Text

1986 Annual Radiological Environ Operating Rept,Turkey Point Plant Units 3 & 4. W/870426 Ltr
	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)
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REGULATORY INt" --.MATION DISTRIBUTION SYSTF~ (R

'CCESSION NBR: 8705060244 DOC. DATE,: 87/04/2cI NOTARIZED: NO DOCKET . 5 FACIL 50250 Turkey Point Planti Unit 3I Florida Power and Light C 05000250 50-251 Turkey Point Plant Unit 4 Florida Power -and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION l4OODY> C. O. Florida Power 8c Light Co.

RECIP. NAME RECIPIENT AFFILIATION SUBJECT; "1986 Annual Radiological Environ Operating Rept Turk g Point Plant Units 3 4. W/870426 1tr.

Kc tl DISTRIBUTION CODE: IEESD COPIES RECEIVED: R NCL SI 2E: 7~

TITLE: Environmental Monitoring Rept (per Tech Specs)

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 0 PD2-2 PD 5 5 McDONALD> D 1 1

'NTERNAL: AEOD/DOA 1 1 AEOD/DSP/TPAB 1 ARM TECH ADV 1 1 LPDR 1 RPPB ADE } 1 NRR/DREP/RPB REQ FIL 02 1 1 RES SPEIS> T 1 1 R 2 FILE 01 1 1 RGN2/DRSS/EPRPB 1 1 EXTERNAL; NRC PDR TOTAL NUMBER OF COPIES REQUIRED: LT I R 21 ENCL 20

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 PEOPLE... SERVING PEOPLE SDF I /009/ I

~ N

~-$ * ). DOCK 0500 R 50 PDR

1986 ANNUAL RADIOiXGICAL ENVIKNVl(%1'ALCH~TIKx POINI'LANI' KNITS hDS. 3 AND 4REXCRI'URKl".Y DESCRIPI'ICN INIaaXX".rICN RADICXmICAL ENVIKN~rAL ~1 azure PRCaRAM DISCUSSICN AND INIERPREI'ATICN OF RESULTS ENVIKMKNIALRADIOIXGICALMNI'KEIR PRCGRAM ANNUAL SQvhIRY TABLE I DEVIATICNS/MISSING DATA TABLE 1A ANALYSES WI'IH LLDs ABOVE TABLE 4.12-3 13EZFA I'ICN CAPABILITIES TABLE IB LAND USE CENSUS TABLE 2 KEY '1Q SAMPLE LCCATICNS ATZACEKKNT A RADICIUGICAL SURVEILLANCZ OF E~ JRRIDA PONER AND LIGHI'CMPANY'S ARM'Y POINI'ITE ATZACH%Ã1' FIRST gIAEQl&, 1986 SECCND QUAILS%, 1986

