ML17352B092

Annual Radioactive Effluent Release Rept Jan-Dec 1994.

ML17352B092
Person / Time
Site:	Turkey Point
Issue date:	12/31/1994
From:	Berg J, Johnson H, Steinke R FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17352B091	List: ML17352B090 ML17352B092
References
NUDOCS 9504050112
Download: ML17352B092 (52)

Text

Turkey Point Pbnt

~lnlts 3 and 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1994 through December 1994 Submitted by:

NUCLEAR CHEMISTRY DEPARTMENT FLORIDA POV/ER AND LIGI-IT COMPANY J.. Berg, Radiochemis upervisor R.N. Ste k Chemistry Supervisor H.I-. h son, Operations Manager

. Jernigan, Plant Manager 9504050112 950330 PDR ADOCK 05000250 R. PDR

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TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1994 THROUGH DECEMBER 1994 Table Of Contents 1.0 REGULATORY LIMITS ... 3 2.0 MAXMUMPERMISSIBLE CONCENTRATION . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 3.0 AVERAGE ENERGY 4 4.0 MEASUREMENTS AND APPROXMATIONS OF TOTAL ACTIVITY.. 4 5.0 BATCH RELEASES 6.0 UNPLANNED RELEASES ~ ~ ~ ~ ~ ~ ~ 8 7.0 REACTOR COOLANT ACTIVITY ~ ~ ~ ~ ~ ~ ~ 8 8.0 SITE RADIATION DOSE........... ~ ~ ~ ~ ~ ~ ~ ~ 8 9.0 OFFSITE DOSE CALCULATIONMANUAL(ODCM) REVISIONS ............ 9 10.0 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 9 11.0 PROCESS CONTROL PROGRAM REVISIONS ~ ~ ~ ~ ~ ~ 9 12.0 INOPERABLE EFFLUENT MONITORING INSTRUMENTATION ............ 9 Page 2

~ 'D TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1994 THROUGH DECEMBER 1994 1.0 REGULATORY LIMITS Lfl. L~dflffl (a) The concentration of radioactive material released in liquid effluent to unrestricted areas shall not exceed the concentration specified in 10CFR20 Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained gases. For dissolved or entrained noble gases, the concentration shall not exceed 2.0 E-04 micro-curies per milliliter.

(b) The dose or dose commitment per reactor to a member of the public from any radioactive materials in liquid effluents released to unrestricted areas shall be limited as follows:

i During any calendar quarter, to less than or equal to 1.5 mrem to the total body and less than or equal to mrem to any organ.

5 i During any calendar year, to less than or equal to 3.0 mrem to the total body and less than or equal to 10 mrem to any organ.

1.2 Gaseous Effluent (a) The dose rate due to radioactive materials released in gasesous effluent from the site to areas at and beyond the site boundary shall be limited to the following:

i Less than or equal to 500 mrem per year to the total body and less than or equal to 3000 mrem per year to the skin due to noble gases.

i Less than or equal to 1500 mrem per year to any organ due to 1-131, 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 to:

i During any calendar quarter, to less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation.

i During any calendar year, to less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

(c) The dose per reactor to a member of the public, due to 1-131, 1-133, tritium, and all radionuclides in particulate form with half-lives greater than S days in gaseous effluent 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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TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1994 THROUGH DECEMBER 1994 2.0 MAXIMUMPERMISSIBLE CONCENTRATION Water: In accordance with 10CFR20, Appendix B, Table 2, Column 2, and for entrained or dissolved noble gases as described in 1.1.a of this report.

Air Release concentrations are limited to dose rate limits described in 1.2.a of this report.

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

4.0 MEASUREMENTS AND APPROXIMATIONS F TOTAL ACTIVI'IY All liquid and airborne discharges to the environment during this 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.

V/hen alplI.I, tritiu tn and named nuclides are shown as "- -" curies on the following tables, this should be interpre:ed as '~no activit 'eas detected on the samples using the Plant Technical Specification analysis tecniques to achieve the required Lower Limit of Detection ("LLD")

sensitivity for radioactive effluents.

Aliquots of representative pre-release samples, from waste disposal system, were isotopically analyzed for gamma emitting isotopes on a multichannel analyzer.

Frequent periodic sampling and analysis were used to conservatively determine if any radi':.ctive 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 radioactivity. Tritium was determined by use of liquid scintillation techniques, and gross alpha radioactivity was determined by use of a solid state scintillation system. The quarterly composite was analyzed for Sr-89, Sr-90, and Fe-55 by chemical separation.

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TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1994 THROUGH DECEMBER 1994 All radioactivity concentrations determined from sample 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 samples from the waste disposal system were analyzed on a pre-release basis by gamma spectrum analysis. The resulting isotope concentrations were multiplied by the total volum 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 respectively.

There were no continuous liquid effluent releases above the lower limit of detection for either Unit 3 or Unit 4 during this reporting period and therefore these have been omitted from Table 2 of this report.

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TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFPLUENT RELEASE REPORT JANUARY 1994 THROUGI.I DECEMBER 1994 4.2 Gaseous Effluents Airborne releases to the atmosphere occurred from the following sources:

Gas Decay Tanks I Containment Purges 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, Sr-90 determination, and gross alpha determination, c) Absorption of halogen radionuclides on a charcoal filter and subsequent gamma spectral analysis, and d) Analysis of water vapor in a gas sample for tritium using liquid scintillation techniques.

All gas 1eleases from the plant which were not accounted for by the above methods were cons'rvatively estinIated as curies of Xe-133 by use of the SPING-4 radiation monitors and the Plant Vent process monitor recorder chart and the current calibration curve for that process 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 1994 through December 1994, in the form of Joint Frequency Distribution Tables, is maintained on site.

