 63 67*
3. Waterborne 3.a Surface Water 3.b Shoreline Sediment Weekly Monthly Semiannually 13 3

0

4. Xngestion 4.a Fish and Xnvertebrates 4.a.l Crustacea 4.a.2 Fish Semiannually Semiannually 4.b Food Products 4.b.l Broadleaf Vegetation Monthly Total:

181

  • Xncludes 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, 09-20-94 Site Collection 12-06-94 N-1 4

~ 94

+ 0.17 NNW-5 NNW-10 4.69

+ 0.16 4 '5

+ 0.17 NW-5 NW-10 WNW-2 WNW-5 WNW-10 (A) 4 '6

+ 0.15 6.35

+ 0.19 4.83

+ 0.15 4.88

+ 0.15 W-2 (B) 5'3

+ 0.17 W-5 5.14

+ 0.15 W-10 '.97

+ 0.14 WSW-2 WSW-5 WSW-10 4.85

+ 0.15 4.96

+ 0.17 4.20

+ 0.16 SW-2 SW-5 SW-10 SSW-2 SSW-5 SSW-10 4

~ 69

+ 0.14 5.52

+ 0.16 4.74

+ 0.17 4.72

+ 0.18 5.08

+ 0.18 5.19

+ 0.16 S-5 S-10 4.75

+ 0.15 5.00

+ 0.17 S/SSE-10 4.52

+ 0.17 SSE-5 (C) 4.65

+ 0.15 SSE-10 4.80

+ 0.16 SE-1 H-32 4.44

+ 0.14 5.29

+ 0.16 (A)

The dosimeter for site WNW-10 was collection was attempted.

missing when (B)

The packaging for the dosimeter at site W-2 was found to have been opened.

(C)

The dosimeter at site SSE-5 was placed at a slightly different location at the beginning of this sampling interval to allow easier access.

I i

~

2.a IODINE-131 IN MEEKLY AIR FILTERS

Ci m3 Collection Date H08 H12 Sam le Site H14 H30 H34 10-03-94 10-10-94 10-20-94 10-25-94

<0.02

<0.02

<0.02

<0.02

<0.02

<0.02

<0.02

<0.02

<0.02

<0.02

<0.02

<0.02

<0. 02

<0. 02

<0.02

<0.02

<0.02

<0.02

<0.02

<0.02 11-01-94 11-07-94 11-16-94 11-21-94 11-28-94

<0. 01

<0. 01

<0: 03

<0. 02

<0. 04

<0.01

<0.01

<0.03

<0.02

<0.03 (C)

(C)

<0. 01

<0.03'-

<0. 02 (D)

<0. 01

<0.03

<0.04

<0.01

<0.04

<0.02

<0.03 r

<0. 03 (A)

<0. 02 (B)

<0. 01 12-05-94 12-13-94 12-20-94 12-27-94

<0. 02

<0. 02

<0.02

<0.02

<0.02

<0.02

<0.03

<0.02

<0. 02

<0. 02

<0.03

<0.02

<0. 02

<0. 02

<0. 03

<0. 02

<0.02

<0.02

<0.03

<0.02 (A)

Electrical power was out at, the end of this sample.

The equipment is estimated to have run for 82 hours9.490741e-4 days <br />0.0228 hours <br />1.35582e-4 weeks <br />3.1201e-5 months <br /> out of the 145 total hours for this sampling interval.

(B)

Electrical power was out at the end of this sample.

The equipment is estimated to have run for 121 hours0.0014 days <br />0.0336 hours <br />2.000661e-4 weeks <br />4.60405e-5 months <br /> out of the 145 total hours for this sampling interval.

(C)

Electrical power was out for this entire sampling interval.

There were no samples for analysis.

(D)

Electrical power was out at the start of this sample.

The equipment is estimated to have'un for 75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> out of the 119 total hours for this sampling interval.

2.b AIR PARTICULATES

GROSS BETA

Ci m3 Collection Date H08 H12 Sam le Site H14 H30 H34 10-03-94 10-10-94 10-20-94 10-25-94 0.007

+ 0.002.

0. 009

+ 0. 002

0. 013

+ 0. 002

0. 017

+ 0. 003 0.010

+ 0.002 0.010

+ 0.002 0.009

+ 0.001 0.023

+ 0.003 0.007

+ 0.002 0.007

+ 0.002 0.008

+ 0.001 0.019

+ 0.003 0.011

+ 0.002 0.008

+ 0.002 0.010

+ 0.001 0.019

+ 0.003 0.011

+ 0.002 0.008

+ 0.002 0.012

+ 0.002 0.023

+ 0.003 11-01-94 11-07-94 11-16-94 11-21-94 11-28-94

0. 017 0-016 0.005 0.009 0.015

+ 0.002

+ 0.002

+ 0. 001

+ 0. 002

+ 0. 002 0.009 0.014 0.006 0.008 0.012

+ 0. 002

+ 0. 002

+ 0. 001

+ 0.002

+ 0.002 (A0.013

+ 0.003 (C)

(C)

