Text

Semiannual Radioactive Effluent Release Rept for Jan-June 1990
	ML20064A455
Person / Time
Site:	Vogtle
Issue date:	06/30/1990
From:	Hairston W; GEORGIA POWER CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	ELV-02033, ELV-2033, NUDOCS 9009040236
	Download: ML20064A455 (80)
	v • d • e

.

i Geo'Oc %n Company 333 Piedmont Avenus Attante. Geo'O n 30300 1 Tegon'ione 404J' 6 3195 i Mading Ad$ess-40 invemess Center Parkway Post Offcc Box 1295 Binningbant Alabama 35201 J 1eWAone 205 668 5581 l

l August 27, 1990 n.uwen ee smem W. G. Hairston,111 i senior Vice President Naclew Operations ELV-02033 0565 i

Docket Nos. 50-424 50-425

! U. S. Nuclear Regulatory Commission ATTN: Document Control Desk ;

Washington, D. C. 20555 t

Gentlemen: :

V0GTLE ELECTRIC GENERATING PLANT ;

SEMIANNUAL RADI0 ACTIVE' EFFLUENT RELEASE REPORT in accordance with requirements of the Vogtle Electric Generating Plan.' Unit I and Unit 2 Technical Specifications, Section 6.8.1.4, please find enclosed the Seuiannual Radioactive Effluent Release Report for January 1,1990 through June 30, 1990. Six copies are provided for your use. Two copies of this report are ,

being provided to the NRC Region 11 office.

Sincerely, bY .l Y &

W. G. Hairston, 111 WGH,III/JLL/gm [

t Enclosure xc: Georoia Power Company e Mr. C. K. McCoy Mr. G. Bockhold, Jr. '

Mr. R. M. Odom ;

Mr. W. R. Woodall, Jr. ;

Mr. P. D. Rushton <

NORMS i

U. S. Nuclear Reaulatory Commission -

Mr. S. D. Ebneter, Regional Administrator Mr. T. A. Reed, Licensing Project Manager, NRR .

Mr. B. R. Bonser, Senior Resident inspector, Vogtle State of Georaia Mr. J. Setser, DNR 1

American Nuclear insurers Mr. L. Cross C a g' 9009040236 900630 PDR R

ADOCK 05000424 PDC

/? /,,k -

t

i i

1 i

l GEORGIA POWER COMPANY ;

V0GTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 NRC DOCKET NOS. 50-424 AND 50-425 ,

FACILITY OPERATING LICENSE NOS. NPF-68 AND NPF-81 SEMIANNVAL RAD!0 ACTIVE EFFLUENT RELEASE REPORT r

FOR JANVARY 1, 1990 TO JUNE 30, 1990 h

i f

S i

f l

r h

7

i V0GTLE' ELECTRIC' GENERATING PLANT r

SEMIANNUAL REPORT PLANT RADIOACTIVE' EFFLUENT' RELEASES t f

SECTION TITLE PAGE 1.0 Liquid Ef'luents 6 l

1.1 Regulatory Limits / Technical Specifications- 6 ,

1.1.1 Effluent Radiation Monitoring System 6 l 1.1.0 Concentration Limits 6 1.1.3 Dose Limits 6 1.1.4 Liquid' Processing 7 1.1.5 Outside Temporary Tanks 7 ,

1.1.6 Reporting of Semiannuci Releases (Unplanned) 7

~

1.2 Maximum Permissible Concentrations 11 1.3 Measurements and Approximations of Total 11

Radioactivity 1.4 Liquid Effluent Release Data 13 -

1.4.1 Methodology 13 ,

1.4.2 Batch Release Data 15 1.5 Radiological Impact on Man Due-to Liquid- 15 Release ;

o 1.6 Abnormal Releases 15 1.7 River Flow 16 2.0 Gaseous Effluents 29 2.1 Regulatory Limits / Technical. Specifications 29 2.1.1 Process Effluent Monitoring System 29 2.1.2 Dose Rate Limit 29 2.1.3 Air Dose Due to Noble Gas 29 2.1.4 Dose to Any Organ 30 2.1.5 Ventilation Exhaust Treatment System and 30 Gaseous Waste Processing System 5

i f

SECTION TITLE PAGE >

i 2.1.6 Explosive Gas Mixture 31 2.1.7 Activity In Gas Decay Tanks 31 2.1.8 Total Fuel Cycle Dose Commitment 31 ,[

2.1.9 Reporting of Semiannual Releases (Unplanned) 32- l l

2.2 . Release Points of Gaseous! Effluents. 37 f

2.3 Sample Collection and Analysis 37 244 Determination of Total Quantities of 30 l Radioactivity,' Dose Rates and Cumulative .;

Doses 2.4.1 Fission and Activation Gas 39 2.4.2 Radioiodine, Tritium and Particulate 39 Released Li 2.4.3 Gross Alpha Release 40 -

2.5 Gaseous Effluent Release Data 40 -i 2.5.1 Methodology 41 r

2.5.2 Gaseous Batch Data 42.

7 2.6 Radiological Impact Due to Gaseous Releases 43 .

3.0 Solid Waste 65 l 3.1 Regulatory Limits / Technical Specifications 65 ;

3.1.1 Use of Solid Radioactive Waste System 65 ,

l 3.1.2 Reporting Requirements 65 f 3.1.3 Process Control Program (PCP) 65 3.2 Solid Waste Data 66 I 4.0 changes to the Vogtle Electric 69 l Generating Plant ODCM 4.1 Changes in the Radiological Environmental _ 71 Monitoring Program 5.0 Doses to Members of the Public Inside 71 The Site Boundary

V0GTLE ELECTRIC-GENERATING PLANT SEMIANNUAL REPORT-RADIOACTIVE EFFLUENT RELEASE > REPORT LIST OF TABLES TABLE LIST OF TABLES PAGE 1-1 Technical Specification Table 3.3-9 Radioactive Liquid Effluent Monitoring Instrumentation 8 <

1-2a Liquid = Effluents - Summation of All Releases Unit 1 17 1-2b Liquid Effluents - Summation of All Releases Unit 2 18 1-2c Liquid Effluents - Summation of All Releases Site 19 1-3a Liquid Effluents - Unit 1- 20 i l

1-3b Liquid Effluents - Unit 2 21 i 1-3c Liquid Effluents - Si.s 22 i 1-4a Individuals Doses Due to uiquid Releases Unit 1 23 1-4b Individuals Doses Due to Liquid Releases t

Unit 2 24 i 1-5 Lower Limits.of Detection - Liquid Sample I Analysis 25

{

1-6a Batch Release Summary of All Releases -

Unit 1 27 1-6b Batch Release Summary of'All Releases -

Unit 2 28 !

2-1 Technical Specification Table 3.3.10 Radioactive Gaseous Effluent Monitoring Instrumentation 33 2-2a Airborne Effluents - Summation of All Releases Unit 1 44 4

l

.. . _ _ _ _ . __ _~ - . -

LIST OF TABLES PAGE TABLE 2-2b Airborne Effluents - Summation of All Releases Unit 2 45 2-2c Airborne. Effluents - Summation of All. Releases 46 Site ,

2-3a Gaseous Effluents - Mixed Mode' Releases Unit 1 47 2-3b C:setas F,ifluents - Mixed Mode Releases 49 Unit 2 Gaseous Effluents - Mixed Mode Releases Site 51 2-3c 1 2-4a Gaseous Eff.sents - Ground Level !

Release - Unit 1 53 e l n

2-4b Gaseous Effluents - Ground Level Release - Unit 2 55 ,

2-4c Gaseous Effluents - Ground Level Releases Site 57 t Air Doses Due to Noble Gases Unit 1 60 2-6a Air Doses Due to Noble Gases Unit 2 61 2-6b 2-7a Individual Doses Due to Radioiodine, Tritium, and Particulates in Gaseous

- Releases - Unit 1 62 2-7b Individual Doses Due to'Radiciodine, Tritium, and Particulates in Gaseous Releases - Unit 2 63 .

l Lower Limits of Detection - Gaseous Sample 2-8 :

Analyses 64 f Solid Waste and Irradiated Fuel Shipments 67 3-1 5-1 Basic Data Assumed in Dose Assessments to Members of the Public 73 ,

I e

_ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . e . ._ , , , , _ , , , . _ , . ,- , , , - , . , , - . . . . ,

1 I

TITLE PAGE I SECTION 6.0 Major Changes to the Liquid, Gaseous ,

and Solid Radweste Treatment Systems 74 s 7.0 Meteorology (TO BE INCLUDED FOR THE '

REPORT DATED JANUARY'1, 1991). 75 l 8.0 Inoperable Liquid or Gaseous Effluent-Monitoring Instrumentation 76 ,

9.0 Tanks Exceeding Curie' Content Limits 77

ii I i

f I

i h

l i

1412A i

3 f

i 4

I k

1.0 Liquid Effluents 1.1 Regulatory Limits / Technical Specifications The Technical Specifications (T/S) presented-in this subsection are for the. site.

1.1.1 Effluent Radiation Monitoring System The radioactive liquid effluent monitoring instrumentation channels shown.in T/S Table 3;3-9 shall be OPERABLE with their Alara/ Trip Setpoints set to ensureL.that the limits of '

Specification 3.11.1.1 are not exceeded. The. ALARM / TRIP i Setpoints of these channels shall be determined and

adjusted in accordance with the methodology and parcaeters in the OFF-SITE DOSE CALCULATION MANUAL (ODCM). Technical Specification Table 3.3-9 is included in this subsection as Table 1-1.

1.1.2 concentration Limits 3.11.1.1 ;

1 The concentration of radioactive material released in I

liquid effluents to UNRESTRICTED AREAS (See Figure 5.1-11of l Technical Specifications and 5.1-2 of Technical j Specifications) shall'be limited to the concentrations j specified in 10 CFR Part 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 limited to 2.0E-4 alcrocurie/a1 e total activity.

1.1.3 Dose Limits l

3.11.1.2 l

The dose or dose commitment to a MEMBER OF THE PUBLIC from i

radioactive materials in liquid affluents released, from each unit, to UNRESTRICTED AREAS (see Figure 5.1-1 and 5.1-2 of Techical Specifications), shall be limited

a. During any calendar quarter to less than or equal to 1.5 areas to the whole body and to less than or equal

! to 5 areas to any organ, and

b. During any calendar year to less than or equal to 3.

areas to the whole body and to less than or equal to-10 areas to any orgar..

l

)

1

, 6 b

,.,__,r, .c, . . , . ,.,,,_,__,,,_e.,,._e,,...,__., ou , , . , _ . , , ,

i 1.1.4 Liquid Processing 3.11.1.3 The Liquid Redwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be uJed to reduce releases of radioactivity when the projected doses due to 1 the~ liquid effluent, from each unit, to UNRESTRICTED AREAS J (See Figure 5.1-1 and 5.1-2 of the Technical' J Specifications)'would exceed 0.06 area to the whole body or 0.2 area to any organ in a 31-day period. i i

1.1.3 Outside Temporary Tanks 3.11.1.4 i

The quantity of. radio' active material-contained in each outside temporary tank shall be limited.to less thanlor equal to 10 curies, excluding tritius'and dissolved or entrained noble gases.

1.1.6 Reporting of Semiannual Releases (Unplanned) .)

6.8.1.4 states'in part ,

The Semiannual Radioactive Effluent Release Reports shall include a list and description of unplanned releases.from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting

- period.

I l

7

l i

I l

I TABLE 1-1 (FROM TECHNICAL SPECIFICATIONS) ,

i (TABLE 3.3-9)

RADI0 ACTIVE = LIQUID' EFFLUENT MONITORING INSTRUMENTATION j i

' MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. Radioactivity. Monitors.Providing [

Alarm and Automatic Termination of !

Release

a. Liquid Radwaste Effluent Line 1 37 (RE-0018)

b. Steam Generator Blowdown Effluent 1 38 Line -

(RE-0021) i

c. Turbine Bldg. (Floor Drains) Sumps 1 38 Effluent Line (RE-0848) g

2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release

a. Nuclear Service Cooling Water 1 39 System Effluent Line (RE-0020A & B)

3. Flow Rate Measurement Devices-

a. Liquid Radwaste Effluent Line 1 40 (FT-0018) ;

b. Steam Generator Blowdown 1 40 Effluent Line (FT-0021)

c. Flow to Blowdown Sump 1 40 l (AFQI-7620, FR-7620, pen 1)

(common) ,

8 i

l TABLE 1-1-(CONTINUED)

' ACTION STATEMENTS' ACTION 37 With the number of channels OPERABLE less than required by the Minimum Channels.0PERABLE requirement,-

effluent releases via this pathway may continue provided that prior to initiating a releases

a. At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and

b. At ; east two technically qualified members of the~

facility staff independently verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactivity effluenta via this pathway. 4 1

1 ACTION 38 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent. releases via-this pathway may continue provided grab samples are analyzed for radioactivity !

at a lower limit of detection of no more than 10-7 microcurie /ml: i g

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than ;

0.01 microcurie / gram DOSE EQUIVALENT I-131, or .j 1

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the sear tdary coolant is less than or equal to 0.01 miers;orie/ gram DOSE EQUIVALENT I-131. i ACTION 39 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue J provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed for radioactivity at a lower limit of detection of no more than 10-7 microcurie /ml. ,

1 9

I, r .. - i.. . . -

1 l

i 1

ACTION 40 With the number of channels OPERABLE less than j required by the Minimum' Channel' OPERABLE requirement, '

effluent releases via this pathway-may continue provided.the flow rate is estimated at least once per !

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. _ Pump performance curves generated in place may be used to estimate' flow.

t i

r I

l F l

I t

i L l

l

'l I

1 i

4 4

b 10

. - , u - r r

e l

b; ^

I 1.2 Maximum : Permis sible Concentration (MPC)-

MPC. values _used(inideterminingLallowable7 11guid ,adwaste- o j

release rates-and concentrations for e principal ~ gamma emitters. I-131,~ tritium, Sr-89,_Sr-90, and-Fe-55-are-taken i from 10;CFR Part 20,- Appendix B.. Table.II, Column'2.

For dissolved or entrained noble gases in liquid radwaste,. I the.MPC:is obtained from Technica1LSpecificationsL3.11.1.1cas 1 2E-04'uCi/mi tota 1Lactivity.'

For gross alpha in liquid radwaste,.the MPC is'obtained from 10 CFR Part 20, Appendix B, Note'2.d as 3.0E-08 uCi/al.

' Further,: f or- all the ' aboven radionuclides ors categorie s of radioactivity, the overall MPC-fraction ~isLdetermined in' .

accordance with 10 CFR Part 20,' Appendix.B. Note 1. .

The'rethod whereby-the MPCsfraction is.used to determine- ,

relea,a rates and liquidLradwaste efflue n radiation monitor- '

set' points is described in Subsection l'.4 oi this report. !

l-1.3- ' Measurements and Approximations iof Total Ra lioactivity ;

Prior to release of any tank containing. liquid radwaste, and following the required recirculations, samples are collected '

and analyzed in accordance with Technical Specification. Table 4.11. A' sample from each. tank' planned'for release.is }

analyzed for principalfgamma esitters, I-131, and dissolved .t

- and entrained noble gases.br3 gamma spectrometry._ Monthly.and ,

quarterly composites-are prepared for~ analysis by extracting i l

aliquots from each sample: taken from1 tanks-which are-released.' Liquid radwaste sample analyses-are performed as fo'. lows: ,

MEA:d6EMENT FREQUENCY METHOD

1. Gamma Isotopic Each Batch Gamma Spectroscopy +

with computerized-data reductiou ,

i

2. Dissolved or entrained Each batch Gamma Spectroscopy-noble gases with computerized data reduction !

3. Tritium Monthly Distillation =and s Composite liquid scintillation counting

4. Gross Alpha Monthly Gas flow proportional r Composite counting -

11 r

_ _ . _ _ ~ . .

- . __. ... . ~ - - . . .

{

MEASUREMENT' FREQUENCY ' METHOD i

'5. Sr-89 and Sr-90 Quarterly; .

! Chemical.separationL Composite andzgas flow

. proportional or 1

-scintillation counting j

6. Fe-55

Quarterly Chemical separation1 Composite and liquid 1 scintillation counting.

Gamma isotopic measureme'nts are performed in-house:in.the l radiochemistry lab using germanium' spectrometry. This consists;of .

