nuclear regulatory commission · accession nbr fac il:50-335 50-389 auth. name woody> c. o....
TRANSCRIPT
ACCESSION NBRFAC IL: 50-335
50-389AUTH. NAME
WOODY> C. O.RECIP. NAME
REGULATO ' INFORMATION DISTRIBUTION STEM (RIDS)
8709080078 DOC. DATE'7/06/30 NOTARIZED: NOSt. Lucie Planti Unit 1> Florida PoUJer 8c Light Co.St. Lucie Planti Unit 2i. Florida Power 8c Light Co.
AUTHOR AFFILIATIONFlorida Poeer 8c Light Co.
RECIPIENT AFFILIATION
DOCKET 00500033505000389
SUBJECT: "Combined Semiannual Radioactive Effluent Release Rept forJan-June 1987," W/870831 ltr.
DISTRIBUTION CODE: IE4SD COPIES RECEIVED: LTR ( ENCL g SIZE: 3TITLE: 50. 36a(a) (2) Semiannual Effluent Release Reports
NOTES:
RECIP IENTID CODE/NAME
PD2-2 LATOUR IGNYs E
INTERNAL: AEOD/DOAARM TECH *DV
RE F 012/DRSS/EPRPB
COPIESLTTR ENCL
01
1
1
1 1
1 1
RECIPIENTID CODE/NAME
PD2-2 PD
AEOD/DSP/TPABNRR/DEST/PSBNRR/PMAS/ILRBRGN2 FILE 02
COP IESLTTR ENCL
5 5
1 1
1
1 1
1 1
EXTERNAL'NL TICHLERe JNRC PDR
1
1 1
LPDR 1 1
TOTAL NUMBER OF COP IES REQUIRED: LTTR 22 ENCL 21
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P. O. Y 14000, JUNO BEACH, FL 33408-0420
Ol/pi
AUGUST 3 g f987
L-87-356
U. S. Nuclear Regulatory Commission'ttn:Document Control Desk
Washington, D. C. 20555
Gent I emen:
Re: St. Lucie Units I and 2Docket Nos. 50-335 and 50-389Semi-Annual Radioactive Effluent Release Re ort
Attached is the Radioactive Effluent Release Report for the period of January I,l987 through June 30, l987 for St. Lucie Units I and 2, as required by TechnicalSpecification 6.9. I.7.
Should there be any questions on this information, please contact us.
Very truly yours,
. O. Woodyroup Vice President
Nuclear Energy
COW/GRM/gp
Attachment,
cc: Dr. J. Nelson Grace, Regional Administrator, Region II, USNRCR. J. Crlenjak, Senior Resident Inspector, USNRC, St. Lucie Plant
GR M5/0 I 4/ Ian FPL Group company
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FLORIDA PONER 8c LIGHT COMPANY
ST. LUCIE PLANT UNITS NO i 8c 2
LICENSE NO.S DPR-b7 5 NPF-)b
COMBINED SENI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
FOR THE PERIOD
JANUARY i~ )987 THROUGH JUNE 38~ )987
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TABLE OF CONTENTS
DESCRIPTION
EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION
OFFSITE DOSE CALCULATION MANUAL REVISIONS . 7
SOLID WASTE AND IRRADIATEK;;'UELSHIPMENTS.......... ~ ~ .. 7
PROCESS CONTROL PROBRAM REVISIONS... 7
LIQUID EFFLUENT:SUMMATION OF ALL RELEASES Zc NUCLIDE SUMMATION BY QUARTER
UNIT 8 1 ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ s ~ ~ ~ ~ or ~ s ~ asa ~ a ~ a ~ o ~ s ~ ~ s ~ ~ ~ 8
UNIT 5 ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~5 > 11
GASEOUS EFFLUENT:SUMMATION OF ALL RELEASES 5 NUCLIDE SUMMATION BY QUARTER
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SOLID NASTE — SHIPMENT SUMMATION ... ~ ... ~ 18
OFFSITE DOSE CALCULATION MANUAL PAGE REVISIONS ATTACHMENT- A
PROCESS CONTROL PROBRAM PROCEDURE PAGE REVISIONS. .. ATTACHMENT- B
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EFFLUENT AND WASTE DISPOSAL SUPPLENENTAL INFORMATION
1. Regulatory Limits
1.1 For Liquid Waste EffluentsA. The concentration of radioactive material released from the site
shall be limited to the concentrations specified in 1$ CFR Part 2$Appendix B, Table XI, Column 2 for radionuclides other thandissolved or entrained noble gases. For dissolved or entrainednoble gases, the concentration shall be limited to 2E-4 micro-Curies/ml total activity.
B. The dose or dose commitment to a MEMBER OF THE PUBLXC fromradioactive material in liquid effluents released, from eachreactor unit, to UNRESTRICTED AREAS shall be limited to:
During any calendar quarter to <= 1.5 mrems to the Total Bodyand to <~ 5 mrems to any organ, and
During any calendar year to <= 3 mrems to the Total Body andto <= 18 mrems to any organ.
1.2 For Gaseous Waste Effluents:A. The dose rate in UNRESTRICTED AREAS due to radioactive materials
released in gaseous effluents from the site shall be limited to:For Noble Bases: <= 5$$ mrems/yr to the total body and
<= 388$ mrems/yr to the skin, andN
For Iodine-131, Iodine-133, Tritium, and all radionuclidesin particulate form with half-lives greater than 8 days:
<= 158$ mrems/yr to any organ.
+B The air dose due to noble gases released in gaseous effluentsfrom each reactor unit, to areas at and beyond the SITEBOUNDARY shall be limited to the following:During any calendar quarter, to <~ 5 mrads for gamma radiation,and
1$ mrads for beta radiation and, during any calendar year to<~ 1$ mrads for gamma radiation and <= 2$ mrads for beta radiation.
+C. The dose to a NENBER OF THE PUBLIC. from Iodine-131, Iodine-133,Tritium, and all radionuclides in particulate form, with half-lives > 8 Days in gaseous effluents released, from each reactorunit to areas at and beyond the site boundary, shall be limitedto the followingsDuring any calendar quarter to <= 7.5 mrem to any organ, andDuring any calendar year to <= 15 mrem to any organ.
The calculated doses contained in a semi-annua) report shall notapply to any STS LCO. The reported values are based on actualrelease conditions instead of historical conditions that the STSLCO dose calcuations are be on. The STS LCO dose limits aretherefore included in Item bf the report, for information only.
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EFFLUENT AND MASTE DISPOSAL SUPPLENENTAL INFORMATION(Continued)
2. Maximum Permissible Concentrations
Mater: As per 1$ CFR 2$ Part 2$ , Appendix B, Table II, Column 2,except for entrained or dissolved noble gases as described in1. 1. A of this report.
Air: Release concentrations are limited to dose rate limitsdescribed in 1.2.A. of this report.
3. Average Energy of fission and activation gases in gaseous effluentsis not applicable.
4. Measurements and approximations of total radioactivityMhere alpha, tritium, and named nuclides are shown as zero Curiesreleased, this should be interpreted as "no acitvity was detected onthe samples using the Plant Technical Specification analyses techniquesto achieve required Lower Limit of Detection (LLD) sensitivity forradioactive effluent''.A summary of liquid effluent accounting methods is describedin Table 3.1.
A summary of gaseous effluent accounting methods is describedin Table 3.2.
4.1 Estimate of ErrorsL!QUID GASEOUS
Error Topic
Avgas
% Max ~ % Avgs % Max o%
Release Point NixingSamplingSample PreparationSample Analysi sRelease Volume
211
32
555
1$5
NA2
34
NA55
1$15
Total % 9
The predictability of error for radioactive releases can only beapplied to nuclides that are predominant in sample spectrums.Nuc)ides that are near background relative to the predominantnuclides in a given sample could easily have errors greater thanthe above listed maximums.
