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 FLORIDA POWER & LIGHT CO.
To:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
L-86-349, NUDOCS 8610270369
Download: ML17216A740 (32)

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RE"-.UL*TORY INPORN*TION DISTRIBUTION SYSTEN (BIDS>

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'CCESSION NBR: 8610270369 DOC. DATE: 86/06/30 NOTARIZED: NO DOCKET ¹ FAC IL: 50-335 St. Luc i e P

,('0-389 lant'nit 1> Florida Power Cr Light Co.

St. Lucie Planti Unit 2i Florida Power 8c Light Co.

05000335 05000389

~,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. Region 2i Office of Director

SUBJECT:

"Combined Semiannual Radioactive Effluent Release Rept for Jan June 1986. " W/860827 ltr.

DISTRIBUTION CODE: IE25D TITLE: Periodic Environ COPIES RECEIVED: LTR Monitoring Rept (50 g

DKT)

ENCL g SI ZE: O

-Annual/Semiannual/Ef fluent/

NOTES:

RECIPIENT COPIES RECIPIENT COP IES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PWR-B PDS LA 0 PWR-B PDS PD 04 5 5 PWR-B PEICSB 3 3 INTERNAL: AEOD 1 1 AEOD/PTB 1 1 IE FILE 01 1 NRR BWR ADTS 1 NR PWR-A ADTS 1 1 NRR PWR-B ADTS 1 NRR7DS RA 1 1 RGN2/DRSS/EPRPB 1 RM/DDA I/MIB 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

TABLE OF CONTENTS DESCRIPTION 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 9 UNIT 2 12 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES 8c NUCLIDE SUMMATION BY QUARTER UNIT 1 15 UNIT 2 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. 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.

B. 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. 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.

B. 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.

wC. 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, ANY CALENDAR YEAR TO <= 15 MREM TO ANY ORGAN.

AND'URING 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 DESCRIBED 2,

IN EXCEPT FOR ENTRAINED OR DISSOLVED NOBLE GASES AS 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. ANALYTICALERROR FOR NUCLIDES TYPE AVERAGE MAXIMUM LIQUID + OR 9X + OR 38K GASEOUS + OR -18K + 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 SAMPLING TYPE OF METHOD OF SOURCE FREQUENCY ANALYSXS ANALYSIS EACH BATCH PRINCIPAL GAMMA EMITTERS P.H.A.

MONITOR MONTHLY TRITIUM L. S.

TANK COMPOSITE GROSS ALPHA G.F.P.

1 RELEASES QUARTERLY SR-89, SR-90 C.S.

COMPOSITE FE-55 CONTINUOUS DAILY PRINCIPAL GAMMA EMITTERS RELEASES GRAB & I-131 4/M COMPOSITE SAMPLES P.H.A.

DXSSOLVED & ENTRAINED GASES ONE BATCH/MONTH TRITIUM COMPOS. MONTHLY L.S.

ALPHA COMPOSITE MONTHLY G.F.P.

SR-89, SR-90, & 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 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 SAMPLING TYPE OF METHOD OF SOURCE FREQUENCY ANALYSIS ANALYSIS WASTE GAS DECAY TANK EACH BATCH PRINCIPAL GAMMA EMITTERS P.H.A.

RELEASES CONTAINMENT PRINCIPAL GAMMA EMITTERS P.H.A.

PURGE EACH PURGE TRITIUM L.S ~

RELEASES PRINCIPAL GAMMA EMITTERS P.H.A.

"

TRITIUM L.S.

PLANT MONTHLY PART XCULATE VENT COMPOSITE GROSS ALPHA G.F.P.

QUARTERLY PARTICULATE C.S.

COMPOSITE SR-89 SR-90 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- 39.5 B. TOTAL TIME PERIOD OF BATCH RELEASES- 21455. MINUTES C. MAXIMUM TIME PERIOD FOR A BATCH RELEASE- 855. MINUTES D. AVERAGE TIME PERIOD FOR A BATCH RELEASE- 543. MINUTES E. MINIMUM TIME PERIOD FOR A BATCH RELEASE- 330. MINUTES F. AVERAGE STREAM FLOW DURING REPORTING PERIOD INTO A FLOWING STREAM- 891590. G.P.M.