'four high purity germanium detectors with resolution of 1.80 kev or-lower. _The detectors are i shielded by four-inchesiof. lead'.; A= liquid ,

radwaste sample;is porred into a-graduated. cylinder to-measure-'out one l liter of sample which is then poured irto-a:bottlefor intoJall/11ter-marinelli in preparation'for a 2000-4000Jsecond count. =A peak sear'ch 4 of the resulting; gamma ray spectrum;is-performed by.the computer- j system. Energyfand net count data of all significant-peaks are. J determined, and a quantitative reduction or MDA calculatio'n is ,

performed. ' The procedure ensures lthat the LLD's: are metif or the .

nuclides specified in. Table - Notation . 3; of Technica11 Specification (

Table 4.11-1 Mn-54,tFe-59, Co-58,;Co-60, Zn-65, Mo-99,Ecs-134, '

Cs-137,_Ce-141 au' Ce-144. The ' quantitative calculations, corrections.

for counting time, decay time,' sample. Volume, sample geometry, J detector efficiency, baseline counts, _ branching ratio, and MDAi

> calculations, are ande based-on the counts at thatlocation on_the:

t spectrum-where the peu_ for that radionuclide.would be located, if present. !

Tritium, Gross Alpha, Sr-89, Sr-90 and;Fe-55 are, in some cases, performed off-site rather than'in-house'to more efficiently use plant. !

technicians. 1

[ The radionuclide concentrations determined' by : gamma spectroscopic -

analysis of a sample taken from a tank planned for release and the 1 most current sample analysis results available'for tritium cgross l l- alpha, Sr-89, Sr-90 and Fe-55 are used along with the-corresponding !

MPC values to determine-a MPC fraction for-the tank planned'.for !

, release. This MPC fraction is then used, with. appropriate' safety- 1 F f&ctors, along with the minimum assured dilution atream' flow.to

- calculate maximum permissible release rate and a111guid effluent- [

l monitor setpoint. The monitor setpoint is calculated 1to'assureithat the limits of Technical Specification.3.11.1.1 are not' exceeded.

1 A monitor reading in excess of the calculeted setpoint results-in an automatic termination of the liquid radwaste'discharre. -

Liquid effluent discharge is also automatlcally terminated Af'the dilution L stream flow rate falls below the minimum assured dilution: flow rate ,

' l used in the setpoint calculations-and established as a setpoint on the i- dilution stream flow monitor.

l 12

-s Radlonuclide concentrations, safety _ factors, dilution stream flow q rate,.and liquid effluent radiation monitor calibrations are entered into the computer and a pre-release printout is generated. If the-release is not permissible, appropriate warnings will be included ~on i If the release is permissible, it is approved by

~

the computer screen. I the Chemistry Foreman on duty and sent to the Operations Department i for approval and processing. When the release is completed. the l necessary data from_the release (ex., release volume) is transferred from the Operations Department to the Chemistry _ Department. These data are input to the computer and a post-release printout is ,

I generated. The post-release. printout contains actual release rates, actual release concentrations and quantities, actual dilution flow, and calculated doses to an individual.

1.4 Liquid Effluent Release Data Regulatory Guide 1.21 Tables 2A and 2B are found in_this; l report.as Table 1-2a and Table 1-Sa for Unit-1, Tables 1-2b and 1-3b for Unit 2. l 1.4.1 Methodology The values for the four categories of Table 1-2a and 1-2b are calculated and are completed as follows:-

1.4.1.1 Fission and activation products 1

The total release values (not including tritium, gases, and :

alphe) are comprised of the sum'of the measured individual radionuclide activities. This sum is for each batch released i co the river for the respective quarter.

I 1.4.1.2 Tritium l l

\

The measured tritium concentra : ions in the monthly composite samples are used to calculate the total release and average diluted concentration during each period.

1.4.1.3 Dissolved and entrained gases l

Concentrations of dissolved and entrained gases-in liquid' l effluents are measured by germanium spectroscopy on each one liter sample for ecch liquid radwaste-batch. Radioisotopes of iodine in any form are also determined during the isotopic-i analysis for each batch; therefore, a separate analysis for I possible forms is not performed because'it would not provideagaseous ditional information l

l 13

1.4.1.4 Gross alpha radioactivity:

The measured gross alpha concentrations inLthe monthly (

composite / samples are used to calculate,the, total release-oof~ alpha radioactivity.- !

h 1.4.1.5 Total Error Measurement The total'or maximum error associated with the effluent measurement will include the-cumulativs1 errors resulting

~

. j from the total operation of sampling and measurementi j .

Because it may be very difficult to. assign errorfterms.for i each parameter;affectingLthe final measurement, detailed i statistical evaluation of errorlis'not suggested. The. ;

objective should be to obtain an overall estimate of :the-

-error associated.with measurements:ofiradioactive: ~l materials released in, liquid effluents.

Estimated errors are based on errore11n counting, equipment' -1 calibration, counting statistics, ~ dilutionEflow rates,"

sample and tank flow rates. 1 i

1.4.1.5.1 Fission and activation total-release was calculated-from sample analysis results and releaseEpoint flow rates.

Sampling and statistical error :10%

, Counting Equipment Calibration "10% 4 Tank Volumes and System' Flow-Rates 20%

TOTAL ERROR

_4 0 %

f 1.4.1.5.2 Total tritium release-was calculated-from sample ~ analysis results and release point' volumes.

Tank volumes and system flow rate! 20% !

Sampling and. statistical' errors 10% 1 Counting equipment calibration- 10% l TOTAL ERROR .40%

t-1.4.1.5.3 Dissolved and entrained gases were calculated-from sample ,

analysis results and release point volumes.. 7 Tank Volumes and system flow rate- 20% ;

Sampling and statistical error 20%

Counting; equipment: calibration- 16%<

TOTAL ERROR 50%

f l

14 i i

i

I v s 1

-l'. 4.1 ~ 5. 4 : Gross alpha radioactivity--was calculated.from-sample analysis results and; release-pointivolumes. ,

l Tanke volumes.and system flowrates' 20% ,

Sampling andystatistical error 10%.

Counting Equipment. calibration 1 .10%' j Compositing sample error. '5%. t TOTAL ERROR

~

' T5f ,

b

-1.'4.1.5.5 Volume of waste' prior.to dilution was2 calculated from level indicators on the tanks and pump discharge flow; i rates and times.- ,

i Leval indicator error 10%

Operator interpretation of gauge 710%- i TOTAL ERROR , "73Y :

i y 1.4.1.5.'6 VolumeHof' dilution water'used was calculated fromLflow

- rate indicators and pump. discharge flow' rates and times. ,

Flow-rate indicator error 10%-

Operator interpretation ofsgauge- 10% - ,

TOTAL ERROR ~20%

1.4.2 Batch Release Data ,

Other data pertinent'to batch releasesLof' radioactive.

liquid effluent are-listed in' Table 1-6a for Unit'1, and' [

Table 1-6b for Unit 2. 1 i

l 1.5 Radiological Impact on Man Due.to, Liquid Releases ls -

Doses to an individual-due--to radioactivity in. liquid effluent were calculated in accordance with Technical-Specification 3/4.11.1.2 using the methodology. presented 11n 7 the Plant 1Vogtle Offsite Dose' Calculation Manual. .Results (

are presented in Table'1-4a for Unit 1 and 1-4b for Unit 1

2. This is submitted as required by section 6.8.1.4Hof ,

Technical Specifications. #

(

)- .>

1 1.6 Abnormal Releases l -1.6.1 Itemization of the Location / Source of the Unplanned Releases !

, 1.6.1.1 There was no unplanned release for this report period. .

l

. 1 2 15 4

i

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

h b

-(-

'i n

' i

-1.7 River: Flow- f s

v 1.7.1. The-average' flow' rate of the Savannah River for this- ;

Sealannual' Effluent Report period was obtained from.the !

-ClarkiHill Dan Corp _of Engineers _ Office. The average- :[

flow. rate is 12262 cubic. feet /sec. 1 7

.e I

4 t

9

~

-t t

1 m

1 i

1 1

k I

4 e

1 I

i 16

- , - - r --- - ,a- -,*

'll

'i Tablo11_2a ,

'G;orgiGl Pow 0r Company. !

Vogtle'ElectriciGenerating Plant .U-11

~

i l

SEMIANNUAL SUMMATION OF ALL' RELEASES BY: QUARTER- 1 ALL LIQUID EFFLUENTS- !

l' Unit: 1 StartingL: 1-Jan-1990, Ending;: 30-Jun-1990f .! >

TYPE OF EFFLUENT UNITS QUARTER'1 QUARTER-2 EST.. TOT' >

ERROR %'- i t

i A. . FISSION i ACTIVATION PRODUCTS.

1 f.

' 1. TOTAL RELEASE (NOT INCLUDING

! TRITIUM, GASES, ALPHA) CURIES l3.996E-01 1.269E-01 40

!.2'. AVERAGE' DILUTED CONCENTRATION DURING PERIOD l uCi/ML 3.'568E-07 . '4 . 2 0E-07 *

3. . % N/A- 'N/A PERCENT OF APPLICABLE LIMIT B. TRITIUM

^1. TOTAL RELEASE CURIES 1.487E+02 3.309E+01 40-

___________________ _____________ _________________________'_______________ ]

t 2.-AVERAGE DILUTED CONCENTRATION 1

l DURING PERIOD uC 1.328E-04 l'.095E-04 L_______________________________________i/ML _________________________________________

3. PERCENT OF APPLICABLE LIMIT % N/A

.___________________..______________________________ _____________N/A _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

lJ b

H C. DISSOLVED AND ENTRAINED GASES L l

4 1.7 TOTAL RELEASE CURIES 9.689E-02 2.055E-03 50 :

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uC1/ML 8.651E-08 6.803E-09

3. PERCENT OF APPLICABLE LIMIT % N/A N/A ,

D. GROSS ALPHA RADIOACTIVITY

__________ ______________________________________________________________ ______ q

1. TOTAL RELEASE CURIES *0E0 *0E0 45

. __ ___ _ ____ ___ _ . _________ __ . ___ _ __ _ __ ,__ ___.._ ___ i 1

1

________________________________________________________________________________ 1 1

LIT 9.871E+05 20 E. WASTE VOL ___ RELEASED

___ _ ___ ______ (PRE-DILUTION)__ _______3.067E+06 F. VOLUME OF DILUTION WATER USED LIT 1.117E+09. 3.011E+08 20

Zeroes in this table indicate that no radioactivity was present above

-detectable levels. See Table 1-5 for typical LLD for liquid sample analyses

'1 17' I

1 a

.Tabli li2b~

Giorgio PowGr Company-E Vogtle Electric Generating Plant U-2" i

SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER - '

ALL LIQUID EFFLUENTS Unit: 2 Starting :~ 1-Jan-1990 Ending :L30-Jun-1990 .

t

. TYPE OF EFFLUENT UNITS QUARTER'1' QUARTER 2: EST.-TOTL I

ERROR:%-

____________________________.__.._________________________________________________ _ j t

A. FISSION & ACTIVATION PRODUCTS 4 I

i

.1._- TOTAL RELEASE f(NOTEINCLUDING ,

TRITIUM, GASES, ALPHA)

CURIES 6.374E-02 - 6.365E-02 40 .

2.sAVERAGE: DILUTED CONCENTRATION DURING-PERIOD .uci/ML 8.897E-08 7.149E-08

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _- j

3. PERCENT OF APPLICABLE LIMIT 't

% N/A N/A:

. 1 s

f B. TRITIUM

.______________________________________________________~_________________________ -

TOTAL RELEASE : CURIES 1.653E+02 1.783E+02: 40 l ' _1. _______________________________________________________________________________

?. . AVERAGE DILUTED CONCENTRATION DURING PERIOD. uCi/ML 2.307E-04 2.003E '

3. PERCENT OF APPLICABLE LIMIT. % N

._____________________________________________________/A- N/A 1 d

l C. DISSOLVED AND ENTRAINED GASES TOTAL RELEASE CURIES t._1. 4.781E-02. - 6 '. 4 4 0E- 0 3 ' 50-l 2. AVERAGE DILUTED CONCENTRATION i DURING PERIOD i

uCi/ML 6.674E 7.233E-09 . i j.3.. PERCENT OF APPLICABLE LIMIT % N/A N j

_________________________________________________________________/A _______________ =

. D. GROSS. ALPHA RADIOACTIVITY

________________________________________________________________________________ i cl. TOTAL RELEASE CUDIES *0E0 *0EO. 45 i

________________________. ,-__~_________________________________.._______________ .

- E. WASTE VOL RELEASED (PRK-DILUTIUN) LIT 1.032E+06 1.607E+06 20

____________________________ ___________~_._____________________________________

F. VOLUME OF DILUTION WATF.R USED Lif 7.154E+08 8.887E+08 20

______________________... _______.._______________________________________________ t

~Zeroesoin this table ludicate that no radioactivity was present'above i

detectable levels. See Tabla 1-5 for typical LLD for liquid sample analyses. ,

18

.i 6

I s

-- -+ - ,* w ,..m -- ===w, * -- 4

' Tab 13<1-2c; ,

G orgie-PowOr Company Vogtle Electric; Generating P1 anti SEMIANNUAL > SUMMATION OF'ALL-RELEASES BY QUARTER LALL LIQUID EFFLUENTS !

SITE.

Starting : 1-J r -1063 Ending':.30-Jun-1990

. TYPE.0F EFFLUENT ' UNITS QUARTER 1 QUARTER 2 EST. TOT-ERROR % :

5 A. FISSION & ACTIVATION ~ PRODUCTS-i - 1. NTAL RELEASE: (NOT INCLUDING- .

TRITIUM, GASES, ALPHA),

i- CURIES 4.63E 1.906E-01 -40 j

2. AVERAGE DILUTED-CONCENTRATION-DURING PERIOD uCi/ML 2.522E-07' l'.602E-07

3. PERCENT OFLAPPLICABLE LIMIT % N/A. N/A

' - B. TRITIUM

1. TOTAL RELEASE CURIES' 3.140E+02 2.114E+02 40 i

2. AVERAGE DILUTED CONCENTRATION !

L DURING PERIOD uci/ML 1.710E-04 1.777E-04 d J3.. PERCENT OF APPLICABLE LIMIT % N/A N/A l C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 1.447E-01 8.495E-03 50 l l2. AVERAGE DILUTED CONCENTRATION

. y DURING PERIOD uCi/ML -7.139E-09 7.880E-.08 >

3. . PERCENT-OF APPLICABLE LIMIT % N/A .N/A

_______________________________._________________________________________________ .i 7

D.. GROSS ALPHA RADIOACTIVITY ,

3 1. TOTAL RELEASE CURIES *0E0 *0E0 45 F

________________________________________________________________________________ l l

i E. WASTE VOL RELEASED (PRE-DILUTION) LIT 4.099E+06 2.594E+06 20 F. VOLUME OF DILUTION' WATER USED LIT 1.832E+09 1.189E+09 20 i

Zeroes in this table indicate that no radioacLivity was present above I

detectable levels. See Table 1 5 for typical LLD for liquid sample analyses.

19

. _ __ _ _ .. . . _-._ ~ _ . . - . . _ _ _ .

~f Tablo 1 30 REPORT CATEGORY 81 SEMIANNUAL LIQUID CONTINUOUS AND: BATCH - RELEASES ' i

TOTALS FOR EACH'NUCLIDE. RELEASED, UNIT 1 TYPE-OF' ACTIVITY : ALL RADIONUCLIDES' REPORTING PERIOD 1990 i

/ QUARTER # 1 AND QUARTER'_#

________________ 2 YEAR.

l CONTINUOUS RELEASES-l- BATCH RELEASES =~l ,

. UNIT : QUARTER 1 l QUARTER 2;l QUARTER 1 l QUARTER 2 l

-NUCLIDE l l: l -l l l AG-110M ! CURIES l 0.00E+00'l 0.00E+00El_8.72E-05..l 1.36E-04 l: !

BA-140 l~ CURIES" l 0.00E+00 l 0.00E+00 l 0.00E+00 1:'2.20E-05-l s BE-7 l ' : CURIES- _'O.00E+00 l l 0.00E+00;l 0.00E+00 l-3.33E-05-l- l

-CE-144 l- . CURIES l 0.00E+00 l 0.00E+00'l-0.00E+00 lL3.69E-06 l CO l . CURIES. l 0.00E+00 l 0.00E+00 l 4.60E-04 l L 1'. 5 6E-04 l ,(

CO-58 l CURIES l 0.00E+00_l 0.00E+00 l :1.10E-01 l14.44E-02 ,

-CO-60 l CURIES l 0.00E+00 l 0.00E+00'l 1.02E-02 l 3.96E-03-l. :

-CR-51 l CURIES l 0.00E+00 l. 0.00E+00 l 3.00E-02-l 1.88E-03 l- ;

CS-137 l CURIES l 0.00E+00'l 0.00E+00 l 9.11E-06 l _ 2. 62E-05. l .

