ML17352A564

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1993 Annual Radiological Environ Operating Rept for Turkey Point Plant Units 3 & 4. W/940425 Ltr
ML17352A564
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 12/31/1993
From: Plunkett T
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-94-094, L-94-94, NUDOCS 9405020233
Download: ML17352A564 (130)


Text

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ACCELERATE OCUlVlENT DISTRIB TION SYSTEM j

e REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9405020233 DOC.DATE: ~M~M NOTARIZED: NO FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C DOCKET 05000250 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION PLUNKETT,T.F. Florida Power 6 Light Co.

RECIP.NAME RECIPIENT AFFILIATION D

SUBJECT:

"1993 Annual Radiological Environ Operating Rept for Turkey Point Plant Units 3 & 4." W/~4Zgltr.

DISTRIBUTION CODE: IE25D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Environmental Monitoring Rept (per Tech Specs)

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD2-2 LA 3 3 PD2-2 PD 1 1 CROTEAU,R 1 1 D

INTERNAL: NRR/DRSS/PRPB11 2 2 G FILE 01 1 1 RGN2 DRSS/RPB 1 1 GN2 LE 02 1 1 EXTERNAL EGGG AKERS i D 1 1 NRC PDR 1 1 D

D D

NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE) CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISIS FOR DOCUMENTS YOU DON'T NEEDt TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL 12

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ApR R5 1994 L-94-094 10 CFR 50.36 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 1993 Annual Radiological Environmental 0 eratin Re ort Attached is the 1993 Annual Radiological Environmental Operating Report for Turkey Point Units 3 and 4, as required by Technical Specification 6.9.1.3.

Should there be any questions or comments regarding this information, please contact us ~

Very truly yours, p+~~~

T, F. Plunkett Vice President Turkey Point Plant TFP/RJT/rt Attachment cc: S. D. Ebneter, Regional Administrator, Region II, USNRC T. P. Johnson, Sr. Resident Inspector, USNRC, Turkey Point Plant 020076 IrN'%9aM Mh68kmo

. R an FPL Group company poa pgE

J' Distri44.txt Distribution Sheet Priority: Normal From: Patricia Exum Action Recipients: Copies:

N RR/D LPM/LP D2-2 1 Paper Copy K Jabbour 1 Paper Copy B Clayton 1 Paper Copy Internal Recipients:

RidsRgn2MailCenter 0 OK Rids NrrWpc Mail 0 OK Rids NrrDssaSrxb 0 GK RidsManager OK RidsAcrsAcnwMailCenter 0 OK OGC/RP Paper Copy NRR/DSSA/SRXB Paper Copy

---FIL ENTER 0 Paper Copy CRS Paper Copy External Recipients:

NOAC Paper Copy Total Copies:

Item: ADAMS Document Library: ML ADAMS"HQNTAD01 ID: 003688038:1

Subject:

Homestead AFB Property Disposal Per Turkey Points, Units 3 and 4.

Body:

ADAMS DISTRIBUTION NOTIFICATION.

Electronic Recipients can RIGHT CLICK and OPEN the first Attachment to View the Document in ADAMS. The Document may also be viewed by searching for Accession Number ML003688038.

Page 1

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Distri44.txt A001 - OR Submittal: General Distribution Docket: 05000260 Docket: 05000261 Page 2

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st I I 24 February 00 US. Nuclear Regulatdry Commission gtterition: Document Control DC .20/55 Desk'ashington

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RE: Turkey Point Units 3 and 4

'Docket'Nos. 50-250 and 50-251.

Homestead AFB Property Disposal

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We appreciate the considerations you have shown us during this process., As y'ou likely qealize, the conversion involving Homestead.Air Force Bas'e is ve+

importaqt to us,an'ji.the base is very close to Turkey Point. We are extremely, concerned about the public safety consequences of the conversion.

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We understand that.ihe Nuclear Regulatory Commission (".NRC")'s. completing a Safety-Evaluation Report ("SER"), for the Final Supplemental Environmental "

Impact Statemen)".'ierra Club, Miami Group,. has notice that a, significant amount of important information s'eems to be missing from the public record I the Draft Sup'plem'ental Environmental Impaht Statement ("DSEIS").',-

'ncluding

.We respectfully, request that.you ensure th~ the information belo~v'is ~

incofyorated into the'calculations and,conclusions of the SEE s

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1. The NRC staff,'n a'llutter (ref. 2) to Florida Powers.Light ("FPEcL"t), states

'that. the probability calculationy of aircraft hazards should comply with NUREG-0800 (ref. 3, p 3.5.1.6-3). FP&L's response (ref.'4 a'nd ref. 7) utilizes foimulae that appear to be inconsistent ~vith NUREG-0800.

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I ge realize <liat in complex calculations, assumptions can mislead and I ~

mistakes can be made. In a Memoranedu'm land Order for the Bi'g. Rock Nuclear '

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Power. Plant (ref. 5),'for example, a conceptual error was discovered in'a .. l .,';

,proIjability analysis, This.error'led to p'conclusion that underestimated a~lane-,

crash risk into tfie nuclear.po~sver plant by, a factor of 23,667,. We. request that a line-by-line, calculation-by-calculatio'n probability'nalysis of aii,crashes

,- 'from Homestead 'Airport, Homestead'Spaceport'and the 'Combined Spacepo'rt/Airport 'alternativd'be'included in the SER, as specified by NUREG-II 0800 s

3. sAside from Me>ico, Guatemala, and'tPe northern Bahamas IslMds, it appears that Homestead is tPe closest mainland American airport to all the 'countries of.

the Caribbean, Central America, and South America. Th'e DSEIS (ref. 1, p 2.2-,9) predicts significant foreign passenger and cargo'perations by the year 2005.. ~

-For 2015 (assuming FPEcL receives a license renewal)'the DSEIS (ref. g p 2.2-9 to 2.2-11) states

st I / / r I "Together,.these commercial passe eaged rsv rouser groups are.

forecast to'have 20,300 jet and 80;f20 turh'oprop annual operations s

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'Not'lind'opposition to,progresst'ut. opposition to blind progress. "

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  • by 2015. Of these 51,220 operations, more 'than 80Y0 are estimated to be Latin- American, Caribbean, or other international locations."-

In NUREG-0800 (ref. 3, p 3.5.1.6-4), the table-for fatal crash probability only states data f6r US. Air Carriers, General Aviation, USN/USMC, and USAF. NUREG-0800 appears to,be inadequate to calculate accident probabilities concerning' large proportions of foreign aircraft operations. Please explain in the SPR what data and calculations are being used,to compensate for the disparity be'tween the pre'dieted Homestead foreign/domestic fleet mix and the general norm.

4. In the Turkey Point Final Safety Analysis Report (ref. 6, flg. 2.2-2, fig. 2.5-1, flg'. 2.5-2), 'the relbvangaerial photograph, maps, and diagrams appear to show thai portions of Homestead Air Force Base Iie within a 5 mile'radius of the "

plant. How does this meet acceptance criteria Il.l.a'hnd IL1.b of NUREC-0800 (ref. 3, p 3.5.1.6-2) 7

'. In an addendum to the DSEIS, on the flight path chart named "HST EAST FLOW," it appears tha't the following flight paths over fly Turkey Point:

1. helicopter arrivals EA1X,"

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2. backbone ND3X, and.

.3. backbone NDQX.

Gn the flight path chart named "EIST WEST FROW," it appears that the'following flight path over flies Turkey Point:

4. backbone SDSX.

~ On the chart named "HA EXISTING & FUTURE LOCAL PATTERN TRACKS," it appears that the following patterns over fiy Turkey Point:

5. NC8
6. NC9, apd
7. SC4.

On the flight path chart named "HST EAST FLOW-ARRIVALS,"'tappears that the following flight paths over fly Turkey Point:

8. backbbne OSJJ,
9. backbone NDAX, apd
10. backbone EA1X.

On the flight path chart named, "HST EASY FLOW-DEPARTURES," it appears that the following flight paths over fly Turl ey Point:

11. backbone 05WP, and
12. backbone 05WJ.

On the flight path chart, named "HST WEST FLOW-ARRIVALS," it appears that the following flight paths over fly Turkey Point:

13.'ackbone 23FJ,

14. backbone 23RJ, and I
15. backbone 23TP.

On the flight path chart named "HST WEST FLOW'-DEPARTURES," it appears that .

', the following flight paths over fly Turkey Point:

16. 231@,
17. 23HP, 4$
18. 23WP;
19. 23WJ,

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20. 23VJ,
21. 23SJ, and
22. WDJX.

FIow do these over flights meet acceptance criteria, II.1.c 6f NUREG.-0800 7.

