ML17216A740

Combined Semiannual Radioactive Effluent Release Rept for Jan - June 1986. W/860827 Ltr

ML17216A740
Person / Time
Site:	Saint Lucie
Issue date:	06/30/1986
From:	WOODY C O FLORIDA POWER & LIGHT CO.
To:	GRACE J N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
L-86-349, NUDOCS 8610270369
Download: ML17216A740 (32)

Text

Region 2i Office of Director If , RE"-.UL*TORY INPORN*TION DISTRIBUTION SYSTEN (BIDS>('CCESSION NBR: 8610270369 DOC.DATE: 86/06/30 NOTARIZED:

NO FAC IL: 50-335 St.Luc i e P lant'nit 1>Florida Power Cr Light Co.,('0-389 St.Lucie Planti Unit 2i Florida Power 8c Light Co.~,L AUTH.NAME AUTHOR AFFILIATION 4.Florida Power 5 Light Co.WOODY>C.O.Florida Power 5 Light Co.RECIP.NAME RECIPIENT AFFILIATION GRACE~J.N.DOCKET¹05000335 05000389

SUBJECT:

"Combined Semiannual Radioactive Effluent Release Rept for Jan-June 1986." W/860827 ltr.DISTRIBUTION CODE: IE25D COPIES RECEIVED: LTR g ENCL g SI ZE: O TITLE: Periodic Environ Monitoring Rept (50 DKT)-Annual/Semiannual/Ef fluent/NOTES: RECIPIENT ID CODE/NAME PWR-B PDS LA PWR-B PEICSB INTERNAL: AEOD IE FILE 01 NR PWR-A ADTS NRR7DS RA RM/DDA I/MIB COPIES LTTR ENCL 0 3 3 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PWR-B PDS PD 04 AEOD/PTB NRR BWR ADTS NRR PWR-B ADTS RGN2/DRSS/EPRPB COP IES LTTR ENCL 5 5 1 1 1 1 1 EXTERNAL: LPDR 03 NRC PDR 02 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL 19

>i FLORIDA POWER&'LIGHT COMPANY ST.LUCIE PLANT UNITS NO.1&2 LICENSE NO.S DPR-67&NPF-16 COMBINED SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD JANUARY 1, 1986 THROUGH JUNE 30, 1986 8610270369 860630 PDR ADOCH, 05000335 R PDR DESCRIPTION TABLE OF CONTENTS PAGE EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION......

1 OFFSITE DOSE CALCULATION MANUAL REVISIONS.

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS.

PROCESS CONTROL PROGRAM REVISIONS.......................-.

7 TECHNICAL SPECIFICATION REQUIRED EXPLANATION TO U.S.NRC FOR REQUIRED MONITOR INOPEEUQ3LE FOR A PERIOD GREATER THAN 38 DAYS (L.C.O.3.3.3.18).............

7 LIQUID EFFLUENT-SUMMATION OF ALL RELEASES 8c NUCLIDE SUMMATION BY QUARTER UNIT 1 UNIT 2 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES 8c NUCLIDE SUMMATION BY QUARTER UNIT 1 UNIT 2 9 12 15 17 SOLID WASTE-SHIPMENT SUMMATION 19 OFFSITE DOSE CALCULATION MANUAL PAGE REVSIONS..ATTACHMENT-A EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION 1.REGULATORY LIMITS FOR LIQUID WASTE EFFLUENTS A.B.THE CONCENTRATION OF RADOIACTIVE 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 NOBLZ GASES.FOR DISSOLVED OR ENTRAINED NOBLE GASES, THE CONCENTRATION SHALL BE LIMITED TO 2E-4 MICRO CURIES/ML TOTAL ACTIVITY.THE DOSE OR DOSE COMMITMENT TO A MEMBER OF THE PUBLIC FROM RADIOACTIVE MATERIALS IN LIQUID EFFLUENTS RELEASED, FROM EACH REACTOR UNIT, TO UNRESTRICTED ARl9LS SHALL BE LIMITED TO-DURING ANY CALENDAR QUARTER TO<=1.5 HERES TO THE TOTAL BODY AND TO<=5 ME%MS TO ANY ORGAN, AND DURING ANY CALENDAR YEAR TO<=3 l66ZS TO THE TOTAL BODY AND TO<=18 MREMS TO ANY ORGAN.1.2 FOR GASEOUS WASTE EFFLUENTS-A.B.wC.THE DOSE RATE IN UNRESTRICED AKEAS DUE TO RADIOACTIVE MATERIALS RELEASED IN GASEOUS EFFLUENTS FROM THE SITE SHALL BE LIMITED TO: FOR NOBLE GASES=<=588 MEKMS/YR TO THE TOTAL BODY AND<=3888&KMS/YR TO THE SKIN, AND FOR IODINE-131, IODINE-133, TRITIUM, AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN 8 DAYS-1588&KMS/YR TO ANY ORGAN.THE AIR DOSE DUE TO NOBLZ GASES RELEASED IN GASEOUS EFFLUENTS FROM, EACH REACTOR UNIT, TO AKEAS AT AND BEYOND THE SITE BOUNDARY SHALL BE LIMITED TO THE FOLLOWING=

DURING ANY CALENDAR QUARTER, TO<=5 MRAD FOR GAMMA RADIATION AND<=18 MRAD FOR BETA RADIATION AND, DURING ANY CALENDAR YEAR TO 18 MRAD FOR GAMMA RADIATION AND<=28 MRAD FOR BETA RADIATION.

THE DOSE TO A MEMBER 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 REACTOR UNIT TO AREAS AT AND BEYOD THE SITE BOUNDARY, SHALL BE LIMITED TO THE FOLLOWING:

DURING ANY CALENDAR QUARTER TO<=7.5 MREM TO ANY ORGAN, AND'URING ANY CALENDAR YEAR TO<=15 MREM 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 CALCULATIONS ARE BASED ON.THE STS LCO DOSE LIMITS ARE THEREFORE INCLUDED IN ITEM 1 OF THE REPORT, FOR INFORMATION ONLY.

EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED) 2.MAXIMUM PERMISSIBLE CONCENTRATIONS WATER: AS PER 18 CFR PART 28, APPENDIX B, TABLE II, COLUMN 2, EXCEPT FOR ENTRAINED OR DISSOLVED NOBLE GASES AS DESCRIBED IN 1.1.A OF THIS REPORT.AIR-RELEASE CONCENTRATIONS ARE LIMITED TO DOSE RATE LIMITS DESCRIBED IN 1.2.A.OF THXS REPORT.3.AVERAGE ENERGY OF FISSION AND ACTIVATION GASES IN GASEOUS EFFLUENTS XS NOT APPLICABLE.

4.MEASURfBLENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY I A

SUMMARY

OF LIQUID EFFLUENT ACCOUNTING METHODS IS DESCRIBED XN TABLE 3.1.A

SUMMARY

OF GASEOUS EFFLUENT ACCOUNTING METHODS IS DESCRIBED IN TABLE 3.2.4.1 ESTIMATE OF ERRORS A.SAMPLING ERROR THE ERROR ASSOCIATED WITH VOLUME MEASUREMENT DEVICES, FLOW MEASURING DEVICES, ETC.BASED ON CALIBRATION DATA AMa DESIGN TOLERANCES HAS BEEN CONSERVATIVELY ESTIMATED COLLECTXVELY TO BE LESS THAN PLUS OR MINUS 18 PERCENT.B.ANALYTICAL ERROR FOR NUCLIDES TYPE LIQUID GASEOUS AVERAGE+OR-9X+OR-18K MAXIMUM+OR-38K+OR-35K EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATXON (CONTINUED) 4.MEASVEKMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY (CONTIN:)4.1 (CONTINUED)

B.(CONTINUED)

TABLE 3.1 RADIOACTIVE LXQUID EFFLUENT SAMPLING AND ANALYSIS LIQUXD SOURCE SAMPLING FREQUENCY TYPE OF ANALYSXS METHOD OF ANALYSIS EACH BATCH PRINCIPAL GAMMA EMITTERS P.H.A.MONITOR TANK 1 RELEASES CONTINUOUS RELEASES MONTHLY COMPOSITE QUARTERLY COMPOSITE DAILY GRAB SAMPLES TRITIUM GROSS ALPHA SR-89, SR-90 FE-55 PRINCIPAL GAMMA EMITTERS&I-131 4/M COMPOSITE DXSSOLVED&ENTRAINED GASES ONE BATCH/MONTH TRITIUM COMPOS.MONTHLY ALPHA COMPOSITE MONTHLY SR-89, SR-90,&FE-55 COMPOSITE QUARTERLY L.S.G.F.P.C.S.P.H.A.L.S.G.F.P.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 EFFLENT TOTALS.P.H.A.-GAMMA SPECTRUM PULSE HEIGHT ANALYSIS USING LITHIUM GERl9LNXUM DETECTORS.

ALL PEAKS ARE IDENTIFIED AND QUANTIFIED.

L.S.-LIQUID SCINTILLATION COUNTING, C.S.-CHEMICAL SEPARATION G.F.P.-GAS FLOW PROPORTIONAL COUNTING 4/M-FOUR PER MONTH EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED) 4.MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY (CONTIN.)4.1 (CONTINUED)

B.(CONTINUED)

TABLE 3.2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS GASEOUS SOURCE SAMPLING FREQUENCY TYPE OF ANALYSIS METHOD OF ANALYSIS WASTE GAS DECAY TANK RELEASES EACH BATCH PRINCIPAL GAMMA EMITTERS P.H.A.CONTAINMENT PURGE RELEASES EACH PURGE PRINCIPAL GAMMA EMITTERS P.H.A.TRITIUM L.S~PRINCIPAL GAMMA EMITTERS P.H.A." TRITIUM L.S.PLANT VENT MONTHLY COMPOSITE QUARTERLY COMPOSITE PART XCULATE GROSS ALPHA PARTICULATE SR-89 SR-90 G.F.P.C.S.P.H.A.-GAMMA SPECTRUM PULSE HEIGHT ANALYSIS USING LITHIUM GEIQ9LNIUM DETECTORS.

ALL PEAKS ARE IDENTIFXED AND QUANTIFIED.

L.S.-LIQUID SCXNTILLATION COUNTING C.S.-CHEMICAL SEPARATION G.F.P.-GAS FLOW PROPORTIONAL COUNTING 4/M-FOUR PER MONTH FLORIDA PORK&LIGHT.COMPANY ST.LUCIE PLANT UNIT NO.1 SEMIANNUAL REPORT JANUARY 1, 1986 THROUGH JUNE 30, 1986 EFFLUENT AND WASTE DISPOSAL-SUPPLZMENTAL INFORMATION (CONTINUED) 5.BATCH RELEASES AND UNPLANNED RELEASES F LIQUXDS FOR-ST.LUCIE PLANT UNIT NO.1 A.NUMBER OF BATCH RELEASES-B.TOTAL TIME PERIOD OF BATCH RELEASES-C.MAXIMUM TIME PERIOD FOR A BATCH RELEASE-D.AVERAGE TIME PERIOD FOR A BATCH RELEASE-E.MINIMUM TIME PERIOD FOR A BATCH RELEASE-F.AVERAGE STREAM FLOW DURING REPORTING PERIOD INTO A FLOWING STREAM-39.5 21455.MINUTES 855.MINUTES 543.MINUTES 330.MINUTES 891590.G.P.M.GASEOUS FOR-ST.LUCIE PLANT UNIT NO.1~A.NUMBER OF BATCH RELEASES-B.TOTAL TIME PERIOD OF BATCH RELEASES-C.MAXIMUM TIME PERIOD FOR A BATCH RELEASE: D.AVERAGE TIME PERIOD FOR A BATCH RELEASE-E.MINIMUM TIME PERIOD FOR A BATCH RELEASE: 6, UNPLANNED RELEASES LIQUIDS FOR-ST.LUCIE PLANT UNIT NO.1 A.NUMBER OF RELEASES=B.TOTAL ACTXVITY RELEASED-GASEOUS FOR-ST.LUCIE PLANT UNIT NO.1 A.NUMBER OF RELEASES-B.TOTAL ACTIVITY RELEASED: SEE ATTACHMENTS (IF APPLICABLE)

FOR: 18.0 6148.MINUTES 997.MINUTES 342.MINUTES 124.MINUTES 0.0.CURIES 0.0.CURIES A.A DESCRIPTION OF THE EVENT AND EQUIPMENT XNVOLVED.B.CAUSE(S)FOR THE UNPLANNED RELEASE.C.ACTIONS TAKEN TO PREVENT A RECURRENCE.