'IHIRD QIPRHW, 1986 FCXHIH glARIER, 1986 RESULTS FRCM THE I PRCGRAM, 1986 ATI'AGREE C

1986 ANNUAL RADIQLCGICAL ENVIRQ4KNTAL GPlXATIM UNITS N3S. 3 AND 4HEXCEG'UFMH'OINI'LANI' 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. RADIGLCGICAL ENVIRCHXÃfALM%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 tritimn measurements.
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.
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1986 ANNUAL RADIOLCGICAL MVIRCt4%MZAL OPERATIC UNITS NOS. 3 AND 4REPCRI'URK%'OINI'LANE
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.
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)
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1986 ANCHL RADIOLCGICAL ENVIRCNvKNI'ALOPERATING REE'CRT
~(EY FOIE'LPÃf - UNITS bDS. 3 PAD 0 I I I. DISCUSSICN M3 INI'ERVETATICN CF 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.
(3)
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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 ANNLML RADIOLCGICAL KNVIKNMEÃZALOPERATING PQINI'LANI', - MITS N3S. 3 AND 4REKKG'03RIKY 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 I4 E notice 86-32.
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e I of 8 BeimeeeAL RADI mamu. 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 Type and Lower Limit All Indicatoi. Location with Highest Control Locgions l4rrher of Pathway Sampled Total f4rrber of Locationg Annual Mean - hJhan (f) Nonroutine (Unit of of Analyses Detection Nhan (f) Nine M n (f)b Range Reported Measurarant) Performed (LLD) Range Distance R Range . Measurarents Direction DIXIT RADIAl1(N TLD Exposure rate 5.0 (83/83) NV-10 7.O (e/0)
(micro-R/hr) 83d) 0.6 - 7.6 IO niiles," l4V-= 7.1 - 7.0 AIRKNNE
.Radioiodines 260. 0. 020 0.17 (12/260) 4-60 0.20 (2/52) 0.2O (2/52)
(pCI/m3)- 0.03-0.07 22 miles %K 0.06-0.02 0.06-0.02 Air Particulates Gross Beta 259 0.0025 0.021 (259/259) T-60 0.022 (52/52) 0.022 (52/52)
'(pCi/m3) 0.007-0.181 22 miles tAE 0.007-0.181 0.007-0.181 4
Gamna Isotopic 20
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 0.0070 (5/20) T-57 0.0077 (I/O) 0.0072 (I/O) 0.0062-0.0077 0 miles, NV 0.00069 0.0035 (5/20) T-60 0.0002 (I/O) 0.0002 (I/O) 0.0033-0.0002 22 miles, ME 137Cs 0.00066 0.0069 (5/20) T-60 0.0075 (I/O) 0.0075 (I/O) 0.0065-0.0075 22 miles, RK
2 of 8 RADlnmlCALhfNIXama XamAM ueUAL 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 Type and Lower Limit All Indicator Location arith Highest Control Locations Hmiber of Pathway Saxp led Total Number of Locations Annual Mean Mean (f) Nonroutine (Unit of of Analyses Detection a Mean (f) Name M an (f) Range Reported Measur eaant ) Perfozaad (rzv) Range Distance & Range Measureaants Direction Surface Water Tritium 45 230 376 (11/45) T-81 376 (11/Zl) < hQA (pCi/1) 140-690 6 miles, S 140-690 Gamna-Isotopic 45 40 T-81 K 60 Z98 (45/45) 311 (21/21) Z75 (12/12) 150-390 6 miles, S 230-390 150-330 4 < hDA < hDA 59F < hQA. < hQA.
< hQA. < hQA.
60~ < hQA. < hQA 6 < hDA < hQA 95Z.-Nb < hQA, < hQA 131I < hQA. < hDA 134C < hQA. < 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 Type and Lower Limit All Indicator Location with Highest Control Neer of Pathway Sarrpled Total Neer of Locations Annual hhan Mean Locations (f) Nonroutine (Unit of of Analyses Detection M an (f) Nane ~an (f) Range Reported Measurarent) Perforrrad (LLD) Range Distance R Range Nhasurerrents Direction Surface IVater 137Cs (pCi/I) 1~0e -La WATERIRMW Sediment Ganna Isotopic 6 (pCi/kg,dry) 100 095 (6/6) .750(2/2) 750(2/2) 280-770 13 -18 miles, 730-770 730-770 N, PATE 226Ra 588 (6/6) T-02 '
780(2/2) 580(2/2) 270-850 mile, ENE 710-850 550-610 71 220 (3/6) T-81 320 (1/2) 200 (1/3) 100-320 6 mile, S
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 Pathway 5aryled
((hit of Measurerrant)
- Type and Total Nerher of Analyses Petformed Lower of Limit All lndicatot Detection
(~)
= Kocat iong Mean (f) hange t4tre ..
location Distance vri th Highest Annual Meah Direction Mean ge (f)
Control LocaItions Mean (f )
Range Number of Nonrout inc Repor ted Measure@ants Sediment
(+j/kg, dry) 2380 59o(6/6) k-a 760 (2/2) 760 (2/2) 190-l100 13-18 miles, 380-1100 380-llr)0 12 10 I
NIR
<NtR
<MR 137cs i2 < KA 232th O7(e/6) T-67 7o(l/2) 7o(1/2) 28-70 i3-18 miles, N, QR 295U 86(2j6) 4-67 1o3(i/2) lo3(1/2) 68-1o9 i3-18 miles)
N,~
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 .
Typeand Lower Limit All Indicator Location with Highest Control Locations f4rrher of Pathway Sarrp 1 ed Total NIrber of Locations Annual M an M an (f) Nonroutine (Unit of of Analyses Detection Mean (f) Nana ~an (f) Range Reported hhasureaant) Performed (LLD) Range Distance R Measure@ants Range'irection IKZSTICN Crustacea Garnna - Isotopic 0 (pt:i/kg,wet) 130 1850 (0/0) T-81 1900 (2/2) 1800 (2/2) 1600-2100 6 miles, 1700-2100 1600-2000 S
226Ra 20 555 (e/O) T-67 6i5(2/2) 615(2/2) 300-890 13-18 miles, S 300-890 300-890 228Ra 150(2/0) T-81 160(1/2) 100(1/2) 100-160 6 miles, S
<i~ < MM 59Fe 16 < NM < NM 58Co- < iVM < 5/M 0 10 < lVM < hM 65Zn 17 < NM < ivM 130Cs < lvM < lVM 137Cs 18 (1/5) T-81 i8 (i/2) < NM 6 mi les, S
e6of 8 ENVIRCNVENI'AL BADIOUGICALKNIKRIN 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 Type and Lower Limit All Indicator Location with Highest Control trier of Pathway Sany led Total i%aber of Locations Annual NLan V.an Locations (f) Nonroutsne (u it of of Analyses Detection a V an (f) Name ~an (f) Range Reported Nieasur errant) Per formed (LLD) Range Distance R Range Measureoents Direction INGEST ICN Fish Ganja Isotopic 0 (Qi/kg,wet) 130 2850 (0/0) T-81 2850 (2/2) 2850 (2/2) 2700-3000 6 miles, S 2800-2900 2700-3000 226Ra 20 63 (3/0) T-81 70(2/2) 50(1/2) 50-80 6 miles, S 60-80
