ML17342A889
| ML17342A889 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 06/30/1987 |
| From: | Woody C FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| L-87-361, NUDOCS 8709080074 | |
| Download: ML17342A889 (35) | |
Text
REGULATORY FORMATION DISTRIBUTION SY ':M (RIDS)
ACCESSION NBR: 8709080074 DOC. DATE: 87/Ob/30 NOTARIZED: NO DOCKET 0 FACIL: 50-250 Turkey Point Planti Unit 3i Florida Poujer and Light C 05000250 50-251 Turkey Point Planti Unit 4i Florida Poeer and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION WOODY'. O. Florida Power 5 Light Co.
RECIP. NAME RECIPIENT AFFILIATION
SUBJECT:
"Semiannual Radioactive Effluent Release Rept Jan-June 1987. " W/870831 1 tr..
DISTRIBUTION CODE: IE4SD COPIES .,RECEIVED: LTR TITLE: 50. 3ba(a) (2) Semiannual Effluent Release 1 ENCL Reports g SIZE:
NOTES:
RECIPIENT COPIES RECIPIENT I COP ES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 0 PD2-2 PD 5 5 MCDONALD' 1 1 INTERNAL'EOD/DOA 1 1 AEOD/DSP/TPAB 1 1 ARM TECH ADV 1 1 NRR/DEBT/PSB 1 1 NRR/ PB 4 4 NRR/PMAS/ I LRB 1 1 Q FIL 01 1 RQN2 FILE 02 1 1 DRSS/EPRPB 1 1 EXTERNAL: BNL TICHLERs J LPDR NRC PDR 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 21
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TURKEY POINT PLANT UNITS 3 AND 0 SEMIANNUALRADIOACTIVEEFFLUENT RELEASE REPORT e
JANUARY THROUGH JUNE 1987 SUBMITTED BY NUCLEAR CHEMISTRY DEPARTMENT TURKEY POINT PLANT FLORIDA POWER AND LIGHT COMPANY DISTRIBUTION J. L. DANEK R."J 'RECHETTE.
A. J. GOULD (3)
D. D. GRANDAGE E. R. LAPIERRE D. E. MEILS FILE 8709080074 870630 PDR ADOCK 05000250 R PDR C8:2
FLO A POWER AND LIGHT COMPAN TURKEY POINT UNITS 3 AND 0 EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT SUPPLEMENTAL INFORMATION 3ANUARYTHROUGH 3UNE 1987 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 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-< 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 < 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-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 < 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-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.
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~ 01/87 06/87 2.0 Maximum Permissible Concentrations The maximum permissible concentrations for liquid and airborne releases are described in Sections I.l-a and 1.2-a of this report.
The average energy of fission and activation gases in gaseous effluents is not applicable.
0.0 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 Technical Specifications was met or exceeded.
Aliquots of representative pre-release samples were either isotopically analyzed for gamma emitting isotopes on a multichannel analyzer, or evaporated and analyzed for gross beta-gamma activity in a 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.
I 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 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.
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Ol/87 06/87 At least one representative batch of liquid effluent'rom 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.'f more than one batch of effluent was analyzed, the concentrations were weighted in an appropriate manner.
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.
0.2 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.
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.
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01/87 06/87 0.3 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 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 T e Avera e Error Maximum Error Liquid +18%
Gaseous +16%
5.0 BATCH RELEASES 5.i ~Li ldd Unit 3 Unit 0 a) Number of batch releases 2.60 E+02 2.60 E+02 b) Total time period of batch releases 2.60 E+00 2.60 E+00 Minutes c) Maximum time period for a batch release 1.02 E+03 1.02 E+03 Minutes d). Average time period for a batch release 1.00 E+02 1.00 E+02 Minutes e) Minimum time period for a batch release 5.00 E+00 5.00 E+00 Minutes f) Average stream flow during periods of 1.10 E+06 1.10 E+06 GPM release of effluent into a flowing stream 5.2 Gaseous a) Number of batch releases 1.85 E+Ol 1.55 E+01 b) Total time period of batch releases 1.82 E+03 1.10 E+03 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 9.81 E+01 7.06 E+Ol Minutes e) Minimum time period for a batch release 3.00 E+01 3.00 E+Ol Minutes C8:2
Ol/S7 - 06/87 6.0 UNPLANNED RELEASES
- 6. I ~iciuid UNIT 3 UNIT 0 a) Number of releases 5.00 E-01 5.00 E-01 b) Total activity released 5.35 E-00 5.35 E-04 Curies
- 6. 2 Gaseous a) Number of releases b) Total activity released Curies 6.3- See attachments (if applicable) for:
a) A description of the event and equipment involved.
b) Cause(s) for the unplanned release.