D.CONSEQUENCES OF THE UNPLANNED RELZASE.

FLORIDA POWER&LIGHT COMPANY ST.LUCIE PLANT UNIT NO.2 SEMIANNUAL REPORT JANUARY 1, 1986 THROUGH JUNE 38, 1986 EFFLUENT AND WASTE DISPOSAL-SUPPLEMENTAL INFORMATION (CONTINUED) 5.BATCH RELEASES AND UNPLANNED RELEASES LIQUIDS FOR=ST.LUCIE PLANT UNIT NO.2 A.NUMBER OF BATCH RELEASES-B.TOTAL TIME PERIOD OF BATCH RELZASES-C.MAXIMUM TIME PERIOD FOR A BATCH RELEASE-D.AVERAGE TIME PERIOD FOR A BATCH RELEASE-E.MINIMUM TIME PERIOD FOR A BATCH RELEASE-F.AVERAGE STREAM FLOW DURING REPORTING PERIOD INTO A FLOWING STREAM-39.5 21455.MINUTES 855.MINUTES 543.MINUTES 338.MINUTES 891598.G.P.M.GASEOUS FOR-ST.LUCIE PLANT UNIT NO.2 A.NUMBER OF BATCH RELEASES-B.TOTAL TIME PERIOD OF BATCH RELEASES-C.MAXIMUM TIME PERIOD FOR A BATCH RELEASE-D.AVERAGE TIME PERIOD FOR A BATCH RELEASE: E.MINIMUM TIME PERIOD FOR A BATCH RELEASE: Co, UNPLANNED RELEASES LIQUIDS FOR-ST.LUCIE PLANT UNIT NO.2 A.NUMBER OF RELEASES-B.TOTAL ACTIVITY RELEASED-GASEOUS FOR: ST.LUCIE PLANT UNIT NO.2 A.NUMBER OF RELZASES-B.TOTAL ACTIVITY RELEASED-SEE ATTACHMENTS (IF APPLICABLE)

FOR=48.8 9463.MINUTES 1845.MINUTES 237.MINUTES 45.MINUTES 8.8.CURIES 8.8.CURIES 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 RELZASE."

8.FLORIDA POWER Sc LIGHT COMPANY ST.LUCIE PLANT UNITS NO.1 85 2 SEMIANNUAL REPORT JANUARY 1, 1986 THROUGH JUNE 30, 1986 EFFLUENT AND WASTE DISPOSAL-SUPPLEMENTAL INFORMATION (CONTIN.)ASSESSMENT OF RADIATION DOSE FROM RADIOACTIVE EFFLUENTS TO THE GENERAL PUBLIC IS REPORTED ON THE JANUARY REPORT.OFFSITE DOSE CALCULATION MANUAL (ODCM)REVISIONS:

THREE PAGES WERE REVISED.PAGES 45 AND 46 PROVIDE NEW FORMAT"AND CLARIFY THAT DILUTION WATER FOR LIQUID RELEASES SHOULD BE THE TOTAL VOLUME OF WATER RELEASED DURING THE REPORTING PERIOD, INCLUDING WATER CONTAINING NO LIQUID RADWASTE.THIS CHANGE WAS MADE AS PER A U.S.NRC LETTER TO MR.J.W.WILLIAMS, GROUP VICE PRESIDENT OF NUCLEAR ENGINEERING, FPL FROM MR.RICHARD A.HARTFIELD OF DIVISION OF BUDGET AND ANALYSIS, OFFICE OF RESOURCE MANAGEMENT.

THE LETTER WAS RECEIVED BY FPL LICENSING ON AUGUST 12, 1985, AND IT POINTED OUT WHAT VOLUME THE NRC WANTED IN THE REPORT.PAGE 81, THE NOTE-1 ON SAMPLE LOCATION H15, PROVIDES FOR A SUPPLEMENTAL SAMPLE LOCATION FOR THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.NONE OF THE ABOVE CHANGES AFFECT ODCM DOSE METHODOLOGY.

THE REVISED ODCM PAGES ARE INCLUDED AS ATTACHMENT-A TO THIS REPORT.SOLID WASTE AND IRRADIATED FUEL SHIPMENTS:

NO IRRADIATED FUEL SHIPMENTS WERE MADE FROM THE SITE.COMMON SOLID WASTE FROM ST.LUCIE UNITS 1 AND 2 WERE SHIPPED JOINTLY.A SUM-MATION OF THESE SHIPMENTS IS GIVEN IN TABLE 3.9 OF THIS REPORTS PROCESS CONTROL PROGRAM REVISIONS:'O REVISIONS WERE MADE DURING THE REPORTING PERIODS TECHNICAL SPECIFICATION REQUIRED EXPLANATION FOR MONITOR INOPERABLE FOR GREATER THAN 30 DAYS: WASTE GAS DECAY TANKS EXPLOSIVE GAS MONITORING SYSTEM OXYGEN MONITOR AS REQUIRED BY TABLE 3.3-13 FOR UNIT¹1 WHERE ONE CHANNEL IS REQUIRED OPERABLE.PURSUANT TO ST.LUCIE UNIT 1 TECHNICAL SPECIFICATION 3.3.3.18, THIS SPECIAL REPORT IS GENERATED TO NOTIFY THE NRC OF BOTH TRAINS OF WASTE GAS OXYGEN MONITORS BEING OUT OF SERVIE FOR GREATER THAN THE ALLOWED 38 DAY PERIOD.ON 7 MARCH 1986, THE 1A OXYGEN MONITOR FAILED AND WAS DECLARED OUT OF SERVICE.THE 1B OXYGEN, MONITOR HAD BEEN OUT OF SERVICE SINCE 9 OCTOBER 1985~THE FAILURE RATE OF THESE BECKMAN OXYGEN MONITORS (MODELS F3 AND 755)WERE VERY FREQUENT, AND SO HAVING BOTH OUT OF SERVICE WAS NOT UNUSUAL.(CONTINUED ON NEXT PAGE)

