ML17342A198

Semiannual Radioactive Effluent Release Rept,Jan-June 1985. W/850830 Ltr

ML17342A198
Person / Time
Site:	Turkey Point
Issue date:	06/30/1985
From:	Williams J FLORIDA POWER & LIGHT CO.
To:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
L-85-338, NUDOCS 8509200058
Download: ML17342A198 (47)

Text

TURKEY POINT PLANT UNITS 3 AND 4 SEMIANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1985 - JUNE 1985 SUBMITTED BY NUCLEAR CHEMISTRY DEPARTMENT TURKEY POINT PLANT FLORIDA POWER AND LIGHT COMPANY DISTRIBUTION J.L. DANEK A.J. GOULD (3)

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FLORIDA POWER AND LIGHT COMPANY TURKEY POINT UNITS 3 AND 4 EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT SUPPLEMENTAL INFORMATION JANUARY 1985 THROUGH JUNE 1985 1.0 Re ulator Limits a) The concentration of radioactive material released in liquid effluents to unrestricted areas shall not exceed the concentrations specified in 10CFR20, Appendix 8, 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 10-4pCi/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 <1.5 mrem to the total body and to <5 mrem to any organ, and, during any calendar year, to <3 mrem to the total body and <10 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-1>l, 1-133, 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 <5 mrad for gamma radiation and <10 mrad for beta radiation and, during any calendar year, to <10 mrad for gamma radiation and <20 mrad for beta radiation.

c) The dose per reactor to a member of the public, due to I-151, I-l>5, 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.

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o1/s5 - o6/s5 2.0, Maximum Permissible Concentrations The maximum permissible concentrations for liquid and airborne releases are described in Sections 1.1-a and 1.2-a of this report.

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

4.0 Measurements and A roximations of Total Radioactivit 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.

Aliquots of representative pre-release samples were either isotopically analyzed for gamma emitting isotopes on a multichannel analyzer in conjunction with a high resolution Qe(Li) or HPGe detector, or evaporated and analyzed for gross beta-gamma activity'inn 2m gas flow proportional counter. The efficiency of the gas flow proportional counter is adjusted so that the activity determined by gross beta-gamma analysis approximates the isotopic activities determined by gamma spectrum analysis and selected beta determinations, exclusive of tritium and dissolved gases.

The above procedure was followed for all releases from the waste disposal system and for secondary system batch releases. Frequent periodic sampling and analysis were used to conservatively determine if any radioactivity was being released via the steam generator blowdown 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 2m 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 sample or 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 period.

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01/85 - 06/85 At least one representative batch of liquid effluent from the waste disposal system was analyzed monthly for dissolved fission and activation gases by use of gamma spectrum analysis. The resulting isotope concentrations were multiplied by the total volume released for the month in order to estimate the total dissolved gases released. If more than one batch of effluent was analyzed, the concentrations were weighted in an appropriate manner.

4.2 Gaseous Effluents Airborne releases to the atmosphere occurred from: release of gas decay tanks, the instrument bleedline, containment purges, and sporadic 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.

All sporadic gas releases from the plant which were not accounted for by the above methods were conservatively estimated as curies of Xe-133 by use of the plant vent process monitor recorder chart and the current calibration curve for the monitor.

4 3 Estimate of Errors 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 +10%.

b) Analytical Error Analytical error will be assessed in the january Semiannual Report.