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EFFLUENT AND NASTE DISPOSAL SUPPLEMENTAL INFORMATION(Continued)
4. Measurements and Approximations of Total Radioactivity (Cont.)4.1 (Continued)
B. (Continued)
TABLE 3 1
RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS
LiquidSource
SamplingFrequency
Type ofAnalysis
Method ofAnalysis
Each Batch Principal Gamma Emitters p h a
MonitorTank
1
Releases
ContinuousReleases
MonthlyComposite
QuarterlyComposite
DailyGrab
Samples
TritiumGross Alpha
Sr-89~ Sr-98~5 Fe-55
Principal Gamma Emitters8c 1-131 for4/M Composite Analysis
Dissolved 5 Entrained GasesOne Batch/ Month
Tritium Composite Monthly
Alpha Composite Monthly
Sr-89, Sr-9$ , 5 Fe-55Composite Quarterly
L S.G.F.P
C S.
p.h. a.
p.h.a.L S
6 F.P.
C S
1-Boric Acid Evaporator Condensate is normal)y recovered to thePrimary Mater Storage Tank for recycling into the reactor coolantsystem and does not contribute to Liquid Waste Effluent Totals.
p.h.a.-Gamma Spectrum Pulse Height Analysis using Lithium GermaniumDetectors. All peaks are identified and quantified.
L.S.-Liquid Scintillation CountingC.S. -Chemi cal SeparationG F P -Gas Flow Proportional Counting4/M-Four per Month
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EFFLUENT AND NASTE DISPOSAL SUPPLEMENTAL INFORMATION(Continued>
4. Measurements and Approximations of Total Radioactivity (Continued>4.1 (Continued)
B. (Continued)
TABLE 3 2
RADIOACTIVE GASEOUS MASTE SANPLINB AND ANALYSIS
GaseousSource
SamplingFrequency
Type ofAnalysis
Nethod ofAnalysis
Waste GasDecay TankReleases
ContainmentPurge
Releases
Each Batch Principal Gamma Emitters
Principal Gamma EmittersEach Purge Tritium
Principal Gamma EmittersTritium
p. h.a.
pshsaeL S.
p.h.a.L. S.
PlantVent
Nonthl yComposite
QuarterlyComposite
ParticulateGross Alpha
ParticulateSr-89 h Sr-'PS
B F P
C S
p.h.a.-Gamma Spectrum Pulse Height Analysis using Lithium GermaniumDetectors. All peaks are identified and quantified.
L.S.-Liquid Scintillation CountingC.S.-Chemical SeparationB.F.P.-Bas Flow Proportional Counting4/M-Four per Nonth
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FLORIDA POSER 4 LIGHT COMPANYST. LUCIS PLANT UNIT NO. 1
SEMIANNUAL REPORTJANUARY 1, 1887 THROUGH JUNE 30, 1987
EFFLUENT AND HASTE Dl'SPOSAL — SUPPLEMENTAL INFORMATION (CONT2NUED)
5. BATCH RELEASES AND UNPLANNED RELEASES
LIQUIDS FOR -'T. LUC2E PLANT UNIT NO. 1
A. NUMBER OF BATCH RELEASES:
B. TOTAL TIME PERIOD OF BATCH RELEASES:
C. MAXl'MUMT2ME PER2OD FOR A BATCH RELEASE:
D. AVERAGE Tl'ME PERIOD FOR A BATCH RELEASE:
E. MINIMUM TIME PERIOD FOR A BATCH RELEASE:
F. AVERAGE STREAM FLOP DURINGREPORT2NG PER2'OD INTO A FLOWING STREAM:
~ -,29;, g161 75. MINUTES
870. MINUTES
568. M2NUTES
407. MINUTES
868441. G.P.M.
6. GASEOUS FOR: ST. LUCIS PLANT UNl'T NO. 1
A. NUMBER OF BATCH RELEASES:
B. TOTAL Tl'ME PERIOD OF BATCH RELEASES:
C. MAX2MUM T2ME PERIOD FOR A BATCH RELEASE:
D. AVERAGE TIME PER2'OD FOR A BATCH RELEASE:
E. M2NIMUM TIME PER1'OD FOR A BATCH RELEASE:
UNPLANNED RELEASES
LIQUIDS FOR -'T. LUCIS PLANT UNIT NO. IA. NUMBER OF RELEASES:B. TOTAL ACTIV1'TY RELEASED:
GASEOUS FOR: ST. LUCIS PLANT UNIT NO.
A. NUMBER OF RELEASES:8, TOTAL ACTIVITYRZLZASZD:
SEE ATTACHMENTS (IF APPLICABLE) FOR:
11. 0
3867. MINUTES
600. MINUTES
352. MINUTES
180. MINUTES
0.0. CURIES
0.0. CURIES
A. A DESCRIPTION OF THE EVENT AND EQUIPMENT 2NVOLVED.B. CAUSE(S) FOR THE UNPLANNED RELEASE.C. ACTIONS TAEEN TO PREVENT A RECURRENCE.D. CONSEQUENCES OF THE UNPLANNED RELEASE.
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. e ~FLORIDA POSER & LIGHT COMPANYST. LUCIE PLANT UNIT NO. 2
SEMIANNUAL REPORTJANUARY 1 > 1987 THROUGH JUNE 80, 1987
EFFLUENT AND HASTE DISPOSAL - SUPPLEMENTAL INFORMATION (CONTINUED)
5. BATCH RELEASES AND UNPLANNED RELEASES
LIQUIDS FOR: ST. LUCIS PLANT UNIT NO. 2
A. NUMBER OF BATCH RELEASES:
B. TOTAL TIME PER1OD OF BATCH RELEASES:
C. MAXIMUMTIME PER1OD FOR A BATCH RELEASE:
D. AVERAGE T1ME PERIOD FOR A BATCH RELEASE:
E. M1N1MUM TIME PERIOD FOR A BATCH RELEASE:
F. AVERAGE STREAM FLOP DURl'NGREPORT1NG PERIOD 1NTO A FLOWING STREAM:
<gag261 75. MINUTES
870. MINUTES
568. MINUTES
407. MINUTES
868441. G.P.M.
6. GASEOUS FOR: ST. LUCIS PLANT UNIT NO. 2
A. NUMBER OF BATCH RELEASES:
B. TOTAL T1ME PER1'OD OF BATCH RELEASES:
C. MAXIMUMTl'ME PER1OD FOR A BATCH RELEASE:
D. AVERAGE T1ME PER1'OD FOR A BATCH RELEASE:
E. MlN1'MUM TIME PERIOD FOR A BATCH RELEASE:
UNPLANNED RELEASES
LIQUIDS FOR -'T. LUCIS PLANT UNIT NO. 2
A. NUMBER OF RELEASES:B. TOTAL ACTIVITY
RELEASED-'ASEOUS
FOR: ST. LUCIS PLANT UNIT NO. 2
A. NUMBER OF RELEASES:B. TOTAL ACTIV1TY RELEASED:
57. 0
14408. MINUTES
4920. MINUTES
258. MINUTES
l5. MINUTES
0.0. CUR1ES
0.0. CURIES
SEE ATTACHMENTS (IF APPLICABLE) FOR:
A. A DESCRIPT1'ON OF THE EVENT AND EQUIPMENT INVOLVED.B. CAUSE(S) FOR THE UNPLANNED RELEASE.C., ACTIONS TAEEN TO PREVENT A RECURRENCE.D. CONSEQUENCES OF THE UNPLANNED RELEASE.
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FLORIDA PONER 8c LIGHT COMPANYST. LUCIE PLANTS UNITS 1 8c 2
SEMIANNUAL REPORT
JANUARY 1, 1987 THROUGH JUNE 38~ 1987
EFFLUENT AND NASTE DISPOSAL — SUPPLEMENTAL INFORMATION
(Continued)
7. Assessment of radiation dose from radioactive effluents to MEMBERS OFTHE PUBLIC due to their activities inside the SITE BOUNDARY is reportedon the January report.