FLORIDA POWER&, LIGHT COMPANY ST.LUCIE PLANT UNITS NO.1&2 SEMIANNUAL REPORT JANUARY 1, 1986 THROUGH JUNE 38, 1986 EFFLUENT AND WASTE DISPOSAL-SUPPLEMENTAL INFORMATION (CONTIN.)11.TECHNICAL SPECIFICATION REQUIRED EXPLANATION FOR MONITOR INOPERABLE FOR GREATER THAN 38 DAYS: (CONTINUED)

DURING THE ENTIRE PERIOD THAT BOTH WERE OUT OF SERVICE, WASTE GAS SAMPLES WERE ANALYZED FOR OXYGEN AS REQUIRED IN THE ACTION STATEMENT OF TECHNICAL SPECIFICATION 3.3.3.18.ON 11 APRIL 1986, IT WAS DISCOVERED THAT THE ALLOWED 38 DAY PERIOD FOR BOTH OXYGEN ANALYZERS TO BE OUT OF SERVICE WAS EXCEEDED.THE PLANT FACILITY REVIEW GROUP (FRG)REVIEWED THE PROLEM.DUE TO THE HIGH FAILURE RATE OF THE BECKMAN OXYGEN MONITORS IT WAS DECIDED TO TEMPORARILY REPLACE THEM WITH ORBISPERE OXYGEN MONITORS (MODEL 27153).A DESIGN CHANGE IS IN DEVELOPMENT TO PERMANENTLY REPLACE THE BECKMAN MONITORS WITH THE ORBISPHERE MONITORS.THE CAUSE FOR EXCEEDING THE ALLOWED 38 DAY PERIOD WAS DUE TO~PLANT PERSONNEL ERRORS.THE HIGH FAILURE RATE OF THE BECKMAN OXYGEN MONITORS IS DUE TO THEIR OXYGEN CELL BEING HIGHLY SENSITIVE TO MOISTURE AND RAPID PRESSURE CHANGES.THE ORBISPHERE REPLACEMENT IS NOT MOISTURE OR PRESSURE SENSITIVE.