< b/M < MM 59Fe 16 < ill < MN.
< MR < NM 10 < i~ < b/M 65Zn 17 < hQA < NM
< IVM < NM 137Cs 20(3/0) T-81 23(2/2) 13(1/2) 13-25 6 miles, S 21-25
4 e7of 8 ENVIRQ4ENTAL RADIOKGICALMNIKRIM HKCBM RÃ43M. 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 Type and Lower Limit All Indicator Location with Highest Control Locations f4aher of Pathway Samp led Total Nurrber of Locations Annual Mean Mean (f) Nonroutine (Unit of of Analyses Detection a M an (f) Narra M-an (f) Range Reported hhasurarant) Perforrred (LLD) Range Distance R Range Measurerrants Direction INGEST ICN, Broad leaf Gamna - Isotopic 36 vegetation (pCi/kg,wet) 71 1393 (36/36) T-00 1630 (12/12) 1329 (12/12) 680-3000 3 miles, 0 700-3000 680-2060 00K 100 2937 (36/36) T-67 3336 (12/12) 3336(12/12) 1700-5300 13-18 miles, 1930-5300 1930-5300 N, ONE 103Ru 20(6/36) T-67 27(2/12) 27(2/12) 10-39 13-18 miles, 15-39 15-39 N, ATE 1311 359(6/36) T-00 371(2/12) 301(2/12)67-675 3 miles, % 67-675 L28-55'8(2/12) 13+s 17(3/36) 4-67 18(2/12) 11-25 13-18 miles 11-25 11-25 N, t+E 137Cs 161 (30/36) T-00 200 (12/12) 55 (IO/12)15-052 3miles, W 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, LNI f bDS. 3 4 0 TABLE lA DEVIATICNS/MISSI¹ MTA Date Location Descri tion of Problem Deviation(s) Corrective Action 03/17/86 M4V-10 TLD's missing at time of Direct exposure data for Replaced TLD's with a new to collection/replacerrent. second quar ter at this set.
06/09/86 Unauthorized removal during location, 10 miles R4V of interval. plant, is unavailable.
05/27/86 T-72 Missing particulate filter Failure to collect par- Review m thod with field due to installation error. ticulate sarrple at this personnel.
location.
08/19/86 T-51 Circuit breaker on rrator Failure to provide contin- Reset breaker upon dis-circuit tripped at about uous sarrpling during period. covery of fault.
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.
09/16/86 T-60 Air purrp failure at about Failure to provide contin- Replaced failed unit upon 73 hours into the 193 hour0.00223 days 0.0536 hours 3.191138e-4 weeks 7.34365e-5 months uous sarpling during period. discovery of fault.
period. Cause unknown.
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1986 ANNUAL MDI(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 RADIOUXICAL ENVIEKRvKÃZALCPERATIK'x
- UNITS MS. 3 AND 4 REFGRI'UiK1D'OINI'LANZ TABLE 2 LAND USE CENSUS DISTANCE IO NEAIKST 6/86 Milk (c) 5/86 6/86 Sector Animal Residence Garden (d)
L (e) 2.1/350 (g) 0 (f) 0 0
0 ESE 0
L (g)
L 1.6/303 3.9/303 3.7/311 3.6/309 L (g) 4.5/328 HP3: 1
1986 ANNUAL RADIOLCGICAL MVIEKNMMI'ALOPERATIC PLANI' MITS NOS. 3 AND 4 REKXG'URMH'OINT 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) Gardens with an estimated growing area of 500 square feet or more.
(e) 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 Distance Description N 1.8/349 24-hour Security Staffing building S 4.9/171 Small building/boat dock-not considered a residence 4.5/327 2 mobile hanes used for field offices 1.8/345 Security booth at park entrance.
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1986 ANNUAL RADIOUXrICAL HCTIRQ4%271'AL GPERATIK'x XQINI'LANI' UNITS NOS. 3 AND 4 REFCRI'UBM'Y ATI'ACHXMl' KEY '10 SAMPLE IDC'ATICNS HP3: 1
RAI)IOLOGICAL ENVIRONHENTAL SURVEILLAtfE TURKEY POINT PLANT Key to Sample Locations amp e Collection Approxirrrate Direction Pa t hway Location Oe seri pt ion 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 TI.O IIuarterly S.W. 87th Ave.
O IRECT RAD IATION NNM-1 Turkey Point TLD IIuarter ly NNW Entrance Road 0 IRECT RAD IATION NNW-10 Burr Rd. at Ilainlin TLO quarterly NNW Hil Or; 1
D IREC T RAD !ATION NW/WNW-I Turkey Point TLO Iluarterly Entrance Road I) IRECT RAD IATION .NW-5 .i Dolan's Farm on TLO quarterly NNW King 's Ilighway I) IRFCT RAI) IATION NW-10 Intersection of Fanrr TLO IIuar ter ly Li te Rd. and Coconut Palm Or.
SURVEILLANCE HAOIOLOG ICAL ENVIRONMENTAL TURKEY POINT PLANT Key to Sample Locations Sample Collection Approximate Direction Pathway Location Description Samples Collected Frequency Uistance (miles) Sector DIRECT RADIATION M/MNM-5 Palm Drive at TLD quarterly Tal lahassee Rd.
0 IHECT RAA IATION WNW-10. Ilomestead near vehicle TLO quarterly inspection station DIRECT HAD IAT ION On site near cooling TLD quarterly tower DIRECT RAD IAT ION W-10 Florida City near TLD quarterly 1U fire tower DIRECT RAD IATION WSW-10 Old ilawk missile site 'TLD Iiuarter ly south of Florida City DIHECT RAI) IATION SW/SSW-1 On site near land TLD quarterly util iza I ton offices I
DIRECT RAI) IATION SW-10 . U~ S. 1 south of TLO quarter ly Florida City Oli)ECT RADIATION . S'SW/SW-5 On site, southeast TLD quarterly corner uf cooling canals
RAD IOLOG ICAL ENVIRONHENTAL SURVE ILLAICE TURKEY POINT PLANT Key to Sample Locations Samp e Collection Approximate Direction Pathway Location Descri pti on -
Sampl es Col l ected frequency Di stance (mi les) Sector D IRECT RAD IAT10N SSM-10 At Card Sound Bridge TLD Ilua r ter ly 10 D IRECT RAD IATION - S-5 On site, south end of i
TLD quarterly cooling canals DIRECT RAD IATION .S-10 Card Sound Rd. at TLD quarterly Stesnboat Creek DIRECT RADIATION SSE/S-I Turtle Point TLO Iiuarterly DIRECT RADIATION SSE-10 Ocean Reef TLD Iluarterly AIRBORNE T51 llunestead Bayfront Radioiodine Meekly NNM Park : and part,iculates AIRBORNE .T57 Tree Nursery Radioiodine Meekly 4 316th Street and particulates AIRBORNE T58 Turkey Point Radioiodine Weekly Entrance Rd. and particulates