" 8. Offsite Dose Calculation Manual Revisions (ODCM):
The affected pages for Revision 88 to C-288 (ODCM) are included asAttachment-A to this report. The reason for the change was due toan NRC Audit of the ODCM where a deficiency was noted. The ODCMreference to R8 CFR 198 Dose Evaluation had excluded exceeding theAnnual Dose Limit L. C. O. s as a requi rement to perf orm 48 CFR 198.dose calculations. This Revision to the ODCM corrects thedeficiency and the ODCM is now correct in its reference to the PlantTechnical Specification requirements.
This item may also be referenced by letter dated March 27, 19B7(C. O. Moody to U.S. Nuclear Regulatory Commission) as the FloridaPower Sc Light Company response to the NRC Audit of the ODCM andthe Process Control Program.
This Revision to the ODCM was administrative in nature and did notchange Dose Methodology.
9. Solid Waste,and Irradiated Fuel Shipments:
No irradiated fuel shipments were made from the site. CommonSolid waste from St. Lucie Units 1 and 2 were shipped jointly.A summation of these shipments is given in Table 3.9 of thisreport.
18. Process Control Program (PCP) Revisions:
The PCP was revised during the reporting interval. The affectedpages are included as Attachment — B to this report. These changeswere administrative in nature and were made as a result of aUS N.R.C. review of the PCP.
FLOR1DA POSER & LIGHT COMPANYST. LUCIS PLANT UNIT NO. 1
SEMIANNUAL REPORTJANUARY 1, 188 7 THROUGH JUNE 30, 198 7
TABLE 3. 3-1LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES
NUCLIDES RELEASED UNIT QUARTER ¹1 QUARTER ¹2A. FISSION AND ACT1 VAT1'ON PRODUCTS
1. TOTAL RELEASE (NOT INCLUDl'NGTRITIUM, GASES, ALPHA)
2. A VERAGE DILUTED CONCENTRA TIONDURING PERIOD
B. TRITIUM
1. TOTAL RELEASE
2. A VERAGE Dl'LUTED CONCENTRA Tl'ONDUR1 NG PERIOD
C. D1SSOLVED AND ENTRAINED GASES
1. TOTAL RELEASE
Z. A VERAGE Dl'LUTED CONCENTRA TlONDUR1 NG PER1'OD
D. GROSS ALPHA RADIOACT1VITY
1. TOTAL RELEASE
E. VOLUME OF HASTE RELEASED(PRIOR TO DILUTION)
F. VOLUME OF D1LUTION h'ATERUSED DURING REPORT1NG PERIOD
2. 61E-01
UC1/ML 7. ZZE-10
8.21E Ol
UC1 /ML Z. 55E-07
1. 04E 01
UCI/ML 2. 87E-08
0. OOE-01
Ll'TERS l. 78E 07
LITERS 3. 61E 11
7.43E-02
1.52E-10
4.54E 01
8. 24E-08
5. 76E-02
1. 1 7E-10
0. OOE-01
2.88E 07
4.81E 11
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0FLORIDA POSER & LIGHT COMPANYST. LUC1'E PLANT UNIT NO. I
JANUARYSEM1 ANNUAL REPORT
I, 1987 THROUGH JUNE 80, 1987
TABLE 8. 4-1
L1QU1D EFFLUENTS
NUCL1'DESRELEASED UNIT
CONTINUOUS MODEQTR. ¹I QTR. ¹2
BATCH MODEQTR. ¹I QTR. ¹2
I-131I-132I-133I-135NA-24CR-51MN-54FE-55CO-57CO-58FE-59CO-60AG-110SN-113SB-122SB-124RB-88SR-89SR-90Y-90ZR-95NB-95NB-97TC-99MRU-103SB-125CS-184CS-136CS-137CS-138
C1CIC1CICICICICICICICICIC1CICIC1CICICICICIC1C1'1
CICIC1C1CI
CI'.
07E-020. OOE-013. 09E-020. OOE-010. OOE-010. OOE-010. OOE-Ol0. OOE-010. OOE-010. OOE-010. OOE-011.25E-050. DOS-010. OOE-010. OOE-010. OOE-010. OOE-010. OOE-010. OOE-010. OOE-010. OOE-Ol0. OOE-010. OOE-010. OOE-010. OOE-010. OOE-011. 40E-030. OOE-013.93E-030. OOE-01
4. ZIE-040. OOE-OI0. OOE-OI0. OOE-010. OOE-01D. DOS-010. ODE-Ol0. OOE-010. OOE-010. OOE-010. OOE-Ol0. OOE-Dl0. OOE-010. OOE-010. OOE-Ol0. OOE-010. OOE-Ol0. OOE-010. OOE-010. OOE-010. OOE-010. OOE-010. OOE-010. OOE-010. OOE-010. OOE-014. 70E-040. OOE-011.10E-03O.DOE-OI
1. 13E-OZ1.14E-031.12E-033. 91E-052. 50E-044. I7E-021. 72E-084. 71E-035. 64E-055. 45E-027.68E-04Z. 98E-021. 57E-033. 26E-040. OOE-011. 16E-026. 20E-049. IOE-D55. 70E-055. 70E-058. 31E-031.26E-029. 08E-04I . 07E-042. 38E-031.60E-OZ2. 78E-036. IIE-055. 18E-032. 84E-04
1. I7E-030. OOE-017. OOE-050. OOE-010. OOE-01I . 15E-OZ5. 96E-045. IOE-080. OOE-011. 09E-021.99E-041.66E-OZ8.99E-041.11E-041.38E-051. 72E-030. ODE-018. 75E-040. OOE-Ol0. OOE-01Z. 91E-034. 96E-03Z. 54E-040. OOE-015. 89E-047. 75E-031.81E-03O.OOE-OI3.58E-03I . 81E-05
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JANUARY
FLORIDA POWER 4 LIGHT COMPANYST. LUCIS PLANT UNIT NO.