FE-55 l CURIES l=0.00E+00fl 0.00E+00 l 1.19E-011 l - .5. 73E-02 l n FE-59 l CURIES l 0.00E+00-l 0.00E+00 l . 9. 86E-C3 : l 72.10E l:

, .G-ALPHA l CURIES ] 0.00E+00 l 0.00E+00- *0E0 , j' *0E0' l. )

H-3 l CURIES l 0.00E+00 l 0.00E+00c l-1.48E+02 ]'3.30E+01Lj CURIES l 0.00E+00 j.0.00E+00 l 4.37E-05-l 2.18E-04-lt j HF-l ' . l I-131. CURIES I-132 l

CURIES l 0.00E+00 [ 0.00E+00 l 1.28E-03.l 8.58E-06 l-I-133 l

CURIES l 0.00E+00 l 0.00E+00 l 4.14E-041l.0.00E+00'l '

.MN-54 l

CURIES l 0.00E+00 l 0.00E4 00 l 9.89E-05-l'0.00E+00 l '

NA-24 l l'0'.00E+00 l 0.00E+00 l 3.70E-03-l 2.13E-03~l l CURIES l 0.00E+00 l 0.*;2+00-l 2.72E-04 .l l'.34E-04 [ i

-NB-95 CURIES l 0.00E+00 l NB-97 l

CURIES 30E+00 l 1.32E-03'l'1'.22E-03 l LSB-122 l l 0.00E+001l s 30E+00 CURIES 'l 0.00E+00 l . 00E+00'l 1.86E-03.l: 0.00E+00 l l 2.30E-04 l 3.38E-05 l 1 l

'SB-124 CURIES SB-125 l l 0.00E+00al 0.00E+00 l 2. 51E-02 :l 3.07E-04_l l CURIES l 0.00E+00 .[:0.00E+00 l 7.65E-02 -l 4.20E-03-l SR-89 l CURIES ] 0.00E+00 l 0.00E+00 l *0E0 *0E0 l [.

SR-90 CURIES TC-99M l l 0.00E+00 l 0.00E+00~l *0E0 -l *0E0 l l CURIES l 0.00E+00-l 0.00E+00 l_l'19E-04 .

l 0.00E+00 l }

TE-129M l . CURIES TF-13'2 CURIES 0.00E+00 l 0.00E+00 l~.7.38E-03-l 0.00E+00 l_ 1

W-187 l

CURIES l 0.00E+00 l 0.00E+00 l 4.67E-04-l 0.00E+00'l XE-131M l

CURIES l 0.00E+00'l 0.00E+00 lfl.03E-05-l' O.00E+00'l XE-133 l

CURIES l 0.00E+00 l 0.00E+001l 2.65E-04 l 0.00E+00_l l

,XE-133M l

CURIES l 0.00E+00 l 0.00E+00 l 9.40E-02 l 2.05E-03 l XE-135 l

CURIES 1.0.00E+00 1 0.00E+00'l'2.83E-04 l 0.00E+00 l ;

ZN-65 l

CURIES l 0.00E+00 l 0.00E+00 l 1.71E-04.l 0.00E+00 l l LZR-95 l

CURIES l- 0.00E+00 l 0.00E+00 l.8.27E-05 l 2.65E-06 l l l 0.00E+00 l 0.00E+00.l 2.63E-04-l 6.26E-04

____________________________________________________________________._________.._l TOTAL FOR PERIOD CURIES l 0.00E+00 l 0.00E+00 l 1.49E+02 l 3.31E+01 l 9__________________._______________________________________l ______________________

Zeroes in-this table indicate that no radioactivity was present above detectable levels. See Table 1-5 for typical LLD for liquid sampleJanalyses.

20 4

Y--

, - - - = aera v N

Tablo-1-3b-REPORT CATEGORY. t SEMIANNUAL LIQUID CONTINUOUS AND' BATCH RELEASES

TOTALS FOR EACH NUCLIDE RELEASED, UNIT 2 TYPE OF ACTIVITY : ALL RADIONUCLIDES ~

REPORTING PERIOD : QUARTER- #L1E AND QUARTER _# 12' YEAR 1990 l CONTINUOUS RELEASES BATCH ' RELEASES

_ -_-_-_--_----_----_-__-_ ---_----------_-_____-__-_--_--l _----_-__-------__---- l _;

. UNIT : QUARTER l'l QUARTER 2!l QUARTER 1 l QUARTER 2'l {

NUCLIDE ll .l l- .l i

._-_---_-__ --___--_-_ -_-__--_-------_--_-__----__----_----_--_-_--_-l ___---_----

l BE-7_ _ l CURIES j.0.00E+00~l 0.00E+00 l 0.00E+00_l 5.71E-05 l -i CE-144 CO-57 CO-58

'll 1' CURIES CURIES. I_0.00E+00fl 0.00E+00J]_5.14E-06 l 3.33E-05 l l 0.00E+00;l 0.00E+00 l-6.98E-05-l 4.76E-05~l; 3 l CURIES l 0.00E+00'l,0.00E+00 l 1.95E-02 l._2.77E-02 l' A 100-60 CR-51 ~ ll -CURIES. l.0.00F+00 l 0.00E+00.l 6.80E-03 l 2.38E-03 l 1 FE-55 -l CURIES CURIES ~ l 0.005+001l 0.00E+00 l-5.11E-03LlL4'.31E-03'l j FE-59 l-- 0. 00E+00 _ l f 0. 00E+00 L l: 2. 05E-02 f l- 1. 85E-02 l. t l CURIES l 0.00E+00 l 0.00E+00 l 9.09E-04 l 6. 8 8 E-04 : l G-ALPHA *0E0

-H-3 l CURIES l l 0.00E+00--l10.00E+00"l l *0E0 , 'l j l CURIES l:0.00E+00-l 0.00E+00.lL1.65E+02-_l l'.78E+02 l- l HF-181 I-131 l l

CURIES-CURIES [~0.00E+00 l 0.00E+00'l'1.38E-05'l 1.54E-05~ll j

'I-133 CURIES -l'O.00E+00 l 0.00E+00 l11.35E-04 l 2.24E-04ul l KR-85M l

CURIES l 0.00E+00 l 0.00E+00'l.1.67E-05-l19.67E-05 l' .!

LA-140 l l 0.00E+00'l 0. 0 0E+00_ .l - 1. 3 4 E-06 '_ l ' 1. 8 0E-06: l ;

CURIES MN-54 l

l CURIES l 0.00E+00 l>0.00F+00ll-2.26E-05 l 4.42E-05 l' ]

NA-24 l CURIES -l 0.00E+00-l 0.00E+00-l 1.542-03 1.1.32E-03 l l

NB-95 l -CURIES 0.00E+00 ].0.00E+00 l . 0. 00E410 lL9.16E-05 l ,

NB-97 l CURIES l 0.00E+00-l 0.00E+00 l 9.06E-u4.l: 8. 2 3 E- 04 l 5 SB-124 l 0.00E+00-l 0.00E+00-l 0.00E+00 l16.03E-06 l l CURIES- l 0.00E+00,l 0.00E+00 ldl.97E-03 i 4.96E-04-l .i SB-125 l CURIES .l SR-89 CURIES 0.00E+00 l 0.00E+00"l 5.70F.-03 l L 6. 24E-03_= l SR-90 l

1. 0.00E+00.] 0.00E+00-l . *0E0' l *0E0 l l CURIES l 0.00E+00 l. 0.00E+00ll' *0E0- l *0EO:

TC-99M _l . CURIES l r M-187 CURIES l 0.00E+00 l 0.00E+00 l 7.83E-06 l l'.84E-05 l '

XE-131M l

CURIES l 0.00E+00 l 0.00E+00-j;0.00E+00 l 2.02E-05 l.

l XE-133 l CURIES 'l 0.00E+00 l O'.00E+00 l 8.53E-04 l'O.00E+00 l

.XE-133M CURIES. l'O.00E+00 l.0.00E+00 l'4.63E-02 l: 5.32E-03 l 1

l '

'XE-135- l CURIES l 0.00E+00 l 0.00E+00-l 2.50E-04 l'O.00E+00 l ZR-95 l CURIES- ll 0.00E+00-0.00E+00 l 0.00E+00 l 3.97E-04 l 1.11E-03 l 0.00E+00 l 4.57E-04-l 4.47E-04 l:

_-_____---__________---_-___-_-_-__--____----_-l _-___-_-_-_-_-_---___----___--___

i TOTAL FOR PERIOD l CURIES l 0.00E+00 0.00E+00 l 1.65E+02 l 1.78E+02 l

---_---_-____--_-_______-__-_----_-___-________l --______-_-_____---_-________-_-_

Zoroes in this table indicate that no radioactivity was present above detectable levels. See Table 1-5 for typical LLD foriligdid sample. analyses, j, i

21

E l '

Tnblo : 1-3c '

REPORT CATEGORY : SEMIANNUAL LIQUID CONTINUOUS AND BATCH' RELEASES

TOTALS FOR EACH NUCLIDE. RELEASED, SITE L TYPE-OF' ACTIVITY

~

ALL RADIONUCLIDES' REPORTINGLPERIOD : QUARTER # 1-AND QUARTER #'2 YEAR = 19 9 0 .

l CONTINUOUS' RELEASES BATCH . RELEASES l

__________________________________________________________l-_______-_ --_______--

UNIT : QUARTER 1 l QUARTER 2-[ QUARTER 1 l QUARTER 2-l. !

NUCLIDE l l l l !

__________________________________________________________l___________l ___________

AG-110M CURIES BA-140 l

. CURIES l 0.00E+00 l-0.00E+00 ] 8.72E-05Ll 1.36E-04 l !

BE-7 l l 0.00E+00 l 0.00E+00~ l 0.00E+00-l2.20E-05 l. d l . CURIES l 0.00E+00-l 0.00E+00 l' O.00E+00 l-9.04E-04 l CE-144 CURIES 1

CO-57 l

CURIES l 0.00E+00~l:0.00E+00 l 5.14E-06.l 3.69E-05 l ;

CO-58 l l 0.00E+00 l 0.00E+00=l 5.30E-04'j.2.04E-04 l -_ '

CURIES CO-60 l

CURIES l 0.00E+00 l 0.00E+00=l 1.30E-01'l'7.21E-02-l~ ,

CR-51 l

l 0.00E+00 l 0.00E+00 l.1.70E-02rl 6.34E-03 l CURIES .l CS-137 l

CURIES 0.00E+00 1 0.00E+00 l 3.51E-02-l 1.42E-02 l j FE-55 l l'O.00E+00 l 0.00E+00 l _9.11E-06;l~2.62E-05 [. 1 CURIES FE-59 l

~l- -CURIES l.0.00E+001l 0.00E+00 l.1.40E-vr l 7.58E-02 l l

-G-ALPHA CURIES l 0.00E+00 l 0.00E+00 l 1.08E-02 1 2.79E-03-l i

.H-3 l

CURIES l 0.00E+00 l 0.00E+00 l *0E0 l' *0E0 l'. ]

HF-181 l l 0.00E+00 l 0.00E+00,l 3.13E+02.l 2;11E+01 l j l CURIES I-131 l CURIES- l 0.'00E+00 1 0.00E+00 l 5.75E-05 l 2.33E-04 l l l 0.00E+00-l- 0.00E+00 -l.1.48E-03-l-2.33E-04-l I-132 l I-133 l CURIES-CURIES l 0.00E+00 1 0.00E+00 l 4.14E-04 l 0.00E+00 l.

KR-85M l CURIES l 0.00E+00 l 0.00E+00 ll1.16E-04 l 9.67E-05 l LA140 l CURIES l 0.00E+00 l 0.00E+00-l.1.34E-06 l 1.80E-06 l MN-54 l CURIES l 0.00E+00 l 0.00E+001l-2.26E-05 l 4.42E-05 l NA-24 l CURIES l 0.00E+00-l 0.00E+00 l 5.24E-03-l 3.45E-03-l NB-95 l CURIES l 0.00E+00 l 0.00E+00 l 2.72E-04 l 2.26E-04 l !

>NB-97 l CURIES l 0.00E+00 l 0.00E+00 l 2.23E-03 l.2.04E-03 l .

~SB-122 l CURIES l 0.00E+00 l 0.00E+00 l 2.30E-04 1 3.98E-05 l l SB-124 CURIES l 0.00E+00 l 0.00E+00 l 1.86E-03 l 0.00E+00 l l 0.00E+00 SB-125 l

l- 0.00E+00 -l 2.71E-02 l 8.03E-04 l l CURIES -l t SR-89 CURIES 0.00E+00 l 0.00E+00-l 8.22E-02'l 1.04E-02 l }

SR-90 l l 0.00E+00 l 0.00E+00 l- *0E0 l *0E0 l l CURIES l 0.00E+00 l 0. 00E+00 - l *0EO- *0E0 !

TC-99M l CURIES l l-TE-129M l 0.00E+00 l 0.00Et00 l31.27E-04 l 1.84E-05 1. .,

TE-132 l

l CURIES CURIES l 0.00E+00 l 0.00E+00 l:7.38E-03 l 0.00E+00-l j W-187 CURIES l 0.00E+00 l 0.00E+00-l 4'.67E-04 l 0.00E+00 l '

XE-131M l l CURIES .l 0.00E+00 l 0.00E+00'l 1.03E-05 1,2.02E-05 l ;

l '

XE-133 l CURIES -l 0.00E+00 1 0.00E+00 l 1.'12E-03 l 0.00E+00 l XE-133M l CURIES 0.00E+)0 l 0.00E+00 l 1.40E-01 l 7.37E-03 l -j

XE-135 l CURIES l 0.00E+00 l 0.00E+00 l 5.33E-04 [ 0.00E+00 1

~ZN-65 l CURIES l 0.00E+00 -l 0.00E+00 l 5.68E-04 l 1.11E-03 l l ZR-95 l CURIES ll 0.00E+00 0.00E+00 l 0.00E+00'l 8.27E-05.l 2.65E-06.l

_______________________________________________l 0.00E+00 l 7.20E-04 l 1.07E-03 l 1 TOTAL FOR PERIOD l CURIES l 0.00E+00 l 0.00E+00

-_________________________________________________________l 3.14E+02 l 2.11E+02 l 1

Zerces in this table indicate that no radioactivity was present above i detectable levels. See Table 1-5 for typical LLD for liquid-sample analyses. ,

i 22 a

TABLE li4A'

~l V0GTLE. ELECTRIC GENERATING: PLANT j SEMIANNUAL'RADI0 ACTIVE EFFLUENT RELEASE REPORT ')

, INDIVIDUAL 1 DOSES DUE-TO LIQUID RELEASES.

l Jania'ry 1, 1990 Through. June 30, 1990 UNIT-1 :!

3 J

Cumulative" Dose?Per~ Quarter' Organ Tech . Units Quarter %'of- . Quarter' of d, I Spec Tech Tech /!

. 'Limi t .

- . - . 1. Limit 12 Limit-I Bone- 5.0 mrea ~

4.38E-03 8.76E-02 -

7.29E-04 1.46E :

Liver 5.0 prem 5.76E-03 1.15E 2.27E-03 4.54E-02. l T. Body 1.5^ laren- :4.94E-03: :3.29E-01 1.79E 1.19E-01 ,

-Thyroid 5.9 aren 5.35E-03 1.07E-01 - 1.14 E-0 3 -- 2.ZBE-02 !f Kidney 5.0~ 'aren' '8.'65E-03' '1.73E-01 1.'29E-03 '2.58E-02 Lung 5.0 aren 1.23E-01 2.46E+00- 1.06E-02 .2.12E GI-LLI 5.0 mrea 4.08E-02 8.16E-01 6.66E-03 1.33E-01 l i

I Cumulative Dose'Per' Year ~ " ,

Organ Tech Units Year to Date .%sof-Tech-Spec Limit l Spec l Limit j Bone 10.0- mrem 5.11E-03 5.11E-02 l Liver 10.0' 'arem: '8.03E-03' ^8.03E-02: '

T. Body 3.0 mrem 6.73E-03 2.24E Thyroid 10.0 ~ mren '6.49E-03~ 6.49E-02' Kidney 10.0 ,

mrem 9.94E-U3 9.94E-02 ;

Lung 10.0 ~ mrem ~ '1.24E-01' '1'.24E+00 ,

GI-LLI 10.0 mrem 4.75E-02 4.75E-01 1

)

N 23

.ii.. .. .

. r TABLE 1-4b' V0GTLE' ELECTRIC _ GENERATING' PLANT .