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O1/S5 - O6/S5 5.0 BATCH RELEASES 5.1 fiuid Unit 3 Unit 4 a) Number of batch releases 2.86 E+02 2.86 E+02 b) Total time period of batch releases 2.72 E+04 2.72 E+04 Minutes c) Maximum time period for a batch release 2.00 E+02 2.00 E+02 Minutes d) Average time period for a batch release 9.51 E+Ol 9.51 E+Ol Minutes e) Minimum time period for a batch release 3.50 E+01 3.50 E+01 Minutes f) Average stream flow during periods of 1.38 E+06 1.38 E+06 GPM release of effluent into a flowing stream 5.2 Gaseous a) Number of batch releases 2.70 E+01 2.40 E+01 b) Total time period of batch releases 2.28 E+03 1.56 E+05 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 8.44 E+01 6.50 E+Ol Minutes e) Minimum time period for a batch release 3.00 E+01 3.00 E+01 Minutes 6.0 UNPLANNED RELEASES 6.1 " LicCuid a) Number of releases b) Total activity released Curies 6.2 Gaseous a) Number of releases 5.00 E-01 5.00 E-01 b) Total activity released 8.55 F+00 8.55 E+00 Curies 6.3 See attachments (if applicable) for:

a) A description of the event and equipment involved.

b) Cause(s) for the unplanned release.

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01/85 -06/85 7.0 Assessment of radiation dose from radioactive effluents to the general public due to their activities inside the site boundary is part of the January Semi Annual Report.

8.0 Offsite Dose Calculation Manual Revisions:

There were no changes to the ODCM during this reporting period.

9.0 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 0 were shipped jointly. A summation of these shipments is given in Attachment 8 of this report.

10.0 Process Control Pro ram Revisions No revisions were made during the reporting period.

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ORIDA POWER AND LIGHT COM i Y TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1985 THROUGH JUNE 1985 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, al ha)

Ci 9.62 E-02 7.95 E-02

2. Average diluted concentration during period pCi/ml 1.21 E-10 184 E-10 B. Tritium Total Release Ci 1.18 E+02 7.55 E+01

2. Average diluted concentration during period pCi/ml 4.45 E-06 7.75 E-06 C. Dissolved and Entrained Gases

1. Total Release Ci 6.75 E-02 2.21 E-01

2. Average diluted concentration during period pCi/ml 8.48 E-11 S.73 E-10 D. Gross Alpha Radioactivity

1. Total Release Ci <1.21 E-08 <9.97 F-09 E. Volume of Waste Released (prior to dilution) Liters 3.15 E+06 3.85 E+06 F. Volume of Dilution Water Used During Period Liters 7.96 E+11 5.91 E+11

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ORIDA POWER AND LIGHT COM Y TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1985 THROUGH JUNE 1985 UNIT 3 TABLE 2 LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 Ag-110m Ci 2.16 E-03 1.04 E-03 Co-57 Ci 5.00 E-06 Co-58 Ci 2 31 E-02 2.46 E-02 Co-60 Ci 2.86 E-02 9.35 E-03 Cr-51 Ci 5.85 E-03 1.05 E-02 Cs-1.34 Ci 6.75 E-04 1.46 E-03 Cs-137 Ci 1.55 E-03 4.42 E-03 Fe-55 Ci 2.77 E-02 4.98 'E-03 Fe-59 Ci 1.34 E-03 5.55 E-04 I-131 Ci 2.53 E-04 3.59 E-04 La-140 Ci 4.85 E-05 1.00 E-04 Mn-54 Ci 1.41 E-03 2.49 E-04 Mo-99/Tc-99m Ci 3 33 E-04 2.84 E-04 Na-24 Ci 1 35 E-05 Nb-95 Ci 067 E-03 1.10 E-03 Ru-103 Ci 5.00 E-04 3.17 E-04 Sb-124 Ci 2.60 E-05 4.74 E-03 Sb-125 Ci 5.70 E-04 1.47 E-02 Sn-117m Ci 1.50 E-06 Sr-89 Ci < 6.00 E-08 <1.00 E-08 Sr-90 Ci < 4.00 E-09 <3.00 E-09 Zn-65 Ci 1.62 E-04 3.75 E-05 Zr-95 Ci 4 36 E-04 4.11 E-04 Ci Ci Unidentified Ci Total for Ci 9.62 E-02 7.95 E-02 Period Above Note: () indicates less than detectable activity.

