Text

Semiannual Radioactive Effluent Release Rept,Jul-Dec 1986
	ML20212G591
Person / Time
Site:	Crystal River
Issue date:	12/31/1986
From:	Johnson S, Mckee P; FLORIDA POWER CORP.
To:	;
Shared Package
ML20212F739	List: 3F0287-14, Forwards Semiannual Radioactive Effluent Release Rept, Jul-Dec 1986. Future Repts Will Include Statement Re Reported Site Boundary Doses to Individual Members of Public; ML20212G591;
References
	NUDOCS 8703050372
	Download: ML20212G591 (74)
	v • d • e

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 7/1/86 - 12/31/86 FLORIDA POWER CORPORATION CRYSTAL RIVER - UNIT 3 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET No. 50-302 FEBRUARY, 1987.

-b Approved by:

e Di' rector, Nuclear Plant Operations 1/23,[I7 Date:

Approved R.y:

M L#W Manager, Sit'eNucleafServices Date:

2-2.3-87 l

1b hk 8703050372 870227 PDR ADOCK 05000302 4 R

PDR l

TABLE OF CONTENTS F.AG.E I

Introduction 1

II Releases of and Doses from Gaseous Effluents 7

III Releases of and Doses from Liquid Effluents 18 IV Solid Waste Shipments 31 V

Meteorological Data 35 VI Technical Specification Reports 64 VII' ODCM and PCP Changes 65 i

h LIST OF TABLES FAGE

-I-1A Summation of. Doses to Individuals from Gaseous and Liquid Effluent Releases - Third and Fourth Quarters 2

I-18 Summation of Doses to Population from Gaseous and Liquid Effluent Releases - Third and Fourth Quarters 3

I-1C

. Annual Doses to Individuals from all Releases 4

II Gaseous. Effluents - Summation of All Releases 11 11-2 Gaseous Effluents - Ground Level Releases 12

-II-3 Doses to Individuals from Continuous Gaseous 14 Effluent Releases II-4

' Doses to Individuals from Batch Gaseous Effluent.

Releases 15

-II-5 Doses to the Population from Continuous Gaseous

' Effluent Releases 16 II-6 Doses to the Population from Batch Gaseous Effluent Releases 17 III-1 Liquid Effluents - Summation of All Releases 24 III-2 Summation of Nuclides in Liquid Effluent Releases 25 III-3 Doses to Individuals from Liquid Effluent Releases -

Third and Fourth Quarters 28

-III-4 Doses to the Porulation from Liquid Effluent Releases - Third and Fourth Quarters 29 IV-1 Summation of Solid Waste Irradiated Fuel Shipments 31 1

IV-2 Effluent and Waste Disposal Report Shipment Summary 32 V-1 Summation of Meteorological Conditions at 33' (10 Meters) - Third Quarter 35 V-2 Summation of Meteorological Conditions at 33' (10 Meters) Concurrent with Batch Gaseous Effluent Releases - Third Quarter 43 V-3 Summation of Meteorological Conditions at 33' (10 Meters) - Fourth Quarter 50 V-4 Summation of Meteorological Conditions at 33' (10 Meters) Concurrent With Batch Gaseous Effluent Releases - Fourth Quarter 57 ii

LIST OF FIGURES PAGE I-1

-Whole Body Doses to the Population From Gaseous Effluent Releases 5

I-2 Whole Body Doses to the Population From Liquid Effluent Releases 6

II Gaseous Releases-Fission and Activation Gases and Tritium 13 III-1 Methods of Meeting 10 CFR 20, Appendix B, Table II, Column 2, MPC Limits 23 III-2 Liquid Releases-Fission and Activation Products 3

(Exclusing H, Gases, Alpha) 27 IV-1 Volume cf Solid Waste Shipped Off-Site 34 IV-2 Ratio of Content to Volume of Waste Shipped off-Site 34 I

l

[

I l

iii l

I.

INTRODUCTION This Effluent and Waste Disposal Report is submitted as required by Techni-cal' Specification 6.9.1.5.d to the Crystal River Unit 3 Facility Operating

. License No. DPR-72.

The data in this report-covers the period from July 1 to December-31, 1986.

There have been no changes to the Technical Specification Requirements for effluents and waste disposal of the Facility Operating License during the period of this report.

Crystal River _ Unit 3 has had no significant measurable radiological. impact on the surrounding environment drring the reporting period.

This is based 1

on the Radiological Environmental Monitoring -Program data and the-doses calculated for individuals and the population due to effluent releases being significantly below the levels required by 10 CFR 50, Appendix I.

The summations of gaseous _ and liquid effluents and solid waste shipments

-are in accordance with the tables in Regulatory Guide 1.21 (Rev. 1, 6/74)

Appendix B.

The individual and population doses were calculated using GASPAR (for gas-eous effluents) and LADTAP (for liquid effluents) computer codes obtained from the Nuclear Regulatory Commission and revised to include site specific data wherever possible.

With respect to doses to individual members of the public, a study was performed to compare the potential dose to members of the public. at the site boundary to that of the worst case individual inside the site boundary.

The evaluation considered only doses due to gaseous effluents:

exposure via liquid effluents was not considered since drinking water pathways are not available, and the seafood ingestion pathway is not site boundary dependent. Meteorological conditions, building wake effects, receptor distance, and receptor residence times were considered.

The study demonstrated that a member of the public at the site boundary receives a dose that-is~several times higher than the worst case seaber of

.the public inside the site boundary. Therefore, the dose summaries in this report are conservative estimates for all members of the public.

The values reported for the activity of nuclides released are the actual measured activities.

The totals of activity released is a total of only the -nuclides that had measured activity.

If no activity for a principle nuclide was detected then an a priori LLD is reported.

It should be noted that Figure III-2 of this report supercedes Figure III-2 of previous reports in that the values on the previous graphs are low by

-one order of magnitude.

l 1

_ _. ~. _ _ _ _ _, _ _ _ _ _.. _ _ _. _. - _.

f TABLE I-1A-4 i -

SUMMATION OF DOSES TO INDIVIDUALS FROM GASEOUS AND LIQUID EFFLUENT RELEASES THIRD OUARTER Beta Air' Dose = 6.89E-01'arads/yr (Design Objective = 2.00E+01'arad/yr) l Gamma Air Dose'= 2.35E-01 mrads/yr (Design Objective = 1 00E+01 mrad /yr).

Whole Body Dose Distance 1

(Mi.) and Design l

Effluent Release Direction Ace Group Orean D2Ag.

Oblectives j-(area /yr).

-(area /yr)

Continuous Gaseous 1.00 N Child 2.79E-02 5.00E+00 Batch Gaseous 1.00 N All 1.19E-01 Continuous Liquid 0.00E-00.

5.00E+00 Batch Liquid Teen 1.80E-02 Organ Dose l

Continuous Gaseous 1.00 N Child

. Skin.

6.18E-02 1.50E+01 Batch Gaseous 1.00 N All Skin-3.42E-01 u

i continuous Liquid 0.00E-00 5.00E+00 j

Batch Liquid Adult

.GI-LLI 3.24E-01 i

FOURTH OUARTER Beta Air Dose = 2.65E-01 mrads/yr.(Design Objective = 2.00E+01 mrad /yr)

Gamma Air Dese = 1.16E-01 mrads/yr (Design Objective = 1.00E+01.arad/yr)

Whole Body Dose Continuous Gaseous 1.00 NME Child 6.17E-02 5.00E+00 Batch Gaseous 1.00 N Child / Infant 1.42E-02 Continuous Liquid Teen 1.26E-04 5.00E+00 i

Batch Liquid Teen 3.87E-02

.l Oraan Dose j

Continuous Gaseous 1.00 NNE.

Infant Thyroid 7.71E-01 1.50E+01 Batch Gaseous 1.00 N Infant Thyroid 5.27E-02 3

Continuous Liquid Teen Liver

'2.08E-04 5.00E+00 Batch Liquid Adult GI-LLI 1.95E-01 j

1 i

I

3 TABLE I-1B SUle4ATION OF DOSES TO THE POPULATION FROM GASEOUS AND LIQUID EFFLUENT RELEASES THIRD OUARTER l

Whole Body Dose Organ Dose Effluent Release Dose Desian Obiectives Organ Dose Desian Obiectives (MAN-REM /YR)

(MAN-REM /YR)

(MAN-REN/YR)

Continuous Gases 1.35E-02 5.00E+02 Skin 3.96E-02 5.00E+02 Batch Gaseous 5.65E-03 Skin 1.97E-02 continuous Liquid 0.00Et00 0.00E+00 Batch Liquid 1.36E+00 GI-LLI 2.80E+01 FOURTH OUARTER Continuous Gaseous 2.95E-02 5.00E+02 Skin 8.99E-02 5.00E+02 l

Batch Gaseous 2.15E-01 Skin 9.03E-01 Liver 2.54E-02 Continuous Liquid 1.52E-02 Batch Liquid 4.24E+00 GI-LLI 2.02E+01 l

1

~

4 4

TABLE I-1C ANNUAL DOSES TO INDIVIDUALS FROM ALL RELEASES Whole Body Dose Orean Dose (area /qtr)-

(area /qtr) ist Ouarter 1986 Continuous Gases Effluents 1.51E-03 6.55E-03 i

Batch Gaseous Effluents 0.00E+00 0.00E+00-Continuous Liquid Effluentsf 2.14E-08 2.14E-08 Batch Liquid Effluents 5.00E-03 1.47E-02 2nd Ouarter 1986 Continuous Gases Effluents 3.03E-04 8.55E-03 Batch Gaseous Effluents 1.43E-06 9.73E-06 Continuous Liquid Effluents 5.90E-04 9.33E-04 Batch Liquid Effluents 4.25E-03 2.75E-02 a

3rd Ouarter 1986 Continuous Gases Effluents 6.98E-03 1.54E-02 Batch Gaseous Effluents 2.98E 8.55E-02

)

Continuous Liquid Effluents 0.00E+00 0.00E+00 Batch Liquid Effluents 4.50E-03

.8.10E-02 4th Ouarter 1986 Continuous Gases Effluents 1.54E-02 1.93E-01 Batch Gaseous Effluents 3.55E-03 1.32E-02 Continuous Liquid Effluents 3.15E-05 5.20E-05 l

Batch Liquid Effluents 9.68E-03 4.89E-02 i

Total (area /yr)

8.16E-02 4.95E 1 i

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- FIGURE I W OLE BODY DOSES TO THE POPULATION FROM GASEOUS EFFLUENT RELEASES EO h

~

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E ag E-2 i

w O

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1981 1982 1983 1984 1985 1986 5

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FIGURE - I -

IMOLE 800Y DOSES TO THE POPULATION FROM LIQUID EFFLUENT RELEASES E1 S

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- - t 1981 1982 1983 1984 1985 1986 6

L

II.

RELEASES OF AND DOSES FROM GASEOUS EFFLUENTS 1.

Reculatory Limits The Technical Specification limits for gaseous effluent releases are as follows:

A.

Specification 3.11.2.1 The dose rate at or beyond the SITE BOUNDARY, due to radioactive materials released in gaseous effluents, shall be limited as follows:

1 a.

Noble gases: less than or equal to 500 area / year total body and less than or equal to 3000 ares / year to the skin.

[

b.

Iodine-131,

Tritium, and radioactive particulates with half-lives of greater than 8 days: less than or equal to

)

1500 ares / year to any organ.

B.

Specification 3.11.2.2 The air dose at or beyond the SITE BOUNDARY, due to radioactive noble gases released in gaseous effluents shall be limited to:

a.

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

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

C.

Specification 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from Iodine-131, Tritium, radioactive particulates with half-lives greater than 8 days in gaseous effluents released from the site to areas at or beyond the SITE BOUNDARY shall be limited as follows:

a.

During any calendar quarter: less than or equal to 15 area to any organ.-

D.

The maximum activity to be contained in one waste gas storage

- tank shall not exceed 39,000 Curies (considered as Xe-133).

2.