SEMIANNUAL REPORT1987 THROUGH JUNE 30, 1987
TABLE 3. 4-1 CONTINUED
LIQUID EFFLUENTS
NUCLIDESRELEASED UNIT
CONTINUOUS MODEQTR. ¹1 QTR. ¹2
BATCH MODEQTR. ¹1 QTR. ¹2
liA-140CE-141CE-144TE-129TE-129M
TOTAL FORPERIOD
AR-41ER-85MXE-131MXE-138XE-133MXE-135
TOTAL FORPERIOD
CICICICICI
CICICICICICI
0. OOE-010. OOE-010. OOE-010. OOE-010. OOE-01,
0. OOE-010. OOE-010. OOE-010. OOE-010. OOE-01
1.96E-033. 31E-04Z. 34E-049. 26E-044.88E-04
3. 47E-049. 49E-052. 54E-040. OOE-010. OOE-01
0. OOE-010. OOE-010. OOE-011.45E-030. OOE-010. OOE-01
0. OOE-010. OOE-010. OOE-010. OOE-010. OOE-010. OOE-01
8. 93E-054. 55E-043. 13E-021.01E 011. 26E-Ol8. 71E-OZ
0. OOE-010. OOE-010. OOE-015. 55E-02Z, 26E-041. 91E-03
1. 45E-03 0. OOE-01 1. 04E 01 5. 76E-OZ
4. 69E-02 2. OOE-03 2. 14E-01 7. 23E-02
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FLORIDA POSER & LIGHT COMPANYST. LUCIS PLANT UNIT NO. 2
SEMIANNUAL REPORTJANUARY 1, 198 7 THROUGH JUNE 80, 198 7
TABLE S. 8-2LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES
NUCLIDES RELEASED UNIT QUARTER ¹1 QUARTER ¹2A. FISSION AND ACTIVATIONPRODUCTS
TOTAL RELEASE (NOT INCLUDINGTRITIUM, GASES, ALPHA)
2. A VERAGE DILUTED CONCENTRA TIONDURING PERIOD
B. TRITIUM
1. TOTAL RELEASE
2. A VERAGE DILUTED CONCENTRA TIONDURING PERIOD
C. DISSOLVED AND ENTRAINED GASES
I . TOTAL RELEASE
2. A VERAGE DILUTED CONCENTRA TIONDURING PERIOD
D. GROSS ALPHA RADIOACTIVITY
1. TOTAL RELEASE
E. VOLUME OF HASTE RELEASED(PRIOR TO DILUTION)
F. VOLUME OF DILUTION PATERUSED DURING REPORTING PERIOD
2. 14E-01
UCI/ML 5.92E-IO
9.21E 01
UCI'/ML 2.55E-07
1. 04E 01
UC1/ML 2. 8 7E-08
0. 00E-01
LITERS 2. 14E 06
LITERS 8. 61E 11
7. ZBE-02
1. 47E-10
4.54E 01
9.24E-08
5. 76E-02
1. I7E-10
0. 00E-01
1.48E 06
4.91E 11
11
M%b,'tUO;> 'lE.)M 4 KEN)'~ hG.AN)44.QA 'V'MO 'Mk<N. '<YMA „,'7,~c
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.,5 QQ>73>bOQ f44 R'O'VXbgQ '7NQ Q;8 c'bMV,R BMY~V%N6Z'QQMVL5 VLQXXNXZQb 95(s 5Q5'c~~<~'>3,
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MAMAS
'KCVAAM Ah%.UV
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JANUARY
FLORIDA POWER 4 LIGHT COMPANYST. LUCIS PLANT UNIT NO. 2
SEM1 ANNUAL REPORTI, 1987 THROUGH JUNE 30, 1987
TABLE 3. 4-2
LIQUID EFFLUENTS
NUCLIDESRELEASED UNIT
CONTINUOUS MODEQTR. ¹I QTR. ¹2
BATCH MODEQTR. ¹I QTR. ¹2
I-131I-132I-133I-135NA-24CR-51MN-54FE-55CO-5 7CO-58FE-59CO-60AG-110SN-113SB-122SB-124RB-88SR-89SR-9DY-90ZR-95NB-95NB-97TC-99MRU-103SB-125CS-134CS-136CS-137CS-138
CICICIC'1'I
CICICICICICICICICICICI'I
C'ICICICICICICICICICIC1'I
CI
0. ODE-010. OOE-OI0. OOE-010. OOE-010. OOE-010. OOE-010. OOE-010. OOE-OI0. OOE-010. OOE-010. OOE-Ol0. OOE-010. OOE-010, OOE-010. OOE" 010. OOE-010. OOE-010. OOE-OI0. OOE-010, OOE-Ol0. OOE-010. OOE-010. OOE-OI0. OOE-OI0. OOE-010. OOE-010. OOE-OI0. OOE-010. OOE-OI0. DOE-01
0. OOE-010. OOE-010. OOE-010. OOE-010. OOE-01D. ODE-010, OOE-Ol0. OOE-010. OOE-010. OOE-010. OOE-010. OOE-010. DOE-010. OOE-010. OOE-010. OOE-010. OOE-010. OOE-OI0. OOE-010. OOE-010. OOE-010. OOE-OI0. OOE-010. OOE-010. OOE-010. OOE-Ol0. OOE-010. OOE-010. OOE-010. OOE-01
1.13E-OZ1.14E-03I.IZE-033. 91E-05Z. 5DE-044. I7E-021. 7ZE-034. 71E-035. 64E-055. 45E-OZ7. 68E-042. 98E-021. 57E-033. Z6E-040. OOE-OI1.16E-OZ6.20E-049.10E-055. 70E-055. 70E-058. 31E-03I . Z6E-OZ9. 08E-041. 07E-04Z. 38E-03I . 60E-022. 78E-036. IIE-055. 13E-032. 84E-04
1. I7E-030. OOE-017. OOE-050. OOE-010. OOE-011. 15E-OZ5.96E-045.10E-030. OOE-011.09E-021.99E-041. 66E-OZ8. 99E-041.11E-041.33E-051. 72E-030. OOE-018. 75E-040. OOE-Dl0. OOE-OI2. 91E-034. 96E-032. 54E-040. OOE-OI5. 89E-047. 75E-031. 81E-030. OOE-013. 58E-031. 81E-05
12
MQYC RQYKKR0 .KV'Q !.0 .RZQ
MQK 'MO!!VIX'1V!QQRW .K<@ Uh .MQ
M='6% l. l!Q-MQ QW-'MQ .3N-'MQ,QN-'MQ .QM-'641. ~ !.!r Q-'KM .0M-'Ml.c~.N-RQQ.QRQ-'KM . 1bQ-'MG .!.RQ-'6M .!bQ-MQ, .80 Q-6l!..!.M-'5.4 .!.M-'K~il . llQ -MQ,Q(>Q-'B,V .8LQ-'KQQ . QlQ"MQ .'Q
R Q-'AM .',~
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V,Q--'KhE . l'M-'M1 . lW-'KN .4bQ-'M4.8RQ-W!.. 0M-NX.1CQ-6D .0N-'Q8.5RQ-M4 . 6R-'MG .7RQ-WP> i.sRQ-W5 ~ t.VQ-KM,.YN-"~NQ .QM-'Mk.l'bQ -'WR .'hM-RQ1 .QV)-'8QX . 0
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RQ-'KSR .!.OQ-'K8Q . 8bQ 'NQ.lM-'MZ,RM-'8QG. K
Ql-MX .4R-'KL1..94Q-'N 1.50'4-'ll'8 ~~
LQ-iMQ .Q!Q-'MQ,QN-VLQQ . QlQ-'MQ .QN-'MQ .QlQ-'MQ .QlQ-MQ .QN-W)Q . QlQ-'8QQ .QLQ-WQ.QN-5M .QlQ«'sNQ .QN-'MQ .Q'N-'M'Q . Q1Q-VQQ .QlQ-'8QQ .'QlQ-'MQ,QN -'MQ .QlQ-6QQ .QlQ-'KQQ .QlQ-'A,QQ . Ql'Q-'MQ . Q!.Q-'MQ,Q
lQ-t QQ.QlQ-MQ QN-~NQ .Q!Q-4QQ,QlQ-'6QQ .QN-'MQ .QJQ-'MQ.Q
!.Q-'MQ . Q!.'Q-'MQ . QlQ-'WN,Q
lQ i1QQ QN-'MQ .Q!.Q-MQ .QN-'MQ .QN-'6QQ .QLQ-'KQQ . QN-'M'Q .'Q
N -'MQ.QN«'~NQ,QN-rmQQ .QN-"AQUA . QN-"re) .Q1Q-'M'Q . QlQ-'MQ,QlQ-'iRQ,Q!.Q-'MQ .'0lQ-MQ .Q1Q-MQ.QN-8QQ .Q!Q-'MQ . Q
N-RQQ.QN-'MQ .Ql'Q-'MQ . Q!.Q-'MQ . QlQ-'8,QQ .QN -'MQ .'Q
N- 'AQQ .Q
o tFLORIDA POSER d'r LIGHT COMPANYST. LUCIS PLANT UNIT NO. 2
JANUARYSEMIANNUAL REPORT
I, 1987 THROUGH JUNE 30, 1987
TABLE 3. 4-2 CONTINUED
LIQUID EFFLUENTS
NUCLIDESRELEASED UNIT