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ORIDA POWER AND LIGHT COM Y TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1985 THROUGH JUNE 1985 UNIT 3 TABLE 2 (Continued)

LIQUID EFFLUENTS Liquid Dissolved Gas Nuclides Released Units Continuous Mode Batch Mode Quarter 1 Quarter 2 Quarter 1 Quarter 2 Xe-131m Ci 1.72 E-03 Xe-133 Ci 6.65 E-02 2.17 E-01 Xe-133m Ci 5.70 E-04 1.25 E-03 Xe-135 Ci 2.23 E-04 6.05 E-04 Ci Ci Ci Total for Ci Period Above 6.75 E-02 2.21 E-01 Note: () indicates less than detectable activity.

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ORIDA POWER AND LIGHT COM Y TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1985 THROUGH JUNE 1985 UNIT 3 TABLE 3 GASEOUS EFFLUENTS - SUMMATIONOF ALL RELEASES Units Quarter 1 Quarter 2 A. Fission and Activation Gases

1. Total Release Ci 2.64 E+02 8.61 F+01

2. Average Release Rate for Period pCi/sec 5.56 E+01 1.10 E+01 B. Iodines

1. Total Iodine-131 2.14 E-03 5.96 E-04

2. Average Release Rate for Period pCi/sec 2.72 E-04 7.58 E-05 C. Particulates

1. Particulates T -1/2)8 Days Ci 1.16 E-04 5.87 E-04

2. Average Release Rate for Period pCi/sec 1.48 E-05 4.93 E-05 Gross Alpha Radioactivity Ci 8.06 E-08 l.U E-07 D. Tritium

1. Total Release Ci 8.01 E-02 1.21 E+02

2. Average Release Rate for Period pCi/sec 1.02 E-02 1.54 E+01 C8:1

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ORIDA POWER AND LIGHT COM Y TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1985 THROUGH JUNE 1985 UNIT 3 TABLE 4 GASEOUS EFFLUENTS Continuous Mode Batch Mode Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission Gases Ar-41 Ci 3.72 E-01 '.24 E-01 Kr-85 Ci 2.65 E-00 Kr-85m Ci 1.12 E-02 3.05 E-02 Kr-88 Ci 6.25 E-03 2.16 E-02 Xe-1)lm Ci 3.97 E-01 3.51 E-01 Xe-13> Ci 289 E+02 6.70 E+01 1.68 E+01 1.86 E+01 Xe-13)m Ci 438 E-02 3.58 E-01 1.15 E-01 Xe-l)5 Ci 5D5 E+00 6.95 E-OI. 983 E-02 Xe-138 Ci 7.05 E-03 Ci Ci Unidentified Ci Total for Ci 2.43 E+02 Period Above 6.70 E+01 2.14 E+01 1.91 E+01

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GASEOUS EFFLUENTS Continuous Mode Nuclides Released Units Quarter 1 Quarter 2

3. Particulates Ba-140 Ci 5.20 E-05 3.59 E-05 Ce-141 Ci 2.04 E-06 Ce-144 Ci 2.72 E-06 Co-58 Ci 4 32 E-06 1.80 E-04 Co-60 Ci 6.40 E-06 7.70 E-05 Cr-51 Ci 3.28 E-06 Cs-134 Ci 9.10 E-07 1.12 E-06 Cs-137 Ci 5.25 E-06 9.40 E-06 I-131 Ci 2.98 E-06 6.50 E-07 La-140 Ci 3.84 E-05 2.55 E-05 Mn-54 Ci 2.95 E-06 3.99 E-05 Nb-95 Ci 2.68 E-07 Ru-103 Ci 2.52 E-07 Sr-89 Ci 5.05 E-07 1.18 E-05 Sr-90 Ci 4.35 E-08 3.12 F-07 Ci Ci Ci Ci Ci Unidentified Ci Total for Ci 1.16 E-04 3.87 E-04 Period Above Note: indicates

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4 ORIDA POWER AND LIGHT COM Y TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1985 THROUGH JUNE 1985 UNIT 4 TABLE 1 LIQUID EFFLUENTS - SUMMATIONOF ALL RELEASES Units Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release(not including tritium, gases, al ha) Ci 9.62 E-02 7.95 E-02