HADlOLOGICAL ENVIRONMENTAL SUHVElLLAN:f TURKEY POlNT P! ANT Key to Sample Locations Sanp e Collection Approxima te Oirection Pathway Location Oescription Sanples Collected Frequency Oistance (miles) Sector AlRBOHNf T64* Natoma Substation Radioiodine Meekly 22 NNE and particulates AIRBORNE T72 Turkey Point Boy Radioiodine Meekly Scout Camp and particulates WATERBORNf T42 Biscayne Bay, at Surface water Honthly tNE Turkey Point Sediment fran Semi-shoreline annually WATEHBOHNf T61* Bi scayne Bay, Surface water Nonthly 13-18 N, NNt vicinity of Cutler Plant, north Sediment fran SBnl to Hatheson llamnock sliore l ine annually Park WATEHBOHNf T81 Card Sound, near Surface water Honthly neuth of old discharge canal Sediment fran Seni-shoreline annually
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RADlOLOG ICAL ENVIRON%:NTAL SURVE lLLAtCk TURKEY PUlNl PLANl Key to Sample Locations S@np e Collection Approximate Direction Pathway Location Oescription Samples Collected Frequency Distance (miles) Sector FODO PRDDIL TS T67* Biscayne Bay, vicinity C rust4cea Semi- 13-18 N, NNE of Cutler Plant north annually to ththeson Ilarweck Park Fish Seni-annually FOOD PROOXTS T81 Card Sound, vicinity Crustacea Semi-of Turkey Point annually Facility Fish Seni-annually FOOD PR(ll)ICTS T40 South of Palm Dr. Broad 'ea f Honthly on SW 117th St,. vege ta t ion extension FOOD PRODUCTS T41. Palm Or. West of old Uroad leaf monthly WNW missile site near vegetation the site boundary FOOD PROOILTS l6I Near Bi scayne Uay, Broad leat thnthly 13-18 NNk vicinity uf Cutler vegetation Plant north to Hatheson Ilaxmock Park Iu nut u~ Control Savu>le.
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1986 ANNUAL HADIOLCOICAL ENVIRQ4%ÃZAL GPERATIKx HEPCRI'T.
LUCIE PLANI' UNITS NOS. 3 AND 4 ATI'ACEMMZ B HADI(XCOICAL SURVEILLANCZ 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 Locations Number of
~Fce cene~ Sa~m led Sa~m lea
1. Direct Radiation Quarterly 21 42
2. Airborne 2.a Air Iodines Weekly 60 2.b Air Particulates Weekly 64*
3. Waterborne 3.a Surface Water Monthly 3 3.b Shoreline Sediment Semiannually 3
4. Ingestion 4.a Fish and Invertebrates 4.a.l Crustacea Semiannually 4.a. 2 Fish Semiannually 4.b Food Products 4.b.l Broadleaf Monthly Vegetation Total: 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 Deployed 12-09-85 Site Collected 3-17-86 N-1 4.6 + 0.2 N-5 5.6 + 0.3 N-10 5.2 + 0.3 NNW-1 5.8 + 0.3 NNW-10 6.3 + 0.3 NW/WNW-1 5.0 + 0.3 NW-5 5.2 + 0.3 NW-10 7.1 + 0.4 w/WNw-5 4.7 + 0.2 wNw-10 5.8 + 0.3 W-1 5.0 + 0.3 W-10 6.5 + 0.3 Wsw-10 4.6 + 0.2 sw/ssw-1 4.8 + 0.3 Sw-10 5.0 + 0.3 ssw/sw-5 5.0 + 0.3 ssw-10 5.3 + 0.3 S-5 4.8 + 0.3 S-10 5.5 + 0.3 SSE/S-l 4.8 + 0.3 Ss E-'10 4.6 + 0.2 NOTES:
l. The error empirical terms reported statistical analysis above are based on of the differences in an 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 for individual accurately representing the error terms measurements.
2. These results have been determined with the assumption that fading is negligible, although detailed .testing to confirm this has not been done.
3. 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 Deployed 12-09-85 Site Collected 3-17-86 N-1 Due to failure of the TLD reader normally N-5 used, these dosimeters were read out on N-10 a new instrument. Final results for NNW-1 these readings cannot be determined until
'NNW-10 the behavior of these dosimeters (i.e.,
Nw/wNw-1 net response, self-exposure rate, and Nw-5 fading) can be determined on this new Nw-10 instrument. This could not be completed w/wNw-5 for this report. This data will be WNW-10 included as an addendum to a future report.
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 2.a IODINE-131 IN WEEKLY AIR FILTERS ( Ci/m 3 )
Collection m! '58 Date T51 T57 T64 T72 1-07-86 <0.02 <0.02 <0.02 <0.02 <0.02 1-14-86 <0.02 <0.02 <0.02 <0. 02 <0.02 1-21-86 <0.04 <0.04 <0.04 <0.04 <0.04 1-28-86 <0.06 <0.06 <0.06 <0.05 <0.06 2-04-86 <0.03 <0.03 <0.03 <0.03 <0.03 2-11-86 <0.04 <0.04 <0.03 <0.04 <0.03 2-18-86 <0.03 <0.03 <0.03 <0.03 <0.03 2-25-86 <0.03 .<0.03 <0.03 <0.03 <0.03 3-04-86 <0.05 <0.05 <0.05 <0.05 <0.05 3-11-86 <0.03 <0.03
<0.03 <0.03 <0.03 3-18-86 <0.03 <0.03 <0.03 <0.03 <0.03 3-25-86 <0.03 <0.03 <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 0.018 + 0 .002 0.016 + 0.002 0. 016 + 0.002 0.018 + 0.002 0.010 + 0.001 1-14-86 0.010 + 0 .002 0.010 + 0.002 0.014 + 0.002 0.011 + 0.002 0.008 + 0.001 1-21-86 0.013 + 0 .002 0.015 + 0.002 0. 015 + 0.002 0.014 + 0.002 0.013 + 0.002 1-28-86 0.014 + 0 .002 0.015 + 0.002 0.012 + 0.002 0.012 + 0.002 0.018 + 0.002 2-04-86 0.016 + 0 .002 0.015 + 0.002 *0. 018 + 0.002 0.018 + 0.002 0. 016 + 0.002 2-11-86 0.012 + 0 .002 0.013 + 0.002 *0.010 + 0.001 0.011 + 0.002 0.011 + 0.002 2-18-86 0.021 + 0 .002 0.020 + 0.002 *0.018 + 0.002 0.017 + 0.002 0.015 + 0.002 2-25-86 0.012 + 0 .002 0.009 + 0.001 *0.015 + 0.002 0.013 + 0.002 0.014 + 0.002 3-04-86 0.015 + 0 .002 0. 014 + 0.002 0. 014 + 0.002 0.016 + 0.002 0.015 + 0.002 3-11-86 0.010 + 0 .002 0.015 + 0.002 0.014 + 0.002 0.015 + 0.002 0.011 + 0.002 3-18-86 0.010 + 0 .002 0.010 + 0.001 0.007 + 0.001 0.007 + 0.001 0.007 + 0.001 3-25-86 0.009 + 0 .001 0.014 + 0.002 0. 010 + 0;001 0.012 + 0.002 0. 011 + 0.002 Means: 0.013 + 0.001 0 .014 + 0 .001 0 .014 + 0 .001 0 .014 + 0 .001 0 .012 + 0.001
DOE split samples.
2.b AIR PARTICUIATES GAMMA SCANS OF QUARTERLY COMPOSITES ( Ci/m 3 )
First Quarter, 1986 Sample Site Be-7 K-40 Cs-134 Cs-137 Pb-210 T51 0.108 + 0.008 <0.026 <0.0008 <0.0009 <0.037 T57 0.126 + 0.010 <0.027 <0.0009 <0.0008 <0.045 T58 0.124 + 0.011 <0.015 <0.0009 <0.0008 <0.040 T64 0.129 + 0.010 <0.029 <0.0008 <0.0009 0.044 + 0.016 T72 0.106 + 0.010 <0.016 <0.0008 <0.0009 <0.044
3.a SURFACE WATER ( Ci/1)
Sample Collection Zr-95 Ba-140 Site Date H-3 K-40 Nn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 (A) (B)
