ML17348A516

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Semiannual Radioactive Effluent Release Rept,Jan-June 1990. W/900827 Ltr
ML17348A516
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 06/30/1990
From: Harris K, Quinn S, Steinke R
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-90-305, NUDOCS 9008310222
Download: ML17348A516 (28)
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P.. Box 029100, Miami, FL, 33102-9100 AUg 2 7 $ 990 L-90-305 10 CFR 50.36(a)(2)

Tech. Spec. 6.9.4.

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. CD 20555 Gentlemen:

Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Semi-Annual Radioactive Effluent Release Re ort Attached is the Radioactive Effluent Release Report for the period of January 1, 1990, through June 30, 1990, for Turkey Point Units 3 and 4, as required by Technical Specification 6.9.4. and 10 CFR 50.36(a) (2) .

Should there be any questions regarding this information, please contact us.

Very truly yours, K. N Harris Vice resident Turkey Point Nuclear KNH/DPS/dps Attachment cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspectorr USNRCr Turkey Point Plant 9008310222 900630 PDR ADOCK 05000250 R PDC an FPL Group company Qr (

TURKEY POINT NUCLEAR PLANT UNITS 3 AND 4 SEMIANNUALRADIOACTIVE EFFLUENT Rf LEASE REPORT JANUARY t 990 THROUGH JUNE 1990 SUBMITTED BY NUCLEAR CHEMISTRY DEPARTMENT TURKEYPOINT NUCLEAR PLANT FLORIDA POWER 8 LIGHT COMPANY

~ ulnn R.. tein e Radiochemist Chemistry Supervisor V.A. amiens as L. W. Pearce Operations Superintend nt Plant Manager-Nuclear

INDEX

!. ~ C PAGE 1.0 Regulatory Limits 1.1 Liquid Ef fluents . ~ ~ ~ . ~ ~ ~ ~.............................. 1 1.2 Gaseous Effluents ...................................... 1 2.0 Maximum Permissable Concentrations ............................ 1 3 .0 Average Energy ............................................ 1 4.0 Measurements and Approximation of Total Radioactivity 4.1 Liquid Effluents - Discussion .............................. 2

a. Unit Liquid Effluents Summation .....................

3 5

b. Unit Liquid Effluents Summation ....................

4 11 4.2 Gaseous Effluents - Discussion ............................. 2

a. Unit Gaseous Effluent Summation .....................

3 8

b. Unit Gaseous Effluent Summation ....................

4 14 4.3 Estimate of Errors ..................................... 3 5.0 Batch Releases O~

5 .1

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Liquid ~ ~ ~ ~ ~ ~ ii ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ i ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3 5~2 Gaseous ............................................. 3 6.0 Unplanned Releases ......................................... 4 V.O Reactor Coolant Activity ..................................... 4 8.0 Site Radiation Dose ......................................... 4 9.0 Offsite Dose Calculation Manual Revisions ......................... 4 10.0 Solid Waste and Irradiated Puel Shipments ......................... 4 11.0 Process Control Program Revisions .............................. 4

FLORIDA POWER R LIGHT COMPANY TURKEY POINT UNITS 3 AND 4 EFFI VENT AND WASTE DISPOSAL SEMIANNUALREPORT SUPPLEMENTAL INFORMATION JANUARY 1990 THROUGH JUNE 1990 1.0 Re lato Limits 1.1 Li uid Effluents a) The concentration of radioactive material released in liquid effluents to unrestricted areas shall not exceed the concentrations specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall not exceed 2 x 10-4 pCi/ml.

b) The dose or dose commitment per reactor to a member of the public from any radioactive materials in liquid effluent released to unrestricted areas shall be limited, during any calendar quarter, to s1.5 mrem to the total body and to s 5 mrem to any organ, and, during any calendar year, to s3 mrem to the total body and s10 mrem to any organ.

1.2 Gaseous Effluents a) The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following.

Less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin due to noble gases and less than or equal to 1500 mrem/yr to any organ due to I-131, I-133, tritium and for all radioactive materials in particulate form with half lives greater than 8 days.

b) The air dose per reactor to areas at and beyond the site boundary due to noble gases released in gaseous effluents shall be limited, during any calendar quarter, to s5 mrad for gamma radiation and s10 mrad for beta radiation and, during any calendar year, to s10 mrad for gamma radiation and s20 mrad for beta radiation.

c) The dose per reactor to a member of the public, due to I-131, I-133, tritium and to particulates with half-lives greater than 8 days in airborne effluents released to areas at and beyond the site boundary shall not exceed 7.5 mrem to any organ during any calendar quarter and shall not exceed 15 mrem to any organ during any calendar year.