FLORIDA POWER&LIGHT COMPANY ST.LUCIE PLANT UNiT NO.1 SEMIANNUAL REPORT JANUARY 1, 1966 THROUGH JUNE 38, 1986 TABLE 3.3-1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT QUARTER¹1 QUARTER¹2 A.FISSION AND ACTIVATION PRODUCTS 1.TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA)2.AVERAGE DILUTED CONCENTRATION DURING PERXOD B.TRITIUM 1.TOTAL RELEASE 2.AVERAGE DILUTED CONCENTRATION DURING PERIOD C.DISSOLVED AND ENTRAINED GASES 1.TOTAL RELZASE 2.AVERAGE DILUTED CONCENTRATION DURING PERIOD D.GROSS ALPHA RADIOACTXVITY CI 1.64E 88 UCX/ML 3.11E-89 CI 7.87E 81 UCI/ML 1.34E-87 CI 1.52E 88 UCI/ML 2.89E-89 2.88E"81 8.87E-18 6.26E 81 1.81E"87 6.67E-81 1.92E-89 1.TOTAL RELEASE CI 7.56E-85 3.84E-85 E.VOLUME OF WASTE RELEASED (PRIOR TO DILUTION)F.VOLUME OF DILUTION WATER USED DURING REPORTXNG PERIOD LITERS 2.85E 87 LITERS 5.28E 11 5.21E 87 3.47E 11 JANUARY FLORIDA POWER 8r, LIGHT COMPANY ST.LUCIE PLANT UNIT NO.1 SEMIANNUAL REPORT 1, 1986 THROUGH JUNE 38, 1986 TABLE 3.4-1 LIQUID EFFLUENTS IO NOCK IDES RELEASED UNIT CONTINUOUS MODE QTR.¹1QTR.¹2 BATCH MODE QTR.¹1.QTR.¹2 I"131 I-132 I-133 I-136 NA-24 CR-51 MN-64 FE-55 CO-57 CO-58 FE-69 CO-68 BR-82 AG-118 SN-113 SB-122 SB-124 NP-239 RB-88 SR"89 SR-98 Y-98 ZR-95 NB"95 NB-97 MO-99 TC-99M RU-183 SB"125 CS-134 CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI'I CI CI ,CI CI CI CI CI CI CI CI 8.88E" 81 8.88E-81 8.88E"81 e.'88E-ea 8.88E-81 8.88E"81 8.88E-81 5.16E"84 8.88E"81 8.88E-81 8.88E"81 8.88E"81 8.88E-81 8.88E-ei 8.88E"81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E"81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 1.18E"82 2.98E"'82 8.88E-81 1.73E-82 8.88E"81 8.88E-81 8.88E"81 8.88E"81 8.88E-81 8.88E-81 1.47E-84 8.88E"81 3.64E-84 8.88E-81 8.88E"81 8.88E-81 8.88E"81-8.88E"81 8.88E"81 8.88E-81 8.88E-81 8,88E"81 8.88E-81 8.88E-81 8.88E"81 8.88E-81 8.88E"81 8.88E-81 8.88E-81 8.88E"81 4.66E-84 1.86E"81 3.48E-84 6.26E-82 8.89E-es 1.96E-84 6.16E-82 6.VSE-83 8.85E"81 8.88E-86 1.78E"81 1.67E-83 7.46E-82 8.88E-81 2.98E-83 8.48E-84 8.82E"8S 8.87E-83 2.48E-84 8.88E-81 2.23E"84 1.87E-84 1.87E"84 1.61E"82 2.94E-82 1.11E-84 3.62E-83 4.22E-83 2.99E-83 2.66E-82 6.77E-82 1.48E"82 2.25E-83 9.18E-84 8.88E-81 7.2SE-86 1.9SE-82 2.88E-83 1.46E"82 8.88E"81 6.98E-82 1.81E-83 1.84E-82 1.75E-85 8.73E"84 1.17E-84 7.S8E-84 9.83E-83 6.88E-83 1.68E"83 1.96E-84 7'8E-85 7.28E-86 2.92E"83 5.32E"83 2.49E"84 5.28E-84 1.49E-83 3.53E-84 3.11E-82 7.69E-83 JANUARY FLORIDA POWER&LIGHT COMPANY ST.LUCIE PLANT UNIT NO.1 SEMIANNUAL REPORT 1, 1986 THROUGH JUNE 38, 1986 TABLE 3.4" 1 CONTINUED LIQUID EFFLUENTS lt NUCLIDES RELEASED UNIT CONTINUOUS MODE QTR.¹1 QTR.¹2 BATCH MODE QTR.¹1 QTR.¹2 CS-136 CS-137 CS-138 BA"148 LA"148 CE"141 CE-144'OTAL FOR PERIOD CI CI CI CI CI CI ,CI CI 8.SSE-81 1.25E-82 S.88E"81 8.SSEW1 8.SSE-81 8.SSE"81 8.SSE-Si 8.SSE-81 7.31E"83 S.SSE-81 S.SSE-Si S.SSE-81 S.SSE"81 S.SSE-81 4.44E"83 8.26E"82 S.SSE-81 8.85E"84 5.26E-83 3.55E"84 3.68E-83 1.18E-84 1.81E"82 8.48E-85 S.SSE-81 3.15E-83 S.SSE-81 S.SSE"81 2.4SE-82 5.54E"82-1.62E 88 2.24E-81 AR-41 ER-85M XE-131M XE-133 XE-133M XE-135 XE-135M TOTAL FOR PERIOD CI Cl CI CI CI CI CI 8.SSE-81 8.SSE-81 8.SSE-81 S.SSE-81 8.SSE-81 8.SSE-81 8.SSE-81 8.SSE-81 8.SSE-81 8.SSE-81 8.SSE"81 8.SSE"81 8.SSE-81 8.SSE" 81 3..84E"84 2.34E-84 S.SSE-81 1.44E 88 2.28E-82 6.59E"82 2.98E-84 1.26E"84 1.81E-Se 2.46E"83 6.43E"81 8.82E-SS 1'6K-82 8.88E-81 CI S.SSE"81 S.SSE-81 1.52E 88 6.67E-81 FLORIDA POWER 4 LIGHT COMPANY ST.LUCIE PLANT UNIT NO.2 SEMIANNUAL REPORT JANUARY 1, 1966 THROUGH JUNE 38, 1966 TABLE 3.3-2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 12 NUCLIDES RELEASED A.FISSION AND ACTIVATION PRODUCTS 1.TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA)CI 1.62E 88 2.24E"81 UNIT QUARTER¹1 QUARTER¹2 2.AVERAGE DILUTED CONCENTRATION DURING PERIOD B.TRITIUM 1.TOTAL RELEASE 2, AVERAGE DILUTED CONCENTRATION DURING PERIOD C.DISSOLVED AND ENTRAINED GASES 1.TOTAL RELEASE.2.AVERAGE DILUTED CONCENTRATION DURING PERIOD D.GROSS ALPHA RADIOACTIVITY CI 7.87E 81 UCI/ML 1.34E-87 CI 1.52E 88 UCI/ML 2.69E-89 UCI/ML 3.87K-89 6.47E-18 6.26E 81 1.81E-87 6.67E"81 1.92E-89 1.TOTAL RELEASE CI 7.56E-85 8.88E-81 E.VOLUME OF WASTE RELEASED (PRIOR TO DILUTION)F.VOLUME OF DILUTION WATER USED DURING REPORTING PERIOD LITERS 2.61E 86 LITERS 5.28E 11 2.21E 86 3.47K 11 JANUARY FLORIDA POWER&LIGHT COMPANY ST.LUCIE PLANT UNIT NO.2 SEMIANNUAL REPORT 1, 1986 TEROUGH JUNE S8, 198B TABLE 3.4-2 LIQUID EFFLUENTS 13 NUCLIDES RELEASED UNIT CONTINUOUS MODE QTR.¹i QTR.¹2 BATCH MODE QTR.¹1 QTR.¹2 I"131=I"132 I-133 I-1S6 NA-24 CR-61 MN-54 FE-55 CO-67 CO"68 FE-59 CO"68 BR-82 AG"118 SN-113 SB-122 SB-124 NP-239 RB-88 SR-89 SR-98 Y"98 ZR-96 NB-95 NB-97 MO-99 TC"99M RU"183 SB-125 CS-134 CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI'I CI 8.88E-81 8,.88E"81 8.88E-81 8.88E-81 8.88E" 81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E"81 8.88E-81 8.88E-81 8.88E"81 8.88E-81 8.88E-81 8.88E"81 8.88E"81 8.88E-81 8.88E-81 8.88E"81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8'.88E-81 8.88E"81 8.88E-81 8.88E-81 8.88E-81 8.88E'-81 8.88E"81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E"81 8.88E"81 8.88E"81 1.86E-81 3.48E-84 6.26E-82 6.69E-83 1.96E-84 6.16E-82 6.73E-8S 8.86E-81 8.88E-86 1.78E"81 1.67E"83 7.46E-82 8.88E-81 2.98E-83 8.48E-84 8.62E-HS 6.87E-83 2.48E"84 8.88E-81 2.2SE-84 1.67E"84 1.67E"84 1.61E"82 2.94E-82 1.11E-84 3.62E-83 4.22E-83 2.99E"83 2.66E-82 6.77E-82 1.48E"82 2.26E-83 9.18E-84 8.88E-81 7.23E-86 1.9SE-82 2.88E-83 1.46E"82 8.88E-81 6.9BE-82 1.81E"83 1.64E-82 1.76E-85 8.7SE"84 1.17E"84 7.38E-84 9.83E-83 6.88E"83 1.68E-83 1.96E"84 7.28E-85 7.28E-85 2.92E-83 5.32E-83 2.49E-84 6.28E-84 1.49E"83 3.53E-84 3.11E-82 7.69E-83 JANUARY FLORIDA POWER 5, LIGHT COMPANY ST.LUCIE PLANT UNIT NO.2 SEMIANNUAL REPORT 1, 1886 THROUGH JUNE 38, 1886 TABLE 3.4-2 CONTINUED LIQUID EFFLUENTS 14 NUCLIDES RELEASED UNIT CONTINUOUS MODE QTR.¹1 QTR.¹2 BATCH MODE QTR.¹1 QTR.¹2 CS-136 CS-137 CS-138 BA-148 LA-148 CE-141 CE"144'ZOTAL FOR PERIOD AR-41 KR-85M XE-131M XE-133 XE"133M XE-135 XE"135M TOTAL FOR PERIOD CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI 8.88E-81 8.88E-81 8.88E-81 8.88K-81 8.88E-81 8.88E"81 8.88E-81 8.88E-81 8.88E"81 8.88E-81 8.88E-81 8.88E-81 8.88E"81 8.88E"81 4.44E"83 8.26E-82 8.88E-81 8.85E"84 5.26E-83 3.55E"84 3.68E-83 1.18E"84 1.81E"82 8.48E-85 8.88E"81 3.15E-83 8.88E-81 8.88E"81 8.88K"81 8.88E-81 8.88E-81 8.88E"81 8.88E-81 8'.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E"81 8.88E"81 8.88E-81 8.88E"81 3.84E-84'.34E"84 8.88E"81 1.44E 88 2.28E"82 6.59E-82 2.88E-84 1.26E-84 1.61E-85 2.46E"83 6.43E-81 8.82E"83 1.36E"82 8.88E-81 8.88E"81 8.88E-81 1.52E 88 6.6VE-81 8.88E-81 8.88E-81 1.,62R 88 2.24E"81 FLORIDA POWER&LIGHT COMPANY ST.LUCIE PLANT UNIT NO.1 SEMIANNUAL REPORT JANUARY 1, 1986 THROUGH JUNE 38, 1986 TABLE 3.6-1 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES't 5 NUCLIDES RELEASED A.FISSION AND ACTIVATION GASES UNIT QUARTER¹1 QUARTER¹2 1~TOTAL RELEASE CI 5.13E 83 1.TOTAL IODINE-131 CI 4.41E-82 2.AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 5.67E-83 C.PARTICULATES 1.PARTICULATES T-1/2>8 DAYS CI 8.88E-81 2.AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 8.88E-81 3.GROSS ALPHA RADIOACTIVITY