T42 1-14-86 <190 260 + 40 <4 <9 <4 <4 <7 <6 <4 <5 <4 <7 2-10-86 <190 240 + 40 <5 <13 <6 <6 <12 <8 <9 <4 <5 <7 3-17-86 <200 340 + 50 <4 <11 <4 <5 <9 <8 <7 <4 <4 <5 T67 1-14-86 <190 220 + 40 <4 <11 - <4 <5 <10 <5 <5 <3 <4 <6 2-10-86 <190 150 + 40 <5 <11 <5 <6 <10 <8 <9 <5 <4 <6 3-17-86 <190 320 + 50 <4 <11 <5 <2 <9 <9 <8 <4 <4 <6 T81 1-14-86 250 + 60 250 + 50 <5 <10 <4 <5 <11 <9 <6 <4 <4 <6 2-10-86 380 + 60 360 + 40 <4 <10 <5 <5 <9 <8 <10 <5 <5 <6 3-17-86 320 + 60 320 + 50 <4 <10 <5 <5 <10 <8 <8 <5 <4 <7 (A) These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.
(B) These tabulated LLD values are for Ba-140,,either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample.
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 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 T67 3-06-86 2000 + 100 <12 <31 <15 <10 <26 <15 <12 340 + 20 T81 3-11-86 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 2700 + 200 <13 <40 <13 <14 <33 <14 <13 50 + 10 T81 2-05-86 2800 + 100 <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 <7 145 + 7 2-10-86 1410 + 70 2300 + 100 <15 <8 249 + 9 3-17-86 1540 + 60 2900 + 100 <12 <7 132 + 7 T41 1-14-86 1130 + 60 2900 + 100 <7 <8 72 + 6 2-10-86 1160 + 60 3100 + 100 <15 <10 85 + 7 3-17-86 1310 + 60 1960 + 90 <10 <6 108+ 6 T67 1-14-86 2010 + 70 2400 + 100 <8 <6 55 + 5 2-10-86 980 + 60 3800 + 100 <13 <10 15 + 4 3-17-86 1020 + 60 3800 + 100 <15 <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 Collection Locations Number of Sam le T e Fre uenc 1'. Direct Rad ia t ion Quarterly 21 40 4
2. Airborne 2.a Air Iodines Weekly 70 2.b Air Particulates Weekly 73*
3. Waterborne 3.a Surface Water Monthly 12 3.b Shoreline Sediment Semiannually 0
4. Ingestion
~
4.a Fish and Invertebrates
~
4.a.l Crustacea Semiannually 4.a.2 Fish Semiannually 4.b Food Products 4.b.l Broadleaf Monthly 10*
Vegetation Total: 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 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% conf idence) for the true activity in the sample.
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 Deployed 3-17-86 Site Collected 6-09-86 N-1 4.9 + 0.3 N-5 5.5 + 0.3 N-10 5.1 + 0.3 NNW<<1 6.0 + 0.3 NNW-10 Note 4 NW/WNW-1 5.3 + 0.3 NW-5 5.2 + 0.3 NW-10 7.3 + 0.4 W/WNW-S 4.9 + 0.3 WNW-10 6.3 + 0.3 W-1 5.2 + 0.3 W-10 6.2 + 0.3 WS W-10 4.8 + 0.3 SW/SSW-1 4.8 + 0.3 Sw-10 5.2 + 0.3 ssw/sw-s a.9 + 0.3 SSW-10 5.4 + 0.3 S-5 4.7 + 0.2 S-lo 5.8 + 0.3 SSE/S-l 4.6 + 0.2 SSE-10 4.8 + 0.3 NOTES:
1. 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.
2. These results have been determined with the assumption that fading is negligible, although detailed testing to confirm this has not been done .
3. Testing to confirm compliance with NRC Reg. Guide 4.13 and ANSI N545-1975 performance standards has not been completed.
4. 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 Deployed 3-17-86 Site Collected 6-09-86 N-1 .Due to failure of the TLD reader normally N-5 used, these dosimeters were read out on N-10 a new instrument. Final results for NNW-1 these readings cannot be determined until NNW-10 (A) the behavior of these dosimeters (i.e.,
NW/WNW-1 net response, self-exposure rate, and NW-5 fading) can be determined on this new NW-10 instrument. This could not be completed W/WNW-5 'for this report. This data will be WNW-10 included as an addendum to a future report.
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 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 Sam le Site Date T51 T57 T58 T64 T72 4-01-86 <0.04 <0.04 <0.04 <0.04 <0.04 4-08-86 <0.06(A) <0.04 <0.04 <0.04 <0.04 4-15-86 <0.03 <0.03 <0.03 <0.03 <0;03 4-23-86 <0.04 <0.04 <0.04 <0.04 <0.04 4-29-86 <0.03 <0.03 <0.03 <0.03 <0.04 5-06-86 <0.03 <0.04 <0.03 <0.03 <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 <0.03 <0.03 <0.05 0.04 + 0.01 6-03-86 <0.03 <0.03 <0.03 <0.03 <0.03 6-10-86 <0.05 <0.05 <0.04 <0.04 <0.04 6-16-86 <0.04 <0.04 <0.04 <0.04 <0.04 6-24-86 <0.02 <0. 02 <0.02 <0.02 <0.02 6-30-86 <0.05 <0.05 <0.05 <0. 05 <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 Sam le Site Date T51 T57 T58 T64 T72 4-01-86 0.009 + 0.001 0.010 + 0.001 0.010 + 0.001 0.014 + 0. 002 0.012 + 0.002 4-08-86 (A0.015 + 0.002 0.023 + 0.002 0.023 + 0. 002 0.018 + 0. 002 0.020 + 0.002 4-15-86 0.016 + 0.002 0.017 + 0.002 0.017 + 0. 002 0.020 + 0.002 0.017 + 0.002 4-23-86 0.013 + 0.002 0.015 + 0.002 0.011 + 0.001 0.014 + 0.002 0.015 + 0.002 4-29-86 0.020 + 0.002 0.027 + 0.002 0.023 + 0. 002 0.022 + 0.002 0.022 + 0.002 5-06-86 0. 017 + 0.002 0.025 + 0.002 *0.024 + 0.002 0.022 + 0.002 0.025 + 0.002 5-13-86 0.157 + 0.005 0.170 + 0.005 *0.148 + 0.005 0.181 + 0.006 0.157 + 0.005 5-19-86 0.077 + 0.004 0.061 + 0.004 *0.053 + 0.003 0.075 + 0.004 0.071 + 0.004 5-27-86 0.070 + 0.003 0.090 + 0.004 *0.067 + 0.003 0.074 + 0.003 (B) 6-03-86 0.068 + 0.004 0.066 + 0.003 0.054 + 0.003 0.061 + 0.003 0.072 + 0.004 6-10-86 0. 030 + 0.002 0.030 + 0. 002 0.031 + 0.002 0.036 + 0.003 0.029 + 0.002 6-16-86 0. 013 + 0.002 0.014 + 0. 002 0.011 + 0.002 0.016 + 0.002 0.019 + 0.002 6-24-86 0. 009 + 0.001 0. 012 + 0. 002 0.008 + 0.001 0. 010 + 0.001 0.009 + 0.001 6-30-86 0. 034 + 0.003 0.018 + 0.002 0.020 + 0.002 0.019 + 0.002 0.022 + 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 error the operator failed to install one upon collection of the previous sample .
NOTE: Elevated radioactivity levels in the samples collected on or after 4-29-86 are attributed to releases from the 4-26-86 disaster at the nuclear facility at Chernobyl, U.S.S.R.
