ML17221A653
| ML17221A653 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 12/31/1987 |
| From: | Conway W FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| L-88-106, NUDOCS 8803040124 | |
| Download: ML17221A653 (34) | |
Text
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. AC'CELEMTZD DISTR'PON DEMONSTRA. >~3N SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8803040124 DOC.DATE: 87/12/31 NOTARIZED: NO DOCKET g FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power 6 Light Co. 05000335 50-389 St. Lucie Plant, Unit 2, Florida Power 6 Light Co. 05000389 AUTH. NAME AUTHOR AFFILIATION CONWAY,W.F. Florida Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
"Combined Semiannual Radioactive Effluent Release Rept for Jul-Dec 1987." W/880229 ltr.
DISTRIBUTION CODE: IE48D COPIES RECEIVED:LTR ( ENCL l SIZQ TITLE: 50.36a(a)(2) Semiannual Effluent Release Reports NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 0 PD2-2 PD 5 5 TOURIGNY,E 1 1.
A INTERNAL: ACRS 1 1 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 ARM TECH ADV 1 1 NRR/DEST/PSB8D1 1 1 NE~MglP/RPB1 OA 4 4 NRR/PMAS/ILRB12 1 1 REG FIL+ 01 1 1 RGN2 FILE 02 1 1 75RSS/EPRPB 1 1 EXTERNAL: BNL TICHLER, J03 1 1 LPDR 1 1 NRC PDR 1 1 A
TOTAL NUMBER OF COPIES REQUIRED: LTTR 23 ENCL 22 88033 0
P. O. Bo 00, JUNO BEACH, FL 33408.0420
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j:E8RUARY, 2 9 1988 L-88-106 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
Re: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Semi-Annual Radioactive Effluent Release Re ort Attached is the Radioactive Effluent Release Report for the period of July 1, 1987 through December 31, 1987 for St. Lucie Units 1 and 2, as required by Technical Specification 6.9.1.7.
Should there be any questions on this information, please contact us Very truly yours, W . Conway Senior Vice President Nuclear WFC/GRM/dh Attachment cc: Dr. J. Nelson Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant, GRM23. RERR
/gp l an FPL Group company
0 -'f s FLORIDA PONER h LIGHT COHFANY ST. LUCIB PLANT UNITS NO. 1 4 2 LICENSE NO.S DPR-87 dr NHF-1B COMBINED SERI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD JULY 1, 1987 THROUGH DECEMKER 31, 19B7 8803040i24 871231 05000335 PDR R ...",.
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TABLE OF CONTENTS DESCRIPTION EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION............ 1 SITE VISITOR DOSE PROM EPPLUENTS... e ~ o 7 OPFSITE DOSE CALCULATION MANUAL REVISIONS............ 8 SOLID WASTE AND IRRADIATIED FUEL SHIPKKHTS............... 8
%%CESS CONTROL X%KGIULH REVISIONS............................... 8 LIQUID EPPLUENT-SUMMATXON OP ALL RELEASES 8r NUCLIDE SUMMATXON BY QUARTER WITH EPPI DENT DOSE UN IT 0 1 o e ~ ~ ~ ~ ~ o ~ ~ o r o ~ ~ ~ ~ o o ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ o o ~ ~ ~ o r 9 UNIT 0 2 ooooooo 18 GASEOUS EFPLUENT-SUHMATION OF ALL REL1QLSES dc NUCLXDE SUMMATION BY QUARTER WITH EFPLUENT DOSE UN IT 0 1 r o o o o ~ o o o o ~ ~ ~ e o o o r 17 UNIT 0 2 o ~ ~ ~ o o ~ ~ o e o o ~ ~ o e o o o ~ r 18 SOLID WASTE SHXPHLNT SUMHATION ............................. 23
EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL 'INFORMATION
- 1. Regulatory Limits 1.1 For Liquid Waste Effluents
- h. The concentration of radioactive material released from the site shall be limited to the concentrations specified in 18 CFR Part 28 Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-i micro-Curies/al total activity.
B. The dose or dose commitment to a MPH'F THE PUBLIC from radioactive material in liquid effluents released, frea each reactor unit, to UNRESTRICTED AREAS shall be limited to-During any calendar quarter to <= ).5 mrems to the Total Body and to <= 5 mrems to any organ, and During any calendar year to <= S areas to the Total Body and to <= 18 mrems to any organ.
1.2 For Gaseous Waste Effluents-
- h. The dose rate in UNRESTRICTED AKEhS due to radioactive materials released in gaseous effluents froa the site. shall be limited to-For Noble Gases: <= 588 mrems/yr to the total body and
<= S888 areas/yr to the shin, and For Iodine-)31, Iodine-133, Tritium, and all radionuclides in particulate form with half-lives greater than 8 days:
<= 1588 mrems/yr to any organ.
4B. The air dose due to noble gases released in gaseous effluents from each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following-During any calendar quarter, to <= 5 mrads for gamma radiation,and
<= 18 mrads for beta radiation and, during any calendar year to
<= 18 mrads for gamma radiation and <= 28 mrads for beta radiation.
4C. The dose to a KEIR OF THE PUBLIC from Iodine-131, Iodine-133, Tritium, and all radionuc)ides in particulate form, with half-lives > 8 Days in gaseous effluents released, from each reactor unit to areas at and beyond the site boundary, shall be limited to the following-During any calendar quarter to <= 7.5 mrem to any organ, and During any calendar year to <= 15 mrea to any organ.
The calculated doses contained in a semi-annual report shall not apply to any STS LCO. The reported values are based on actual release conditions instead of historical conditions that the STS LCO dose calcuations are based on. The STS LCO dose limits are therefore included in Item 1 of the report, for information only.
I EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued)
- 2. Maximum Permissible Concentrations Water- As per 18 except CFR 28 Part 28, Appendix B, Table for entrained or dissolved II, Column 2, noble gases as described in 1.1.A of this report.
Air- Release concentrations are limited to dose rate limits described in 1.2.h. of this report.
- 3. Average Energy of fission and activation gases in gaseous effluents is not applicable.
- 4. Measurements and approximations of total radioactivity Where alpha, tritium, and named nuclides are shown as sero Curies
'eleased, this should be interpreted as "no acitvity was detected on the samples using the Plant Technical Specification analyses techniques to achieve required Lower Limit of Detection (LLD) sensitivity for radioactive effluents".
A summary of liquid effluent accounting methods is described in Table 3.1.
A summary of gaseous effluent accounting methods is described in Table 3.2.
4.1 Estimate of Errors LIQUID Error Topic Avg.% Max. X Avg.% Max. I Release Point Mixing 5 NA NA Sampling 5 2 5 Sample Preparation 5 1 5 Sample Analysis 18 18 Release Volume 5 15 Total X 9 The predictability of error for radioactive releases can only be applied to nuclides that are predominant in sample spectrums.
Nuclides that are near background relative to the predominant nuclides in a given sample could easily have errors greater than the above listed maximums.
EFFLUENT AND WASTE 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 Liquid Sampling Type of Method of Source Frequency Analysis Analysis Each Batch Principal Gamma Eaitters p.h.a.
Monitor Monthly Tritium L.S.
Tank Cownpo site Gross Alpha G.F.P.
1 Releases Quarterly Sr-89, Sr-98, Composite 5, Fe-55 C. S.
Continuous Daily Principal Gamma Emitters Releases Grab 8r I-191 for p.h.a.
Samples 4/M Composite Analysis Dissolved h, Entrained Gases One Batch/ Month p.h.a.
Tritium Composite Monthly L.S.
Alpha Composite Monthly G.F.P.
Sr-89, Sr-98, h, Fe-55 Composite Quarterly C.S.
1-Boric Acid Evaporator Condensate is normally recovered to the Primary Water Storage Tank for recycling into the reactor coolant system and does not contribute to Liquid Waste Effluent Totals.
p.h.a.-Gamma Spectrum Pulse Height Analysis using Lithium Germanium Detectors. All peaks are identified and quantified.
L.S.-Liquid Scintillation Counting C.S.-Chemical Separation G.F.P.&as Flmr Proportional Counting 4/M-Four per Month
EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued)
- 4. Measurements and Approximations of Total Radioactivity (Continued) 4.1 (Continued)
B. (Continued)
TABLE 3.2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS Gaseous Saiipling Type of Method of Source Frequency Analysis Analysis Waste Gas Decay Tank Each Batch Principal Gamma Emitters p.h.a.
Releases Containment Principal Gama Emltters p.h.a.
Purge Each Purge Tritium L.S.
Releases Principal Gaaaa Eaitters p.h.a.
Tritium L. S.
Plant Monthly Particulate Vent Coaposite Gross Alpha G.F.P.
Quarterly Particulate Composite Sr-Ba a Sr-98 C.S.
p.h.a.-Ganuaa Spectrum Pulse Height Analysis using Lithium Germanium Detectors. All peaks are identified and quantified.
L.S.-Liquid Scintilgation Counting C.S. Chemical Sepazation G.F.P.&as Fleer Proportional Counting 4!M-Four per Month
FLORIDA POSER & LIGHT COMPANY ST. LUCIE PLANT, UNIT NO. 1 SEMIANNUAL REPORT JULY I, 1987 THROUGH DECEMBER 3I, 1987 EFFLUENT AND HASTE DISPOSAL SUPPLEMENTAL INFORMA TION (CONTINUED)
- 5. BATCH RELEASES AND UNPLANNED RELEASES LIQUIDS FOR: ST. LUCIE PLANT UN1 T NO. 1 A. NUMBER OF BATCH RELEASES:
B. TOTAL T1ME PERIOD OF BATCH RELEASES: 22 486. MINUTES C. MAXIMUM TIME PERIOD FOR A BATCH RELEASE: 920. M2NUTES D. AVERAGE Tl'ME PERIOD FOR A BATCH RELEASE: 623. MINUTES E. M1NIMUM T1MZ PERIOD FOR A BATCH RELEASE: 403. Ml'NUTES F. AVERAGE STREAM FLOP DURING REPORTING PERIOD INTO A FLOWING STREAM: 896444. G. P. M.
- 6. GASEOUS FOR: ST. LUCIS PLANT UNIT NO. 1 A. NUMBER OF BATCH RELEASES: 7. 0 B. TOTAL T1ME PER1OD OF BATCH RELEASES: 22 80. M2 NUTES C. MAX2MUM T2ME PZR1OD FOR A BATCH RELEASZ: 600. MlNUTES D. AVERAGE Tl'ME PERIOD FOR A BATCH RELEASE: 31 1 . MlNUTES E. Ml'N2MUM TIME PZR2OD FOR, A BATCH RELEASE: 2 78. Ml'NUTES UNPLANNED RELEASES LIQUIDS FOR: ST. LUCIZ PLANT UNIT NO. I A. NUMBER OF RELEASES: 0.
B. TOTAL ACTI'VITY RELEASED: 0. CUR2ES GASEOUS FOR: ST. LUCIS PLANT UNl T NO.
. 1 A. NUMBER OF RELEASES: 0.