2.0 Maximum Permissible Concentrations Water: As per 10CFR20 Part 20, 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.

3.0 The average energy of fission and activation gases in gaseous effluents is not applicable.

CHKll llew@:DAB

01/90 - 06/90 4.0 ~

Measurements and roximations of Total Radioactivi

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All liquid and airborne discharges to the environment during this reporting period were analyzed in accordance with Technical Specification requirements. The minimum frequency of analysis as required by Regulatory Guide 1.21 was met or exceeded.

Where alpha, tritium and named nuclides are shown as - curies, this should be interpreted as "no activity was detected on the samples using the Plant Technical Specification analyses techniques to achieve required Lower Level of Detection (LLD) sensitivity for radioactive effluents".

4.1 Li uid Effluents Aliquots of representative pre-release samples were isotopically analyzed for gamma emitting isotopes on a multichannel analyzer.

The above procedure was followed for all releases from the waste disposal system. Frequent periodic sampling and analysis were used to conservatively determine if any radioactivity was being released via the steam generator blowdown system and the storm drain system.

Monthly and quarterly composite samples for the waste disposal system were prepared to give proportional weight to each liquid release made during the designated period of accumulation. The monthly composite was analyzed for tritium and gross alpha activity. Tritium was determined by use of liquid scintillation techniques and gross alpha radioactivity was determined by use of a 2a gas flow proportional counter. The quarterly composite was analyzed for Sr-89/90 and Fe-55 by chemical separation.

All radioactivity concentrations determined from analysis of a pre-release composite were multiplied by the total represented volume of the liquid waste released to determine the total quantity of each isotope and of gross alpha activity released during the compositing period.

Aliquots of representative pre-release samples from the waste disposal system were analyzed on a per release basis for dissolved fission and activation gases by use of gamma spectrum analysis. The resulting isotope concentrations were multiplied by the total volume released in order to estimate the total dissolved gases released.

The liquid waste treatment system is shared by both units at the site and generally all liquid releases are allocated on a 50/50 basis to each unit.

4.2 Gaseous Effluents Airborne releases to the atmosphere occurred from: release of gas decay tanks, the instrument bleedline, containment purges, and releases incidental to operation of the plant. The techniques employed in determining the radioactivity in airborne releases are:

a) Gamma spectrum analysis for fission and activation gases, b) Removal of particulate material by filtration and subsequent gamma-spectrum analysis, Sr-89/90 determination and gross alpha analysis, c) Absorption of halogen radionuclides on a charcoal filter and subsequent gamma-spectrum analysis, and d) Analysis of water vapor in a gas sample for tritium using liquid scintillation techniques.

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All t

gas releases 01/90 - 06/90 from the plant which were not accounted for by the above methods were conservatively estimated as curies of Xe-133 by use of the SPING 4 Radiation Monitor and the plant vent process monitor recorder chart and the current calibration curve for the monitor.

Portions of the gas waste treatment system are shared by both units and generally all gas releases from the shared system are allocated on a 50/50 basis to each unit.

Meteorological data for the period January, 1990 to June, 1990, in the form of Joint Frequency Distribution Tables is maintained on-site.

4.3 Estimate of'rrors a) Sampling Error The error associated with volume measurement devices, flow measuring devices, etc., based on calibration data and design tolerances has been conservatively estimated to be collectively less than 2 1096.

b) Analytical Error Our quarterly Q.C. cross-check program involves counting unknown samples provided by an independent external lab. The errors associated with our analysis of these unknown samples, and reported to us by the independent lab, were used as the basis for deriving the following analytical error terms.