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 0 .110 + 0 .009 <0 .022 0 .0077 + 0 .0010 0 ..0033 + 0 .0003 0 .0069 + 0 .0006 <0.03 T58 0.110 + 0.008 <0.021 0.0062 + 0.0011 0.0033 + 0.0003 0.0070 + 0.0006 <0.03 T64 0.124 + 0.008 <0.024 0.0072 + 0.0011 0.0042 + 0.0004 0.0075 + 0.0006 <0.03 T72 0.124 + .0.009 <0.025 0.0062 + 0.0011 0.0033 + 0.0003 0.0068 + 0.0005 <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 Kr-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 4-14-86 <180 340 + 40 <3 <8 <3 <3 <9 <7 <ll <5 <4 <7 5-12-86 "
<190 300 + 50 <4 <10 <4 <5 <9 <8 <7 <5 <5 <4 6-09-86 <190 380 + 50 <4 <12 <4 <4 <11 <7 <8 <5 <5 <8 T67 4-14-86 <180 320 + 40 <4 <11 <4 <5 <11 <8 <11 <4 <5 <5 5-12-86 <190 330 + 50 <4 <11 <5 <5 <10 <8 <7 <5 <5 <6 6-09-86 <190 270 + 50 <4 <12 <4 <4 <11 <6 <11 <5 <5 <7 T81 4-14-86(C) <180 380 + 50 <4 <10 <5 <5 <11 . <9 <12 <5 <4 <8 4-14-86(D) <210 230 + 50 <4 <11 <4 <5 <10 <7 <12 <5 <4 <9 5-12-86(C) <190 330 + 50 <3 <11 <4 <4 <9 <8 <9 <6 <5 <6 5-12-86(D) 390 + 60 390 + 50 <4 <9 <4 <5 <12 <8 <7 <4 <4 <5 6-09-86 (C ) <190 330 + 50 <4 <13 <4 <5 <11 <8 <ll <4 <5 <7 6-09-86(D) <190 260 + 50 <4 <13 <4 <5 <12 <8 <ll <5 <5 <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 T40 4-14-86 1860 + 80 3900 + 100 <34 <8 332 + 10 5-12-86 700 + 50 2000 + 100 <10 675 + 19 <10 140 + 7
6-10-86 1150 + 70 2600 + 100 26 + 4 67+14 <10 372 + 11 T41 '-14-86 1100 + 60 2500 + 100 <8 <30 <7 95 + 6 5-12-86 870 + 60 1700 + 100 <12 655 + 19 <10 212 + 9 6-10-86 760 + 60 2700 + 100 18+5 75 + 12 <10 215 + 8 T67 4-14-86 1730 + 70 3400 + 100 <9 <27 <8 71 +.6 5-12-86 1020 + 60 2200 + 100 <9 554 + 18 <9 36+ 4 6-09-86 1480 + 60 2400 + 100 39+ 5 128+ ll 25+ 3 53+6 DOE Split Sample.
NOTE: 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 Collection Locations Number of Sam le T e Fre uenc
1. Direct Radiation Quarterly 21 42
2. Airborne 2.a Air Iodines Weekly 65 69*
2.b Air Particulates Weekly
3. Waterborne 3.a Surface Water Monthly 12 3.b Shoreline Sediment Semiannually 3
4. Ingestion 4.a Fish and Invertebrates 4.-a.l Crustacea Semiannually 4.a.2 Fish Semiannually 4.b Food Products 4.b.l Broadleaf Monthly Vegetation Total: 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 Deployed 6-09-86 Site Collected 9-23-86 N-1 4.9 + 0.3 N-5 5.9 + 0.3 N-10 5.4 + 0.3 NNW-1 5.7 + 0.3 NNW-10 6.1 + 0.3 NW/WNW-1 5.0 + 0' NW-5 5.5 + 0.3 NW-10 7.6 + 0.4 W/WNW-5 4.9 + 0.3 WNW>>10 6.5 + 0.3 W-1 5.5 + 0.3 W-10 6.5 + 0.3 WSW-10 4.7 + 0.2 SW/SSW-1 5.4 + 0.3 SW-10 5.2 + 0.3 SSW/SW-5 5.4 + 0.3 SSW-10 5.5 + 0.3 S-5 4.8 + .0.3 S-10 5.6 + 0.3 SSE/S-1 4.8 + 0.3 SSE-10 4.7 + 0.2 NOTES:
1 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 than of the ~t ical error for such measurements rather accurately representing the error terms for individual measurements.
2. These results have been determined with the assumption that fading is negligible, although detailed testing to confirm this has not been done.
3. 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 Deployed 6-09-86 Site Collected 9-23-86 N-1 Due to failure of the TLD reader N-5 normally used, these dosimeters N-10 were read out on a new instru-NNW-1 ment. Final results for these NNW-10 readings cannot be determined NW/WNW-1 until the behavior of these Nw-5 dosimeters (i.e., net responsei Nw-10 self-exposure rate, and fading)
W/WNW-5 can be determined on this new WNW-10 instrument. This could not be W-1 completed for this report. This W-10 data will- be included as an Wsw-10 addendum to a future report.
SW/SSW-1 Sw-10 SSW/SW-5 Ssw-10 S-5 S-10 SSE/S-1 SSE-10
2.a IODINE-131 IN WEEKLY AIR FILTERS ( Ci/m3 )
Collection Sam le Site Date T51 T57 T58 T64 T72 7-08-86 <0. 02 <0; 02 <0.02 <0.02 <0.02 7-15-86 <0.03 <0.03 <0.03 <0.03 <0.03 7-22-86 <0.03 <0.03 <0.03 <0.03
<0.03'0.03 7-29-86 <0.03 <0.03 <0.03 <0.03 8-05-86 <0.03 <0.03 <0.03 <0.03 <0.02 8-12-86 <0.02 <0.02 <0.02 <0.03 <0.02 8-19-86 <0.05(A) <0.04 <0.03 <0.03 <0.03 8-25-86 <0.04 <0.04 <0.03 <0.04 <0.04 9-02-86 <0.02 <0.02 <0.02 <0.02 <0.03 9-08-86 <0.03 <0.03 <0.03 <0.03 <0.03 9-16-86 <0.02 <0.02 <0'. 02 ~0.06(B) <0 '2 9-23-86 <0.02 <0.02 <0. 02 <0.02 <0.02 9-30-86 <0.03 <0.03 .<0.03 <0.03 <0.02 (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/m3 )
Collection Sam le Site Date T51 T57 T58 T64 T72 7-08-86 0. 017 + 0.002 0.020 + 0.002 0.019 + 0.002 0.021 + 0.002 0.019 + 0.002 7-15-86 0.017 + 0.002 0.015 + 0.002 0.016 + 0.002 0.015 + 0.002 0.017 + 0.002 7-22-86 0.017 + 0.002 0.018 + 0.002 0.018 + 0.002 0.016 + 0.002 0.020 + 0.002 7-29-86 0.017 + 0.002 0.016 + 0.002 0.017 + 0.002 0.020 + 0.002 0.015 + 0.002 8-05-86 0.014 + 0.002 0.014 + 0.002 *0.016 + 0.002 0.014 + 0.002 0.011 + 0.002 8-12-.86 0.009 + 0.001 0.013 + 0.002 *0.012 + 0.002 0.010 + 0.002 , 0.009 + 0.001 8-19-86 (A0.016 + 0.002 0.013 + 0.002 '""0.012 + 0.002 0.011 + 0.002 0.017 + 0.002 8-25-86 0.022 + 0.002 0.016 + 0.002 *0.022 + 0.002 0.020 + 0.002 0,028 + 0.003 9-02-86 0.016 + 0.002 0.013 + 0.002 0.015 + 0,.002 0.012 + 0.002 0.019 + 0.002 9-08-86 0.014 + 0.002 0.014 + 0.002 0.015 + 0.002 0.010 + 0.002 0.014 + 0.002 9-16-86 0.019 + 0.002 0.022 + 0.002 0.018 + 0.002 (B0.029 + 0.004 0.025 + 0.002 9-23-86 0.012 + 0.002 0.014 + 0.002 0.012 + 0.002 0.012 + 0.002 0.013 + 0.002 9-30-86 0.016 + 0.002 0.014 + 0.002 0.010 + 0.002 0.012 + 0.002 0.017 + 0.002 Means: 0.016 + 0.001 0'.016 + 0.001 0.016 + 0.001 0.016 + 0.001 0.017 + 0.001 DOE split samples.
(A) 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/m3 )
Third {}uarter, 1986 Sample Site Be-7 K-40 Cs-134 Cs-137 Pb-210 T51 0.098 + 0.007 <0. 023 <0.0007 <0.0009 <0.034 T57 0.092 + 0.008 <0.013 <0.0009 <0.0009 <0.030 T58 0.091 + 0.008 <0.016 <0.0009 <0.0008 <0.035 T64 0.100 + 0.009 ,<0.024 <0.0008 <0.0008 <0.035 T72 0.111 + 0.008 <0.023 <0.0009 <0.0008 <0.033