SEMIANNUAL" RADIOACTIVE [ EFFLUENT RELEASE REPORT' INDIVIDUAL. DOSES DUE TO LIQUID RELEASES

. January 11,~1990 Through June 30, 1990 UNIT"2 -c i

Cdmulative Dose *Per?Qdarter Organ . Tech, Units 1 Quarter- % of Quarter %.of-t Spec . Tech- Tech. !

Limit 1- . .

Limit. 2- Limit Bone '5.0- 'aren' 4.91E 9.82E 3.72E 7.44E-03 .i Liver- 5.0 mren 6.15E-03 1.23E-01 7.47E 1.49E-01' 'I T. Body 1. 5 - aren- 5.77E-03: 3.85E-01' 7.35E 4.90E-01 7 Thyroid 5.0- aren 5.73E-03 1.15E-01 7.47E-03 1.49E-01.' f

. Kidney 5.0- area 5.53E-03' 1.10E 7.14E-03 1.43E-01. -(

, - Lung '

'5.0~ :aren- ~2.08E-02' '4.17E-01 ~1.96E-02~ '3.92E l GI-LLI 5.0 mrem 1.09E-UZ Z.15E-Ul. 1.09E-UZ Z.15E-Ul-P- .

~ '

Cumulative' Dose"Per' Year' i

Organ Tech. Units Year to Date %-of Tech Spec' Limit Spec.

Limit -

l- y l Bone- 10.0 mrem 8.63E-04 8.63E ;

E Liver- 10.0 mrem ~1.36E-02' ~1.36E-01

!. T. Body 3.0 mrem 1.31E 4.37E-01 .

l Thyroid 10.0 mrem 1.32E-02 1.32E-01 l i Kidney 10.0- mrem 1.' 2 7 E-0 2 1.27E-01 ,

l Lung 10.0 mrem 2.79E-02. 2.79E-01 1 l GI-LLI 10.0 arem 2.18E 2.18E-01 l i

I i

n i

L r

4 e

i 24

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

i

)

1 i

~)

1

~

TABLEL1-5L(Page l'of 2)

._ 9 LOWER' LIMITS 0F' DETECTION - LIQUID SAMPLELANALYSES V0GTLELELECTRICJGENERATING-PLANT (JANUARY'1,.1990.Through'JUNEL30,l1990).

-1 The values in this' table representhapriori~ lower' limits of detection t LLD)!which 'arettypicallyfachieved?in laboratory; analyses of liquid 7 radwaste, samples.- }

RADIONUCLIDE LLD UNITS ;

=!

Mn-54 2.73E-08 uCi/ml- ". t Fe-59 8.33E-08 JrCi/ml

Co 3.'78E-08 uCi/ml Co-60. '6.76E-08 uCi/ml Zn-65 1.32E-07 uC1/mi a Mo-99 4.31E-07 uC1/mi t Cs-134 3.06E-08 .uci/mi; Cs-137. -4.51E-08 uCi/m1T q

.Ce-141 .6.99E-08' uC1/m16 i Ce-144 2.95E-07= - uC1/m15 I-131- 5.97E-08' uci/ml _!

L. Xe-133 .9.11E-08 .uci/ml. i Xe-135 4.27E-08 u Ci /mi-Fe-55 1.00E-06 ~ uci/ml1 .:

Sr-89 5.00E-08 u Ci /ml- 1

-Sr-90 7.00E-09. uCi/mi -

H-3 2.00E-06 uCi/m1~

Gross. Alpha 7.00E-08 uCi'/ml. t i

L I

i i i

25 ;

F ..,, ,.,

ii

(

L

-TABLE'1-5 (Page 2 of 2)

- LOWER' LIMITS OF DETECTION -' LIQUID SAMPLE ANALYSES V0GTLE: ELECTRIC GENERATING PLANT.

-JANUARY :.1,: 199 0 ; Through. JUNE - 30,:1990

.The-valuesiin 1his table 1representfapriori lower limits of detection

- (LLD)L whichiar r typically achieved .iu .labo'ratoryJanalyses of ' liquid j Eradwaste samp14s.1 , j O

RADIONUCLIDE LLD ^ UNITS. j Au-198 3.47E-08 uCi/al' l Ba-140 1.16E uCi/ml j Be-7 3.49E-07 uC1/mli !

Co-57 ^3.35E-08 u Ci /mi- !

Cr-51 4.~ 2 4 E-0 7- uC1/mi !

Cs-138 5~37E-08 'uCi/ml l l I-133 7-.17 E-08 ' uCi/al' ;

. I-135 -2.05E-07 -uCi/ml a

La-140 8.21E-08 uC1/mi- 1 Mn-56 '2.39E-07 uci/m1T "i i Na-24 7.22E-08l uCi/ml: :

Nb-95 6.67E-08 - uct /m1' .l Nb-97 7.17E-08 uCi/ml. !

- Np-239 1.62E uCi/ml- ]

i- Ru-106 5.24E-07 uCi/ml !

Sb-122 5.53E-08 'uci/ml- 1 Tc-99m -2.90E-08 uCi/ml -l

! Te-132' 3.59E-08 'uC1/ml !

W-187 2.09E-07 -uci/mi -l Xe-131m 2.75E-07 uCi/mi-Xe-133m 3.86E-07 uCi/ml ;

Zr-95 9.03E-08 uCi/mi !

Zr-97 4.13E-08' uCi/ml !'

Sb-124 9.47E-08 uCi/ml e

s -

i I

I i

26- j l

-)

Table-1-6a '

Georgia Power Company Vogtle-Electric Generating Plant .U-1 BATCH RELEASE

SUMMARY

OF.ALL RELEASES. ,

Sta, ,ingl: . 1-Jan-1990 Ending : 30-Jhn-1990-LIQUID RELEASES

___----__-----__----__--_-_-----_------_--__---___----_--------_----_-------__-- y NUMBER OF RELEASES : 121 .

4 TOTAL TIME FOR ALL RELEASES : 14036.00 ' MINUTES 1 MAXIMUM TIME FOR A RELEASE : 563.00 MINUTES ~ ..

. AVERAGE TIME =FOR~A RELEASE : 116.00 MINUTES: !

MINIMUM TIME FOR A RELEASE : . 0. 0 0 ~- MINUTES AVERAGE STREAM FLOW : 76.32 GPM

)

i

~ GASEOUS RELEASES

___---__________-__-_-_-____~_-_____-_-______-_______________-__--_______-___-_

l NUMBER OF RELEASES : 103 TOTAL TIME FOR ALL RELEASES : 81495.00 MINUTES MAXIMUM TIME FOR A RELEASE : 20360.00 MINUTES LAVERAGE TIME FOR A RELEASE : -791.21 MINUTES MINIMUM TIME FOR it RELEASE : 5.00 MINUTES-l '1i l

I i

t I.

27

. c. ._. . . .. . -.. - - . . -,

a t

TGblo 1-6b Georgia-Power Company i

'Vogtle Electric Generating Plant U-2 BATCH RELEASE

SUMMARY

OF ALL RELEASES-Starting :- 1-Jan-1990 Ending :-30-Jun-1990- i

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

=,

LIQUID RELEAS

_-------------_---- ES- t NUMBER OF RELEASES ---------------_-------__-

92 .--_ ---_---_-------------_--

(

TOTAL. TIME'FOR ALL RELEASES't 16813.00-MAXIMUM' TIME.FOR A RELEASE' ' MINUTES.

. AVERAGE. TIME FOR A RELEASE-'-

: 591.00 MINUTES MINIMUM TIME FOR A: RELEASE' :

182.75 MINUTES- ~;

AVERAGE STREAM FLOW :

22.00 . MINUTES

.40.18 'GPM '

GASEOUS RELEA

.--___-- . SES --

NUMBER OF: RELEASES ___

30 TOTAL TIME FOR ALL RELEASES :

MAXIMUM TIME FOREA RELEASE :

9015.00 MINUTES. ,

AVERAGE TIME FOR A RELEASE- :

3056.00 ' MINUTES..

MINIMUM TIME.FOR A RELEASE :

300.50' . MINUTES-:

6.00 ' MINUTES 1 - ---------.... .-_-------._.--_____-____.---...--.....-----___

i L

l-4 t I

i i

i

?

i 2

28 i

4 i t f T b 2.0 Gaseous Effluents i . -

2.1 REGULATORY" LIMITS / TECHNICAL ~ SPECIFICATIONS The Technica'. Specifications presentedlin_this section are- -

for Unit 1 and' Unit;2. ;The instrumentation-required may; +

be found-in Tablec2-1.of^this report.

i 2.1.1 Process EffluentLMonitoring System-a 3.3.3.10 The. radioactive gaseous; effluent monitoring. .

instrumentation channelstshownLin, Table 3'.3-10 shall be-OPERABLE with theirJAlarm/ Trip Setpoints set to ensure' that the limits of Specifications'3.11.2.la'and 3.11.2.5 are not exceeded. - The Alarm / Trip-Setpoints of these~

channels meeting Specification 3.11.2.la shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

2.1.2 Dose Rate Limit 3.11.2.1 The dose rate due'to radioactive materials released in gaseous effluents from the site to-areas atiand beyond the l SITE BOUNDARY (see Figure 5.1-1 and.5.1-2) shall'be limited to the following:~ ,

a. For noble gases: 'Less.than or equal to-500 arems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin, and H.

b. For Iodine-131,.for Iodine-133, for tritium,'and for.

all radionuclides in particulate form with-half-lives greater than 8 days: Less than or equal-to 1500-mrems/yr to any' organ.

2.1.3 Air Dose Due to Noble Gas 3.11.2.2 The air dose due to noble gases released in~ gaseous effluents, from each unit, to areas at and beyond the SITE -j BOUNDARY (see Figure 5.1-land 5.1-2) shall be limited to ,

the following:

29

t 1

- H

a. During any calendar quarter: Less'than or equal'to:5 )

mrada for.gammafradiation'and less than or equal to 10 j mrads.for beta radiation,.and

b. During any calendar yeart Less than or equal 1.to 10' ]

mrads for gamma _ radiation and less than orLequal to 20 )

r: rads for beta radiation.; .I'l l

'2.1.4' Dose to'Any: Organ 3.11.2.3' The dose to a. MEMBER-OF'THE PUBLIC from Iodine-131, Io d i n e -13 3', tritium,-and all radionuclides.in particulateL form 1with half-lives: greater than.8 days.in gaseous .

1 effluents released, from each unit,-to.' areas.at and beyond- i the SITE BOUNDARY'(see-Figure.5.1-1 and'5'.1-2 of the~~ l Technical Specifications);shall be limited to the i r

followings l

a .- During'any calendar lquartert. less than or equal to' 7.5 areas to any organ and, ,

1

b. During any= calendar-yeart Less-than or~ equal to 15 mreas to any organ.

1 2.1.5 Ventilation Exhaust Treatment System and Gaseous Waste 3 Processing System:

i

-- 3.11.2.4

'i 1

ThelVENTILATION EXHAUST TREATMENT SYSTEM and.the. GASEOUS WASTE PROCESSING SYSTEM shall'be 0PERABLE and, appropriate portions of these systems shall.be'used to? reduce releases >

of. radioactivity when1the projected dosessin 31: days due- '

to gaseous effluent releases, from each unit, to-areas at and beyond the' SITE BOUNDARY-(See Figure LS.1-land 5.1-2 of .,J the Technical Specifications) would exceed:

a. 0.2'arad to air from gsmaa radiation, or a

1 I

L b. 0.4 mrad to air from beta-radiation, or L c. 0.3 mram to any organ of a MEMBER.0F;THE PUBLIC. ]

i 30

-)

i

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

. . . . ~ s u o <

( 2 51. 6 l LExjeJ osivo; Gcs Mixturo

'3.11.2.5-Thelconcentration of oxygen intthe GASE0USLWASTE l

a PROCESSING SYSTEM sbk11 be limited to less!than.or. equal '

a to?2% by volume whenever the h'ydrogen concentration '

exceeds:4% by volume.

2.1.7 Activity inl Gas _ Decay TanksL Li i

13.11.2.6 ;

'l The quantity of radioactivity containedLin each gas decay tank sha.'.1 be limited-tofless_than1or equa1>to 2.0E5l curies of noble gases;(considered asEXe-133 equivalent). 1 l

\

2.1.8 Total Fuel Cycle Dose Commitment ;

-i 3 .~ 11.' 4 ' i The annual (calendar year) dose or-dose commitment to any-MEM3ER OF THE PUBLIC due to releases of radioactivity and-to radiation from uranium. fuel, cycle sourcessshall be j

, limited to less than or equal to 25 mreas to the whole- '

body or any organ, except the: , thyroid , ' which- shall?be:

limited to less than or equal to 75 areas. ;

APPLICABILITY ACTION:

At all times.

4

a. With the calculated doses from the-release'of radioactive materials;in liquidforigaseous effluents j

exceeding twice the limitatof Specifications ;

3.11.1.2a, 3.11.1.2b, 3.11.2-2a,s3.11.2.2b, 3.11.2.3a,

. j or 3.11.2.3b calculations shall be:made including '

direct radiation' contributions.from:the; units (including outside storage-tanks etc.) to determine whether the above limits of specification 3.11.4 have been exceeded.

6.8.1.4 States in part:

The Semiannual Radioactive Effluent Release' Report =to be submitted within 60 days after January 1 of each year shal1~also' include'an assessment of radiation doses to the likely most exposed MEMBER ~OF THE PUBLIC from reactor releases and other uranium fuel' cycle-resources within 8 km, including doses from primary effluent pathways and direct radiation for the previous-calendar year to show conformance with 40 CFR part 190, " Environmental Radiation Protection Standards for Nuclear Power Operation."

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in-Regulatory Guide 1.109, Rev. 1, October 1977.

31 m -

. . . . . ~ . . - .- --

i i

!- 1 l

k Reporting of Semia'anual. Releases (Unplanned),.

~ ~

2.1.9 6.8.1.4 states in part:- ,

The Semiannual Radioactive EffluentfRelease Reports shall.

include a list and description ~of: unplanned _' releases from ,

.the' site'to UNRESTRICTED' AREAS of radioactive materials,in gaseous. and- liquid ^ ef fluents-.made';during the _ reporting c

- i period. i -

VEGP unplanned' releases-are-described:in section 1.6 of:

j this report, t

i 4

r 1

l i

l-l i

i l

1 32

, _ _ , ,. . m , m _ - , , - , . .. , . . . _ . , ,, ,

. V.

i. > ;

'l

[ A TABLE'2-1 (Sheet:1 of 4)

L U (From Technical Specifications) .

(TABLE 3.3-10)

I

- AADICACTIVE GASEOUS-EFFLUENT MONITORING INSTRUMENTATION' MINIMUM CHANNELS ^ -

INSTRUMENT

-OPERABLE APPLICABILITY . ACTION-s

1. GASEOUS WASTE PROCESSING

a. Noble _ Gas Activity 4 Monitor-Providing -

Alarm and Automatic Termination of

'q Release (ARE-0014) 'l *** 45 '

13. ; Effluent System Flow '.

Rate Measuring Device 1 ***

(AFT-0014) - 46

2. GASEOUS MASTE-PROCESSING '

SYSTEM - Explosive Gas - '

Monitoring l System 1 a. Hydrogen Monitor 1/recombiner **- 50 ,

(]) b. Oxygen Monitor 2/recombiner **

49- l

3. CONDENSER AIR EJECTOR AND STEAM PACKING EXHAUSTER SYSTEM l

a. Noble Gas Activity _ ,

. Monitor (RE-12839C) 1 *** 47

b. Iodine Sampler (RE-128395) 1- ***

5L

,i

c. Particulate Sampler (RE-128394) 1- *** 51~ l

d. Flow Rate.Nonitor 1 ***- 46 i

L (FT-12839) (FIS-12862) #

e. Sampler F' low Rate 1 *** ' 46-Monitor (FI-13211) 1 i

(S) 33 j

n - --

a . - - , - - - - . ,, -n- , . - - - , . - , , , - - , + - s,as-+--.new .--,w- w.-

-TABLE 2-1".(Sheet-2 of 4)

(From Technical? Specifications)

-O (TABLE 3.3-10) ;

l RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION- ---

MINIMUM CHANNELS INSTRUMENTS ^ l LOPERABLE' APPLICABILITY ACTION'.

'4. PLANT VENT

a. Noble Gas' Activity Monitor (RE-12442C'or RE-12444C) 1 -* 41, 48 i

,i

b. -Iodine: Sat'.cler/ Monitor (RE-12442h.or'RE-12444B) 1 *

-51

~c. Particulate Sampler / '

Monitor (RE-12442A p

-or RE-12444A)-

. 1-

51; i l

d. Flow Rate Monitor * :i

( FT-12442), 'l 1 *. 4g I i_ _e. Sampler Flow Rate j

' Monitor (FI-12442 or FI-12444) '

1 *:

46

j. <

TABLE NOTATIONS-At.all times.