Nuclide Maximum Error Liquid k5 211 Gaseous ill 212 5.0 BATCH RELEASES 5.1 Llhtuid Unit 3 Unit 4 a) Number of batch releases 2.35 E+02 2.35 E+02 b) Total time period of batch releases 1.92 E+04 1.92 E+04 Minutes c) Maximum time period for a batch releases 1.60 E+02 1.60 E+02 Minutes d) Average time period for a batch release 8.1V E+01 8.1V E+01 Minutes e) Minimum time period for a batch release 6.00 E+00 6.00 E+00 Minutes f) Average stream flow during period of 1.15 E+06 1.15 E+06 GPM release of effluent into a flowing stream 5.2 Gaseous a) Number of batch releases 3.50 E+01 3.10 E+01 b) Total time period of batch releases 2.93 E+03 1.9V E+03 Minutes c) Maximum time period for a batch release 2.40 E+02 2.40 E+02 Minutes d) Average time period for a batch release 8.3V E+01 6.36 E+01 Minutes e) Minimum time period for a batch release 1.50 E+01 1.50 E+01 Minutes CHEM l9QO: DiiJ 01/90 - 06/90 6.0 . Un lanned Releases 6.1 Liciuid UNIT 3 UNIT 4 a) Number of releases 0 b) Total activity released 0 Curies 6.2 Gaseous a) Number of releases 0 b) Total activity released 0 Curies 6.3 See Attachment (if applicable) for:

a) A description of the event and equipment involved.

b) Cause(s) for the unplanned release.

V.O Reactor Coolant Activi V.l Unit 3 Reactor Coolant Activity exceeded the 1.0 pCi/gm Dose Equivalent I-131 limit for 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> during February, 1990. The 100/E-Bar limit was not exceeded. See Attachment 1.

7.2 Unit 4 Reactor Coolant Activity limits of 100/E and 1.0 pCi/gm Dose Equivalent I-131 were not exceeded.

8.0 Site Radiation Dose The assessment of radiation dose from radioactive effluents to the general public due to their activities inside the site boundry is part of the Year Ending Semiannual Report.

9.0 Offsite Dose Calculation Manual ODCM There were no ODCM revisions during this reporting period.

10.0 Solid Waste and Irradiated Fuel Shi ments No irradiated fuel shipments were made from the site. Common solid waste from Turkey Point Units 3 and 4 were shipped jointly. A sumation of these shipments is given in Table 5 of this report.

11.0 Process Control P m Revisions See Attachment 2.

CHEN t990:DAJ FIBIDA POWER R LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1990 THROUGH JUNE 1990 UNIT 3 TABLE 1 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Units Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release (not including tritium, gases, 5.07 E-02 al ha Ci 4.15 E-02
2. Average diluted concentration during period pCi/ml 5.11 E-10 6.10 E-10 B. Tritium
1. Total Release Ci 6.97 E + 01 9.76 E + 01
2. Average diluted concentration during period pCi/ml 7.03 E-07 1.44 E-06 C. Dissolved and Entrained Gases
1. Total Release Ci 1.48 E+ 00 1.11 E-02
2. Average diluted concentration during period pCi/ml 1 49 E-08 1.63 E-10 D. Gross Alpha Radioactivity
1. Total Release Ci <1.82 E-08* <1.87 E-08*

E. Volume of Batch Waste Released (prior to dilution) Liters 2.79 E + 06 2.37 E + 06 F. Volume of Continuous Waste Released (prior to dilution) Liters 6.25 E+ 05 G. Volume of Dilution Water Used During Period Liters 9.92 E+10 6.80 E+10

  • MDAValue in pCi/ml CIIElf l990:VAJ t ORIDA POWER R LIGHT COMPA~

TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1990 THROUGH JUNE 1990 UNIT 3 TABLE 2 LIQUID EFFLUENTS - SUMMATIONOF ALL RELEASES Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 Na-24 Ci 6.06 E-06 Cr-51 Ci 4.20 E-04 1.76 E-03 Mn-54 Ci 1.76 E-03 5.38 E-03 Fe-55 Ci 1.09 E-02 8.79 E-03 Co-57 Ci 9.20 E-06 Co-58 Ci 1.69 E-02 1.41 E-02 Fe-59 Ci 1.73 E-04 1.79 E-05 Co-60 Ci 7.78 E-03 7.76 E-03 SR-89 Ci Sr-90 Ci Nb-95 Ci 3.87 E-04 Zr-95 Ci 2.86 E-05 Zr-97 Ci 1.67 E-05 6.08 E-06 Mo-99 Ci 2.44 E-04 Ru-103 Ci 6.80 E-05 Ag-110 Ci 1.29 E-03 1.41 E-03 Sn-117m Ci 2.40 E-05 Sb-124 Ci 8.75 E-04 8.29 E-06 Sb-125 Ci 4.69 E-03 9.34 E-04 I-131 Ci 1.62 E-04 2.94 E-04 6.81 E-06 l-133 Ci 1.29 E-04 2.00 E-06 4.63 E-06 Cs-134 Ci 9.95 E-04 1.18 E-04 Cs-137 Ci 4.01 E-03 7.50 E-04 Unidentified Ci Total for Period Above Ci 2.91 E-04 5.04 E-02 4.15 E-02 Cl(EM l 990: DAJ P~RIDA POWER R LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1990 THROUGH JUNE 1990 UNIT 3 TABLE 2 (Continued)