2. Average diluted concentration during period pCi/ml 1.21 E-10 194 E-10 B. Tritium Total Release Ci 1.18 E+02 7.55 E+01

2. Average diluted concentration during period pCi/ml 4.45 E-06 7.75 E-06 C. Dissolved and Entrained Gases

1. Total Release Ci 6.75 E-02 2.21 E-01

2. Average diluted concentration during period pCi/ml 8.48 E-11 3.7S E-10 D. Gross Alpha Radioactivity

1. Total Release Ci < 1.21 E-08 < 9.97 E-09 E. Volume of Waste Released (prior to dilution) Liters 5.15 E+06 3.8F E+06 F. Volume of Dilution Water Used During Period Liters 7.96 E+11 5.91 E+11

+ MDA value in pCi/ml 0 Based on Cooling Canal Tritium Concentration C8:1

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RIDA POWER AND LIGHT CO Y TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1985 THROUGH JUNE 1985 UNIT 4 TABLE 2 LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 Ag-110m Ci 2.16 E-03 1.04 E-03 Co-57 Ci 5.00 E-06 Co-58 Ci 2.31 E-02 2.46 E-02 Co-60 Ci 2.86 E-02 9.35 E-03 Cr-51 Ci 5.85 E-03 1.05 E-02 Cs-134 Ci 6.75 E-04 1.46 E-03 Cs-137 Ci 1.55 E-03 4.42 E-03 Fe-55 Ci 2.77 E-02 4.98 E-03 Fe-59 Ci 1.34 E-03 5.55 E-04 I-131 Ci Z.53 E-04 3.59 E-04 La-140 Ci b.85 E-05 1.00 E-04 Mn-54 Ci 1.41 E-03 2.49 E-04 Mo-99/Tc-99m Ci 333 E-04 2.84 E-04 Na-24 Ci ,

1 35 E-05 Nb-95 Ci 1.67 E-03 1.10 E-03 Ru-103 Ci 5.00 E-04 3.17 E-04 Sb-124 Ci 2.60 E-05 4.74 E-03 Sb-125 Ci 5.70 E-04 1.47 E-02 Sn-117m Ci 1.50 F-06 Sr-89 Ci < 6.00 E-08 <1.00 E-08 Sr-90 Ci < 4.00 E-09 <3.00 E-09 Zn-65 Ci 1..62 E-04 3.75 E-05 Zr-95 Ci 4.36 E-04 4.11 E-04 Ci Ci Unidentified Ci Total for Ci Period Above 9.62 E-02 7.95 E-02 Note: () indicates less than detectable activity.

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LIQUID EFFLUENTS Liquid Dissolved Gas Nuclides Released Units Continuous Mode Batch Mode Quarter 1 Quarter 2 Quarter 1 Quarter 2 Xe-I.31m Ci 1.72 E-03 Xe-133 Ci 6.65 E-02 2.17 E-01 Xe-133m Ci 6.70 E-04 1.25 E-03 Xe-135 Ci Z.23 E-04 6.05 E-04 Ci Ci Ci Ci Total for Ci Period Above 6.75 E-02 2.21 E-01 Note: ( ) indicates less than detectable activity.

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i. Total Release Ci 4.79 E+02 2.74 E+02