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TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1994 THROUGH DECEMBER 1994 4.3 Estimation 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, reported to us by the independent lab, were used as the basis for deriving the following analytical error terms:

NUCLIDE TYPE AVERAGE ERROR MAXIMUMERROR Liquid ~ 6.1% ~ 17.0'/0 Gaseous g 6.2% g 12.4%

5.0 BAT H RELEASES 5.1 LR?UID Unit3 Unit 4 a) Number of releases 2.83E+02 2.83E+02 b) Total time period of batch releases 2.39E+04 2.39E+04 c) Maximum time period for a batch release, minutes 2.00E+02 2.00E+ 02 d) Average time period for a batch release, minutes 8.33E+01 8.33E+01 e) Minimum time for a batch release, minutes 1.00E+00 1.00E+00 f) Average stream flow during period of release of effluent into a flowing stream, liters-per-minute 2.62E+06 2.62E+06 5.1 QASE0 US Unit3 Unit 4 a) Number of releases 1.15E+01 1.15E+01 b) Total time period of batch releases 7.50E+02 7.50E+02 c) Maximum time period for a batch release, minutes 2.40E+02 2.40E+02 d) Average time period for a batch release, minutes 1.30E+02 1.30E+02 e) Minimum time for a batch release, minutes 2.00E+01 2.00E+01 Page 7

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1994 THROUGH DECEMBER 1994 6.0 UNPLANNED RELEASES 6.1 Liciuid There were no unplanned liquid releases this period for either Unit 3 or Unit 4.

6.2 Gaseous There were no unplanned gaseous releases this period for either Unit 3 or Unit 4 7.0 REACTOR COOLANT ACTIVITY 7.1 Unit 3 Reactor coolant activity limits of 100/E-Bar and 1.0 uCi/gram Dose Equivalent I-131 were not exceeded.

7".2 11nit 4 Reactor coolant activity limits of 100/E-Bar and 1.0 uCi/gram Dose Equivalent I-131 were not exceeded. 4 8.0 SITE RADIATIONDOSE The assessment of radiation dose from radioactive effluents to the general public due to their activities inside the site boundary assumes a visitor was at the child development center/fitness center for ten hours a day, five days each week for fifty weeks of the year, receiving exposure from both Unit 3 and Unit 4 at Turkey Point. The child development center/fitness center is located approximately 1.75 miles WNW of the plant. Specific activities used in these calculations are the sum of the activities listed in Unit 3 Table 3 and Unit 4 Table 3. The following dose calculations were made using historical, meteorological data:

Bone rnrem 9.00E-07 1.71E-06 Liver mrem 1.47E-06 3.76E-06 Th roid mrem 3.41E-04 5.33E-04 Kidne m rem 2.55E-06 2.35E-06 Lun m rem 4.85E-07 2.00E-06 GI-LLI mrem 9.14E-07 2.21E-06 Total Body (mrem) 6.03E-07 2.21E-06 Gamma Air Dose (mrad), 3.62E-05 Beta Air Dose (mrad) 7.70E-05 Page 8

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1994 THROUGH DECEMBER 1994 9.0 FFSITE DOSE CAL ULATION MANUAL ODCM REVISIONS Attachn:ent 1 is the revision to the ODCM for this report.

10.0 SOLID IVASTE AND IRRADIATED FUEL SHIPMENTS No irradiated fuel shipments were made from the site. Common solid waste from Turkey Point Units 3 and 4 was shipped jointly. A summation of these shipments is given in Table 6 of this report.

11.0 PROCESS ONTR L PRO RAM RE IONS There were no changes to the Process Control Program during this reporting period.

12.0 IN PERABLE EFFLUENT MONITORING INSTRUMENTATION No inoperable effluent monitoring instrumentation requiring reportability during this period.

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I TURKEY POINT UNCS 3 AND4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1994 THROUGH DECEMBER 1994 LIQUIDEFFLUENTS

SUMMARY

UNIT 3 TABLE 1 A. FISSION AND ACTIVATIONPRODUCTS UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)

1. Total Roloaso (not including tritium,gases, alpha) Cl 7.48EZ2 9.1 5EZ2 S.89')2 4.72E4)2

. Average diluted concentration during tho period uCI/ml 1.24E49 1.55E-10 8.55E-11 125E-10  !.";."" .".',",;.,"; !! .'i";"

. Porcont of applicablo limit 2.32')1 2.98E<1 8.70E4)2 8.31 E4)2 B. TRITIUM UNITS Qtr 1 Qtr 3 Qtr 4 Est. Error (%)

1. Total Roioaso CI 1.51E+02 1.06E+02 8.45E+01 3.44E+01

2. Average diluted concentration during tho period uCi/ml 4.24E46 3.23')6 3.66E4)6 1.02E46 9"-'"""""'=='~=-'~0tt>

. Percent of applicablo limit 4.24E4)I 3.23')1 3.66E<1 1.02')1 C. DISSOLVED AND ENTRAINED GASES UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 EsL Error (%)

1. Total Release Ci 2.55EZ2 4.62')3 1.44')3 2.33')4

. Average diluted concentration during tho porlod uCi/ml 7.16E-1 0 1.41E 10 624E-11 6.90E-12

. Porcont of applicablo limit 3.58E4)4 7.07')5 3.12')5 3.45E46 D. GROSS ALPHA RADIOACTIVITY UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)

1. Total Release Ci E. LIQUIDVOLUMES Qtr 1 Qtr 2 Qtr 4 Est. Error (%)

1. Batch waste reloased, prior to dilution UTER S 1.43E+06 1.74E+06 1.37E+06 2.06E+06 10.00

2. Continuous waste released, prior to dilution UTERS

3. Dilution water used during period UTERS 3.S6E+10 3.27E+10 2.31E+10 339E+10 el% t4 tbjttn<"ctt Page 10

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TURKEY POINT UNI1$ 3 AND4 ANNUALRADIOAC11VE EFFLUENT RELEASE REPORT JANUARY1994 THROUGH DECEMBER 1994 LIQUID EFFLUENTS