- - During GAS 5008' WASTE PROCESSING' SYSTEM operation -

! i During radioactive releases via this: pathway During Eaergency Filtration ~

j l

1 I .

')

3 l .!

1- ,

e

{'

eu .

c ,. ,

e ,

L- l

.O o

l 34 o

i-

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

fr y n>

ITABLE 2-1-(Sheet'L3 of'4)

(FROM TECHNICALLSPECIFICATONS)'

TABLE:3.3-10 1

' ACTION' STATEMENTS, o ACTION'45 'With1the. number of channels OPERABLE less,thani ,

requirediby the Minimum Channels-OPERABLE. requirement.--

the' contents'of the tank (s);mayfbe releasedLto: the.

environment:provided that prior-to=initiatingLthe:

release '

a. At -.le a s t two: independent samples'of'the=thnk's-contents:are analyzed, and ,

b.- At least two-technically; qualified.memberstof.the l facility staff independently verify the? release-

'i rate' calculations and-dischargeLvalve:? lineup. .

Otherwise, suspend l release of radioactive effluents- i via-thisJpathway.- !

ACTION 46 With the number-of channels' OPERABLE ~1esalthan .

required by the Minimum Channels OPERABLE _' requirement, '

]' ;

effluent releases via_thisLpathway may:conti'nue' provided the flow rate is estimatedlat least once per l 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . !

.. l ACTION 47 With the number of channels GPERABLE-less-thane required by the Minimum Channels 1 OPERABLE requirement, I effluent releases via this' pathway may continue-provided grab samples are taken-at'least'once per 12 l hours and these= samples are-analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . i ACTION 48 With the number of channels.0PERABLE'lessL than required by theEMinimum' Channels.0PERABLEirequirement,

~

immediately suspend containment' PURGING of. radioactive effluents via this pathway.

ACTION 49 a. With the outlet oxygen monitor channel inoperable, operation of the system'may continue provided-grab samples are'taken and analyzed'at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the-oxygen ,

concentration remains less than 1 percent.

b. With the inlet oxygen' monitor inoperable, operation may continue if the inlet hydrogen monitor is OPERABLE.

1 35 j

1

-r TABLE 2-1 (Sheet 4-of 4). .,

FROM TECHNICAL SPECIFICATIONS. <

TABLE '3.~ 3-10

-TABLE NOTATIONS (Continued) *

') !

,' -- c . - -With;bothioxygen channels or:both of.thelinlet. i oxygenland inlet hydrogen: monitors inoperable, j suspend. oxygen supply to.the:recombiner.. j Additionof, waste' gas to;the system may continue provided_ grab samplesiareLtaken and analyzedJat

.least1once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months duringidegassing: 1 operationsEor atileast once;per 24. hours (during-

.other operations and the oxygen;concent' ration! ~i remains leastthan: 11 percent. ,

~

. ACTION 50 With the number:of channels OPERABLE one less tha n~

required by the Minimum. Channels'OPERABLEJrequirement,.

suspend oxygen-supply to the recombiner.- Addition of waste gasato tlue system mayLcontinue provided~ grab ,I

,~

samples are-takenland-analyzed at_least once per'4: ,

hours duringfdegassing operation'or:at least once-per l

24. hours during other operations.and the: oxygen

. concentration remains less than*l' percent. !

ACTION 51 With the number of channels 0PERABLE less than.

required.by the Minimum Channels: 0PERABLE requirement ,

effluent releasestvia the affected pathway may. ,

continue provided samples are continuous 1yrcollected with auxiliary sampling equipment:as required in Table 4.11-2 of the. Technical Specifications.

4 s

\

s r

f k

e

. 36

1 1

2.2, Release Points'of Gaseous-Effluents-Gaseous Effluents at Vogtle Electric Generating Plant- !

are currently confined tolfourfpathatfplant-vents: ~!

(Unit _l'and Unite 2),Jand the< condenser air-ejector and?

steca packing exhausterjsystems (Unit 1 and Unit 2).

Waste gas" decay tanks'are batch releases andtthe waste !

gas? decay tanks are_zreleasedithrough'theaUnit 1 plant' ]

vent. Containment purges are1 released through1their 1 respective plant vents,

~

j

l l

2. 3' Sample - Collection andEAnalysis-All of the paths can be continuously monitnred for, gaseous radioactivity. Each is' equipped with an a integrated-type sample collection = device :f or - ;

collecting:particulates:andniodines. Sample: ,

collection is in accordance with' Technical i Specification Table-4.11-2. During this release _ l period, there were no radioactive releases;through the condenser air. ejector and. steam packing exhauster system. vents. Unless required more frequentlyfunder certain-circumstances specifiedLin. Table Notations'to :

the above mentioned tables, samples are-collectedias

follows:

i

1. Noble, gas samples are collected by grab sampling monthly. ;

2. Tritium samples are' collected by grab sampling monthly. Since spent fuel was placed in the spent fuel pool during the first Unit 71 ref ueling,: , j tritium samples are collected weekly on-the Unit 1 and Common Plant Vent.'

3. Radioiodine samples are collected from the sample l

. stream through a charcoal cartridge-over a 7-day I period.

4. Particulates are collected from the sample stream throu.h a particulate' filter over's 7-day-period.

5. The 7-day particulate filters above are analyzed for gross alpha activityk

6. Quarterly composite samples _are prepared from the ,

particulate filters collected over the previous quarter and the quarterly composite sample is analyzed for Sr-89 and Sr-90, 37

+ , ,

4

(;

7

'1

'1 Batch Waste Gas DecayJTank releases _aro analyzedIfor_ i lodines, particulates and noble gases befora;eachl L release. . In addition, the containmentJatmosphereLis L analyzed for tritius'

at least aLmonthly basis.

b Sample analyses results and releasefflowarates,from I the release. points; form the basis'foricalculating.

released quantitiess.of 'radionuclide' specific

radioactivity, dose rates associated-with gaseous ,

releases and cumulative-doses for the current quarter 1 and' year..- This task'is normally performed with' computer assistance.

-4'

_The noble gas. grab. sample and analysis (for principal' gamma-emitters) results aresused alonglwith maximum expected release flow rates f rom each .of . the vents :to calculate monitor setpoints,-for:the' gaseous: effluent, monitors serving:the two'releasecpoints,cto~ assure that thel 11mits of Technical 1Specifi cations 3.11. 2. la-are not exceeded. Calculation of monitor setpoints is described in the Vogtle Electric Generating" Plant ODCM.; ,

'With each release period and batch release,

- radioactiviev, dose rates and cumulativeldoses-are-calculated. Cumulative dose'results are; tabulated,'

along with percent of Techrinal Specification = limits :

(3.11.2.2/and 3.11.'2.3), # .ach release for the; current quarter and year. -

After each calendar qua'ter r (13~ weeks), a summary of waste gas releases-from tie two vents and batch.

processes is compiled for preparation of;the Semiannual Radioactive' Effluent Release Report .

l required by Technien1. Specifications 6.8.1.4'and NRC .

l Regulatory Guide 1.21. !

2.4 Determination Of Total' Quantities of Radioactivity, Dose' Rates and Cumulative-Doses' !

The methods for determining release quantities'of I radioactivity, dose rates and cumulative! doses-are as -!

follows: -

1 l 1:

i l

1 h i L !

2.4.1 Fission and Activation Gas The radionuclide-specific released radioactivity is determined from' sample analyses results collected as described.above and average release _ flow rates over the period represented by the' collected sample.

Instantaneous dose rates due to noble gases and due to radiolodines, tritium, and'particulates are ca.'culated (with computer assistance). Calculat-?. dose rates are compared to the dose rate limits specified in 3.11.2.la for noble. gases, and 3.11.2.lb of the Technical Specifications for radiciodine, tritium, and particulates. Dcae' rate calculation methodology is-presented in the ODCM.

Beta and gamma air doses due to noble gases are calculated for the' location in the unrestricted area with the. potential for the highest exposure due to gaseous releases. Air doses are calculated fot.eachi release period and cemulative totals are kept for each

, unit for the calendar quarter and year. Cumulative air doses are compared to the dose limits specified in Technical Specification 3.11.2.2. Current. percent of the technical specification limits are shown on the l

printout for cach release period. Ait- dose :

calculation methodology is presented in the ODCM. l 2.4.2 Radioiodine, Tritium and Particulate Releases Released quantities of radioiodinea;are determined-from the weekly samples and release flow rates for the I two release potr?.s. Radioiodine concentrations are I determined by gamma spectroscopy. !

Release quantities of particulates are determined from the weekly (filter) samples and release flow rates for i the two release points. Camma spectroscopy is used to j quantify concentrations of principal gamma emitters.

7 After each ouarter, the particulate filters from each vent are combined, fused, and a strontium. separation i is performed. If Sr-89 or Sr-90 is not detected, ;

LLD's are calculated. Strontium concentrations are t

'nput to the composite file of the computer to be used for release dose rate and individual dose calculations.

Tritium samples tre obtained at least monthly from each vent by bubbling the sample: stream through a water trap. The tritium concentration in water is converted to tritium concentration in air and this value is input into-the composite file of the computer to be used in release, dose rate, and individual dose calculations.

Dose rates due to radioiodine. tritium,-and particulates are calculated for a hypothetical child, exposed to_the inhalation pathway, at the locatJon in-the unrestricted area where the potential dose-rate is expected to be the highest. Dose rates are calculated for each release point, for each release period, and the total doke rate from both release points are compared to the dost rate limits specified in Technical Specification 3.11.2.lb.

Individual doses duc-to radiciodine, tritium and; particulates are calculated for the critical receptor, which for Vogtle Electric Generating Plant is a child exposed to the inhalation and ground plane pathways. !

Individual doses are calculated for each release period, and cumulative totals are kept for each unit for the current calendar quarter and year. Cumulative j individual doses are compared to the dose limits !

specified in Technical Specification 3.11.2.3.

Jurrent percent of technical specification limits are shown on the printout for~each release period.

2.4.3 Gross Alpha Release The gross alpha release is computed each month 'oy-counting the particulate filters offsite for each week for gross alpha activity in-a proportional counter.

The four or five weeks' numbers are then recorded on a -

data sheet and the activity is summed at the end of-the month. This concentration is input to the composite file si the computer and is used1for release calculations. j l

2.5 Gaseous Effluent Release Data i 1

I 1

40 l

2.5.1 Methodology Regulatory Guide 1.21 Tables 1A, 1B, and 1C are found s in.this report as Tables 2-2a,-2-2b, 2-3a 2-3b, 2-4a and 2-4b. Data is presented on a quarterly basis as required by Regulatory-Guide 1.21. j To complete Table 2-2a.and 2-2b, total release for each of the four categories.(fission and act),vation

. gases, iodines, particulates, and tritium) was divided by the number of: seconds in the quarter to obtain a release rate in uCi/second for each category for each quartet. . However, the percent of the applicable Technical Specification limits are not applicable because we have no, curie limits foragaseous releases. Noble gases are limited as specified in Technical Specification 3.11.2.la.- The other three categories (tritium, radiciodines, and particulates)-

are limited as a group:as specified in Technical Specification 3.11.2.lb. Dose rates due to noble gas releases and dut to radiciodine, tritium, and particulates were calculated as Part 4 of the pre-release and post-release permits'on individual permits. No limits were exceeded for this reporting period.

Gross alph'a radioactivity is reported in Table 2-2a ,

and 2-2b as curies released in each quarter.

l i

Limits for cumulative beta and samma air doses due to noble gases are specified in Technical Specification -- -3.11.2.2. Cumulative air doses are presented in Table 2-6a and 2-6b along with percent of technical specification limits.

Limits for cumulative individual doses due to radiciodine. tritium, and particulates, are specified in Technical Specification 3.11.2.3.. Cumulative individual doses are presented in Table 2-7a and 2-7b along with percent of technical specification limits.

i The total or maximum error =ansociated with the t effluent measurement will include.the cumulative errors resulting f rom the -tota' operation of sampling and asasurement. Because it may be very difficult,to assign error teras for each parameter affecting the i final measurement, detailed statistical evaluation of !

error are not suggasted. The objective should be to J

, obtain an overall ostimate of'the error associated :

with measurements of radioactive materials released in liquid and gaseous effluents and solid waste.

41

Estiosted crrors cro based ca orrors in counting equipment I rates, ventcalibration, counting' statistics, vent-flow sample flow rates, non-steady release {

rates, chemical' yield factors and sample losses for ;

such items as charcoa1' cartridges. '

I ;

I 2.5.1.1 Fission and activation total release-was calculated ?

from sample analysis results'and: release point flow ra t e s . j

't Sampling and statistical error in. counting 10%

Counting equipment calibration '10%

Vent flow rates 10%

l Non-steady relense rates 20%

TOTA.L ERROR l

TUT 2.5.1.2 i 1-131 releases were calculated ~fron eac)- weekly l sample: "

Stattetical error in counting 10%

I Counting equipment calibration 10%

Vent flow rates 10%'

Vent sample flow rates 50%

Non-steady release rates 10%-

i Losses f rom charcoal ca re ridgia.

10%

TOTAL ERROR ' 0 ;

100%

t 2.5.4.3 t Particulates with half lives creater than 8 day i releases and release werepoint calculated flow rates. from sample analysis resulta j Statistical error at LLD concentration Counting equipment calibration 10%

10%

Vent flow rates -

Vent 9 ample flow rates 10%

50%

Non-steady release rates '

TOTAL ERROR 10%

33Y 2.5.1.4 Total tritium releases were calculated from sample ~

analysis results and release point flow rates.

Water vapor in semple stream determination 101 Vent flow rates 10%

Counting calibration and statistics 10%

l Non-steady release rates 101 TOTAL ERROR ~

TDY i 2.5.2 Gaseous Batch Data .

Other data pertinent to batch releases of radioactive ?

gaseous effluent from Unit Table 1-6a and 1-6b. 1 and-Unit 2 are listed in 1 42

- . - - - . , . - _ - - .-_--.w,. -

-._m.

. . . . , , . . . e --,.-y. . , _ - . , . . , . . . - . , , . ~ . . < ,

)

i l

i

2. 6' j Radiological Impact Due to Gaseous Releases Dose rates due. to noble gas releases were calculated i for the site in accordance Specification 3/4.11.2.la. with. Technical $

radiciodine tritium, and particulates Dose rates due to.

in gaseous ,

releases wer,e calculated in accordance with. Technical ~ i Specification 3/4.11.2.lb. .'

As'part ',f release permits, pre-release these dose and post release on individual limits were exceeded for this rates were calculated. No reporting period'.

Cumulative air- doses dat to ' noble ' gas' releases were

. calculated'for'each Specification 3/4.11.2.2. unit in accordance with Technical /

These results arel presented 2 in Tables 2-6a-and 2-6b.

Cumulative doses to en individual due to radiciodine, tritinu, and particulates were calculated in accordance with Technical Specification 3/4.11.2.3.

These results-are presented in Tables.2-7a and 2-7b.' 1 Dose rates.and doses were calculated using the methodology presented in the Vogtle Electric Generating plant Off site Dose Calcult ion Manual.

1 1

i 43

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

i a

I Table 2-2a Georgia Power Company .

Vogtle Electric Generating Plant ,

SEMIANNUAL SUMMATION OF ALL R2 LEASES BY QUARTER l ALL AIRBORNE EFFLUENTS j UNIT 1 Starting : 1-Jan.1990 Ending : 30.Jun.1990

]

TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 IST. TOT i ERROR %

1 A. FISSION & ACTIVATION PRODUCTS i

1. TOTAL RELEASE CURIES -6.318E+01 4.732E+00 50

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 8.115E+00 6.019E.01 :

3. PERCENT OF APPLICABLE LIMIT N/A

+

% N/A- l L

B. RADIOIODINES s

i

1. TOTAL IODINE-131 CURIES 1.000E-05 1.001E-06 100 ,

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.286E-06 1.273E 07 I l ....__.....__....._____..__.............___........_________............______

3 'ERCENT OF APPLICABLE LIMIT

% N/A N

.___....__ _________...._________________ .... ________________/A __....________

l C. PARTICULATES l

1.