2. Average Release Rate for Period pCi/sec 6.09 E+01 5.49 E+01 B. Iodines

1. Total iodine-151 Ci 2.14 E-03 5.04 E-04

2. Average Release Rate for Period pCi/sec 2.72 E-04 6.41 E-05 C. Particulates

1. Particulates T - 1/2)8 Days 1.16 E-04 3.87 E-04

2. Average Release Rate for Period pCi/sec 1.48 E-05 4.93 E-05 Gross Alpha Radioactivity 8.06 E-08 1.13 E-07 D. Tritium

1. Total Release Ci 1.45 E-01 7.89 E+01

2. Average Release Rate for Period pCi/sec . 1.84 E-02 1.00 E+01 C8:1

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RIDA POWER AND LIGHT CO Y TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1985 THROUGH JUNE 1985 UNIT 4 TABLE 4 GASEOUS EFFLUENTS Continuous Mode Batch Mode Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission Gases Ar-41 Ci 4.17 E-01 3.85 E-01 4.55 E-01 5.81 E-02 Kr-85 Ci 2.65 E+00 1.25 E+00 Kr-85m Ci 4.75 E-02 6.12 E-02 5.49 E-02 2.52 E-02 Kr-88 Ci 2.29 E-02 3.56 E-02 3.04 E-02 1.96 E-02 Xe-131m Ci 1.01 E+00 1.12 E+00 1.55 E+00 1.04 E+00 Xe-133 Ci 3.07 E+02 1.79 E+02 1.61 E+02 8.68 E+01 Xe-133m Ci 1.08 E+00 9.14 E-01 1 33 E+00 7.75 E-01 Xe-135 Ci 1 33 E+00 1.18 E+00 1.11 E+00 7.84 E-01 Xe-138 Ci 7.05 E-03 Ci Ci Unidentified Ci Total for

'eriod Above Ci 3.11 E+02 1.83 E+02 1.68 E+02 9.08 E+01

2. Iodines I-131 Ci 2.14- E-03 5.04 E-04 I-133 Ci 1.48 E-03 1.95 E-04 Ci Total for Ci 3.62 E-03 6.99 E-04 Period Above Note: ( ) indicates less than detectable activity.

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RIDA POWER AND LIGHT COM Y TURKEY POINT PLANT SEMIANNUALREPORT 3ANUARY 1985 THROUGH DUNE 1985 UNIT 4 TABLE 4 (Continued)

GASEOUS EFFLUENTS Continuous Mode Nuclides Released Units

3. Particulates Ba-140 Ci 5.20 E-05 3.59 E-05 Ce-141 Ci 2.04 E-06 Ce-144 Ci 2.72 E-06 Co-58 Ci 4.32 E-06 1.80 E-04 Co-60 Ci 6.40 E-06 7.70 E-05 Cr-51 Ci 3.28 E-06 Cs-l.34 Ci 9.10 E-07 1.12 E-06 Cs-137 Ci 5.25 E-06 9.40 E-06 I-131 Ci 2.98 E-06 6.50 E-07 La-140 Ci 3.84 E-05 2.55 E-05 Mn-54 Ci 2.95 E-06 3.99 E-05 Nb-95 Ci 2.68 E-07 Ru-103 Ci 2.52 E-07 Sr-89 Ci < 2.56 E-15 1.18 E-05 Sr-90 Ci 4 35 E-08 2.46 E-07 Ci Ci Ci Ci Ci Unidentified Ci Totalfor Ci 1.16 E-04 3.87 E-04 Period Above Note: ( ) indicates less than detectable activity.

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TURKEY POINT PLANT VnZTS ~ ANO O SEMIANNUALRAOIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1985 - 3JNE 1985 I

ATTACHMENTA UNPLANNED RELEASES C8:1

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ol/85 - 06/85 UNPLANNED RELEASES On 3une 28, 1985, a slight over-pressurization of the vent header system led to the lifting of a relief valve on a hold-up tank, which is part of the Chemical Volume Control System.

This resulted in the release of approximately 17.1 Ci,of gas as Xe-l33.

This represented less than 190 of the maximum permissable concentration for Xel33 at the site boundary.

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TURKEY POINT PLANT Units 3 R 0 SEMI-ANNUALEFFLUENT RELEASE REPORT (3anuary 1985 - 3une 1985)

ATTACHMENT8 SOLID RADIOACTIVE WASTE SHIPMENTS

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Florida Power E Light Co.