GASEOUS FOR - ST. LUCIE PLANT UNIT NO. 1

~

A. NUMBER OF BATCH RELEASES- 18.0 B. TOTAL TIME PERIOD OF BATCH RELEASES- 6148. MINUTES C. MAXIMUM TIME PERIOD FOR A BATCH RELEASE: 997. MINUTES D. AVERAGE TIME PERIOD FOR A BATCH RELEASE- 342. MINUTES E. MINIMUM TIME PERIOD FOR A BATCH RELEASE: 124. MINUTES 6, UNPLANNED RELEASES LIQUIDS FOR - ST. LUCIE PLANT UNIT NO. 1 A. NUMBER OF RELEASES= 0.

B. TOTAL ACTXVITY RELEASED- 0. CURIES GASEOUS FOR - ST. LUCIE PLANT UNIT NO. 1 A. NUMBER OF RELEASES- 0.

B. TOTAL ACTIVITY RELEASED: 0. CURIES SEE ATTACHMENTS (IF APPLICABLE) FOR:

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- 39.5 B. TOTAL TIME PERIOD OF BATCH RELZASES- 21455. MINUTES C. MAXIMUM TIME PERIOD FOR A BATCH RELEASE- 855. MINUTES D. AVERAGE TIME PERIOD FOR A BATCH RELEASE- 543. MINUTES E. MINIMUM TIME PERIOD FOR A BATCH RELEASE- 338. MINUTES F. AVERAGE STREAM FLOW DURING REPORTING PERIOD INTO A FLOWING STREAM- 891598. G.P.M.

GASEOUS FOR - ST. LUCIE PLANT UNIT NO. 2 A. NUMBER OF BATCH RELEASES- 48.8 B. TOTAL TIME PERIOD OF BATCH RELEASES- 9463. MINUTES C. MAXIMUM TIME PERIOD FOR A BATCH RELEASE- 1845. MINUTES D. AVERAGE TIME PERIOD FOR A BATCH RELEASE: 237. MINUTES E. MINIMUM TIME PERIOD FOR A BATCH RELEASE: 45. MINUTES Co, UNPLANNED RELEASES LIQUIDS FOR - ST. LUCIE PLANT UNIT NO. 2 A. NUMBER OF RELEASES- 8.

B. TOTAL ACTIVITY RELEASED- 8. CURIES GASEOUS FOR : ST. LUCIE PLANT UNIT NO. 2 A. NUMBER OF RELZASES- 8.

B. TOTAL ACTIVITY RELEASED- 8. CURIES SEE ATTACHMENTS (IF APPLICABLE) 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 RELZASE."

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.

8. 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 UNIT ¹ 1 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 QUARTER ¹1 QUARTER ¹2 A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CI 1.64E 88 2.88E"81

2. AVERAGE DILUTED CONCENTRATION DURING PERXOD UCX/ML 3.11E-89 8.87E-18 B. TRITIUM

1. TOTAL RELEASE CI 7.87E 81 6.26E 81

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD UCI/ML 1.34E-87 1.81E"87 C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELZASE CI 1.52E 88 6.67E-81

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD UCI/ML 2.89E-89 1.92E-89 D. GROSS ALPHA RADIOACTXVITY

1. TOTAL RELEASE CI 7.56E-85 3.84E-85 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) LITERS 2.85E 87 5.21E 87 F. VOLUME OF DILUTION WATER USED DURING REPORTXNG PERIOD LITERS 5. 28E 11 3.47E 11