  • (D)<0.010
  • 0.012

+ 0.002 (B0.016 0.015 0.007 0.004 0.012

+ 0.003

+ 0.002

+ 0.001

+ 0.002

+ 0.002 0.005

+ 0.002 0.010

+ 0.002 0.004

+ 0.001

<0.006 0.013

+ 0.002 12-05-94 12-13-94 12-20-94 12-27-94

0. 009

+ 0. 002 0.007

+ 0.002 0.011

+ 0.002 0.015

+ 0.002 0.008

+ 0.002 0.008

+ 0.002 0.005

+ 0.002 0.012

+ 0.002

  • 0.003

+ 0.001

  • 0.007

+ 0.002 0.009

+ 0.002 0.016

+ 0.002 0.006

+ 0.002 0.007

+ 0.002 0.010

+ 0.002 0.013

+ 0.002'.007

+ 0.002 0.008

+ 0.002 0.010

+ 0.002 0.017

+ 0.002 Means:

0.012

+ 0.001 0.010

+ 0.001 0.010

+ 0.001 0.011

+ 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 82 hours9.490741e-4 days <br />0.0228 hours <br />1.35582e-4 weeks <br />3.1201e-5 months <br /> out of the 145 total hours for this sampling interval.

(B)

Electrical power was out at the end of this sample.

The equipment is estimated to have run for 121 hours0.0014 days <br />0.0336 hours <br />2.000661e-4 weeks <br />4.60405e-5 months <br /> out of the 145 total hours for this sampling interval.

(C)

Electrical power was out for this entire sampling interval.

There were no samples for analysis.

(D)

Electrical power was out at the start of this sample.

The equipment. is estimated to have run for 75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> out of the-119 total hours for this sampling interval.

I J

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 H08 H12 H14 H30 H34

0. 1044

+ 0. 0091 0.0824

+ 0.0085 0.0999

+ 0.0138 0.0917

+ 0.0097 0.1197

+ 0.0117

<0.0206

<0.0174

<0.0241

<0.0182

<0.0197

<0.0011

<0.0007

<0.0011

<0.0010

<0.0006

<0.0007

<0.0009

<0.0012

<0.0007

<0.0008

0. 0113

+ 0. 0030 0.0108

+ 0.0030 ND 0.0118

+ 0.0021 0.0126

+ 0.0019 ND Non-detectable.

3.a SURFACE WATER

Ci l Sample Collection Site Date H-3 Zr-95 t

Ba-140 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 H15 10-03-94

<134 10-11-94

<134 10-21-94

<134 10-26-94

<134 400

+ 33

<4 379

+ 39

<4 269

+ 37

<2 330

+ 34

<4

<4

<4

<4

<3

<7

<7

<9

<6

<5

<4

<4

<4

<9

<10

<9

<7 (A)

<8

<7

<6

<7

<7

<4

<6

'<4

<5

<5

<4

<4

<4

<3

<4

<3 (B)

<7

<5

<5

<9 11-01-94 11-08-94 11-17-94 11-22-94 11-29-94

<138

<137

<137

<142

<140 287

+

336

+

372

+

274

+

199

+

33

<2 36

<4 37

<3 34

<3 32

<4

<3

<4

<5

<4

<3

<8

<8

<7

<9

<7

<5

<3

<5

<3

<5

<9

<8

<7

<10

<8

<7

<6

<7

<7

<5

<5

<4

<12

<8

<5

<4

<4

<4

<4

<4

<4

<4

<4

<4

<5

<7

<5

<6

<5

<7 12-06-94 12-13-94 12-19-94 12-27-94

<141

<136

<136

<137 281

+ 35

<4 268

+ 33

<4 272

+ 36

<4 290

+ 18

<2

<3

<4

<4

<2

<7

<8

<7

<3

<4

<4

<3

<2

<9

<6

<9

<8

<7

<7

<4

<3

<5

<6

<5

<2

<4

<4

<4

<2

<4

<3

<4

<2

<8

<6

<6

<3 H59 10-04-94

<134 347

+ 37

<3

<4

<7

<5

<8

<7

<8 11-07-94

<154 303

+ 32

<4

<4

<6

<3

<8

<5

<4 12-07-94

<14'1 319

+ 32

<3

<4

<6

<4

<7

<7

<6

<5

<4

<4

<4

<4

<3

<4

<6

<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.

4.b. 1 BROADLEAF VEGETATION

Man rove

Ci k wet wei ht Sample Collection Site Date Be-7 K-40 I-131 Cs-134 Cs-137 Pb-210 H51 10-04-94 11-08-94 12-07-94 1141

+ 70 885

+ 55 615

+ 73 3634

+ 145 2796

+ 112 2745

+ 129

<8

<9

<7

<8

<8

<9 ND 569

+ 235 ND H52 10-04-94 11-08-94 12-07-94 611

+ 56 639

+ 52 573

'+ 51 2460

+ 119 2806

+ 120 2495

+ 119

<9

<8

<8

<9

<7

<9

<9

<9

<9 ND ND ND H59 10-04-94 11-07-94 12-07-94 758

+ 58 711

+ 48 599

+ 79 3126

+ 118 3037

+ 127 3400

+ 160

<8

<9

<8

<10

<12

<8

<10

<10 ND ND ND ND Non-detectable.