Turkey Point Units No. 364 Semi Annual Report Jan. 1, 1985 through June 30, 1985 II Solid Radioactive Waste Shipments A. Solid Waste Shipped Offsite for Burial 3., Type of Waste Unit 6 month period Est. Total Error 0 a., Spent Resins, filter sludges, m 51. 4 evaporator bottoms, etc. Ci 285 20 3 388. 6 b, Dry Canpressible Waste Contaminated Equip. Ci l. 73 20 c, Irradiated components, control rods, etc.

d, Other 2, Estimate of major composition (by type of waste)

" '137 60 69 6

58 6

134 3

55 Fg 2 H 1 60 b, Co55 52 Fe6 27 Ni137 9 6

134 Cs 2

3. Solid Waste Disposition Number of shipments Mode of transport Destination 26 Sole Use Truck Barnwell, S. C.

4. Irradiated Fuel Shipments Number of shipments Mode of transport Destination none

Florida Power 6 Light Co.

Turkey Point Unit Nos. 364 Semi-Annual Report Jan. 1, 1985 through June 30, 1985 (Notel)

Total Total (Notes 1,2) (Note 3) (Note 4)

Waste Volume Curie Principal Type of R. G. 1.21 Type of Solidification or Classification Ft3 ~9UBIlt1t Radionuclides Container Absorbent Agent Class A 13507 ..985 None PWR Trash l.b. Non-Spec. NA Strong, Tight Packages Class A 215 .744 None PWR Trash l.b, NRC Certified Class A 1420 13. 820 Sr Cs

'i3H PWR Ion Exchange 3.,q, LSA~Type NRC LSAF Type A A

Certified Resins Class A 168 6.967 None PWR l,a, NRC Certified Filters LSA +Type A Class A 143 . 008 None PWR Ion l. a. Non-Spec, Exchange Strong, Tight Resins Packages Class 8 84 264 241TRU PWR IOn l,a, NRC Certified Sr -

Ni Exchange LSB, P TypeA CQ60Cs 1 37 Resins

Florida Power 6 Light Co.

Turkey Point Unit Nos. 384 Semi-Annual Report Jan. 1, 1985 through June 30, 1985 Table 3.9 (Cont.)

Solid Waste Supplement Note 1: The total curie quantity and radionuclide composition of solid waste shipped from the Turkey Point Units 364 are determined using a combination of qualitative and quantitive techniques. In general, the Turkey Point Plant follows the guidelines outlined in the Low Level Waste Licensing Branch Technical Position (BTP) on Radioactive Waste Classification (5/ll/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

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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 H, 14C, 99Tc, 129I, TRU 241Pu 242Cm 63Ni Note 2: "Principal Radionuclides" refers to those radionuclides contained in the waste in concentrations greater than .Ol times the concentration of that nuclide listed in Table 1 or .Ol times the smallest concentration of that nuclide listed in Table 2 of 10CFR61.

Note 3: "Type of Waste" is generally specified as described in NUREG 0782, Draft Environmental Impact Statement on 10CFR61 "Licensing Requirements for Land Disposal of Radioactive Waste".

Note 4: "Type of Container" refers to the transport package.

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~ 2<&-0 qadi lu FLORIDA POWER & LIGHT COMPANY NAR 0 4 F86 L-85-90 Dr. J. Nelson Grace Regional Administrator, Region II U. S. Nuclear Regulatory Commission Suite 2900 101 Marietta Street NW Atlanta, Georgia 30323

Dear Dr. Grace:

Re: Turkey Point Units 3 and 4 Docket Dos. 50-250 a 5 50-251 Semi-Annual Re orts Please find attached the Radioactive Effluent Release Data Report and the Radiological Environmental Monitoring Report for the period July 1, 1984 to December 31,,1984 for Turkey Point Units 3 and 4, as required by Technical Specification 6.9.4.

Should you or your staff have any questions on this information, please contact us.

Very truly yours, J. W. Williams, Jr.

Group Vice President Nuclear Energy JWW/SAV/js Attachment cc: Director, Office of Inspection and Enforcement, USNRC Document Control Desk, USNRC Harold F. Reis,'squire P NS-LI -'85-086-1 PEOPLE... SERVING PEOPLE I