SUMMARY

UNIT 3 TABLE 2 NUCLIDES CH MOD RELEASED Qtr 2 Qtr 4 3.07E42 4.31 E4Q 1.70E4Q Sr4I9 1.54E44 9.44E45 Sr-90 6.56 4IS 6.34E45 Na-24 CI 6.34E4IS Cr%1 CI 4.20E4I4 4.1 4E44 Mn-54 Ci 1.09 W2 2.64EZ2 1.90 1.53 4Q Co47 Ci 2.14E4IS 2.04E4IS 4'.24E45 CI 2.08E42 1.11EZ2 1.25E4Q 154E4Q Fo49 CI 1.14 EBS 2.47E4N 8.69E4N 1.15 4Q 6. 4I3 3.4 43 2.41 CI 4.74E48 3.19E45 9.58E45 r-97 CI 2.13E4lS 4.11E4IS Ru-1 03 CI g-110 CI 1.53EW3 2.1 SE4L1 Sn-113 CI 3.69E4N Sn-117 Sb-1 24 6.70E4I4 4.04E45 1.87 44 Sb-125 CI 1$ 0E44 7.76E4I4 6.20E44 3.42E44 I-131 Ci 7.70E46 1-133 1.49 W 1-134 Cs-134 1.66E4I4 2.42E4I3 h135 CI Cs-137 Ci 1.85E4I4 233 E4I4 3.00E4I3 5.06E44 La-140 Ci 3.99E415 6.65E<7 1.12E46 Ce-141 Ci Co-144 CI 4.63E46

-187 Ci 4.17E46 5.51E45 9.80E45 N 239 OTAL FOR PERIOO UNIT 3 LIQUIDEFFLUENTS- DISSOLVED GAS

SUMMARY

TABLE 2 RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Ci Ci Ci 2.99E4L3 1A4EZ3 2.55E42 1.63E43 2.31 44 0-133m Ci o-1 35 2.12E46 TOTAL FOR PERIOO Ci 2.55E<2 4.62EZ3 1.44EZ3 2.33E414 LIQUIDEFFLUENTS - DOSE SUMMATION Age gnwp r Teenager Location: Cooling Canal Shoreline Deposition Doso (mrem)  % of Annual Limit 0 ALBOD 1.41 4.69 42

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1994 THROUGH DECEMBER 1994 GASEOUS EFFLUENTS

SUMMARY

UNIT 3 TABLE 3 A. FISSION AND ACTIVATIONPRODUCTS UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)

o a cease CI 9.11E+00 5.50E+00 O.OOE+00 8.63E%3

2. Average release rate for the period uCI/sec 6.84E-07 1.07E-09

3. Percent of Technical Specification Limit 1.64E-10 1.13E-10 O.OOE+00 6.08E-14 iI"iti-,il;-il'i'.<'.

IOD INES UNITS Qtr 1 Qtr 2 3 Qtr 4 Est. Error (%)

1. Total Release CI 2.37E-03 1.68E~ 3.23E%7 5.05EZ7 2.00

2. Average release rate for the period

3. Percent of Technical Specification Limit uCVsec 1.82E48 4.58E%3 3.25'tr 1.28E-10 243E-12 6.24EZ7 3.81E-12 9.77E%7 C. PARTICULATES UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)

a icuaeswi a -ie> ays CI 2.18E~ 6.10E&8 15.00

2. Average release rate for the period uCI/sec 1.66E-10 4.60E-13

3. Percent of Technical Specification Limit

4. Gross Alpha Radioactivity CI D. TRITIUM UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)

1. Total Release CI 3.06M)1 1.29E<1 2.83E-01 4.00

2. Average release rate for the period uCi/sec 2.34E~ 9.74EC7 2.14E46 '-

3. Percent of Technical Specification Limit f NOTE: THESE PERCENTAGES ARE INCLUDED IN THE IODINE LIMITCALCULATION Page 12

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY I 994 THROUGH DECEMBER 1994 GASEOUS EFFLUENTS

SUMMARY

UNIT 3 TABLE 4 A. FISSION GASES NUCLIDES uRITs BATCH MODE RELEASED Qtr 1 Qtr2 I Qtr3 I Qtr 4

-85m CI 3.88E43 Kr-85 Ci 5.36E-03 e-131m Ci 1.41EC1 1.19E-01 8.59E-05 e-1 33 CI 8.25E+00 1.20E+00 3.15E%3 e 133m CI 1.23E-01 3.22E-05 e-135 CI 1.01E41 1.37E-03 4.02E-06 CI 3.78 -02 TOTAL FOR PERIOD Ci 8.62E+00 1.36E+00 0.00E+00 8.63E-03 NUCLIDES CONTINUOUS MODE RELEASED Qtr1 Qtr 2 Qtr 3 Qtr 4 Ci Kr-85 CI Kr-85m Ci Kr-87 Ci Kr-88 CI e-131m Ci e-133 Ci 4.95E-01 4.14E+00 e-133m Ci e-135 Ci Xe-135m Ci e-138 CI TOTAL FOR PERIOD Ci 4.95E-01 4.14E+00 I B. IODINES NUCLIDES uRITs RELEASED Qtr 1 Qtr 2 I Qtr 3 i Qtr 4 Br-82 Ci 1-131 Ci 2.37E<3 1.68 EBS 3.23E%7 5.05E%7 I-133 CI 1.59E-02 TOTAL FOR PERIOD 1.82 -02 1.68 -05 3.23 %7 5.05 -07 C. PARTICULATES NUCLIDES uwTs CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Co-58 CI 3.5 E46 6.10E48 Co-60 Ci 6.30E-06 Mn-54 Ci 5.47E-06 Cr-51 CI 6.52E<6 OTAL FOR PERIOD Page 13

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1994 THROUGH DECEMBER 1994 DOSES DUE TO IODINE,TRITIUI0,AND PARTICULATES UNIT 3 TABLE 5 PATHWAY BONE THYROID KIDNEY LUNG Glut SKIN TOTAL BODY Cow milk - Infant (mrem) 1.08E44 1.36E44 4.09E42 3.49E45 5.39E46 1.23E45 7.82 f45 Fruit & Veg Fresh (mrem) 3 48E-06 6.09E46 1.56E43 9.77E46 9.15E47 2.91E46 3.62E46 Ground Plane (mrem) 6.63E-06 6.63E46 6.63E46 6.63E46 6.63E46 6.63E46 7.96E46 6.63E46 Inhalation - Adult (mrem) 6.24E-07 3A6E46 2 40E44 4.21 E-06 2.77E-06 3.07E46 TOTAL (mrem) 1.18E-04 1.52E44 4.27E42 5.56E45 1.57E-05 2.49E45 7.96E46 9.13E45