LIQUID EPFLUENTS Liquid Dissolved Gas Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 Kr-85 Ci 4.07 E-03 Xe-131m Ci 6.40 E-02 4.06 E-04 Xe-133 Ci 1.14 E-04 1.41 E + 00 6.43 E-03 Xe-133m Ci 3.60 E-03 Xe-135 Ci 9.84 E-05 1.70 E-04 Xe-135m Ci 2.06 E-06 Total for Period Above Ci 1.14 E-04 1.48 E + 00 1.11 E-02 CHSN l990:DAd RIDA POWER R LIGHT COMPAN~

TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1990 THROUGH JUNE 1990 UNIT 3 TABLE 3 GAS EFFLUENTS - SUMMATION OF ALL RELEASES Units Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release Ci 4.27 E + 02 9.55 E + 01
2. Average Release Rate for Period pCi/sec 5.49 *E+01 1.22 E+01 B. lodines
1. Total iodine-131 Ci 4.26 E-03 3.07 E-05
2. Average Release Rate for Period pCi/sec 5.48 E-04 3.91 E-06 C. Particulates
1. Particulates T-1/2>8 Days Ci 4.47 E-05 4.90 E-05
2. Average Release Rate for Period pCi/sec 5.75 E-06 6.23 E-06
3. Gross Alpha Radioactvity Ci <4.65 E-16* <6.94 E-16*

D.. Tritium

1. Total Release Ci 1.72 E+ 01 1.09 E+ 01
2. Average Release Rate for Period pCi/sec 2.21 E+00 1.39 E+ 00
  • <MDA Values Expressed in pCi/ml CHEM lSlO:DAJ RIDA POWER R LIGHT COMPAN~

TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1990 THROUGH JUNE 1990 UNIT 3 TABLE 4 GASEOUS EFPLUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission Gases Ar-41 Ci 1.38 E-01 4.41 E-02 1.26 E-01 Kr-85 Ci 8.81 E-01 4.23 E + 00 3.56 E-01 Kr-85m Ci 2.03 E-03 4.63 E-04 1.63 E-02 4.28 E-05 Kr-87 Ci 9.89 E-04 Xe-131m Ci 2.98 E-01 1.80 E + 00 1.49 E-01 Xe-133 Ci 3.29 E + 02 8.63 E+ 01 8.56 E+ 01 8.46 E + 00 Xe-133m Ci 6.37 E-02 6.31 E-01 7.76 E-02 Xe-135 Ci 3.55 E+ 00 7.01 E-03 3.17 E-01 1.06 E-02 Xe-135m Ci 2.35 E-03 3.30 E-02 Total for Ci Period Above 3.34 E+ 02 8.64 E + 01 9.28 E + 01 9.05 E + 00
2. lodines l-131 Ci 4.24 E-03 3.07 E-05 1-133 Ci 1.29 E-04 2.30 E-05 Ci Total for Ci Period Above 4.37 E-03 5.37 E-05 P RIDA POWER 8 LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1990 THROUGH JUNE 1990 UNIT 3 TABLE 4 (Continued)