Maximum Permissible Concentrations The maximum permissible concentrations of nuclides in gaseous releases is based on the resultant doses at the site bour.dary as determined from the concentrations of nuclides at the release point. The OFFSITE DOSE CALCULATION MANUAL provides the equations and dose factors that relate to the gaseous activity to be released to doses at the site 7

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r-w-

--,,,,..,m-

,,--,-,,_m,,

y.

m.--

-.-,4,

-e

-r-,-r,

~v.--

boundary,.and restrictions are placed on quarterly and yearly release rates..- The gaseous releases do not exceed the cor. centration limits

- specified in 10 CFR 20 and.are as. low as reasonably achievable in accordance, with the requirements of 10 CFR 50.

The total dose and dose rate calculations are derived from the methodology-in NUREG-0133 and the dose factors in Reg. Guide 1.109.

3.

Measuramants and Anoroximations of Total andioactivity The gaseousLeffluent release via the Auxiliary Building Exhaust.is treated as a continuous release subdivided into discrete periods of filter changes and the radioactivity measured as follows:

A.

Fission and Activation Gases - The total activity released is based on the total vent flow and the activity cf ' the T individual nuclides obtained.from an isotopic aaalysis of a grab sample taken at least weekly.

B.

Iodines - The activity released as Iodine-131, 133, and 135 is based on the charcoal' cartridge activities (RMA-2I), the particulate filters activities (RMA-2P) and the total vent flow.

C.

Particulates. - The activity released via particulates with half-lives greater than eight days is determined by isotopic analysis of particu-late filters (RMA-2P) and the total vent flow.

The radioactivity. released by batch releases of the Waste Gas Decay Tanks via the Auxiliary Building Exhaust is measured as follows:

A.

Fission and Activation Gases - The activity released is based on the volume released and the activity of the individual nuclides obtained from an isotopic analysis of a grab sample taken prior to the release.

B.

Iodines - The iodines from batch releases are included in the iodine determination from the continuous Auxiliary Building releases.

C.

Particulates - The particulates from batch releases are included in the particulate determination from the continuous Auxiliary Building release.

D.

Tritium - The activity released as tritium is based on a grab sample analysis of-each batch and the batch volume.

The radioactivity released by purge releases of the - Reactor Building through the Reactor Building vent is measured as follows:

A.

Fission and Activation Gases - The total activity released is based on the total vent flow and the activity of the individual nuclides obtained from an isotopic analysis of a grab sample taken prior to the beginning of the Reactor Building purge and at least weekly during continuous ventilation.

i 8

B.

Iodines - The total curies released as lodine-131, 133 and 135 were determined from the charcoal cartridge activities (RMA-11) and - the particulate filter activities (RMA-1P).

C.

Particulate - The total curies released via particulates with half-lives greater than eight days are determined by isotopic analysis of each purge' particulate filter (RMA-1P).

D.

Tritium - The total curies released as tritium are based on grab samples taken for each purge (or the average if more than one grab sample was taken).

Estimated errors are based on errors in counting equipment calibration, counting statistics, vent flow rates, vent sample flow rates, nonsteady re-lease rates, - chemical yield factors and sample losses for such items as charcoal cartridges.

A.

Fission and Activation Gas Total Release as calculated from process monitor readings and grab sample isotopics.

Monitor Statistical Error 30%

Monitor Error in Calibration 50%

Vent. Flow Rate 10%

Non-Steady Release Rate

._2Q1 110%

B.

I-131 Total Release as calculated from charcoal and particulate filter activity.

Statistical Error 60%

Counting Equipment Calibration 10%

Vent Flow Rate 10%

Vent Sample ~ Flow Rate 10%

Non-Steady Release Rate 10%

Losses from Charcoal Cartridge

._1Q1 110%

9

C.

Particulates with half-lives greater than eight days release as calcu-lated from particulate filter activities.

Statistical Error 60%

Counting Equipment Calibration 10%

Vent Flow Rate 10%

Vent Sample Flow Rate 10%

Non-Steady Release Rate

_JD1 100%

D.

Total Tritium release as calculated from periodic grab sample analy-ses.

Water Vapor in Sample Stream Determination 20%

Vent Flow Rate 10%

Counting Calibration and Statistics' 10%

Non-Steady Release Rate

_1Q1 90%

4.

Batch and Unclanned Releases The batch gaseous effluent releases may be summarized as follows:

7/1/86 - 12/31/86 Number of Batch Releases 3.70E+01 Total. time for all releases (minutes) 3.79E+04 Maximum time for any one release (minutes) 1.51E+03 Average time for all releases (minutes) 1.02E+03 Minimum time for any one release (minutes) 1.10E+02 Number of Unplanned Releases 0.00E+00 Total Unplanned Activity Released (Curies) 0.00E+00 The summation of gaseous effluent releases is in Table II-1 and the summa-tion of nuclides in gaseous effluent ground level releases is in Table II-2.

10

(

TABLE II-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 7/1/86 - 12/31/86 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 3

4 Error %

A.

Fission and Activation Gases 1.

Total Release Ci 7.34E+02 1.83E+03 1.10E+02 2.

Average Release Rate for Period uCi/sec 9.23E+01 2.30E+02 3.

Percent of Technical Specification Limit t

6.49E-01 1.69E+00 B.

Iodines 1.

Total Iodine - 131 Ci 9.57E-06 6.23E-04 1.10E+02 2.

Average Release Rate for Period uCi/sec 1.20E-06 7.84E-05 3.

Percent of Technical Specification Limit 1.07E-01 5.30E+00 C.

Particulates 1.

Particulates with half-lives > 8 days Ci 2.55E-04 2.60E-05 1.00E+02 2.

Average Release Rate for Period uCi/sec 3.21E-05 3.27E-06 I

3.

Percent of Technical Specification Limit i

1.07E-01 5.30E+00 4.

Gross Alpha Radioactivity Ci 2.49E-08 4.02E-06 D.

Tritium i

1.

Total Release Ci 8.75E+00 6.33E+00 9.00E+01 2.

Average Release Rate for Period uCi/sec 1.10E+00 7.96E-01 3.

Percent of Technical Specification Limit 1.07E-01 5.30E+00 11

TABLE II-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 7/1/86 - 12/31/86 GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 1.

Fission gases krvoton-85 Ci 6.17E-01 9.64E+00 krvoton-85m Ci 1.52E+00 8.81E+00 9.39E-03

2. 58E- 03 krypton-87 Ci 4.68E-01 3.10E+00 (6.53E-05 (1.35E-03 krvoton-88 Ci (1.42E+01 1.06E+01 (8.94E-05 (1.84E-03 xenon-133 Ci 3.90E+02 1.35E+03 2.99E+02 3.19E+02 xenon-133m Ci 2.36E+00 1.39E+01 1.53E+00 1.94E+00 xenon-135 Ci 3.18E+01 9.52E+01 4.18E-01 5.09E-01 xenon-135m Ci 7.20E-01 xenon-131m Ci 2.15E+00 7.37E+00 3.53E+00 6.47E+00 xenon-138 C :.

<5.28E+01 (5.83E+01 (3.33E-04 (6.87E-03 unidentified Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for Period Ci 4.28E+02 1.49E+03 3.06E+02 3.38E+02 Iodines iodine-131 Ci 9.57E-06 6.06E-04 (2.57E-08 1.68E-05 iodine-132 Ci iodine-133 Ci 4.16E-06 4.63E-07 Total for Period Ci 9.57E-06 6.10E-04 0.00E+00 1.73E-05 3.

Particulates colbalt-58 Ci

<8.80E-04 (9.72E-04 (5.55E-09 (1.14E-07 cesium-134 Ci (1.74E-03 (1.92E-03 (1.10E-08 (2.26E-07 cesium-137 Ci

<1.10E-03 (1.22E-03 (6.94E-09 (1.43E-07 mancanese-54 Ci

<1.27E-03 (1.41E-03 (8.03E-09 (1.66E-07 iron-59 Ci (3.73E-03 (4.12E-03 (2.35E-08 (4.85E-07 cobalt-60 Ci (2.12E-03 (2.34E-03 (1.34E-08 (2.76E-07 zine-65 Ci (2.43E-03 (2.69E-03 (1.53E-08

<3.16E-07 Colybdenum-99 Ci

<6.19E-03 (6.84E-03 (3.91E-08 (8.06E-07 cerium-141 Ci 2.55E-07 (1.41E-03 (8.03E-09 (1.66E-07 cerium-144 Ci (4.30E-03 (4.75E-03 (2.71E-08

<5.59E-07 strontium-89 Ci 1.24E-06 6.32E-06 (3.65E-08 4.43E-09 strontium-90 Ci 7.77E-08 1.59E-07 (3.~5E-08 (7.53E-07

-=

unidentified Ci 2.53E-04 1.88E-05 0.00E+00 7.44E-07 Total Ci 2.55E-04 2.53E-05 0.00E+00 7.48E-07 12

F.

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- FIGURE II GASEOUS RELEASES-FISSION AND ACTIVATION GASES AND TRITIUM O - Fission and Activation Gases O - Tritium E3 l

l E2 s.

Er.)

u El l

l EO t

.._.__.__p_____..

_. _.. _ _ _.... _ _:. _ _ q_ ___ _ __ _. j t

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E-1 1982 1983 1984 1985 1986 1981 13

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t TABLE II-3 Doses to Individuals fros. Continuous Gaseous Effluent Releases I

THIRD OUARTER Beta Air Dose = 7.63E-02 mrads/yr (1.0 mile,'N) l Gamma Air Dose = 3.11E-02 arads/yr (1.0 mile,-N)

I

(

_ Distance Distance

'Whole Body Dose Oraan Dose i

I (Mi.) and Dose (Mi.) and Dose I

Pathway Direction Ace Group (area /vr)

Direction Ace Group Organ (area /vr) i

.1.89E-02 1.00 N-Skin.

5.29E 1 Plume Innersion 1.00 N Skin 2.11E -'

g i

Ground Contamination 1.00 N 1.74E-07.

1.00 N

)

Inhalation 1.00.N Teen 1.69E-03 1.00 N--

Teen.

Thyroid 1.71E-03:

j Vegetable Consumption 1.00 N Child 3.33E-03 1.00 N.

Child Thyroid 3.74E-03 I

Cow Milk Consumption 1.00 N Infant 1.96E-03 1.00 N Infant ^

Thyroid 1.13E-02.

i Goat Milk Consumption 1.00 N Infant 3.99E-03 1.00 N Infant Thyroid 1.52E-02 7

l Meat Consumption-1.00 N Adult 2.66E-04~

1.00 N Adult

. Thyroid 3.10E-04 j

5 Total 1.00 N Child' 2.79E-02 1.00 N Child

-Skin 6.18E-02 l

TOURTH OUARTER Beta Air Dose = 1.88E-01 arads/yr.(1.0 mile, NNE)

{

Gamma Air Dose = 9.14E-02 mrads/yr (1.0 mile, NNE) whole Body Dose Oraan Dose i

Distance Distance-l (Mi.) and Dose (Mi.) and Dosei j

Pathway Direction Ace Group (area /vr)

Direction Ace Group Orean (area /vr) i j

Plume Immersion 1.00 NME 5.67E-02

'1.00 NME-

' Skin 1.43E-01 i

Ground Contamination 1.00 NME 5.76E-06 1.00 NNE-l Skin.

6.99E-06 i

Inhalation 1 00 NME_

Teen 8.51E-04

-1.00 NNE-Teen.

Thyroid)1.74E-03 j,....

Vegetable Consumption 1.00 NME Child 1.74E-03 1.00 NME Child Thyroid 1.75E-02

' "f' Cow Milk Consumption 1.00 NNE Infant 1.41E-03 1.00 NME Infant.

Thyroid 3.24E-01' Goat Milk Consumption 1.00 NNE Infant 2.52E-03 1.00_NME Infant'

. Thyroid 3.89E-01 j

Meat Consumption 1.00 NNE Adult 1.36E 1 00 NNE Child Thyroid 1.78E-03f',

~

j Total 1.00 NME Child.