7.0 The assessment of radiation dose from radioactive effluents to the general public due to their activities inside the site boundary is part of the Year Ending Semiannual Report.
S.O Offsite Dose Calculation Manual Revisions:
No changes were made to the ODCM during this reporting period.
9.0 Solid Waste and Irratiated 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 Table 5 of this report.
10.0 Process Control Pro ram Revisions There were no changes to the process control program during this reporting period.
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FLO A POWER AND LIGHT COMPAN TURKEY POINT PLANT SEMIANNUALREPORT.
JANUARY THROUGH JUNE 1987 UNIT 3 TABLE I LIQUID EFFLUENTS - SUMMATIONOF ALL RELEASES Units Quarter I Quarter 2 A. Fission and Activation Products I. Total Release (not including tritium, gases, Ci 1.20 E-01 1.13 E-01>>
al ha)
- 2. Average diluted concentration during period p Ci/ml 3.99 E-10 0.60 E-10 B. Tritium I. Total Release Ci 1.60 E+02 2.09 E+0 1
- 2. Average diluted concentration during period p Ci/ml 1.85 E-09 7.13 E-08 C. Dissolved and Entrained Gases I. Total Release Ci 1.65 E-01 3.20 E-02
- 2. Average diluted concentration during period p Ci/ml 5.31 E-10 1.32 E-10 D. Gross Alpha Radioactivity I. Total Release Ci < 9.78 E-09 < 7.01 E-09 E. Volume of Waste Released (prior to dilution) Liters 2.90 E+06 0.62 E+06 F. Volume of Dilution Water Used During Period Liters 3.11 E+ I I 2.06 E+ I I h Based on Cooling Canal Tritium Concentration
+ MDA value in pCI/ml C8:2
FLO A POWER AND LIGHT COMPAN TURKEY POINT PLANT SEMIANNUALREPORT 3ANUARY THROUGH 3UNE 1987 UNIT 3 TABLE 2 LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Units uarter 1 uarter 2 uarter 1 uarter 2 Ag-110m Ci 1.59 E-03 1.63 E-03 Ba-leo Ci 3.00 E-06 Co-57 Ci 2.85 E-05 6.70 E-05 Co-58 Ci 3.00 E-02 0.27 E-02 Co-60 Ci 2.08 E-02 2.06 E-02 Cr-51 Ci 1.55 E-03 2.07 E-03 Cs-130 Ci 6.90 E-00 1.73 E-03 Cs-137 Ci 2.28 E-03 6.00 E-03 Fe-55 Ci 0.91 E-02 3A0 E-02 Fe-59 Ci 6.25 E-00 8.65 E-05 I-131 Ci 0.35 E-03 2.57 E-00 I-132 Ci 1.50 E-05 I-133 Ci 2.88 E-00 La-100 Ci 1.32 E-03 3.30 E-05 Mn-50 Ci 2.08 E-03 0.06 E-00 Mo-99/Tc-99m Ci 1.09 E-03 6.00 E-06 Na-20 Ci 9.50 E-00 Nb-95 Ci 2.05 E-00 6 A5 E-00 Ru-103 Ci 0.50 E-05 6.65 E-05 Sb-120 Ci 2.52 E-00 8.25 E-05 Sb-125 Ci 5.00 E-03 6.15 E-00 Sn-117m Ci 2.50 E-06 Sr-89 Ci ( 3.6 E-08 1.06 E-03 Sr-90 Ci 3.20 E-05 1.18 E-00 Zr-95 Ci 0.05 E-05 6.65 E-05 Unidentified Ci Total for Ci 1.20 E-01 1.13 E-01 Period Above NOTE ( ) Indicates Less Than Detectable Activity