3.a SURFACE HATER ( 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 7-17-86 <210 240 + 50 <4 <10 <4 <5 <9 <8 <5 <5 <5 <6 8-11-86 <210 360 + 50 <5 <9 <4 <5 <9 <9 <5 <6 <5 <4 9-10-86 <210 340 + 50 <4 <9 <4 <4 <ll <7 <5 <5 <5 <7 T67 7-17-86 <210 260 +. 50 <4 <10 <4 <5 <9 <8 <6 <4 <5 <4 8-12-86 <210 260 + 50 <5 <10 <5 <5 <11 <8 <7 <4 <4 .<5 9-10-86 <210 260 + 50 <4 <9 <4 <5 <11 <8 <6 <5 <5 <8 T81 7-17-86 7-17-.86 (C) 350 + 60 (D)'40 + 60 250 240
+
+
50 50
<5
<5
<1'4
<10 <4
<4
<5
<12
<10
. <8
<8
<6
<6
<6 <5 <8
<5 <5 <6 8-11-86 8-11-86 (C) 560 + 70 290 + 50 <3 <11 <4 <5 <ll <9 <8 <5 <5 <5 (D) 690 + 70 310 + 50 <4 <12 <4 <4 <12 <8 <7 <5 <5 <8 9-10-86 (C) <210 300 + 50 <5 <8 <4 <5 <11 <7 <5 <5 <4 <10 9-10-86 (D) <210 330 + 50 <4 <8 <3 <5 <8 <8 <4 <5 <4 <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 mouth.
at the normal location in the old discharge canal about 200'est of the.
(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 + 20 Th-232: 33 +7 U-235: 68 + 7 U-238: 700 + 100 T67 7-17-86 200 + 60 - 770 + 90 <11 <12 <14 <14 <12 Ra-226: 550 + 30 Th-232: 70 + 30 U-238: 380 + 90 T81 7-17-86 320 + 60 - 470 + 70 <11 <11 <9 <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 <46 <15 <13 <32 <13 13 + 5 Ra-226: <220 Ra-228: <60 T81 8-06-86 2900 + 200 <14 <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 11+4 <13 <11 204 +
8-12-86 9-10-86 1620 + 70 2320 + 80 2500 + 100 2900 + 100
<10
<10
<16
<16
<10
<10 386 +
102 +
ll 9
6 T41 7-17-86 1730 + 60 3100 + 100 10+4 <11 14+ 6 108 + 7 8-12-86 1480 + 70 2800 + 100 <10 <14 <10 147 + 8 9-10-86 1520 + 70 3800 + '=00 <10 <16 <11 425 + ll T67 7-17-86 2060 + 80 4100 + 100 15+4 <13 11+ 2 114 + 7 8-12-86 680 + 50 5300 + 200 <10 <13 <11 28+5 9-10-86 1480 + 70 2800 + 100 <9 <16 <9 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 Collection Locations Number of Sam le T e Fre uenc
1. Direct Radiation Quarterly 21 42
2. Airborne 2.a Air Iodines Weekly 65 2.b Air Particulates Weekly 69*
3. Waterborne 3.a Surface Water Monthly 12 3.b Shoreline Sediment Semiannually 0
4. Ingestion 4.a Fish and Invertebrates 4.a.l Crustacea Semiannually 4.a.2 Fish Semiannually 4.b Food Products 4.b.l Broadleaf Monthly 10*
Vegetation Total: 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 Deployment 9-22-86 Site Collection 12-15-86 N-1 4.9 + 0.3 N-5 5.6 + 0.3 N-10 5.0 + 0.3 NNW-1 5.7 + 0.3 NNW-10 5.9 + 0.3 NW/WNW-1 4.9 + 0.3 Nw-5 5.2 + 0.3 Nw-10 7.4 + 0.4 W/WNW-5 4.7 + 0.2 WNW-10 6.6 + 0.3 W-1 5.1 + 0.3 W-10 6.6 + 0.3 Wsw-10 4.8 + 0.3 SW/SSW-1 4.7 + 0.2 Sw-10 4.9 + 0.3 SSW/SW-5 5.2 + 0' Ssw-10 5.3 + 0.3 S-5 5.0 + 0.3 S-10 5.3 + 0 3 SSE/S-1 4.8 + 0.3 SSE-10 4.7 + 0.2 NOTES:
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.
2. These results have been determined with the assumption that fading is negligible, although detailed testing to confirm this has not been done.
3. 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 Deployment 9-23-86 Site Collection 12-15-86 N-1 Due to failure of the TLD reader N-5 normally used, these dosimeters N-10 were read out on a new instru-NNW-1 ment. Final results for these NNW-10 readings cannot be determined NW/WNW-1 until the behavior of these Nw-5 dosimeters (i.e., net response, Nw-10 self-exposure rate, and fading)
W/WNW-5 can be determined on this new WNW-10 instrument. This could not be W-1 completed for this report. This
. W-1O data will be included as an WSW-10 addendum to a future report.
Sw/SSW-1 Sw-10 SSW/SW-5 SSW-10
$ -5 S<<lo SSE/S-1 SSE-10
2.a IODINE-131 IN WEEKLY AIR FILTERS - ( Ci/m 3 )
Collection Sam le Site Date T51 T57 T58 T64 T72 10-07-86 <0.03 <0.03 <0.03 <0.03 <0.03 10-14-86 <0.03 <0.03 <0.03 <0.03 <0.03 10-21-86 <0.03 <0.03 <0.03 <0.03 <0.03 10-28-86 <0.02 <0.02 <0.02 <0.02 <0.02 11-04-86 <0.03 <0. 03 <0.03 <0.02 <0.02 11-12-86 <p.p6 (A) <p.p6 (A) <0.06 (A) <0 ~ 06 (A) <0.06 (A) 11-18-86 <0.03 <0.02 <0. 02 <0 ..02 <0. 02 11-25-86 <0. 03 <0.03 <0. 03 <0.03 <0.03 12-02-86 <0. 02 <0.02 <0.02 <0.02 <0.02 12-09-86 <0. 03 <0.03 <0.03 <0.03 <0.03 12-16-86 <0. 02 <0.02 <0.02 <0.02 <0.02 12-22-86 <0.02 <0.02 <0.02 <0.02 <0. 02 12-30-86 <0.03 '0.03 <0.03 <0.03 <0.03 (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/m3 )
Collection Sam le Site Date T51 T57 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 0.015 + 0.002 0.013 + 0-002 0-011 + 0-002 0-010 + 0-002 0.012, + 0.002 10-21-86 0.015 + 0.002 0.013 + 0.002 0.0 ' + 0.002 0.013 + 0.002 0.016 + 0.002 10-28-86 0.012 + 0.002 0.012 + 0.002 0.014 + 0.002 0.013 + 0.002 0.013 + 0.002 11-04-86 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 0.011 + 0.002 0.009 + 0-002 *0.011 + 0-002 0.009 + 0.002 0.012 + 0.002 11-25-86 0.008 + 0.001 0.012 + 0.002 *0.011 + 0-002 0-009 + 0.001 0.010 + 0.002 12-02-86 0.011 + 0.002 0.007 + 0.001 0.008 + 0.001 0.008 + 0.001 0.007 + 0.001 12-09-86 0.011 + 0.002 0.013 + 0.002 0.018 + 0.002 0.015 + 0.002 0.016 + 0.002 12-16-86 0.012 + 0.002 0.010 + 0 002 0-009 + 0.001 0-012 + 0.002 0-010 + 0.002 12-22-86 0.015 + 0.002 0.016 + 0.002 0.016 + 0.002 0.012 + 0.002 0.014 + 0.002 12-30-86 0.010 + 0.001 0.016 + 0.002 . 0.012 + 0.002 0.013 + 0.002 0.020 + 0.002 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, which resulted in a longer than usual delay before they could be analyzed.
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 <0. 023 <0.0007 <0.0008 T57 0.102 + 0.008 <0. 025 <0.0008 <0.0007 T58 0.112 + 0.009 <0.024 <0.0008 <0.0007 T64 0.105 + 0.008 <0.023 <0.0007 <0.0007 T72 0.104 + 0.007 <0.016 <0.0009 <0.0007
3.a SURFACE WATER ( Ci/1)