6.17E-02 1.00 NNE-Infant Thyroid 7.71E-01 i

r i

+%

.1-.*

r

TABLE II-4 Doses to Individuals from Batch Gaseous Effluent Releases THIRD OUARTER Beta Air Dose'= 6.13E-01 mrads/yr (1.0 mile, N)

Gamma Air' Dose = 2.04E-01 mrads/yr (1.0 mile, N)

Whole Body Dose Oraan Dose Distance Distance (Mi.) and Dose (Mi.) and Dose Pathway Direction Age Group furea/vr)'

Direction Ace Group Organ (aren/yr)

Plume Immersion 1.00 North 1.19E-01

-1.00 North Skin

-3.42E-01 Ground Contamination 1.00 North 0.00E+00-1.00 North.

0.00E+00 Inhalation 1.00 North 1.00 North.

Vegetable Consumption 1.00 North.

1.00 North Cow Milk Consumption 1.00 North 1.00 North Goat Milk Consunption 1.00 North 1.00 North Meat Consumptien 1.00 North 1.00 North Total 1.00 North All 1.19E 1.00 North All Skin 3.42E-01 FOURTH OUARTER Beta Air Dose = 7.67E-02 mrads/yr (1.0 mile, N)

Gamma Air Oose = 2.42E-02 mrads/yr (1.0 mile, N)

Whole Body Dose Oraan Dose Distance Distance (Mi.) and Dose (Mi.).and Dose Pathway Direction Age Group furen/vrl' Direction Ace Group Organ farem/vri Plume Immer sion 1.00 North 1.41E-02 1.00 North Skin-4 33E-02 Ground Contamination 1.00 North 3.13E-07.

1.00 North

~ Skin 3.80E-07 Inhalation 1.00 North Teen 1.60E-05.

1.00 North child-

. Thyroid 6.75E-05 Vegetable Consumption 1.00 North Child-3.22E-05 1.00 North Child Thyroid 8.91E-04 Cow Milk Consumption 1.00 North Infant 4.17E-05 1.00 North Infant Thyroid 1.75E-02 Goat Milk Consumption 1.00 North Infant 6 54E-05 1.00 North Infant

Thyroid.2.10E-02 Meat Consumption 1.00 North' Adult 2.64E-06 1.00 North ' Adult-Thyroid 9.32E-05 Total 1.00 North Child / Infant 1.42E-02 1.00 North Infant Thyroid 5.27E-02;

c,

/,

TABLE II-5 Doses to'the Population from continuous Gaseous Effluent Releases THIRD OUARTER Whole B0dy Dose Organ Dose Pathway (Man-Rea/Yr)

Organ Dose (Man-Ram /Yr)

Plume Immersion 1.09E-02~

Skin 3.70E-02 Ground Contamination 3.68E-08 Skin-4.46E-08 Inhalation 1.45E-03 Thyroid 1.46E-03 Vegetable Consumption 7.96E-04 Thyroid-9.38E-04 zMilk Consumption 1.5$E-04 Thyroid 2.28E-04 Neat Consumption 1.59E-04 Thyroid' 1.68E-04 C'

Total 1.35E-02 Skin 3.96E-02 FOURTH OUARTER 1

Whole Body Dose Organ Dose Pathway (Man-Rem /Yr)~

Organ Dose (Man-Rem /Yr)

~ Plume Immersion 2.83E-02 Skin 8.99E-02 Ground contamination 1.25E-06 Skin 1.51E-06 Inhalation 7.10E-04 Thyroid 1.27E-03 Vegetable Consumption 3.42E-04 Thyroid 4.51E-03 Milk Consumption 9.49E-05 Thyroid 3.47E-03 Meat Consumption 7.44E-05 Thyroid 3.80E-04 Total 2.95E-02 Skin 9.11E-02 I

b 4

1 1

16 3

,r.,,---r-,,

v..--,,-,,-,

...=,-,,e~-..

---,,,e,

,--,.,---,va, e,,

a-,

,n-

TABLE II-6 l

Doses to the Population from Batch Gaseous Effluent Releases I

THIRD OUARTER l

Whole Body Dose Organ Dose l.

. athway (Man-Res/Yr)

Oraan Dose (Man-Res/Yr)

Plume Immersion 5.65E-03 Skin 1.97E-02 Ground Contamination Inhalation-Vegetable' Consumption Milk Consumption Meat Consumption.

Total 5.65E-03 Skin 1.97E-02 FOURTH OUARTER Whole Body Dose Organ Dose Pathway (Man-Res/Yr)

Organ Dose (Man-Res/Yr Plume Immersion 2.12E-01 Skin 9.00E-01 Ground Contamination 4.31E-08 Skin 5.23E-08 Inhalation 3.31E-04 Thyroid 3.54E-04 Vegetable Consumption 1.04E-03 Thyroid 1.26E-03 Milk Consumption 6.07E-04 Thyroid 7.28E-04 Meat Consumption 5.20E-04 Thyroid 5.31E-04 Total 2.15E-01 Skin 9.03E-01 17

III. RELEASES OF AND DOSES FROM LIQUID EFFLUENTS There are four sources of liquid effluents released to the discharge canal:

1) the Laundry and Shower Sump Tanks, 2) the Evaporator Condensate Storage Tanks, 3)'the Regeneration Waste Neutralization Tank, and 4) the Condenser Hotwell.

The Laundry Tanks and Evaporator Condensate Storage Tanks are batch type releases made through the plant liquid release monitor RML-2.

The Regeneration Waste Tank discharges are batch type, the Condenser Hot-well discharges are continuous types, both of which are made through plant liquid release monitor RML-7.

1.

Reaulatory Limits The Technical Specification - limits for' liquid effluent releases are as follows:

Specification 3.11.1.1 The ' concentration of radioactive material released to UNRESTRICTED AREAS shall be less ' than or equal to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble gases, the concentration shall be less than or equal to 2x 10-4 microcuries/ml. total activity.

Specification 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive material is in liquid effluents released to UNRESTRICTED AREAS shall be limited as follows:

a.

During any calendar quarter to less than or equal to 1.5 arem to the total body and less than or equal to 5 arem to any organ.

b.

During 'any calendar year to'less than or equal to 2 mres to the total body and to less than or equal to 10 area to any organ.

I.

l l

18 t

2.

Radionuclide concentrations The maximum permissible concentration values used in determining allowable liquid release concentrations are taken from 10 CFR 20, Appendix B,

Table II, column 2.

Release rate and dilution" ratio for each batch are determined by'a mixed nuclide MPC calculation' performed before the release of the. batch.

The concentration of each of the gamma emitting nuclides specifically noted in Figure' III-1 is measured individually due to the requirements of the Technical Specification.

If any of the radionuclides, manganese-54, iron-59, cobalt-58, cobalt-60, zine-65, cesium-134, molybdenua-99, cesium-137, cerium-141, or cerium-144, are less than their LLD value, an a priori systen LLD for each isotope is used to calculate the minimum detectable release activity.

Individual measurements are made on proportional composite liquid radwaste samples to determine the Fe-55, Sr-89 and Sr-90 concentration to be applied to individual release calculations.

A distillation and liquid scintillation counting technique is used to measure the tritium concentration on each batch release.

The measured and calculated concentration values for each batch are used to calculate the dilution ratio, release rate, and dilution rate, and expected doses prior to the release.

The ' release data is then updated with actual release conditions and stored on a computer disc file.

The disc file data is used to assure that quarterly and annual release limits are not exceeded.

A.

Fission. and activation products - The total release values (not including tritium, gases, gross alpha) are comprised of the sum of the individual radionuclide activities released to the discharge canal for the respective quarter.

These values represent the activity known to be present in the liquid radwaste effluent.

Percent of applicable limit is determined-by dividing the calculated total body or organ dose by the applicable Technical Specification limit and then multi-

. plying the result by 100.

The most restrictive percent of limit is then used.

B.

Tritium - The measured tritium concentration.is used to calculate the total release and average diluted concentration during each period.

Average diluted concentration divided by the MPC limit, 3 x 10-3 uCi/al, is converted to give the percent of applicable limit.

i l

I 19

- 3 t

.t C.

Dissolved'_and entrained gases - Concentrations of dissolved and en-trained gases in liquid effluents are seasured by Ge(Li) spectroscopy on a sample.fron each liquid release.

Dissolved ~and entrained gases' for which measured concentrations-are determined include noble gases with half : lives greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Iodine radionuclides in any -

'j form are determined during the isotopic analysis for each release, therefore a separate analysis for possible gaseous forms is not per-I formed.

~

The average' diluted ~ concentration of the dissolved and entrained gases-is divided by the MpC limit, 2 x 4 uCi/al, and converted to give the percent of' applicable limit.

~

3.

Mammuramants and Acornrimations of Total Radioactivity Details of the analytical procedures for liquid radwaste analysis are as

~

follows:

Measurement Frequency Method 1.

Gamma Isotopic Each Release Ge(Li) spectrometry with on-line computer 2.

Sr-89 Monthly Composite Chemical separation and gas flow proportional counting.

3.

Sr-90 Monthly Composite chemical separation and gas flow proportional counting 4.

Tritium

.Each Release Distillation and liquid scintillation counting 5.

Alpha Monthly Coaposite Alpha scintillation 6.-

Dissolved Gases Each Relcase Ge(Li) spectrometry with on-line computer 7.

Fe-55 Monthly composite Chemical separation and liquid scintillation counting

. Estimated errors are based on errors in counting equipment calibration, counting statistics, nonsteady release flow rate, chemical yield factors, sampling and mixing: losses, and volume determinations.

l A.

Fission and Activation Products Total Release. as calculated for each batch.

Statistical Error at MDA 60%

j.

Waste Volume 10%

Counting Equipment Calibration 10%

Sampling and Mixing

_2B 100%

t 2

3 9

.. - ~

_ _ _ _ _ _. _ _ _. _ _ _., _ _ _ _. _. _. ~ _. _ _ _ _. _ _. -. - _ _ _ _

B.

Total Tritium Release as calculated from a monthly composite.

Waste Volume 10%

. Counting Equipment Calibration 10%

Sampling and Mixing

_201 40%-

C.

Dissolved and Entrained Gases Total Release as calculated from each release.

Statistical' Error at MDA 60%

Waste Volume 10%

Counting Equipment Calibration 10%

Sampling and Mixing

_2Q1 100%

D.

Total Gross Alpha Radioactivity Release as calculated from a monthly composite.

Statistical Error at MDA 60%

Waste Volume 10%

Counting Equipment Calibration 10%

Sampling and Mixing

_2Q1 100%

4.

Batch and Unolanned Releases The batch liquid effluent releases may be summarized as follows:

7/1/86 - 12/31/86 Number of Batch Releases 2.76E+02 Total Time for all Releases (minutes) 3.54E+04 Maximum Time ~for any one Release (minutes) 3.90E+02 Average Time for all Releases (minutes) 1.28E+02 Minimum time for any one Release (minutes) 2.00E+00 Average dilution flow of Units 1, 2, and 3 during all Releases (liters / minutes)-

2.54E+07 Number of Unplanned Releases 0.00E+00 Total Unplanned Activity Releases (Curie) 0.00E+00 The summation of liquid effluent releases is in Table III-1 and the summa-tion of nuclides in liquid effluent releases is in Table III-2.

These re-leases are based on the dilution of the radioactive liquid effluent by the nuclear services sea water of Unit 3.

l l

21

The doses to individuals from liquid effluent releases are in Table III-3 and the doses to the population from liquid effluent releases are in

' Table III-4.

These : doses are based on the dilution of the radioactive liquid effluents by.the condenser cooling water of-Units 1, 2, and 3.