6. FP&L lists the critical structures for, risk assessment (ref. 7 p 3) as the containment buildings, turbine building, control building, auxiliary building spent fuel= buildings, emergency diesel generator buildings, intake structure and the (twin 400') fossil unit chimneys (413'bove mean sea level). We request'that all Are fighting dquipment, all fuel'tanks (including the tanks associated with fossil units 1 4 Z), and.the switchyard be added to the list for risk assessment, even thought they may not'.be structures in the strictest sense.
7. In a study conducted by Brookhaven Natonal Laboratory (ref.', p 4-2) the worst case scenario of an accident at a spent fuel pool of a typical decommissioned pressurized water reactor 'anticipates that prompt fatalities will be 95, latent fataliues,'will be 143,000 mid condemned land will be 2,790 square miles. We realize that Turkey Point has not been decommissioned, but there are two reactors on site, not one.i The Reactor Spent Fuel Storage report (ref. 9, p 3) sties that as of 11/4/98 there are 1,578 spent fuel assemblies being 4tor'ed on, site. This potential catastrophic accident should receive a separate risk assessment analysis since the consequences are comparable to a core-melt atmospheric accident at one r'eactor (ref. 8, p 4-4).
8. Bird strike hazards are a documented problem at Homestead Air Reserve Base (ref. 10). Bird strikes have the potential for causing additional aircraft, crashes in the Turkey Point area. Efforts to mitigate this situation are not likely to occur, due to the close proximity of Biscayne National Park and Everglades National Park. Bird populations are protected and the killing of

- birds, the destruction of their habitat or attempts to traumatize bird life by noise or chemical means wouId be politically.and 'legally impossible. Recently Miami-Dade goVernment stated a willingness,to maintain a buffer of undeveloped land around the former HAFB. This <void likely increase bird habitat and exacerbate the problem. A site-specific quantitative muitiplier based upon the bird strike hazards needs to be incorporated into the probability calculations of the air crashes in the SER. '

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-Without'uessing the outcome of the SER, Sierra Club, Miami Group believes that. developing a com~rcia1 airport next to two nuclear reactors at Turkey '

Point creates an, intolerable radiological danger for south Florida far exceeding the 1,0 CFR 100'guideliries. We agree with FP&L that adjacent structures and canals may mitigate some aspects of an air crash and we agree '

that the c'ontainment buildings yrobably would not experience perforation.

However, as discussed supra,> the existence'of the'ollowing unquantified problems may increase the risk of air cr'ashes. 'I ~

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.Foreign aircraft may not be up to the standards to which we are. accustomed, e.g. old aircraft, reduced piaintenance, marginally, trained pilots planes. language difficulties may also occur between air traffic and'verloaded controllers and foreign 'air pilots. moreover, the arrjval ang'departure flight

.patterris appear to be complex and "convoluted'(ref.11, p ill) with airer'aft leave'the airport...

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crossing oyer and under various federal airways to reach or

'inally there is a significantly-higher risk of bird strikes at Homestead than is the norm'nationally. r 4 I Sincerely',

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,.Conservation!Chair Energy Chair =

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er ~ o c, Draft Supplem'ental Environmental Impact Statement, Aviation Administration, December, 1999, U.S.Air Forct: and o .

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2. Letter to Thomas F. Plunkett, Flor'ida Power'nd Light from Kahtan N.

Jabbour, Senior Project Manager, Office of Nuclear'Reactor Regulation, May 4,

3. NUREG@800, St, rev. 2- July 1981 a -

v ew a 10 CFR Part 100, $ .5.1.6 i

Aircraft Hazards,

4. Letter to U.S. Nuclear Regulatory Commission from R.J. Hovey, Vice PresidentTurkey Point Plant, June 15, 998...
5. m ndum d rder in the matter of Consumers Power Company (Big, Rock Nuclear Power Plant) Atomic Safety and Licensing Board, U.S. Nuclear Regulatory Commission, March 6, 1984 (Docket No. 50-155-OLA).
6. 'af A a sis e, I Turkey Point Plant, Units 3 and Light Company, volume 1, rev. 5, July 1987.

Ee 4, Florida Power 7, Letter to U.S. Nuclear Regulatory Commission from R.J. Hovey, Vice President, Turkey Point Plant, November 17, 1999.

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8. NUREG/CR-6451, Safet' dR ul sessment o Ge e c HWRa W erma e tl Shutdow u lear Po~ e Pl ts, Brookhaven,National Laboratory, August 1997.
9. e et u S rae )

http://www.nrc.gov/OPA/drycask/sfdata.htm, November 4, 1998.

10. Memorandum'for Distribution from Steven R. Fulghum, Col., USAFR, 482d Fighter Wing Bird Hazard Working Group, March 25, 1996.

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11. Letter to U:S..Nuclear Regulatory Commission from Douglas J. Heady, SAF/GCN U.S. Air Force, August 23, 1999 enclosure e d v I 'tud

1993 ANNUAI RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT UNITS 3 5 4 LICENSE NOS. DPR-31, DPR-41 DOCKET NOS. 50-250, 50-251 Data submitted by: Florida DHRS Prepared by:

Reviewed by: p/yg/Fgc

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1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT - UNITS 3 & 4 TABLE OF CONTENTS DESCRIPTION PAGE Introduction Radiological Environmental Monitoring Program Discussion and Interpretation of Results Environmental Radiological Monitoring Program TABLE 1 Annual Summary t Deviations/Missing Data Analyses with LLDs Above Table 4.12-1 Detection Capabilities Land Use Census TABLE 1A TABLE 1B TABLE 2 Key to Sample Locations ATTACHMENT A Radiological Surveillance of Florida Power ATTACHMENT B and Light Company's Turkey Point Site First Quarter, 1993 Second Quarter, 1993 Third Quarter, 1993 Quarter, 1993 'ourth Results from the Interlaboratory Comparison ATTACHMENT C Program, 1993 e

REPORT/RADENVOP.PTN

1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT - UNITS 3 &. 4 EXECUTIVE

SUMMARY

The data obtained through the Turkey Point Radiological Environmental Monitoring Program verifies the levels of radiation and concentrations of radioactive materials in environmental samples is not increasing.

These measurements verify that the dose or dose commitment to members of the public, due to operation of Turkey Point Units 3 & 4, during the surveillance year, is well within the'limits established by 10 CFR 50, Appendix I.

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

REPORT/RADENVOP.PTN

1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT - UNITS 3 6c 4 INTRODUCTION This report is submitted pursuant to Specification 6.9 of Turkey Point Units 3 8 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 ose I

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 k 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.

REPORT/RADENVOP.PTN

0 1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT - UNITS 3 Ec 4

c. Surface water samples are collected from three locations. Samples are collected and analyzed monthly. Analyses include gamma isotopic and tritium measurements.
d. Shoreline sediment samples are collected from three locations coinciding with the locations for surface water samples. Samples are collected and analyzed semi-annually. Sediment samples are analyzed by gamma isotopic measurements.
e. Fish and invertebrate samples are collected from the two locations coinciding with two of the locations for surface water samples. Samples are collected and analyzed semi-annually. Fish and invertebrate samples are analyzed by gamma isotopic measurements.
f. Broad leaf vegetation samples are collected from three locations. Samples are collected and analyzed monthly. Broad leaf vegetation samples are analyzed by gamma isotopic measurements.

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

2. Analytical Responsibility:

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

Samples are collected and analyzed by HRS personnel.

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

C. Anal tical Results Table 1, Environmental Radicle ical Monitorin Procrram Annual ~Summa'rovides 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 in Tables "A PRIORI" LLD, if any, are respectively.

noted and explained 1A and 1B Analysis data for all specified samples analyzed during the surveillance period is provided in Attachment B.

REPORT/RADENVOP.PTN (2)

0 1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT - UNITS 3 Ec 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

~Summaa 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 & 4 Technical Specifications. Table 1 provides a summary of the measurements made for the nuclides required by Technical Specifications, Table 3.12-2, for all samples specified by Table 3.12-1. In addition, summaries are provided for other nuclides identified in the specified samples, including those not related to station operation. These include nuclides such as K-40, Th-232, Ra-226, and Be-7 which are common in the Florida environment.

REPORT/RADENVOP.PTN (3)

1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT - UNITS 3 6c 4 B.

Inter retation of. Results

1. Direct Radiation:

All the results for the first quarter are unavailabl~ due to exposure during transit. The results for direct radiation monitoring and for the remainder of the year are consistent with past measurements for the specified locations. The exposure rate data shows no indication of any trends attributed to effluents from the plant. The measured exposure rates are consistent with exposure rates that were observed during the preoperational surveillance program. Direct radiation monitoring results are summarized in Table 1.

2. Air Particulates/Radioiodine:

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

3. Waterborne; Surface Water:

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

Tritium was reported as present in the surface water samples collected from sites T-81 and T-42. These results are 'onsistent 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 4% of the reporting value specified by Technical Specifications, Table 3.12-2.

4. Waterborne; Sediment:

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

5. Food Products:

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

REPORT/RADENVOP.PTN (4)

1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT - UNITS 3 & 4

6. Broad Leaf Vegetation:

The results for radioactivity measurements are consistent with past measurements. Cs-137 was detected, as in the past, in samples collected from all locations. The maximum value is about 22'. of the Table 3.12-2 reporting level. No other fission products were detected.

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

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

criteria established by 10 CFR 50, Appendix I.

