Text

1986 Annual Radiological Environ Operating Rept,Turkey Point Plant Units 3 & 4
	ML17347A458
Person / Time
Site:	Turkey Point
Issue date:	12/31/1986
From:	Woody C; FLORIDA POWER & LIGHT CO.
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	L-87-172, NUDOCS 8705060244
	Download: ML17347A458 (102)
	v • d • e

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REGULATORY INt" --.MATION DISTRIBUTION SYSTF~

(R IDS)

'CCESSION NBR: 8705060244 DOC. DATE,: 87/04/2cI NOTARIZED:

NO FACIL 50250 Turkey Point Planti Unit 3I Florida Power and Light C

50-251 Turkey Point Plant Unit 4 Florida Power -and Light C

AUTH. NAME AUTHOR AFFILIATION l4OODY> C. O.

Florida Power 8c Light Co.

RECIP. NAME RECIPIENT AFFILIATION DOCKET. 5 05000250 05000251 SUBJECT; "1986 Annual Radiological Environ Operating Rept Turk g

Point Plant Units 3 Kc 4. W/870426 1tr.

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TITLE: Environmental Monitoring Rept (per Tech Specs)

NOTES:

RECIPIENT ID CODE/NAME PD2-2 LA McDONALD>D

'NTERNAL: AEOD/DOA ARM TECH ADV RPPB ADE REQ FIL 02 R

2 FILE 01 EXTERNAL; NRC PDR COPIES LTTR ENCL 0

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1 RECIPIENT ID CODE/NAME PD2-2 PD AEOD/DSP/TPAB LPDR NRR/DREP/RPB RES SPEIS> T RGN2/DRSS/EPRPB COPIES LTTR ENCL 5

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P, O. BOX I4000, JUNO BEACH. FL 33408 FLORIDA POWER & LIGHT COMPANY APRIL 06 1987 L 87 l72 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gent lemen:

Re:

Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-25 I I 986 Annual Radiological Environmental 0 eratin Re ort This letter transmits the subject report in accordance with Technical Specification 6.9.4.b for Turkey Point Units 3 and 4.

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

Very truly yours, C. O. Wopd Group ge'President Nuclear Energy COW/SDF/gp Attachment cc:

Dr. J. Nelson Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant g0 SDF I /009/ I PEOPLE... SERVING PEOPLE

~ N

~-$*

). DOCK 0500 50 R

PDR

1986 ANNUALRADIOiXGICALENVIKNVl(%1'ALCH~TIKx REXCRI'URKl".Y POINI'LANI' KNITS hDS.

3 AND 4 DESCRIPI'ICN INIaaXX".rICN RADICXmICALENVIKN~rAL~1 azure PRCaRAM DISCUSSICN AND INIERPREI'ATICN OF RESULTS ENVIKMKNIALRADIOIXGICALMNI'KEIRPRCGRAM ANNUAL SQvhIRY DEVIATICNS/MISSING DATA ANALYSES WI'IH LLDs ABOVE TABLE 4.12-3 13EZFA I'ICN CAPABILITIES LAND USE CENSUS KEY '1Q SAMPLE LCCATICNS RADICIUGICAL SURVEILLANCZ OF E~JRRIDA PONER AND LIGHI'CMPANY'S ARM'Y POINI'ITE FIRST gIAEQl&,