'I D.TRITIUM 5.98E-88 1.TOTAL RELEASE CI 1.29E 81 2~AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 1.66E 88 2.AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 6.68E 82 B.IODINES 1.39E 84 1.76E 83 1.78E-81 2.27E-82 8.64E-87 1.18E-87 2.33E-87 1.72E 81 2.19E 88 FLORIDA POWER&LIGHT COMPANY ST.LUCIE PLANT UNIT NO.1 SEMIANNUAL REPORT JANUARY 1, 1986 THROUGH JUNE 38, 1986 TABLE 3.7-1 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES 16 NUCLIDES CONTINUOUS MODE RELEASED UNIT QTR.¹1 QTR.¹2 1.NOBLE GASES BATCH MODE QTR.¹1 QTR.¹2 AR-41 KR-85 KR-85M KR-87 KR-88 XE-131M XE-133 XE-133M XE-135 XE-135M TOTAL FOR PERIOD 2.IODINE I-131 I-132 I-133 I-135 TOTAL FOR PERIOD 3.PARTICULATE CS-137 TOTAL FOR PERIOD CI CI CI CI CI CI CI CI CI CI 8.HSE-81 8.SSE-81 1.21E 81 8.SSEM1 1.33E 81 8.SSE-81 4.49E 83 2.55E 81 2.8SE 82 8.SSE-81 2.78EW2 8.HSE-81 8.18E 81 2.51E 81 5.67E 81 S.SSE-81 1.11E 84 1.96E 82 9.92E 82 S.SSE-81 1.83E-81 ,1.68E 88 8.17EM2 1.39E-82 4.77E-82 2.35E 88 3.84E 82 1.51E 88 1.45E 88 S.SSE-81 1.51E 88 1.53E 88 3.1HE 88 6.18EM2.1.84E 88 6.13E 88 1.31E 83 1.71E 81 1.24E 82 1.84E-83 CI CI CI CI 4.41E-82'.78E-81 9.56E-82 5.98E-82 2.36E-81 1.99E-81 8.38E-82 7.55E-82 CI 4.59E-81 5.12E-H1 CI S.SSE-81 8.64E-87 CI S.SSE-81 8.64E-87 CI 4.74E 83 1.24E 84 3.91E 82 1.46E 83 FLORIDA POWER Sc LIGHT COtPANY ST.LUCIE PLANT UNIT NO.2 SEMIANNUAL REPORT JANUARY 1, 1986 THROUGH JUNE 38, 1986 TABLE 3.6-2 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES 17 NUCLIDES RELEASED A.FISSION AND ACTIVATION GASES UNIT QUARTER 01 QUARTER 02 1.TOTAL RELEASE CI 4.63E 83 1.TOTAL IODINE-131 CI 1.28E-82 2.AVERAGE RELZASE RATE FOR PERIOD UCI/SEC 1.65E-83 C.PARTICULATES 1.PARTICULATES T-1/2>8 DAYS CI 2.44E-85 2.AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 3.13E-86 3.GROSS ALPHA RADIOACTIVITY D.TRITIUM 1.TOTAL RELEASE CI CI 2'4E-87 6.47E 88 2.AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 8.32E-81 2.AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 5.96E 82 B.IODINES 4.28E 82 5.34E 81 5.28E-83 6.61E-84 1.28E-84 1.53E-85 3.14E-87 4.14E 88 5.26E-81 FLORIDA POWER Bc LIGHT COMPANY ST.LUCIE PLANT UNIT NO.2 SEMIANNUAL REPORT 1, 1986 THROUGH JUNE 38.1986 TABLE 3.7-2 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES NUCLIDES RELEASED UNIT 1.NOBLE GASES CONTINUOUS MODE QTR.¹1 QTR.¹2 BATCH MODE QTR.¹1 QTR.¹2 AR-41 KR-85 KR-85M KR-87 KR-88 XE-131M XE-133 XE-133M XE-135 TOTAL FOR PERIOD CI CI CI CI CI CI CI CI CI CI 8.98E 88 8.SSE-81 1.13E 82 4.15E Si 1.46E 82 6.18E 81 3.22E 83 S.SHE-81 8.57E 82 8.SHE-'81 8.SSE-81 2.98E 88 S.SSE-81 2.14E 88 S.SSE-81 3.68E 82 S.SSE-81 3.99E 81 1.43E 88 1.57E-81 5.43E-81 2.76E-82 3.42E-81'.42E 88 1.78E 82 2'6E 88 9.85E 88 7.75E-81 1.89E-81 1.94E-82 S.SHE-81 2.18E-82 6.89E-82 1.35E 81 1.68E-Sl 3.67E-81 4.45E 83 4.85E 82 1.85E 82 1.5HE 81 2.IODINE I-131 I-133 TOTAL FOR PERIOD 3~PARTICULATE CO-57 CO-58 CS-137 TOTAL FOR PERIOD CI 1.28E-82 5.28E-83 CI 2.52E-82 3.31E-83 CI 3.88E-82.8.51E-83 CI 4.46E-86 S.SHE-81 CI S.SSE-81 1.2HE-84 CI 1.99E-85 S.SHE-81 CI 2.44E-85 1.28E-84 FLORIDA POWER AND LIGHT COMPANY ST.LUCIE PLANT SEMIANNUAL REPORT JANUARY lg 1986 THROUGH JUNE 30, 1986 UNITs 1 s 2, TABLE 3.9 19 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.Solid Waste Shipped Offsite for Burial or Disposal 1.TYPE OF WASTE UNIT 6 MONTH PERIOD ERROR a.Spent Resins, Process Filters M3 Ci 1.80E+1 1.98E+3 2.0E+1 b.Dry Compressible Waste M3 Ci 2.17E+2 7.90E+0 2.0E+1 c.Irradiated Components d.Other M3 Ci M3 Ci N/A N/A 2.Estimate of Major Nuclide Composition (by type of waste)a.Co 58 Cs 137 Cs 134 Co 60 Mn 54 39.9 27.2 25.1 4.4 1.0 b.Co 60 Cs 137 C 14 Cs 134 Fe 55 Co 58 23.5 17.0 12.1 12.0 10.4 9.2 Cr 51 Ni 63 Nb 95 H 3 Mn 54 Zr 95 3.2 2.6 2.5 1.9 1.6 1.5 3.'olid Waste Disposition Number of Shi ments Mode of Trans ortation Destination 13 Sole Use Truck Barnwell, S.C.B.Irradiated Fuel Shipments Number of Shi ments Mode of Trans ortation-Destxnatxon N/A N/A N/A-Not Applicable TABLE 3.9 (continued)