REPORT/RADENVOP.PTN (5)

Pag 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 Januar 1 December 31 1993 (County, State)

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

Locations Mean (f)

Name'ean Distance Annual Mean f b Control Locations Mean (f)b Performed Range Direction Range Range Exposure 5.6 (61/61) NW- 10 7. 7 (3/3) 6. 2 (3/3)

Rate, 64~ 4.4 7.8 10 mi., NW 7.6 - 7.8 5.8 - 6.4 Number of Nonroutine Reported Measurements = 0 HP3: 1/RADENVOP . PTN

0 Pag 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 1993 (County, State)

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

- Locations Mean (f)

Name'ean Distance Annual Mean f b Control Locations Mean (f)b Performed Range Direction Range Range

"'I, 259 0.024 <MDA <MDA Gross Beta, 258 0.0025 0. 013 (202/206) T-71 0.013 (51/52) 0.013 (52/52) 0.002 0.,027 0.5 mi., NNE 0.004 - 0.027 0.004 0.026 Composite Gamma Isotopic, 20

'Be 0.0052 0.1282 (16/16) T-71 0. 1347 (4/4) 0. 1358 (4/4) 0.1052 0.1596 0.5 mi., NNE 0.1180 .1485 0.1165 0.1597 40K 0.012 0.0178 (1/16) T-72 0.0178 (1/4) <MDA

<1 mile, WSW 134 Cs 0.00069 <MDA <MDA 137Cs 0.00066 <MDA <MDA Number of Nonroutine Reported Measurements = 0 HP3:1/RADENVOP.PTN

,J, Pag 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 Januar 1 - December 31 1993 (County, State)

PATHWAY: WATERBORNE SAMPLES COLLECTED: SURFACE WATER UNITS: PICO Ci/LITER Location with Highest All Indicator Type and Total Number of Analyses Lower of Limit Detection'LLD)

Locations Mean (f)

Name'ean Distance Annual Mean fb Control Locations Mean (f)b Performed Range Direction Range Range Tritium, 36 230 295 (8/24) T-81 324 (7/12) <MDA 87 937 6 mi., S 9 937 Gamma Isotopic, 36 60 292 (24/24) T-81 296 (12/12) 217 (11/12) 40'4Mn 184 400 6 mi., S 184 - 375 94 358

<MDA <MDA s8Fe <MDA <MDA 58Co <MDA <MDA 60Co <MDA <MDA 6sZn <MDA <MDA "Zr-Nb <MDA <MDA 131I <MDA <MDA 134Cs <MDA <MDA 137 <MDA Cs <MDA 140Ba-La <MDA <MDA Number of Nonroutine Reported Measurements = 0 HP3: 1/RADENVOP . PTN

Pag 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 1993 (County, State)

PATHWAY: WATERBORNE SAMPLES COLLECTED: SHORELINE SEDIMENT UNITS: PICO Ci/Kg, DRY Location with Highest Type and Total Number of Analyses Lower of Limit Detection'LLD)

All Indicator Locations Mean (f)

Name'ean Dz.stance Annual Mean f Control Locations Mean (f)b Performed Range Direction Range Range Gamma Isotopic, 6

'Be 100 158 (4/4) T-42 180 (1/2) 94 (1/2) 118 184 <1 mi., ENE 176 - 184 40K 140 312 (4/4) T-42 348 (2/2) 151 (2/2) 233 375 <1" mi., ENE 321 375 117 - 185 52 54 (2/4) T-42 57 (1/2) 50 (1/2) 50 57 <1 mi., ENE 226Ra 516 (4/4) T-42 648 (2/2) 107 (2/2) 297 669 <1 mi., ENE 627-669 62-152 235U 83 (1/4) T-81 83 (1/2) <MDA 6 mi., S "Co <MDA <MDA 60Co <MDA <MDA 134Cs 14 <MDA <MDA 137Cs 12 <MDA <MDA Number of Nonroutine Reported Measurements = 0 HP3:1/RADENVOP.PTN

Pag of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL S'tJMMARY Name of Facility Turke Point Units 3 &. 4 , Docket No(s). 50-250 l'0-251 Location of Facility Dade Florida , Reporting Period Janua 1 - December 31 1993 (County, State)

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

All Indicator Locations Mean (f )

Name'ean Distance Annual Mean 6

f b Control Locations Mean (f)b Performed Range Direction Range Range Gamma Isotopic, 4 40K 130 2167 (2/2) T-81 2167 (2/2) 1276 (2/2) 1447 - 2887 6 mi., S 1447 2887 1198 1353 226R 20 584 (2/2) T-81 584 (2/2) <MDA 256 911 6 mi., S 256 911 "Mn <MDA <MDA "Fe 16 <MDA <MDA 58Co <MDA <MDA 60Co <MDA <MDA Zn 17 <MDA <MDA 134Cs <MDA <MDA 137Cs <MDA <MDA Number of Nonroutine Reported Measurements = 0 HP3:1/RADENVOP.PTN

Pag of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3 E 4, Docket No(s) . 50-250 k 50-251 Location of Facility Dade Florida , Reporting Period Januar 1 December 31 1993 (County, State)

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

Name'ean Distance Annual Mean k.

f " Control Locations Mean (f) ~

Performed (LLD) Range Direction Range Range Gamma Isotopic, 4 40K 130 2014 (2/2) T-81 2014 (2/2) 2679 (2/2) 1701 2327 6 mi., S 1701 2327 1187 4171 "Mn <MDA <MDA "Fe 16 <MDA <MDA "Co <MDA <MDA 60Co 10 <MDA <MDA Zn 17 <MDA <MDA 134 <MDA CS <MDA 131CS <MDA <MDA Number of Nonroutine Reported Measurements = 0 HP3: 1/RADENVOP . PTN

0 4

Pag 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 1993 (County, State)

PATHWAY: INGESTION SAMPLES COLLECTED: BROAD LEAF VEGETATION UNITS: PICO - Ci/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 6

f Control Locations Mean (f) b Performed Range Direction Range Range Gamma Isotopic, 36

'Be 1259 (24/24) T-41 1345 (12/12) 1153 (12/12) 247 2262 2 mi., W/NW 632 2071 730 1662 40K 100 3644 (24/24) T-40 3757 (12/12) 4140 (12/12) 1952 5690 3 mi., W 2434 5690 3299 -- 5349 137Cs 89 (23/24) T-41 137 (12/12) 14 (1/12) 13 426 2 mi., W/NW 23 426 226Ra 20 38 (2/24) T-40 38 (2/12) <MDA 27 48 3 mi., W 27 48 131 I <MDA <MDA 134Cs <MDA <MDA Number of Nonroutine Reported Measurements = 0 HP3: 1/RADENVOP. PTN

0 Pa of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Docket No.(s Turke Point Units 3 & 4 50- 0 an 50-251 Location of Faci a.ty Da e F orz. a County, State Reporting Period Janua 1 - December 31 1993 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 ~ield a net count above system background that will be detected with 95. probability with only 5'robability 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.

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

MDA refers to minimum detectable activity.

HP3:1/RADENVOP.PTN

1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Sc 4 TABLE 1A Page 1 of 3 DEVIATIONS/MISSING DATA A) Pathway: Direct Exposure Location: All locations listed on Page 1 of Attachment A Date: 12/16/92 to 03/24/93 Deviation: Failure to provide continuous monitoring.

Description The TLDs, as a batch, were accidentally exposed of Problem: to one or more sources of radiation during transit from field to Lab. Extensive analysis of data and shipping conditions failed to yield useable results.

t Corrective Counseled personnel in care required while Action: handling these devices.

B) Pathway: Direct Exposure Location: NW-S, 5 miles NW Date: 06/17/93 to 09/22/93 Deviation: Failure to provide continuous monitoring.

Description TLDs were missing when collection was attempted.

of Problem:

Corrective ReplacediTLDs.

Action:

C) Pathway: Airborne Particulates Location: T-72, (1 mile WSW Date: 07/07/93 to 07/13/93 Deviation: Failure to provide continuous air sampling.

Description Upon collection attempt, particulate filter found of Problem: damaged and separated from equipment.

Corrective Replaced filter.

Action:

HP3:1/RADENVOP.PTN

1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Ec 4 TABLE lA Page 2 of 3 DEVIATIONS/MISSING DATA D) Pathway: Airborne - Particulates and Xodines

'Location: T-71, 0.5 mile NNE Date: 08/24/93 to 09/03/93 Deviation: Failure to provide continuous air sampling.

Description Suspected power outage caused an estimated of Problem: sampling duration of 205 hours0.00237 days <br />0.0569 hours <br />3.38955e-4 weeks <br />7.80025e-5 months <br /> out of the 238 hour0.00275 days <br />0.0661 hours <br />3.935185e-4 weeks <br />9.0559e-5 months <br /> period.

Corrective Verified equipment operability.

t Action:

E) Pathway: Direct Exposure Location: WNW-10, 10 miles WNW Date: 09/22/93 to 12/14/93 Deviation: Failure to provide continuous monitoring.

Description The TLDs were missing when collection was of Problem: attempted.

Corrective Replaced TLDs.

Action:

F) Pathway: Airborne - Particulates and Iodines Location: T-71, 0.5 miles NNE Date: 10/05/93 to 10/12/93 Deviation: Failure to provide continuous air sampling.

Description Suspected power outage caused an estimated of Problem: sampling duration of 140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br /> out of the 168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> period.

Corrective Verified equipment operability.

Action:

HP3:1/RADENVOP.PTN

1b 1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Ec 4 TABLE 1A Page 3 of 3 DEVIATIONS/MISSING DATA G) Pathway: Airborne - Particulates and Xodines Location: T-72, (1 mile, WSW Date: 10/12/93 to 10/20/93 Deviation: Failure to provide continuous air sampling.

Description High winds disrupted sampling equipment.

of Problem: Estimated sample duration of 110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br /> out of the 191 hour0.00221 days <br />0.0531 hours <br />3.158069e-4 weeks <br />7.26755e-5 months <br /> period.

Corrective Reset sampling equipment and verified operability.

t Action:

H) Pathway: Airborne - Particulates and Iodines Location: T-52, 7 miles W Date: 11/02/93 to 11/09/93 Deviation: Failure to provide continuous air sampling.

Descxiption Air sampling hose became disconnected from pump o f Problem: during the sampling period.

Corrective Repaired sampling equipment and verified Action: operability.

HP3:1/RADENVOP.PTN

1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Ec 4 TABLE 1B ANALYSES WITH LLDs ABOVE TABLE 4.12-1 DETECTION CAPABILITIES 1/1/93 - 12/31/93 The values specified in Table 4.,12-1, Detection Capabilities, were achieved for all samples.

HP3: 1/RADENVOP . PTN

1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Ec 4 TABLE 2 LAND USE CENSUS Distance to Nearest a b 6/93 Milk (c) 6/93 6/93 Sector Animal Residence Garden (d)

L (e) 2.1/3S0 (g) 0 (f) 0 NE 0 ENE 0 ESE SE SSE 0 SSW SW WSW W L 3.6/302 (h) L L (g) 3.6/308 4.7/328 4 '/328 HP3:1/RADENVOP.PTN

1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Ec 4 TABLE 2 LAND USE CENSUS NOTES

a. All categories surveyed out to 5 miles radius from the Turkey Point Plant.
b. The following format is, used to denote the location:

distance (miles)/bearing (degrees) l c.

d.

e.