% of Annual Limit 7.89E44 1.02E43 2.85E-01 3.70E44 1.05E44 1.66E44 5.31 E45 6.09E-04 DOSE DUE TO NOBLE GASES Y of Annvol Link Gamma Air Dose 1.01E44 1.01E43 Beta Air Dose 2.85E-04 2.85E43 Page 14

TURKEY POINT UNrIS 3 AND4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1994 THROUGH DECEMBER 1994 LIQUIDEFFLUENTS SUMIMARY UNIT 4 TABLE 1 A FISSION AND ACTIVATIONPRODUCTS UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)

1. Total Release (not Including trilium,gases, alpha) Ci 7.48E4I2 9.15E4)2 5.89EZ2 4.72E4)2

. Average diluted concentration durfng tho period uCVml 6.18E 10 7.75E 11 4.27E-11 6.73E-11

. Percent of applicable limit 2.32E<1 2.98E<1 8.70E<2 8.31E4)2 '."iILktti:.Il'-Lt', tt B. TRITIUM UNITS Qtr 1 Qlr 2 Qtr 3 Qtr 4 Est. Error (1o)

1. Total Release CI 1.51E+02 1.06E+02 8.45E+01 3.44E+01

. Average diluted concentration during the period uCVml 424E46 3.23E46 3.66E46 1.02E4)6

. Percent of applicable limit 424')t 323E%1 3.66E4)t 1.02E4)I .Iiti)'kt04!i<jii)i.ivrti C. DISSOLVED AND ENTRAINED GASES UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)

1. Total Release Ci 2.55E42 4.62E4)3 1.44E4)3 233E4I4

. Average diluted concentration during the period uCi/ml 7.16E-10 1.41E-10 6.24E-11 690E-12 (',y',.",.';)I'",,'8-"(it",,'-'>

. Percent of applicablo limit 3.58E4)4 7.07')5 3 12E<5 3 45E4I6 D. GROSS ALPHA RADIOACTIVITY UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Ermr (9o) ota e ease E. LIQUIDVOLUMES Qtr 1 Qtr 2 Qtr 3 Est. Error (%)

1. Batch waste released, prior to dilution UTERS 1.43E+06 1.74E+06 1.37E+06 2.06E+06 10.00

. Continuous waste roleased, prior to dilution LITERS

. Dilution water used during period LITERS 3.56E+10 3.27E+10 2.31E+10 3.39E+10 ll.'4IU>>". <<I) tli'll'iiU Page 15

ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1994 THROUGH DECEMBER 1994 LIQUID EFFLUENTS

SUMMARY

UNIT 4 TABLE 2 NUCLIDES UNITS BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 3.07 42 4.31 E42 1.0 42 1.02 42 1.54E44 9 44E45 Sr'r-90

6. 6 9.1 E45 4.21 Na-24 CI 6.34E45 Cr%1 CI 4.20E44 4.14E44 1.09 42 2.64E42 1.90 42 Co-57 Cj 2.14E45 2.04E45 4.24E45 CI 2.08E42 1.11E42 1.25E42 1.54E42 Fe49 CI 1.14E45 2.47E46 8.69E46 1.5 42 6.80 43 3.4 43 2.41 43 Nb-95 CI 4.74E46 3.19E45 9.58E45 Zr-97 CI 2.13E45 4.11E45 Ru-103 Cj Ag-110 CI 2.68E44 1.53E43 3.80E44 2.15E43 Sn-113 CI 3.69E46 Sn-11 S 124 6.70E44 4.04 45 1.87E44 Sb-125 CI 1.50E44 7.76E44 6.20E44 3.42E44 I-131 CI 7.70E46

-133

-134 Cs-134 2.42 43 .9 E 1-135 CI Cs-137 Cj 1.85E44 2.33E44 3.00E43 5.06E44 La-140 CI 3.99E45 6.65E47 1.12E46 Ce-141 CI Ce-144 Cj 4.63E46 W-187 Cj 4.17E46 5.51 E45 9.80E45 TOTAL FOR PERIOO LIQUIDEFFLUENTS - DISSOLVED GAS

SUMMARY

NUCUDES UNITS BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr4 Ar<1 CI Cj 2.99E43 1A4E43 Xe-133 Cj 2.55E-02 1.63E43 2.31E44 Xe-133m Cj 2.12 46 TOTAL FOR PERIOO Cj 2.55E42 4.62E43 1.44E43 2.33E44 LIQUIDEFFLUENTS - DOSE SUMMATION Ago gnwpl Toonegor Locetlonl Cooling Cenel Shoreline Deposition Dose (mrem)  % of Annual Limit TOTAL BODY 1.41E%3 4.69E%2 Page 16

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TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1994 THROUGH DECEMBER 1994 GASEOUS EFFLUENTS

SUMMARY

UNIT 4 TABLE 3 A. FISSION AND ACTIVATIONPRODUCTS UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)

1. Total Release Cl 9.11E+00 3.97E+00 O.OOE+00 3.86EZ2 7.00

2. Average release rate for the period uCVsec 1.13')6 4.94E%7 4.81E-09

. Percent of Technical Specification Limit 1.64E-10 6.87E-11  ! i'~ i.< i,"I'-".

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IODINES UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)

1. Total Release Ci 2.37EZ3 1.13E-OS 3.23EZ7 5.05E<7 2.00

2. Average release rate for the period uCVsec 1.82E48 8.62E-11 2A3E-12 3.81 E-12

3. Percent of Technical Specification Limit 4.58E<3 2.19E~ 6.24E<7 9.77E<7 r','i C. PARTICULATES UNITS Qtr1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)

1. Particulates with half-life >8 days CI 2.18EAS 6.10E<8

2. Average release rate for the period uCI/sec 1.66E-10 466E 13 'liriik>>i'<"

3. Percent of Technical Specification Limit "1'.

4. Gross Alpha Radioactivity CI TRITIUM UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)

I. Total Release CI 2.54EZ3 1.29EZ1 1.84E%1 4.00

2. Average release rate for the period uCVsec 1.96E~ 9.95EZ7 1.42E-06:;i,>t;t!".I "i'.1,"i'.v,i

3. Percent of Technical Specification Limit NOTE: THESE PERCENTAGES ARE INCLUDED IN THE IODINE LIMITCALCULATION Page 17

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1994 THROUGH DECEMBER 1994 GASEOUS EFFJ UENTS