PARTICULATES(HALF. LIVES >8 DAYS) CURIES 2.621E-05 3.160E-06

____....______ .____________..__..._____ ...........__________.._________90 ___ ...

2 AVERAGE RELEASE RATE FOR PERIOD uC1/Sec 3.370E.06 4.019E.07

3. PERCENT OF APPLICABLE LIMIT % N .N/A

... __......____...__.___ __....__.......__ __......._/A...._______...____________

4. GROSS ALPHA RADIOACTIVITY CURIES 2.587E.07 3.797E.07 D. TRITIUM

1. TOTAL RELEASE CURIES 3.790E+01 3.460E+01

__..___.________..____..______________.....________.. ______. ......______40 _ ___.. ;

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.874E+00 4.401E+0 '

___....______...... _______..._______ __...__._______....__...__. ._0____________

3. PERCENT OF APPLICABLE LIMIT % N

_..__.._______ ____..._____ ..._______________.....__ ___ N/A

/A ___.._________..___... -

Zoroes in this table indicate that no radioactivity was present above dotcetable levels. See Table 2-8 for typical LLD for gaseous sample analyses.

i 44

1 4

Table 2-2b Georgia Power Company i Vogtle Electric Generating Plant SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER i l

ALL AIRBORNE EFFLUENTS Starting 2 UNIT: 2 ,

1-Jan-1990 EndingL: 30.Jun-1990 TYJE OF EFFLUENT l

UNITS QUARTER 1- !

QUARTER 2 EST. TOT '

l I

....................... _........ ERROR %

I A. FISSION & ACTIVATION PRODUCTS .

1. "?OTAL RELEASE..............___..........................__.........______...............

l I

.............____......____..____... CURIES 1.270E+01 2. 50

2. AVERAGE RELEASE RATE FO ............____..........680E+01 ..........__.....

..............____..___ ..R PERIOD..... uCi/Sec ....... 1.63 3

PERCENT OF APPLICABL2

............3E+00 .......

3.372E+00

__.. .............. j

....... _.........______. LIMIT........__........______...N/A- N/A B. RADICIODINES

1. TOTAL IODINE-131 0.000E+00

_____............................... CURIES......_-___..... ...... 7. 4E 100 i

2. AVERAGE RELEASE RATE ....................

uCi/Sec 0.

9.209E-08 i -__.......___............FOR

3. PERCENT OF APPLICABL LIMIT PERIOD....__ ..................000E+00

.._____ .__ ___..... __E %

___..........___......___..._N/A N/A t

C. PARTICULATES 1

1. PARTICULATES(HALF-LIV

.....___ .._____ CURIES ____......

...____ES>8 DAYS)_____.__________....____0.000 2.950E-06 I

2. AVERAGE RELEASE RATE F ..____________90 uCi/Sec 0.

3. .OR PERIOD....__.......... ________.000E+00 3.716E-07 PERCENT OF APPLICABLE % ........... ____......... ___

......... ___ ... ____ __ LIMIT _ ___..........._.......

4. GROSS ALPHA RADIOACTI

__N/A N/A-

CURIES

........................VITY.. ___............ __...5.008E-08 3.061E-08 D. TRITIUM

1. TOTAL RELEASE 1.662E+01

_.AVERAGE

__.___............__..__......__.. CURIES...___......__ __.....__7.700E+00 40 F i

- 2. RELEASE RATE uCi/Sec. __.___ ___._____... '

__.......___.....FOR PERIOD __._.....______......... 137E+00 2

9.687E-01 1

3. PERCENT OF APPLICABL LIMIT

.....__..............._E % ...._______...____.____.......

_...... .......___...__ .__..N/A N/A-

!a Zoroos in this table indicate that no radioactivity was ..... __.................___

present' abo )

i dotcetable levels. See Table 2-8 ve i for typical LLD for gaseous sample analyses. !

45 ;

,\, .

\

Table 2-2c Georgia Power Company Vogtle Electric Generating Plant SEMIANNUAL SUMMATION OF ALLLRELEASES'BY QUARTER ALL AIRBORNE EFFLUENTS SITE Starting 1-JAN-1990 Ending : 1-JUN-1990 1

TYPE'OFEEFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT 1 ERROR % i

-l4 A. FISSION & ACTIVATION PRODUCTS 1._ TOTAL RELEASE CURIES 7.588E+01, -3.353E+01 50 ;

4

2. AVERAGE RELEASE RATE FOR PERIOD uC1/Sec 9.758E+00 4.264E+00

..____........-........__.......______ ........________...__.... ..........___._ i

3. PERCENT OF APPLICABLE LIMIT

% N/A N/A B. RADIOIODINEC

1. TOTAL IODINE-131 CURIES 1.000E-05 1.733E-06 100 '

..__...__.............. ....._____....__.__.....__...__.......... ...........~._

2. AVERAGE kELEASE RATE FOR PERIOD uCi/Sec 1.286E-06 2.204E-07

3. PERCENT OF APPLICABL2 LIMIY % N/A N

.____..__. ....___. ...._____....____...........__....__'_..___.../A ...............

P C. PARTICULATES

.__.....__as.__........____._..................__.._..................___......__

1. PARTICULATES (HALF-LIVES >8 DAYS) CURIES 2.621E-05 3.294E-06 90

3. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.371E-06 4.189E-07 3, PERCENT OF APPLICABLE LIMIT % N/A N

_ ...__ ......... ___ ................ _..... ....__ ./A- . . . . . _ . . _ _ _ _ _ _ .

4. GROSS ALPHA RADIOACTIVITY CURIES 3.088E-07 4.103E-07 l

D. TRITIUM

1. TOTAL RELEASE CURIES 5.452E+01 4.230E+01 40

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Jac 7.011E+00 5.380E+00

3. PERCENT OF APPLICABLE LIMIT % N/A N

__...._______...._________________________________________ . ..../A. ____________. )

Zoroes in this table indicate that no radioactivity was present above l dstectable levels. See Table 2-8 for typical LLD for gaseous sample analyses.

46

^l TABLE 2-3a'(Page 1 of 2)

V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT REPORT .l GASEOUS EFFLUENTS - MIXED MODE -'

January 1, 1990 Through June 30, 1990 l' UNIT 1 i

l Continuous Mode Batch Mode Nuclides Unit -Quarter. Quarter Quarter Quarter I Released 1 2 l'~ 2 I

1. Fission Gases l l

Xe-137 Ci 80E0 *0E0 *0E0 *0E0 l Kr-85 Ci *0E0 *0E0 *0E0 1.56E Xe-133 C1 4.16E+01 3.80E+00 1.o3E+01 4.46E-01 Xe-135 ~ C1 4.32Er5T - 2.94E-02 2.56E-02 1.01E-03 Ar-41 C1 80E0 80E0 1.26E+00 2.92E-01 !

i Xe-131m Ci *0E0 *0E0 1.25E+00 1.22E-03 Xe-133m Ci *0E0 *0EO. 2.38E-01 8.28E-04 Kr-85m Ci *0E0 *0E0 1.01E-03 6".'20E-07 l TOTAL FOR PERIOD C1 4.20E+01 3.83E+00 2.11E+01 8.98E-01 l

2. Iodines -[

l 1-131 C1 1.00E-05 1.00E-06 *0E0 *0E0 I

1-133 Ci 4.80E-06 80E0 80E0 *0E0 TOTAL FOR PERIOD C1 1.48E-05 1.00E-06 80E0 a0E0 .

I e

Zeroes in this table indicate that no radioactivity.was present above

! detectable levels. See Table 2-8 for typical lower limits of detection for gaseous sample analyses.

t

.i 47

.,- , - - , , .. - . . . - , ,,wy ...w-.-- -~ri - e

i TABLE 2-30 (Pcgo 2 of 2)

VOCTLE ELECTRIC GENERATING PLANT i SE!!I ANNUAL RADIOACTIVE EFFLUENT REPORT ;

GASEOUS EFFLUENTS -MIXED MODE January 1, 1990 Through June 30, 1990' UNIT 1 )

I i

Continuous Mode ~ Batch Mode Nuclides Unit -Quarter Released 1 Quarter - Quarter Quarter '

2 1

3. Particulates** 2 i

Co-57 C1 2.00E-07 Co-58

0E0 *0E0 *0E0 Co-60 C1 1.27E-05 -3.16E-06 *0E0 *0E0 C1 1.6/E-06 "0EC Mn-54 #0E0 a0E0 Ci 8.38E-07 80E0 - 80E0 L

H-3 Ci 80E0 ;

3.34E+01 3.32E+01 4.54E+00 G-Alpha ci 2.58E-07 1.35E+00~

Cr-51 80E0 *0E0 *0E0 G1 7.06E-06 Fe-59 80E0 #0E0 #0E0 C\ 3.74E-06 a0E0 #0E0 80E0 TOTAL FOR PERIOD- Ci 3.34E+01 3.32E+01 4.54E+00 1.35E+00-

Zeroes in this table indic.ste that no radioactivity was present above detectable levels. See Tabit 2-8 for typical lower limits of detection for gaseous sample analyses. l Walf lives greater than 8 days.

l I 1

I 48 1

I

. ,

v-'ew y T* --Wa- *-W't e'+

^

--*y --

.t 4

)

l J

TABLE 2-3b (Page 1 of 2T V0GTLE ELECTRIC GENERAT* NG PLANT ;

SEMIANNUAL RADI0 ACTIVE EFFLUENT REPORT CAFEOUS EFFLUENTS - MIXED MODE ,

January 1, 1990 Through June 30, 1990 UNIT 2 3 l

t l

Continuous Mode Batch Mode Nuclides Unit Quarter Quarter Quarter Quarter Released '

1 2 1 2

1. Fission Gases ,

Kr-85a ci 7.80E-02 80E0 4.94E-05 *0E0 Ke-133 Ci 1.11E+01 1.92E+01 2.38E-02 2.68E+00 Xe-135 C1 1.49E+00 2.04E+00 1.46E-03 1.70E-01 Ar-41 Ci "0ED 1.ZlE+00 1.65E-02 1.49E+00 TOTAL FOR PERIOD Ci 1.77h+61 2.25E+01 4.18E-02 4.34E+00

! 2. Iodines

i I-131 '

Ci * ' E0

- 7.32E-07 80E0 80E0 ?

1-133 Ci *0E0 1.38E-05 n0E0 80E0 TOTAL FOR PERIOD Ci 80E0 1.45E-05 *0E0 *0E0 1

Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical lower limits of detection for gaseous sample analyses.

4 49 ;

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

. TABLE 2-3b (Poge 2 of 2) ,

V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - MIXED MODE January 1, 1990 Through June 30, 1990 ,

UNIT 2 ,

t

' Continuous Mode Batch Mode I

Nuclides Unit Quarter Quarter Quarter Quarter '

Released- 1 2 1 2

3. Particulates** ,

CO-57 C1 *0E0 3.46E-08 *0E0 80E0 Co-58 Ci 80E0 *0E0 *0E0 2.82E-06 co-60 C1 " O,5 0 "OEO- "0E0 "0E0 ,

Mn-54 Ci *010 80EO- 80E0 *0E0 H C1 1.2TE+01 7.70E+00 4.30E+00 80E0 G-Alpha Ci 5.00E-08 3.06E-08 80E0 *0EO-Sr-90 Ci 80E0 9.94E-08 80E0 80E0 I

TOTAL FOR PERIOD Gi 1.23E+01 7.70E+00 4.30E+00 2.82E-06 L

Zeroes in this' table indicate that no radioactivity was present above

! detectable levels. See Table 2-8 for typical lower limits of detection for gaseous sample analyses.

?

- Half lives greater than 8 days.

O

?

f 50 w ,--- - n v ,.,,,a - + , --

i s

. TABLE 2-3c'(Page 1 of 2) l V0GTLE ELECTRIC GENER ATING PLANT l SEMIANNUAL-RADIOACTIVE EFtL"*.NT REPORT t GASEOUS. EFFLUENTS - MIXED MODE-- -

January 1, 1990 through June- 30, 1990 l Site )

i Continuous Mode Batch Mode Nuclides Unit Quarter Quarter Quarter Quarter.

Released 11 ' 2 1 2 >

1. Fission Gases Ci Xe-137 Ci *0E0 *0E0- *0E0 *0E0 Kr-85a Ci 7.80E-02 *0E0 =1.06E 6.20E-07 Kr-55 Ci =0E0 "OED "OEO 1.56E-01 Xe-133 Ci 5.27E+01 2.30E+01 1.83E+01 3.13E+00 Xe-135 Ci 1.92E+00 2.07E+00 2.71E-02 1.71E-01 Ar-41 C1 80E0 1.21E+00 '1.7BE+00 1.78E+00 Xe-131m Ci 80E0 80E0 1.25E+00 1.22E-03 Xe-133a Ci a0E0 80E0 2.38E-01 8.22E-04 TOTAL FOR PERIOD Ci 3.47E+01 2.63E+01 2.llE+01 5.24E+00 t

2. Iodines i

'I-131 Ci 1.00E-05 1.73E-06 *0E0 *0EO-I-133 G1 4.5UE-UO 1.35E-U3 "OE0 =0E0 i TOTAL FOR PERIOD C1 1.48E-05 1.55E-05 *0E0 80E0 t

Zeroes in this table indicate that no radioactivity was present above r detectable levels. See Table 2-8 for typical lower limits of detection l_ for gaseous sample analyses.

d

?

51

TABLE 2-3c (Page 2 of 2). j V0GTLE ELECTRIC GENERATING PLANT i SEMIANNUAL RADIOACTIVE EFFLUENT REPORT I GASEOUS EFFLUENTS - MIXED MODE !

January'1. 1990 Through June 30, 1990 l Site l l

l

)

Continuous Mode Batch Mode Nuclides Unit Quarter Quarter Quarter Quarter-Released 1 2 1 2 l

3. Particulates** j Co-57 C1 2.00E-07 3.46E-08 80E0' *0E0 co-58 C1 1.27E-05 3.16E-06 *0E0 2.82E-06 f Co-60 C1 1.67E-06 80E0 80E0 80E0

'Mn-54 Ci 8.38E-07 80E0 #0E0 #0E0 ,

W-3 Ci 4.57E+01 4.09E+01 8.84E+00 1.35E+00 G-Alpha Ci 3.08E-07 -4.09E-07 *0E0 a0E0 Cr-51 C1 7.06E-06 80E0 80E0 #0E0 '

Fe-59 C1 3.74E-06 80E0 80E0 #0E0 Sr-90 Ci *0E0 9.94E-08 80E0 #0EO-TOTAL FOR PERIOD C1 4.57E+01 4.09E+01 8.84E+00 1.35E+00 :

i

Zeroes in this table indicate that no radioactivity was present above ;

detectable levels. See Table 2-8 for typical lower limits of detection for gaseous sample analyses.

- Half lives greater than 8' days. (

[

52

d 1

')

TABLE-2-4a-(Page 1 of 2) j V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE E) FLUENT REPORT GASEOUS EFFLUENTS - GLOUND RELEASES January.1, 1990 Through June 30, 1990 l UNIT 1

' Continuous' Mode Batch' Mode l' Nuclides. Unit Quarter * ~ ' " Quarter

Quarter * ' Quarter * ;

Released' ~1 2' ~~'~1' 2~

1. Fission Gases C1

-Kr-85 'Ci' _

Kr-85m Ci Kr-87 Ci Kr Ci ~

Xe-133 Ci Xe-135 'Ci .

Xe-135m Ci Xe-135 Ci

~

Xe-133m Ci ,

TOTAL FOR PERIOD:~C1 -

2. Iodines I-131 ~C1 1-lJ3 G1 TOTAL FOR PERIOD Ci

! i

No releases during this period.

I l 53 1

^

1 1

TABLE 2-4a (Page 2 of 2)

V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT REPORT l GASEOUS EFFLUENTS - GROUND LEVEL January 1, 1990 Through June 30, 1990 i UNIT 1 l i

l Continuous Mode Batch Mode I Nuclides Unit Quarter

Quarter

Released 1 Quarter

Quarter

2 1

3. Particulates ** 2-I Mn-54 Ci Fe-59 . C1

~

a-58 ~ Ci ~

Co-60 '

Ci. ~

Zn-65 Ci '

Sr-89 Ci Sr-90 Ci Mo-99 Ci Nb-95 Ci Cs-134 Ci Cs-137 Ci Ba-140 C1 l La-140 Ci ~

Ce-144 C1 Ce-141 Ci TOTAL FOR PERIOD Ci No releases during this period .