B. TOTAL ACTIV1TY RELEASED: 0. CURIES SEE A TTACHMENTS (1F APPLICABLE) FOR:
A. A DESCRIPTION OF THZ EVENT AND EQUIPMENT INVOLVED.
B. CA USE(S) FOR THE UNPLANNED RELEASE.
C. ACTIONS TAKEN TO PREVENT A RECURRENCE.
D. CONSEQUENCES OF THE UNPLANNED RELEASE.
FLOR2DA POWER & L1GHT COMPANY ST. LUCIE PLANT. UN2T NO. 2 SEM2ANNUAL REPORT JUL Y 2, I 98 7 THROUGH DECEMBER 31, 1 98 7 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED)
- 5. BATCH RELEASES AND UNPLANNED RELEASES LIQU2DS FOR: ST. LUCIS PLANT UNIT NO. Z A. NUMBER OF BATCH RZLZASZS: 34.
B. TOTAL TIME PZR1'OD OF BATCH RELEASES: 22 486. MlNUTES C. MAXIMUM TIME PERIOD FOR A BATCH RELEASE: 920. Ml'NUTES D. AVERAGE TIME PERl'OD FOR A BATCH RELEASE: 623. MlNUTES E. MIN1'MUM T1ME PERIOD FOR A BATCH RELEASE: 403. M2NUTES F. AVERAGE STREAM FLOW DURING REPORTING PERIOD INTO A FLOWING STREAM: 8964 75. G.P. M.
- 6. GASEOUS FOR: ST. LUCIS PLANT UN2T NO. Z A. NUMBER OF BATCH RELEASES: 34. 0 B. TOTAL T2ME PERIOD OF BATCH RELEASES: 23698. MINUTES C. MAXIMUM T1MZ PERlOD FOR A BATCH RELEASE: 2647. MINUTES D. AVERAGE T2ME PERIOD FOR A BATCH RELEASE: 697. MlNUTES E. M1NlMUM TIME PZR2OD FOR A BATCH RELEASE: 30. Ml'NUTES UNPLANNED RELEASES LIQUIDS FOR: ST. LUCIS PLANT UNIT NO. 2 A. NUMBER OF RELEASES: 0.
B. TOTAL ACTIVITY RELEASED: 0. CURIES GASEOUS FOR: ST. LUCIS PLANT UN2T NO. 2 A. NUMBER OF RELEASES: 0.
B. TOTAL ACT1 VITY RELEASED: 0. CURIES SEE ATTACHMENTS (IF APPL1CABLE) FOR:
A. A DESCRIPTION OF THE EVENT AND EQUIPMENT INVOLVED.
B. CAUSE(S) FOR THE UNPLANNED RELEASE.
C. ACTIONS TAKEN TO PREVENT A RECURRENCE.
D. CONSEQUENCES OF THE UNPLANNED RELEASE.
FLORIDA POSER 8r LIGHT COMPANY ST. LUCIE PLANTS UNITS 1 Sr 2 SEMIANNUAL HEPCAT JULY 1, 1987 THROUGH DECEMBER 31, 1987 EFFLUENT AND HASTE DISPOSAL SUPPUKMENTAL INFORMATION (Continued)
- 7. Assessment of x'adiation dose fma radioactive effluents to MEME'F THE PUBLIC due to their activities inside the SITE BOUNDARY assume the visitor onsite for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, at an average distance of 8.3 hilometers in the eorst dispersion direction, and received exposure from each of the two reactox units on the St. Lucie Site.
VISITOR DOSE RESULTS FOR CAIZNDAR YEAR 1987 WEHE-GASEOUS PARTICULATES NOBLE GAS %EXPOSURE Br, IODINE KE'OSURE DOSE in mrad ORGAN DOSE (mrem)
Gamma Air Dose 1.67 E-82 Bone 7.55 E-86 Beta Air Dose 2.94 E-82 Liver 1.84 E-84 Thyroid 2.93 E-83 Kidney 4.48 E-85 9.48 E-85 GI-LLI 9.52 E-85 Total Body 1.26 E-84
FLORIDA PONER 8c LIGHT COMPANY ST. LUCIE PLANT UNITS NO. 1 Zc 2 SEMIANNUAL REPORT JULY 1 1987 THROUGH DECEMBER 51 1987 EFFLUENT AND NASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued)
- 8. Offsite Dose Calculation Manual Revisions (ODCM) s The ODCM was not revised during the reporting period Solid Maste and Irradiated Fuel Shipmentsa No irradiated fuel shipments were made from the site. Common Solid waste from St. Lucia Units 1 and 2 were shipped jointly.
A summation of these shipments is given in Table 3.9 of this report r
- 18. Process Control Program (PCP) Revisionsa The PCP was not revised during the reporting interval.