GASEOUS EPFLUENTS Continuous Mode Nuclides Released Units Quarter 1 Quarter 2

3. Particulates Co-58 Ci 3.74 E-06 4.43 E-06 Co-60 Ci 3.60 E-06 4.04 E-05 I-131 Ci 1.82 E-05 I-133 Ci 6.80 E-06 Cs-134 Ci 3.91 E-06 Cs-136 Ci 9.80 E-07 Cs-137 Ci 6.70 E-06 4.15 E-06 RU-103 Ci 7.68 E-07 Total for Period Above Ci 4.47 E-05 4.90 E-05 CHEM l 990:DAJ ORIDA POWER R LIGHT COMP TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1990 THROUGH JUNE 1990 UNIT 4 TABLE 1 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Units Quarter 1 Quarter A. Fission and Activation Products
1. Total Release (not including tritium, gases, Ci 5.06 E-02 4.15 E-02 al ha
2. Average diluted concentration during period pCi/ml 5.10 E-10 6.10 E-10 B. Tritium
1. Total Release Ci 6.97 E + 01 9.76 E + 01
2. Average diluted concentration during period pCi/ml 7.03 E-07 1.44 E-06 C. Dissolved and Entrained Gases
1. Total Release Ci 1.48 E + 00 1.11 E-02
2. Average diluted concentration during period pCi/ml 1.49 E-08 1.63 E-10 D. Gross Alpha Radioactivity
1. Total Release Ci (1.82 E-08* (1.87 E-08*

E. Volume of Batch Waste Released (prior to dilution) Liters 2.79 E+06 2.37 E+06 F. Volume of Continuous Waste Released (prior to dilution) Liters G. Volume of Dilution Water Used During Period Liters 9.92 E + 10 6.80 E + 10

  • MDAValue in pCi/ml CHEM f990:OAl

i ORIDA POWER @LIGHT COMPAN~

TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1990 THROUGH JUNE 1990 UNIT 4 TABLE 2 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 Na-24 Ci 6.06 E-06 Cr-51 Ci 4.20 E-04 1.76 E-03 Mn-54 Ci 1.76 E-03 5.38 E-03 Fe-55 Ci 1.09 E-02 8.79 E-03 Co-57 Ci 9.20 E-06 Co-58 Ci 1.69 E-02 1.41 E-02 Fe-59 Ci 1.73 E-04 1.79 E-05 Co-60 Ci 7.78 E-03 7.76 E-03 Sr-89 Ci Sr-90 Ci Nb-95 Ci 3.87 E-04 Zr-95 Ci 2.86 E-05 Zr-97 Ci 1.67 E-05 6.08 E-06 Mo-99 Ci 2.44 E-04 Ru-103 Ci 6.80 E-05 Ag-110 Ci 1.29 E-03 1.41 E-03 Sn-117m Ci 2.40 E-05 Sb-124 Ci 8.75 E-04 8.29 E-06 Sb-125 Ci 4.69 E-03 9.34 E-04 I-131 Ci 2.94 E-04 6.81 E-06 I-133 Ci 2.00 E-06 4.63 E-06 Cs-134 Ci 9.95 E-04 1.18 E-04 Cs-137 Ci 4.01 E-03 7.50 E-04 La-140 Ci 4.64 E-05 Np-239 Ci 5.60 E-05 Unidentified Ci Total for Period Above Ci 5.06 E-02 4.15 E-02 CHfM 19%K'OAI ORIDA POWER R LIGHT COMPAN~

TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1990 THROUGH JUNE 1990 UNIT 4 TABLE 2 (Continued)

LIQUID EFFLUENTS Liquid Dissolved Gas Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 Kr-85 Ci 4.07 E-03 Xe-131m Ci 6.40 E-02 4.06 E-04 Xe-133 Ci 1.41 E + 00 6.43 E-03 Xe-133m Ci 3.60 E-03 Xe-135 Ci 9.84 E-05 1.70 E-04 Xe-135m Ci 2.06 E-06 Total for Period Above Ci 1.48 E + 00 1.11 E-02 CHEM 1990: DAI FLORIDA POWER R LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT A

JANUARY 1990 THROUGH JUNE 1990 UNIT 4 TABLE 3 GAS EFFLUENTS SUMMATIONOF ALL RELEASES Units Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release Ci 3.57 E + 02 6.65 E + 01
2. Average Release Rate for Period pCi/sec 4.59 E + 01 8.46 E+ 00 B. lodines
1. Total iodine-131 Ci 1.55 E-03 1.35 E-05
2. Average Release Rate for Period pCi%ec 1.99 E-04 1.72 E-06 C. Particulates
1. Particulates T-1/2)8 Days Ci 2.51 E-05 4.90 E-05
2. Average Release Rate for Period .pCi/sec 3.23 E-06 6.23 E-06
3. Gross Alpha Radioactvity Ci (4.65 E-16* (6.94 E-16*

D. Tritium

1. Total Release Ci 1.31 E+ 01 7.56 E + 00
2. Average Release Rate for Period pCi/sec 1.68 E+00 9.62 E-01
  • MDAValues Expressed in pCi/ml CHfM 1990:DAI 3?LORIDA POWER R LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT

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JANUARY 1990 THROUGH JUNE 1990 UNIT 4 TABLE 4 GASEOUS EFPLUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 1 ~ Fission Gases Ar-41 Ci 2.46 E-01 1.53 E-01 1.04 E-01 7.22 E-02 Kr-85 Ci 2 74 E+00 3.56 E-01 Kr-85m Ci 2.06 E-03 5.52 E-03 6.98 E-04 4.28 E-05 Kr-87 Ci 9.91 E-04 Xe-131m Ci 1.78 E-01 8.57 E-02 9.69 E-01 1.91 E-01 Xe-133 Ci 3.20 f + 02 5.00 f + 01 2 92 E+01 1.53 E + 01 Xe-133m Ci 9.41 E-02 5.11 E-02 6.77 E-02 1.47 E-01 Xe-135 Ci 3.56 E + 00 9.86 E-02 4.64 E-02 5.80 E-02 Xe-135m Ci 3.30 E-02 Total for Period Above Ci 3.24 E+ 02 5.04 E+ 01 3.32 E+ 01 1.61 E+ 01

2. lodines I-131 Ci 1.54 E-03 1.35 E-05 l-133 Ci 1.21 E-04 2.30 E-05 Total for Period Above Ci 1.66 E-03 3 65 f-05 CHEM f 990: OAI FLORIDA POWER R LIGHT COMPANY 1 S J TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1990 THROUGH JUNE 1990 UNIT 4 TABLE 4 (Continued)

GASEOUS EFFLUENTS Continuous Mode Nuclides Released Units Quarter 1 Quarter 2

3. Particulates Co-58 Ci 3.29 E-06 4.43 'E-06 Co-60 Ci 3.60 E-06 4.04 E-05 l-131 Ci 6.09 E-06 Cs-134 Ci 3.91 E-06 Cs-136 Ci 9.80 E-07 Cs-137 Ci 6.70 E-06 4.15 E-06 Ru-103 Ci 5.35 E-07 Total for Period Above Ci 2.51 E-05 4.90 E-05

< MDA Values Expressed in pCi/ml CHEM f990: OAI FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JANUARY 1990 THROUGH JUNE 1990 UNITS 3 AND 4 TABLE 5 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS" A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL

1. TYPE OF WASTE UNIT 6 MONTH PERIOD ~oERR Spent resin, filters m 9.57 EO sludge, evaporator bottoms Ci 2.96 E2 20
b. Dry Compressible waste m 1. 08 E2 (note 1) Ci 7. 15 E-1 20 c ~ Irradiated components 0.00 EO Control rods, etc. 0.00 EO

/i d Other non-compressible m 1.75 E1 Waste (Note 2) Ci 2.47 E-1 20 2 ~ ESTIMATE OF MAJOR NUCLIDE COMPOSITION BY TYPE-OF WASTE a ~ Co-60 69 Ni-63 20 Cs-137 4 Fe-55 3 Co-58 2 Cs-134 1

b. Co-60 44 Co-58 27 Fe-55 13 Ni-63 8 Cr-51 4 I-131 2 Cs-137 2 c ~
d. Cs-137 51 Co-60 0 37 Ni-63 >o 6 Fe-55 ~O 0 4 Co-58 1 Cs-134 9. 1

Page 2

3. SOLID WASTE DISPOSITION NUMBER OF SHIPMENTS MODE OF TRANSPORT DESTINATION 13 (Note 3) Sole use truck Oak Ridge, TN 2 Sole use truck Barnwell, SC B. IRRADIATED FUEL SHIPMENTS None RKR/eb/055

FLORIDA POWER 8 LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JANUARY 1990 THROUGH JUNE 1990 UNITS 3 & 4 TABLE 5 SOLID WASTE SUPPLEMENT (HOTE 4) (NOTE 5) (NOTE 6) (NOTE 7)

Total Total Principal Type of R.G. 1 '1 Type of Solidification Waste Volune Curie Radionvclides Waste Category Container or Absorbent Classification Ft3 Quantity Agent Class A 4431.9 0.96 None Compactable 1.b,d Strong, H/A and Non- Tight Compactable Package Trash Class A 202.1 2.03 Hone Dewatered Bead 1.a Cask N/A Resin >Type A LSA Class B 135.8 294 Co-60, Cs-137 Dewatered Bead 1.a Cask N/A Ni-63, Sr-90 Resin >Type A LSA RKR/eb/056

FLORZDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JANUARY 1990 THROUGH JUNE 1990 UNITS 3 AND 4 TABLE 5 SOLID WASTE AND ZRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPMENT OFFSITE FOR BURIAL OR DISPOSAL Note 1: Dry compressible waste volume indicates volume shipped to burial site following reduction by a waste processing facility. Volume shipped to the waste processing facility was 906.2 m .