1986 SECCND QUAILS%, 1986

'IHIRD QIPRHW, 1986 FCXHIH glARIER, 1986 RESULTS FRCM THE I

PRCGRAM, 1986 TABLE I TABLE 1A TABLE IB TABLE 2 ATZACEKKNTA ATZACH%Ã1' ATI'AGREE C
1986 ANNUALRADIQLCGICALENVIRQ4KNTALGPlXATIM HEXCEG'UFMH'OINI'LANI' UNITS N3S.
3 AND 4 INIRCGUCTICN
/
This report is suhnitted pursuant to.Specification 6.9 of Turkey Point, Units 3
8g 4 Technical Specifications.
The Annual Radiological EnviroxInental Operating Report provides information, sumnaries 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 No."3 -and Unit No. 4. Technical Specifications.
II.
RADIGLCGICALENVIRCHXÃfALM%I'ICK~PBCGRAM A.
~Pur ose:
The purpose of the ragiological environoental ttonitoring 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 fran station operation.
The radiological enviroxmental monitoring program also supplements the radiological effluent monitoring program by verifying that the'easureable concentrations of.radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurexmmts,and the modeling of the enviroanental exposure/pathways.
Pro ram13escri tion:
The Radxologxcal Enviroxmental Monitoring Program for the Turkey >oint Plant is conducted pursuant to Technical Specifications 4.12 of Turkey Point Units 3 h 4 Technical Specifications.
S le Locations es and Fre uencies:
Direct radiation gamna exposure rate is monitored continuously at 21 locations by thexmoluminescent dosixn.ters (TLD's).,TLD'.s,~e.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 gamna isotopic measurements.
c.
Surface water samples are collected fran three locations.
Samples are collected.and analyzed aunthly.
Analyses include ganma isotopic and tritimnmeasurements.
d.
Shoreline sedinant samples are collected frcm three locations coinciding with the locations, for surface water samples.
Samples are collected and analyzed semi-annually.
Sediment samples are analyzed by gamna isotopic measurements.
HP3:1
Cb
~
1986 ANNUAL RADIOLCGICALMVIRCt4%MZALOPERATIC REPCRI'URK%'OINI'LANE UNITS NOS.
3 AND 4 e.
Fish and invertebrate samples are each collected fran 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 gamna isotopic measurements.
f.
Broad leaf vegetation samples are collected fran three locations.
Samples are collected and analyzed monthly.
Broad leaf vegetation sanyles are analyzed by ganma isotopic measurements.
Attachment A provides specific information pertaining to sample locations, types and frequencies.
2.
Anal tical Res onsibilit Radiological enviroanental monitoring for the Turkey Point Plant is conducted by the State of Florida, Department of Health and Rehabilitative Services (HRS).
Samples're collected and analyzed by HRS personnel.
Samples are analyzed at the HRS Environmental Radiation Control Laboratory in Orlando, Florida.
Monitorin'ro rsm Annual ~Sumnar provides a sumnary for all specified samples collected during the referenced surveillance period.
Deviations fran the sample
schedule, missing data and/or samples not meeting the specified "A PRICRI" LID, if any, are noted and explained in Tables lA and lB respectively.
Analysis data for all specified samples analyzed during the surveillance period is provided in Attachment B.
D.
Land Use Census:
A land use census out to a distance of 5 miles radius fran 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 sumnary of the land use census for the surveillance year is provided in Table 2, Land Use Census
~Sumnar No locations yielding a calculated dose or dose cannitment greater than the values currently being calculated were identified by the land use census.
No locations yielding a calculated dose or dose ccamitment (via the same exposure pathway) 20 % greater than locations currently being sampled in the radiological enviromental monitoring program were identified by the land use census.
HP3: 1 E.
Interlaborator arison Pro ram:
The State of Florida Environmental Radiation Control Laboratory participates in the Enviromental Radioactivity Laboratory Intercazyarison Studies Program conducted by the Environmental Protection Agency.
Results frcm the Interlaboratory Canparison Program are provided in Attachment C.
(2)
1986 ANCHL RADIOLCGICAL ENVIRCNvKNI'ALOPERATING REE'CRT
~(EY FOIE'LPÃf - UNITS bDS.
3 PAD 0 I I I.
DISCUSSICN M3 INI'ERVETATICNCF RESULTS A.
Re ortin of Results:
The Annual Radiological Envirorrrmntal Operating Report contains the sunnaries, interpretations and information required by the Turkey Point Units 3 4 0 Technical Specifications.
Table 1 provides a su@nary of the measurements made for the nuclides required by Technical Specifications, Table 0.12-2, for all samples specified by Table 0.12-1.
In addition, sumaries are provided for other nuclides identified in the specified sarrples, including those not related to station operation.
These include nuclides such as
<0K, 232Th, 226Ra 228Ra 7'35U
238U, and 210Pb which are ccrmon in the Florida envirorrrant.
B.
Inter retation of Results 1.
Direct Radiation:
The results for direct radiation monitoring are consistent with past measurements for the specified locations.
The exposure rate data shows no indication of any trends attributed to effluents fran the plant.
The measured exposure rates are consistent with exposure rates that were observed during the preoperational surveillance program.
Direct radiation rronitoring results are sumerized in Table l.
2.
Air Particulates/Radioiodine:
The results for radioactive air-borne particulates and radioiodine were influenced by the passage of the ply resulting form the Chernobyl inicident.
The annual average gross beta measurement is 00/o higher than 1985.
Twenty-Five out of 259 sarrples collected showed results in excess of ten times the historical average.
These 25 san@les were collected during the late May early 3une plure passage.
Twelve of the 25 san@les indicated radioiodine-131 in excess of IvM.
The highest
value, 0.07 pCi/m3, was 52% of the repor.ting level identified in the Technical Specifications.
Additionally, radiocesiun 130 R 137 were detected by garnna spectroscopy at a maximm level of 0.0&o R 0.037/o of the Technical Specification Reporting Levels.
Rutheniun-103 was also identified.
Samples collected before and after the plure passage yielded results consistent with past rn asurem nts.
HP3:1 (3)
1986 PbNUAL RADIOLCGICAL ENVIKMXNI'ALOPERATIN REFCRT TRACEY FOINI'LAHI - LNITS K5.
3 MD 0 3.
Surface Water:
The results for radioactivity rreasurem nts in surface water san@les are consistent with past measurem nts.
Tritiun was reported as present in ll of 21 of the surface water sarrples collected fran Site T-81.
These results are consistent with the known subsurface interchange that occurs between the closed cooling canal and its surrounding waters, and the pressure gradients caused by the flow of aquifer subsurface waters in South Florida.
The highest reported tritiun (690 pCi/1) is less than 096 of the concentration of tritiun that is permitted in camanity drinking water systems and less than 3% of the reporting value specified by Technical Specifications Table 0.12-2.
0.
Waterborne Sed*iment and Food Products:
The results for radioactivity measurements in waterborne sediment and fish samples are consistent with past rreasurem nts and (except for Cs-137) with measurements made during the preoperational surveillance program.
Three fish smples, of four collected, had a positive Cs-137 value reported.
The maximrn value, is 31% of the table 0.12-3 LLD and is about 1% of the table 0.12-2 reporting levels.
Although the reported concentration was very low, future sarrples will be closely evaluated to determine any trends which might be attributed to station operation.
Results for the waterborne sedirrent, fish and crustacea samples are sumerized in Table l.
5.
Broad Leaf Ve etation:
The results for radioactivity measurements were also influenced by the passage of the plum resulting frcm the Chernobyl incident.
Cs-137 results were consistent with past measurements.
Cs-130 was identified in 3 out of 36 sarrples collected along with Ru-103 and 1-131 found in 6.out of 36 samples collected.
All of the sarrples showing positive Cs-130, Ru 103 and I-131 results were collected during the plure passage.
The remaining sanyles collected yeilded results consistent with past m asurem nts.
C.
Conclusions The data obtained through the Turkey Point Plant Radiological Envirormental Monitoring Program verifies that the levels of radiation and concentr'ations of radioactive rraterials in envirormental
sanples, representing the highest potential exposure pathways to mrrbers of the public, are not being increased.