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 more.

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

feet or

f. 0 denotes that the sector area is predominantly an ocean area.
g. Non-residential occupied buildings in these sectors include the following:

Sector Distance N 1. 8/349 24-hour Security Staffing Building 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 HP3:1/RADENVOP.PTN

1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 6c 4 ATTACHMENT A 0 KEY TO SAMPLE LOCATIONS HP3:1/RADENVOP.PTN

0 1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Ec 4 Cc ~C' Ctt NNW-2 Day bee conO oUght

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SSE-1 Y Turtle Point Turkey Point Sampling Locations Plant Site Area

1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Sc 4 NNE-22 T -64,12 miles 8 T-67 I srr 5'I N -10 Soa Sr ~a a Chal lar

~ Sa

-10 Osvltr i

NW -10 IraaaI

~ \v Qar ~ /~

taaadaf Ca a

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~ r54rNt

~ Ort rr at rtrr aa arwrrrtaa

~ ~ ~

~ aaa WNW-10 "..F,= NW-5 T-57 a ra ra aa T-52 W-5 T-40 vaa I ~ row rtrratr

~ art55 aa 51 arCra Sw 5~ ~ 5

~ ~

M ~A WSW-8 5IOOEL t.AIIO CAHAt.

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6 SSE-10 Ir arrr (aaa

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SSW-10 I 5 I'~ S-10

""""-.j Turkey Point Sampling Locations / /';

1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 &, 4 ATTACHMENT A Page 1 of 4 PATHWAY: DIRECT RADIATION SAMPLES COLLECTED: TLD SAMPLE COLLECTION FREQUENCY: QUARTERLY Location" Name 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 & U.S. N1 NW-1 Turkey Point Entrance Road NW-5 Mowry Drive & 117th Avenue NW-10 Newton Road, North of Coconut Palm Drive WNW-10 Homestead Middle School On-Site, North Side of Discharge Canal W-5 Palm Drive & Tallahassee Road W-9 Card Sound Road, 0.6 mile from U.S. g1 WSW-8 Card Sound Road, 3.4 miles from U.S. N1 SW-1 On-Site near Land Utilization Offices SW-8 Card Sound Road, 5 miles from U. S. Nl SSW-5 On-Site, Southwest Corner of Cooling Can als SSW-10 Card Sound Road, west side of Toll Plaza S-5 On-Site, South East Corner of Cooling Can als 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)

HP3: 1/RADENVOP. PTN

1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Ec 4 ATTACHMENT A Page 2 of 4 PATHWAY: AIRBORNE SAMPLES COLLECTED: RADIOIODINE AND PARTICULATES SAMPLE COLLECTION FREQUENCY: WEEKLY Approximate Location Direction Distance Name Descri tion Florida City Substation Interim Alternate to T-51 T-58 NW 1 Turkey Point Entrance Road T-71 NNE 0.5 Florida City Sutstation Interim - Alternate to T-57 T-72 WSW Turkey Point Boy Scout Camp ntrol:

T-64 22 Natoma Substation HP3:1/RADENVOP.PTN

0 1993 e ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Sc 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 <1 Biscayne Bay at Turkey Point T-81 S 6 Card Sound, near Mouth of Old Discharge Canal Control:

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 Descri tion T-42 ENE <1 Biscayne Bay at Turkey Point A1A T-81 S 6 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 HP3:1/RADENVOP.PTN

0 1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Ec 4 ATTACHMENT A Page 4 of 4 PATHWAY: INGESTION SAMPLES COLLECTED: CRUSTACEA AND FISH SAMPLE COLLECTION FREQUENCY: SEMI-ANNUALLY Approximate Location Direction Distance Name Descri tion T-81 Card Sound Vicinity of Turkey Point Facility Control:

N, NNE 13-18 Near Biscayne Bay, Vicinity of Cutler Park, North to Matheson Hammock Park SAMPLES COLLECTED: BROAD LEAF VEGETATION SAMPLE COLLECTION FREQUENCY: MONTHLY Approximate Location Direction Distance Name 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 HP3: 1/RADENVOP . PTN

1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 Sc 4 ATTACHMENT B RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE 1993 First Quarter, 1993 Second Quarter, 1993 Third Quarter, 1993 Fourth Quarter, 1993 HP3:1/RADENVOP.PTN

4 RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY 'S TURKEY POINT SITE First Quarter, 1993 Office of Radiation Control l Florida Department. of Health and Rehabilitative Services

TURKEY POINT SITE Technical Specifications Sampling First Quarter, 1993 Collection Locations Number of Sam le T e Fre uenc

1. Direct Radiation Quarterly 22 42
2. Airborne 2.a Air Iodines Weekly 65 2.b Air Particulates Weekly 69*
3. Waterborne 3.a Surface Water Monthly 3.b Shoreline Sediment Semiannually
4. Ingestion I

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

  • Includes NRC split samples.

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

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

DIRECT RADIATION TLDs micro-R hour Each result is the average net response of two dosimeters.

Sample Site

'eployment Collection 12-16-92 03-24-93 N-2 (A)

N-7 (A)

N-10 (~)

NNW-2 (G)

NNW-10 (B) < (D)

NW-1 (A)

NW-5 (A)

NW-10 (A)

WNW-10 (A)

W-1 (A)

W-5 (A)

W-9 (A)

WSW-8 (A)

SW-1 (A)

SW-8 (A)

SSW-5 (A)

SSW-10 (B)

S-5 (A)

S-10 (A)

SSE-1 (A)

SSE-10 (A)

NNE-22 (A)

The dosimeters for the first quarter, 1993, were accidentally exposed to a container of radioactive sources while they were being transported from Miami to Orlando on March 25, 1993.

Although two control dosimeters did accompany the field dosimeters on this trip, the two control dosimeters gave widely differing results for the exposures they measured--

25.5 mR and 36.1 mR. (An exposure of approximately 1.0 mR would be normal for the six-day interval that the control dosimeters measured.) Many of the dosimeters from the respective field locations also showed wide differences between the different individual dosimeters for a given site. Due to the combined effects of the "poor geometry" of the radiation field, possible random shifting of the positions of the array of dosimeters and of the sources within their container during transportation, and effects of dosimeters near the sources apparently having shielded some of the low-energy radiation from reaching dosimeters farther away from the sources, it will not be possible to correct for this accidental exposure nor to recover any reasonable measurement data from the affected dosimeters.

1 These dosimeters were found lying on the ground near where they had been deployed.

~ (G) These dosimeters were missing when The dosimeters for site NNW-10 rut, and they had been crushed.

collection was attempted.

were found lying in a tire

2.a IODINE-131 IN WEEKLY AIR FILTERS Ci m3 Sam le Site Collection Date T52 T58 T64 T71 T72 01-07-93 <0.01 <0.01(A) <0.01 <0.01 <0. 01 01-12-93 <0.02 <0. 02 <0.02 <0.02 <0 '2 01-19-93 <0.01 <0.01 <0.01 <0.01 <0.01 01-26-93 <0.01 <0.01 <0.01 <0.01 <0.01 02-03-93 <0. 02 <0.02 <0.02 <0.02 <0 ~ 02 02-08-93 <0. 03 <0.03 <0.03 <0.03 <0.03 02-16-93 <0 '2 <0.02(B) <0.02 <0.02 <0 '2 02-22-93 <0.03 <0.03, <0.03 <0.03 <0.03 03-02-93 <0.03 <0. 03 <0.03 <0.03 <0.03 03-09-93 <0.01 <0.01 <0.01 <0.01 <0.01 03-16-93 <0.02 <0.02 <0.02 <0.02 <0.02 03-25-93 <0.02 <0.02 <0.02 <0.02 <0.02 03-31-93 <0.01 <0.01 <0.01 <0.01 <0.01 (A) This sample had a low volume due to a low flowrate setting.

(B) The sampling equipment was moved from the FP&L Wellness Center back to the Plant Entrance Road area at the beginning of this sample.

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

Supplementary air sample site T71 is substitute for Technical Specifications site by Hurricane Andrew.

now being temporarily used as a T51, which was destroyed I

0 0

4

Collection Sam le Site Date T52 T58 T64 T71 T72 01-07-93 0.009 + 0.001 (AO. 005 + 0.002 0. 009 + 0. 001 0.004 + 0.001 0.005 + 0.001 01-12-93 <0.006 0. 007 + 0.002 0.007 + 0.002 0.004 + 0.002 <0.007 01-19-93 0.010 + 0.002 0. 011 + 0.002 0.015 + 0.002 0.013 + 0.002 0.010 + 0.002 01-26-93 0.010 + 0.002 0. 008 + 0.002 0.010 + 0.002 0.011 + 0.002 0.012 + 0.002 02-03-93 0. 018 + 0. 002 0. 013 + 0. 002 0.018 + 0.002 0.013 + 0.002 0.016 + 0.002 02-08-93 0.009 + 0.002 0.007 + 0.002 0.004 + 0.002 0.009 + 0.002 0.009 + 0.002 02-16-93 0.013 + 0.002 (B*0.013 + 0.002 0.012 + 0.002 0.012 + 0.002 0.012 + 0.002 02-22-93 0.022 + 0.003 *0.015 + 0.002 0.014 + 0.002 0.017 + 0.002 0.023 + 0.003 03-02-93 0. 014 + 0.002 *Q 013 + 0. 002 0. 014 + 0. 002 0. 013 + 0. 002 0. 014 + 0.002 03-09-93 0. 017 + 0.002 *Q 016 + 0. 002 0. 019 + 0.002 0.018 + 0.002 0. 018 + 0.002 03-16-93 0. 018 + 0.002 0. 015 + 0.002 0.016 + 0.002 0.013 + 0.002 0. 013 + 0.002 03-25-93 0.004 + 0.001 0. 002 + 0.001 0.003 + 0.001 0.004 + 0.001 <0 .003 03-31-93 0.009 + 0.002 0. 012 + 0.002 0.011 + 0.002 0.009 + 0.002 0.010 + 0.002 Means: 0.012 + 0.001 0.011 + 0.001 0. 012 + 0. 001 0.011 + 0.001 0.011 + 0.001

  • NRC split samples.