CONTINUOUS MODEQTR. ¹I QTR. ¹2
BATCH MODEQTR. ¹I QTR. ¹2
LA-140CS-141CE-144TE-129TE-129M
TOTAL FORPERIOD
AR-41ER-85MXS-131MXE-133XE-133MXE-135
TOTAL FORPERIOD
CICICICICI
CICICICICICI
0. ODE-010. OOE-010. OOE-010. OOE-010. OOE-01
0. OOS-010. OOE-Ol0. OOE-Ol0. OOE-010. OOE-01
1.96E-033. 31S-042. 34E-049. 26E-044. 88E-04
3. 47E-049.49E-052.54E-040. OOE-010. OOS-01
0. OOE-010. OOE-010. OOE-010. OOE-010. OOE-010. OOE-01
0. OOE-010. OOE-010, OOE-010, DOE-010. OOE-010. OOE-Ol
8. 93E-054. 55E-043. 13E-02I.OIE Ol1. 26S-OI8. 71E-02
0. OOE-010. OOE-Ol0. OOE-015. 55E-OZ2. Z6E-041. 91E-03
0. OOE-01 0. OOE-01 1. 04E 01 5. 76E-02
O.OOE-OI O.OOE-OI 2.14E-OI 7.23E-02
13
suez «vvm,R% .'A%9 D),Mg
MQ5 BOW'ARMORR0> .KYQ LW .8%9
BMXQQMZ MQ W~ 6MLZAR
0 Q-"AX0AQ-Mt .6OQ-'Kb4.RLQ-'MQ .QLQ-'MQ .Q
M-MR.lbQ-'KH .V>
bQ-'Kb4 .RLQ-'MR.RL~Q-'688 .'4
LQ-'6QQ .QLQ-'MQ .QLQ-MQ .QLQ-'MQ,QLQ-'SN, Q
LQ-'MQ .QLQ-MQ .QLQ-'MQ .QLQ-MQ .QLQ-'MQ .Q
RQ-MR.N LQ-84L .R LQ-'6QQ .Q LQ-MQ.Q
LQ -'6QQ .QLQ-'KQQ .'Q
LQ-'MQ .QRQ-'KVA .0.WQ-MR.RM-'6M.. L
KQ-'h9 .8bQ-'K0vRQ-'AG L . 6LQ 'KLQ.!.!.Q-MR. L'~Q-KD
T.Q-'WQ .QLQ-'MQ .'Q
LQ-MQ .QLQ-'MQ .QLQ-'MQ .QLQ-MQ .Q
LQ-'MQ .QLQ-'MQ .QLQ-MQ .0LQ-'M'0,'QLQ-MQ .QLQ-4QQ .Q
RQ-AN .4 LQ KbQ .L LQ-'KQO .Q LQ-MQ .Q
Qb! -hKD L-'RQ
KARL-'KZ%04 ilhXUR
ROM'8%
LV-Rh,MG-R'A
5D L-8YGG L-'AY
'MZ!-'NML-'MMSi G,KYMM'MM
FLORIDA POSER & LIGHT COMPANYST. LUClZ PLANT UNIT NO. 1
SEMlANNUAL REPORTJANUARY 1, 198 7 THROUGH JUNE 80, 198 7
TABLE 3. 6-1
GASEOUS EFFLUENTS — SUMMATlON OF ALL RELEASES
NUCLlDES RELEASEDA. FlSSION AND ACTIVATIONGASES
UNlT QUARTER ¹1 QUARTER ¹2
1. TOTAL RELEASE CI 8.89E 08
1. TOTAL IODINE-131 CI 3. 31E-02
2. AVERAGE RELEASE RATS FOR PSRl'OD UCI/SEC 4. 25E-08
C. PARTICUliATES
1. PARTlCULATES T-1/2 > 8 DAYS 1. 74E-05
2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 2. 24E-06
8, GROSS ALPHA RADIOACTIVITY
D. TRITIUM
1. TOTAli RELEASE CI
8. 85E-09
1.98E 00
2. AVERAGE RELEASE RATS FOR PERl OD UCI'/SEC 2. 55E-01
2. AVERAGE RELEASE RATE FOR PERlOD UCI/SEC 4. 35E 02
B. l'ODINSS
5. 08E 02
6.46E 01
6. 58E-04
8. 80E-05
7. 57E-07
9.68E-08
1.99E-07
1.30E 01
1.65E 00
14
'3%MM<Y) 'DkM..X A MWQR, AQ.M()i',.'0% 'YXVM 'MAM, KV0434 .'Y~c
ZYiQ'VM ANN%A'1.KRRXM,L,M VAN'4 EKN30're% NML,L. XYLAOM,D
l-b.RMBA'&AM'RR
MA 'W NM.'VAN&% - RXKMZ~VCHt U3M)RAG
'~0 MXRQ39 kW KN!'AAQQ 'H%U QMA'MVY!BMXhW%RMAG MVXZN'V7QA GV!A ROMPED .b,
M MQ.0
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bQ"'KY~b .8
W-MV .8
RQ MR,V MAMM RAKE
M-'AL.Y..G 3.RL-'M'HEM. Q,K7M . lZQ-W4'R.b MRXLW3 QO'le YLQ5> '44'EAR MAMM'MAMMA
UKT,AM&.'MAlBXM. 8 c RXL-7 KKTAAQQYZKAK
M 'MV>.b MB,sly GM.KAK %M, 'RADAR MV6LM 'KQAKKHA
BR|rtlN>% .6
M 'K'QP..L
<N "548.%
W-MR .8
'00 'M9.t5QYY~')Y(
MAMM AKXCR
JANUARY
FLORIDA POHER Zi LIGHT COMPANYST. LUC1E PLANT UNIT NO.
SEMIANNUAL REPORT1, 198 7 THROUGH JUNE 30, 198 7
TABLE 3. 7-1
GASEOUS EFFLUENTS - GROUND LEVEL RELEASES
NUCLIDESRELEASED UN1 T
NOBLE GASES
CONTINUOUS MODEQTR. ¹1 QTR, ¹2
BATCH MODEQTR. ¹1 QTR. ¹2
AR-41ER-85MER-87
CICICI
XE-135TOTAL FOR
PERIOD
CI
CI
ER-88 CIXE-131M CIXE-133 CI
CI
0. OOE-014.29E Ol2. 41E 017.90E 010. OOE-01Z,34E 032. 75E 013.89E 02
0. OOE-Ol0. OOE-010. OOE-010. OOE-Ol0. OOE-014. 37E 020. OOE-016.02E 01
9. 14E-019. 45E-Ol0. OOE-013.13E-Ol9.53E-Ol4.44E 028.20E 002. 73E 01
0. OOE-010. OOE-010. OOE-Ol0. OOE-010, OOE-011. 01E 011. 70E-011. 03E-02
2,90E 03 4.98E OZ 4.82E OZ 1.02E 01
2, IODINEI-131I-132I-133I-135
TOTAL FORPERIOD
CI 3. 31E-OZ 6. 53E-04CI 1. 03E-Ol 9. 24E-05CI 3.29E-02 1.38E-03CI 4.66E-02 O.OOE-OI
CI 2.16E-01 2.12E-03
3. PARTICULATERB-88SR-89CS-137
TOTAL FORPERIOD
CICICI
CI
1.56E 003. 76E-061. 36E-05
0. OOE-017. 57E-070. OOE-01
1.56E 00 7.57E-07
15
MM %3'7 AR.
RO,RYQ LW .MQMQK V)QKNATANQRW .'iYYQ LS .RT.Q
BMAd A~M.QVL
LQ-'MQ,QLQ-VQQ .QLQ-'WQ .'Q
LQ-MQ .QLQ-'HiQQ . Q
1Q 'KLQ.LLQ-'KQX . LRQ-ViRQ . 2
LQ-'KbL,PLQ-Mh .GLQ-'MQ . QLQ-'8XL .4LQ-ME,BRQ 'Mb.bQQ MY,.SlQ 6M ~ R
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7 Q-MQ .QXQ-N5.XLQ-'MQ .Q
FLORIDA POSER & LIGHT COMPANYST. LUCIE PLANT UNIT NO. 2
SEMIANNUAL REPORTJANUARY 1, 1987 THROUGH JUNE 80, 1987
TABLE 8. 6-2
GASEOUS EFFLUENTS — SUMMATION OF ALL RELEASES
NUCLIDES RELEASEDA. FISSION AND ACTIVATIONGASES
UNIT QUARTER ¹I QUARTER ¹Z
1. TOTAL REliEASE 2.66E 08
1. TOTAL IOD1NE-131 7. 44E-03
2. AVERAGE RELEASE RATE FOR PERIOD UCIJ/'SEC 9. 56E-04
C. PARTICULATES
1. PART1CULATES T-1//2 > 8 DAYS CI 0. OOE-01
Z. AVERAGE RELEASE RATE FOR PERIOD UCI//SEC 0. OOE-Ol
8. GROSS ALPHA RADIOACTIVITY
D. TRITIUM
TOTAL RELEASE
CI
CI
9, 80E-08
2.Z1E 01
2. AVERAGE RELEASE RATE FOR PERIOD UCI/J"SEC Z.84E 00
2. AVERAGE REliEASE RATE FOR PERIOD UCI/SEC 8. 42E 02
B. IODINES
8.17E 08
4. 08E OZ
1.49E-OZ
1.90E-08
8. 05E-05
3.88E-06
1.80E-07
2.88E 01
3. 08E 00
16
't%b,'BK)a XN)LA h >V~ALQ'4 b<XM(W.'1.ON 'IXV'Mb,<M. 'than%)A .'VP~
XRQ'LM hQVMh.DYM3 M,T.,'0~, "6N)4 %W)MM X8Rk, L XRMMiihh
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"4 'iiK5(t6)Q L% M,'YQ,bMQ Z'MQ 'MRKKLMBMXQiQMKM,h9 M,QIZNVEQk QVih M,MK6'R3~, b.