+MDA Value in p Ci/ml C8:2
FLO A POWER AND LIGHT COMPAN TURKEY POINT PLANT SEMIANNUALREPORT 3ANUARY THROUGH 3UNE 1987 UNIT 3 TABLE 2 (Continued)
LIQUID EFFLUENTS Liquid Dissolved Gas Nuclides Released Units Continuous Mode Batch Mode uarter 1 uarter 2 uarter 1 uarter 2 Xe-133 Ci 1.63 E-01 3.20 E-02 Xe-133m Ci 1.05 E-03 Xe-135 Ci 9.15 E-00 Ci Ci Total for Ci 1.65 E-01 3.20 E-02 Period Above NOTE: ( ) indicates less than detectable activity C8:2
FLO A POWER AND LIGHT COMPAN TURKEY POINT PLANT SEMIANNUALREPORT JANUARY THROUGH JUNE 1987 UNIT 3 TABLE 3 GASEOUS EFFLUENTS - SUMMATIONOF ALL RELEASES Units Quarter 1 Quarter 2 A. Fission and Activation Gases
- 1. Total Release Ci 8.19 E+02 3.99 E-01
- 2. Average Release Rate for Period p Ci/sec 1.00 E+02 5.08 E-02 B. Iodines
- 1. Total Iodine-131 Ci 8.66 E-03 2.16 E-00
- 2. Average Release Rate for Period pCi/sec 1.10 E-09 '.75 E-05 C. Particulates
- 1. Particulates T - 1/2) 8 Days Ci 1.06 E-03 2.26 E-05
- 2. Average Release Rate for Period pCi/sec 1.35 E-00 2.88 E-06
- 3. Gross Alpha Radioactivity Ci 5.85 E-08 1.09 E-07 D. Tritium
- 1. Total Release Ci 8.02 E+01 741 E+00
- 2. Average Release Rate for Period p Ci/sec 1.07 E+01 9.03 E-01 P
+Unit 3 was shutdown for refueling and maintenance the entire Second Quarter.
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FLO A POWER AND LIGHT COMPAN TURKEY POINT PLANT SEMIANNUALREPORT JANUARY THROUGH JUNE 1987 UNIT 3 TABLE 0 GASEOUS EFFLUENTS Continuous Mode Batch Mode Nuclides Released Units uarter uarter 2 uarter uarter 1 1 2
- 1. Fission Gases Ar-Ol Ci 2.27 E-01 3.53 E-02 Kr-85 Ci 2.10 E+00 Kr-85m Ci 1.01 E-01 1.08 E-01 Kr-87 Ci 1.10 E-02 Kr-88 Ci 9.27 E-02 6.00 E-02 Xe--131m Ci 1.33 E+00 2.35 E+00 Xe-133 Ci 5.30 E+02 2.71 E+02 3.99 E-01 Xe-133m Ci 1.62 E+00 2.71 E+00 Xe-135 Ci 1.28 E+00 1.89 E+00 Xe-135m Ci 2A7 E-03 2.05 E-02 Ci Ci Unidentified Ci Total for Period Above Ci 5.39 E+02 0.00 E+00 2.80 E+02 3.99 E-0 1
- 2. Iodines I-131 Ci 8.53 E-03 2.16 E-00 1-133 Ci 1.93 E-03 Ci Total for Period Above Ci 1.05 E-02 2.16 E-00
'I NOTE: () Indicates less than detectable activity
+Unit 3 was shutdown for refueling and maintenance the entire Second Quarter.