(A) This sample had a low volume due to a low flowrate setting.

l (B) The sampling equipment was moved from the FP&L Wellness Center back to the Plant Entrance Road area at

/

the beginning of this sample.

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

Supplementary air sample site T71 is now being temporarily used as a substitute for Technical Specifications site T51, which was destroyed by Hurricane Andrew.

2.b AIR PARTICULATES GAMMA SCANS OF UARTERLY COMPOSITES Ci m3 First Quarter, 1993 Sample Site Be-7 K-40 Cs-134 Cs-137 T52 0.1052 + 0.0108 <0. 0211 <0.0008 <0.0011 T58 0.1218 + 0.0118 <0.0227 <0.0009 <0.0007 T64 0.1319 + 0.0112 <0.0215 <0.0011 <0.0013 Tjl 0.1304 + 0.0108 <0.0201 <0.0012 <0.0008 T72 0.1145 + 0.0107 <0.0188 <0.0011 <0.0011 I

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

Supplementary air sample site T71 is now being temporarily used as a substitute for Technical Specifications site T51, which was destroyed by Hurricane Andrew.

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

T42 01-13-93 <138 214 + 31 <3 <8 <4 <4 , <9 <8 <8 <5 <6 02-15-93 <134 239 + 34 <3 <8 <3 <4 <8 <8 <6 <4 <4 <4 03-15-93 <138 303 + 36 <4 <7 <5 <5 <10 <6 <5 <5 <4 <5 T67 01-13-93 <138 147 + 27 <4 <8 <4 <4 <9 <7 <8 <4 <4 <7 02-15-93 <134 282 + 35 <3 <10 <5 <4 <9 <8 <6 <4 <4 <6 03-15-93 <138 <80 <3 <9 <4 <3 <7 <7 <5 <4 <4 <5 T81 01-13-93 559 + 52 227 + 34 <4 <8 <4 <4 <11 <8 <7 <5 <4 <6 02-11-93 -

186 + 44 258 + 38 <4 <8 <4 <4 <8 <4 <6 <4 <4 <8 03-12-93 <138 278 + 38 <4 <9 <4 <5 <7 <6 <7 <4 <4 <4

/

(A) These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.

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

3.b SEDIMENT Ci k dr wei ht Sample Collection Site Date K-40 Co-58 Co-60 Co-134 Cs-137 Others T42 01-14-93 176 + 69 375 + 71 <13 <12 <12 Ra-226: 669 + 23 Th-232: 57 + 26 T67 01-13-93 94 + 31 117 + 42 <6 <7 <8 <9 Ra-226: 152 + 10 T81 01-13-93 153 + 49 319 + 65 <8 <10 <10 Ra-226: 469 + 20 U-235: 83 + 33 4.a.l CRUSTACEA Blue Crab Ci k wet wei ht Sample Collection Site Date K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 03-09-93 1198 + 170 <19 <19 <10 <13 <43 <18 <20 ND ND T81 03-04-93 1447 + 177 <17 <44 <17 <21 <44 <15 <19 256 + 26 ND 4.a.2 FISH Mixed S ecies Ci k wet wei ht Sample Collection Site Date K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 03-08-93 1187 + 162 <17 <38 <14 <15 (31 <19 <19 ND ND T81 03-04-93 1701 + 191 <13 (39 <17 <24 <32 <19 <23 ND ND ND Non-detectable.

4 b 1 BROAD EAF VEGE 0 B a 'l'a P e C wet we't Sample Collection Site Date Be-7 K-40 I-131 Cs-134 Cs-137 T40 01-15-93(A) 247 + 36 1952 + 102 <12 <8 <8 02-15-93 1117 + 72 4217 + 168 <10 <12 54 + 7 03-15-93 1017 + 58 3562 + 146 <11 <11 '13 + 5 T41 01-15-93(A) 1728 + 94 3915 + 182 <19 <14 28 + 6 02-15-93 1199 + 65 4973 + 166 <10 <ll 55 + 7 03-15-93 1002 + 65 3009 + 140 <10 <11 52 + 7 1645 + 83 3720 + 155 <17 <10 . 14 + 5 02-15-93 1419 + 69 4962 + 168 <10 <11 <11 03-15-93 871 + 71 3636 + 164 <11 <11 (A) Other species of green leafy vegetation were added to the Brazilian pepper for these samples because sufficient quantities of only Brazilian pepper were not available due to damage to the pepper trees caused by Hurricane Andrew.

0 f

'\

RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE Second Quarter, 1993 Office of Radiation Control Florida Department of Health and Rehabilitative Services

TURKEY POINT SITE Technical Specifications Sampling Second Quarter, 1993 Collection Locations Number of Sam le T e Fre uenc

1. Direct Radiation Quarterly 22 44
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.1 Crustacea Semiannually 4.a.2 Fish Semiannually 4.b Food Products 4.b.1 Broadleaf Monthly 10*

Vegetation Total: 197

  • - 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.

I 0

DIRECT RADIATION TLDs micro-R hour Each result is the average net response of two dosimeters.

Sample Deployment 03-24-93 Site Collection 06-17-93 N-2 (A) 6.9 + 0.4 N-7 5.7 + 0.3 N-10 5.7 + 0.3 NNW-2 (B) 5.1 + 0.3 NNW-10 6.0 + 0.3 NW-1 5' + 0.3 NW-5 5.3 + 0.3 NW-10 7 ' + 0.4 WNW-10 6.6 + 0.3 W-1 7.2 + 0.4 W-5 5.0 + 0' W-9 5.0 + 0.3 WSW-8 5 ' + 0.3 SW-1 '5.4 + 0.3 SW-8 5 ' + 0' SSW-5 5.3 + 0.3 SSW-10 (C) 5.4 + 0' S-5 5.4 + 0.3 S-10 6.2 + 0' SSE-1 5.3 + 0.3 SSE-10 6.3 + 0' NNE-22 6.4 + 0.3 (A) The utility pole upon which the dosimeters for site N-2 were mounted had been removed during this sampling interval due to construction operations. The dosimeters were recovered attached to the pole which still was lying in a storage area at the site.

(B) -. The PVC container in which the dosimeters at site NNW-2 were deployed had been stolen. The dosimeters themselves were found hanging at the proper location in a plastic bag.

(C) The result for site SSW-10 is based on a single dosimeter due to failure of the other dosimeter.

2 ' IODINE-131 IN WEEKLY AIR FILTERS Ci m3 Sam le Site Collection Date T52 T58 T64 T71 T72 04-06-93 <0.01 <0 '1 E

<0 ~ 01 <0. 01 <0.01 04-13-93 <0.01 <0.01 <0.01 <0. 01 <0.01 04-20-93 <0.03 <0.03 <0.03 <0. 03 <0.03 04-27-93 <0.01 <0.01 <0.01 <0. 01 <0.01 05-03-93 <0.02 <0. 02 <0. 02 <0.02 <0.02 05-10-93 <0.01 <0. 01 <0.01 <0.01 <0.01 05-18-93 <0.01 <0 F 01 <0.01 <0.01 <0.01 05-25-93 <0.01 <0.01 <0.01 <0.01 <0.01 06-01-93 <0.01 <0.01 <0. 01 <0. 01 <0.01 06-08-93 <0.03 <0.03 <0. 03 <0.03 <0.03 06-14-93 <0.02 <0.02 <0 02

~ <0.02 <0.02 06-23-93 <0.02 <0.01 <0.02 <0.01 <0.01 06-29-93 <0 '3 <0.03 <0.03 <0.03 <0 '4 Supplementary air sample site T52 is now being temporarily used as a substitute for Technical Specifications site T57, which was destroyed t by Hurricane Andrew.

Supplementary air sample site T71 is now being temporarily used as a substitute for Technical Specifications site T51, which was destroyed by Hurricane Andrew.

2.b AIR PARTICULATES GROSS BETA Ci m3 Collection Sam le Site Date T52 T58 T64 T71 T72 04-06-93 0. 014 + 0.002 0. 016 + 0.002 0.016 + 0.002 0.013 0. 002 0.011 + 0. 002 04-13-93 0.018 + 0.002 0. 013 + 0.002 0.013 + 0.002 0.011 0.002 0.014 + 0.002 04-20-93 0.018 + 0.002 0.019 + 0.002 0.015 + 0.002 0. 016 0.002 0.019 + 0.002 04-27-93 0.015 + 0.002 0.017 + 0.002 0.016 + 0.002 0.019 0.002 0.020 + 0.003 05-03-93 0.017 + 0.003 0.015 + 0.003 0.013 + 0.002 0.013 0.002 0.014 + 0.003 05-10-93 0.016 + 0.002 *0.007 + 0.002 0.009 + 0.002 0.009 0.002 0.013 + 0.002 05-18-93 0.013 + 0.002 *0.015 + 0.002 0.017 + 0.002 0.012 0.002 0.016 + 0.002 05-25-93 0.017 + 0.002 *0.012 + 0.002 0.015 + 0.002 0.019 0.002 0.014 + 0.002 06-01-93 0.006 + 0.002 *0.006 + 0.002 0.009 + 0.002 0.008 0.002 0.007 + 0.002 06-08-93 0.006 +'0.002 0.006 + 0.002 0.006 + 0.002 0.008 0.002 0.008 + 0.002 06-14-93 0.006 + 0.002 0.015 + 0.002 0.015 + 0.002 0.014 0.002 0.015 + 0.002 06-23-93 0.009 + 0.002 0.008 + 0.001 0.007 + 0.002 0.008 + 0.001 0.009 + 0.001 06-29-93 0.017 + 0.002 0.022 + 0.003 0.024 + 0.003 0.027 0.003 0.025 + 0.003 Means: 0.013 + 0.001 0.013 + 0.001 0.013 + 0.001 0.014 + 0.001 0.014 + 0.001

  • - NRC split samples.