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LQ-'AQ'0 Q Q'8,6~XQQ QM.KM. 'M% AZN, XCKKAM '69M'KVh,
'CYXHXKQhM.Q.bK QRQ.h, MQQQ
5L)VD.'iV7
U) MR.." YCM,~Y~5L h(A~Y7
9 ) 'DS.R 'NiR~L".)9 QW.K>H, 'M~l ~YEbK '<R.VhiYM 'AQb)NV b,
O'0-'M4.R 4KB~XQL) QM.'AM WL~MbR '<%lO,AM RDKVi;Nb.
M7M'.0:H.'7%hN
JANUARY
FLORIDA POHER 4 LIGHT COMPANYST. LUCIE PLANT UNIT NO. 2
SEMIANNUAL REPORT1, 1987 THROUGH JUNE 30, 1987
TABLE 8. 7-Z
GASEOUS EFFLUENTS - GROUND LEVEL RELEASES
NUCLIDESRELEASED UNIT
1. NOBLE GASES
CONTINUOUS MODEQTR. ¹1 QTR. ¹2
BATCH MODEQTR, ¹1 QTR. ¹2
AR-41ER-85ER-85MER-87ER-88XE-131MXE-188XE-188MXE-135
'OTALFORPERIOD
2, IODINEI-131I-182I-188
TOTAL FORPERIOD
8. PARTICULATERB-88SR-89
TOTAL FORPERIOD
CICICICICICICICICI
CI
CICICI
CI
CICI
CI
0, OOE-010. ODE-012. 01E 011.Z6E 001.56E 010. OOE-012.26E 081.04E 012.68E 02
0. OOE-.010. OOE-Ol1.98E 010. OOE-012.00E 010. OOE-012.20E 081.48E 012. 48E 02
1.99E 003, 67E-016. 5ZE-020. OOE-011. 89E-021.84E 007.82E 018. 68E-011.18E 00
1.11E 001.64E DO4. 09E-010. DOE-011. 18E-018.54E 006.42E 028.12E 001. 03E 01
7.44E-08 1.49E-025.44E-04 5.48E-046. 68E-03 1. 89E-02
1. 47E-02 8. 48E-02
8.24E 000. OOE-OI
0. OOE-018. 05E-05
8,24E 00 8. 05E-05
2.58E 08 2.50E 08 7.95E 01 6.67E 02
17
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4,%
FLORIDA POWER 8( LIGHT COMPANYST. LUCIE PLANT
SEMIANNUAL REPORTJANUARY 1, 1987 THROUGH JUN 30, 1987
UNITS 1 AND 2, TABLE
A. Solid Waste Shipped Off-Site for Burial or Disposal
1. TYPE OF WASTE UNITa. Spent resin, M«3
process filters Ci
b. Dry Compressible M«3Waste Ci
6 MONTH PERIOD ERROR%2. 002 E+16. 516 E+2 2 ~ 0 E+1
00
c. IrradiatedComponents
M«3Ci
00
d. Other1.Sol idified Oil M«3
Ci2. 334 E+11. 08 E-4 2.0 E+1
2. Sol i di f i ed STP4 M«3and Tank Sludge Ci
3. Solidi% i ed Tank M«3Sludge Ci
4. Non-compressible M«3Metal (Note 5) Ci
5. 834 E+11 ~ 70 E-2
5. 83 E+04. 72 E-1
1.377 E+11. 43 E-1
2. 0 E+1
2. 0 E+1
2 ~ 0 E+1
STP, Sewage Treatment Pl ant
2 ~ ESTIMATE OF MAJOR NUCLIDECategory Nuclide
a ~ 131 I137 Cs
S8 Co60 Co
134 Cs51 CrS5 Fe95 Nb63 Ni54 Mn95 Zr
COMPOSITION (BY TYPE OF WASTE)
2 ~ 89 E+12. 14 E+11. 56 E+11. 10 E+19. 10 E+03 ~ 30 E+02. 30 E+02. 10 E+02. 00 E+01. 80 E+01. 30 E+0
b. NA
C ~ NA NA
18
d
t
lh '
Table 3.9 Continued:
60 Co3 H
55 Fe137 Cs54 Mn63 Ni58 Co
134 Cs
4.29 E+14. 04 E+11.07 E+11. 80 E+01.00 E+08. 00 E-17. 00 E-17.00 E-1
3 ~ SOLID WASTE DISPOSITIONNumber of Shipments Node of Transportation Destination
142
B. Irradi ated Fuel Shi pments
Sole Use TruckSole Use Truck
Barnwell, SCRichland, WA
Number of Shipments Node of Transportation Destination
0 NA
NA- Not App1 i cab 1 e
19
Table 3ta (Cont.)
KasteClass
TotalVolumeCubic ft
TotalCuriesNote i
Pr incipalRadionuclidesNotes i 8 2
Type ofHasteNote 3
Cateaor yRea Guidei2X
Type ofContainerNote 4
SolidificationAgent
Class A
Class A
Class A
Class A
Class B
Class C
Class C
824
2060
206
486.4
202
i.08e-4
i.70e-2
4.72e-i
i.43e-i
33.9i
560.57
na
na
na
na
Ni63 Sr99,Ce13
Co60, Ni63.Sr90, Csl37Pu24i, THU;
Sum of Nuc-li es withTi 2<5yr
Co60, Ni63,Pu24i, THU,
Sum of Nuc-li es withTi 2<5yr
SolidifiedOil
STP 8 TankSludge
SolidifiedTank Sludge
Non-Com-
pressibleeeete[Note5)
PIIH ionExchangeResin
PNR ion
exchangeresin
PtrR
ProcessFilters
i.d
i.d
i.d
i.a
i.a
i.a
Non-specificationStrong tight package
Non-specificationStrong tight package
NRC Certified LSA> Type A
Non-specificationStong tight package
NRC Certified LSA> Type A
NRC Certified LSA> Type A
NRC CertifiedType B
Cement
Cement
Cement
None
None
None
None
FLORIDA POWER AND LIGHT CONPANYST ~ LUCIE PLANT
SENIANNUAL REPORTJANUARY 1, 1987 THROUGH JUNE 30, 1987
UNITS 1 AND 2 TABLE 3.9 (CONT.)SOLID WASTE SUPPLENENT
Note 1: The total curie quantity and radi onucl ide composi tion ofsolid waste shipped from the St. Lucie Unit 1 8< 2 aredetermined using a combination of qualitative andquantitative techniques. In general, the St. LuciePlant follows the guidelines outlined in the Low LevelWaste Licensing Branch Technical Position (BTP) onRadioactive Waste Classification (5/11/83> for thesedetermi nati ons.