There were no unplanned releases for the third and fourth quarters of 1986, t

6 i

22

Figure III-1 METHODS OF MEETING 10 CFR 20, APPENDIX B, TABLE II, COLUMN 2 MPC LIMITS MPC RANGE GAMA-RAY BETA ALPHA fuci/ml)

ENITTERS ENITTERS EMITTERS

-I-131. I-132. I-133 Sr-89, Sr-90 I-135. Cs-134 (Separation and Beta (9 x 10-6 Scintillation Counting)

(Ge(Li) Gamma-Ray Fe-55 Spectroscopy)

(Separation and All Liquid Scintil-(Alpha lation Counting)

Counting Sensitivity 10-7 uCi/m1'as Pu-239)

Ba-La-140. Na-24. Cu-64 Tritium co-60. Fe-59. In-65 (Distillation and Liquid Scintillation 19 x 10-6 Aa-110m. Mn-54. Co-58 Counting 10-5 uci/al)

Zr-Nb-95. Cs-Ba-137' As-76. F-18. Cr-51 No-239. Ce-141 No-Tc-99. Ce-Pr-144 (Ge(Li) Gamma-Ray Spectroscopy) 23

TABLE III-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 7/1/86 - 12/31/86 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 3

4 Error %

A.

Fission and Activation Products 1.

Total Release (not including tritium, gases, alpha)

Ci 2.12E-01 2.43E-01 1.00E+02 Avera$edilutedconcentrationduring 2.

perio uCi/ml 3.66E-08 5.90E-08 3.

Percent of applicable limit 7.98E-01 1.20E+01 B.

Tritium 1.

Total Release Ci 6.18E+01 6.77E+01 4.00E+01 2.

Average diluted concentration during periM uti/ml 9.62E-06 1.40E-05 3.

Percemt of applicable limit 3.21E-01 4.67E-01 4.00E+01l I

C.' Dissolved and entrained gases 1.

Total release Ci 1.41E+00 2.04E+00 1.00E+02 2.

Average diluted concentration during perid uCi/ml' 2.26E-07 4.10E-07 3.

Percent of applicable Aimit~

1.13E-01 2.05E-01 D.

Gross alpha radioactivity 1.

Total release ci 3.19E-05 2.73E-05 1.00E+02 E.

Volume of Waste released (prior to dilution) 1.

Batch and continuous Modes Liters 1.15E+07 1.48E+07 1.00E+01 F.

Volume of dilution water used during period 1.

Batch and Continuous Modes Liters 1.88E+10 1.81E+10 1.00E+01 l-24

il TABLE III-2 EFFLUENT AND WASTE' DISPOSAL SEMIANNUAL REPORT - 7/1/86 - 12/31/86 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Nuclides Released?

Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 sodium-24 Ci 2.41E-04 chromium-51

-Ci manaanese-54 Ci (9.01E-05 3.73E-03 1.69E-03 iron-55 Ci (5.60E-03 1.00E-01 1.80E-02 iron-59 Ci (2.55E-04 (5.25E-04 (4.18E-04 cobalt-58 Ci (6.27E-05 1.99E-02 2.86E-03 cobalt-60 Ci-(1.42E-04 3.87E-02 2.85E-02 zinc-65 Ci (1.66E-04 (3.42E-04 (2.72E-04 rubidium-88 Ci 7.85E-03 5.2SE-04 strontium-89 Ci 3.41E-05 5.18E-03 1.34E-04 strontium-90 Ci (2.80E-04 6.32E-05 1.84E-04

-strontium-92 Ci 1.08E-03 3.71E-03 zirconium-95 Ci zirconium-97 Ci 6.79E-05 2.53E-04 niobium-95 C1 2.14E-06 3.22E-05 molybdenum-99 C1' (4.46E-04 (9.16E-04 3.38E-06 technetium-99m Ci 5.94E-05 2.38E-03 technetium-101 Cl-5.71E-05 ruthenium-106

-C1 2.30E-04 milver-110m Ci 2.65E-03 7.56E-03 tellurium-132 Ci iodine-131 Ci (7.95E-05 1.08E-03 1.18E-02 iodine-132 Ci iodine-133 C1 1.07E-04 3.85E-05 cesium-134 C1 2.42E-04 1.83E-03 __

6.02E-02 cesium-136 Ci 7.54E-03 cesium-137 Ci 3.33E-04 4.29E-03 6.66E-02 i

barium-139 5.12E-05 lanthanum-140 Ci 1.20E-05 cerium-141 Ci (1.14E-04 2.27E-05 (1.87E-04 cerium-144 Ci (3.95E-04 (8.11E-04 (6.46E-04 l

unidentified Ci 2.76E-05 2.95E-02 2.86E-02 Total for period (above)

Ci 0.00E-00 6.37E-04 2.12E-01 2.42E-01 25

4 5

TABLE III-2 (Continued).

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 7/1/86 - 12/31/86 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Dissolved & Entrained Unit Quarter 3

. Quarter 4 Quarter 3 Quarter 4 Gases vanan-133' C1 1.37E+00 1.97E+00 gnagpd 3fg__

C1 1.78E-02 2.03E-02 XERQR-213n ci 1.31E-02 1.73E-02 menon-131m C1 1.04E-02 3.82E-02 krvoton-85m C1 1.07E-03 3.60E-04 krvoton-87 Ci 3.04E-05 krypton-88 Ci 7.44E-04 tritium C1 1.25E-01 6.18E+01 5.76E+01 1

NOTE: There were no continuous releases during the third quarter.

26 1

e-FIGURE III -

LIQUID RELEASES-FISSION AND ACTIVATION PRODUCTS 3

(EXCLUDING H, GASES, ALPHA)'

EO E-1 u

Fr>

o E-2 E-3 w

s a,

- em m

a w

.e

+eewe.

e e

i 1982 1983 1984 19B5 1986

~

27

TABLE III-3

= Doses to Individuals.from Liquid Effluent Releases THIRD OUARTER - CONTINUOUS RELEASES Whole Body Dose Oroan Dose Dose Dose Pathway Ace Group.

faren/vr)

Ace Group Oroan (aren/vr)

Fish 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Invertebrates Shoreline Use 0.00E+00 0.00E+00 Total 0.00E+00 0.00E+00 FOURTH OU4RTER - CONTINUOUS RELEASES Whole Body Dose Oraan Dose Dose Dose Pathway Ace Group furen/vr)

Ace Group Organ furen/vr)

Fish Adult 1.02E-04 Adult / Teen Liver 1.38E-04 Invertebrates

' Adult 1.52E-05 Adult / Teen Liver 2.05E-05 Shoreline Use Teen 4.95E-05 Teen Skin 5.78E-05 Total Adult 1.26E-04 Teen Liver 2.08E-04 THIRD OUARTER - BATCH RELEASES Whole Body Dose Oraan Dose Dose Dose Pathway Ace Grcup faren/vr)

Ace Group Organ (aren/vr)

Fish Adult 6.13E-03 Adult GI-LLI 1.33E-01 Invertebrates Adult 8.85E-03 Adult GI-LLI 1.90E-01 Shoreline Use Teen 6.17E-03 Teen Skin 7.25E-03 Total Teen 1.80E-02 Adult GI-LLI 3.24E-01 FOURTH OUARTER - BATCH RELEASES Whole Body Dose Oraan Dose Dose Dose Pathway Ace Group (aren/vr)

Ace Group Oroan (area /vr)

Fish Adult 2.67E-02 Adult GI-LLI 1.13E-01 Invertebrates Adult 7.38E-03 Adult GI-LLI 7.91E-02 Shoreline Use Teen 1.78E-02 Teen Skin 2.08E-02 Total Teen 3.87E-02 Adult GI-LLI 1.95E-01 28

TABLE III-4 Doses to the Population from Liquid Effluent Releases THIRD OUARTER - CONTINUOUS RELEASES Whole Body Dose Organ Dose Pathway (Man-Rem /Yr)

Organ Dose (Man-Rem /Yr)

Sport Fish 0.00E+00 All 0.00E+00 Commercial Fish 0.00E+00 All 0.00E+00 Sport Invertebrate' O.00E+00 All 0.00E+00 Commercial Invertebrate 0.00E+00 All 0.00E+00 Shoreline Use 0.00E+00 0.00E+00 Swimming 0.00E+00 0.00E+00 Boating 0.00E+00 0.00E+00 Total 0.00E+00 All 0.00E+00 FOURTH OUARTER - CONTINUOUS RELEASES Whole Body Dose Organ Dose Pathway (Man-Rea/Yr)

QIggn Dose (Man-Rem /Yr)

Sport Fish 1.44E-02 Liver 2.43E-02 Commercial Fish 1.48E-05 Liver 2.50E-05 Sport Invertebrate 6.06E-04 Liver 1.20E-03 Commercia' Invertebrate 4.37E-06 Liver 7.34E-06 Shorelira 7se 2.22E-04 Skin 2.59E-04 Swimming 7.02E-07 Thyroid 7.02E-07 Boating 7.02E-07 Thyroid 7.02E-07 Total 1.52E-02 Liver-2.54E-02 THIRD OUARTER - BATCH RFEFASES' Whole Body Dose Organ Dose s

Pathway (Man-Rem /Yr)

Organ Dose (Man-Rem /Yr)

Sport Fish 9.42E-01 GI-LLI 1.99E+01 Commercial' Fish 9.70E-04 GI-LLI 2.05E-02 Sport Invertebrate 3.89E-01 GI-LLI 8.00E+00 Commercia1' Invertebrate 2.80E-03 GI-LLI 5.76E-02 Shoreline Use 2.76E-02 Skin 3.25E-02 Swimming 1.21E-04 Thyroid 1.21E-04 Boating 1.21E-04 Thyroid 1.21E-04 Total 1.36E+00 GI-LLI 2.80E+01 FOURTH OUARTER - BATCH RELEASES Whole Body Dose Organ Dose Pathway (Man-Rem /Yr)

Organ Dose (Man-Rem /Yr)

Sport Fish 3.83E+00 GI-LLI 1.68E+01 Commercial Fish 3.94E-03 GI-LLI 1.72E-02 l

Sport Invertebrate 3.18E-01 GI-LLI 3.31E+00 L

Commercial Invertebrate 2.29E-03 GI-LLI 2.38E-02 Shoreline Use 7.96E-02 Skin 9.31E-02 Swimming 3.33E-04 Thyroid 3.33E-04 l

Boating 3.33E-04 Thyroid 3.33E-04 Total 4.24E+00 GI-LLI 2.02E+01 29

IV.

SOLID WASTE SHIPMENTS Solid waste shipments from the plant may include solidified liquid waste, dry compressed waste, spent resins, irradiated components and spent fuel.

1.

Reaulatory Limits The Technical Specification for solid waste shipment u norting is as follows:

Specification 6.9.1.5(d)

The - radioactive effluent release report shall include the following information for each type of solid waste shipped offsite during the report period:

1.

container volume, 2.

total curie quantity (specify whether determined by measurement or estimate),

3.

principle radionuclides (specify whether determined by measure-ment or estimate),

4.

type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),

5.

type of container (e.g., LSA, Type A, Type B, large quantity),

and 6.

solidification agent (e.g., cement).

The summation of solid waste and irradiated fuel shipments is presented in Table IV-1 and Shipment Summaries in Table IV-2.

30

TABLE IV-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

.7/1/86 - 12/31/86 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Non irradiated fuel)

Second 1.

Type of waste Unit 6-month Est. Total period Error, %

3 a.

Spent resins, filter sludges, evaporator m

1.43E+02 bottoms, etc.

Ci 1.14E+03 2.00E+01 3

b.

Dry compressible waste, contaminated m

6.06E+01 equip, etc.

Ci 6.68E+00 5.00E+01 3

c.

Irradiated components, control m

E+00 rods, etc.

Ci E+00 5.00E+01 3

d.

Other (describe) m E+00 Ci E+00 2.00E+01 2.

Estimate of major nuclide composition (by type of waste) a.

Cs-137 3.78E+01%

Ni-63 3.90E+00%

E Co-60 2.71E+01%

Mn-54 3.73E+00%

E

\\

Cs-134 1.91E+01%

E E

Co-58 5.52E+00%

E E

b.

Co-60 5.28E+01%

Co-58 2.96E+00%

E Ni-63 2.59E+01%

E E

\\

Cs-137 9.02E+00%

E E

Mn-54 5.92E+00%

E E

c.

E E

\\

E E

d.

E

\\

E E

E 3.