SUMMARY

UNIT 4 TABLE 4 A. FISSION GASES NUCLIDES UNITS BATCH MODE RELEASED Qtr2 I Qtr3 I, tr4 Ci 1.71E-02

-85 5.36E-03 e-131m Ci 1.41E-01 8.59E-05 6-1 33 Ci 8.25E+00 6.15E-02 1.61E-02 e-133m Ci 1.23E-01 3.22E-05 e-135 1.01E-01 1.37E-03 4.02E%6 e-135m ToTAL FoR PERIoo I Ci 8.62E+00 6.29E<2 3.86E-02 UNITS RELEASED tr2 Qtr 3 Qtr 4 r-41 CI Kr-85 Ci r-85m CI r-87 CI Kr-88 Ci 6-1 31nl Ci 6-133 Ci 4.95E%1 3.91E+00 6-1 33m Ci e-135 Ci e-135m Ci e-138 Ci TOTALFoRI aRIoo Ci I 4.95E-01 I 3.91E+00 B. IODINES NUCLIDES UNITS CONTINU US MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr4 Br-82 Ci l-131 Ci 2.37 -03 1.13E-05 3.23E47 5.05E%7 1-133 CI 1.59E-02 TQTALFQRPERIQD Ci 1.82E-02 I 1.13E-05 I 3.23E-07 I 5.05E-07 C. PARTICULATES NUCLIDES UNITS C NTINUOUS M D RELEASED Qtr1 Qtr 2 Qtr 3 Qtr 4 Co-58 CI 3.51E46 6.10E-08 Co-60 Ci 6.30E-06 Mn-54 Ci 5.47E-06 Cr-51 6.52E-06 OTAL FOR PERIOO .1 -5 6.1 Page 18

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1994 THROUGH DECEMBER 1994 DOSES DUE TO IODINE,TRITIUIIf,AND PARTICULATES PATHWAY BONE LNER a UNIT 4 TABLE 5 TNYROIO KIONEY LUNG GIXLI SKIN TOTAL BOGY Cow milk - Infant (mrem) 1.07E44 1.33E44 4.08E42 3.35E45 2.37E46 9.23E48 7.50E45 Fruit & Veg Fresh (mrem) 3.48E46 5.57E46 1.56E-03 8.88E46 4.01E47 2 40E46 3.10E46 Ground Plane (mrem) 3.57f 46 3.57E46 3.57E46 3.57 f46 3.57E46 3.57E46 4.24E46 3.57E46 Inhalation - Adult (mrem) 6.24E47 3 46E46 2 40E44 4.21 E48 2.77E46 3.07E46 2.85E46 TOTAL (mrem) 1.15E44 1 46E44 4.27E-02 5.02E-OS 9.11E-06 1.83E45 4.24E46 8 45E45

% of Annual Limit 7.67E44 9.71E44 2.84E41 3.35E44 6.07E45 1.22E-04 2.83 f45 5.63E44 DOSES DUE TO NOBLE GASES mrod IE of Anoooilinit Gamma Air Dose 1.53E44 1.53E43 Beta Air Dose 2.56E44 2.56E43 Page 19

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT IANUARY1994 THROUGH DECEMBER 1994 DOSES DUE TO IODINE,TRITIUIM,AND PARTICULATES SUMMATION TABLE 5 PATHWAY BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY Cow milk - Infant 2.15')4 2.69E~ 8.1 BE<2 7.76E4I6 2.15E~ 1.53E<4 Fruit & Veg Fresh 6.96E4I6 1.17E4I5 3.12E43 1.87EZ5 1.32E4I6 1.02'.85E~ 5.31 E-06 6.73E~

Ground Plane 1.02E4I5 1.02E4I5 1.02M)5 1.02E-05 1.02E45 1.22E45 1.02E<5 .

Inhalation - Adult 1.25E4I6 6.91E4I6 4.79E4I4 8.41 E46 -.

5.54E46 5.71E4M TOTAL (mrem) 2.33E44 2.98E4I4 8.54E-02 1.06E<4 1.65'.14E46 4.32E~ 1.76E<4

% of Annual Limit 1.56E<3 1.99E4I3 5.69E-01 7.05E~ 2.88E~ 8.13E45 1.17E%3 DOSES DUE TO NOBLE GASES tntod  % of Annool tinit Gamma Air Dose 2.55E44 2.55EZ3 Beta Air Dose 5.41 E<4 5.41 E<3 Page 20

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENTS RELEASE REPORT TABLE 6 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS A. Solid Waste Shipped Off-Site for Burial or Disposal

1. Type of Waste Units 12 Mo. Period Error %

a. Spent Resin, m 9.637E+0 Process Filters Ci 3.769E+1 2.0 E+1 (Note 1)

b. Dry Compressible m'i 5.821E+1 Waste (Note 2) 1.200E+0 2.0 E+1

c. Irradiated m 8.269E-1 Components Ci 1.484E+3 2.0 E+1

d. Other

1. Non-Compressible Waste m 1.139E+1 Ci 7.385E+0 2.0 E+1

2. Estimate of Major Nuclide Composition By Type of Waste Units Value Fe 55 34.8 Ni 63 30.7 Co 60 18.2 Co 58 7.4 Cs 137 5.1 Cs 134 2.8

b. Fe 55 44.4 Co 60 32.0 Ni 63 15.9 Co 58 2.5 Cs 137 2.3 Sb 125 1.0 Ni 59 0.9 Page 21

~ \

ANNUAL l TURKEY POINT UNITS 3 AND 4 RADIOACTIVE 1

EFFLUENTS RELEASE REPORT TABLE 6

2. Estimate of Major Nuclide Composition (continued)

Units Value Cr 51 30.5 Co 58 20.2 Fe 55 12.5 Co 60 11.7 Nb 95 9.2 Zr 95 7.4 Ni 63 6.6 Ce 144 1.0 d.l. Fc 55 56.8 Co 60 31.5 Ag 110m 5.4 Ni 63 3.2 Mn 54 2.8