The measurements verify that the dose or dose carrnitment to merrbers of the public, due to operation of Turkey Point Units Nos.
3 2 0, during the surveillance
year, are well within "as low as reasonably achievable (ALABA)"criteria established by 10 CFR 50, Appendix I.
1986 ANNLMLRADIOLCGICALKNVIKNMEÃZALOPERATING REKKG'03RIKY PQINI'LANI',- MITS N3S.
3 AND 4 D.
Notes
1) Maxirazn values attributed to the Chernobyl incident are canparable to levels associated with the Chinese weapons test of 1980 Ee 1978 but occurred over a shorter period of time.
2) M asurement attributed to Chernobyl were reported to the NRC pursuant to I 4 E notice 86-32.
HP3:1
e I of 8
BeimeeeAL RADImamu. kmimum, mXam me~ Seeexr f4rre of Facility Turke Point Chit Noh.
3 ind 0 Docket No.(s) 50-250 and 50-251 Location of Facility Dade Florida Re@rting Period 3anuar 1 - Decerrher 31 1986 County, State Medium ot Pathway Sampled (Unit of Measurarant)
DIXITRADIAl1(N TLD (micro-R/hr)
AIRKNNE Type and Total f4rrber of Analyses Performed Exposure rate 83d)
Lower Limit All Indicatoi.
of Locationg Detection Nhan (f)
(LLD)
Range 5.0 (83/83) 0.6 - 7.6 Location with Highest Annual Mean b
Nine M
n (f)
Distance R Range Direction NV-10 7.O (e/0)
IO niiles,"
l4V-=
7.1 - 7.0 Control Locgions l4rrher of hJhan (f)
Nonroutine Range Reported
. Measurarents
.Radioiodines (pCI/m3)-
Air Particulates
'(pCi/m3) 260.
0. 020 0.17 (12/260) 0.03-0.07 Gamna Isotopic 20 Gross Beta 259 0.0025 0.021 (259/259) 0.007-0.181 4-60 22 miles %K T-60 22 miles tAE 0.20 (2/52) 0.06-0.02 0.2O (2/52) 0.06-0.02 0.022 (52/52) 0.022 (52/52) 0.007-0.181 0.007-0.181 4
0. 0052
0. 109 (20/20)
T-60 0.115 (0/0) 0.115 (0/0) 0.091-0.129 22 mile, bbK 0.100-0.129 0.100-0.129 103Ru 137Cs 0.0070 (5/20)
T-57 0.0062-0.0077 0 miles, NV 0.00069 0.0035 (5/20)
T-60 0.0033-0.0002 22 miles, ME 0.00066 0.0069 (5/20)
T-60 0.0065-0.0075 22 miles, RK 0.0077 (I/O) 0.0072 (I/O) 0.0002 (I/O) 0.0002 (I/O) 0.0075 (I/O) 0.0075 (I/O)
2 of 8
RADlnmlCALhfNIXama XamAMueUAL Smam Naxa of Facility Turke Point Unit Nos.
3 and 4 Docket No.(s) 50-250 and 50-Z51 Location of Facility Dade Florida Reporting Period Sanuar 1 Decenker 31 1986 (County, State)
Medium or Pathway Saxp led (Unit of Measur eaant
)
Type and Total Number of Analyses Perfozaad Lower Limit of a
Detection (rzv)
All Indicator Locations Mean (f)
Range Location arith Highest Annual Mean Name M an (f)
Distance &
Range Direction Control Locations Hmiber of Mean (f)
Nonroutine Range Reported Measureaants Surface Water (pCi/1)
Tritium 45 230 60 Gamna-Isotopic 45 40 K 376 (11/45) 140-690 Z98 (45/45) 150-390 T-81 6 miles, S
T-81 6 miles, S
376 (11/Zl)
< hQA 140-690 311 (21/21)
Z75 (12/12) 230-390 150-330 59F 60~
6 95Z.-Nb 131I 134C 4
< hDA
< hQA.
< hQA.
< hQA.
< hDA
< hQA,
< hQA.
< hQA.
< hDA
< hQA.
< hQA.
< hQA
< hQA
< hQA
< hDA
< hDA
e3of 8
ENVIRCMiENI'ALRADIOUXiICALlVuiIKRI¹PRO(BN4 Pbbkl'9. SMNRY Name of Facility Turke Point Unit Nos.
3 and 0 Docket No.(s) 50-250 and 50-251 Location of Facility Dade Florida Reporting Period 3anuar 1
December 31 1986 County, State Mediun or Pathway Sarrpled (Unit of Measurarent)
Type and Total Neer of Analyses Perforrrad Lower Limit of Detection (LLD)
All Indicator Locations M an (f)
Range Location with Highest Annual hhan Nane
~an (f)
Distance R Range Direction Control Locations Neer of Mean (f)
Nonroutine Range Reported Nhasurerrents Surface IVater (pCi/I)
WATERIRMW Sediment (pCi/kg,dry) 137Cs 1~0e -La Ganna Isotopic 6
100 095 (6/6) 280-770
.750(2/2) 13 -18
miles, 730-770 N,
PATE 750(2/2) 730-770 226Ra 588 (6/6) 270-850 T-02 '
mile, ENE 780(2/2) 710-850 580(2/2) 550-610 71 220 (3/6) 100-320 T-81 6 mile, S
320 (1/2) 200 (1/3)
eOof 8
ENVIRQ4ENI'AL RADI(XCGICALNCNI KRI&G FRXB5M %DUAL SlMHRY Name of Facility Turke Point Chit Nos. 3 and r)
Docket No. (s) 50-250 and 50-251 Location of Facility Dade Florida Reporting Period Januar I - Decerrber 31 1986 Gounty, State Meditrn or
- Type and Pathway 5aryled Total Nerher
((hit of of Analyses Measurerrant)
Petformed Lower Limit All lndicatot of
=
Kocat iong Detection Mean (f)
(~)
hange location vrith Highest Annual Meah t4tre..
Mean (f)
Distance ge Direction Control LocaItions Number of Mean (f)
Nonrout inc Range Repor ted Measure@ants Sediment
(+j/kg, dry) 2380 59o(6/6) 190-l100 k-a 13-18 miles, 760 (2/2) 760 (2/2) 380-1100 380-llr)0 137cs 232th 295U 12 10 i2
<I
< NIR
< KA O7(e/6) 28-70 86(2j6) 68-1o9 T-67 i3-18 miles, N, QR 4-67 i3-18 miles)
N,~
7o(l/2) 1o3(i/2)
<NtR
<MR 7o(1/2) lo3(1/2)
e5of 8
ENVIRCMIENI'ALRADIQKGICALNCNI1QU¹ PBQGRM PbNNL SQMARY f4rne of Facility Turke Point Unit Nos.
3 and 0 Docket No.(s) 50-250 and 50-251 Location of Facility Dade Florida Reporting Period 3anuar 1
Decerrber 31 1986 County, State)
Mediun or Pathway Sarrp 1ed (Unit of hhasureaant)
Typeand Lower Limit Total NIrber of of Analyses Detection Performed (LLD)
All Indicator Locations Mean (f)
Range Location with Highest Annual M an Nana
~an (f)
Distance R Range'irection Control Locations f4rrher of M an (f)
Nonroutine Range Reported Measure@ants IKZSTICN Crustacea (pt:i/kg,wet)
Garnna - Isotopic 0
130 1850 (0/0) 1600-2100 T-81 6 miles, S
1900 (2/2) 1700-2100 1800 (2/2) 1600-2000 226Ra 228Ra 59Fe 58Co-65Zn 130Cs 137Cs 20 16 10 17 555 (e/O) 300-890 150(2/0) 100-160
<i~
< NM
< iVM
< lVM
< NM
< lvM 18 (1/5)
T-81 6 miles, S
160(1/2)
T-81 6 mi les, S
i8 (i/2)
T-67 6i5(2/2) 13-18 miles, S
300-890 615(2/2) 300-890 100(1/2)
< MM
< NM
< 5/M
< hM
< ivM
< lVM
< NM 0
e6of 8
ENVIRCNVENI'ALBADIOUGICALKNIKRIN PKXXVbh AbbLK.
SUMMARY
Name of Facility Turke Point Unit Nos.
3 and ODocket No.(s) 50-250 and 50-251 Location of Facility Dade Florida Reporting Period 3anuar I - Decerber 31 1986 County, State Median or Pathway Sany led (u it of Nieasur errant)
Type and Lower Limit Total i%aber of of Analyses Detection a Per formed (LLD)
All Indicator Locations V an (f)
Range Location with Highest Annual NLan Name
~an (f)
Distance R Range Direction Control Locations trier of V.an (f)
Nonroutsne Range Reported Measureoents INGEST ICN Fish (Qi/kg,wet)
Ganja Isotopic 0
226Ra 59Fe 65Zn 137Cs 130 20 16 10 17 2850 (0/0) 2700-3000 63 (3/0) 50-80
< b/M
< ill
< MR
< i~
< hQA
< IVM 20(3/0) 13-25 T-81 6 miles, S
T-81 6 miles, S
T-81 6 miles, S
2850 (2/2) 2800-2900 2850 (2/2) 2700-3000 23(2/2) 21-25
< MM
< MN.
< NM
< b/M
< NM
< NM 13(1/2) 70(2/2) 50(1/2) 60-80
4 e7of 8
ENVIRQ4ENTAL RADIOKGICALMNIKRIM HKCBMRÃ43M. SLNNRY Name of Facility Turke Point Unit Nos.
3 and 0
Docket No.(s) 50-250 and 50-251 Location of Facility Dade Florida Reporting Period 3anuar 1 Decarber 31 1986 County, State)
Medinn or Pathway Samp led (Unit of hhasurarant)
Type and Total Nurrber of Analyses Perforrred Lower Limit of Detection a (LLD)
All Indicator Locations M an (f)
Range Location with Highest Annual Mean Narra M-an (f)
Distance R Range Direction Control Locations f4aher of Mean (f)
Nonroutine Range Reported Measurerrants INGESTICN, Broad leaf vegetation (pCi/kg,wet) 71 00K 100 Gamna - Isotopic 36 1393 (36/36) 680-3000 2937 (36/36) 1700-5300 T-00 3 miles, 0 T-67 13-18 miles, N, ONE 1630 (12/12) 1329 (12/12) 700-3000 680-2060 3336 (12/12) 3336(12/12) 1930-5300 1930-5300 103Ru 20(6/36) 10-39 T-67 13-18 miles, N, ATE 27(2/12) 15-39 27(2/12) 15-39 1311 13+s 137Cs 359(6/36)67-675 17(3/36) 11-25 161 (30/36)15-052 T-00 3 miles, 4-67 13-18 miles N, t+E T-00
3miles, W
371(2/12)67-675 18(2/12) 11-25 301(2/12)
L28-55'8(2/12) 11-25 200 (12/12) 55 (IO/12) 102-V2 15-lie
Page 8 of 8
TABLE 1 The LID 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 99Yo probability with only 9YO probability of falsely concluding that a blank observation represents a real signal.
LID's in this column are at time of measurement.
The 1vGAs reported in attachment B for the individual samples have been corrected to the time of sample collection.
b.
khan and range based upon detectable amasurements only.
Fraction of detectable measurements at specified locations is indicated in parentheses (f).
c.
Specific identifying information for each sample location is provided in.Attachment A.
d.
Results are based upon the average net response of two TIDs.
(Thermoluminescent dosimeters).
EGA refers to mininMm detectable activity
Pag A%LPK RPDIOLCGICAL ENV IREE% AL OPERAT IN" REREAD TLRICl=Y R3INI PLPNI, LNIf bDS.
3 4 0 TABLE lA DEVIATICNS/MISSI¹MTA Date 03/17/86 to 06/09/86 05/27/86 Location M4V-10 T-72 Descri tion of Problem TLD's missing at time of collection/replacerrent.
Unauthorized removal during interval.
Missing particulate filter due to installation error.
Deviation(s)
Direct exposure data for second quar ter at this
location, 10 miles R4V of
plant, is unavailable.
Failure to collect par-ticulate sarrple at this location.