FLO A POWER AND LIGHT COMPAN TURKEY POINT PLANT SEMIANNUALREPORT JANUARY THROUGH JUNE 1987 UNIT 3 TABLE 0 (Continued)
GASEOUS EFFLUENTS Continuous Mode Nuclides Released Units uarter 1 uarter 2
- 3. Particulates Ba-leo Ci 5.90 E-05 Co-58 Ci 0.18 E-05 8.90 E-06 Co-60 Ci 0.81 E-06 0.85 E-06 Cr-51 Ci 1.77 E-05 Cs-130 Ci 2.50 E-00 1.02 E-06 Cs-136 Ci 1.13 E-00 Cs-137 Ci 3.97 E-00 6.85 E-06 I-131 Ci 1.22 E-00 5.30 E-07 La-100 Ci 0.13 E-05 Mn-50 Ci 5.05 E-06 Sr-89 Ci 1.13 E-05
< 1.52 E-15' Sr-90 Ci 1.50 E-07 0.60 Ci Ci Ci Ci E-16'.26 Ci Ci Ci Ci Unidentified Ci Total for Ci 1.06 E-03 E-05 Period Above NOTE: ( ) indicates less than detectable activity
+MDA value in p Ci/cc C8:2
FLO A POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY THROUGH 3UNE 1987 UNIT 0 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 1.20 E-01 1.13 E-01
- 2. Average diluted concentration during period p Ci/ml 3.99 E-10 0.60 E-10 B. Tritium
- 1. Total Release Ci 1.60 E+02 2.09 E+01
- 2. Average diluted concentration during period p Ci/ml 1.85 E-OP 7.13 E-Od C. Dissolved and Entrained Gases
- 1. Total Release Ci 1.65 E-Ol 3.20 E-02
- 2. Average diluted concentration during period pCi/ml 5.31 E-10 1.32 E-10 D. Gross Alpha Radioactivity
- l. Total Release Ci < 9.78 E-09 < 7.01 E-09 E. Volume of Waste Released (prior to dilution) Liters 2.90 E+06 0.62 E+06 F. Volume of Dilution Water Used.During Period Liters 3.11 E+11 2.06 E+11 h Based on Cooling Canal Tritium Concentration
+ MDA value in pCi/ml A
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FLOR A POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT 3ANUARY THROUGH 3UNE 1987 UNIT 0 TABLE 2 LIQUID EFFLUENTS Units Continuous Mode Batch Mode Nuclides Released uarter I uarter 2 uarter I uarter 2 Ag-110m Ci 1.59 E-03 1.63 E-03 Ba-100 Ci 3.00 E-06 Co-57 Ci 2.85 E-05 6.70 E-05 Co-58 Ci 3.00 E-02 0.27 E-02 Co-60 2.08 E-02 2.06 E-02 Cr-51 Ci 1.55 E-03 2.07 E-03 Cs-130 Ci 6.90 E-00 1.73 E-03 Cs-137 Ci 2.28 E-03 6.00 E-03 Fe-55 Ci 0.91 E-02 3.00 E-02 Fe-59 Ci 6.25 E-00 8.65 E-05 I-131 Ci 0.35 E-03 2.57 E-00 I-132 Ci 1.50 E-05 I-133 Ci 2.88 E-00 La-100 Ci 1.32 E-03 3.30 E-05 Mn-50 Ci 2.08 E-03 OA6 E-00 M o-99/Tc-99m Ci IA9 E-03 6.00 E-06 Na-20 Ci 9.50 E-00 Nb-95 Ci 245 E-00 6.05 E-00 Ru-103 Ci 0.50 E-05 6.65 E-05 Sb-120 Ci 2.52 E-00 8.25 E-05 Sb-125 Ci 5.00 E-03 6.15 E-00 Sn-117m Ci 2.50 E-06 Sr-89 Ci ( 3.6 E-08 1.06 E-03 Sr-90 Ci 3.20 E-05 1.18 E-00 Zr-95 Ci 0.05 E-05 6.65 E-05 Unidentified Ci Total for Ci I;20 E-Ol 1.13 E-01 Period Above NOTE ( ) Indicates Less Than Detectable Activity
+MDA Value in Ijt Ci/ml C8:2
FLO A POWER AND LIGHT COMPAN TURKEY POINT PLANT SEMIANNUALREPORT JANUARY THROUGH JUNE 1987 UNIT 0 TABLE 2 (Continued)
LIQUID EFFLUENTS Liquid Dissolved Gas Nuclides Released Continuous Mode Batch Mode Units uarter uarter 1 2 uarter 1 uarter 2 Xe-133 Ci 1.63 E-01 3.20 E-02 Xe-133m Ci 1.05 E-03 Xe-135 Ci 9.15 E-00 Ci Ci Total for Ci 1.65 E-01 3.20 E-02 Period Above NOTE: ( ) indicates less than detectable activity C8:2
FLO A POWER AND LIGHT COMPAN TURKEY POINT PLANT SEMIANNUALREPORT JANUARY THROUGH JUNE 1987 UNIT 0 TABLE 3 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES Units Quarter I Quarter 2 A. Fission and Activation Gases
- 1. Total Release Ci 5.90 E+02 1.19 E-03
- 2. Average Release Rate for Period pCi/sec 7.51 E+Ol 1.51 E-00 B. Iodines
- l. Total Iodine-131 Ci 8.66 E-03 2.16 E-00
- 2. Average Release Rate for Period pCi/sec 1.10 E-03 2.75 E-05 C. Particulates I. Particulates T- I/2) 8 Days Ci 1.06 E-03 2.26 E-05
- 2. Average Release Rate for Period p Ci/sec 1.35 E-00 2.88 E-06
- 3. Gross Alpha Radioactivity Ci 5.85 E-08 1.09 E-07 D. Tritium I. Total Release Ci 8.02 E+Ol 7.01 E+00
- 2. Average Release Rate for Period p Ci/sec 1.07 E+Ol 9.03 E-01
+Unit 0 was shutdown for maintenance the entire Second Quarter.