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

Supplementary -air sample site T71 is now being temporarily used as a substitute for Technical Specifications site T51, which was destroyed by Hurricane Andrew.

2.b AIR PARTICULATES GAMMA SCANS OF UARTERLY COMPOSITES Ci m3 Second Quarter, 1993 Sample Site Be-7 K-40 Cs-134 Cs-137 T52 0.1246 + 0.0118 <0. 0199 <0.0009 <0.0008 T58 0.1596 + 0.0132 <0. 0195 <0.0012 <0.0011 T64 0.1597 + 0.0145 <0.0149 <0.0016 <0.0006 T71 0.1485 + 0.0138 <0.0155 <0.0012 <0.0008 T72 0.1431 + 0.0126 0.0178 + 0.0067 <0.0006 <0.0011

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

T42 04-19-93 <136 348 + 37 <4 <8 <4 <4 <8 <6 <6 <5 <4 <5 05-17-.93 <136 327 + 40 <4 <10 <4 <5 <9 <7 <7 <3 <5 <7 06-09-93 <143 297 + 39 <4 <9 <4 <6 <10 <6 <8 <3 <4 <4 T67 04-19-93 <136 185 + 32 <4 <9 <4 <5 <8 <9 <8 <4 <4 <6 05-17-93 <136 358 + 38 <4 <8 <4 <5 <8 <6 <7 <4 <5 <6 06-11-93 <143 173 + 31 <5 <9 <4 <4 <9 <8 <7 <3 <4 T81 04-19-93 <136 332 + 37 <4 <11 <4 <4 <10 <7 <7 <4 <4 <7 05-17-93 <136 375 + 37 <4 <7 <4 <5 <11 <6 <7 <4 <4 <8 06-09-93 937 + 59 308 + 39 <4 <9 <4 <4 <8 <7 <9 <5 <4 <5 (A) These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.

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

4.b.l 'ROADLEAF VEGETATION Brazilian Pe er Ci k wet wei ht Sample :Collection Site Date Be-7 K-40 1-131 Cs-134 Cs-137 Ra-226 T40 04-19-93 1020 + 69 2709 + 135 <15 <10 21+ 5 ND

  • 05-18-93 546 + 55 3972 + 156 <13 <12 31+7 ND 06-11-93 791 + 63 4478 + 165 <21 <9 30+ 6 27+ 9 T41 04-19-93 632 + 52 3307 + 125 <10 23+5 ND 05-17-93 792 + 74 4143 + 170 <17 <12 65+9 ND 06-14-93 870 + 63 3724 + 149 <19 116 + 8 ND T67 04-19-93 1415 + 74 3263 + 151 <17 <9 <12 ND 05-17-93 766 + 60 4080 + 167 <16 <13 <12 ND 06-11-93 924 + 73 4646 + 181 <22 <10 ND
  • NRC split sample. ND - Non-detectable.

4 RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY '

TURKEY POINT SITE Third Quarter, 1993 Office of Radiation Control Florida Department of Health and Rehabilitative Services

0 TURKEY POINT SITE 0 Technical Specifications Sampling Third Quarter, 1993 Collection Locations Number of Sam le T e Fre uenc Sam led Sam les

1. Direct Radiation Quarterly 22 42
2. Airborne 2.a Air Iodines Weekly 65 2.b Air Particulates Weekly 68*
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: 198
  • Includes NRC split samples.

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

Measurement results that are not significantly above background are reported as "non-detectable" (ND) or as less than a Lower Limit of Detection (<LLD), which is an estimated upper limit (with at least 95~ confidence) for the true activity in the sample.

DIRECT RADIATION TLDs micro-R hour Each result is the average net response of two dosimeters.

Sample Deployment 06-17-93 Site Collection 09-22-93 N-2 (A) 6.3 + 0.3 N-7 5.6 + 0' N-10 5.4 + 0' NNW-2 (B) 5.1 + 0.3 NNW-10 6.2 + 0.3 NW-1 5.4 + 0.3 NW-5 (C)

NW-10 7.7 + 0.4 WNW-10 6.4 + 0.3 W-1 6.8 + 0.4 W-5 5.7 +

'+

0.3 W-9 5.4 0.3 WSW-8 5.3 + 0.3 SW-1 6.1 + 0.3 SW-8 5.4 + 0.3 SSW-5 5.9 + 0.3 SSW-10 (D) 5.2 + 0' S-5 5.7 + 0.3 S-10 6.5 + 0.3 SSE-1 5.6 + 0.3 SSE-10 (D) 6.6 + 0.4 NNE-22 6.3 + 0.3 (A) These dosimeters for site N-2 were deployed at a new location at this site due to construction operations at the previous location.

(B) - These dosimeters for site NNW-2 were moved much higher on their utility pole in attempt to reduce the frequency of vandalism t

an at this site.

(C) The dosimeters for site NW-5 were missing when collection was attempted.

(D) The results for sites SSW-10 and SSE-10 are each based on single dosimeters due to anomalous behavior of the other dosimeters.

e" IODINE-131 IN WEEKLY AIR FILTERS Sam le Site Ci m3 Collection Date T52 T58 T64 T71 T72 07-07-93 <0. 01 <0. 01 <0.01 <0.01 <0. 01 (A) 07-13-93 <0. 02 <0. 02 <0.02 <0.02 <0. 01 (B) 07-19-93 07-27-93

<0 '2

<0.01

<0.02

<0.01

<0.02

<0.01

<0.02

<0.01

<0.02

<0.01 08-02-93 <0. 02 <0. 02 <0.02 <0. 02 <0.02 08-12-93 <0. 02 <0. 02 <0.02 <0. 02 <0.02 08-18-93 <0. 02 <0 02

~ <0 F 01 <0. 02 <0.02 08-24-93 <0. 02 <0. 02 <0.02 <0. 02 <0.02 09-03-93 09-08-93 09-14-93

<0. 01

<0.04

<0.01

<0.01

<0.04

<0.01

<0.01

<0.04

<0.01

<0.01(C)

<0.04

<0.01

'0.01<0.04

<0.01 09-21-93 <0.01 <0.01 <0.01 <0.'01 <0.01 09-29-93 <0.01 <0.01 <0.01 <0.01 <0.01 (A) The sampling equipment had been disturbed during this sampling interval. The gas meter was knocked over and did not measure the full volume for this sample. This result is based on an estimated volume. Also, a counting geometry with higher than normal sensitivity was used for this sample.

(B) - The sampling equipment had been disturbed during this sampling interval. The particulate filter was not in place during most of this sample interval. The iodine filter cartridge did not appear to have been disturbed.

(C) A power outage is suspected to have occurred during this sample.

The equipment is estimated to have run for 205 hours0.00237 days <br />0.0569 hours <br />3.38955e-4 weeks <br />7.80025e-5 months <br /> out of the 238 total hours for this sampling interval.

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

by Hurricane Andrew.

Supplementary air sample site T71 is now being temporarily used as a substitute for Technical Specifications site T51, which was destroyed by Hurricane Andrew.

2.b AIR PART1CULATES GROSS BETA Ci m3 Collection Sam le Site Date T52 T58 T64 T71 T72 07-07-93 0.023 + 0.002 0.020 + 0.002 0.026 + 0.002 0.024 + 0.002 (A0.021 + 0.002

,07-13-93 0.012 + 0.002 0.016 + 0.002 0.020 + 0.003 0.016 + 0.003 (B) 07-19-93 0.020 + 0.003 0.021 + 0.003 0.028 + 0.003 0.021 + 0.003 0.021 + 0.003 07-27-93 0.013 + 0.002 0.012 + 0.002 0.018 + 0.002 0.017 + 0.002 0.013 + 0.002 08-02-93 0.011 + 0.002 *0.012 + 0.003 0.019 + 0.003 0.014 + 0.003 0.013 + 0.003 08-12-93 0.020 + 0.002 *0.018 + 0.002 0.025 + 0.002 0.020 + 0.002 0.019 + 0.002 08-18-93 0.017 + 0.002 *0.016 + 0.002 0.019 + 0.002 0.011 + 0.002 0.014 + 0.002 08-24-93 0.015 + 0.002 *0.019 + 0.003 0.019 + 0.003 0.020 + 0.003 0.017 + 0.002 09-03-93 0.010 + 0.001 0.008 + 0.001 0.008 + 0.001 (C0.007 + 0.001 0. 008 + 0.001 09-08-93 0.012 + 0.002 0.012 + 0.003 0.011 + 0.002 0.007 + 0.002 0. 012 + 0.002 09-14-93 0.011 + 0.002 0.015 + 0.002 0.010 + 0.002 0.012 + 0.002 0. 012 + 0.002 09-21-93 0.009 + 0.002 0.007 + 0.002 0.008 + 0.002 0.009 + 0.002 0. 008 + 0.002 09-29-93 0.008 + 0.002 0.011 + 0.002 0.013 + 0.002 0.009 + 0.002 0. 010 + 0.002 Means: 0.014 + 0.001 0.'014 + 0.001 0.017 + 0.001 0.014 + 0.001 0.014 + 0.001

  • NRC split samples.