Solid Waste Disposition Number of Shipments Mode of Transportation Destination 22 Transport Truck -

Chem-Nuclear Systems, Inc.

Exclusive Use Vehicle Barnwell, SC B.

IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None NA NA l

31

- TA8LE IV EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

-7/1/86 - 12/31/86 SHIPMENT'

SUMMARY

DATE AND CONTAINgR TOTAL WASTE CONTAINERS SOLIDIF.

SMIPMENT 8 VOL-FT CURIES PRINCIPLE RADIONUCLIDES TYPE' TYPE AGENT-7-1-86

.402 2.17E-6 Co-60, Cs-134, Cs-137, Sb-122. H-3 SC LSA N.A.

C-14

.86 7-17-86 NI-63.Mn-54, 46-35 119-210 Cs-134, Cs-137, Co-58,~Co-60 F

Type 8 N.A.

7-24-86 H-3 C-14 86-36 402 2.06E-4 Co-58, Co-60, Cs-134 Cs-137 Sb-122 SC LSA N.A.

4-6-86 Ni-63, Mn-54, 86-30 119-11.9 Cs-134, Cs-137, Co-58, Co-60, Sr-89 F

LSA N.A.

8-14-86 86-39 402 1.38E-4 Cs-134, Cs-137, Sb-122, H-3 SC LSA N.A.

8-19-86 86-40 161 1.43 Co-60, Mn-54, Ni-63, Co-58, Sr-89 CE LSA N.A.

8-21 Ni-63, Mn-54

~86-41 193 17.4 Cs-134 Cs-137, Co-58, Co-60, H-3 SR LSA N.A.

9-4-86 Ni-63 Cs-13d,Mn-54 86-42 119 199.7 Cs-137, Co-58, Co-60 SR LSA N.A.

5-11-86

'Co-60,-

86-43 402-3.14E-4 Cs-134, Cs-137, Sb-122, H-3, C-14 SC LSA N.A.

9-23-86 Ni-63, Mn-54 86-44

-119 199.7 Cs-134, Cs-137, Co-58, Co-60 SR LSA N.A.

9-25-86 86-45 402 1.68E-4 Cs-134, Cs-137, I-131 H-3 SC LSA N.A.

10-2-86 Ni-63, Mn-54 86-46 119 166 Cs-134, Cs-137, Co-58, Co-60 SR LSA N.A.

10-9-86 86-47 402 2.61E-4 Cs-134, Cs-137, Sb-122 H-3 SC LSA N.A.

10-23-86 Ni-63, Mn-54 86-50 119 166 Cs-134, Cs-137, Co-58, Co-60 SR LSA N.A.

10-30-86 86-52 402 2.15E-4 Cs-134, Cs-137, I-131, H-3 SC LSA N.A.

11-6-86 8 9 7.5 C-14 86-54 42 3 11.6 0.429 Co-60, Mn-54, Ni-63, Co-58, Sb-125 CW LSA N.A.

11-6-86 86-54 2392 1.789 Co-58, Co-60, Mn-54, Sb-125, Ni-63 NW LSA N.A.

11-13-86 Cs-134, 46-55 402 2.51E-4 Cs-137, I-131, H-3, C-14, Fe-55 SC LSA N.A.

WASTE TYPE:

SR - Spent Resin NW - Non-Compacted Waste CE - Contaminated Equipment SC - Secondary Rosin CW - Compacted Waste IC - Irradiated Components F - Filters Et - Evaporator Bottoms 32

i 1

- TA8LE IV-2 (Continued) -

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 7/1/86 - 12/31/86 SHIPMENT

SUMMARY

DATE AND CONTAINgR TOTAL WASTE CONTAINERS SOLIDIF.

VOL-FT CURIES PRINCIPLE RADIONUCLIDES TYPE TYPE AGENT SHIPMENT #

Ni-63 Cs-13d,Hn-54, 11-18-86 86-57 119 170 Cs-137, Co-58 Co-60 SR LSA N.A.

11-20-86 1 9 11.6-86-58 83 3 7.5 2.78 Co-60, Hn-54, Ni-63, Co-58, Sb-125 CW LSA N.A.

11-25-86 Cs-134,

.86-59 402 2.59E-6 Cs-137, Sb-122, H-3, C-14, Fe-55 SC LSA N.A.

12-11-86 86-61 402 2,51E-4 Cs-134, Cs-137.-H-3, C-14, Fe-55 SC LSA N.A.

12-18-86 86-62 82 9 7.5 0.25 Co-60 Hn-54, Ni-63 Co-58 CW LSA N.A.

WASTE TYPE: SR - Spent Rosin NW - Non-Compacted Waste CE - Contaminated Equipment SC - Secondary Resin CW - Compacted Waste IC - Irradiated Components F - Filters E8 - Evaporator Bottoms l-33

- FIGURE IV VOLUE OF SOLID WASTE SHIPPED OFF-SITE 800-600-Waste

mglume, V

408 400 254 250 289 280 h

2_2_3 2_1_8 204 200-188 160 A

B A

B 1982 1983 1984 1985 1986 L

{

- FIGURE IV RATIO OF CURIE CONTENT TO VOLUE OF WASTE SHIPPED OFF-SITE 9.

15.76 hh 8.0 "

7.5 "

7.0 -

6.5-6.0 "

5.64

5. 5 -

5.0 4.5 C1/m3 4,0 3.5 "

3.0 -

2.5 1.57 1.77 1.8 2*0 1.5 1.23 1.0 0.56 0.5 0.21 1

1 A

B A

3 1982 1983 1984 1985 1986 A - First Half B - Second Half 34

V -METEOROLOGICAL DATA The meteorological data at 33 feet (10 meters) is summarized in Tables V-1, V-2, V-3, and V-4.

The classification of atmosphere stability is as follows:

Stability.

Pasquill-Temperature change Classification Cateaories with heiahtf*c/100m) t Extremely unstable A

<-1.9 Moderately unstable B

1-1.9 to <-1.7 Slightly unstable C

1-1.7 to <-1.5 Neutral D

1-1.5 to <-0.5 Slightly stable E

1-0.5 to < 1.5 Moderately stable F

1 1.5 to < 4.0 Extremely stable G

1 4.0 The dato recovery rates are:

Third Quarter...... 97%

Fourth Quarter..... 82%

The meteorological data for this period was manually recovered from strip charts.

35

TABLE V-1 FLO2IDA POWER CORPORATION HOURO-AT EACH WIND-3 PEED AND DIRECTION SIRIOD-OF DEC010

- JULY 1,17 36 TH ROUGH SEPTEMBER 30, 1986 CONT.

STA11LITY CLASS-A 3 3 F T.-

ELEVATION

. WIND

'JIND 30EED (MPH)

DI9 1-3 4-7 3-12 13-13 19-24 24+

TOTAL N

O 1

1 0

0 0

2 NNE 1

3 4

0 0

0 a

NE 1

2 2

0 0

0 5

ENE 2

7 16 0

0 0

25 E

2 7

15 0

0 0

24 ESE 4

2 4

0 0

0 10 SI 1

4 7

1 0

0 13 S3E O

4 9

0 0

0 13 S

1 5

5 0

0 0

11 SGw 0

6 9

0 0

'O 15 SW G

13 15 0

0 0

23

'J S W 2

20 27 0

0 0

49 W

0 20 11 0

0 0

31 d 'lW 0

20 3

0 0

0 25 NW 1

2 1

0 0

0 4

NNW 0

0 0

TOTAL 15 116 134 1

0 0

26o PERIODS OF CALM (HOURS) 0 36

~

7AoLE.V-1

.FLbRIDA' POWER' CORPORATION 900R$ AT-'EACH WIND SPEED AND DIRECTION-

-PiRIOD.0F QECORD -

JULY 1,1936 THROUGH SEPTE MBE R 30, 1986 CONT.

STA3ILITY CLASS il 33 FT.

. ELEVATION WIND WINO SPEED (MPH)

DIR.

1-3 4-7 5-12 13-13 19-24 24+

TOTAL N

0 1

1 0

0 0

2 NNE C

0 0

NE O

1 0

0 3

0 1

ENE O

2 1

0 0

0 3

E O

3 2

0 0

0 5

ESE 1

1 3

0 0

0 5

SE' O

5 0

1 0

0 6

SSE O

3 3

0 0

0 6

5 0

2 10 1

0 0

13 SSd 0

-4 7

1 0

0 12 SW 0

10 7

0 0

0 17 WSW 1

10 12 0

0 b

23 W

0 4

2 0

0 0

6 WNW 3

3 5

1 0

0 12 NV O

2 1

0 0

0 3

NNW 1

2 0

0 0

3 3

l l

TOTAL 6

53 34 4

0 3

117 I

PERIOOS OF CALM (HOURS) 0 l

l l

l i

l I

37

TAOLE-V-1

~

FL0kIDA DOWEP ' C OE POR AT ION J

HOURS AT EACH WIND SPEED AND DIRECTION JULY 1,1986 TH ROU3H OIPTEM3Ed 30, 1930 CONT.

PERIOD OF RECORD OTA.i!LITY CLA30

-C 33 FT.

ELEVATION J!hD WIND GPEED (MPH)

DIo 1-3 4-7 3-12 13-13 19-24 24+

TOTAL N

1 0

3 0

0 0

1 NNE 3

1 0

0 0

0 1

NE O

3 0

0 0

0 3

.ENE 1

5 0-

~0 0

3 6

E O

1 2

0 0

0 3

ESE O

1 1

0 0

0 2

SE O

3 3

0 0

0 6

SSE O

7 1

0 0

0 3

G 1

9 4

0 0

0 14 SSW 1

7 3

3 0

0 11 GW 0

5 2

0 0

0 7

WSW 0

3 3

1 0

0 7

W 0-5 2

0 0

0 7

WN.

0 8

0 0

3 NW 0

2 0

0 0

0 2

NNW 0

0 0

TOTAL 4

60 21 1

0 0

36 0

PERIODS O F CALM (HOURS) 38

TABLE V-1 FLORIDA POWER CORPORATION MOU9S AT EACH WIND 3*EED AND DIRECTION PER IOD OF REC 0a0 -. JULY 1,1936 THROUGH SEPTEMBER 30, 1936 CONT.

STABILITY CLA33

-0 33 FT.

ELEVATION WIND JIND SPEED-(MPH)

DIF 1-3 4-7 6-12 13-13 19-24 24+

TOTAL a

4 N'

0 4

1 0

0 0

5 NNE J

10 2

0 0

0 12

-NE 3

0 3

0 0

0 15 UN2 3

11 2

0 0

0 16 E

13 15 6

1 0

0 35 ESE 2

14 5

0 0

0 21 3E 2

24 6

0 0

0 32 3SE 2

15 16 3

0 0

3o S

2 21 26 4

0 0

53 534 1

27 26 3

1 0

63 SW 4

39 26 1

0 0

70 r

43W 2

28

-18 2

0 0

50 W

3 22 16 2

0 0

43 JNW 1

26 19 0

0 0

45 i

j NW 2

14 3

0 0

0 24 N '4 W 0

4 0

0 0

0 4

TOTAL 40 283 180 21 1

0 525 2

PERIODS OF CALM (HOURS) 39

TA3LE V-1 FLORIDA 00WE0 COAPCRATION HOURS AT EACH WIND SPEED AND DIRECTION JULY 1,1736 THROUGH SEPTEM3E4 30, 1936 CONT.