FLOR2DA POSER d'c LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 SEM1 ANNUAI REPORT JULY 1, 1 98 7 THROUGH DECEMBER 31, 1 98 7 TABLE 3. 3-1 LI'QUID EFFLUENTS SUMMAT1'ON OF ALL RELEASES J
NUCL2DES RELEASED UN2 T QUARTER ¹3 QUARTER ¹4 A. F1SSION AND ACTIVATION PRODUCTS
- 1. TOTAL RELEASE 1. 44Z 02 5.64E 01
- 2. A VERAGE DILUTED CONCENTRA T2 ON
,.DURING PERIOD UCI/ML Z. 86E-07 1.45E-07 C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CI 7. 34E-01 4.Z5E-01 Z. AVERAGE D2LUTED CONCENTRATION DURING PER2 OD UCI'/ML 1.45E-09 1.09E-09 D. GROSS ALPHA RAD2OACT1'VITY
- 1. TOTAL RELEASE CI 0. OOE-01 1. 1 OZ-05 E. VOLUME OF HASTE RELEASED (PRIOR TO D1LUTION) 3. 44E 07 3. 72E 07 F. VOLUME OF DILUTION HATER PERIOD'ITERS USED DURING REPORTING L2TERS 5. 05E 11 3.89E 11
FLORIDA POA'ER ck, LIGHT COMPANY ST. LUCI'E PLANT UNIT NO. Z SEMIANNUAL REPORT JULY 1, 1 98 7 THROUGH DECEMBER 31, 1 98 7 TABLE 3. 3-Z LIQU2D EFFLUENTS SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT QUARTER ¹3 QUARTER ¹4 A. FISSION AND ACTIVATIONPRODUCTS
- 1. TOTAL RELEASE (NOT 2NCLUD2NG TRI Tl'UM, GASES, ALPHA) 3. 97E-02 Z. 16E-01 Z. A VERAGE Dl LUTED CONCENTRA TION DURING PER2 OD UCI/PIL 7. 86E-11 5. 57E-10 B. TRITIUM
- 1. TOTAL RZLEASE 1. 44Z 02. 5. 64E 01
- 2. A VERAGE D2LUTED CONCENTRA Tl ON
, DURING PERIOD UCI/ML 2.86E-07 1.45E-07 C. Dl'SSOLVED AND ENTRAINED GASES
- 2. AVERAGE DILUTED CONCENTRA TION DURING PERIOD UCIr'ML 1.45E-09 1.09E-09 D. GROSS ALPHA RADIOACT1 VITY
- 1. TOTAL RELEASE 0. OOZ-01 1.10E-05 E. VOLUME OF FASTS RELEASED (PR2OR TO DILUTION) LITERS 2. 54Z 06 1. 80E 06 F. VOLUME OF DILUTION h'ATER USED DURING REPORTING PER2 OD LITERS 5. 05E 11 3.89E 11 10
FLOR1DA POSER dc LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 SEM1ANNUAL REPORT JULY 1, 1987 THROUGH DECEMBER 31, 1987 TABLE 3. 4-1 LIQU1D EFFLUENTS NUCL1 DES CONT1'NUOUS MODE BATCH MODE RELEASED UN1 T QTR. ¹3 QTR. ¹4 QTR. ¹3 QTR. ¹4 I-131 CI 0. OOE-01 1. 05E-03 1.30E-02 9. 71E-03 I-132 CI 0. OOE-01 0. OOE-01 0. OOE-01 8. 1 OE-04 I-1 33 CI 0. OOE-01 0. OOE-01 1.18E-03 9. 20E-04 I-1 35 CI 0. OOE-01 0. OOE-01. 0. OOE-01 6. 25E-05 NA-24 CI'I 0. OOE-01 0. OOE-01 0. OOE-01 4. 12E-04 CR-51 0. OOE-01 0. OOE-01 0. OOE-01 1. 78E-02 MN-54 G'I 0. OOE-01 0. OOE-01 5. 18E-04 1. 36E-03 FE-55 CI 0. OOE-01 0. OOE-01 8. 05E-04 2. 97E-02 CO-57 CI 0. OOE-Ol 0. OOE-01 0. OOE-01 1. 04E-04 CO-58 CI 0. OOE-01 0. OOE-01 2. 98E-03 7. 58E-02 FE-59 CI 0. OOE-01 0. OOE-01 0. OOE-01 3. 13E-03 CO-60 0. OOE-01 0. OOE-01 8. 41E-03 7. 54E-03 AG-11 0 C1'1'1
- 0. OOE-01 0. OOE-01 4. 42E-04 1.93E-03 SN-11 3 0. OOE-01 0. OOE-01 4. 19E-05 8. 05E-04 SB-122 CI 0. OOE-01 0. OOE-01 3.20E-05 5. 86E-04 SB-1Z4 CI 0. OOE-01 0. OOE-01 Z. 5 7E-04 1. 91E-02 NP-239 CI 0. OOE-01 0. OOE-01 0. OOE-01 9. 94E-04 SR-89 C1'I 0. OOE-01 0. OOE-01 1. 37E-04 1.98E-04 SR-90 0. OOE-01 0. OOE-01 0. OOE-01 3.4ZE-05 Y-90 G'I 0. OOE-01 0. OOE-01 0. OOE-01 3.42E-05 ZR-95 CI 0. OOE-01 0. OOE-01 2. 28E-04 1.55E-03 NB-95 C1 0. OOE-01 0. OOE-01 8. 13E-04 3. 03E-03 NB-97 CI 0. OOE-01 0. OOE-01 6. 14E-04 2. 70E-03 TC-99M CI 0. OOE-01 0. OOE-01 8. 80E-05 4. 02E-05 RU-I 03 CI 0. OOE-Ol 0. OOE-01 0. OOE-01 2.80E-04 SB-125 C1 0. OOE-01 0. OOE-01 4. 13E-03 2. 09E-02 CS-134 CI 0. OOE-01 8. 97E-04 2. 39E-03 4. 10E-03 CS-136 C1 0. OOE-01 0. OOE-01 9. 77E-05 0. OOE-01 CS-137 G'1 0. OOE-01 2. 07E-03 3. 1 OE-03 8.26E-03 CS-138 C1 0. OOE-01 0. OOE-01 5. 82E-05 3. 82E-04 11