1 Half lives greater than 8 days t

i e

54

4 i

TABLE 2-4b'(Page.1 of 2) ;

voGTLE ELECTRIC GENERATING PLANT j SI" r?UAL RADIOACTIVE EFFLUENT REPORT 6.t@a,S EFFLUENTS - GROUND RELEASES i January 1, 1990 Through June 30,-1990 ,

UNIT 2 .

i i

4

'Continuouc Mode' ~ Batch Mode Nuclides Unit Quarter

Quarter

Quarter

Quarter *

^ ~

'2' ;

Released l' '2' l' i

1. Fission Gases Ci Kr Ci Kr-85m Ci ,

Kr-87 Ci

Kr-88 Ci _

R '3 Ci Xe-135 Ci ' '

Xe-135m Ci Xe-138 Ci Xe-133m Ci TOTAL FOR' PERIOD ~ Ci

2. Iodines I-131 Ci l 1-133 Ci i

1-135 Ci TOTAL FOR 'ERIOD Ci

No releases durin8 this period. ,

55

l, I

i TABLE 2-4b (Page 2 of 2) !

i V0GTLE ELECTRIC GENERATING PLANT j SEMIANNUAL RADIOACTIVE EFFLUENT. REPORT GASEOUS EFFLUENTS - GROUND LEVEL )

January 1, 1990 Through June 30, 1990 i UNIT 2 '

l Continuous Mode Batch Mode Nuclides Unit Quarter

Quarter

_ Released 1 Quarter

Quarter

1 2 1

_3 . Particulates **' 2 l 1

Mn~54 Ci Fe-59 Ci -

_Co-58 Ci ~

Co-60 c1 )

En-65 Ci i Sr-89 Ci- 1

.Sr-90 Ci Mo-99 Ci

_Nb-95 C1 Co-134 Ci Cs-137 Ci Ba-140 Ci La-140 C1 !

Co-144 Ci Ce-141 Ci TOTAT FOR PERIOD Ci ,

F Wo releases during this period I l Half lives greater than 8 days l

4 l

l 1

u .

1 i

TABLE 2-4c (Page 1 of 2)

V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUBNT REPORT GASEOUS EFFLUENTS - GROUND RELEASES-January 1, 1990 Through June 30, 1990 Site

' Continuous' Mode Batch Mode Nuclides Unit Quarter

Quarter * ~ ^ ~ Quarter

Quarter *

~1'

~l~

Released ~2~ 2^

1. Fission Gases Ci Kr-85 'C1 Kr-85a 'C1 Kr-87 Ci Kr-88 Ci Xe-133 Ci Xe-135 Ci Xe-135m Ci Xe-138 Ci ~

Xe-133m Ci TOTAL FOR PERIOD C1

2. Iodines I-131 Ci i 1-133 C1 !

1 TOTAL FOR PERIOD Ci i

No releases during this period.

57 W

l i

TABLE 2-4c (Page 2 of 2) .

-V0GTLE ELECTRIC GENERATING (LANT !

SEMIANNUAL RADI0 ACTIVE EFFLUENT REPORT i GASEOUS EFFIUENTS - GROUND LEVEL ;

January 1, 1990 Throush June 30, 1990 Site i 1

I 4

Continuous Mode Batch Mode Nuclides Unit Quarter

Quarter

Released 1 Quarter

Quarter

2 1 2

3. Particulates **

Mn-54 Ci Fe-59 C1 Co-58 C1 Co-60 Ci Zn-65 Ci Sr-89 -Cf Sr-90 C1 Mo-99 Ci Nb-95 C1 Cs-134 Ci Cs-137 Ci Ba-140 ' Ci La-140 Ci ~ ~ ~

co-144 Ci ^

Ce-141 Ci "

a~

TOTAT FOR PECIOD C1

No releases during this period.

Half lives greater than 8 days s.

- - _ -- - .-- - , , - - - - , , - - _w, -.-_.--,---------,___-------------,---,-_,,-----,,,---,_m, TABLE 2-5 INTENTIONALLY LEFT BLANK

?!

i i

l I.

59 i

a

l 1

i TABLE 2-6A ,

V0GTLE ELECTRIC GENERATING PLANT !

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE' REPORT AIR DOSES DUE TO NOBLE GAS RELEASES i'

January 1, 1990 Through. June 30, 1990 UNIT 1 l

Type of Tech Units Quarter % of Quarter % of Radiation Spec Tech Tech Limit 1 Limit 2 Limit ;

Gamma 5.0 mrad 5.00E-04 1.00E-02 1.75E-04 3.50P.-03 ['

Beta 10.0 mrad 1.03E-03 1.03E-02 4.86E-04 4.86E-03 5

?

Cumulative Doses'Per Year'(Year ^to Date)

Gamma 10.0 'arad 6.75E-04 6.75E-03 ;

Be,ta 20.0 mrad 1.52E-03 7.60E-03 .

j t

i 3

l-w

.i

,, ,. . . . . . . . . . _ _ . , . - _ _ _ I

.l 1

i i

TABLE 2-6b ]

V0GTLE ELECTRIC GENERATING PLANT j l

-SEMIANNUAL RADIOACTIVE EFFLUENT = RELEASE REPORT AIR DOSES DUE TO NOBLE GAS RELEASES .

}

January 1. 1990: Through June 30, 1990 ]

UNIT 2 ]

J Type of Tech Units Quarter % of Quarter % of Radiation Spec Tech Tech .

Limit 1 Limit 2 Limit ~ !

Gamma 5.0 mrad 1.03E-04 2.06E-03 5.74E-04 1.15E-02 Beta 10.0 mrad 2.27E-04 2.27E-03. 6.19E-04 6.19E-03 i

e Cumulative ~ Doses Per~ Year'(Year:to'Date)'

Gamma 10.0 'arad '6.77E-04 6.77E-03 #

Peta 20.0 mrad 8.46E-04 4.23E-03

?

f i

I 61 :

1 I

i

l I

TABLE 2-7A V0GTLE ELECTRIC GENERATING PLANT l SEMIANNUAL RADI0 ACTIVE EFFLUENT. RELEASE REPORT ;

. INDIVIDUAL DOSES DUE TO RADI0 IODINE, TRITIUM i AND PARTICULATES IN GASEOUS RELEASES ;

January 1, 1990 Through June 30, 1990 j UNIT 1 s l

i

?

Cumulative Dose'Per~ Quarter' ;

Organ Tech Units Quarter 1 of Quarter 1 of Spec Tech Tech >

Limit 1 Limit 2 Limit . >

Bone 7.5 aren '1.40E-06 1.87E-05 8.68E-08 1.16E-06 Liver 7.5 aren 1.73E-04 2.31E-03 1.56E-04 2.08E-03 ,

T. Body 7.5 mren 1.73E-04 2.31E-03 1.56E-04 2.08E-03 Thyroid 7.5 aren 1.73E-04 2.31E-03 1.56E-04 2.08E-03 Kidney 7.5 aren 1.73E-04 2.31E-03 1.56E 2.08E-03 -

L'ung 7.5 arem 1.74E-04 2.32E-03 1.56E-04 2.08E-03 ;

GI-LLI 7.5 aren 1.73E-04 2.31E 1.56E-04 2.08E-03

~

Cumulative' Dose ^Per' Year' Organ Tech Units Year to Date % of. Tech Spec Limit Spec Limit ,

Bone 15.0 mren 1.49E-06 -

9.93E-06 i Liver 15.0 aren 3.30E-04 2.20E-03 T. Body 15.0 mren 3.30E-04 2.20E-03 -,

Thyroid 15.0 mrea 3.30E-04 2.20E-03 Kidney 15.0 aren 3.30E-04 2.20E-03 Lung 15.0 aren 3.30E-04 2.20E-03 ,

GI-LLI 15.0 aren 3.29E-04 2.19E-03 t-i i

a l

l q

l l

62 L . , _. ._. . _ ._ __ .U

1 l

J TABLE 2-7b )

V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

INDIVIDUAL DOSES.DUE'TO RADI0 IODINE. TRITIUM AND PARTICULATES IN GASEOUS RELEASES January 1, 1990 Through June 30. 1990 UNIT 2'

~

Cumulative' Dose ~Per' Quarter' ,

Organ Tech Units Quarter % of Quarter % of ,

Spec . Tech Tech

Limit 1 Limit = 2 Limit ,

Bone 7.5 ares 0.00E+00 0.00E+00 7.66E-08 1.02E-06 :

Liver 7.5 aren 7.52E-05 1.00E-03 3.49E-05 4.65E-04' ,

T. Body 7.3 aren 7.52E-05 1.00E-03 3.49E-05 4.65E-04 Thyroid' 7.5 aren 7.52E-05' ~1;00E-03 3.50E-05 . 4.67E-04 Kidney 7.3 area 7.32E-05 1.UDE-03 3.49E-05 4.63E Lung 7.5 aren 7.52E-05 1.00E-03' '3.50E-05 4.67E-04 GI-LLI 7.5 aren 7.52E-05 1.00E-03 3.49E-05 4.65E-04 l Cumulative Done Per' Year ,

L Organ Tech Units Year to Date % of Tech Spec Limit l

Spec Limit .

Bone 15.0~ aren 7.66E-08 5.11E-07 Liver 15.0 aren 1.10E-04 7.33E-04 .

T. Body 15.0 area 1.10E-04 7.33E-04

' area' 7.33E-04~

~

i Thyroid 15.0' '1.10E-04'~

Kidney 15.0 aren 1.10E-04 7.33E-04 '

Lung 15.0 aren 1.10E-04 7.33E-04 GI-LLI 15.0 aren 1.10E-04 7.33E-04 P

+

63 1

, e a w -- -,w

i j

I l

l l

TABLE 2-8' i

~ LOWER LIMITS OF DETECTION GASEOUS SAMPLE ANALYSES V0GTLE ELECTRIC GENERATING PLANT JANUARY 1,1990 - JUNE 30,1990 The values in this table represent spriori,, lower limit' of dete. -p (LLD)-..which a re typically _ achieved in laboratory analy.es of r as' * '

radwaste samples.

h RADIONUCLIDE LLD' UNTIS I Kr-87 1.82E-08 uCi/mi Kr-88. 2.53E-08 uCi/mi Xe-133 2.05E-08 uCi/mi Xe-133m 8.63E-08 uCi/mi .

Xe-135 7.12E-08 uci/mi e Xe-138' 1.05E-07 uC1/mi '

I-131 7.93E-15 'uci/ml !

Mn-54 3.94E-14 uC1/n1 :

Fe-59 2.45E-14 uCi/mi i Co-58 1.39E-14 uCi/ml Co-60 1.75E-14 uC1/mi !

Zn-65 2.82E-14 uCi/mi-Mo-99 9.57E-14 uCi/mi Cs-134 1.12E-14 uCi/mi ?

Cs-137 8.71E-15 uC1/mi Ce-141 8.62E-15 uCi/mi-Ce-144 2.773-14 uCi/mi- 't Sr-89 1.00E-13* uCi/n1 Sr-90 1.00E-13* uCi/mi

, 11 - 3 9.00E-08 uC1/mi Gross Alpha 1.00E-13 uCi/nl-

Based on an estimated sample volume of 5.7E+08 cc's. )

5 A

I 54

. I i,

3.0 Solid Wosto I 3.1; Regulatory Limits / Technical Specification The Technical Specifications presented in this section are for Unit 1 and Unit 2 and are stated in part.

3.1.1 Use of Soli 6 Radioactive Waste System f 3.11.3 Radioactive wastes shall be solidified or dewatered in accordance with the PROCESS CONTROL PROGRAM to' meet- -

shipping and transportation requirements during transit, and disposal site requirements when received at the disposal site.- ,

3.1.2 Reporting Requirements 6.8.1.4 The Semiannual Radioactive Effluent Release Reports j shall include a summary of the quantities of ,

radioactive liquid and-gaseous effluents and solid waste released from the unit as outlined in Regulatory ,

Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid: Snd Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants",

Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three additional- >

categories class of solid wastes (as defined by 10-CFR Part 61), type of container (e.g., LSA, Type A, Type B, Large Quantity) and SOLIDIFICATION agent or absorbent (e.g., cement, urea formaldehyde).

3.1.3 Process Control Program (PCP) 4

, 6.12.1 1

The PCP shall be approved by ti.e Cormission prior to implementation.

6.12.2 I l

Licensee - initiated changeu to the PCP.

a. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made.

This submittal shall contain:

1. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental l information; 65 l

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

l i

i

2. A determination that the change did.not reduce the overall.conformance of the solidified waste product-to existing.

criteria for solid wastes, and

3. Documentation of.the fact that'the change ,

has been reviewed'and found acceptable by the PRB. l

b. Shall become effective upor approval by the Generni Manager Nuclear Ple'at.

For this reporting period there was no revision to the'PCP. ,

3.2 Solid Waste Data Regulatory Guide 1.21 Table 3 is found in this report as Table 3-1.

I v

l I

l l

l~

l 1

l 66 1

1 4 - . + -. .- , ~ - -

, n. -

~,T ABLE ' 3-1( ( Page--- 11 of " ' ~

~

, ,-V0GTLE ELECTRICTGENERATING PLANTJ, i JANUARY 1, 1990: THROUGH JUNE 30, 1990 '

1 EFFLUENT AND1 WASTE DISPOSAL SEMIANNUAL-REPORT- i SOLID AND-IRRADIATED FUEL' SHIPMENTS 4

+

Solid Waste'. Shipped Offsite for Burial'or. Disposal-u j (Not Irradiated Fuel')!

-j

1. Type of Waste Unit. -6 month' -Est. Total

. Period ErrorE%:

~

a. Spent resins, filter sludges .mJ 1.322E+01- < l.00E+01-evaporator botton, etc.

'Ci 1.191E+02 . ,

b. Dry compressible' waste, mJ -1.476E+01 q contaminated equipment etc. Ci 7.'079E-02; 4.00E+011

c. Irradiated components, m3 *- -*

c ont r.1 ro d , e t c . Ci *

a

d. Other (describe) oily trash >- m3> * *

, speedi-dry six equipment, C1' *- 'o l

etc., Solidified oil,

'~' ' ~ '~' '~" ~ ' ^

CRD' filters'"'

i

2. Estimate'ofinajor:nuclide' composition'(by'typeTof waste) -

d

]

' Isotope' ' ' Percent ~ ' Curies 7

. ~(

a. Co-58 2.617E+01 3.117E+01:

Co-60 3.053E+01' '3.636E+01- l All'others 4.330E+01 5.157E+01 1

b. ;o-60 4.336E+01 31069E-02 I Fe-55 2.398E+01 < 1.698E-02 All others ,

3.268E+01 2.313E-02

No solid waste during this resort period.'

i l

67 u

.g- .g- - - -

y ,, .

g. ..

mm , p + e- .

, ,;- ,, *1 % T "~ ~ ~ f T.' ~~ S 4

m i

a 1 TABLE 3-1 (PageL2 Eof.2)'

V0GTLE ELECTRIC' GENERATING PLANTE l JANUARYJ1,L1990-THROUGH JUNE'30,:1990- 1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT- J

-SOLID;AND; IRRADIATED FUEL SHIPMENTS b ,

~

E i .

Isotope Percent Curies; q l-l (c . None-shipped.this period

d. Co-60

I

-Zn i- Nb *- *: j Zr-95

4 All others

No' solid waste shipped during this' report period. ,

'3. LSolid Whste Disposition

~

Number'of Shipments Mode'ef" Transportation _ Pestinatf.onL 3 Tractor and Shielded cask-s Chem Nuclear z ,

Barnwell, S '. C . ,

4 ' Tractor -Trailer Scientific Ecology, ,

0akridge,-TN. l

4. Irradiated. Fuel Shipments-(Disposition)

Number'of' Shipments Mode"ofETransportation-. ~~

' Destination !

O ~N/A N/A-Additional Informatica Required by? Tech Specs: ;

! I Shipment Waste Type Shipping Solidification Agent ;

~ Class" No. ~ Class ~Contair.er RWS-90-001 A stable- High-Integrity LSA -N/A

.RWS-90-002 class B LSA- N/A l RWS-90-003 A stable LSA N/A .i RVRS-90-001 A unstable Strong-Tight LSA .N/A p RVRS-90-002 .A uno..ble Strong-Tight: LSA- N/A-RVRS-90-003 A unstable LSA ~N/A RV"S-90-004 A unstable. LSA 1N/A NOTES: Vogtle Electric Generating Plant performed three (3) sh'ipments to Chem Nuclear, Barnwell ,

Ecology Group, Inc. in Oak SCsudfour-(4)1shi$mentstoScientific Ridge,.TN.' Dur ng this reporting period, the waste volume and activity'on this report reflects.

.only that volume of waster and activity which was:proce.asedeand- l disposed of as radioactive wastecatiChem-Nuclear Systems',KInc.,

~Barnwell Waste Management ~ Facility, or by Scientific Ecology i 3

Group, Inc. during this reporting. period.