HASTE CLASSIFICATION TOTAL VOLUME (Note 1)TOTAL CURIE (Notes 1&2)PRINCIPAL NUCLIDES (Note 3)TYPE OF WASTE R.G.1.21 CATEGORY (Note 4)TYPE OF CONTAINER SOLIDIFICATION OE ABSORBENT AGENT CLASS A 195ft3 6.354 C14,Ni63 Csl37,I129 Pwr Trash l.b.NRC Certified LSA>Type A None CLASS A 7470ft3 1.545 NONE Pwr Trash l.b.Non-Specification None Strong Tight Pkg, CLASS B 193ft3 62.787 Ni63,Sr90, Csl37,Sum of Nuclides w/T4<5 years Pwr Ion-Exchange Resins l.a.NRC Certified LSA>Type A None CLASS C 12lft'607.576 Co60,Sr90,Ni63, Cs137,Sum of Nuclides w/T4<5 years, C14 Pwr Ion-Exchange Resins l.a.NRC Certified Type B Nohe CLASS C 119ft 37.984 Co60, Csl37, Ni63, Sr90, Sum of Nuclides w/T9<5 years, I129-Pwr Process Filters l.a.NRC Certified Type B None CLASS C 202ft3 271.738 Co60,Ni63,Sr90, I129,Cs137, Sum of Nuclides w/TQ<5 years Pwr Ion-Exchange Resins l.a.NRC Certified LSA>Type A None 21 FLORIDA POWER Bc LIGHT COMPANY ST.LUCIE PLANT SEMIANNUAL REPORT JANUARY,.1986.THROUGH VQEB 1986 UNITS I AND 2 TABLE 3.9 (CONT.)SOLID WASTE SUPPLEMENT NOTE I: The total curie quantity and radionuclide composition of solid waste shipped from the St.Lucie Units 1 R 2 are determined using a combination of qualitative and quantitive techniques.

In general, the St.Lucie Plant follows the guidelines outlined in the Low Level Waste Licensing Branch Technical Position (BTP)on Radioactive Waste Classification (5/11/83)for these determinations.

The 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 some 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 gamma emitters and periodic off-site analyses for other radionuclides.

The 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.Offsite analyses are used to establish scaling factors or other estimates for radionuclides such as 3H, 1"C;99Tc, 1291, TRU 2k 1Pu, 202Cm 63NI, and 55Fe.NOTE 2:."Principal Radionuclides" refer to those radionuclides contained in the waste in concentrations

'greater than.Ol 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 iVUREG 0782, Draft Environment Impact Statement on 10 CFR 61"Licensing Requirements for Land Disposal of Radioactive Waste".NOTE 0: "Type of Container" refers to the transport package.