FLORIDA POWER Ec LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 SEM1 ANNUAL REPORT JUL Y 1, 1 98 7 THROUGH DECEMBER 31, 1 98 7 TABLE 3. 4-1 CONTINUED LIQUID EFFLUENTS NUCLIDES CONTINUOUS MODE BATCH MODE RELEASED UNIT QTR. ¹3 QTR. ¹4 QTR. ¹3 QTR. ¹4 BA-140 CI 0. OOE-01 0. OOE-01 7.64E-05 0. OOE-01 LA-1 40 CI 0. OOE-01 0. OOE-01 7.26E-04 I . 31E-03 CE-1 41 CI 0. OOE-01 0. OOE-01 O.OOE-01 4. 35E-05 PR-1 44 CI 0. OOE-01 0. OOE-01, O.OOE-01 2. 26E-03 TE-129 CI 0. OOE-01 0. OOE-01 0. OOE-01 2. 07E-03 TE-I Z9M CI 0. OOE-01 0. OOE-01 0. OOE-01 7.23E-05 TE-132 CI 0. OOE-01 0. OOE-01 0. OOE-01 5.25E-04 NI-56 CI 0. OOE-01 0 OOE-01
~ 0. OOE-01 1.14E-04 TOTAL FOR PERIOD 0. OOE-01 4. 01E-03 3. 97E-02 2. 16E-01 AR-41 CI 0. OOE-01 0. OOE-01 0. OOE-01 5. OOE-04 ER-85M CI 0. OOE-01 0. OOE-01 0. OOE-01 2. 05E-05 XE-131M CI 0. OOE-01 0. OOE-01 3. 14E-03 I . 39E-03 XE-133 CI 0."OOE-01 0. OOE-01 7. 14E-01 3. 73E-01 XE-133M CI 0. OOE-01 0. OOE-01 8.28E-03 3.83E-03 XE-135 CI 0. OOE-01 0. OOE-01 7.98E-03 4. 61E-OZ TOTAL FOR PERIOD CI 0. OOE-01 0. OOE-01 7. 34E-01 4. 25E-01 12
FLORIDA POWER dc LIGHT COMPANY ST. LUCIE PLANT UNIT NO. Z SEMIANNUAL REPORT JULY 1, 1987 THROUGH DECEMBER 31, 1987 TABLE 3. 4-Z LIQUID EFFLUENTS NUCLIDES CONTINUOUS MODE BATCH MODE RELEASED UNIT QTR. ¹3 QTR. ¹4 QTR. ¹3 QTR. ¹4 I-131 CI 0. OOE-01 0. OOE-01 1. 30E-02 9. 71E-03 I-132 CI 0. OOE-01 0. OOE-01 0. OOE-01 6. 1 OE-04 I-133 CI 0. OOE-01 0. OOE-01 1.18E-03 9. 20E-04 I-135 CI 0. OOE-01 0. OOE O.OOE-01 6. 25E-05 NA -24 CI 0. OOE-01 0. OOE-01 O.OOE-OI 4. 12E-04 CR-51 CI 0. OOE-01 0. OOE-01 O.OOE-01 1. 78E-02 MN-54 CI 0. OOE-01 0. OOE-01 5.18E-04 1.36E-03 FE-55 CI 0. OOE-01 0. OOE-01 6. 05E-04 Z. 97E-OZ CO-5 7 G'I 0. OOE-01 0. OOE-01 0. OOE-01 1.04E-04 CO-58 CI 0. OOE-01 0. OOE-01 2.98E-03 7.58E-02 FE-59 CI 0. OOE-01 0. OOE-01 0. OOE-01 3.13E-03 CO-60 CI 0. OOE-01 0. OOE-01 8. 41E-03 7.54E-03 AG-j10 CI 0. OOE-01 0. OOE-01 4. 42E-04 1.93E-03 SN-113 CI 0. OOE-01 0. OOE-01 4. 19E-05 8. 05E-04 SB-122 CI 0. OOE-01 0. OOE-01 3. 20E-05 5.86E-04 SB-124 G'I 0. OOE-01 0. OOE-01 2. 57E-04 1. 91E-02 NP-239 CI 0. OOE-01 0. OOE-01 0. OOE-01 9. 94E-04
-SR-89 CI 0. OOE-01 0. OOE-01 1. 37E-04 1.98E-04 SR-90 CI 0. OOE-01 0. OOE-01 0. OOE-01 3.4ZE-05 Y-90 CI 0. OOE-01 0. OOE-01 0. OOE-01 3.42E-05 ZR-95 CI 0. OOE-01 0. OOE-01 2. 28E-04 1.55E-03 NB-95 CI 0. OOE-01 0. OOE-01 6.13E-04 3.03E-03 NB-97 G'I 0. OOE-01 0. OOE-01 6.14E-04 2. 70E-03 TC-99M CI 0. OOE-Ol 0. OOE-01 8.80E-05 4.02E-05 RU-1 03 CI 0. OOE-01 0. OOE-01 O.OOE-01 Z.60E-04 SB-125 CI 0. OOE-01 0. OOE-01 4.13E-03 Z. 09E-OZ CS-134 CI 0. OOE-01 0. OOE-01 2.39E-03 4. 10E-03 CS-136 CI 0. OOE-01 0. OOE-01 9. 77E-05 0. OOE-01 CS-137 CI 0. OOE-01 0. OOE-01 3.10E-03 6.26E-03 CS-138 CI 0. OOE-01 0. OOE-01 5.82E-05 3.62E-04 13
t FLORIDA POSER 4 LIGHT COMPANY ST. LUCIE PLANT UNIT NO. Z t
SEMIANNUAL REPORT O'ULY I, 1 98 7 THROUGH DECEMBER 31, 1 987 TABLE 3. 4-Z CONTINUED LIQUID EFFLUENTS NUCLIDES CONTINUOUS MODE BATCH MODE RELEASED UNIT QTR. ¹3 QTR. ¹4 QTR. ¹3 QTR. ¹4 BA-1 40 CI 0. OOE-01 0. OOE-01 7. 64E-05 0. OOE-01 LA-140 CI 0. OOE-01 0. OOE-01 7. 26E-04 1. 31E-03 CE-1 41 CI'I 0. OOE-01 0. OOE-01 0. OOE-01 4. 35E-05 PR-I 44 0. OOE-01 0. OOE-01. 0. OOE-01 Z. Z6E-03 TE-129 CI 0. OOE-01 0. OOE-01 0. OOE-01 2. 07E-03 TE-129M CI 0. OOE-01 0. OOE-01 0. OOE-01 7.23E-05 TE-132 CI 0. OOE-01 0. OOE-01 0. OOE-01 5.25E-04 NI-56 CI 0. OOE-01 0. OOE-01 0. OOE-01 1.14E-04 TOTAL FOR PERIOD CI 0. OOE-01 0. OOE-01 3. 97E-02 2. 16E-01 AR-41 CI 0. OOE-01 0. OOE-01 0. OOE-01 5. OOE-04 ER-85M CI 0. OOE-01 0. OOE-01 0. OOE-01 2. 05E-05 XE-1 31M CI 0. OOE-01 0. OOE-01 3. 14E-03 1. 39E-03 XE-133 CI 0. OOE-01 0. OOE-01 7. 14E-01 3. 73E-01 XE-133M CI 0. OOE-01 0. OOE-01 8. 28E-03 . 3. 83E-03 XE-135 CI 0. OOE-01 0. OOE-01 7.98E-03 4. 61E-OZ TOTAL FOR PERIOD CI 0. OOE-01 0. OOE-01 7. 34E-01 4. 25E-01 14