IO FLORIDA POWER 8r, LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 SEMIANNUAL REPORT JANUARY 1, 1986 THROUGH JUNE 38, 1986 TABLE 3.4-1 LIQUID EFFLUENTS NOCK IDES CONTINUOUS MODE BATCH MODE RELEASED UNIT QTR.¹1 QTR.¹2 QTR.¹1 . QTR.¹2 I"131 CI 8. 88E" 81 2. 98E"'82 1.86E"81 1.48E"82 I-132 CI 8. 88E-81 8. 88E-81 3.48E-84 2.25E-83 I-133 CI 8. 88E"81 1.73E-82 6.26E-82 9.18E-84 I-136 CI e.'88E-ea 8.88E"81 8.89E-es 8.88E-81 NA-24 CI 8. 88E-81 8.88E-81 1.96E-84 7.2SE-86 CR-51 CI 8. 88E"81 8.88E"81 6.16E-82 1.9SE-82 MN-64 CI 8. 88E-81 8.88E"81 6.VSE-83 2.88E-83 FE-55 CI 5.16E"84 8.88E-81 8.85E"81 1.46E"82 CO-57 CI 8.88E"81 8.88E-81 8.88E-86 8.88E"81 CO-58 CI 8.88E-81 1.47E-84 1.78E"81 6.98E-82 FE-69 CI 8.88E"81 8.88E"81 1.67E-83 1.81E-83 CO-68 CI 8.88E"81 3.64E-84 7.46E-82 1.84E-82 BR-82 CI 8.88E-81 8.88E-81 8.88E-81 1.75E-85 AG-118 CI 8.88E-ei 8.88E"81 2.98E-83 8.73E"84 SN-113 CI 8.88E"81 8.88E-81 8.48E-84 1.17E-84 SB-122 CI 8.88E-81 8.88E"81 8.82E"8S 7.S8E-84 SB-124 CI 8.88E-81 -8.88E"81 8.87E-83 9.83E-83 NP-239 RB-88 SR"89 SR-98

'ICI CI 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 2.48E-84 8.88E-81 2.23E"84 1.87E-84 6.88E-83 1.68E"83 1.96E-84 7 '8E-85 Y-98 CI 8.88E-81 8.88E-81 1.87E"84 7.28E-86 ZR-95 ,CI 8.88E"81 8.88E-81 1.61E"82 2.92E"83 NB"95 CI 8.88E-81 8.88E"81 2.94E-82 5.32E"83 NB-97 CI 8.88E-81 8.88E-81 1.11E-84 2.49E"84 MO-99 CI 8.88E-81 8.88E"81 3.62E-83 5.28E-84 TC-99M CI 8.88E-81 8.88E-81 4.22E-83 1.49E-83 RU-183 CI 8.88E-81 8.88E-81 2.99E-83 3.53E-84 SB"125 CI 8.88E-81 8.88E"81 2.66E-82 3.11E-82 CS-134 CI 1.18E"82 4.66E-84 6.77E-82 7.69E-83

lt FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 SEMIANNUAL REPORT JANUARY 1, 1986 THROUGH JUNE 38, 1986 TABLE 3. 4" 1 CONTINUED LIQUID EFFLUENTS NUCLIDES CONTINUOUS MODE BATCH MODE RELEASED UNIT QTR.¹1 QTR.¹2 QTR.¹1 QTR.¹2 CS-136 CI 8. SSE-81 8. SSE-81 4.44E"83 1.18E-84 CS-137 CI 1. 25E-82 7.31E"83 8.26E"82 1.81E"82 CS-138 CI S. 88E"81 S.SSE-81 S.SSE-81 8.48E-85 BA"148 CI 8. SSEW1 S.SSE-Si 8.85E"84 S.SSE-81 LA"148 CI 8. SSE-81 S.SSE-81 5.26E-83 3.15E-83 CE"141 CI 8. SSE "81 S.SSE"81 3.55E"84 S.SSE-81 CE-144'OTAL

,CI 8. SSE-Si S.SSE-81 3.68E-83 S.SSE"81 FOR PERIOD CI 2.4SE-82 5.54E"82 -

1.62E 88 2.24E-81 AR-41 CI 8. SSE-81 8. SSE-81 3..84E"84 1.26E"84 ER-85M Cl 8. SSE-81 8. SSE-81 2.34E-84 1.81E-Se XE-131M CI 8. SSE-81 8. SSE-81 S.SSE-81 2.46E"83 XE-133 CI S. SSE-81 8. SSE"81 1.44E 88 6.43E"81 XE-133M CI 8. SSE-81 8. SSE"81 2.28E-82 8.82E-SS XE-135 CI 8. SSE-81 8. SSE-81 6.59E"82 1 '6K-82 XE-135M CI 8. SSE-81 8. SSE" 81 2.98E-84 8.88E-81 TOTAL FOR PERIOD CI S.SSE"81 S.SSE-81 1.52E 88 6.67E-81