Sample Collection H 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 10-13-86 <190 270 + 50 <4 <9 <4 <6 <10 <9 <6 <4 <5 <8 11-18-86 <180 240 + 50 <5 <11 <4 <5 <11 <7 <7 <5 <5 <8 12-15-86 <260 280 + 50 <4 <11 <5 <5 <12 <7 <5 <5 <4 <4 T67 10-13-86 <190 280 + 50 <4 <12 .<4 <4 <10 <7 <5 <5 <4 <5 "11-18-86 <180 320 + 50 <4 <11 <4 <5 <10 <9 <8 <5 <4 <6 12-16-86 '<260 310 + 50 <4 <8 <4 <4 <10 <9 <5 <5 <5 <7 T81 10-13-86 (C) 140 + 60 320 + 60 <5 <11 <4 <4 <8 <9 <9 <5 <5 <7 10-13-86 (D) <190 350 + 50 <5 <12 <5 <6 <10 <9 <9 <5'4 <5 <8 11-18-86 (C) 150 + 60 320 + 50 <4 <8 <4 <5 <11 <9 <6 <4 <5 11-18-86 (D) 570 + 60 300 + 50 <4 <10 <4 <4 <9 <6 <6 <5 <6 <7
- 12-15-86(C) <260 320 + 50 <4 <9 <4 <5 <9 <8 <5 <5 <5 <7 12-15-86(D) <260 360 + 50 <4 <10 <4 <5 <7 <7 <6 <5 <4 <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 <11 452 + 13
11-18-86 1100 + 60 3600 + 100 <8 <7 214 + 9 12-16-86 1790 + 70 2500 + 100 <12 <9 201 + 9 T41 10-13-86 1540 + 70 2700 + 100 <16 <9 312 + 10 11-18-86 720 + 40 3000 + 100 <6 <7 77+ 6 12-16-86 1260 + 60 3100 + 100 '10 <11 134+ 8 T67 10-13-86 780 + 50 1930 + 90 <10 60+ 5 11-18-86 1080 + 50 3500 + 100 <8 <9 <9 12-16-86 1630 + 60 4400 + 100 <11 <9 <10
- DOE split sample.
1986 ANNUAL RADIQQXICAL H47IBCRvKNZAL OPERATIC 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 January through June, 1986 Media Nuclide Collection EPA Units Normal. Mean of N.DE K. Action Mon Day Yr Known Range Analyses Level REFILTER FILTER Alpha 04 25 86 15 pCi/F 0 16 0. 34 Beta 04 25 86 47 pCi/F 0.474 46 -0.34 FILTER Cs-137 04 25 86 10 pCi/F 0.118 12. 66 0.92 FILTER Sr-90 04 25 86 18 pCi/F 0.395 15. 33 -3.08 FOOD I-131 01 31 86 20 pCi/Kg 0.197 20. 66 0. 19 FOOD Cs-137 Ol 31 86 15 pCi/Kg 0.118 14.33 -0.23 FOOD K Ol 31 86 950 pCi/Kg . 0.248 1013.'33 0. 77 FOOD Sr-89 01 31 86 25 pCi/Kg 0.237 11 -4.85 (2)
FOOD Sr-90 01 31 86 10 pCi/Kg 0.395 11. 66 1. 92 MILK I-131 10 25 85 42 pCi/L 0.197 49.66 2.21 MILK I-131 06 27 86 pCi/L NA MILK Cs-137 10 25 85 56 pCi/L 0.355 58. 67 0.92 MILK Cs-137 06 27 .86 pci/L NA MILK K 10 25 85 1540 pCi/L 0.23 1596.66 1.27 MILK K 06 27 86 pCi/L NA MILK Sr-89 10 25 85 48 pCi/L 0.237 46.66 -0.46 MILK Sr-89 06 27 86 pCi/L 'NA MILK Sr-90 10 25 85 26 pCi/L 24 -2. 31 MILK Sr-90 06 27 86 pCi/L NA WATER Alpha 11 22 85 10 pCi/L 0.118 11.,66 0.58 ATER Alpha Ol 24 -
86 3 pCi/L 0.118 3. 66 0. 23 TER Alpha 03 21 86 15 pCi/L 0.118 12.33 -0. 92 ATER Alpha 05 23 86 8 pCi/L 0.118 6.67 -0.46 WATER Beta 11 22 85 13 pCi/L 0 16 1.03 WATER Beta 01 24 86 7 pCi/L 0.118 7. 67 0.23 WATER Beta 03 21 86 8 pCi/L 0.118 9.33 0.46 WATER Beta 05 23 86 15 pci/L 0.118 16.66 0.58 WATER Cr-51 02 07 86 38 pCi/L "0.576 44 2.07 WATER Cr-51 06 06 86 0 pCi/L 0 0 0 WATER Co-60 02 07 86 18 pCi/L 0. 118 19. 66 0.58 WATER Co-60 06 06 86 66 pCi/L 0.118 66. 67 0.23 WATER Zn-65 02 07 86 40 pCi/L 0.237 43 1.03 WATER Zn-65 06 06 86 86 pCi/L 0.592 90.67 1.61 WATER RU-106 02 07 86 0 pCi/L 0 0 0 WATER Ru-106 06 06 86 50 pCi/L 0. 711 50.33 0. 11 WATER Cs-134 02 07 86 30 pCi/L 0.118 28.66 -0. 46 WATER Cs-134 06 06 86 49 pCi/L 0.237 47 -0.69 Cs-137 22 pCi/L 0.237 22 WATER WATER WATER Cs-137 H-3 02 06 02 07 06 14 86 86 86 10 5227 pCi/L pCi/L 0.091 0
5183.33 ll 0. 34
-0.14 0
WATER H-3 06 13 86 3125 pCi/L 0.362 3143.33 0. 09 WATER I-131 12 06 85 45 pCi/L 0.197 50 1.44 WATER Sr-89 01 10 86 31 pCi/L 0.355 29. 66 -0.46 WATER Sr-89 05 09 86 5 pCi/L 0.237 5 0 WATER Sr-90 01 '10 86 15 pCi/L 0 15 0 WATER Sr-90 05 09 86 5 pCi/L 0.395 4. 66 -0.38
NOTES:
Normal.: Normalized range. As defined in "Environmental Radioactivity Lab-ange 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) Cause: Chemical recovery too low. Corrective action: Try to improve recovery.
(2) 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 EPA Units Normal. Mean of N.D.K. Action Mon Day Yr Known Range Analyses Level FILTER Alpha 09 12 86 22 pCi/F 0. 829 17. 33 -1. 61 FILTER Beta 09 12 86 66 pCi/F 0. 237 64.67 -0. 46 FILTER Cs-137 09 12 86 22 pCi/F 0. 237 25.00 1. 03 FILTER Sr-90 09 12 86 22 pCi/F 0.395 21.33 -0. 77 FOOD I-131 07 25 86 30 pCi/Kg 0.197 29.00 -0. 29 FOOD Cs-137 07 25 86 20 pCi/Kg 0.118 21.66 0. 58 FOOD K 07 25 86 1150 mg/Kg 0.817 1173.33 0. 70 FOOD Sr-89 07 25 86 30 pCi/Kg NDP FOOD Sr-90 07 25 86 19 pCi/Kg NDP MILK I-131 06 27 86 41 pCi/L 0. 197 44. 00 0.87 MILK I-131 10 31 '86 pCi/L NA MILK Cs-137 06 27 86 31 pCi/L 0.000 4.00 -9.35 MILK Cs-137 10 31 86 pCi/L NA MILK K 06, 27 86 1600 mg/L 0.296 1616.66 0.36 MILK K 10 31 86 mg/L NA MILK Sr-89 06 27 86 pci/L 0.237 0. 67 0.23 MILK Sr-89 10 31 86 pCi/L NA MILK Sr-90 06 27 86 16 pCi/L 0.395 12. 33 -4. 23 (2)
MILK Sr-90 10 31 86 pCi/L NA
,. WATER Alpha 07 18 86 6 pCi/L 0.118 5. 67 -0.11 WATER Alpha 09 19 86 15 pCi/L 0.000 00 0. 34 ATER ATER Alpha Beta ll 07 21 18 86 86 20 18 pCi/L pCi/L 0.237 0.000
~;6.
13.
18.
66 00
-2. 19
0. 00 (3)
WATER Beta 09 19 86 8 pCi/L 0.000 10. 00 0. 69 WATER Beta 21 86 20 pCi/L 0.000 22. 00 0.69 WATER Cr-51 06 06 86 0 pCi/L 0.000 0. 00 0.00 WATER Cr-51 10 10 86 59 pCi/L 0.592 55. 33 -1.27 WATER Co-60 06 06 86 66 pCi/L 0.118 66.67 0.23 WATER Co-60 10 10 86 31 pCi/L 0. 118 31.66 0. 23 WATER Zn-65 06 06 86 86 pCi/L 0.592 90.67 1.61 WATER Zn-65 10 '10 86 85 pCi/L 0.576 89.33 1.50 WATER Ru-106 06 06 86 50 pCi/L 0.711 50.33 0.11 WATER Ru-106 10 10 86 74 pCi/L 1.927 72.00 -0.69 WATER Cs-134 06 06 86 49 pCi/L 0.237 47.00 -0.69 WATER Cs-134 10 10 86 28 pCi/L 0. 237 26.00 -0. 69 WATER Cs-137 06 06 86 10 pCi/L 0. 000 11.00 0. 34 WATER Cs-137 10 10 86 44 .pCi/L 0. 237 44.66 0. 23 WATER H-3 06 13 86 3125 pCi/L 0. 362 3143.33 0. 09 WATER H-3 10 17 86 5973 pCi/L NDP WATER I-131 08 08 86 45 pCi/L 0.197 41.33 -1.05
NOTES ormal.: Normalized range. As defined in "Environmental Radioactivity Lab-ange 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.

ML17347A458

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