FLORIDA POWER &. LIGHT COMPANY ST. LUCIE UNIT NO. 1 SEMI-ANNUAL REPORT JULY 1, 1987 THROUGH DECEMBER 31, 1987 TABLE 3.5-1 LIQUID EFFLUENTS DOSE SUMMATION Age Group: ADULT Location: Any ADULT Exposure Interval: January 1, 1987 through December 31, 1987 FISH & SHELLFISH Calendar Year ORGAN Dose (mrem)
Bone 2.77 E-02 Liver 1.17 E-01 Thyroid 3.02 E-02 Kidney 1.89 E-03 Lung 1.33 E-01 GI-LLI 2.64 E-01 Total Body 3.50 E-02 15
FLORIDA POHER & LIGHT COMPANY ST. LUCIE UNIT NO. 2 SEMI-ANNUAL REPORT JULY 1, 1987 THROUGH DECEMBER 31, 1987 TABLE 3.5-2 LIQUID EFFLUENTS- DOSE SUMMATION Age Group: ADULT Location: Any ADULT Exposure Interval: January 1, 1987 through December 31, 1987 FISH 8c SHELLFISH Calendar Year ORGAN Dose -(mrem)
Bone 2.73 E-02 Liver 1.16 E-01 Thyroid 1.98 E-02 Kidney 1.59 E-03 Lung 1.33 E-01 GI-LLI 2.64 E-01 Total Body 3.45 E-02
FLORIDA POWER d'c LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 SEMl ANNUAL REPORT JULY 1, 1987 THROUGH DECEMBER 31, 1987 TABLE 3. 6-1 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT QUARTER ¹3 QUARTER ¹4 A. FISSION AND ACTIVATION GASES 1 . TOTAL RELEASE CI 1. 81E 03 4. 98E 02
- 2. A VERAGE RELEASE RATE FOR PERIOD UCI/SEC 2. 28E OZ 6.26E 01 B. IODINES
- 1. TOTAL IODINE-131 CI 4. 14E-04 5. 35E-03
- 2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 0. 00E-01 1.09E-07
- 1. TOTAL RELEASE 5.12E 01 1. 03E 01
- 2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 6. 44E 00 1.Z9E 00 17
FLORIDA POSER ck LIGHT COMPANY ST. LUCIE PLANT. UNI T NO. 2 SEMIANNUAL REPORT JULY 1, 1 98 7 THROUGH DECEMBER 31, 1 98 7 TABLE 3. 6-2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT QUARTER 0'3 QUARTER 0'4 A. FISSION AND ACTIVATION GASES
- 1. TOTAL RELEASE CI 2. 24E 03 5.34E 02 Z. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 2.81E 02 6. 72E 01 B. IODINES I. TOTAL IODINE-131 CI 2.25E-02 1.02E-02
- 2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 2. 83Z-03 1.28E-03 C. PARTICULATES
- 2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 2. 36E 00 4. 66E-01 18
FLORIDA POSER ck LIGHT COMPANY ST. LUCIS PLANT. UNIT NO. 1 SEMIANNUAL REPORT O'ULY 1, 1 98 7 THROUGH DECEMBER 31, 1 98 7 TABLE 3. 7-1 GASEOUS EFFLUENTS GROUND LEVEL RELEASES NUCLIDES CONT1'NUOUS MODE BATCH MODE RELEASED UNIT QTR. ¹3 QTR. ¹4 QTR. ¹3 QTR. ¹4 I. NOBLE GASES AR-41 Cl 0. OOE-01 0. OOE 0. OOE-01 3. 44E-01 ER-85 CI 0. OOE-01 0. OOE-01 0. OOE-01 7. 06E-01 ER-85M 1.11E 01 0. OOE-01 0. OOE-01 2.09E-01 Cl'R-87
- 0. OOE-Ol 0. OOE-01 0. OOE-01 1.30E-02 Cl Cl'R-88 7.25E 00 0. OOE-01 0. OOE-01 1.36E-01 XE-131M 0. OOE-01 0. OOE-01 0. OOE-01 5. 37E-01 33 1.58E 03 3.63E 02 8. 54E-01 4.93E 01 Cl'E-1 2.60Z 01 0. OOE-01 1.34E-02 7. 95E-01 Cl'Z-1 33M Cl Cl'E-135 1.86E 02 7.60E 01 2.40E-03 6.93E 00 TOTAL FOR PZR1'OD Cl 1. 81E 03 4. 39E 02 8. 69E-01 5. 90E 01
- 2. IODINE I-131 Cl 4. 1 4E-04 5. 35E-03 1-133 Cl 9. 62E-04 1 .1 OE-02 TOTAL FOR PERIOD Cl'.38E-03 1.64E-02
FLOR1DA POSER 4 LIGHT COMPANY ST. LUCIE PLAN1'NIT NO. 2 SEMIANNUAL REPORT JULY 1, 1 98 7 THROUGH DECEMBER 31, 1 98 7 TABLE 3. 7-2 GASEOUS EFFLUENTS GROUND LEVEL RELEASES NUCL1'DES CONTINUOUS MODE BATCH MODE RELEASED UNIT QTR. ¹3 QTR. ¹4 QTR. ¹3 QTR. ¹4
- 1. NOBLE GASES AR-42 C1 OOE-01 0. OOE-01 6. OOE-01 2. 77E-02 ER-85 0. OOE-01 0. OOE-01 2. 87E-01 1.06E-01 C1'R-85M
- 0. OOE-01 0. OOE-01 0. OOE-01 ER-88 CI 4. 49E 01 2.14E 00 Z. 76E-03 1. 30E-01 XE-131M CI 0. OOE-02 0. OOE-01 2. 83E-02 5. 83E-01 XE-133 CI 2.84E 03 Z.51E 02 8.83E 01 2.26E 02 XE-133M XE-135 C1'.