Corrective Action Replaced TLD's with a new set.
Review m thod with field personnel.
08/19/86 09/16/86 T-51 T-60 Circuit breaker on rrator circuit tripped at about 118 hours0.00137 days 0.0328 hours 1.951058e-4 weeks 4.4899e-5 months into the 170 hour0.00197 days 0.0472 hours 2.810847e-4 weeks 6.4685e-5 months sarrpling period.
Suspected cause is lightning.
Air purrp failure at about 73 hours8.449074e-4 days 0.0203 hours 1.207011e-4 weeks 2.77765e-5 months into the 193 hour0.00223 days 0.0536 hours 3.191138e-4 weeks 7.34365e-5 months period.
Cause unknown.
Failure to provide contin-Reset breaker upon dis-uous sarrpling during period. covery of fault.
Failure to provide contin-Replaced failed unit upon uous sarpling during period. discovery of fault.
HP3: 1
1986 ANNUALMDI(XCGICALENVIEKN4&l'ALOPERATIC REKRI'T.
LUCIE PldÃI'~ MIT NOS.
1 8r. Z TABLE 1B ANALYSES WI'IH LIDs AHA TABLE 4.1Z-1 l3EHHCTICN CAPABILITIES 1/1/86 - 1Z/31/86 Date S
leT e
Location Radionuclide Table 4.1Z-1 LID R~easo for Deviation The values specified in Table 4.12-3, Detection Capa~-lities, were achieved for all samples.
0
1986 ANNUAL RADIOUXICALENVIEKRvKÃZALCPERATIK'x REFGRI'UiK1D'OINI'LANZ
- UNITS MS.
3 AND 4 TABLE 2 LAND USE CENSUS DISTANCE IO NEAIKST Sector 6/86 Milk (c)
Animal 5/86 Residence 6/86 Garden (d)
L (e) 0 (f) 0 0
2.1/350 (g) 0 ESE 0
L (g)
L 1.6/303 3.7/311 L (g) 3.9/303 3.6/309 4.5/328 HP3: 1
1986 ANNUAL RADIOLCGICALMVIEKNMMI'ALOPERATIC REKXG'URMH'OINT PLANI' MITS NOS.
3 AND 4 TABLE 2 N3IKS lAND USE CENSUS (a)
All categories surveyed out to 5 miles radius fran the Turkey Point Plant (b)
The following format is used to denote the location:
distance (miles)/bearing (degrees)
For example, a residence located in the north sector at a distance of 2.1 miles bearing 350 degrees is recorded as 2.1/350.
(c)
Potential milk animal locations.
(d)
(e)
Gardens with an estimated growing area of 500 square feet or more.
L denotes that the sector area is predominently a land area unoccupied by the category type.
(f) 0 denotes that the sector area is predaninently an ocean area.
(g)
Non-residential occupied buildings in this sector include the following:
Sector N
S Distance 1.8/349 4.9/171 4.5/327 1.8/345 Description 24-hour Security Staffing building Small building/boat dock-not considered a
residence 2 mobile hanes used for field offices Security booth at park entrance.
HP3: 1
1986 ANNUAL RADIOUXrICAL HCTIRQ4%271'AL GPERATIK'x REFCRI'UBM'Y XQINI'LANI' UNITS NOS.
3 AND 4 ATI'ACHXMl' KEY '10 SAMPLE IDC'ATICNS HP3: 1
RAI)IOLOGICAL ENVIRONHENTAL SURVEILLAtfE TURKEY POINT PLANT Key to Sample Locations Pa t hway Location Oe seri pt ion amp e Collection Approxirrrate Direction Samples Col 1 ected Frequency Oi stance (mi les) hector 0 IRECT RAD IATION N-1 Convoy Point TLO quarterly DIRECT RAI)IATION N-5 North of Hoody Or.
TLO quarterly DIRECT RADIATION N-10 Old Cutler Rd. at S.W. 87th Ave.
TI.O IIuarterly O IRECT RAD IATION NNM-1 Turkey Point Entrance Road TLD IIuarterly NNW 0 IRECT RAD IATION NNW-10 Burr Rd. at Ilainlin Hil 1 Or; TLO quarterly NNW D IREC T RAD !ATION NW/WNW-I Turkey Point Entrance Road TLO Iluarterly I) IRECT RAD IATION
.NW-5.i Dolan's Farm on King 's Ilighway TLO quarterly NNW I) IRFCT RAI) IATION NW-10 Intersection of Fanrr Li te Rd. and Coconut Palm Or.
TLO IIuarter ly
HAOIOLOGICAL ENVIRONMENTAL SURVEILLANCE TURKEY POINT PLANT Key to Sample Locations Pathway Location Description Sample Collection Approximate Direction Samples Collected Frequency Uistance (miles)
Sector DIRECT RADIATION M/MNM-5 Palm Drive at Tal lahassee Rd.
TLD quarterly 0 IHECT RAA IATION WNW-10.
Ilomestead near vehicle inspection station TLO quarterly DIRECT HAD IATION On site near cooling tower TLD quarterly DIRECT RAD IATION W-10 Florida City near fire tower TLD quarterly 1U DIRECT RAD IATION WSW-10 Old ilawk missile site south of Florida City
'TLD Iiuarter ly DIHECT RAI)IATION SW/SSW-1 On site near land util iza I ton offices TLD quarterly DIRECT RAI) IATION SW-10 U ~ S.
1 south of Florida City I
TLO quarter ly Oli)ECT RADIATION S'SW/SW-5 On site, southeast corner uf cooling canals TLD quarterly
RAD IOLOG ICAL ENVIRONHENTAL SURVE ILLAICE TURKEY POINT PLANT Key to Sample Locations Pathway Location Descri pti on Samp e
Collection
- Sampl es Col lected frequency Approximate Direction Distance (mi les)
Sector D IRECT RAD IAT10N SSM-10 At Card Sound Bridge TLD Iluarter ly 10 D IRECT RAD IATION
- S-5 Onsite, south end of cooling canals TLD i
quarterly DIRECT RAD IATION
.S-10 Card Sound Rd. at Stesnboat Creek TLD quarterly DIRECT RADIATION SSE/S-I Turtle Point TLO Iiuarterly DIRECT RADIATION SSE-10 Ocean Reef TLD Iluarterly AIRBORNE T51 llunestead Bayfront Park Radioiodine Meekly
and part,iculates NNM AIRBORNE
.T57 Tree Nursery 316th Street Radioiodine Meekly and particulates 4
AIRBORNE T58 Turkey Point Entrance Rd.
Radioiodine Weekly and particulates
HADlOLOGICAL ENVIRONMENTAL SUHVElLLAN:f TURKEY POlNT P! ANT Key to Sample Locations Pathway Location Oescription Sanp e
Collection Sanples Collected Frequency Approxima te Oirection Oistance (miles)
Sector AlRBOHNf T64*
Natoma Substation Radioiodine Meekly and particulates 22 NNE AIRBORNE T72 Turkey Point Boy Scout Camp Radioiodine Meekly and particulates WATERBORNf T42 Biscayne Bay, at Turkey Point Surface water Honthly tNE Sediment fran shoreline Semi-annually WATEHBOHNf T61*
Bi scayne
Bay, vicinity of Cutler Plant, north to Hatheson llamnock Park Sediment fran sliore line SBnl annually Surface water Nonthly 13-18 N, NNt WATEHBOHNf T81 Card Sound, near neuth of old discharge canal Sediment fran shoreline Seni-annually Surface water Honthly
> Bunnies control sanple.
RADlOLOGICAL ENVIRON%:NTAL SURVE lLLAtCk TURKEY PUlNl PLANl Key to Sample Locations Pathway Location Oescription S@np e Collection Approximate Direction Samples Collected Frequency Distance (miles)
Sector FODO PRDDIL TS T67*
Biscayne Bay, vicinity of Cutler Plant north to ththeson Ilarweck Park C rust4cea Fish Semi-annually Seni-annually 13-18 N,
NNE FOOD PROOXTS T81 Card Sound, vicinity of Turkey Point Facility Crustacea Fish Semi-annually Seni-annually FOOD PR(ll)ICTS T40 South of Palm Dr.
on SW 117th St,.
extension Broad 'ea f vege ta t ion Honthly FOOD PRODUCTS T41.
Palm Or. West of old missile site near the site boundary Uroad leaf vegetation monthly WNW FOOD PROOILTS l6I Near Bi scayne
Uay, vicinity uf Cutler Plant north to Hatheson Ilaxmock Park Broad leat vegetation thnthly 13-18 NNk Iu nut u~ Control Savu>le.
~ 5+
5 5
s I
~I I
I
~
~
~
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~ 1% ~
n 5
n I
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.I GENERAL IIIGH TVAY NAF DADE COUNTY FLORIDA
~r o<<
~tltI 1<<a>>at<<r a>><<aa
>>ao<<<<a <<oa
~Tare or TIortOa DIfkrTI>>TIITor Taa<<lroATAT~
ITLOlrarrtaltri Or Tra<<T>>OhTaTIOI>>
~Ia<<a v<<var rrl<>>>tart 4r~
1986 ANNUAL HADIOLCOICALENVIRQ4%ÃZALGPERATIKx HEPCRI'T.
LUCIE PLANI' UNITS NOS.
3 AND 4 ATI'ACEMMZB HADI(XCOICALSURVEILLANCZ GF IIQRIQA KMER AND LIGHI'QvPANY'S ST. LUCIE SITE 1986 First Quarter,1986 Second Quarter, 1986 Third Quarter,1986 Four th Quar ter, 1986 HP3: 1
RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND TIGHT COMPANY'S TORKEY POINT SITE First Quarter, 1986 Office of Radiation Control Florida Department of. Health and Rehabilitative Services
TURKEY POINT SITE Technical Specif ications Sampling First Quarter, 1986 Collection
~Fce cene~
Locations Number of Sa~m led Sa~m lea
1. Direct Radiation
2. Airborne 2.a Air Iodines 2.b Air Particulates Quarterly Weekly Weekly 21 42 60 64*
3. Waterborne 3.a Surface Water 3.b Shoreline Sediment Monthly Semiannually 3
3
4. Ingestion 4.a Fish and Invertebrates 4.a.l Crustacea 4.a. 2 Fish Semiannually Semiannually 4.b Food Products 4.b.l Broadleaf Vegetation Monthly Total:
191
Includes DOE 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.
1
TORKEY POINT TECHNICAL SPECIFICATIONS SAMPLING FIRST QUARTERf 1986 1.
DIRECT RADIATION
TLDs
(micro-R/hour)
Each result is the average net response of two dosimeters.
Sample Site N-1 N-5 N-10 NNW-1 NNW-10 NW/WNW-1 NW-5 NW-10 w/WNw-5 wNw-10 W-1 W-10 Wsw-10 sw/ssw-1 Sw-10 ssw/sw-5 ssw-10 S-5 S-10 SSE/S-l Ss E-'10 Deployed 12-09-85 Collected 3-17-86 4.6
+ 0.2 5.6
+ 0.3 5.2
+ 0.3 5.8
+ 0.3 6.3
+ 0.3 5.0
+ 0.3 5.2
+ 0.3 7.1
+ 0.4 4.7
+ 0.2 5.8
+ 0.3 5.0
+ 0.3 6.5
+ 0.3 4.6
+ 0.2 4.8
+ 0.3 5.0
+ 0.3 5.0
+ 0.3 5.3
+ 0.3 4.8
+ 0.3 5.5
+ 0.3 4.8
+ 0.3 4.6
+ 0.2 NOTES:l.
2.
3.
The error terms reported above are based on an empirical statistical analysis of the differences in the results from the individual dosimeters at each site.