PERIOD OF DEC040 STA91LITY CLA'5 E

33 FT.

ELEVATION WIND WIND SPEED (MPH)

DID 1-3 4-7 S-12 13-13 19-24 24+

TOTAL N

2 3

0 0

5

(

NNE 7

10 1

0 0

C 1B NE 30 5

0 0

0 43

[

ENE 20 e2 2

0 0

0 34 E

16 41 2

0 0

0 59 ESE 3

25 4

0 0

0 37 SE 7

59 6

0 0

0 72 S3E 2

24 12 0

0 0

3,5 i

S 3

27 17 0

0 0

47 GS.

2 21 13 2

0 0

43 Sd 3

45 15 0

0 0

63 WSW 4

36 28 0

0 0

33 W

6 40 12 0

0 0

58 JNd 12 70 3

0 0

0 70 NW 6

8 0

0 0

0 14 NNd 1

7 0

0 0

0 3

TOTAL 107 523 130 2

0 0

767 PERIODS OF CALM (HOURS) 2 40

er i

It 0

(SHOOH) W7v3 3 0 S00Ib3d LE2 0

0 0

0 6tl SCL 7Y101 9

C 0

0 0

5 L

PNN SL 0

0 0

0 LL t

MN ZL 0

0 C

0-OL 2

MNM 9

C C

0 0

9 2

t 0

0 0

0 E

O FSM L

0 0

0 L

.9 s L

C C

0 0

C L

MSS L

C 0

0 0

'O L

S 9

0 0

L 5

ass 02 C

C 0

0 LL 6

35 Et 0

0 0

C LL 92 353 fB 0

0 0

0 SE St 3

55 0

0 0

0 2E E?

3N3 LL 0

0 0

G 1

t 3N tl C

0 C

0 4

2 3NN i

0 0

C-0 L

2 N

7Y101

+12 12-6L SL-EL 2L-S 1-7 E-L WIC (HdW) C33d5 CNIP ONI*

NOI1YA373

13 EC 3-05173 A117IE115

1NO3 9E6L 'OE b3Ek31d35 HenobH1 GE6L'l A70f

- Ce033e 30 00I13d NCI135dIC Cht C33d! CNIM'H3t3 14 SdDOH NOI1Ye0dt03.E3P0d 70lbO73 t-s 3,ev:

_L-

. 'l. )

ZW 1

0 (Shn0H) W7V3 JO S00I03d OS 0

0 0

0 et LE 7V101 2

0 0

L L

MNN i

0 0

0 i

RN 2

0 0

2 0

N N.*

2 0

0 0

0 2

0 M.

9 0

0 0

0 i

i P S P.

L 0

0 0

0 L-0 MS 0

0 0

P.S S 0

0 0

L 0

0 0

0 L

0 3SS i

5 0

0 0

0 t

L 3S

?L 0

0 0

0 2

5 3S3 SL 0

0 C

0 OL 5

3 02 0

0 0

C 2L 6

3N3 i

0 C

0 0

L 2

3N L

0 0

0 C

0-L 3hN L

C 0

0 C

0 L

h 7V101

+t2 92-6L 8L-il 2L-F 2-1 E-L WIC (Hdk) 033d5 CNIr CNIP

13 11 NCI1Y/373 D-

??Y13 A117Itv1S

1NO3 9E6L 'Of 835h31d3S HDn0dH1 SF6L't A7Dr

- CE033B 30 00Ie3d NOI133b1C Chy 033aS'QNIP H3Y3 1Y Sh00F N011Vd0d W03 E3M0d VCIbO73 L_r 37evi

..a

Et

-i

)

1 (Sun 0H) W1Y3 30 SC0IN3d 0

Et 0

0 0

L2 22 0

7t101 0

0 0

C 0

Y N te 0

0 0

MN 4

0 0

0 L

9 0

Frim C

0 0

0 L

5 0

OL 0

0 0

4 E.

O MSM 9

0 0

0 1

2 0

MS s

0 0

0 2

E O

r.S S 0

0 0

S 2

0 0

2 0

.3ES L

0 0

0 L

0 0

3S 2

C C

0 2

0 0

3S3 0

0 0

0 C

3 0

0 0

3h3 0

0 0

C C

0 0

3N 1

0 0

0 i

L 0

SNN-0 0

0 0

C 0

0 N

74101

+t2 92-cL El-EL 2L-F 4-9 E-L HIC (HdW) C33d5 CNIP.

CNIP NOI1YA373

13 it SSY13 A1I1I E f1!

V H31YE 036L'OE h3EW31c3S HD00bH1 GScL's A1Rf

- GbC 33 E 30 'GOI h3d NOI133EIC C f. ! 033e5 O f41 M H3t3.it Sbn0F

, N011VB0dc03 d3P0d VC18073-2-A 37EV1 I

TGLE V-2 FLODIDA POWER CORPORATION HOURS AT EACH WIND SPEED AND DIRECTION PERIOD'0F RECORD JULY 1,1986 THROUGH SEPTEM9ER 30,1936 BATCH-STABILITY CLASS B

E L E V A T I 0'.

33-FT.

W I P. D WIND SPEED (MPH)

DIR 1-3 4-7.

3-12 13-13.

19-24 24+

TOT 4L N

O O

1 0

0 0

1 N'4 E O

O 3

0 0

NE O

O O

E'1E O

O O

E O

O 1

0 0

0 1

ESE O

O 1

0 0

0 1

SE O

2 0

0 0

0 2

SSE O

1 1

0 0

0 2

S 0

1 4

0 0

0 5

L S in 0

2 1

1 0

0 4

S9 0

1 4

0 0

0 5

.SW 0

0 5

0 0

0 5

W 0

0 0

f Wild 0

0 2

0 0

0 2

NW 0

1 0

0 0

0 1

l NNW 0

0 0

j.

TOTAL 0

8 20 1

0 0

29 i

i PERIODS OF C4LM (HOURS)

O l

1

1 TABLE V-2 FLORIDA POJER CORPORATION HOURS AT EACH WIND SOEED AND' DIRECTION JULY 1,1936 THROUGH SEPTE13ER 30,1936 BATCH PERIOD OF RECORD STABILITY CLA33 C

13 FT.

ELEVATION JIND JIND SPEED (MPM)

DIP 1-3 4-7 3-12' 13-13 19-24 24+

TOTAL N

3 0

0 3

0 0

0 NNE 3

1 0

0 0

0 1

NE O

O O

ENE O

O O

E O

O O

E;E O

O O

- 3E O

2 3

0 0

0 5

S3e 0

2 0

0 0

0 2

S O

1 1

0 0

0 2

SSW 0

0 0

SW 0

1 0

0 0

0 1

WSW 0

2 2

0 0

0 4

w 0

0 0

i WNW 0

1 0

0 0

0 1

NW 0

0 0

NNW 0

0 0

TOT AL 0

10 6

0 0

0 16 0

PERIODS OF CALM (HOURS)

I 45 i-

TAeLE V-2 FLORIDA. POWER CORPORATION HOURSJAT EAC4 WIND SPEED AND DIRECTION PERIOD OF RECORD -

JULY 1,1986 THROUGH SEPTEMBER' 30,1986 9ATCH STa1ILITY CLASS D-33 FT.

ELEVATION WIND WIND SPEED (MPH)

DIR 1-3 4-7 5-12 13-18 19-24 24+

TOTAL N

O 2

0 0

2 NNE O

3 2

0 0

0 5

NE O

3 0

0 0

ENE O

O O

0 0

E O

1 0

0 0

0 1

ESE 1

4 1

0 0

0 6

SE O

3 0

0 0

0 3

SSE O

3 3

0 0

0 6

S 0

2 4

0 0

0 6

SSV 0

10 6

0 0

0 16 SJ 2

3 4

0 0

0 9

dSW 1

7 4

0 0

0 12 W

1 4

3 0

0 C

3 r

WNW 0

4 2

0 0

0 6

NW 1

1 2

0 0

0 4

NNW 3

1 0

0 0

0 1

TOTAL 6

43 31 0

0 0

33 PERIODS O F CALM (HOURS) 0 46

TABLE V-2 j

FLORIDA POWER CORPORATION HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD -

JULY 1,1986 THROUGH SE PTE MB ER 30,1986 5ATCH STABILITY CLASS E

33 FT.

ELEVATION WIND WIND SPEED (MPH)

DIR 1-3 4-7 8-12 13-13 19-24 24+

. TOTAL N

O 2

0 0

2 NNE 1

4 1

0 0

0 6

NE 2

5 2

0 0

0 9

ENE 4

6 0

0 0

0 10 E

1 4

0 3

0 0

5 ESE 1

4 0

0 0

0 5

SE O

4 0

0 0

0 4

$3E O

4 1

0 0

0 5

5 0

13 9

0 0

0 22 S$w 0

5 4

0 0

0

?

S 'J 1

9 1

0 0

0 11 WSW ^

0 5

3 0

0 6

S J

0 7

0 0

7 kNW 1

16 2

0 0

0 19 NW 0

1 0

0 0

0 1

NNW 0

0 0

TOTAL 11 89 23 0

0 0

123 PERIODS OF CALM (HOURS) 1 47

TA3LE V-2 FLORIDA POWER CORPORATION HOURS AT EACH WIND SSEED AND DIRECTION PERIOD OF RECORD -

JULY 1,1936 THROUGH S E P T E '4E E R 25,173o 94TCH STA11LITY CLASS F

33 FT.

ELEVATION JIND WIND $ PIED (MPH)

DIP 1-3 4-7 8-12 13-18 19-24 24+

TOTAL N

O O

O NNE O

O O

NE O

O O

ENE 2

3 J

0 0

0 2

E 9

5 0

0 0

0 14 ESE 2

2 0

0 0

0 4

SE 2

1 0

0 0

0 3

135 0

0 0

S 0

0 0

3 0

SSW 0

0 0

SW G

0 0

WSW 0

0 0

d 0

0 0

W4d 2

0 0

C 2

Nw 0

1 0

0 0

0 1

i NNW 1

1 0

0 0

0 2

TOTAL 18 10 0

0 0

0 23 PERIODS O F CALM (HCURS) 0 48 l

69 0

(SB00H) W7V3 30 SCole3d SL 0

0 0

0 LL t

7t101 0

0 0

MNN 0

0 0

FN O

O O

M t. M 0

0 0

M 0

0 0

Mir 0

0 0

hs 0

0 0

MSS 0

0 0

S 0

0 0

3!S 0

0 0

3S L

0 0

L 0

3S3 8

0 0

5 E

3 5

0 0

5 0

3 t.3 L

0 0

0 L

3N O

G 0

0 0

3NN 0

O O

N 7V101

+12 72-6L EL-fL ZL-S 1-1 E-L HIC (HdW) 033ds CNIM CNIM NOI1YA373

13 it 0-SSV13'A1I7 ICV 1S H31V3 99 6 L'OE W3 9m 31d3S HS00MH1 9E6L'L A70r

- 080338 30 00It3d NOI133dIC.0NV 033dS CNIM H3Y3 1Y SEDOH NOI1VW0ddO3 U3 Mod VOIbC13-2-A 31FV1 w

TA3LE V-3' FLORIDA POWER CORPORATION HOURS AT EACM WIND SPIED AND DIRECTION PEAIOD OF PECORD - ' OCTOBER 1,17 36 T HROU GH D EC EMB ER 31,19 3 6 C ONT.

S T A.IIL I TY CLASS A

33 FT.

ELIVATION J I T. 3 WIND iPEED (MPH)

DI9 1-3

-7 3-12 13-13 19-24 24+

TOTAL N

O 2

1 0

3 0

3 NNE O

1 2

0 0

0 3

t4 E O

9 21 4

0 0

33 ENE G

3 2

2 0

0 12

~

L 0

10 4

0 0

0 14 ESE O

4 4

0 0

0 SE O

5 4

0 0

33E O

2 1

0 0

0 3

S 1

4 2

0 0

0 7

5 3 '-

3 2

2 0

0 0

4 SW 0

0 0

WSw 0

3 1

0 0

0 4

J 0

9 4

0 0

0 13

'e r w 0

1 4

0 0

0 5

4W 0

0 0

N4V 1

1 0

0 0

0 2

TOTAL 2

60 52 6

0 0

120 0

PERIGOS OF C ALM (HOUas) 50

TABLE V-3 FLORIDA P0.ER C0APO4ATION HOURS AT EACH WIN) SPEED.AND DIRECTION PiAIOD OF *EC340 -

OCT056R 1,1136 TH 40U3H DE CIM3 ER 31,1936 CONT.

S T A 11LI TY CLA33 i3 33 FT.