G'1 C1 1.37E 2.19E 01 OZ
- 0. OOE-01 3.91E 01 1.88E 00 3.90E 00 4.18E 00 1.67E 02 TOTAL FOR PERIOD 2.14E 03 2.96E 02 9.53E 01 2.39E 02
- 2. IODINE I-131 G'I 2.25E-02 1.02E-02 I-132 CI O.OOE-01 3.13E-04 I-133 CI 2.89E-02 9.40E-03 TOTAL FOR PERIOD C1 5.14E-02 2.99E-02
- 3. PARTICULATE CO-58 G'I 0. OOE-01 6. 09E-05 SR-89 C1 5. 72E-06 0. OOE-01 TOTAL FOR PERIOD C1'. 72E-06 6. 09E-05 20
FLORIDA POWER 8c LIGHT COMPANY ST. LUCIK PLANT UNIT 0 1 TABLE 3.8-1 GASEOUS EFFLUENTS DOSK SUMMATION QUKQlER 0 N.A.
Age Group- INFANT Exposure Interval- January 1, 1987 through December 31, 1987 NOTK- The below dose results were calculated using actual meterological data during the specified time interval with Met data reduced as per Reg. Guide 1.111, 'March GI-LLI 1976'ATHWAY LIVER THYROID KIDNEY LUNG T. BODY RLX%5R mreÃl arem mrem mrem Ground Plane (A) 8.88 E-Sl 8.88 KM1 8.88 K-81 8.88 K-81 8.88 E-81 8.88 K-81 1 81 K-84 Grass-Cow-Hilh(B) 1.95 EM3 2.83 E-83 7.42 KMl 7.97 E~ 4.95 K-84 5.86 E-S4 1.84 E-83 Inhalation (A) 2.36 KM5 3.98 E-84 9.18 KM3 1.78 K-84 3.68 KW4 3.78 E-84 3.82 E-84 TOTAL . 1.98 E-83 3.23 K-83 7.51 EMl 9.67 E-84 8 63 E-84 9.56 K-84 2.32 EM3 (A)-Sector - WEST Range- 1. 78 miles (B)-Sector - WEST Range- 4.25 miles (Default Animal)
CALENDAR YEAR NOBLE GASES (mrad)
Gajima Air Dose 6.48 K-82 Beta Air Dose 1.87 E-81 Sector - WEST Range- 1.78 miles
FLORIDA POWER 8c LIGHT COMPANY ST. LUCIE PLANT UNIT 4 2 TABLE 3.8-2 GASEOUS EPPLUENTS DOSE SUMMATION QUhEKfK 4 N.A.
Age Group- INFANT Exposure Interval- Januaxy 1, 1987 through December 31, 1987 NOTE- The below dose results were calculated using actual meterological data during the specified time interval with Met data reduced as per Reg. Guide 1.111, March 1976 LIVER THYROID KIDNEY LUNG GX-LLI T. BODY PATHWAY mrem mrem mrem mrem mrem mzem Ground Plane (A) 8.88 K-81 8.88 E-81 8.88 KM1 8.88 EM1 8.88 E-Sl 8.88 K-81 9. 57 E-85 Grass-Cow-Milk(B) 2.71 E-83 3.67 E-83 1.8$ K SS 1.88 E-83 4.41 E~ 5.71 E-84 2.32 E-83 Inhalat,ion (A) 3.28 EW5 $ .B9 K-84 1.24 E-82 1.54 E-84 3.38 E-84 3.31 E-84 3.49 RW4 TOTAL 2 74 EM3 4.84 EM3 1.85 E 88 1.1B KM3 ?.71 E-84 9.82 KM4 2.76 E-83 (A) -Sector - WEST Range- 1.78 miles (B)-Sector - WEST Range- 4.25 miles (Default Animal)
CAIZHMR YEAR NOBLK . GASES (mrad)
Gamma hir Dose 7.54 EM2 Beta hir Dose 1.48 EM1 Sector - WEST Range- 1.78 miles
RIDA POWl& 6 ZZGRZ COMPANY ST. WCIE PIANT S1MEANNUAL REPORT JULY 1 g 1987 KKKUGH DECEMBIK 3 1 g 1987 UNZXS 1 AND 2, TABLE 3.9 A. Solid Waste Shipped Off-Site for Burial or Disposal
- 1. TYPE OF WASTE 6 MOWQi PERIOD ERRORS
- a. Spent resin, MA*3 2.257 E+1 process filters Ci 3.893 E+2 2.0 E+1
- b. Dry compressible MA*3 1.961 E+2 waste (NOXK 5) Ci 1.075 E+1 2.0 E+1
- c. Irradiated MA*3
~nents Ci
- d. Other Mb*3 1.306 E+1
- 1. Non-compressible Ci 5.400 E-2 2.0 E+1 metal (DAW)
(NOTE 6)
- 2. 'OF MM'OR NUCLIDE (ZHPOSITION (BY TYPE OF WASTE)
ESTXIMATl.