12 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 NUCLIDES RELEASED UNIT QUARTER ¹1 QUARTER ¹2 A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CI 1.62E 88 2.24E"81

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD UCI/ML 3.87K-89 6.47E-18 B. TRITIUM

1. TOTAL RELEASE CI 7.87E 81 6.26E 81 2, AVERAGE DILUTED CONCENTRATION DURING PERIOD UCI/ML 1.34E-87 1.81E-87 C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE. CI 1.52E 88 6.67E"81

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD UCI/ML 2.69E-89 1.92E-89 D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CI 7.56E-85 8.88E-81 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) LITERS 2.61E 86 2.21E 86 F. VOLUME OF DILUTION WATER USED DURING REPORTING PERIOD LITERS 5. 28E 11 3.47K 11

13 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 2 SEMIANNUAL REPORT JANUARY 1, 1986 TEROUGH JUNE S8, 198B TABLE 3.4-2 LIQUID EFFLUENTS NUCLIDES CONTINUOUS MODE BATCH MODE RELEASED UNIT QTR.¹i QTR.¹2 QTR.¹1 QTR.¹2 I"131 CI 8. 88E-81 8. 88E-81 1.86E-81 1.48E"82

=I"132 CI 8,. 88E"81 8. 88E "81 3.48E-84 2.26E-83 I-133 CI 8. 88E-81 8. 88E-81 6.26E-82 9.18E-84 I-1S6 CI 8. 88E-81 8. 88E-81 6.69E-83 8.88E-81 NA-24 CI 8. 88E" 81 8. 88E"81 1.96E-84 7.23E-86 CR-61 CI 8. 88E-81 8. 88E-81 6.16E-82 1.9SE-82 MN-54 CI 8. 88E-81 8. 88E-81 6.73E-8S 2.88E-83 FE-55 CI 8. 88E-81 8. 88E "81 8.86E-81 1.46E"82 CO-67 CI 8. 88E-81 8. 88E"81 8.88E-86 8.88E-81 CO"68 CI 8. 88E-81 8. 88E-81 1.78E"81 6.9BE-82 FE-59 CI 8. 88E-81 8. 88E-81 1.67E"83 1.81E"83 CO"68 CI 8. 88E-81 8. 88E"81 7.46E-82 1.64E-82 BR-82 CI 8. 88E-81 8. 88E-81 8.88E-81 1.76E-85 AG"118 CI 8. 88E-81 8. 88E-81 2.98E-83 8.7SE"84 SN-113 CI 8. 88E-81 8. 88E-81 8.48E-84 1.17E"84 SB-122 CI 8. 88E-81 8. 88E-81 8.62E-HS 7.38E-84 SB-124 CI 8. 88E-81 8'.88E-81 6.87E-83 9.83E-83 NP-239 CI 8. 88E-81 8. 88E "81 2.48E"84 6.88E"83 RB-88 CI 8.88E-81 8. 88E-81 8.88E-81 1.68E-83 SR-89 CI 8.88E-81 8. 88E-81 2.2SE-84 1.96E"84 SR-98 CI 8.88E-81 8. 88E-81 1.67E"84 7.28E-85 Y"98 CI 8.88E-81 8. 88E'-81 1.67E"84 7.28E-85 ZR-96 CI 8.88E-81 8. 88E"81 1.61E"82 2.92E-83 NB-95 CI 8.88E-81 8. 88E-81 2.94E-82 5.32E-83 NB-97 CI 8.88E-81 8. 88E-81 1.11E-84 2.49E-84 MO-99 CI 8.88E-81 8. 88E-81 3.62E-83 6.28E-84 TC"99M CI 8.88E-81 8. 88E-81 4.22E-83 1.49E"83 RU"183 CI'I 8.88E-81 8. 88E "81 2.99E"83 3.53E-84 SB-125 8.88E-81 8. 88E"81 2.66E-82 3.11E-82 CS-134 CI 8.88E-81 8. 88E"81 6.77E-82 7.69E-83