ELEVATION 4IND WIND 3DEiD (MaH)

OIR 1-3 4-7 d-12 13-13 19-24 24+

TOTAL 1

0 0

3 0

3 1

NNE G

'1 0

0 0

0 1

NE O

3 4

4 0

0 11 ENE 0

3 1

1 0

0 5

t 1

5 0

3 0

0 6

23E 3

2 1

0 0

0 3

$5 0

2 0

0 0

0 2

01E-0 3

0 0

3 3

0 0

3 396 0

2 3

0 0

0 5

s.

1 0

0 0

2 WOW.

0 3

0 0

3 W

0 4

3 0

0 0

7 w'i d-0 0

3 0

0 0

3 i

Nw 0

2 0

0 0

0 2

.'4 N W D

0 S

3 0

0 0

TOTAL 2

30 17 5

0 0

Se 7

0 l-PE91003 0 F CALM (HOU R S) l l

1 l

51 i

L TABLE V-3 FLORIDA POWE3 CO220 RATION.

HOURS 4T EACH h!ND 3 PEED'AND DIRECTION PERIOD OF RECO4D -

OCTOBER 1,1036 THROUGH DEC293E4 31,19 86 CONT.

S T A 91LI TY CLASS C

33 FT.

ELEVATION WIND WIND $PE23 (mph)

DIR 1-3 4-7 3-12 13-13 19-24 24+

TOTAL 1

0 2

1 0

0 0

3 NNE O

1 1

0 0

0 2

NE 2

5 3

1 0

0 16 ENE-0 5

1 1

0 0

7 E

O O

O 3

0 0

0 ESC 0

2 0

0 0

0 2

3E O

2 0

0 0

.0 2

SSE O

5 3

0 0

0 4

3 0

1 1

0 0

0 2

S3W 0

1 2

0 0

0 3

SW 3

1 0

0 0

0 3

WSW 0

0 1

0 0

b 1

W 0

6 2

0 0

0 3

WNW 0

2 0

0 0

0 2

NW 0

2 1

0 0

0 3

NNd 0

1 0

0 0

0 1

TOTAL 2

36 21 2

0 0

63 0

PERIODS OF CALM (H0095) 52

1V013 A-$

4106101 c0.rir 3Ced0WT1ICh F0neS Y1 3t3H *INC 0c33C YNQ CId331ICh 418100 03 e'00hC -

C31093W l'L6L9 1Hk000H 0333Wt3e tL # L t 39 3CN1*

S1V01111A 37T$$

C LE dl*

373A;1:0h

.* 1.' C nIhC tdr30 )hoH(

C1b L-f t-2 t-L2 Lf-LS te-21 294 101v1 h

2 21 5

C 0

0 19

'.t 3

/

tL L5 C

C 0

5E l

hL i

vL 9E LS 0

C tti 3h3 9

1c iL L

0 0

21 3

c L7 2

C O

O EO 3C3 2

LS 5

0 0

0 25

!3 5

4 2

C C

C Lt S03 C

LO t

0 C

U ti C

0 LL 9

0 C

O ll 5 !.P i

10 tt C

0 0

2S

!P S

ZL 5

0 0

C iL PP 2

L9 t

C 0

0 22 L

L6 i

C 0

C 2[

e 4*

i 16 li i

0 0

iF NP i

20 LL L

0 0

15 4h' i

lE 0

0 C

tf 101t7 CG EEC L69 20 0

0 904 C

e3H 200$ C d 391W )H006$(

SC

TABLE V-3 FL0tIDA POWER CORPCRATION 40VR3 AT CACM WIND 30EED AND DIRECTION PEAIOD OF REC 04D -

OCT0JIR 1,1786 THROUGH DECZv3C4 31,1036 CONT.

STA1ILITY CL433

-E 33 FT.

(LCVATION W I t. D WIN 3 SDEED (MOH)

CIR 1-3 4-7 3-12 13-14 19-24 24+

TOTAL N

7 17 5

0 0

0 27 tc4E 5

31 11 0

0 0

47 NT 5

32 06 2

0 0

105 ENE O

47 14 1

0 0

70 E

22 51 4

0 0

3 77 E3E 13 42 4

0 0

0 59 SE 13 34 4

0 0

0 56 SSE 5

26 6

0 0

0 37 3

5 20 1

0 0

0 2o S$w i

12 3

0 0

0 24 SJ 10 22 2

0 0

0 34 d s'4 4

13 3

0 0

0 25 d

4 11 11 1

0 0

27 dNw 7

13 4

0 0

0 24 Nd 7

9 4

0 0

0 20 P4W 10 17 1

0 0

0 23 TOTAL 137 402 143 4

0 0

693 1

PERIOOS OF CAli (HOURS) 54

~

' TABLE'V-3

. FLORIDA POWER C04PORATION WOURS AT E A C H '41N 9 3 PEED AND DI4ECTION-PEdIO3 0F PIC040 -

OCT00ER 1,1986 THROUGH DECEMBER 31,1986 CohT.

STA1!LITY CL415 F

31 FT.

ILEVATION 4: 3. 0 WIh3 30!ED (MPd)

DIS 1-3 4-7 8-12 13-IS 19-24 24+

TOT 4L N

13 4

0 0

14 N '4 E 11 5

5 0

0 0

21 NE 2

1 13 0

0 0

16 E 'J E 9

31 0

0 0

0 40 5

14 17 0

0 3

0 31 ESE 16 13 0

0 0

0 29 SE S

4 0

0 0

0 12 SSE 2

4 0

0 0

0 6

S 0

2 0

0 0

0 2

SSw 2

2 0

0 0

0 4

54 0

0 0

dSW 2

0 0

3 i

W 1

3 0

0 0

0 4

WNw 2

1 1

0 0

0 4

NW 0

0 0

s NNW 1

0 0

0 1

TOTAL 34 do 19 0

0 0

172 1

piPI005 0 F CALM (HOURS) 55 L

M (sen0H) h1v3 JO SCO2v3d 0

il L

0 C

7 09 01 7t101 L

0 0

0 L

P.h 4 0

0 0

MN 0

0 0

PNM L

0 0

L 0

M t

0 0

i L

Mtr Z

0 0

2 0

MS 0

0 0

0 C

P!S L

0 0

L 0

2 0

0 0

0 2

0 3;t t

0 0

L 2

35 LL C

0 0

0 i

3t3 OL 0

0 0

0 t

a 3

52 0

0 0

L CL G

3 f.3 t

0 0

0 f

0 L

LN 9

0 0

0 C

?

2 3NA 9

0 0

C I

N 14101

+t2 tt-6L P L -i l JL-9 1.t 51 h!C (hew) 03345 CNIP C N I P.

f.011t A373

13 it 9-

!!t73 A117!tfit

1NCO 966L'Lt W36*333C HS00kH1 956L't b?cotac

. cp033e 40 CO:d3d NOI133BIC bht 073dS CNIr H3r3 it Sanch NOI1Yt0dbO3 43604 VCIM01A 9

E-A 37C41' t

TABLE V-4 FLdPIDA POWER C00POPATION HOURS AT EACH WIND SSEED %ND DIRECTION PERIOD OF RECORD -

OCT30E4 1,1996 TdR3 UGH DECEM324 31,1986 BATCH STA3ILITY CLAi$

A 33 FT.

ELEVATION WIN)

WIND SPEED (MPH)

D!w 1-3 6-7 8-12 13-13 19-24 24+

TOTAL N

O O

O 3

0 kNE O

O O

NE O

O 1

0 0

0 1

ENE O

O O

0 0

E O

1 0

0 0

0 1

E3E 3

1 0

0 0

0 1

SE C

0 0

0 2

$$E O

O O

S 0

2 0

0 0

0 2

SsW G

0 0

J 0

0 0

SJ 0

0 0

WSW 0

0 0

0' 0

W 0

0 3

0 0

dNW 0

0 3

0 0

0 3

NW 3

0 0

NNW 3

0 0

TOTAL 0

6 4

0 0

0 10 PEH10DS OF CALM (HOURS) 0 57

C3 i

4 r

i 0

(SWOOH) W1V3 Jo 500!d3d 1

t 0

0 C

L 9

0 14101 0

C D

0 0

M. ti L

0 0

L 0

P t.

0 0

0 C

0 0

0 Mh*

I C

C C

L 2

0 6

0 0

C Mtm 0

0 0

C C

0 0

P, t 0

0 0

0 C

"5s 0

0 0

C 0

0 0

S C

0 C

C C

0 C

35$

L 0

0 0

0 L

C 3t 0

0 0

313 L

C 0

0 0

L 0

3 0

0 0

3h3 L

0 0

L 0

Sh 0

0 0

0 C

3NN O

C C

C 0

0 0

N 7V101

+t2 12-6L SL-tL EL-F 4-1 1-L eIC (HdW) 033d5 CNI.*

CNIP

14 11 P 011V/.37 2 E-SSY13 All'IEvi$

H31VC 96 6 L'Lt t30 3 330 H000MH1 996L'l biFC130

- ObO33W J0.003*3d NCI133 TIC QNY C33cS ONIM H3Y3 it ta00b ACI1YWOdt03 W3M0d VOIko73 T-A 37EV1

i C3 F

i i

(Skn0H) h1V3 Jo f00!W3e 0

i

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0 0

t i

L 14101 L

0 0

1 0

MN t.

I L

0 0

0 L

0 0

MN 0

0 0

mh*

L C

0 0

0 L

0 P

O O

O ese 1

0 0

L 0

?

0 0

L mit 0

0 0

0 C

5 0

0 0

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L 0

0 0

0 L

0

?S 0

0 0

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353 0

0 0

?

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0 I

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Ph 0

0 0

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0 0

0 C

L L

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l 14101

+12

??-6L BL-El EL-5 I-t 1-L SIC (HdW) 033dt CNIP QN7*

l

.011 Y A ? 7 ? -

14 ff 3-5 5 V10 A1I110 V A S H31VG 906L'Li 83Ek3330 h000WH1 9f(L': 4220130

- OtC33V JO Coldid NOI133d!C'ONY 033d5 CNIF, H3V3 it 5bOCH N011Vd0da03 b3P0d WCIt07J 1-A 37EV1 l

L 2

C3 i

(Sun 0H) kly) A0 Scolcid 0

16 0

0 0

22 09 Li 14101 1

0 0

0 L

2 C

MNA 5

0 0

0 t

2 0

MN 2

0 0

0 t

t 0

Mhe A

C 0

0 0

L A

2 0

0 0

0 2

0 MSh t

0 0

0 L

2 0

PS i

O O

O L

2 C

Mtt t

0 0

t C

S 0

0 0

3SS t

0 0

0 2

i L

3S 2

0 0

2 0

353 2

0 0

C C

2 0

3 P

0 0

2 L

3NI LE C

0 C

7 SL 2

3N SL 0

0 C

9 T

inh 9

0 0

9 2

N 7V101

+t2 12 6L 96.El 2L.?

21 f.L 81C (HdW) 03345 CNIP CN1r NCIIVA373

1J It J

0

!$Y13 A117'wY15 H31V6 9t o L' Lt b3 0 2 33C H000eH1 996 L' L W3E0130

- CdO33W A0 00ItiId h01133NIC ChV C33d5 CNIM H3V3 IV !WOOh hC11VW0da03 h3M0d VOIe07d t.A 370V1

l l

19 1

1 0

- (Shn0H) kly) JO Sco!sid 1

906 0

0 C

ft 49 OL 1V101 t

0 0

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MNN l

1 l

2 0

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L t

i NN I

C 0

0 0

2 i

P t. P L

0 0

0 L

5 L

F 2

0 0

L L

MCM 2

0 0

0 L

L 0

P. S 2

0 0

0 L

P.C S l

9 0

0 0

0 5

i G

l l

C 0

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0 3SS t

0 0

C C

t 0

is LL 0

0 C

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0 0

0 TL 2

3 9

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3N3 6

0 0

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3N ft C

0 0

5 i

L 3h4 2L C

0 0

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13 EC 3-

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H31YG 9fet'Li W36 3330 HD00bH1 086L't d!E013C

- CPC338 40 00!d3e NOI133EIC CNY 033d5 CNIM H3t3 11 Sen0k f4011thodd03 V370d VCIe074 9-A 378Yi J

39 4

1 0

- (Sen0H) h1V3 JO $00!b3s 1

lt 0

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L ol il 14101 I

l 0

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0 0

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L 0

0 0

0 L

0 P.

L 0

0 0

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0 85m

[

r 0

0 0

AS L

0 0

0 L

mss L

0 0

L 0

a C

0 C

0 0

30!