Note 2: Other noncompressible waste indicates volume shipped to burial site following decontamination and volume reduction by a waste processing facility. Volume shipped to the waste processing facility was 0.0 m .

Note 3: Material transported to Oak Ridge, Tennessee, was consigned to licensed processing facilities for volume reduction and decontamination activities. The material remaining after processing was transported by the processor to Barnwell, South Carolina, for burial.

Note 4: The total curie quantity and radionuclide composition of solid waste shipped from the Turkey Point Plant Units 3 and 4 are determined using a combination of qualitative and quantitive techniques. The Turkey Point Plant follows the guidelines in the Low Level Waste Licensing Branch Technical Position on Radioactive Waste Classification (5/11/83) for these determinations.

The most frequent used techniques for determining the total activity in a package are the dose to curie method and inference from specific activity and mass or activity concentration and volume. Activation analysis may be applied when it is appropriate. The total activity determination by any of these methods is considered to be an estimate.

Page 2 The composition of radionuclides in the waste is determined by both on-site analysis for principle gamma emitters and periodic off-site analyses for difficult to measure isotopes. The on-site analyses are performed either on a batch basis or on a routine basis using representative samples appropriate for the waste type.

Off-site analyses are used to establish scaling factors or other estimates for difficult to measure isotopes.

Note 5: Principle radionuclide refers to those radionuclides contained in the waste in concentrations greater than 0.01 times the concentration of the nuclide listed in Table 1 or 0.01 times the smallest concentration of the nuclide listed in Table 2 of 10 CFR 61.

Note 6: Type of waste is specified as described in NUREG 0782, Draft Environment Impact Statement on 10 CFR 61 "Licensing Requirements for Land Disposal of Radioactive Waste".

Note 7: Type of container refers to the transport package.

RKR/eb/057

F ORIDA POWER k LIGHT COMPAN TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1990 THROUGH JUNE 1990 n

ATTACHMENT1 7.0 Reactor Coolant Activit 7.1 Unit 7.1.1 Power, Cleanup, and Dose Equivalent Iodine 48 Hr. History Date Time DE~Ci/ml) RX. Power % Cleanu PM 1 FEB 0905 Not Performed 100 40 2 FEB 1130 5.28 E-02 100 3 FEB 0353 4.71 E-02 100 40 3 FEB 1325 6.26 E-02 100 3 FEB 2108 5.04 E-02 85 45 4 FEB 0030 8.97 E-01 90 4 FEB 0330 1.01 E+01 91 4 FEB 0600 9.39 E-01 90 4 FEB 0730 V.85 E-01 90 7.1.2 Degas History Unit 3 Reactor Coolant System was degassed from 1958, 2 FEB until 0145, 3 FEB 1990.

7.1.3 Time Duration of Dose Equivalent Iodine >1pCi/gm.

Unit 3 Dose Equivalent Iodine 131 exceeded 1.0 microcurie per gram for a period of 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

7.1.4 Batch Average Burnups PTP3, End of Cycle II (14537 MWD/MTU)

Burnup Batch MWD MTU 10D 27830 11A 36102 llB 36894 12A 347V9 12B 31079 13A 19481 13B 14851 13C 19484 13D 1896V RNSIDAJ+CIIEhf DISK III(1990)

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FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JANUARY 1990 THROUGH JUNE 1990 UNITS 3 AND 4 ATTACHMENT 2

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM During this reporting period Turkey Point. Plant awarded a contract for resin dewatering equipment, and services to Westinghouse Electric Corporation. Turkey Point Operating Procedure 11550.48, Process Control Program for Dewatering Radioactive Waste Liners, was substantially revised to eliminate all references to the previous vendor, Chem-Nuclear Systems, Inc., and incorporate applicable requirements for the new vendor's equipment and procedures. The new dewatering process is operated following procedures approved by the State of South Carolina, Department of Health and Environmental Control, Radioactive Waste Management Section, in applicable certificates of compliance for the vendor's disposal containers. Therefore, this change does not reduce the overall conformance of the dewatered waste to existing disposal site criteria for waste form and stability. The following is a detailed description of the revision.