As such, these error terms are representative of the ~tical error for such measurements rather than accurately representing the error terms for individual measurements.
These results have been determined with the assumption that fading is negligible, although detailed.testing to confirm this has not been done.
Testing to confirm compliance with NRC Reg.
Guide 4.13 and ANSI N545-1975 performance standards has not been completed.
1.
DIRECT RADIATION
TLDs
(micro-R/hour)
Each result is Sample Site N-1 N-5 N-10 NNW-1
'NNW-10 Nw/wNw-1 Nw-5 Nw-10 w/wNw-5 WNW-10 w-1 W-10 WSW-10
~
sw'/ssw-1 Sw-10 ssw/sw-5 SSw-10 S-5 S-10 Ss E/S-l Ss E-10 the average net response of two dosimeters.
Deployed 12-09-85 Collected 3-17-86 Due to failure of the TLD reader normally
used, these dosimeters were read out on a
new instrument.
Final results for these readings cannot be determined until the behavior of these dosimeters (i.e.,
net response, self-exposure
rate, and fading) can be determined on this new instrument.
This could not be completed for this report.
This data will be included as an addendum to a future report.
2.a IODINE-131 IN WEEKLY AIR FILTERS
( Ci/m
)
3 Collection Date 1-07-86 1-14-86 1-21-86 1-28-86 2-04-86 2-11-86 2-18-86 2-25-86 3-04-86 3-11-86 3-18-86 3-25-86 T51
<0.02
<0.02
<0.04
<0.06
<0.03
<0.04
<0.03
<0.03
<0.05
<0.03
<0.03
<0.03 T57
<0.02
<0.02
<0.04
<0.06
<0.03
<0.04
<0.03
.<0.03
<0.05
<0.03
<0.03
<0.03 m! '58
<0.02
<0.02
<0.04
<0.06
<0.03
<0.03
<0.03
<0.03
<0.05
<0.03
<0.03
<0.03 T64
<0.02
<0. 02
<0.04
<0.05
<0.03
<0.04
<0.03
<0.03
<0.05
<0.03
<0.03
<0.03 T72
<0.02
<0.02
<0.04
<0.06
<0.03
<0.03
<0.03
<0.03
<0.05
<0.03
<0.03
<0.03
2.b AIR PARTICULATES GROSS BETA
( Ci/m
)
3 Collection Date T51 T57 T58 T64 T72 1-07-86 1-14-86 1-21-86 1-28-86 2-04-86 2-11-86 2-18-86 2-25-86 3-04-86 3-11-86 3-18-86 3-25-86 0.018
+
0 0.010
+
0 0.013
+
0 0.014
+
0 0.016
+
0 0.012
+
0 0.021
+
0 0.012
+
0 0.015
+
0 0.010
+
0 0.010
+
0 0.009
+
0
.002
.002
.002
.002
.002
.002
.002
.002
.002
.002
.002
.001 0.016 0.010 0.015 0.015 0.015 0.013 0.020 0.009
0. 014 0.015 0.010 0.014
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.001
+ 0.002
+ 0.002
+ 0.001
+ 0.002
0. 016 0.014
0. 015 0.012
0.018
0.010
0.018
0.015
0. 014 0.014 0.007
0. 010
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.001
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.001
+ 0;001 0.018 0.011 0.014 0.012 0.018 0.011 0.017 0.013 0.016 0.015 0.007 0.012
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.001
+ 0.002 0.010 0.008 0.013 0.018
0. 016 0.011 0.015 0.014 0.015 0.011 0.007
0. 011
+ 0.001
+ 0.001
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.001
+ 0.002 Means:
0.013
+ 0.001
DOE split samples.
0.014
+
0.001 0.014
+
0.001 0.014
+
0.001 0.012
+ 0.001 2.b AIR PARTICUIATES
GAMMA SCANS OF QUARTERLY COMPOSITES
( Ci/m
)
3 Sample Site Be-7 First Quarter, 1986 K-40 Cs-134 Cs-137 Pb-210 T51 T57 T58 T64 T72 0.108
+
0.126
+
0.124
+
0.129
+
0.106
+
0.008 0.010 0.011 0.010 0.010
<0.026
<0.027
<0.015
<0.029
<0.016
<0.0008
<0.0009
<0.0009
<0.0008
<0.0008
<0.0009
<0.0008
<0.0008
<0.0009
<0.0009
<0.037
<0.045
<0.040 0.044
+ 0.016
<0.044
3.a SURFACE WATER
( Ci/1)
Sample Collection Site Date H-3 Zr-95 Ba-140 K-40 Nn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 T42 1-14-86
<190 2-10-86
<190 3-17-86
<200 T67 1-14-86
<190 2-10-86
<190 3-17-86
<190 T81 1-14-86 250
+ 60 2-10-86 380
+ 60 3-17-86 320
+ 60 260
+
40
<4 240
+
40
<5 340
+ 50
<4 220
+
40
<4 150
+
40
<5 320
+ 50
<4 250
+ 50
<5 360
+
40
<4 320
+ 50
<4
<9
<4
<4
<13
<6
<6
<11
<4
<5
<11
<4
<5
<11
<5
<6
<11
<5
<2
<10
<4
<5
<10
<5
<5
<10
<5
<5 (A)
<7
<6
<4
<5
<12
<8
<9
<4
<9
<8
<7
<4
<10
<5
<10
<8
<9
<9
<5
<9
<8
<3
<5
<4
<11
<9
<6
<4
<9
<8
<10
<5
<10
<8
<8
<5
<4
<5
<4
<4
<4
<4
<4
<5
<4 (B)
<7
<7
<5
<6
<6
<6
<6
<6
<7 (A)
These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.
(B)
These tabulated LLD values are for Ba-140,,either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample.
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 U-238 U-235 T42 1-21-86
<140 280
+ 70
<ll
<10
<12
<10 710
+ 20 55
+
9 440
+ 20
<170 T67 1-21-86
<140 730
+ 90
<13
<14
<12
<13 610
+ 60
<33 1140
+ 120 103
+
8 T81 1-16-86
<120 300
+ 60
<11
<11
<9
<10 540
+
30
<23 330
+
30
<150 4.a.l CRUSTACEA
Blue Crab
( Ci/k,
wet wei ht)
Sample Collection Site Date T67 3-06-86 T81 3-11-86 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 2000
+ 100
<12
<31
<15
<10
<26
<15
<12 340
+ 20 2100
+ 100
<12
<33
<13
<14
<31
<15
<12 490
+ 40 4.a.2 FISH
Mixed S ecies
( Ci/k wet wei ht)
Sample Collection Site Date K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 T67 3-06-86 T81 2-05-86 2700
+ 200 2800
+ 100
<13
<40
<13
<14
<33
<14
<13 50
+ 10
<12
<35
<12
<14
<28
<12 21
+
6 80
+ 10
4.b.l BROADLEAF VEGETATION - Brazilian Pe er
( Ci/k wet wei ht)
Sample Collection Site Date Be-7 K-40 I-131 Cs-134 Cs-137 T40 1-14-86 3000
+ 80 1750
+
90
<8 2-10-86 1410
+ 70 2300
+ 100
<15 3-17-86 1540
+
60 2900
+ 100
<12
<7 145
+
7
<8 249
+
9
<7 132
+
7 T41 1-14-86 1130
+ 60 2900
+ 100
<7 2-10-86 1160
+
60 3100
+ 100
<15 3-17-86 1310
+ 60 1960
+ 90
<10
<8 72
+
6
<10 85
+
7
<6 108+
6 T67 1-14-86 2-10-86 3-17-86 2010
+ 70 2400
+ 100
<8 980
+
60 3800
+ 100
<13 1020
+ 60 3800
+ 100
<15
<6 55
+
5
<10 15
+
4
<8 30
+
5
RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE Second Quarter, 1986 Office of Radiation Control Florida Department of Health and Rehabilitative.Services
TURKEY POINT SITE Technical Specifications Sampling Second Quarter, 1986 Sam le T e
Collection Fre uenc Locations Number of 1'. Direct Rad iation
2. Airborne 2.a Air Iodines 2.b Air Particulates Quarterly 4
Weekly Weekly 21 40 70 73*
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 4.b Food Products 4.b.l Broadleaf Vegetation Monthly Semiannually Semiannually Semiannually Monthly 12 0
10*
Total:
205 Includes DOE 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 are reported
- as'non-detectable" (ND) or Lower Limit of Detection
((LLD),
which is an limit (with at least 95% conf idence) for the the sample.
above background as less than a
estimated upper true activity in
TURKEY POINT TECHNICAL SPECIFICATIONS SAMPLING SECOND QUARTER, 1986 1.
DIRECT RADIATION
TLDs
(micro-R/hour)
Each result is the average net response of two dosimeters Sample Site N-1 N-5 N-10 NNW<<1 NNW-10 NW/WNW-1 NW-5 NW-10 W/WNW-S WNW-10 W-1 W-10 WS W-10 SW/SSW-1 Sw-10 ssw/sw-s SSW-10 S-5 S-lo SSE/S-l SSE-10 Deployed 3-17-86 Collected 6-09-86 4.9
+ 0.3 5.5
+ 0.3 5.1
+ 0.3 6.0
+ 0.3 Note 4
5.3
+ 0.3 5.2
+ 0.3 7.3
+ 0.4 4.9
+ 0.3 6.3
+ 0.3 5.2
+ 0.3 6.2
+ 0.3 4.8
+ 0.3 4.8
+ 0.3 5.2
+ 0.3 a.9
+ 0.3 5.4
+ 0.3 4.7
+ 0.2 5.8
+ 0.3 4.6
+ 0.2 4.8
+ 0.3 NOTES:
1.
2.
3.
4.
The error terms reported above are based on an empirical statistical analysis of the differences in the results from the individual dosimeters at each site.
As such, these error terms are representative of the
~t ical error for such measurements rather than accurately representing the error terms for individual measurements.
These results have been determined with the assumption that fading is negligible, although detailed testing to confirm this has not been done.
Testing to confirm compliance with NRC Reg.
Guide 4.13 and ANSI N545-1975 performance standards has not been completed.
The Dosimeters from site NNW-10 were missing when collection was attempted.
1.
DIRECT RADIATION
TLDs
(micro-R/hour)
Each result is the average net response of two dosimeters.
Sample Site Deployed 3-17-86 Collected 6-09-86 N-1 N-5 N-10 NNW-1 NNW-10 (A)
NW/WNW-1 NW-5 NW-10 W/WNW-5 WNW-10 W-1 w-10 Wsw-10 SW/SSW-1 Sw-10 SSW/SW-5 Ssw-10 S-5 (B)
S-10 Ss E/S-l-SSE-10
.Due to failure of the TLD reader normally
used, these dosimeters were read out on a
new instrument.
Final results for these readings cannot be determined until the behavior of these dosimeters (i.e.,
net response, self-exposure
rate, and fading) can be determined on this new instrument.
This could not be completed
'for this report.
This data will be included as an addendum to a future report.
A
The dosimeters for site NNW-10 were missing when collection was attempted.
B
The dosimeters for site S-5 and their holder were found on the ground upon collection.
2.a IODINE-131 IN WEEKLY AIR FILTERS
( Ci/m
)
3 Collection Date T51 T57 Sam le Site T58 T64 T72 4-01-86
<0.04 4-29-86
<0.03 5-06-86
<0.03 4-08-86
<0.06(A) 4-15-86
<0.03 4-23-86
<0.04
<0.04
<0.04
<0.03
<0.04
<0.03
<0.04
<0.04
<0.04
<0.03
<0.04
<0.03
<0.03
<0.04
<0.04
<0.03
<0.04
<0.03
<0.03
<0.04
<0.04
<0;03
<0.04
<0.04
<0.03 5-13-86 0.47
+ 0.04 0.17
+ 0.01 0.21
+ 0.01 0.42
+ 0.04 0.22
+ 0.01 5-19-86 O.ll + 0.01 0.06
+ 0.01 0.09
+ 0.01 0.06
+ 0.01 0.12