ATTACHMENT-A TO SEMIANNUAL REPORT 0.D.C.M.REVISED PAGES AS PER TECHNICAL SPECIFICATION 6.14.2 Page 45 of 84 ST~LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.C-200, REVISION 6 OFFSITE DOSE CALCULATION MANUAL (ODCM)4.0 (continued) 5.Batch Releases A.Liquid 1.%aiber of batch releases: 2.Total time period of batch releases: 3.%wham time period for a batch release: 4.Average time period for a batch release: 5.Mhdrnm time period for a batch release: 6.Average dilution strean flow during the period (see Note 1 on'Ihble 3.3): All liquid releases are sumnarized in tables minutes minutes minutes minutes B.Gaseous 1.Number of batch releases: 2.Total the period for batch releases: 3.Radram time period for a.batch release: 4.Average the period for batch releases: 5.Mirdmn time pertod for a batch release: All gaseous waste releases are sunnarized in tables minutes minutes minutes minutes 6.Unplanned Releases A.Liquid 1.Number of releases: 2.Total activity releases: Curie s B.Gaseous 1.Number of releases: 2.Total activity released: C.See attachnents (if applicable) for: Curie s 2t 3t 4, A description of the event ard equipnent involved.Cause(s)for the mplanned release.Actions taken to prevent a recurrence (bnseqmnces of the unplanned release 7.Description of dose assessnent of radiation dose fran radioactive effluents to the general public due to their activities inside the site are reported on the January semiannual report.8.Offsite dose calculation manual revisions initiated during this reporting period.See STSW 6.14 for required attachnents tea the Smdannual Report.

Page 46 of 84 ST+LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO~C-200, REVISION 6 OFFSITE DOSE CALCULATION MANUAL (ODCM)FU3IDA PWER 6 LID QMPANY ST.LUCIE l5XZ 8 SIMIANNm, REKBT-//mrna//'IM3IZ 3+3: QUID EFHIIMS-SUMMATION OF ALL I EUMES A.Fission and Activation Products Total Release-(Not LnchxUxg Tritium, Gases, Alpha)2.Average Diluted Concentration During Period B.Trittun KIAK E E 1.'Ibtal Release E 2.Average Diluted Omcentration During Period C.Dissolved and Entrained Gases l.'Ibtal Release 2.Average Diluted Concentration During Period D.Gross A1pha Radioactivity 1.'Ibtal Release E.Volune of Waste Released (Prior to Dilut&n)F.Volune'of Dilution Water Used During Perodl IJXERS E E 1-The volure reported shxQd be for the entire interval of the reporting period, not~t during release intervals.

'Ihis volune should also be used to calculate average dilutIon stream flow durirg the period.

ST UCIE PLANT CHEMISTRY OPERATING E'aiuCEDURE NO.C-200, REVI'SIOn 6 OFFSITE DOSE CALCULATION MANUAL (ODCH)Page 81 of 84 APPBBIX E RADIOIlGICAL BVIRONINIAL SURVEILIANCE Si.'.uJCIE HANf Key to Sarrple Locations Food Products Food Paxhcts Food Products Ocean side vicinity of St.Lucia Plant (NKE 1)Offsite aar orth pmperty line Offsite near south pmperty line Near srnth end of HutcIriruxn Island SAMPLE rXLUZHB'rustacea Fish Breed leaf vegetatt.on (rrangmve)

Brrnd leaf vegetatirn (rrangmve)

Grus tacea Fish Bread leaf vegetation (rrangmve)

SemL-Annually Semi-Annually monthly (when avaQable)Monthly (whn avai3able)

Semi-Anrru ally Semi-AnnuQly deathly APPROXIMATE DISMASK (miles)10-20 E ESE S SSE It is the policy of Flori&Pmer&Light Crgpany (FPL)that the St.Lucie 1&2 Radio1ogical Ehvirienral Monitoring Pmgrams are onducted by the State of Florida Deparurent of Health and Rehabilitative Services (DHRS), pursuant to an Agreerrent between FPL snd I3RS and;tlat mmrdinaticn of th.Radiological Fnvirrnrrental Honitoring Pmgrarns with EHRS and corrpliance with tb Radiological Fnviraurental Hcnitoring Pmgram TecInical Specificaticns are tIa responsibility of the Nuclear Energy Services Departrrent.

NKE 1 Ihese sarry1es rray be collected from or supplenented by san@les collected fmm the plant intake aual if the required analyses are urable to be perforrred due to uravailability or iradequate quantity of sample fmm the oem side location.

FLORIDA POWER&LIGHT COMPANY gg 2 7 1986 L-86-309, Dr.J.Nelson Grace Regional Administrator, Region II U.S.Nuclear Regulatory Commission Suite 2900 101 Marietta Street, N.W.Atlanta, Georgia 30323 I

Dear Dr.Grace:

Re: St.Lucie Units 1 and 2 Docket Nos.~"-335 and 30-389 0 chemi-..Annual~kadioactiver~luent-.Release-.Re or t, Attached is the Radioactive Effluent Release Report for the period of January I, 1986 through June 30, 1986 for St.Lucie 1 and 2, as required by Technical Speci f ication 6.9.1.1.0.

Should you or your staff have any questions on this information, please contact us.Very truly yours, C.O.Woo Group Vic President Nuclear Energy COW/SA V/aa Attachment cc: Director, Office of Inspection and Enforcement, USNRC Document Control Desk, USNRC Harold F.Reis, Esquire PNS 303/I Ll:1 P=QPLE.SEi VING PSOPI=

P.O.BOX 14000, JUNO BEACH, FL 33408 0420 NARGH tl 0 198't L-87-95 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gentlemen:

Re: St.Lucie Units I 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 I, l986 through December 30, l986 for St.Lucie Units I 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, Group Vice President Nuclear Energy COW/GRM/gp At tachment cc: Dr.J.Nelson Grace, Regional Administrator, Region II, USNRC R.J.Crlenjak, Senior Resident Inspector, USNRC, St.Lucie Plant GRM5/0IO/I I I an FPL Group company