14 FLORIDA POWER 5, LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 2 SEMIANNUAL REPORT JANUARY 1, 1886 THROUGH JUNE 38, 1886 TABLE 3.4-2 CONTINUED LIQUID EFFLUENTS NUCLIDES CONTINUOUS MODE BATCH MODE RELEASED UNIT QTR.¹1 QTR.¹2 QTR.¹1 QTR.¹2 CS-136 CI 8.88E-81 8. 88E-81 4.44E"83 1.18E"84 CS-137 CI 8. 88E-81 8. 88E "81 8.26E-82 1.81E"82 CS-138 CI 8.88E-81 8. 88E-81 8.88E-81 8.48E-85 BA-148 CI 8. 88K-81 8. 88E-81 8.85E"84 8.88E"81 LA-148 CI 8. 88E-81 8. 88E-81 5.26E-83 3.15E-83 CE-141 CI 8. 88E "81 8. 88E"81 3.55E"84 8.88E-81 CE"144 CI 8. 88E-81 8. 88E"81 3.68E-83 8.88E"81

'ZOTAL FOR PERIOD CI 8.88E-81 8.88E-81 1.,62R 88 2.24E"81 AR-41 CI 8. 88K "81 8. 88E-81 3.84E-84'.34E"84

1. 26E-84 KR-85M CI 8. 88E-81 8. 88E-81 1.61E-85 XE-131M CI 8. 88E-81 8. 88E-81 8.88E"81 2.46E"83 XE-133 CI 8. 88E"81 8. 88E"81 1.44E 88 6.43E-81 XE"133M CI 8. 88E-81 8. 88E "81 2.28E"82 8.82E"83 XE-135 CI 8'.88E-81 8. 88E-81 6.59E-82 1.36E"82 XE"135M CI 8. 88E-81 8. 88E "81 2.88E-84 8.88E-81 TOTAL FOR PERIOD CI 8.88E"81 8.88E-81 1.52E 88 6.6VE-81

't 5 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 NUCLIDES RELEASED UNIT QUARTER ¹1 QUARTER ¹2 A. FISSION AND ACTIVATION GASES 1 ~ TOTAL RELEASE CI 5.13E 83 1.39E 84

2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 6.68E 82 1.76E 83 B. IODINES

1. TOTAL IODINE-131 CI 4.41E-82 1.78E-81

2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 5.67E-83 2.27E-82 C. PARTICULATES

1. PARTICULATES T-1/2 2.

3.

> 8 DAYS

'I CI AVERAGE RELEASE RATE FOR PERIOD UCI/SEC GROSS ALPHA D. TRITIUM

1. TOTAL RELEASE RADIOACTIVITY CI

8. 88E-81 8.88E-81 5.98E-88 1.29E 81 8.64E-87 1.18E-87 2.33E-87 1.72E 81 2 ~ AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 1.66E 88 2.19E 88

16 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 NUCLIDES CONTINUOUS MODE BATCH MODE RELEASED UNIT QTR.¹1 QTR.¹2 QTR.¹1 QTR.¹2

1. NOBLE GASES AR-41 CI 8. HSE-81 2. 78EW2 1.83E-81 1.51E 88 KR-85 CI 8. SSE-81 8. HSE-81 ,1.68E 88 1.53E 88 KR-85M CI 1.21E 81 8.18E 81 8. 17EM2 3.1HE 88 KR-87 CI 8. SSEM1 2.51E 81 1.39E-82 6. 18EM2.

KR-88 CI 1.33E 81 5.67E 81 4.77E-82 1.84E 88 XE-131M CI 8. SSE-81 S.SSE-81 2.35E 88 6.13E 88 XE-133 CI 4.49E 83 1.11E 84 3.84E 82 1.31E 83 XE-133M CI 2.55E 81 1.96E 82 1.51E 88 1.71E 81 XE-135 CI 2.8SE 82 9.92E 82 1.45E 88 1.24E 82 XE-135M CI 8. SSE-81 S.SSE-81 S.SSE-81 1.84E-83 TOTAL FOR PERIOD CI 4.74E 83 1.24E 84 3.91E 82 1.46E 83