+ 0.01 5-27-86 0.03
+ 0.01 6-03-86
<0.03 6-10-86
<0.05 6-16-86
<0.04 6-24-86
<0.02 6-30-86
<0.05
<0.03
<0.03
<0.05
<0.04
<0. 02
<0.05
<0.03
<0.03
<0.04
<0.04
<0.02
<0.05
<0.05
<0.03
<0.04
<0.04
<0.02
<0. 05 0.04
+ 0.01
<0.03
<0.04
<0.04
<0.02
<0.05 A
This sample had a low volume due to a low flowrate setting.
NOTE:
Detectable concentrations of I-131 in these samples are attributed to releases from the 4-26-86 disaster at the nuclear facility at Chernobyl, U.S.S.R.
Y
2.b AIR PARTICULATES
GROSS BETA
( Ci/m
)
3 Collection Date T51 T57 Sam le Site T58 T64 T72 4-01-86 4-08-86 4-15-86 4-23-86 4-29-86 5-06-86 5-13-86 5-19-86 5-27-86 6-03-86 6-10-86 6-16-86 6-24-86 6-30-86 0.009 (A0.015 0.016 0.013 0.020
0. 017 0.157 0.077 0.070 0.068
0. 030
0. 013
0. 009
0. 034
+ 0.001
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.005
+ 0.004
+ 0.003
+ 0.004
+ 0.002
+ 0.002
+ 0.001
+ 0.003 0.010
+
0.023
+
0.017
+
0.015
+
0.027
+
0.025
+
0.170
+
0.061
+
0.090
+
0.066
+
0.030
+
0.014
+
0. 012
+
0.018
+
0.001 0.002 0.002 0.002 0.002 0.002 0.005 0.004 0.004 0.003
0. 002
0. 002
0. 002 0.002 0.010
+
0.023
+
0.017
+
0.011
+
0.023
+
0.024
+
0.148 +
0.053
+
0.067 +
0.054
+
0.031
+
0.011
+
0.008
+
0.020
+
0.001
0. 002
0. 002 0.001
0. 002 0.002 0.005 0.003 0.003 0.003 0.002 0.002 0.001 0.002 0.014
+
0.018
+
0.020
+
0.014
+
0.022
+
0.022
+
0.181
+
0.075
+
0.074
+
0.061
+
0.036
+
0.016
+
0. 010
+
0.019
+
0. 002
0. 002 0.002 0.002 0.002 0.002 0.006 0.004 0.003 0.003 0.003 0.002 0.001 0.002 0.012 0.020 0.017 0.015 0.022 0.025 0.157 0.071 0.072 0.029 0.019 0.009 0.022
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.005
+ 0.004 (B)
+ 0.004
+ 0.002
+ 0.002
+ 0.001
+ 0.002 Means:
0.039
+ 0.001 0.041
+ 0.001 0.036
+ 0.001 0.042
+ 0.001 0.038
+ 0.001
DOE split samples.
(A)
This sample had a low volume due to a low flowrate setting.
(B)
There was no particulate filter upon collection due to a procedural operator failed to install one upon collection of the previous sample.
NOTE:
Elevated radioactivity levels in the samples collected on or after attributed to releases from the 4-26-86 disaster at the nuclear Chernobyl, U.S.S.R.
error the 4-29-86 are facility at
2.b AIR PARTICULATES
GAMMA SCANS OF QUARTERLY COMPOSITES
( Ci/m
)
3 Second Quarter, 1986 Sample Site Be-7 K-40 Ru-103 Cs-134 Cs-137 Pb-210 T51 0.110
+
0.008
<0.022 0.0076
+
0.0010 0.0036
+
0.0003 0.0065
+
0.0006 0.03
+
0.01 T57 T58 T64 T72 0.110
+
0.009
<0.022 0.0077
+
0.0010 0..0033
+
0.0003 0.0069
+
0.0006 0.110
+ 0.008
<0.021 0.0062
+ 0.0011 0.0033
+ 0.0003 0.0070
+ 0.0006 0.124
+ 0.008
<0.024 0.0072
+ 0.0011 0.0042
+ 0.0004 0.0075
+ 0.0006 0.124
+.0.009
<0.025 0.0062
+ 0.0011 0.0033
+ 0.0003 0.0068
+ 0.0005
<0.03
<0.03
<0.03
<0.07 NOTE:
Detectable concentrations of Ru-103, Cs-134, and Cs-137 in these samples are attributed to releases from the 4-26-86 disaster at the nuclear facility at Chernobyl, U.S -S -R.
-3.a SURFACE WATER
( Ci/1)
Sample Collection Site Date H-3 (A)
(B)
Kr-95 Ba-140 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 T42 4-14-86
<180 5-12-86
<190 6-09-86
<190 340
+
40 300
+ 50 380
+ 50
<3
<8
<4
<10
<4
<12
<3
<4
<4
<3
<9
<7
<ll
<5
<4
<7
<5
<9
<8
<7
<5
<5
<4
<4
<11
<7
<8
<5
<5
<8 T67 4-14-86
<180 5-12-86
<190 6-09-86
<190 320
+ 40
<4
<11 330
+ 50
<4
<11 270
+ 50
<4
<12
<4
<5
<4
<5
<11
<8
<11
<4
<5
<5
<5
<10
<8
<7
<5
<5
<6
<4
<11
<6
<11
<5
<5
<7 T81 4-14-86(C)
<180 4-14-86(D)
<210 5-12-86(C)
<190 5-12-86(D) 390
+ 60 6-09-86 (C )
<190 6-09-86(D)
<190 380
+ 50 230
+ 50 330
+ 50 390
+ 50 330
+ 50 260
+ 50
<4
<10
<4
<11
<3
<11
<4
<9
<4
<13
<4
<13
<5
<4
<4
<4
<4
<4
<5
<5
<4
<5
<5
<5
<11
<9
<10
<7
<9
<8
<12
<8
<11
<8
<12
<8
<12
<5
<12
<5
<9
<6
<7
<4
<ll
<4
<ll
<5
<4
<4
<5
<4
<5
<5
<8
<9
<6
<5
<7
<7 (A)
These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.
(B')
These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample.
(C )
Collected at the normal location in the old discharge canal about 200 'est of the mouth.
(D)
Collected at a comparison location at the mouth of the old discharge canal on the south side of the prominent embankment in this area.
4.b.l BROADLEAF VEGETATION Brazilian Pe er
( Ci/k,
wet wei ht)
Sample Collection Site Date Be-7 K-40 RU-103 I-131
's-134 Cs-137 5-12-86
6-10-86 700
+ 50 2000
+ 100
<10 1150
+ 70 2600
+ 100 26
+
4 T40 4-14-86 1860
+
80 3900
+ 100
<34 675
+ 19 67+14
<8 332
+ 10
<10 140
+
7
<10 372
+ 11 5-12-86 6-10-86 870
+ 60 1700
+ 100 760
+
60 2700
+ 100 T41 '-14-86 1100
+
60 2500
+ 100
<8
<12 18+5
<30 655
+ 19 75
+ 12
<7 95
+
6
<10 212
+
9
<10 215
+
8 T67 4-14-86 5-12-86 6-09-86 1730
+ 70 3400
+ 100 1020
+ 60 2200
+ 100 1480
+ 60 2400
+ 100
<9
<9
<27 554
+ 18
<8
<9 39+
5 128+ ll 25+
3 71 +.6 36+
4 53+6 NOTE:
DOE Split Sample.
Detectable concentrations of Ru-103, I-131, and Cs-134 in these samples are attributed to releases from the 4-26-86 disaster at the nuclear facility at Chernobyl, U.S.S.R.
Some of the Cs-137 may also be attributable to residual activity from the testing of nuclear weapons.
RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE Third Quarter, 1986 Office of Radiation Control Florida Department of Health and Rehabilitative Services
TURKEY POINT SITE Technical Specifications Sampling Third Quarter, 1986 Sam le T e
1. Direct Radiation Collection Fre uenc Quarterly 21 42 Locations Number of
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 4.b Food Products 4.b.l Broadleaf Vegetation Monthly Semiannually Semiannually Semiannually Monthly 12 3
Total:
204 Includes.
DOE 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
TURKEY POINT TECHNICAL SPECIFICATIONS SAMPLING THIRD QUARTERf 1986 1.
DIRECT RADIATION
TLDs (micro-R/hour)
Each result is the average net response of two dosimeters.
Sample Site N-1 N-5 N-10 NNW-1 NNW-10 NW/WNW-1 NW-5 NW-10 W/WNW-5 WNW>>10 W-1 W-10 WSW-10 SW/SSW-1 SW-10 SSW/SW-5 SSW-10 S-5 S-10 SSE/S-1 SSE-10 Deployed 6-09-86 Collected 9-23-86 4.9
+ 0.3 5.9
+ 0.3 5.4
+ 0.3 5.7
+ 0.3 6.1 + 0.3 5.0
+
0 '
5.5
+ 0.3 7.6
+ 0.4 4.9
+ 0.3 6.5
+ 0.3 5.5
+ 0.3 6.5
+ 0.3 4.7
+ 0.2 5.4
+ 0.3 5.2
+ 0.3 5.4
+ 0.3 5.5
+ 0.3 4.8
+.0.3 5.6 + 0.3 4.8
+ 0.3 4.7
+ 0.2 NOTES:
1 ~
2.
3.
The error terms reported above are based on an empirical statistical analysis of the differences in the results from the individual dosimeters at each site.
As such, these error terms are representative of the
~t ical error for such measurements rather than accurately representing the error terms for individual measurements.
These results have been determined with the assumption that fading is negligible, although detailed testing to confirm this has not been done.
Testing to confirm compliance with NRC Reg.
Guide 4.13 and ANSI N545-1975 performance standards has not been completed.
1.
DIRECT RADIATION
TLDs
(micro-R/hour)
Each result is the average net response of two dosimeters.
Sample Site Deployed 6-09-86 Collected 9-23-86 N-1 N-5 N-10 NNW-1 NNW-10 NW/WNW-1 Nw-5 Nw-10 W/WNW-5 WNW-10 W-1 W-10 Wsw-10 SW/SSW-1 Sw-10 SSW/SW-5 Ssw-10 S-5 S-10 SSE/S-1 SSE-10 Due to failure of the TLD reader normally used, these dosimeters were read out on a
new instru-ment.
Final results for these readings cannot be determined until the behavior of these dosimeters (i.e.,
net responsei self-exposure
rate, and fading) can be determined on this new instrument.
This could not be completed for this report.
This data will-be included as an addendum to a future report.
2.a IODINE-131 IN WEEKLY AIR FILTERS
( Ci/m
)
3 Collection Date T51 T57 Sam le Site T58 T64 T72 7-08-86 7-15-86 7-22-86 7-29-86 8-05-86 8-12-86 8-19-86 8-25-86 9-02-86 9-08-86 9-16-86 9-23-86 9-30-86
<0. 02
<0.03
<0.03
<0.03
<0.03
<0.02
<0; 02
<0.03
<0.03
<0.03
<0.03
<0.02
<0.04
<0.02
<0.03
<0.02
<0.02
<0.03
<0.04
<0.02
<0.03
<0.02
<0.02
<0.03
<0.05(A)
<0.04
<0.02
<0.03
<0.03
<0.03
<0.03
<0.02
<0.03
<0.03
<0.02
<0.03
<0'. 02
<0. 02
.<0.03
<0.02
<0.03
<0.03'0.03
<0.03
<0.03
<0.03
<0.04
<0.02
<0.03
<0.02
<0.03
<0.03
<0.03
<0.02
<0.02
<0.03
<0.04
<0.03
<0.03
<0.02
<0.03
<0.02
<0.02
~0.06(B)
<0'2 (A)-
A circuit breaker had tripped at this location during this
sample, possibly due to lightning.
The equipment is estimated to have run for 118 hours0.00137 days 0.0328 hours 1.951058e-4 weeks 4.4899e-5 months out of the 170 total hours for this sample interval.
(B) -
The air pump had failed at this location.
The equipment is estimated to have run for 73 hours8.449074e-4 days 0.0203 hours 1.207011e-4 weeks 2.77765e-5 months out of the 193 total hours for this sample interval.
2.b AIR PARTICULATES
GROSS BETA
( Ci/m
)
3 Collection Date T51 T57 Sam le Site T58 T64 T72 7-08-86 7-15-86 7-22-86 7-29-86 8-05-86 8-12-.86 8-19-86 8-25-86 9-02-86 9-08-86 9-16-86 9-23-86 9-30-86