C'he
most frequently usedtechniques for determining thetotal curie quantity in a package are the dose to curiemethods and -the (concentration) x (volume or mass>calculations. Where appropriate, engineering typeactivation analyses may be applied. Since each of theabove methodologies involves to some extent qualitativeparameters, the total curie quantity is considered to bean estimate.
The composition of radionuclides in the waste isdetermined by both on-site analyses for principal gammaemitters and periodic off-site analyses for otherradionuclides. The on-site analyses are performed eitheron a batch basis or on a routine basis using reasonablerepresentative samples as appropriate for the wastetype. Off-site analyses are used to establish scalingfactors or other estimates for radionuclides such as 3H,14C, 99Tc, 129I, TRU, 241Pu, 242Cm, 63Ni, 55Fe, and90Sr.
Note 2: "Principal Radionuclides" refer to those radionuclidescontained in the waste in concentrations greater than.01 times the concentration of the nuclides listed inTable 1 or .01 times the smallest. concentration of thenuclides listed in Table 2 of 10 CFR 61.
Note 3: "Type of Waste" is generally specified as described inNUREG 0782, Draft Environment Impact Statement on 10 CFR61, " Licensing Requirement~ for Land Disposal ofRadioactive Waste".
Note 4: "Type of Container" refers to the transport package.
Note 5: The volume and activity listed for non-compressiblemetal represent the quantity of material that to datecould not be recycled by a contracted vendor andrequired disposal. The initial volume of material sentto the recycle facility was 77.02 cubic meters.
21
Page 1. of 84
At'tachment - A
HIRER PNER 6 LIGHl COMPANY
SI', IIKIEPIANI'RBKSIRY
OPERATBQ PRO(XDURE M)~ 0-2IORE%SION 8
TTILE:
Offsite Dose Calculaticn Manual (ODQl)
REVIN QB APPRDFAL
Reviewed by Facility Review Gmup
Appmved by C. M. We
Revt.sicn 8 Reviewed by F R G
Appmved by
ril 22 1982
19~19+7
S OPS
DATEDOCT PROCEDURE
DOCN C-200SYSCOMP COMPLETEDITM 8
Page 41 of 84
STe LUCIE PLANTCHEMISTRY OPERA'BING PROCEDURE NO. C-200, REVISION 8
OFFSITE DOSE CALCULATION MANUAL (ODCM)
2.7 (continued)
1. Obtain the latest zesults of the nznthly calculaticns of the gmna air dose(Secticn 2.4) md the beta air dose if pezforned (Secticn 2.5). 'Ihese doses can beobtained fzom the in~lant records.
2. Divide these doses by th. number af days the pLant was cpezatioral during themonth.
3. Multiply the quotient by the number of days the p1ant is pmPcted to be
aperatioral durIng the next mcnth. 'Ihe pmduct is the pmPcted dose for the nextnznth. %he value should be ad~ted as receded to acmunt for any changes infai1ed-fuel or other identifiable operating ccnditicns that could significantlyalter the actual releases.
4. If the pmpcted dhses are K.2 mcads gmaa air dose or 0.4 mzads beta air dose,the apprcpriate subsystens of the gaseous zadwaste system shall be used to znducethe zadioactivity levels prior to zelease.
3.0 40 CFR 190 Dose Evaluation
Dtscnsntm - Dose or dose comnLtsent to a mml htdtvldntt fmm all ummtmn fuel cycleswcmm be Hndtad to <25 mtem to tha tohtl body or any orden (except thycotd, nhtch isLind,ted to <75 mzem) over a period of 12 consecutive ncnths. 'Ihe fallowing appzcech shlldbe used to demcnstrate conpliance with these dose limits. This approach is based cn MJREG-
0133, Secticn 3.8.
3.1 Evaluation Bases
Dose evatustins to denrnstzate conpliance with the alive dose limits need only beperfozned if the quarterly doses calculated in Secticns 1.4, 2.4 and 2e6 exzaed twicethe dose Lindts of Tech. Specs. 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2a, 3.1.2.2b, 3.11.2.3a,and 3.11.2.3b ze~ively; i.e., quarterly doses exceeding 3 mzem to the total body(liquid releases), 10 mzem to any cage (liquid releases), 10 mzads gmaa air dose, 20
nnads beta air dose, or 15 mzem to the thymid or any'rgan from zadioiodines and
particulates (atnnspheric releases). Otherwise, no evaluatims are zequized and thezenninder of this sectim can be omitted.
3.2 Doses Fmm Li id Releases
For the evaluate af cbses to zeal individuals fmm liquid releases, the sana
calculaticn nethod as enplayed in Section 1.4 wil1 be used. Heaver, nnze zealisticassunpticns willbe nade ancerning the diluticn and in~tim of fish and shellfish byindividuals who live snd fish in the area. A1so, the results of the RadiologicalEmd.zcnnental Mcnitccing pmgzam wi11 be included in determIning naze zealistic dose tothese real people by pmviding data m actual naasum1 levels af plant relatedzadicnuclides in the envirient.
tAttachment~-. BFLORIDA POWER 6 LIGHT COMPANY
ST- -LUCIE PLANTADMINISTRATIVEPROCEDURE NUMBER 0520025
REVISION 6
Page 1 of 10
1. 0 TITLE
PROCESS CONTROL PROGRAM
2.0 REVIEW AND APPROVAL:
Reviewed by Facility Review Group
Approved by J. H. Barrow (for)December 28, 1982
Plant Manager December 28, 1982
'Revision 6 Reviewed F R G 1/7Approved by 'Q
3. 0 SCOPE:
3. 1 Purpose
The St. Lucie Plant Process Control Program (PCP) implements therequirements of the St. Lucie Plant Technical Specifications forboth units. Specifically, the PCP applies to waste formclassification of all radioactive waste destined for land burial inaccordance with 10 CFR 20. 311, dewatering of bead resins fordisposal, and solidification, encapsulation, or absorption vendorsupplied processes for liquid radioactive waste.
3. 2 Discussion
1. The PCP contains provisions to assure that dewatering of beadresins results in a waste form with characteristics that meetthe requirements of 10 CFR 61 as implemented by 10 CFR 20 and ofthe low level radioactive waste disposal site. The ProcessControl Program includes in addition to this procedure thefollowing related procedures:
A. St. Lucie Plant Health Physics Procedure No. 49 "DewateringRadioactive Bead Resins".
B. CHEM-NUCLEAR SYSTBfS, INC. Test procedure for DewateringConical Bottom Demineralizers and Resin Liners - ProspectNo. 11118.
/R6
C. CHEM-NUCLEAR SYSTEMS, INC. Lab Record Sheet for ConicalBottom Demineralizers and Resin Liners - Prospect No. 11118.
FOB INFORIIATlot). 0 )EELY
This documenf is nof confrolled. Before use,
vttrlfy informefion wifh a confrolled cfocumenf.
f S OPS f
IDATE I
fDOCT PROCEDURE
fDOCN 0520025 f
ISYS . -
I
fCOMP COMPLETED
fIm 6
lST. LUCIE PLANT
ADMINISTRATIVEPROCEDURE NUMBER 0520025, REVISION 6PROCESS CONTROL PROGRAM
Page 2 of 10
3.0 SCOPE: (continued)3. 2 (continued)
2. Vendor supplied processes for solidification, encapsulation, orabsorption of liquid radioactive waste is handled under atopical report which the vendor has submitted to the NuclearRegulatory Commission for approval or under an N. R. C. approvedprocess control program. Controlled copies of appropriatevendor procedures for these processes must be used to assureprovision 'under the topical report are met.
3. All radioactive waste shiped for land burial must meet therequirements of 10 CFR 20. 311 regarding waste formclassification and packaging. This is implemented throughprocedure HP-47, "Classification of Radioactive Waste Materialfor Land Disposal".
3.3 Authority
The authority and responsibility to perform the requirements of thisprocedure come from 10 CFR 20, 10 CFR 61, St. Lucie Plant Unit 1Technical Specifications, St. Lucie Plant Unit 2 TechnicalSpecifications, and from disposal site criteria.