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FLO i A POWER AND LIGHT COMPAN TURKEY POINT PLANT SEMIANNUAL REPORT JANUARY THROUGH JUNE 1987 UNIT 0 TABLE 0 GASEOUS EFFLUENTS Nuclides Released Continuous Mode Batch Mode Units uarter uarter 1 2 uarter 1 uarter 2
- 1. Fission Gases Ar-01 Ci 2.69 E-01 2.38 E-02 Kr-85m Ci 3.36 E-02 1.31 E-02 Kr-87 Ci 1.26 E-03 Kr-88 Ci 3.92 E-02 1.92 E-00 Xe-131m Ci 1.21 E+00 1.27 E+00 Xe-133 Ci 0.62 E+02 1.19 1.22 E+02 Xe-133m Ci 5.90 E-01 1.18 E+00 Xe-135 Ci 6.95 E-01 5.91 E-01 E-03'.19 Ci Ci Unidentified Ci Total for Ci Period Above 0.65 E+02 E-03 1.25 E+02 0.00 E+00
- 2. Iodines I-131 Ci 8.53 E-03 2.16 E-00 I-133 Ci 1.93 E-03 Ci Total for Ci 1.05 E-02 Period Above 2.16 E-00 NOTE: ( ) Indicates less than detectable activity
+Unit 0 was shutdown for maintenance the entire Second Quarter.
FLO A POWER AND LIGHT COMPAN TURKEY POINT PLANT SEMIANNUALREPORT 3ANUARY THROUGH 3UNE 1987 UNIT 0 TABLE 0 (Continued)
GASEOUS EFFLUENTS Continuous Mode Nuclides Released Units uarter 1 uarter 2
- 3. Particulates Ba-100 Ci 5.90 E-05 Co-58 Ci 0.18 E-05 8.90 E-06 Co-60 Ci 0 81 E-06 0.85 E-06 Cr-51 Ci 1.77 E-05 Cs-130 Ci 2.50 E-00 1.02 E-06 Cs-136 Ci 1.13 E-00 Cs-137 Ci 3.97 E-QO 6.85 E-06 I-131 Ci 1.22 E-00 5.30 E-07 La-100 Ci 0.13 E-05 Mn-50 Ci 585 E<<06 Sr-89 Ci 1.13 E-05
< 1.52 E-15 Sr-90 Ci 1.50 E-07
< 0.60 E-16" Ci Ci Ci Ci Ci Ci Ci Ci Unidentified Ci Total for Ci 1.06 E-03 2.26 E-05 Period Above NOTE: ( ) indicates less than detectable activity
+MDA value in p Ci/cc C8:2
ORIDA PNER AND LIGHT COMPANY TURKEY POINT PUNT SEMIANNUAL REPORT JANUARY 1987 THROUGH JUNE 1987 UNITS 3 AND 4 TABLE 5A SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL
- 1. Type of Waste UNIT 6 MONTH PERIOD ERROfC
- a. Spent Resins, Filter sludges m 5.77 El evaporator bottoms, etc. Ci 4.13 E2 2.0 E+1
- b. Dry Compressible Waste m3 5.83 EO Ci .7.94 E-1 2.0 E+1 c~ Irradiated Components m3 0.00 EO Control rods, etc. Ci 0.00 EO
- d. Other
- 1. Hon-Compressible Metal m3 2.0 EO (Note 5) Ci 1.6 E-3
- 2. Estimate of Major Nuclide Composition (by type of waste) a ~ Co60 19 Cs137 18 Co58 17 Ni63 7 Fe55 2 Mn54 2
- b. Co60 50 Co58 17 Fe55 16 Ni63 9 Cs137 3 c~
d.