0. 017 0.017 0.017 0.017 0.014 0.009 (A0.016 0.022 0.016 0.014 0.019 0.012 0.016
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.001
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002 0.020
+
0.015
+
0.018
+
0.016
+
0.014
+
0.013
+
0.013
+
0.016
+
0.013
+
0.014
+
0.022
+
0.014
+
0.014
+
0.002 0.002 0.002 0.002 0.002 0.002 0.002 0.002 0.002 0.002 0.002 0.002 0.002 0.019
+ 0.002 0.016
+ 0.002 0.018
+ 0.002 0.017
+ 0.002
0.016 + 0.002
0.012 + 0.002
'""0.012 + 0.002
0.022 + 0.002 0.015
+ 0,.002 0.015
+ 0.002 0.018
+ 0.002 0.012
+ 0.002 0.010
+ 0.002 0.021 0.015 0.016 0.020 0.014 0.010 0.011 0.020 0.012 0.010 (B0.029 0.012 0.012
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.004
+ 0.002
+ 0.002 0.019 0.017 0.020 0.015 0.011
, 0.009 0.017 0,028 0.019 0.014 0.025 0.013 0.017
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.001
+ 0.002
+ 0.003
+ 0.002
+ 0.002
+ 0.002
+ 0.002
+ 0.002 Means:
0.016
+ 0.001 0'.016
+ 0.001 0.016
+ 0.001 0.016
+ 0.001 0.017
+ 0.001 (A)
DOE split samples.
A circuit breaker had tripped at this location during this sample, probably due to lightning.
The equipment is estimated to have run for 118 hours0.00137 days 0.0328 hours 1.951058e-4 weeks 4.4899e-5 months out of the 170 total hours for this sample interval.
The air pump had failed at this location.
The equipment is estimated to have run for 73 hours8.449074e-4 days 0.0203 hours 1.207011e-4 weeks 2.77765e-5 months out of the 193 total hours for this sample interval.
2.b AIR PARTICULATES GAMMA SCANS OF QUARTERLY COMPOSITES
( Ci/m
)
3 Third {}uarter, 1986 Sample Site T51 T57 T58 Be-7 0.098
+ 0.007 0.092
+ 0.008 0.091
+ 0.008 T72 0.111
+ 0.008 T64 0.100
+ 0.009 K-40
<0. 023
<0.013
<0.016
,<0.024
<0.023 Cs-134
<0.0007
<0.0009
<0.0009
<0.0008
<0.0009 Cs-137
<0.0009
<0.0009
<0.0008
<0.0008
<0.0008 Pb-210
<0.034
<0.030
<0.035
<0.035
<0.033
3.a SURFACE HATER
( Ci/1)
Sample Collection Site Date H-3 Zr-95 Ba-140 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 7-17-86
<210 8-11-86
<210 9-10-86
<210 T67 7-17-86
<210 8-12-86
<210 9-10-86
<210 240
+ 50
<4 360
+ 50
<5 340
+ 50
<4 260
+. 50
<4 260 + 50
<5 260 + 50
<4
<10
<4
<9
<4
<9
<4
<10
<4
<10
<5
<9
<4
<5
<9
<8
<5
<9
<9
<4
<ll
<7
<5
<9
<8
<5
<11
<8
<5
<11
<8
<5
<5
<5
<6
<7
<6
<5
<6
<5
<4
<4
<5
<5
<5
<5
<5
<4
<5
<6
<4
<7
<4
.<5
<8 T81 7-17-86 (C) 350
+ 60 7-17-.86 (D)'40 + 60 8-11-86 (C) 560
+ 70 8-11-86 (D) 690 + 70 9-10-86 (C)
<210 9-10-86 (D)
<210 250 +
240 +
290 +
310 +
300
+
330 +
50
<5 50
<5 50
<3 50
<4 50
<5 50
<4
<1'4
<4
<10
<4
<5
<11
<4
<5
<12
<4
<4
<8
<4
<5
<8
<3
<5
<12
<8
<10
<8
<ll
<9
<12
<8
<11
<7
<8
<8
<6
<6
<8
<7
<5
<4
<6
<5
<5
<5
<5
<5
<5
<5
<5
<5
<4
<4
<8
<6
<5
<8
<10
<8 (A)
These
~ tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.
(B)
These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample.
(C)
Collected at the normal location in the old discharge canal about 200'est of the.
mouth.
(D)
Collected at a comparison location at the mouth of the old discharge canal on the south side of the prominent embankment in this area.
3.b SEDIMENT
( Ci/k dr wei ht)
Sample Collection Site Date Be-7 K-40 Mn-54 Co-58 Co-60 Cs-134 Cs-137 Others T42 7-17-86 140 + 40 420 + 70
<13
<15
<14
<14
<14
- Ra-226:
850 Th-232:
33 U-235:
68 U-238:
700
+ 20
+7
+ 7
+ 100 T67 7-17-86 200 + 60 770
+ 90
<11
<12
<14
<14 T81 7-17-86 320 + 60
- 470
+ 70
<11
<11
<9
<12 Ra-226:
550
+ 30 Th-232:
70 + 30 U-238:
380 + 90
<10 Ra-226:
270 + 20 Th-232:
28 + 7 U-238:
190
+ 60 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 Others T67 9-10-86 1600
+ 100
<13
<36
<13
<16
<33
<17
<15 Ra-226:
890
+ 30 Ra-228:
140
+ 30 T81 7-31-86 1700
+ 200
<14
<39
<15
<14
<39
<16
<18 Ra-226:
50'0
+ 20 Ra-228:
160
+ 30
4.a.2 FISH
Mixed S ecies
( Ci/k wet wei ht)
Sample Collection Site Date K-40 Mn-54 Fe-59 Co-50 Co-60 Zn-65 Cs-134 Cs-137 Others T67.
9-08-86 3000
+ 200
<10 T81 8-06-86 2900
+ 200
<14
<46
<15
<13
<32
<13 13 + 5 Ra-226:
<220 Ra-228:
<60
<38
<12
<15
<33
<15 25 + 5 Ra-226:
60 + 10 Ra-228:
<60 4.b.l BROADLEAF VEGETATION Brazilian Pe er
( Ci/k,
wet wei ht)
Sample Collection Site Date Be-7 K-40 Ru-103 1-131 Cs-134 Cs-137 T40 7-17-86 1570
+ 70 2900
+ 100 8-12-86 1620
+ 70 2500
+ 100 9-10-86 2320
+ 80 2900
+ 100 T41 7-17-86 1730
+ 60 3100
+ 100 8-12-86 1480
+ 70 2800
+ 100 9-10-86 1520
+ 70 3800
+
'=00 T67 7-17-86 2060
+ 80 4100
+ 100 8-12-86 680
+ 50 5300
+ 200 9-10-86 1480
+ 70 2800
+ 100 11+4
<10
<10 10+4
<10
<10 15+4
<10
<9
<13
<16
<16
<11
<14
<16
<13
<13
<16
<11
<10
<10 14+
6
<10
<11 11+
2
<11
<9 204 +
9 386 + ll 102 +
6 108 + 7 147 +
8 425
+ ll 114
+
7 28+5 88+7
RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE Fourth Quarter, 1986 Office of Radiation Control Florida Department of Health and Rehabilitative Services
TURKEY POINT SITE Technical Specifications Sampling Fourth Quarter, 1986 Sam le T e
Collection Fre uenc Locations Number of
1. Direct Radiation Quarterly 21 42
2. Airborne 2.a Air Iodines 2.b Air Particulates Weekly Weekly 65 69*
3. Waterborne 3.a Surface Water 3.b Shoreline Sediment Monthly Semiannually 12 0
4. Ingestion 4.a Fish and Invertebrates 4.a.l Crustacea 4.a.2 Fish 4.b Food Products 4.b.l Broadleaf Vegetation Semiannually Semiannually Monthly 10*
Total:
198 Includes DOE 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.
TURKEY POINT TECHNICAL SPECIFICATIONS SAMPLING FOURTH QUARTER, 1986 1.
DIRECT RADIATION
TLDs
(micro-R/hour)
Each result is the average net response of two dosimeters.
Sample Site N-1 N-5 N-10 NNW-1 NNW-10 NW/WNW-1 Nw-5 Nw-10 W/WNW-5 WNW-10 W-1 W-10 Wsw-10 SW/SSW-1 Sw-10 SSW/SW-5 Ssw-10 S-5 S-10 SSE/S-1 SSE-10 Deployment 9-22-86 Collection 12-15-86 4.9
+ 0.3 5.6
+ 0.3 5.0
+ 0.3 5.7
+ 0.3 5.9
+ 0.3 4.9
+ 0.3 5.2
+ 0.3 7.4
+ 0.4 4.7
+ 0.2 6.6
+ 0.3 5.1
+ 0.3 6.6
+ 0.3 4.8
+ 0.3 4.7
+ 0.2 4.9
+ 0.3 5.2
+
0 '
5.3
+ 0.3 5.0
+ 0.3 5.3
+
0 3
4.8
+ 0.3 4.7
+ 0.2 NOTES:
2.
3.
The error terms reported above are based on an empirical statistical analysis of the differences in the results from the individual dosimeters at each site.
As such, these error terms are representative of the
~t ical error for such measurements rather than accurately representing the error terms for individual measurements.
These results have been determined with the assumption that fading is negligible, although detailed testing to confirm this has not been done.
Testing to confirm compliance with NRC Reg.
Guide 4.13 and ANSI N545-1975 performance standards has not been completed.
1.
DIRECT RADIATION
TLDs
(micro-R/hour)
Each result is the average net response of two dosimeters.
Sample Site Deployment 9-23-86 Collection 12-15-86 N-1 N-5 N-10 NNW-1 NNW-10 NW/WNW-1 Nw-5 Nw-10 W/WNW-5 WNW-10 W-1
. W-1O WSW-10 Sw/SSW-1 Sw-10 SSW/SW-5 SSW-10
$-5 S<<lo SSE/S-1 SSE-10 Due to failure of the TLD reader normally used, these dosimeters were read out on a
new instru-ment.
Final results for these readings cannot be determined until the behavior of these dosimeters (i.e.,
net response, self-exposure
rate, and fading) can be determined on this new instrument.
This could not be completed for this report.
This data will be included as an addendum to a future report.
2.a IODINE-131 IN WEEKLY AIR FILTERS
( Ci/m
)
3 Collection Date T51 T57 Sam le Site T58 T64 T72 10-07-86 10-14-86 10-21-86 10-28-86 11-04-86 11-12-86 11-18-86 11-25-86 12-02-86 12-09-86 12-16-86 12-22-86 12-30-86
<0.03
<0.03
<0.03
<0.03
<0.03
<0.03
<0.02
<0.02
<0.03
<0. 03
<0.03
<0.03
<0.03
<0.02
<0.03
<0.03
<0.03
<0.03
<0.02
<0.02
<0.03
<0.03
<0.03
<0.02
<0.02
<0.03
<0.02
<0. 03
<0. 02
<0. 03
<0. 02
<0.03
<0.02
<0.03
<0.02
<0.02
<0.02
<0.03
'0.03
<0. 02
<0. 03
<0.02
<0.03
<0.02
<0.02
<0.03
<0..02
<0.03
<0.02
<0.03
<0.02
<0.02
<0.03
<0. 02
<0.03
<0.02
<0.03
<0.02
<0. 02
<0.03
<p.p6 (A)
<p.p6 (A)
<0.06 (A)
<0 ~ 06 (A)
<0.06 (A)
(A)
These samples became misdirected in the mail, which result-ed in a
longer than usual delay before they could be analyzed.
2.b AIR PARTICULATES
GROSS BETA
( Ci/m
)
3 Collection Date T51 T57 Sam le Site T58 T64 T72 10-07-86 0.017
+ 0.002 0.016
+ 0.002 0.014
+ 0.002 0.017
+ 0.002 0.013
+ 0.002 10-14-86 10-21-86 10-28-86 11-04-86 0.015
+ 0.002 0.013
+ 0-002 0-011
+ 0-002 0-010 + 0-002 0.012, + 0.002 0.015
+ 0.002 0.013
+ 0.002 0.0 '
+ 0.002 0.013
+ 0.002 0.016
+ 0.002 0.012
+ 0.002 0.012
+ 0.002 0.014
+ 0.002 0.013
+ 0.002 0.013
+ 0.002 0.010
+ 0.002 0.008
+ 0.001
0.009 + 0.001 0-011
+ 0.002 0.010
+ 0.001 11-12-86(A) 0.011
+ 0.002 0.014
+ 0.002
0.012 + 0.002 0.010
+ 0.001 0.007
+ 0.001 11-18-86 11-25-86 12-02-86 12-09-86 12-16-86 12-22-86 12-30-86 0.011
+ 0.002 0.013
+ 0.002 0.018
+ 0.002 0.015
+ 0.002 0.016
+ 0.002 0.012
+ 0.002 0.010
+
0 002 0-009
+ 0.001 0-012 + 0.002 0-010