3. Solid Waste Disposition Number of Mode of Transportation Destination Shipments 6 Sole Use Truck Barnwell, S.C.

22 (Note 3) Sole Use Truck S.E.G., Oak Ridge, TN B. Irradiated Fuel Shipments None Page 22

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENTS RELEASE REPORT TABLE 6 SOLID WASTE SUPPLEMENT Waste Total Total Curies Principal Type of Waste Category Type of Container Solidification Class Volume (Note 4) Radionuclides (Note 6) Reg-Guide (Note 7) Agent Ft (Note 5) 1.21 Class A 2055.8 1.20 None PWR Compactible l.b Non-Specification None Trash Strong Tight Package Class A 402.1 7.38 Ni,Pu" TRU* PWR Noncompactible l.d. 1 NRC Certified LSA None Trash >Type A 137 Class A 205.8 6.04 N 63 C PWR ion Exchange l.a NRC Certified LSA None Resins >Type A Class C 135.8 31.65 C'4, Co", Ni", Sr", PWR Filter Cartridges l.a NRC Certified LSA None Cs'", Sum of >Type A Nuclides th T'5 Years, TRU~

Class C 29.2 1483.71 Co, Ni, Sum of LWR Nonfuel Reactor l.c Type B None Nuclides with T'~ Components

<5 Years

• TRU - Alphawmitting transunranic nuclides with T'~ >5 years.

Page 23

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENTS RELEASE REPORT TABLE 6 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Note 1: Spent resin and process filter volume indicates the volume of waste shipped directly to the disposal site.

Note 2: Dry compressible waste volume indicates the volume of waste shipped to the disposal site following reduction by a waste processing facility. The volume shipped to the waste processing facility was 1,105.6 m'.

Note 3: Material shipped to Oak Ridge, Tennessee was consigned to a licensed processing facility for volume reduction or decontamination activities. The material remaining after processing was shipped by the processor to Barnwell, South Carolina for disposal.

Note 4: The total curie quantity and the radionuclide composition of solid waste shipped &om the Turkey Point Plant Units 3 and 4 are determined using a combination of qualitative and quantitative techniques. In general, 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 frequently 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.

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 radionuclides. The on-site analyses are performed either on a batch basis or routine basis using representative samples appropriate for the waste type. Off-site analyses are used to establish scaling factors or other methods for estimating difficult to measure radionuclides.

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 for the nuclide listed in Table 2 of 10 CFR 61.55.

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

Note 7: "Type of Container" refers to the transport package.

Page 24

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUE<NTS RE<LE<ASK REPORT JANUARY 1994 THROUGH DECEMBER 1994 ATTACHMENT 1 The following information is provided in Attachment 1:

i PNSC approval for the ODCM revisions i The revised List Of Effective Pages for the ODCM i The revised pages of the 0"'CM Pages dated 1/1/94 were reported with the 1993 Turkey Point Unit 3 and 4 Annual Radioactive effluent Release Report.

PTN-NC-94-075 TO: PNSC DATE: Aug 9, 1994 FROM: J. E. Berg DEPARTMENT: Nuclear Qxmistry

SUBJECT:

Off Site Dose Calculation Manual Attached are revised pages of the Off Site Dose Calculation Manual, (ODCM),

necessary to implement setpoint calculations for iodine and particulate channel alarm setpoints. This revision is in response to Condition Report 94-689 and will ensure that the limits of Tech Spec 3.11.2.1.b will not be exceeded. A table outlining how radiation monitor setpoints are determined is also included to this revision.

This revision was revi'ewed by Site Licensing, and Corporate Chemistry/HP with all comments resolved or incorporated as appropriate.

ames E. Berg adiochemistry Su vi or Richard N. Steinke Chemistry Supervisor FNSC APPRQ'LT.

MQR.

APPROVAL GATE

OFFSITE DOSE CALCULATION MANUAL FOR GASEOUS AND LIQUID EFFLUENTS FROM THE TURKEY POINT PLANT UNITS 3 AND 4 REVISION 5 AMENDMENT 1 CHANGE DATED 08 09 94 Florida Power and Light Company

Page 1 of 5 08/09/94 LIST OF EFFECTIVE PAGES Title Pacae Date Table of Contents Vi 01/01/94 Vii 01/01/94 Offsite Dose Calculation Manual 1 01/01/94 2 01/01/94 3 01/01/94 4 01/01/94 5 01/01/94 6 01/01/94 7 01/01/94 8 01/01/94

9. 01/01/94 10 01/01/94 11 01/01/94 12 01/01/94 13 01/01/94 14 01/01/94 15 01/01/94 16 01/01/94 17 Ol/01/94 18 01/01/94 19 01/01/94 20 01/01/94 21 01/01/94 22 01/01/94 23 01/01/94 24 01/01/94 25 01/01/94 26 01/01/94 27 01/01/94 28 Ol/01/94 29 01/01/94 30 01/01/94 31 01/01/94 32 01/01/94 33 01/01/94 34 01/01/94 35 08/09/94 36 01/01/94 37 08/09/94 38 08/09/94 39 08/09/94 40 01/01/94 41 01/01/94 42 01/01/94 43 01/01/94 44 01/01/94

Page 2 of 5 08/09/94 LIST OF EFFECTIVE PAGES Title Pacae Date Offsite Dose Calculation Manual 45 01/01/94 46 01/01/94 47 01/01/94 48 01/01/94 49 01/01/94 50 01/01/94 51 01/01/94 52 01/01/94 53 01/01/94 54 01/01/94 55 01/01/94 56 01/01/94 57 01/01/94 58 01/01/94 59 01/01/94 60 01/01/94 61 01/01/94 62 01/01/94 Appendix A A-1 07/20/84 A-2 12/19/84 A-3 07/20/84 A-4 07/20/84 A-5 07/20/84 A-6 07/20/84 A-7 07/20/84 A-8 07/20/84 A-9 07/20/84 A-10 07/20/84 A-11 07/20/84 A-12 07/20/84 A-13 07/20/84 A-14 07/20/84