(A) The sampling equipment had been disturbed during this sampling interval. The gas meter was knocked over and did not measure the full volume for this sample. This result is based on an estimated volume.

(B) The sampling equipment had been disturbed during this sampling interval. The holder for the particulate filter was detached from the air hose soon after the beginning of this sample, and the filter itself was severely damaged. No meaningful analysis could be performed on this filter.

(C) A power outage is suspected to have occurred during this sample. The equipment is esti-mated to have run for 205 hours0.00237 days <br />0.0569 hours <br />3.38955e-4 weeks <br />7.80025e-5 months <br /> out of the 238 total hours for this sampling interval.

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

Supplementary air sample site T71 is now being temporarily used as a substitute for Technical Specifications -site T51, which was destroyed by Hurricane Andrew.

0

~c 0

AIR PARTICULATES GAMMA SCANS OF UARTERLY COMPOSITES Ci m3 Third Quarter, 1993 Sample Site Be-7 K-40 Cs-134 Cs-137 T52 0.1133 + 0.0106., <0.0201 <0.0012 <0.0009 T58 0.1086 + 0.0110 -<0.0206 <0.0011 <0.0011 T64 0.1165 + 0.0104 <0.0206 <0.0009 <0.0010 T71 0.1180 + 0.0112 <0.0275 <0.0012 <0.0008 T72 0.1079 + 0.0115 <0.0184 <0.0011 <0.0010 Supplementary air sample site T52 is now being temporarily used as a substitute for Technical Specifications site T57, which was destroyed by Hurricane Andrew.

Supplementary air sample site T71 is now being temporarily used as a substitute for Technical Specifications site T51, which was destroyed by Hurricane Andrew~.

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

T42 07-13-93 <137 338 + 38 <4 <10 <3 <4 <8 <7 <6 <5 <4 <7 08-18-93 87 + 41 400 + 39 <3 <8 <4 <4 <8 <8 <5 <4 <5 <7 09-16-93 <134 289 + 33 <3 <8 <4 <4 <9 <7 <6 <4 <3 <5 T67 07-19-93 <137 252 + 32 <3 <9 <3 <4 <9 <7 <5 <4 <4 <6 08-19-93 <131 326 + 37 <4 <8 <4 <5 <8 <8 <5 <3 <3 <5 09-17-93 <134 249 + 33 <3 <6 <4 <4 <9 <6 <6 <5 <3 <5 T81 07-14-93 210 + 46 317 + 38 <5 <9 <4 <5 <10 <8 =

<7 <6 <7 08-18-93 159 + 43 305 + 36 <4 <8 <4 <5 <8 <6 <6 <4 <4 09-16-93 <136 334 + 38 <4 <9 <4 <6 <7 <7 <7 <5 <3 <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.

3.b SEDIMENT Ci k dr wei ht Sample Collection Site Date Be-7 K-40 Co-58 Co-60 Cs-134 Cs-137 Ra-226 Th-232 T42 07-14-93 184 + 55 321 + 72 <10 <11 <13 627 + 21 ND T67 07-12-93 <66 185 + 41 <6 <5 <7 <6 62 + 24 50 + 12 T81 07-14-93 118 + 38 233 + 58 <8 <8 <7 <7 297 + 13 50 + 16 4.a.l CRUSTACEA Blue Crab Ci k wet wei ht Sample Collection Site Date K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 08-19-93  : 1353 + 191 <16 <38 <19 <20 <44 <21 <18 ND ND T81 We were not able to schedule attempts to collect this sample. Efforts continue.

4.a.2 FISH T67: Needlefish Ci k wet wei ht Sample Collection Site Date K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 09-13-93 4171 + 299 <23 <48 <23 <26 <49 <25 <25 ND ND

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

ND Non-detectable.

0 4.b.1 BROADLEAF VEGETATION Brazilian Pe er Ci k wet wei ht Sample Collection Site Date Be-7 K-40 1-131 Cs-134 Cs-137 T40 07-19-93 650 + 54 3600 + 148 <11 <8 36+ 6 08-20-93 1761 + 79 3656 + 149 <13 <10 23 + 7 09-17-93 2262 + 89 3875 + 159 <24 <11 88 + 8 1142 + 67 4025 + 161 <12 <10 98 + 8 08-20-93 1534 + 82 2558 + 124 <13 <9 426 + 14 09-17-93 2071 + 96 3481 + 150 <24 <10 192 + 10 T67 07-19-93 730 + 50 - 4500 + 161 <10 <11 <10 08-19-93 1047 + 59 4973 + 155 <11 <10 <11 09-17-93 1024 + 74 5349 + 187 <23 <10 <12

RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE Fourth Quarter, 1993 Office of Radiation Control Florida Department of Health and Rehabilitative Services

TURKEY POINT SITE Technical Specifications Sampling Fourth Quarter, 1993 Collection Locations Number of Sam le T e Fre enc

1. Direct Radiation Quarterly 22 21
2. Airborne 2.a Air Iodines Weekly 5 64 2.b Air Particulates Weekly 68*
3. Waterborne 3.a Surface Water Monthly 3.b Shoreline Sediment Semiannually
4. Ingestion 4.a Fish and Invertebrates 4.a.1 Crustacea Semiannually 4.a.2 Fish Semiannually 4.b Food Products 4.b.1 Broadleaf Monthly 10*

Vegetation Total: 174

  • Includes NRC split samples.

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

Measurement results that are not significantly above background are reported as "non-detectable" (ND) or as less than a Lower Limit of Detection (<LLD), which is an estimated upper limit 0 (with at least 95% confidence) for the true activity in the sample.

0 DIRECT RADIATION - TLDs micro-R hour Sample Deployment 09-22-93 Si e C lection 2 3 (A)

N-2 5.54 + 0.17 N-7 4.79 + 0.15 N-10 (B) 4.94 + 0.16 NNW-2 4.36 + 0.14 NNW-10 5 '8 + 0.17 NW-1 4.65 + 0.13 NW-5 4.74 0 ~ 13 NW-10 7.55 + 0.27 WNW-10 (C)

W-1 6.38, + 0. 17 W-5 4.35 + 0.14 W-9 4.60 + 0.14 WSW-8 r

4.80 + 0.16 SW-1 4.91 + 0.14 SW-8 4.94 + 0.15 SSW-5 4.89 + 0.16 SSW-10 (B) 5.00 + 0.15 S-5 4 ~ 43 + 0.13 S-10 5.38 + 0.19 SSE-1 4.59 + 0.14 SSE-10 5.65 + 0.16 NNE-22 5.84 + 0.16 (A) All of the above results were obtained using Panasonic UD-814 environmental dosimeters and a Panasonic UD-706A TLD reader.

Previous results in recent years were obtained using Victoreen CaF2.Mn TLD bulbs and a Harshaw 2000 TLD reader, which are now obsolete. All subsequent results will be obtained using the Panasonic equipment, until equipment.

it needs to be replaced with newer (C) This dosimeter was missing when collection was attempted.

t 0

IODINE-131 IN WEEKLY AIR FILTERS Ci m Sam le Site Collection Date T52 T58 T64 T71 T72 10-05-93 <0.02 <0. 02 <0.02 <0. 02 <0 02

~

10-12-93 <0.03 <0. 03 <0.03 <0. 03 (A) <0. 03 10-20-93 <0.01 <0. 01 <0.01 <0.01 <0. 02 (B) 10-25-93 <0.02 <0.02 <0.02 <0.02 <0 02

~

11-02-93 <0. 01 <0.01 <0.01 <0. 01 <0. 01 11-09-93 11-16-93 (G)

<0. 03

<0.01

<0;02

<0.01

<0.02

<0 '2

<0.02

<0.01

<0.02 11-23-93 11-30-93

<0. 02

<0. 02

<0.02

<0.02

<0 '2

<0.02

<0.02

<0.02

<0.02

<0 '2 12-07-93 <0.01, <0.01 <0.01 <0.01 <0. 01 12-16-93 <0.02 <0.01 <0.01 <0.01 <0.01 12-22-93 <0.02 <0.02 <0.02 <0.02 <0.02 12-29-93 <0.02 <0.02 <0.02 <0.02 <0.02 t (A) This sample had a low (B) -

We believe a power collected volume with a normal flow rate.

outage occurred. The equipment is estimated to have run for 140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br /> out of the 168 total hours for this sampling interval.

Sampling was interrupted during the mid-part of this sample due to disruption of the sampling equipment by high winds. The equipment is estimated to have run for 110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br /> out of the 191 total hours for this sampling interval. Also, the air hose may have been loose during the early part of this sample.

(C) There was no~sample because an air hose became disconnected near the beginning of this sampling interval.