+ 0.002 0.015
+ 0.002 0.016
+ 0.002 0.016
+ 0.002 0.012
+ 0.002 0.014
+ 0.002 0.010
+ 0.001 0.016
+ 0.002
. 0.012
+ 0.002 0.013
+ 0.002 0.020
+ 0.002 0.011
+ 0.002 0.009
+ 0-002
0.011 + 0-002 0.009
+ 0.002 0.012
+ 0.002 0.008
+ 0.001 0.012
+ 0.002
0.011 + 0-002 0-009
+ 0.001 0.010
+ 0.002 0.011
+ 0.002 0.007
+ 0.001 0.008
+ 0.001 0.008
+ 0.001 0.007
+ 0.001 Means:
0.012
+ 0.001 0.012
+ 0.001 0.012
+ 0.001 0.012
+ 0.001 0.012
+ 0.001
DOE split samples.
(A)
These samples became misdirected in the mail, delay before they could be analyzed.
which resulted in a longer than usual
2.b AIR PARTICULATES -
GAMMA SCANS OF QUARTERLY COMPOSITES
( Ci/m
)
Fourth Quarter, 1986 Sample Site Be-7 K-40 Cs-134 Cs-137 T51 0.097
+ 0.009 T57 0.102
+ 0.008 T58 0.112
+ 0.009 T64 0.105
+ 0.008 T72 0.104
+ 0.007
<0. 023
<0. 025
<0.024
<0.023
<0.016
<0.0007
<0.0008
<0.0008
<0.0007
<0.0009
<0.0008
<0.0007
<0.0007
<0.0007
<0.0007
3.a SURFACE WATER
( Ci/1)
Sample Collection Site Date H-3 (A)
(B)
H Zr-95 Ba-140 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-.65 Nb-95 I-131 Cs-134 Cs-137 La-140 T42 10-13-86 11-18-86 12-15-86
<190
<180
<260 270 + 50 240
+ 50 280
+ 50
<4
<9
<4
<5
<11
<4
<4
<11
<5
<6
<10
<5
<11
<5
<12
<9
<6
<7
<7
<7
<5
<4
<5
<5
<5
<5
<4
<8
<8
<4 T67 10-13-86 "11-18-86 12-16-86
<190
<180
'<260 280
+ 50 320
+ 50 310
+ 50
<4
<12
.<4
<4
<11
<4
<4
<8
<4
<4
<10
<5
<10
<4
<10
<7
<5
<9
<8
<9
<5
<5
<5
<5
<4
<4
<5
<5
<6
<7 T81 10-13-86 (C) 10-13-86 (D) 11-18-86 (C) 11-18-86 (D) 15-86(C) 12-15-86(D) 140 + 60
<190 150
+ 60 570
+ 60
<260
<260 320
+ 60 350
+ 50 320
+ 50 300
+ 50 320
+ 50 360 + 50
<5
<11
<5
<12
<4
<8
<4
<10
<4
<9
<4
<10
<4
<5
<4
<4
<4
<4
<4
<8
<6
<10
<5
<11
<4
<9
<5
<9
<5
<7
<9
<9
<9
<9
<9
<6
<6
<6
<8
<5
<7
<6
<5
<5'4
<5
<5
<5
<5
<5
<4
<6
<5
<4
<7
<8
<5
<7
<7
<6 (A)
These tabulated LLD values for ZrjHb-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.
(C)
Collected at the normal location in the old discharge canal about 200'est of the mouth.
(D)
Collected at a comparison location at the mouth of the old discharge canal on the south side of the prominent embankment in this area.
4.b.l BROADLEAF VEGETATlON -
Brazilian Pe er
( Ci/k wet wei ht)
Sample Collection Site Date Be-7 K-40 I-131 Cs-134 Cs-137 T40 10-13-86 1550
+ 80 3500
+ 100
<17
11-18-86 1100
+ 60 3600
+ 100
<8 12-16-86 1790
+ 70 2500
+ 100
<12
<11
<7
<9 452
+ 13 214
+
9 201
+
9 T41 10-13-86 1540
+ 70 2700
+ 100
<16 11-18-86 720 + 40 3000
+ 100
<6 12-16-86 1260
+ 60 3100
+ 100
'10
<9
<7
<11 312
+ 10 77+
6 134+
8 T67 10-13-86 780
+ 50 1930
+ 90
<10 11-18-86 1080
+ 50 3500
+ 100
<8 12-16-86 1630
+ 60 4400
+ 100
<11
<9
<9 60+
5
<9
<10 DOE split sample.
1986 ANNUALRADIQQXICALH47IBCRvKNZALOPERATIC REKR1 ST. LUCIE PLANI' IJJITS N3S.
3 AND 4 ATI'ACE5%ÃZ C RESULTS FRCM 'IHE 1986 HP3: 1
FLORIDA DEPT.
OF HRS EPA INTERLABORATORY CROSS-CHECK PROGRAM DATA Media Nuclide Collection Mon Day Yr EPA Known Units Normal.
Range January through June, 1986 Mean of Analyses N.DE K.
Action Level FILTER REFILTER FILTER FILTER FOOD FOOD FOOD FOOD FOOD MILK MILK MILK MILK MILK MILK MILK MILK MILK MILK WATER ATER TER ATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER Alpha Beta Cs-137 Sr-90 I-131 Cs-137 KSr-89 Sr-90 I-131 I-131 Cs-137 Cs-137 K
KSr-89 Sr-89 Sr-90 Sr-90 Alpha Alpha Alpha Alpha Beta Beta Beta Beta Cr-51 Cr-51 Co-60 Co-60 Zn-65 Zn-65 RU-106 Ru-106 Cs-134 Cs-134 Cs-137 Cs-137 H-3 H-3 I-131 Sr-89 Sr-89 Sr-90 Sr-90 04 04 04 04 01 Ol Ol 01 01 10 25 25 25 25 31 31 31 31 31 25 86 86 86 86 86 86 86 86 86 85 06 10 06 10 27 86 25 85 27
.86 25 85 06 27 86 10 06 10 06 11 Ol 25 27 25 85 86 85 27 86 22 85 24
- 86 03 05 11 01 03 05 02 06 02 06 02 06 02 06 02 06 02 21 23 22 24 21 23 07 06 07 06 07 06 07 06 07 06 07 86 86 85 86 86 86 86 86 86 86 86 86 86 86 86 86 86 06 06 86 02 06 12 01 05 09 01
'10 05 09 86 86 86 14 86 13 86 06 85 10 86 15 47 10 18 20 15 950 25 10 42 56 1540 48 26 10 3
15 8
13 7
8 15 38 0
18 66 40 86 0
50 30 49 22 10 5227 3125 45 31 5
15 5
pCi/F pCi/F pCi/F pCi/F pCi/Kg pCi/Kg pCi/Kg pCi/Kg pCi/Kg 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 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 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 0
0.474 0.118 0.395 0.197 0.118
. 0.248 0.237 0.395 0.197 0.355 16 46
12. 66
15. 33
20. 66 14.33 1013.'33 11
11. 66 49.66
58. 67 0.237 0.118 0.118 0.118 0.118 0
0.118 0.118 0.118 "0.576 0
0. 118 0.118 0.237 0.592 0
0. 711 0.118 0.237 0.237 0
0.091 0.362 0.197 0.355 0.237 0
0.395 46.66 24 11.,66
3. 66 12.33 6.67 16
7. 67 9.33 16.66 44 0
19. 66
66. 67 43 90.67 0
50.33 28.66 47 22ll 5183.33 3143.33 50
29. 66 5
15
4. 66 0.23 1596.66
0. 34
-0.34 0.92
-3.08
0. 19
-0.23
0. 77
-4.85
1. 92 2.21 NA 0.92 NA 1.27 NA
-0.46
'NA
-2. 31 NA 0.58
0. 23
-0. 92
-0.46 1.03 0.23 0.46 0.58 2.07 0
0.58 0.23 1.03 1.61 0
0. 11
-0. 46
-0.69 0
0. 34
-0.14
0. 09 1.44
-0.46 0
0
-0.38 (2)
NOTES:
Normal.:
ange Normalized range.
As defined in "Environmental Radioactivity Lab-oratory Intercomparison Studies Program Fiscal Year 1981 1982",
Environmental Monitoring Systems Laboratory, U.
S.
Environmental Protection
Agency, P.
O.
Box 15027, Las Vegas,
Nevada, 89114.
EPA-600/4-81-004,
February, 1981.
N.DE K.:
Normalized deviation of the mean from the known value.
As defined in EPA-600/4-81-004.
NDP:
No data provided.
No data was provided to EPA for inclusion in their report.
NA:
Not available.
Report containing this data has not yet been re-ceived from EPA, Las Vegas.
(1)
(2)
Cause:
Chemical recovery too low.
Corrective action: Try to improve recovery.
Cause:
Unknown.
Corrective action:
None at this time.
FLORIDA DEPT.
OF HRS EPA ZNTERLABORATORY CROSS-CHECK PROGRAM DATA June through December, 1986 Media Nuclide Collection Mon Day Yr EPA Known Units Normal.
Range Mean of Analyses N.D.K.
Action Level FILTER FILTER FILTER FILTER FOOD FOOD FOOD FOOD FOOD MILK MILK MILK MILK MILK MILK MILK MILK MILK MILK
,. WATER WATER ATER ATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER Alpha Beta Cs-137 Sr-90 I-131 Cs-137 KSr-89 Sr-90 I-131 I-131 Cs-137 Cs-137 K
KSr-89 Sr-89 Sr-90 Sr-90 Alpha Alpha Alpha Beta Beta Beta Cr-51 Cr-51 Co-60 Co-60 Zn-65 Zn-65 Ru-106 Ru-106 Cs-134 Cs-134 Cs-137 Cs-137 H-3 H-3 I-131 09 09 09 09 07 07 07 07 07 06 10 06 10 06, 10 06 10 06 10 07 09ll 07 09 12 12 12 12 25 25 25 25 86 86 86 86 86 86 86 86 31 27 31 27 31 27 31 18 19 21 18 19 86 86 86 86 86 86 86 86 86 86 86 86 06 10 06 10 06 21 06 10 06 10 06 86 86 86 86 86 86 10
'10 06 06 10 10 86 86 86 06 10 06 10 06 10 08 06 10 06 10 13 17 08 86 86 86 86 86 86 86 25 86 27 86 31
'86 27 86 22 66 22 22 30 20 1150 30 19 41 31 1600 16 6
15 20 18 8
20 0
59 66 31 86 85 50 74 49 28 10 44 3125 5973 45 pCi/F pCi/F pCi/F pCi/F pCi/Kg pCi/Kg mg/Kg pCi/Kg pCi/Kg pCi/L pCi/L pCi/L pCi/L mg/L mg/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 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L
.pCi/L pCi/L pCi/L pCi/L
0. 829
0. 237
0. 237 0.395 0.197 0.118 0.817
17. 33 64.67 25.00 21.33 29.00 21.66 1173.33
0. 197 0.000
44. 00 4.00 0.237 0.395 0.118 0.000 0.237 0.000 0.000 0.000 0.000 0.592 0.118
0. 118 0.592 0.576 0.711 1.927 0.237
0. 237
0. 000
0. 237
0. 362 0.197
0. 67
12. 33
5. 67
~;6. 00
13. 66
18. 00
10. 00
22. 00
0. 00
55. 33 66.67 31.66 90.67 89.33 50.33 72.00 47.00 26.00 11.00 44.66 3143.33 41.33 0.296 1616.66
-1. 61
-0. 46
1. 03
-0. 77
-0. 29
0. 58
0. 70 NDP NDP 0.87 NA
-9.35 NA 0.36 NA 0.23 NA
-4. 23 NA
-0.11
0. 34
-2. 19
0. 00
0. 69 0.69 0.00
-1.27 0.23
0. 23 1.61 1.50 0.11
-0.69
-0.69
-0. 69
0. 34
0. 23
0. 09 NDP
-1.05 (2)
(3)
NOTES ormal.:
ange Normalized range.
As defined in "Environmental Radioactivity Lab-oratory Zntercomparison Studies Program Fiscal Year 1981 1982",
Environmental Monitoring Systems Laboratory, U.
S.
Environmental Protection
Agency, P.
O.
Box 15027, Las Vegas,
Nevada, 89114.
EPA-600/4-81-004,
February, 1981.
N.DE K.:
Normalized deviation of the mean from the known value.
As defined in EPA-600/4-81-004.
NDP:
No'data provided.
No data was provided to EPA for inclusion in their report.
NA:
Not available.
Report containing this data has not yet been re-ceived from EPA, Las Vegas.
(1)
Cause:
Decimal point in wrong position.
Corrective action:
Use more care in recording data.
(2)
Cause:
Poor chemical recovery of strontium carrier.
Corrective ac-tion: Try to improve chemical recovery.
(3)
Cause:
Unknown.
Corrective action:
None at this time.

L-87-172, 1986 Annual Radiological Environ Operating Rept,Turkey Point Plant Units 3 & 4

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L-87-172, 1986 Annual Radiological Environ Operating Rept,Turkey Point Plant Units 3 & 4

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