Nuclides ao Cs-137 5.93 E+1 Cs-134 1.69 E+1 Ni-63 1.04 E+1 Co-60 7.48 E+0 Co-58 2.36 E+0 Mn-54 1.28 E+0 Fe-55 9.60 E-1 C-14 8.60 E-1
- b. Cs-137 2.52 E+1 Go-60 2.48 E+1 Go-58 1.76 E+1 Fe-55 1.01 E+1 Cs-134 8.91 E+0 H-3 3.61 E+0 Ni-63 2.76 E+0 Nb-95 1.92 E+0 Mn-54 1.36 E+0 Zr-95 1.32 E+0 Cr-51 9.50 E-1 Ce-144 2.60 E-1 C-14 1.70 E-1 23
- d. Co-60 9.70 E+1 Mn-54 2.82 E+0 I-129 2.00 E-1
- 3. SOIZD NM)TR DISPOSITION Number of Shipments Mode of Transportation Destination 40 Sole Use Truck Barnwell, SC B. Irradiated Fuel Shipments Nutnber of Shipments Mode of Transportation Destination n/a n/a = Not Applicable 24
PGXUDA HRER & IZGHZ CCMPANY ST. IIJCIE PIANOS SEMIANNUAL REPORT JULY 1, 1987 'IHRCUGH DECEMBER 31, 1987 UNZIS 1 AND 2, TABIZ 3.9 (CGNZ'D)
Total Total Principal Type of Category Type of Solidification Volume Curies Radionuclides Waste Reg. Guide Container Agent Cubic ft. (Nate 1) (Notes 1 & 2) (Note 3) 1.21 (Note 4) 6736.0 2.15 1. b. Non-specification Nane Oavpactable Strong tight Trash package (Note 5) 194 1 8.60 Cs-137, NiW3, EWR 1. b. NRC Certified ISA Nane Sr-90, I-129 Ocmpactable Type A Pu-241 Trash 461.4 5.4 E-2 N/A 1. d. Non-Specification Nane Non- Strong tight Campactable package (Nate 6) 595 102.97 Cs-137, Ni-63, RR Ion- 1. a. NRC Certified ISA S~O, I-129, E>xhange Type A Pu-241, IHJ 203.7 286.36 Cs-137, NiW3, PHR Ian- 1. a. NRC Certified ISA Nane S~O, I-129, Exdmnge Type A Co-60, ~9, C-14, Sum of nuclides with T 1/2 < 5 yr.
25
4 f
ST. IIJCIE PZt&Z S1MEANNUAL RER)RT JULY 1, 1987 IHRQUGH DECEMBER 31, 1987 UNITS 1 AND 2 TABLE 3.9 (CON'T)
SOLID WASTE SUPPLEMENT Note 1: Jhe total curie quantity and radionuclide composition of solid waste shipped fram the St. Iucie Plant, Units 1 & 2 are deternuned using a combination of qualitative and quantitative techniques. In general, the St. tucie Plant follows the guidelines outlined in the Tow Level Waste Licensing Branch Technical Posit,ion (8IP) on Radioactive Waste Classification (5/11/83) for these determinations.
%he most frequently used techniques for determining the total curie quantity in a package are the dose to curie methods and the (concentration) x (volume or mass) calculations. Where appropriate, engineering type activation analyses may be applied. Since each of the above methodologies involves to same extent qualitative parameters, the total curie quantity is considered to be an estimate.
The composition of radionuclides in the waste is determined by both on-site analyses for principal gamne emith~ and periodic off-site analyses for other radionuclides. 'Ihe on site analyses are performed either on a batch basis or on a routine basis using reasonably representative samples as appropriate for the waste type. Of flite analyses are used to establish scaling factors or other estimates for radionuclides such as 3H, 14C, 99Tc, 129I, TRU, 241Pu, 242Cm, 63Ni, 55Fe, and 90Sr.
Note 2 "Principal Radionuclides" refer to those radionuclides contained in the waste in concentrations greater than .01 times the concentration of the nuclides listed in Table 1 or .01 times the smallest concentration of the nuclides listed in Table 2 of 10 CFR 61.
Note 3: "Type of Waste" is generally specified as described in NUMB 0782, Draft Environment Impact Statement on 10 CFR 61, "Licensing Requirements for Iand Disposal of Radioactive Waste".
Note 4: "Type of Container" refers to the transport package.
Nate 5: %he volume and activity listed for Dry Compressible Waste represent the quantity of material that to date has been sent to the Barnwell, South Camlina burial facility. These totals include material that was shipped directly from the St. Zucie Plant (194. 1 cubic feet, 8. 6 Curies, NRC ~fied ISA ) Type A package) and material that was shipped by a contracted vendor fram their "SupeL~zapaction" facility (6736 cubic feet, 2.15 Curies) . During the reporting period, 14 shipments of Dry Compressible Waste (15088 cubic feet, 3.38 Curies) were'ade fram the St. tucie Plant to the volume reduction facility.
This material was shipped via "Sole Use Truck" in nonspecification strong tight packages.
26
ST. WCIE PIAFZ SEMIANNUAL REPORP JULY 1 g 1987 THROUGH DECEM' 1 ~ 1987 UNITS 1 AND 2 TABIZ 3.9 (CON'T)
SOLID NMHK SUPPUHEFZ
%he volume and activity listed for non-ccmpressible metal represent the cpantity of material that during the reporting period could not be recycled by the contracted vendor and recpixed disposal. None of this material was shipped to the vendor during the reporting period.
27