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

t Supplementary air sample site T71 is substitute for Technical Specifications site by Hurricane Andrew.

now being temporarily used as a T51, which was destroyed

2.b AIR PARTICULATES GROSS BETA Ci m3 Collection Sam le Site Date T52 T58 T64 T71 T72 10-05-93 0.011 + 0.002 0.013 + 0.002 0.012 + 0.002 0.010 + 0.002 0.005 + 0.002 10-12-93 0.008 + 0.002 0.007 + 0.002 0.006 + 0.002 <0.007(A) 0.005 + 0.002 10-20-93 0.009 + 0.002 0.012 + 0.002 0.012 + 0.002 0.012 + 0.002 (B0.006 + 0.002 10-25-93 0.011 + 0.003 0.006 + 0.002 0.010 + 0.002 0.007 + 0.002 0.007 + 0.002 11-02-93 0.010 + 0.002 0.010 + 0.002 0.011 + 0.002 0.010 + 0.002 0.011 + 0.002 11-09-93 (C) *0.013 + 0.002 0.014 + 0.002 0.014 + 0.002 0.017 + 0.002 11-16-93 0.007 + 0.002 *0.008 + 0.002 0.007 + 0.002 0.005 + 0.002 0-008 + 0.002 11-23-93 0.009 + 0.002 *0.010 + 0.002 0.014 + 0.002 0.008 + .0.002 0.008 + 0.002 11-30-93 0.014 + 0.002 *0.009 + 0.002 0.010 + 0.002 0.012 + 0.002 0-010 + 0.002 12-07-93 0. 017 + 0. 002 0.016 + 0.002 0.020 + 0.002 0.019 + 0.002 0.017 + 0.002 12-16-93 0. 018 + 0. 002 0.017 + 0.002 0.020 + 0.002 0.018 + 0.002 0.019 + 0.002 12-22-93 0.012 + 0.002 0.012 + 0.002 0.011 + 0.002 0.009 + 0.002 0-014 + 0.002 12-29-93 0.016 + 0.002 0.017 + 0.002 0.012 + 0.002 0.018 + 0.002 0 '12 + 0.002 Means: 0.012 + 0.001 0.012 + 0.001 0.012 + 0.001 0.012 + 0.001 0.011 + 0.001

  • NRC split samples.

(A) This sample had a low collected volume with a normal flow rate. He believe that a power outage occurred. The equipment is estimated to have run for 140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br /> out of the 168 total hours for this.sampling interval.

(B) Sampling was interrupted during the mid-part of this sample due to disruption of the sampling equipment by high winds. The equipment is estimated to have run for 110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br /> out of the 191 total hours for this sampling interval. Also, the air hose may have been loose during the early part of this sample.

(C) There was no sample because an air hose became disconnected near the beginning of this sampling interval.

Supplementary air sample site T52 is now being temporarily used as a substitute for Technical Specifications site T57, which was destroyed by Hurricane Andrew. Supplementary air sample site T71 is now being temporarily used as a substitute for Technical Specifications site T51, which was destroyed by Hurricane Andrew.

2.b AIR PARTICULATES GAMMA SCANS OF UARTERLY COMPOSITES Ci m3 Fourth Quarter, 1993 Sample Site Be-7 K-4 0 Cs-134 Cs-137 T52 0.1491 -+ 0;0152 <0.0127 <0.0011 <0.0008 T58 0. 1462 + 0.0121 <0.0159 <0.0013 <0.0008 T64 0. 1350 + 0.0116 <0.0217 <0.0009 <0 F 0008 T71 0.1420 + 0.0121 <0.0200 <0.0011 <0.0011 T72 0.1188 + 0.0120 <0.0217 <0.0013 <0.0008 Supplementary air sample site T52 is now being temporarily used as a substitute for Technical Specifications site T57, which was destroyed by Hurricane Andrew. Supplementary air site T71 is now being temporarily used as a substitute for Technical Specifications sitesample T51, which was destroyed by Hurricane Andrew.

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

T42 10-14-93 <131 257 + 34 <4 <10 <4 <5 <7 <5 <6 <4 <6 11-05-93 <140 201 + 38 <4 <10 <4 <5 <7 <7 <9 <4 <7 12-10-93 <135 235 + 36 <4 <7 <4 <5 <10 <8 <8 <4 <3 <5 T67 10-18-93 <131 196 + 39 <4 <9 <4 <5 <8 <8 <7 <4 <6 11-08-93 <127 94 + 32 <4 <6 <4 <4 <8 <5 <6 <3 <6 12-09-93 <135 130 + 27 <3 <7 <3 <5 <9 <6 <8 <3 <6 T81 10-14-93 129 + 42 344 + 39 <4 <8 <4 . <4 <10 <8 <7 <4 <5 11-05-93 93 + 40 184 + 35 <4 <10 <5 <3 <9 <7 <9 <4 <4 <7 12-09-93 <135 294 + 33 <4 <9 <4 <4 <8 <6 <8 <5 <9 (A) These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.

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

4.a.1 CRUSTACEA Blue Crab Ci k wet wei ht Sample Collection Site Date K-4 0 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T81 11-03-93 2887 + 599 <68 <137 <66 <69 <149 <70 <68 911 + 269 ND 4.a.2 FISH Mixed S ecies Ci k wet wei ht Sample Collection Site Date K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 -Cs-137 Ra-226 Ra-228 T81 11-03-93 2327 + 299 <26 <64 <26 <27 <65 <28 <41 ND ND 4.b.1 BROADLEAF VEGETATION Brazilian Pe er Ci k wet wei ht Sample Collection Site Date Be-7 K-40 I-131 Cs-134 Cs-137 Ra-226 T40 ,10-19-93 1671 + 71 3615 + 146 <11 <9 16+ 4 ND

  • 11-09-93 1654 + 75 2442 + 118 <16 <8 45 + 5 48 + 10 12-10-93 1240 + 74 4282 + 159 <16 <9 49+7 ND T41 10-19-93 1505 + 79 2434 + 118 <17 <10 405 + 13 ND 11-09-93 1915 + 87 5690 + 201 <19 <11 37+ 8 ND 12-10-93 1753 + 74 3825 + 158 <15 <11 148 + 10 ND T67 10-1'8-93 1662 + 77 3299 + 143 <16 <9 <18 ND 11-08-93 1302 + 71 3710 + 149 <20 <12 <10 ND 12-09-93 1053 + 63 3537 + 134 <14 <10 <10 ND
  • NRC split sample. ND Non-detectable.

k 0

1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT, UNITS 3 & 4 ATTACHMENT C RESULTS FROM THE INTERLABORATORY COMPARISON PROGRAM 1993 HP3: 1/RADENVOP . PTN

FLORIDA DEPT. OF HRS - EPA INTERLABORATORY CROSS-CHECK PROGRAM DATA January through June, 1993 Media Nuclide Collection EPA Units Normal. Mean of N.D.K. Action Mon Day Yr Known Range Analyses Level WATER Alpha 01 29 93 34 pCi/L 0.656 145.67 21.49 1 WATER Beta 01 29 93 44 pCi/L 0.236 45.67 0.58 WATER Co-60 06 11 93 15 pCi/L 0.000 14.00 -0.35 WATER Zn-65 06 11 93 103 pCi/L 0.118 106.67 0.64 WATER Ru-106 06 11 93 119 pCi/L 0.049 103.33 -2.26 WATER Ba-133 06 11 93 99 pCi/L 0.059 95.33 -0.64 WATER Cs-134 06 11 93 5 pCi/L 0.000 5.00 0.00 WATER Cs-137 06 11 93 5 pCi/L 0.118 4.67 -0.12 WATER H-3 06 04 93 9844 pCi/L 0 '72 9756.67 -0.15 WATER I-131 02 05 93 100 pCi/L 0.177 98.67 -0.23 WATER Sr-89 01 15 93 15 pCi/L 0.236 12.00 -1.04 WATER Sr-90 01 15 93 10 pCi/L 0.118 7.67 -0.81 NOTES:

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

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

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

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

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

ACTION LEVEL:

Cause: The cause of the result exceeding the action level is not two-thirds known.

of the It should be noted, however, that participating laboratories in this cross-check exceeded the control limit.

Corrective Action: None at this time.

FLORIDA DEPT'F HRS EPA INTERLABORATORY CROSS-CHECK PROGRAM DATA July through December, 1993 Media Nuclide Collection EPA Units Normal. Mean of N.DE K. Action Mon Day Yr Known Range Analyses Level FILTER Alpha 08 27 93 19 pCi/F 0 000 F 21.00 0.69 FILTER Beta 08 27 93 47 pCi/F 0.000 50.00 1.04 FILTER Cs-137 08 27 93 9 pCi/F 0.000 10.00 0.35 FILTER Sr-90 08 27 93 19 pCi/F 0.354 13.67 -1.85 MILK I-131 09 24 93 120 pCi/L 0.148 117.00 -0.43 MILK Cs-137 09 24 93 49 pCi/L 0.236 49.67 0.23 MILK K 09 24 93 1679 mg/L 0.359 1591.33 -1.81 MILK Sr-89 09 24 93 30 pCi/L 0.354 16.67 -4.62 1 MILK Sr-90 09 24 93 25 pCi/L 0.118 15.33 -3.35 2 WATER Alpha 07 23 93 15 pCi/L 0.000 15.00 0.00 WATER Alpha 10 29 93 20 pCi/L 0.000 22.00 0.69 WATER Beta 07 23 93 43 pCi/L 0,341 47.00 1.00 WATER Beta 10 29 pCi/L 0.236 21.00 WATER WATER Co-60 Zn-65 ll 11 12 12 93 93 93 15 30 150 pCi/L pCi/L 0,118 0.158 2.08 29.33 -0.23 156.67 0.77 WATER Ru-106 11 12 93 201 pCi/L 0.148 186.00 -1.30 WATER Ba-133 11 12 93 79 pCi/L 0.148 76.00 -0.65 WATER Cs-134 11 12 93 59 pCi/L 0.236 54.00 -1.73 WATER WATER Cs-137 H-3 ll 12 93 40 7398 pCi/L pCi/L 0.118 42.67 0.92 11 05 93 0.079 7452.33 0.13 WATER I-131 10 08 93 117 pCi/L 0.049 112.67 -0 '3 WATER Sr-89 07 16 93 34 pci/L 0.118 30.33 1 27

~

WATER Sr-90 07 16 93 25 pCi/L 0.000 22.00 -1.04

I> ~

0

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

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

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

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

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

ACTION LEVEL:

Cause: Erroneously over estimated chemical recovery of strontium carrier.

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

(2) Cause: Erroneously over estimated chemical recovery of strontium carrier.

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

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