Section 3.1, "Discussion", was revised to delete all references to Chem-Nuclear Systems, Inc. procedures and replace them with the following Westinghouse Electric Corporation procedures:

Westinghouse Radiological Services, Inc. procedure STD-D-03-009, A User's Manual for Westinghouse RADLOK-200, RADLOK-500, RADLOK-100, RADLOK-179, and RADLOK-195.

2 ~ Westinghouse Radiological Services, Inc. procedure STD-P-03-003, RADLOK Manway Assembly Closure and Sealing Procedure.

3. Westinghouse Radiological Services, Inc. procedure STD-P-03-004, Closure of Hittman RADLOK High Integrity Container Fill Port Closure Assembly.

4 ~ Westinghouse Radiological Services, Inc. procedure STD-P-03-046, Transfer and Dewatering Ion Exchange Resin and/or Activated Charcoal Filter Media Using the Hittman Rapid Dewatering System.

5. Westinghouse Radiological Services, Inc. procedure STD-P-03-052, Transfer and Dewatering Ion Exchange Resin and/or Filter Media Using the Press Pak System.
6. Westinghouse Radiological Services, Inc. procedure STD-P-03-010, Transfer and Dewatering Bead Resin in Hittman RADLOK High Integrity Containers With a Single Layer Underdrain Assembly to Less Than 14 Drainable Liquid.

Page 2

7. Westinghouse Radiological Services, Inc. procedure STD-P-03-020, RADLOK Inspection Procedure.
8. Westinghouse Radiological Services, Inc. Process Control Program STD-PCP-03-003, Westinghouse Hittman Mobile Incontainer Dewatering and Solidification Systems.

Sections 4.6 through 4.8, which listed specific container model numbers allowable for disposal of each dewatered resin waste stream, were replaced with new Sections 4.6 through 4.10, which specify the minimum disposal container requirements for each waste stream.

Section 6.1, "References", was revised to delete all Chem-Nuclear Systems, Inc. procedures and replace them references to with the following Westinghouse Electric Corporation procedures 1 ~ Westinghouse Radiological Services, Inc. procedure STD-D-03-009, A User's Manual for Westinghouse RADLOK-200, RADLOK-500, RADLOK-100, RADLOK-179, and RADLOK-195.

2 ~ Westinghouse Radiological Services, Inc. procedure STD-P-03-003, RADLOK Manway Assembly Closure and Sealing Procedure.

3 ~ Westinghouse Radiological Services, Inc. procedure STD-P-03-004, Closure of Hittman RADLOK High Integrity Container Fill Port Closure Assembly.

4 ~ Westinghouse Radiological Services, Inc. procedure STD-P-03-046, Transfer and Dewatering Ion Exchange Resin and/or Activated Charcoal Filter Media Using the Hittman Rapid Dewatering System.

5. Westinghouse Radiological Services, Inc. procedure STD-P-03-052, Transfer and Dewatering Ion Exchange Resin and/or Filter Media Using the Press Pak System.
6. Westinghouse Radiological Services, Inc. procedure STD-P-03-010, Transfer and Dewatering Bead Resin in Hittman RADLOK High Integrity Containers With a Single Layer Underdrain Assembly to Less Than 14 Drainable Liquid.
7. Westinghouse Radiological Services, Inc. procedure STD-P-03-020, RADLOK Inspection Procedure.

8; Westinghouse Radiological Services, Inc. Process Control Program STD-PCP-03-003, Westinghouse Hittman Mobile Incontainer Dewatering and Solidification Systems.

Page 3 Section 7.3 was revised to eliminate records that are no longer applicable or are generated in the new vendor procedures.

Section 8.4 was revised to replace the requirements for use of Chem-Nuclear Systems, Inc. equipment and procedures with Westinghouse Electric Corporation equipment and procedures.

Section 8.5 was deleted.

Section 8.6 was renumbered to 8.5 Section 8.7 was deleted.

Section 8.8 was renumbered to Section 8.6 and revised to replace the requirements for use of Chem-Nuclear Systems, Inc. equipment and procedures with Westinghouse Electric Corporation equipment and procedures.

RKR/eb/059

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