'-15 07/20/84 A-16 07/20/84 A-17 07/20/84 A-18 07/20/84 A-19 07/20/84 A-20 07/20/84 A-21 07/20/84 A-22 07/20/84 A-23 07/20/84 A-24 07/20/84 A-25 07/20/84 A-26 07/20/84 A-27 07/20/84 A-28 07/20/84 A-29 07/20/84 A-30 07/20/84 A-31 07/20/84 A-32 07/20/84 ii

Page 3 of 5 08/09/94 LIST OF EFFECTIVE PAGES Title Pacae Date Appendix A A-33 07/20/84 A-34 07/20/84 A-35 07/20/84 A-3 6 07/20/84 A-37 07/20/84 A-38 07/20/84 A-39 07/20/84 A-40 07/20/84 A-41 07/20/84 A-42 07/20/84 A-43 07/20/84 A-44 07/20/84 A-45 07/20/84 A-46 07/20/84 A-47 07/20/84 A-48 07/20/84 A-49 07/20/84 A-50 07/20/84 A-51 07/20/84 A-52 07/20/84 A-53 07/20/84 A-54 07/20/84 A-55 07/20/84 A-56 07/20/84 A-57 07/20/84 A-58 07/20/84 A-59 07/20/84 A-60 07/20/84 A-61 07/20/84 A-62 07/20/84 A-63 07/20/84 A-64 07/20/84 A-65 07/20/84 A-66 07/20/84 Appendix B B-1 07/20/84 B-2 07/20/84 B-3 07/20/84 B-4 07/20/84 B-5 07/20/84

Page 4 of 5 08/09/94 LIST OF EFFECTIVE PAGES Title Pacae Date Appendix C C-1 11/12/92 C-2 11/12/92 C-3 11/12/92 C-4 11/12/92 C-5 11/12/92 C-6 11/12/92 C-7 11/12/92 C-8 11/12/92 C-9 11/12/92 C-10 11/12/92 Appendix D D-1 01/01/94 D-2 01/01/94 D-3 01/01/94 D-4 01/01/94 D-5 01/01/94 D-6 01/01/94 D-7 01/01/94 D-8 01/01/94 D-9 01/01/94 D-10 01/01/94 D-11 01/01/94 D-12 01/01/94 D-13 01/01/94 D-14 01/01/94 D-15 01/01/94 D-16 01/01/94 D-17 01/01/94 D-18 01/01/94 D-19 01/01/94 D-20 01/01/94 D-21 01/01/94 D-22 01/01/94 D-23 01/01/94 D-24 01/01/94 D-25 01/01/94 D-26 01/01/94 D-27 01/01/94 Appendix E E-1 01/01/94 E-2 01/01/94 E-3 01/01/94 E-4 01/01/94 E-5 01/01/94 E-6 01/01/94

Page 5 of 5 08/09/94 LIST OF EFFECTIVE PAGES Title Pacae Date Appendix E E-7 01/01/94 E-8 01/01/94 E-9 01/01/94 E-10 01/01/94 E-11 01/01/94 E-12 01/01/94 E-13 01/01/94 E-14 01/01/94 E-15 01/01/94 E-16 01/01/94 E-17 01/01/94 E-18 01/01/94 E-19 01/01/94 E-20 01/01/94 E-21 01/01/94 E-22 01/01/94 E-23 01/01/94 E-24 01/01/94 E-25 01/01/94 E-26 01/01/94 E-27 01/01/94 E-28 01/01/94 E-29 01/01/94 E-30 01/01/94 E-31 01/01/94 E-32 01/01/94 E-33 01/01/94 E-34 01/01/94 E-35 01/01/94 E-36 01/01/94 E-37 01/01/94 Figures 2-1 01/01/94 3-1 01/01/94 3-2 01/01/94

5. 1-1 01/01/94

5. 1-2 01/01/94

0 The dose to a person from tritium via the vegetation (fruit and vegetables),

air-grass-cow-milk, or air-grass-cow-meat pathways is evaluated at the nearest garden (with residence assumed) 3.6 miles west northwest of the plant. At that location, the reference atmospheric dis-persion factor is X/Q = 1 x 10 sec/m .

The dose commitment via a given pathway as a result of measured discharges from a release point is accumulated with (26) where:

the dose commitment to organ n of a person in age group a k = the counting index; either:

it may represent p, analysis of a grab sample w, a weekly sample analysis m, a monthly composite analysis, or q, a quarterly composite analysis Effluent Gas Monitor Alarm Set pints The radioactive gaseous effluent monitoring instrumen-tation channels alarm setpoints are set in accordance with Specification 3.3.3.6, to ensure the limits of Specification 3.11.2.1 are not exceeded.

Each radioactive noble gas effluent monitor setpoint is derived on the basis of total body dose equivalent rate at or beyond the site boundary. The setpoint derivation assumes that noble gas releases occur at ground-level.

For the purpose of deriving a setpoint, the distribution of radioactive noble gases in an effluent stream may be determined in one of the following ways:

35 08/09/94

Sg A factor to allow for multiple sources from different or common release points. The allow-owable operating setpoints will be controlled administratively by assigning a fraction of the total allowable release to each of the release sources.

Each monitoring channel has a unique response, h, which is determined by the instrument calibration.

Atmospheric dispersion depends upon the local atmospheric conditions. For the purpose of calculating a radioactive noble gas effluent monitor setpoint, the atmospheric dispersion factor, y/Q, will be based on prevailing meteorological conditions or on reference meteorological conditions. The minimum atmospheric dispersion off-site derived from reference meteorological conditions at the site boundary is 5.8 x 10~ sec/m't a location 1950 meters south southeast of the plant.

The applicable dose conversion factors, DF;, for deriving setpoints are in Table 3-5.

The limiting factor for Equation 27 is the total body dose rate limit of 500 mrem/year which is included in the 1.06 conversion factor. The use of the total body dose assumes that the total body dose will be the controlling dose rate and the dominant contributor to this dose will be Xe-133.

Each iodine and particulate effluent monitor setpoint may be calculated using the equation below, or a method which gives a lower setpoint value. Since the iodine and particulate channels are not required by Technical Specification 3.3.3.6, the primary method to ensure Technical Specification 3.11.2.1 is met is the performance of the sampling and analysis program in table 4.11-2 and the noble gas alarm setpoints.