- 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 15 (Note 6) Sole Use Truck Barnwell, S.C.
B. IRRADIATED FUEL SHIPMENTS Number of Shipments Mode of Transportation Destination N/A H/A N/A - Hot applicable GLL/eb/016
FLORIDA POWER 5 LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JANUARY 1987 THROUGH JUNE 1987 UNITS 3 AND 4 TABLE 5B SOLID WASTE SUPPLEMENT (Note 1)
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 quantity Radionuclides Waste Category Container Absorbent Agent Class A 70.4 .03 None Non l.b Non-Spec N/A Compressible Strong, Tight Waste (Note 5) Package Class A 206 .75 None PWR l.b NRC Certified N/A Trash LSA > Type A Class A 1670.5 32.8 None PWR Ion l.a NRC Certified N/A Exchange LSA > Type A Resins A
Class A 119 12.5 Ni63 PWR l.a NRC Certified N/A Cartridge Type 8 Filters Class 8 249. 367.7 r90, Ni63 PWR Ion l.a NRC Certified N/A Co60, Csl37 Exchange LSA > Type A T',( 5yr. Resins GLL/eb/022/1
e
~ FLORIDA POWER 5 LIGHT COMPANY TURKEY POINT UNIT NOS. 3 5 4 SEMI-ANNUAL REPORT JANUARY 1987 THROUGH JUNE 1987 TABLE 5B (CONTINUED)
SOLID WASTE SUPPLEMENT NOTE l: The total curie quantity and radionuclide composition of solid waste shipped from the Turkey Point Units 3 & 4 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 basis or on a routine basis using reasonably representative samples as appropriate for the waste type. Offiste analyses are used to establish scaling factors or other estimates for radionuclides such as 3H, 14C, 99Tc, 129I, TRU, 241Pu, 242Cm, 63Ni, and 55Fe NOTE 2: "Principal Radionuclides" refer to those radionuclides contained in the waste in concentrations greater than .01 times the concentration of the nuclide listed in Table 1 or .01 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 Environment Impact Statement on 10CFR61 "Licensing Requirements for Land Disposal of Radioactive Waste".
NOTE 4: "Type of Container" refers to the transport package.
NOTE 5: The volume and activity. listed for non-compressible metal represent the quantity of material that to date could not be recycled by a contracted vendor and required disposal.
The initial volume of material sent to the recycle facility was 28.6 cubic meters.
NOTE 6: One shipment'hipped from decontamination facility to disposal facility.
GLL/eb/003
FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMI-ANNUALREPORT 3ANUARY THROUGH JUNE 1987 ATTACHMENTA UNPLANNED RELEASES On April 17, 1987, radioactively contaminated water entered the demineralized water system. The radioactive water originated from the Unit 3 Spent Fuel Pool and made its way throughout the demineralized water system including the Demineralized Water Storage Tank. Contaminated water was released to the circulating water cooling canals through several demineralized water lines which were free draining to the storm drain system. Routine sampling of the storm drain system discovered the release. The event resulted in the release of the following:
Co-57 1.66 E-06 Ci Co-58 8.52 E-00 Ci Co-60 2.17 E-00 Ci Nb-95 1.80 E-06 Ci Total 1.07 E-03 Ci During this evolution, Unit 3 was shutdown for refueling and Unit 0 was shutdown for extensive maintenance repairs. An Event Response Team was formed to investigate this event and they concluded that a check valve, which is in the system to prevent backflow from the Spent Fuel Pool to the primary water/demineralized water fill line, failed and allowed contaminated water to enter the demineralized water system. The check valve was replaced and several procedures were enhanced to help prevent a similar event from recurring.
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P. O. BOX 00, JUNO BEACH, FL 33408.0420 AUGUST, 5 1 1987 L-87-36 I U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gen t le men:
Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-25 I Semi-Annual Radioactive Effluent Release Re ort Attached is the Radioactive Effluent Release Report for the period of January I, l987 through June 30, l987 for Turkey Point Units 3 and 4, as required by Technical Specification 6.9.4.
Should there be any questions on this information, please contact us.
Very truly yours,
. O. Woody roup Vice President Nuclear Energy COW/SDF/gp Attachmen t cc: Dr. J. Nelson Grace, Regional Administrator, Region II; USNRC Senior Resident Inspector, USNRC, Turkey Point Plant
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