2. IODINE I-131 CI 4.41E-82 '.78E-81 I-132 CI 9.56E-82 5.98E-82 I-133 CI 2.36E-81 1.99E-81 I-135 CI 8.38E-82 7.55E-82 TOTAL FOR PERIOD CI 4.59E-81 5.12E-H1

3. PARTICULATE CS-137 CI S.SSE-81 8.64E-87 TOTAL FOR PERIOD CI S.SSE-81 8.64E-87

17 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 NUCLIDES RELEASED UNIT QUARTER 01 QUARTER 02 A. FISSION AND ACTIVATION GASES

1. TOTAL RELEASE CI 4.63E 83 4.28E 82

2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 5.96E 82 5.34E 81 B. IODINES

1. TOTAL IODINE-131 CI 1.28E-82 5.28E-83

2. AVERAGE RELZASE RATE FOR PERIOD UCI/SEC 1.65E-83 6.61E-84 C. PARTICULATES

1. PARTICULATES T-1/2 > 8 DAYS CI 2.44E-85 1.28E-84

2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 3.13E-86 1.53E-85

3. GROSS ALPHA RADIOACTIVITY CI 2 '4E-87 3.14E-87 D. TRITIUM

1. TOTAL RELEASE CI 6.47E 88 4.14E 88

2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 8.32E-81 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 CONTINUOUS MODE BATCH MODE RELEASED UNIT QTR. ¹1 QTR. ¹2 QTR.¹1 QTR.¹2

1. NOBLE GASES AR-41 CI 8.98E 88 8. SHE-'81 1.43E 88 7.75E-81 KR-85 CI 8. SSE-81 8. SSE-81 1.57E-81 1.89E-81 KR-85M CI 1.13E 82 2.98E 88 5.43E-81 1.94E-82 KR-87 CI 4.15E Si S.SSE-81 2.76E-82 S.SHE-81 KR-88 CI 1.46E 82 2.14E 88 3.42E-81'.42E 2.18E-82 XE-131M CI 6.18E 81 S.SSE-81 88 6.89E-82 XE-133 CI 3.22E 83 3.68E 82 1.78E 82 1.35E 81 XE-133M CI S.SHE-81 S.SSE-81 2 '6E 88 1.68E-Sl XE-135 CI 8.57E 82 3.99E 81 9.85E 88 3.67E-81 TOTAL FOR PERIOD CI 4.45E 83 4.85E 82 1.85E 82 1.5HE 81

2. IODINE I-131 CI 1. 28E-82 5. 28E-83 I-133 CI 2. 52E-82 3. 31E-83 TOTAL FOR PERIOD CI 3.88E-82 . 8.51E-83 3 ~ PARTICULATE CO-57 CI 4.46E-86 S.SHE-81 CO-58 CI S.SSE-81 1.2HE-84 CS-137 CI 1.99E-85 S.SHE-81 TOTAL FOR PERIOD CI 2.44E-85 1.28E-84

19 FLORIDA POWER AND LIGHT COMPANY ST. LUCIE PLANT SEMIANNUAL REPORT JANUARY lg 1986 THROUGH JUNE 30, 1986 UNITs 1 s 2, TABLE 3.9 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 M3 1.80E+1 Filters Ci 1.98E+3 2.0E+1

b. Dry Compressible Waste M3 2.17E+2 Ci 7.90E+0 2.0E+1

c. Irradiated Components M3 Ci N/A

d. Other M3 Ci N/A

2. Estimate of Major Nuclide Composition (by type of waste)

a. Co 58 39.9 Cs 137 27.2 Cs 134 25.1 Co 60 4.4 Mn 54 1.0

b. Co 60 23.5 Cr 51 3.2 Cs 137 17.0 Ni 63 2.6 C 14 12.1 Nb 95 2.5 Cs 134 12.0 H 3 1.9 Fe 55 10.4 Mn 54 1.6 Co 58 9.2 Zr 95 1.5

3. 'olid Waste Disposition Mode of Destination Number of Shi ments Trans ortation 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)

(Note 1) (Notes 1 & 2) (Note 3) (Note 4)