S =

DR '2 S '600 ' '

R

+ BZg TA gp y, ~/g (28) where:

DR = the dose rate limit the effluent pathway is limited to; 1500 mrem/year.

37 08/09/94

a factor relating the airborne concentration time integral of radionuclide i to the dose equivalent TA~p to organ n of a person in age group a exposed via pathway p (inhalation), as described in section 3 ~ 3~3f 3600 = conversion constant, (sec/hr).

h = monitor response to activity deposited on the sample collection media, cpm/uCi.

t = period of time over which the effluent release takes place, (hours).

X~/Q = atmospheric dispersion factor adjusted for depletion by deposition at the off-site location of interest (sec/m ) .

A factor to allow for multiple sources from different or common release points. The allow-able operating setpoints will be 'ontrolled administratively by assigning a fraction of the total allowable release to each of the release sources.

V~ = Ratio of sample volume to release volume.

Other miscelleaneous radiation monitor alarm setpoints are determined as outlined below:

Channel Set oint Determination 3/4-R-11 Determined from Technical Specifications 3/4-R-12 Determined from Technical Specifications R-14 From ODCM Section 3.6 3/4-R-15 Between 2 and 5 times the monitor Background at the time of Calibration 3/4-R-17A/B Between 2 and 5 times the monitor Background at the time of Calibration R-18 From ODCM Section 2.6 3/4-R-19 From ODCM Section 2.6 3/4-R-20 Between 2 and 5 times the monitor Background at the time of Calibration SPING ch 1g2g3g6 From ODCM Section 3.6 or default maximum Sping ch. 5,7,9 From ODCM Section 3.6 Monitor setpoints may be changed, from between 2 and 5 times the monitor background at the time of calibration, in the event of system in leakage, changes in background radiation levels, or other 38 08/09/94

events that would necessitate further monitoring of the channel without recieving alarms.

3.7 Pro'ected Dose for Gaseous Effluents Technical Specification 3.11.2.4 requires that the gas decay tank system shall be operable and used to reduce radioactive materials in gaseous waste prior to their discharge if the projected gaseous effluent dose per reactor due to gaseous effluent releases to areas at and beyond the site boundary when averaged over 31 days exceeds 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation, and the ventilation exhaust treatment system shall be used to reduce radioactive materials in gaseous waste prior to their discharge if the projected gaseous effluent dose per reactor due to gaseous effluent releases to areas at and beyond the site boundary when averaged over 31 days exceeds 0.3 mrem to any organ.

Technical Specification 4.11.2.4.1 requires the doses, to areas at and beyond the site boundary, due to radioactive material released in gaseous effluent to be projected at least once per 31 days.

This requirement is satisfied by extrapolating the dose to date during the current month to include the entire month.

The dose to date is calculated as described in Sections 3.4.1, 3.4.2, and 3.5.2.

The dose is projected with the relation:

31 'D X (30) where:

P = the projected dose during the month, (mrem) 31 = number of days in a calendar month, (days)

X = number of days in current month to date represented by available radioactive effluent sample, (days)

D = dose to date during current month calculated according to Sections 3. 4. 1, 3. 4. 2, and 3. 5. 2, (mrem), i. e., gamma, beta, or organ dose respectively.

Alternately, the monthly dose may be projected by computing the dose accumulated during the most recent month and assuming the result represents the projected dose for the current month. The dose during the proceeding month will be computed as described in Sections 3.4.1, 3.4.2, and 3.5.2.

39 08/09/94

The limiting factor when using equation 27 to determine a setpoint is the total body dose rate limit of 500 mrem/yr which is included in the 1.06 conversion factor. The use of total body dose assumes that the total body dose will be the controlling dose rate and the dominant contributor to this dose will be Xe-133.

Each iodine and particulate effluent monitor setpoint may be calculated using the equation below, or a method which gives a lower setpoint value.

DR'A'S'3600'O'V f azg S =

TA g '~/g +

(28) where:

DR = the dose rate limit the effluent pathway is limited to; 1500 mrem/year.

a factor relating the airborne concentration TAanip time integral of radionuclide i to the dose equivalent to organ n of a person in age group a exposed via pathway p (inhalation), as described in section 3.3.3, mrem r pCi/m  ; See Appendix A.

3600 conversion constant, (sec/hr).

monitor response to activity deposited on the sample collection media, cpm/uCi.

period of time over which the effluent release takes place, (hours).

Xd/Q atmospheric dispersion factor adjusted for depletion by deposition at the off-site location of interest (sec/m ) .

A factor to allow for multiple sources from different or common release points. The allow-able operating setpoints will be controlled administratively by assigning a fraction of the total allowable release to each of the release sources.

VR Ratio of sample volume to release volume.

41 08/09/94

P I I "I

3

Other miscellaneous radiation monitor alarm setpoints are determined as outlined below:

Channel Set oint Determination 3/4-R-11 Determined from Technical Specifications 3/4-R-12 Determined from Technical Specifications R-14 From ODCM Section 3.6 3/4-R-15 Between 2 and 5 times the monitor Background at the time of Calibration 3/4-R-17A/B Between 2 and 5 times the monitor Background at the time of Calibration R-18 From ODCM Section 2.6 3/4-R-19 From ODCM Section 2.6 3/4-R-20 Between 2 and 5 times the monitor Background at the time of Calibration SPINGch 1g2g3g6

~ From ODCM Section 3.6 or default maximum Sping ch. 5,7,9 From ODCM Section 3.6 Equation 28 is based on limiting dose due to iodine, tritium and particulates to less than 1500 mrem/year. These factors in this equation assume that a hypothetical infant located at the site boundary where the minimum atmospheric dispersion occurs is the receptor. This approach assures the most conservative estimate of dose. When this assumption is used, the infant thyroid via the inhalation pathway is the critical organ and controlling pathway respectively. The dose transfer factor is based solely on the radioiodines (I-131, I-133) because the radioiodines contribute essentially all of the dose to the infant s thyroid, when estimating dose due to iodines, tritium, and particulates with half lives greater than 8 days.

42 08/09/94

0 1 W

~ lk l'