~

P

~

/

'I

~

~

4 1994 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ST.

LUCIE PLANT, UNITS 1 Ec 2

ATTACHMENT C RESULTS FROM THE INTERLABORATORY COMPARISON PROGRAM 1994 HP3:1/RADENVOP.PSL

FLORIDA DEPT.

OF HRS EPA INTERLABORATORY CROSS-CHECK PROGRAM DATA January through June, 1994 WATER WATER WATER.

WATER WATER WATER WATER WATER WATER WATER WATER WATER Alpha Beta Co-60 Zn-65 RU-106 Ba-133 Cs-134 Cs-137 H-3 I-131 Sr-89 Sr-90 Media Nuclide Collection Mon Day Yr 01 28 94 01 28 94 06 10 94 06 10 94 06 10 94 06 10 94 06 10 94 06 10 94 03 04 94 02 04.

94 01 14 94 01 14 94 EPA Known 15 62 50 134 252 98 40 49 4936 119 25 15 Units pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L Normal.

Range 0.591 0.354 0 '54 0.091 0.213 0.059 0.236 0.118 0.005 0.148 0.591 0 '54 Mean of Analyses 16.33 65.00 50.33 145.00 196.00 83.33 37.67 54.33 4957.67 115.00 20 F 00 11.67 N.D.K. Action Level 0.46 0.52 0.12 1.47

-3.88 1

~ -2. 54

-0.81 1,85 0.08

-0.58

-1.73

-1.15 NOTES:

Normal.:

N.D.K.:

NDP:

NA:

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

'ormalized deviation of the mean from the known value, as defined in EPA-600/4-81-004.

No data provided.

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

Not available.

Report containing this data has not yet been received from EPA, Las Vegas.

ACTION LEVEL:

Cause:

Problem with Ruthenium-106 standard.

Corrective Action:

See attached letter from Dr. George Dilbeck.

A I ~~

~< og>t4 UNITED STATES ENVIRONMENTALPROTECTION AGENCY OFFICE OF RESEARCH AND DEVELOPMENT ENVIRONMENTALMONITORING SYSTEMS LABORATORYLAS VEGAS P.O. BOX 93478 LAS VEGAS. NEVADA89193 3478 I702/798 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 Mater 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 PE Study.

Sincerely, George Dilbeck Chemist Performance Evaluation Program Radioanalysis Branch (RSA-RADQA)'

g<

~

v s

0

'I FLORXDA DEPT.

OF HRS EPA XNTERLABORATORY CROSS-CHECK PROGRAM DATA July through December, 1994 FXLTER FXLTER FXLTER FXLTER MXLK MXLK-MXLK MXLK MXLK WATER WATER WATER HATER WATER WATER WATER WATER WATER WATER HATER WATER HATER Alpha Beta Cs-137 Sr-90 X-131 Cs-137 KSr-89 Sr-90 Alpha Alpha Beta Beta Co-60 Zn-65 Ba-133 Cs-134 Cs-137 H-3 X-131 Sr-89 Sr-90 Media Nuclide Collection Mon Day Yr 08 26 94 08 26 94 08 26 94 08

'26 94 09 30 94 09 30 94 09 30 94 09 30 94 09 30 94 07 22 94 10 28 94 07 22 94 10 28 94 11 04 94 11 04 94 11 04 94 11 04 94 ll 04 94 08 05 94 10 07 94 07 15 94 07 15 94 EPA Known 35 56 15 20 75 59 1715 25 15 32 57 10 23 59 100 73 24 49 9951 79 30 20 Units pCi/F pCi/F pCi/F pCi/F pCi/L pCi/L mg/L'Ci/L pCi/L pCi/L pCi/L pci/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L Normal.

Range 0.000 0.000 0.000 0.118 0.148 0.118 0.220 0

F 000 0.000 0.517 0.253 0.000 0.000 0.118 0.236 0.338 0.236 0.118 0.149 0.222 0.591 0.236 Mean of Analyses 37.00 61.00 16.00 17.33 73.33 62.67 1726,00 22.00 15.00 45 F 00 61.67 15.00 30.00 60.67 108.33 66.00 23.00 53.67 9985.33 77.33 30.67 20.00 N.D.K. Action Level 0.38 0.87, 0.35

-0.92

-0.36 1.27 0;22

-1. 04 0.00 F 81 0.58 1.73 2.42 0.58 1.44 1

~ 7 3

-0.35 1.62 0.06

-0.36 0.23 0.00 NOTES:

Normal.:

N. D.K.:

NDP:

NA:

Normalized range.

As defined in "Environmental Range Radioactivity Laboratory Xntercomparison Studies Program Fiscal Year 1981 1982", Environmental Monitoring Systems Laboratory, U.

S. Environmental Protection

Agency, P. 0.

Box 93478, Las Vegas,

Nevada, 89193-3478.

EPA-600/4-81-004,

February, 1981.

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

No data provided'o data was provided to EPA for inclusion in their report.

Not available.

Report containing this data has not yet been received from EPA, Las Vegan

l (i

+Lc~ t~

,a 0