3.4 Definitions
Absorption - The process of absorbing liquid radioactive wastematerials onto an absorbent material.
2. Dewatering - The process of removing "free standing" water froma final disposal package which contains radioactive bead resins.
3. Encapsulation — The process of enclosing radioactive wastematerial within cement-like material, such that the finalproduct is a free-standing monolith.
4. "Free Standing" Water - Liquid which is not retained by thewaste form.
5. Solidification — The process of solidifying liquid radioactivewaste material in cement-like material, such that the finalproduct is a free-standing monolith.
6. Process Control Program (PCP) — The Process Control Programshall contain the provisions, based on full scale testing, toassure that dewatering of radioactive bead resins results in awaste form with the properties that meet the requirements of 10CFR 61 (as implemented by 10 CFR 20) and of the low levelradioactive waste disposal site at the time of disposal.
ST. LUCIE PLANTADMINISTRATIVEPROCEDURE NUMBER 0520025, REVISION 6
PROCESS CONTROL PROGRAM
Page 3 of 10
3.0 SCOPE: (continued)
3. 4 (continued)
7. Visual Inspection - " The direct observation of the bead resinsduring the entire period of resin transfer as they are packagedin the final disposal container.
8. Waste Form Classification — Classification of radioactive wasteAs per 10CFR 61. 55 and 10CFR 61. 56. /R6
4.0 PRECAUTIONS:
4. 1 Process Control Procedures used for the dewatering of radioactivebead resins that establish the conditions that must be met shall bebased on full scale testing. This is to provide reasonableassurance that the dewatering of the resin and disposal containerwill result in volumes of free standing water, at the time ofdisposal, within the limits of 10CFR, Part 61 as implemented by10CFR20 and of the low level radioactive waste disposal site.
4.2 Vendor supplied solidification, encapsulation, and absorptionprocesses shall be NRC approved or under a topical report which hasbeen submitted to NRC for approval. Procedures which are to be usedmust be controlled per the vendor's gA program.
4.3 All changes to the St. Lucie Plant Process Control Program must bereviewed and approved by the Facility Review Group before theybecome effective.
/R6
4.4 All changes to the St. Lucie Plant Process Control Program must besubmitted to the NRC in the Semiannual Radioactive Effluent ReleaseReport for the period in which the change(s) was made. Thissubmittal must contain the following:
1. Sufficiently detailed information to totally support therationale for the change without benefit of additional orsupplemental information.
2. A determination that the change did not reduce the overallconformance of the dewatered bead resins to existing criteriafor solid wastes.
3. Documentation of the fact that the change has been reviewed andfound acceptable by the Facility Review Group.
ST. LUCIE PLANTADMINISTRATIVE PROCEDURE 'NUMBER 0520025, REVISION 6
PROCESS CONTROL PROGRAM
Page 4 of 10
5 0 RESPONSIBILITIES:
5.1 It is the responsibility of the Plant Manager to assure that allnecessary procedures, equipment and support are provided to properlyimplement the PCP.
5.2 It is the responsibility of the Health Physics Supervisor or hisdesignee to assure that the radioactive bead resin will be dewateredin accordance with the PCP.
5.3 It is the responsibility of the Health Physics Supervisor or hisdesignee to assure that radioactive waste material is classified inaccordance with the PCP.
5.4 FPL Dewatering equipment shall be operated by or under the directionof FPL personnel. /R6
6 ' REFERENCES:
6.1 Bead Dewatering Procedure for CNSI 14-195 or smaller liners—FO-OP-023.
6.2 Lab Record Sheet for Conical Bottom Demineralizers and Resin Liners,Prospect No. 11118.
6.3 Test Procedure for Dewatering Conical Bottom Demineralizers andResin Liners, Prospect No. 11118.
6.4 Health Physics Procedure, HP-47, "Classification of RadioactiveWaste Material for Land Disposal".
6.5 Health Physics Procedure, HP-49, "Dewatering Radioactive BeadResins" /R6
7 ' RECORDS AND NOTIFICATIONS:
7.1 Records shall be as per St. Lucie Plant Health Physics ProcedureNo. 49, "Dewatering Radioactive Bead Resins". /R6
7.2 Notifications
1. If it is suspected that the free standing water requirements maynot be met for any container of radioactive 'bead resin shippedto a disposal site, notify the Plant Manager and the HealthPhysics Supervisor.
2. If the process control procedures have not been followed or iffree standing water may be present in the final shippingcontainer of bead resin in amounts greater than allowed byregulations, notify the Health Physics Supervisor or hisdesignee.
eST. LUCIE,PLANT,
ADMINISTRATIVEPROCEDURE NUMBER 0520025, REVISION 6PROCESS CONTROL PROGRAM
I
Page 5 of 10
8 ' INSTRUCTIONS:
8.1 Dewatered radioactive bead resins:
1. Disposal of dewatered radioactive bead resins is limited to thecontainers for which full scale dewatering tests have beenconducted; and, -in the case of high integrity containers, forwhich certification by the State of South Carolina for use atthe Barnwell, South Carolina land disposal facility has beenestablished.
2. Dewater the container as per St. Lucie Health Physics ProcedureNo. 49, "Dewatering of Radioactive Bead Resins".
A. Only containers compatible with FPL owned resintransfer/dewatering equipment may be used.
B. Figure 1 through 5 depict the FPL owned resintransfer/dewatering equipment.
3. With dewatering not meeting disposal site, shipping, andtransportation requirements, suspend shipment of theinadequately dewatered bead resin and correct the processcontrol program, the applicable procedures(s), and/or thedewatering system as necessary to prevent recurrence.
4. With dewatering not performed in accordance with the PCP:(1) if the dewatered bead resin has not already been shipped fordisposal, verify each container to ensure that it meets burialground, shipping and transportation requirements and/or (2) takeappropriate administrative action to prevent recurrence.
5. Close the container as per the manufacturer's instructions.
8.2 Solidification, encapsulation, or absorption of radioactive wastematerials shall be performed in accordance with FPL approved vendorprocedures. These procedures shall provide for the following:
l. Independent verification of steps within the process that arecrucial to the process; and
2. Testing of the final wast'e form to determine acceptability(where ALARA concerns permit testing) for shallow land burial.
8.3 All radioactive waste material packaged and destined for landdisposal shall conform to the requirements of 10 CFR 20.311 asimplemented by procedure HP-47. If waste form classificationexceeds Class C or packaging does not meet the requirements of thewaste form class, the Health Physics Supervisor shall be notifiedand shipment shall not be made.
/R6
ST. LUCIE PLANTADMINISTRATIVEPROCEDURE NUMBER 0520025, REVISION 6
PROCESS CONTROL PROGRAM
Page 6 of 10
PROCESS CONTROL PROGRAM
FIGURE 1
TOP VIP'F P;t.'680PRt+AayQSvlA~'lAQ
Pl% VauS
r lb'
Q<M'R6
ST. LUCIE PLANT
ADMINISTRATIVEPROCEDURE NUMBER 0520025, REVISXON 6
PROCESS CONTROL PROGRAM
page 7 of l0
PXGURE 2
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/R6
ST. LUCIE PLANTADMINISTRATIVEPROCEDURE NUMBER'0520025, REVISION 6
PROCESS CONTROL PROGRAM
Page 8 of 10
- FIGURE 3
«IIIH Pll(
~~444%4C'l ~
~M4I. Bevel(. «~~~or
II
rlL4 isoETIO@
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/R6
ST. LUCIE PLANTADMINISTRATIVE PROCEDURE iVUMBER 0520025, REVISION 6
PROCESS CONTROL PROGRAM
Page 9 of 10
FIGURE 4
a;aa V==-~ Ot= -It.:~aWO-'"CTRXCAt CONNECT ONS
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/R6
ST. LUCIE PLANTADMINISTRATIVEPROCEDURE NUMBER 0520025, REVISION 6
PROCESS CONTROL PROGRAM
Page 10 of 10
FIGURE 5
i 'I iNQNITQ8
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