HASTE TOTAL TOTAL PRINCIPAL TYPE OF R.G.1.21 TYPE OF SOLIDIFICATION OE CLASSIFICATION VOLUME CURIE NUCLIDES WASTE CATEGORY CONTAINER ABSORBENT AGENT CLASS A 195ft3 6.354 C14,Ni63 Pwr l.b. NRC Certified None Csl37,I129 Trash LSA > Type A CLASS A 7470ft3 1.545 NONE Pwr l.b. Non-Specification None Trash Strong Tight Pkg, CLASS B 193ft3 62.787 Ni63,Sr90, Pwr Ion- l.a. NRC Certified None Csl37,Sum of Exchange LSA > Type A Nuclides w/ Resins T4 < 5 years CLASS C 12lft '607.576 Co60,Sr90,Ni63, Pwr Ion- l.a. NRC Certified Nohe Cs137,Sum of Exchange Type B Nuclides w/ Resins T4 < 5 years, C14 CLASS C 119ft 37.984 Co60, Csl37, Ni63, Pwr l.a. NRC Certified None Sr90, Sum of Process Type B Nuclides w/ Filters T9 < 5 years, I129-CLASS C 202ft3 271.738 Co60,Ni63,Sr90, Pwr Ion- l.a. NRC Certified None I129,Cs137, Exchange LSA > Type A Sum of Nuclides Resins w/TQ < 5 years

21 FLORIDA POWER Bc LIGHT COMPANY ST. LUCIE PLANT SEMIANNUALREPORT 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: minutes

3. %wham time period for a batch release: minutes

4. Average time period for a batch release: minutes

5. Mhdrnm time period for a batch release: minutes

6. Average dilution strean flow during the period (see Note 1 on 'Ihble 3.3):

All liquid releases are sumnarized in tables B. Gaseous

1. Number of batch releases:

2. Total the period for batch releases: minutes

3. Radram time period for a.batch release: minutes

4. Average the period for batch releases: minutes

5. Mirdmn time pertod for a batch release: minutes All gaseous waste releases are sunnarized in tables

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: Curie s C. See attachnents (if applicable) for:

A description of the event ard equipnent involved.

2t Cause(s) for the mplanned release.

3t Actions taken to prevent a recurrence 4, (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 KIAK E E B. Trittun

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.

Page 81 of 84 ST UCIE PLANT CHEMISTRY OPERATING E'aiuCEDURE NO. C-200, REVI'SIOn 6 OFFSITE DOSE CALCULATION MANUAL (ODCH)

APPBBIX E RADIOIlGICAL BVIRONINIALSURVEILIANCE Si.'. uJCIE HANf Key to Sarrple Locations APPROXIMATE SAMPLE DISMASK rXLUZHB (miles)

Food Products Ocean side vicinity of St. Lucia Plant 'rustacea SemL-Annually E ESE (NKE 1) Fish Semi-Annually Food Paxhcts Offsite aar orth pmperty line Breed leaf monthly vegetatt.on (when avaQable)

(rrangmve)

Offsite near south pmperty line Brrnd leaf Monthly vegetatirn (whn avai3able)

(rrangmve)

Food Products Near srnth end of HutcIriruxn Island Grus tacea Semi-Anrru ally 10-20 S SSE Fish Semi-AnnuQly Bread leaf deathly vegetation (rrangmve)

It is the policy of Flori& Pmer & Light Crgpany (FPL) that the St. Lucie 1 & 2 Radio1ogical Ehvirienral Monitoring Pmgrams NKE 1 are onducted by the State of Florida Deparurent of Health and Ihese sarry1es rray be collected from or supplenented by Rehabilitative Services (DHRS), pursuant to an Agreerrent between san@les collected fmm the plant intake aual if the required FPL snd I3RS and; tlat mmrdinaticn of th. Radiological analyses are urable to be perforrred due to uravailability or Fnvirrnrrental Honitoring Pmgrarns with EHRS and corrpliance with tb iradequate quantity of sample fmm the oem side location.

Radiological Fnviraurental Hcnitoring Pmgram TecInical Specificaticns are tIa responsibility of the Nuclear Energy Services Departrrent.

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 fication 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 Attachment cc: Dr. J. Nelson Grace, Regional Administrator, Region II, USNRC R. J. Crlenjak, Senior Resident Inspector, USNRC, St. Lucie Plant I I an FPL Group company GRM5/0IO/I