0 C

C 0

0 0

C 35 t

0 0

L Z

333 i

OL 0

0 0

0 4

1 3

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0 0

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L 1h3 L

0 0

0 L

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4 0

0 0

0 L

G 3hh E

C 0

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+t2 TC-6L EL-EL 2L-f 2-1 i-l SIC (hew) 033d! ONIM CNIM N02AVA313

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'm

VI TECHNICAL SPECIFICATION REPORTS Technical Specification Sections 3.3.3.8, 3.3.3.9, and 3.12.1.2.b require reporting out of specification conditions in the Semiannual Radioactive Effluent Release Report.

There were no reports as required by the above specifications for the period of this report.

64

VII ODCM AND PCP CHANGES Technical Specifications Section 6.9.1.5.d reouires reporting of changes to the Offsite Dose Calculation Manual (00CM) and the Process Control Program (PCP) in the Sealannual Radioactive Effluent Release Report.

Revisions to the 00CM for the period of this report are included in this section. The changes are marked for ease of review.

{

l l

f I

I, l

l

-l 65 1

=..

NOCLIOE AN& LYSIS 1.2-1 REACTOR SOILDING FORGE IIE&BST NOCLIDE SafELE SOURCE LLD(b)(uci/cc)

A.

Principal Gamma Esitters (a)

Mn-54 1x10-4/1x10-11 Fe-59 1x10-4/1x10-11 Co-58 Pre-release grab sample for Batch 1x10-4/1x10-11 Co-60 Type release. Weekly Particulate 1x10-4/1x10-11 Zn-65 Filter Analysis for continuous (c) 1x10-4/1x10-11 Mo-99 type release.

1x10-4/1x10-11 Cs-134 1x10-4/1x10-11 Cs-137 1x10-4/1x10-11 Ce-141 1x10-4/1x10-11 Ce-144 1x10-4/1x10-11 Kr-87 Pre-release grab sample for Batch 1x10-4/1x10-6 Kr-88 type release. Noble Gas monitor 1x10-4/1x10-6 Xe-133 during batch and continuous releases 1x10-4/1x10-6 Xe-133a 1x10-4/1x10-6 Grab sample within 2-6 hr. following Xe-135 startup, shutdown or 15% RTP 1x10-4/1x10-6 Xe-138 change in 1 hr.

1x10-4/1x10-6 8.

Iodine 131 Pre-release grab sample for Satch NA/1 x 10-12 type release. Weekly charcoal filter and once per 24 hr for 7 days following startup shutdown or 15% RTP change in 1 hr unless 1-131 concentration at site boundary 10% 10 CFA 20 Limit.

C, Tritius Pre-release Grab Sample and within 1x10-6 12-24 hr following flooding of refueling canal and once per 7 days while canal is flooded.

D.

Gross Alpha Monthly Particulate Filter Composite 1x10-11 E.

Sr 89 Quarterly Particulate Tilter Composite 1x10-11 T.

St-90 Quarterly Particulate Tilter Composite Ix10-11 (a) Other.dentified Cassa taitters not listed in this table shall be included in dose and setpoint calculations.

(b) The first value refers to the LLO for pre-release grab sample: the second value refers to the LLD for weekly Particulate Tilter Analysis or the Noble Gas Monitor during continuous purge.

(c) Reactor Sullding Purge is considered continuous af ter a minimus of one Reactor Building volume has been released on a continuous basis (i.e., first volume is a batch type).

FCVla0N 8

NBCLIDE ANALYSIS 1.2-3 WhSTE GAS DECAT Tams NOCLIDE SA M LE 500RCE LLD(b)(uci/al)

A.

Principal Gaasa, Emitters (a)

Mn-54 1x10-4/1x10-11 Fe-59 1x10-4/1x10-11 Co-58 1x10-4/1x10-11 Co-60 1x10-4/1x10-11 In-65 1x10-4/1x10-11 Pre-release Orab sample and weekly Mo-99 Particulate Filter Sample from RM-A2.

1x10'4/1x10-11 Cs-134 1x10-4/1x10-11 Cs-137 1x10-4/1x10-11 Ce-141 1x10-4/1x10-11 Ce-144 1x10-4/1x10-11 Kr-87 1x10-4/1x10-6 Kr-88 1x10-4/1x10-6 Xe-133 Pre-release Orab sample.

1x10-4/1x10-6 Xe-133a 1x10-4/1x10-6 Xe-135 1x10-4/1x10-6 Xe-138 1x10-4/1x10-6 8.

Iodine 131 weekly Charcoal Filter from AM-A2.

1x10-12 (a) other identified Oamma Esitters not listed in this table shall be included in dose and setpoint calculations.

(b)

The first value refers to the LLD for pre-release grab samples the second value refers to the LLD for weekly Particulate filter Analysis or the Noble 04s Monitor during continuous purge, LEV!30\\1 8

L...._....-......-..-.-.-

SETPOINT CALCULATION 1.4-1A REACTOR BUILDING PURGE EIRAUST DUCT MONITOR (RM-A1)

(SPECIAL RELEASE FOR FUNCTIONAL TESTING OF THE REACTOR BUILDING PURGE SYSTEM)

INTRODUCTION To11owing completion of the analyses required by Section 1.2-1 and determination of release rates and concentration limits in accordance with Section 1.3-1, the monitor setpoint requires adjustment to ensure that alara and pathway isolation occur if the nuclide concentration or release rate exceed the limits determined.

METHODOLOGY Auxiliary Building and Fuel Handling Area atmosphere is continuously passed through radiation monitor RM-A2 and the count rate is observed.

The observed count rate is correlated to a corresponding count rate for RM-A1, and factors are applied to account for background radiation and statistical counting variations.

The obtained value is used as the alara/ trip setpoint and RM-Al is adjusted to this valve prior to initiating the release.

CALCULATION Monitor Setpoint (CPM) = Net CPM Y Vent. Fractio VAC RM-A2 Cone. RM-A2/ CPM PDAR X Admin Limit VAC KM-A1 Conc. RM-A1/ CPM

+ Skg + 3.3 yEi Where:

Net CPM =

The observed monitor count rate, in counts per minute.

Vent Traction = The portion of the total plant gaseous release associated with this vent and discharge type valve is' equal to 0.5.

PDRR =

The noble gas ganna emission Project Dose Rate Ratio (PORR) calculated in accordance with 'Section 1.3.

This ratio is the actual projected dose rate divided by the allowable dose rate referenced in Section 1,3-1 equation 4.

See note.

Admin Limit =

Administrative Limit to reduce'setpoint to 10 of allowable limit Admin Limit = 10 Vac RM-A2 =

The actual vacuum reading at RM-A2 at the time of sampling.

Vac RM A1 =

The actual or average vacuus reading at RM-At during normal

, operation.

Conc.RM-A2/ CPM = The ratio of uci/cc to cpa at RM-A2 based on an actual sample or desired from the calibration curve.

Cone.RM-A1/ CPM = The ratio of uci/cc to cpa at RM-At based on an actual sample or derived from the calibration curve.

3EVlC ON 8

.,,a.

Bkg =

The background count rate at RM-A1 in counts per minute (CPM).

3.3 VBkg =

A statistical spread on the background count rate which represents a 99.95% confidence level on monitoring counting.

This factor _is included to prevent inadvertent high/ trip alarms due to random counts on the monitor. Only the positive (+) side of the spread is applied.

NOTE:

If there are no isotopes identified in the sample, the LLD's for Xe-133 and Kr-85 may be used as actual values for the purpose of the setpoint calculation.

W t

R O

l c.dF/ S!ONt o

l

-18b-l

)

Tchls 4.4-17 Liquid Effluent - Adult Ingestion Dose Factors Nuclide agng Idy.gr T. Body Thyroid Kidney Lugg GI-LLI Nb-95 4.47E2 2.49E2 1.34E2 ND 2.46E2 ND 1.51E6 Mo-99 ND 9.05E-4 1.72E-4 ND 2.05E-3 ND 2.10E-3 Tc-99m 1.30E-2 3.66E-2 4.66E-1 ND 5.56E-1 1.79E-2 2.17E1 Tc-101 1.33E-2 1.92E-2 1.88E-1 ND 3.46E-1 9.81E-3 5.77E-14 Ru-103 1.07E2 ND 4.60E1 ND 4.07E2 ND 1.25E4 Ru-105 8.89E0 ND 3.51E0 ND 1.15E2 ND 5.44E3 Ru-106 1.59E3 ND 2.01E2 ND 3.06E3 ND 1.03E5 Ag-110s 1.57E3 1.45E3 1.33E1 ND 2.85E3 ND 5.91E5 Sb-124 2.77E2 5.23E0 1.09E2 6.70E1 ND 2.15E2 7.83E3 Sb-125 2.20E2 2.37EO 4.42E1 1.95E1 ND 2.30E4 1.94E4 Sb-126 1.13E2 2.31E0 4.09E1 6.95E1 ND 6.95E1 9.27E3 Te-125m 2.17E2 7.86E1 2.91E1 6.52E1 8.82E2 ND 8.66E2 Te-127m 5.48E2 1.96E2 6.68E1 1.40E2 2.23E3 ND 1.84E3 Te-127 8.90E0 3.20E0 1.93E0 6.60E0 3.63E1 ND 7.03E2 Te-129s 9.31E2 3.47E2 1.47E2 3.20E2 3.89E3 ND 4.69E3 Te-129 2.54E0 9.55E-1 6.19E-1 1.95E0 1.07E1 ND 1.92E0 Te-131s 1.40E2 6.85E1 5.71E1 1.08E2 6.94E2 ND 6.80E3 Te-131 1.59E0 6.66E-1 5.03E-1 1.31E0 6.99E0 ND 2.26E-1 ~

l Te-132 2.04E2 1.32E2 1.24E2 1.46E2 1.27E3 ND 6.24E3 I-130 3.96E1 1.17E2 4.61E1 9.91E3 1.82E2 ND 1.01E2

}

I-131 2.18E2 3.12E2 1.79E2 1.02E5 5.35E2 ND 8.23E1 I-132 1.06El 2.85E1 9.96E0 9.96E2 4.54E1 ND 5.35E0 I-133 7.54E1 1.30E2 3.95E1 1.90E4 2.26E2 ND 1.16E2 I-134 5.56E0 1.51E1 5.40E0 2.62E2 2.40E1 ND 1.32E-2 I-135 2.32E1 6.08E1 2.24E1 4.01E3 9.75E1 ND 6.87E1 Cs-134 6.84E3 1.63E4 1.33E4 ND 5.27E3 1.75E3 2.85E2 Cs-136 7.16E2 2.83E3 2.04E3 ND 1.57E3 2.16E2 3.21E2 Cs-137 8.78E3 1.20E4 7.85E3 ND 4.07E3 1.35E3 2.32E2 Cs-138 6.07E0 1.20E1 5.94E0 ND 8.81EO 8.70E-1 5.12E-5 Ba-139 7.85E0 5.59E-3 2.30E-1 ND 5.23E-3 3.17E-3 1.39E1 Ba-140 1.64E3 2.06E0 1.08E2 ND 7.02E-1 1.18E0 3.38E3 Ba-141 3.81E0 3.69E-3 1.29E-1 ND 2.68E-3 1.63E-3 1.80E-9 Ba-142 1.72E0 1.77E-3 1.08E-1 ND 1.50E-3 1.00E-3 2.43E-18 La-140 1.57EO 7.94E-1 2.10E-1 ND ND ND 5.83E4 La-142 8.06E-2 3.67E-2 9.13E-3 ND ND ND 2.68E2 9 "t r"\\ f ' Q t p \\ g h

i ii V Vikil k

.

ML20212G591

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