68

--. - , . ~ -. . . . - . a. . .- - .- . . - . . . . . .

e ,

h

-a 4 '.~ 0 5 Change.sito'the Vogtle Electric Conorating'Picat:ODCM

- 6 . 8.1'.' 4

Technical Specification l6.8.1.4~ requires, fin part,. I that changes;to the Offsite Dose Calculation Manual; (ODCM) be1 reported toftheJCommission.in the~next

Semiannual Effluent Release Report.

'There were no changes to'the-Vogtle Electric.

Generating Plant..0DCM for theLperiod of January 1.-

1990.through; June 30, 1990.-

16.13.2!

Licensee-initiated. changes'to theiODCM- 5!

d

-a. Shall'be submitted-to the Commission inLthe Semitunual-Radioactivc Effluent Release' Report-- l for the period in which the change (s) was!mades 1 effective. The' submittal'shall-contain: 1 i

- 1. !Sufficiently detailedLinformation"to t'otally; j support:the rationaleffor the-change without :i benefitiofisupplementaliinformation.

-Information subaittedishould consist of a- i package of1those-pages of'the ODCMLto be l changed,;with'each page' numbered, dated and containing the revision number together with appropriate analyses or evaluation -i justifying'thc1 change (s); 1

2. A determination t"nat the change;will'not. '

reduce theiaccuracy-or-reliability lof! dose .. !

calculations or'setpointideterminations;:and l

3. Documentationsof the fact that the change = d has_been reviewed-and;found!acceptableLby "

the'PRB..

b. Shall-become effective upon approval by the :i General Marager - Nucienr, Plant. :

3.12.1 The Radiological:Eavironmentai Monitoring' Program::

.shall be conducted 1as~specified^in" Table 3.12-1.

Table Notation 1(1) states in part: I it du recognized;thet,'ut time it:may not be possible or practicable to continue to-obtain samples of the media of choice at:the moat desired-' location-or, time. .In these inat.ances,. suitable alternative media-and locations may be chosen:for'the particular pathway in question and appropriate. substitutions,-if available, will be made=within'30: days:in the i Radiological Environmental' Monitoring ' Program given f n the ODCM.

c 69-

.;n.; .-

' ' ~

,,4?< *' i'

'f,,' . yQ , g4 , *: 4 p' ;. ' ' ' gj' ~,4 ,

a y j. ' j- .

7

,g

'E,. .5 .

1 [igs A . ? h. ~ kl. '44 [ - L: 4

= . .- - ,

Y

> a, Pursuant-to specification 16.13. submit"in-:the'next.

Semiannual Radioactive' Effluent 1 ReleaseEReport' ]

documentation-for'a: change in the.0DCM= including a revised figure (s) and!Tablelfor the.0DCM reflecting- _l the new location (s),1 1fLany, with supporting: '!

~1aformation' identifying the cause ofLthe-l unavailability'ofisamples'for the pathway =and: .

. justifying theLselection"of the new location (s) for !

obtaining samplee, or the.uuavailability-of suitable j new locations.-

3.12.2 states in-part n A LandiUse Censuolshall be conducted.-.....

The Action Statement f or this' requirement ; states > inc j J

- parts:

a. With a Land' Usa Census,iden'tifying'a location (s)l f that yields'a calculated doset or! dose = commitment greater ~thanithe-value; currently being calculated' in specification 4.11.2.3,fpursuantito'

~

specification 6.8.1.4,=identifyothe'new-location (s) in the next'Sealannual Radioactife- -

Effluent Release Report.-

i i

1 r

'E l

. 70~

.i

- , 2I

if s si t

~ 4 '.1 Changee1 1;: . the. _ Radiologic a'll Environneut al ' Moni t oring -

Program For thisLsemiannual' period, there[has1been'no! change; to ' the' Radiological ( Environme nt a1 L Moni to ring : Program.' {

~5. 0 Doses to. Members oflthe Public Inside the Site Boundary' y r

6.8.1.4. states in, parts-l This same report shall_also3 include assessment'of'the radiation-doses.fronx radioactive, liquid and: gaseous; ,

I effluents-to MEMBERS OF THE.PUBLIC.due-to their-activities inside-the-SiteEBoundary _(FigureDS.1-1 Eof: l thefTechnical-Specifications) during.the' report perted. 'All assumptions used in making the se.e time,- [

assesstents, i.e.,! specific. activity', ' e z r'

~

l ts..

and. J ocatioa . shall be. included in - these' ,

LThe locations of' concern within the sity coundary are: 3 j- che Visitors Center'and= Plant Wilson. The activities i l' at the Visitor' Center consists:of the' occasional:

l_

attendance at meetings and/or,short;. visits-for informational. purposes.-The activity at Pla't' u Wilson consists;of. regular employment;- -There will'be'no ,

- radiationtdose at'these locations'due to radioactive liquid effluents.: DelineatedLin Table 5-1 for.each"of these locations are.thervalues'of the basic. data l i assumed in the' dose asses 6uent.due toaradioactive-

~

gaseous effluents'.- Listed in this table are:- The distances and direc tionst f rom a . point' aidway between ,

the center of Unit 1: and ' the = Unit 2 reactors; 'the. l dispersion and deposition factors-for any releases l

from the plant vent-(mixed mode) and'fron the turbine-

" building (ground level); and the estimated maximum; occupancy factor for an individual'and the assumed' age ;

group of this individual.

Listed in; h Not listed in Table 5-1 is the source term. J Tables 2-4a and 2-4b.for the ground level releases and' in Tables 2-3a and'2-3b for the mixed mode releases are theinoble. gases, radioiodines, and'particulates' F

with half lives greater 7than'eight_ days;EtheseDare- 3 '

tabulated by radionuclide and by quarter. The tritium releases in units of curies were-as follows:- n i-1 2 I Quarter 4.23E+01!

i 5.45E+01' Mixed Mode i~ l n >3 i

' 71

,. m ;t 1]- t l

Y =

s .

~

,1 The' maximum doses in--units.of aren-accumulated-by an individual l MEMBER OF THE:PUBLICLdue'to their '

I

. activities inside the site; boundary.during-the,second half.of the year were assessed:to be_as.follows: -

l

} VISITORS ~ CENTER. PLANT WILSON

~ Total Body 7.69E-07 9.44E-05

.(direct radiation from plume)'

q

. 1.08E-06 -1.'42E-04 '

Maximum Organ (Thyroid) --Inha1'ation.and. ground plane , l

}

i r

y I

r t

i 1

l I

l-l 1

f 72 I

w - .vw-.. ,-we-- .,-e w - , - . , - , --e . - , = -er ,,*.---we,.. -*+wer - -- . - - + *

'?

Table 15 JANUARY 1,1990 THROUGH JUNE 30,1990 .

Basic Data' Assumed in' Dose,assessmentsi '

TO MEMBERS OF THE PUBLIC-Item- Visitors conter; -Plant Wilson

' Distance (meters) 447.; 1420 SSctor SE ESE X/Q'(sec/m3) (1)' 5.93e-06 9.45e-07c ;

Dspleted X/Q . (sec/m3) (1) 5.58e-06 -8.34e-07 }

D/Q (m-2)L (1) ' ~

-2.28e-08 4.20e-09L X/Q (sec/m3)

(2) 7.12e-07 1.76e D3pleted X/Q: (s. 0/m3) (2) 6.74e-07 -1.59e-07 HD/Q (m-2) (2) 5.77e ' 2. 07 e-0 9 -- . t occupancy factor 0.00046 (4hr/yr) 0.228 (2000:hr/yr)i s Age group ' Child Adult (1) Ground level release (2) Mixed mode release

VISITORS CENTER PLANT. WILSON ~

Quarter.l' Quarter 2 Total Quarter 1:- Quarter.2 Total; mrem mrem mrem. . mrem, . mrem: mrem'

. Total Body 3.73e-07 3.96e-07 7.69e-07 4.58e-05 4.86e-05: ~9.44e-05 :f r

I. ORGAN DOSE > I

( Bone 4.13E-09 4.27E-10 4.56E-09 7.34E-07. 6.93E-08 8s03E-07 Liver 6.06E-07 4.68E-07 1.07E-06 7.99E 6.15E-05: 1.41E-04 j

C TBody 6.06E-07 4.68E-07 1.07E-06 7.99E 6.15E-05 1.41E-04.

Thyroid 6.08E-07 4.69E-07 1.08E-06 8.00E-05 6.15E-05 1.42E-04 Kidney 6.06E-07 4.68E-07 1.07E-06 7.99E-05 6.15E-05 1.41E-04 i

Lung 6.06E-07 4.68E-07 1.07E-00 -8.00E-05 '6.15E-05 1.42E-04 GI 6.06E-07 4.68E-07. 1.?' -06 7.99E-05' G.15E-05 1.41E-04

[

73 L

?

__ _ ~_. ._- _ _ _ _ _ . _ - _ _ _ _ _ _ . _ - . - -____

1 F .- )

6.0' MajorLChanges.to1 Liquid,, Gaseous,or Solid Radwaste- 1

: Treatment Systems. ,

~ '

1 '

, 4.'8.1.4Latates in part' The Semiannual Radioactive-Effluent Release' Report. j d

shall-include . . ..any-major chang'e~to liquid; Gaseous.cor Solid Radwaste Treatment Systems pursuantL j to Specification.6.14.

6.14.1- ,

il L . . .

a f_ Licensee-initiated' major: changes to theJRadwastel ,

i

" Treatment Systems.(liquid, gaseous, andisolid):; ;

-1 ..

a. Shall be reported:to the' Commission:inithe-Semiannual Radiactive Effluent Release Report-forL l

.the-period in which~the evaluation was;' reviewed L by thetPRB. 'TheEdiscussion of.each; change shall' .

l contains, l

! O i 1. ALaummary of the. evaluation,that led-toNthe .

I

' determination- thati the: change- could~- be tmade"in; 1 accordance with10 CFR150.59;.

2. Sufficient detailed informarion to totally support the reason for the change without benefit of-additional or supplementalEinformation;

3. A. detailed. description of equipment,1 components, and processes-involved-and the interfaces with l other- plant 'syste.as ;- j i

4.- An evaluation'ofz the change,=which.showsLthe 9

predicted releases oferadioactive. materials in 'l l

liquid and gaseous ~ effluents and/or; quantity'of sclid waste that differ from those1previously

]

j predicted in the. License ApplicationLand amendments 1thereto;L 1

5. An evaluation of the. change,1which shows the j l expected maximum exposures'to:a' MEMBER'0F_THE ;

PUBLIC'in the' UNRESTRICTED 1AREAJand!to.the- )

general. population that-differ from those ->

I previously estimated in the License 0 application

~

j~

and amendments-thereto; .

6. A comparison of the predicted releases of.

e radioactive materials,.in-liquid and gaseous ;l 4

effluents and'in solid waste, to the actual ^

ll

releases for the period prior to when the 1 change- l 7

is to be made; 3 I

t S J i t!

- 74 l

4 l1 ps . ; : a

( -.

7. An.estimateLof the~ exposure to plant operating-

personnel as'a result ofltheEchangel and

8. Documentation of the fact;that tho' change was reviewed and found. acceptable;by~the PRB.

b. Shall.become' effective upon apr ~ val by-tho' ]

General Manager. Nuclear Plant.:

'ThereLhave:been no major; changes tolthe. Liquid,. '

1 Gaseous or Solid Radweste Treatment Systems:

l during'this report p e ri o d .' j 7.0 Meteorological < Data j

-l 6.8.1.4Lstates in parts:

{

The Semiannual Radioactive 4 Effluent Release' Report to

(

' be submitted within'60' days.aftarfJanuary.1 of)each yearJehall include an annua 11 summary 1of hourly. ,

meteorological' data; collected-over the, previous. year. .j This1 annual. summary may.be either:in tha. form:of an- i hour-by-hour listing on magnetic: tape-of wind speed.. H windLdirection, atmospheric stability, and. l precipitation (if measured), or in theLform of' joint frequencyidistributions of windespeed..: wind direction, j and atmospheric: stability.- i i

I

.]

' ,i t s

75 i

'1 I

l

t 7-a, t

i i

8.0' Inoperable Liquid"or' Gaseous Effluent Mhnitoring In s t rume nt ati on 6.8 1.4 statesJin-part-thatt' ,

i The Semiannual Radioactive Effluent Release:R'eports-shall also include-the.following _ an explanation as to why the inoperability of liquidior gaseous: effluent monitoring instrumentation was not corrected within the time;specified in Specifications 13 3.3.9 or- ;

3.3'3.10

. z respectively-.

3.3.3.9 states in part:

The radioactive liquid effluent monitoring ~

= instrumentation: channels shown int Table 3.3-9'shal1:be -I OPERABLE . . .-

Action b.-states:-

q With'less than the minimum ~ number lof radioactive i liquid effluent monitoring: instrumentation channels" f OPERABLE,: take the' ACTION shown in Table 3.3-9. l Restore-the inoperable1 instrumentation;to OPERABLE i status within 30 days-and, if unsuccessful,. explain in the next Semiannual' Radioactive: Effluent Release,

~

Report. pursuant-to Specification 6.8.1.4.whyithis ;

inoperability was not corrected in-altimely manner.

3.3.3.10 states in part:- !

i The radioactive gaseous' effluent monitoring j inst rumentation channels' showni in 0 Table 3.3-10 shall- !

be OPERABLE . . .

Action b. s t a t e s' : -

With-less-than the minimum number-oftradioactive gaseous effluent monitoring

instrumentation channels ;

OPERABLE, takenthe ACTION shown in Table 13.3-10.

Restore the inoperable instrumentation ~to OPERABLE status within 30 days'and,Jif unsuccessful,. explain-in l the next Semiannual Radioactive Effluent Release Report pursuant to specificationz 6.8.1.4'why:this<

inoperability was not corrected in a. timely manner.

i 76 4 m

.i

. a

Inoperable:,TechLSpec monitors are tracked on5 Limiting Condition of, Operation (LCO)~ Forms. .;The' operators. ,

declare equipment. operable andLinoperable and monitors: i are considered-inoperable if: there:are open.LCO's for.

that monitor.. l 8 .1.1 - The LCO'slinitiated do not'have"to beJreported for. ,

'this reportlperiodisince~the:LCO's initiated were closed!before 30; day period. - .

9. 0 - Tanks Exceeding 1 Curie Content-Limits 6.8.1.4 states'-inopart:

The Semiannual 1 Radioactive EffluentLRelease Reports i

'shal1~also include the~following, " and' description off the events leading.to liquid holdup tanks or. gas- 1 storage-tanks exceeding the-limits'of specification 3~'11.1.4 or:3.11.2.6,crespectively ".

3.'11.1.4.

The-quantity of: radioactive material. contained in each -i outside temporary tank shall'be limited'to less than

or equal to.10 Curies, excludingrtritium;and-dissolved or entrained' noble gases. ,

Action A statest With the. quantity of~ radioactive: material.in any?of; the outside temporary. tanks-exceeding the:above limit, '

2 immediately suspend all additionsLofEradioactive material to the tank,c within 481 hours0.00557 days 0.134 hours 7.953042e-4 weeks 1.830205e-4 months ,~ reduce-the tank >

contents to within the limit, Land-describe the events. i leading to this condition--in the next; Semiannual Radiocctive Effluent Release Report,' pursuant ^to '

i specification 6.8.1.4. ,

3.11.2.6 The quantity of radioactivity contained-in each gas dec ay; tank: shall' be limited to -less than: or0 equal:to 2h5 curies of noble gases-(consideredias Xe-J33 equivalent)'.

Action A statest With th'e. quantity of radioactive material inIany gas

' decay tank. exceeding the above: limit, immediately( l suspend n11' additions of radioactive material to'the tank, wit'hin 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce"the tank contents-to. i withinLthe-limit, and describe the events leadingito j j'

l this. condition in the next Semiannual Radioactive. !

L Effluent' Release Report, pursuant to specification

l- 6.8.1.4. ,

L i m i 77 L

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

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

f 6

t,

, .l There were.no'outside' temporary liquid tJaks for'- d radioactive.11gulds:during'this report.ag-period,' D e- '

u.

f radioactive material. contained:in-each vastefgas-decay ~

tank did not' exceed '2E5 curies =.of noble'. gases.

(con'aidered as Xe-133. equivalent).

1 1

.l

, u 1

l l

.I

' f.

~h 1412A 1 i

!{

1 I \

-j

.f i

i. . .,

-I L .

K t

, 78 L

')

l.

I t

l' s

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

ELV-02033, Semiannual Radioactive Effluent Release Rept for Jan-June 1990

Text

SUMMARY

SUMMARY

Navigation menu

ELV-02033, Semiannual Radioactive Effluent Release Rept for Jan-June 1990

Text

SUMMARY

SUMMARY

Navigation menu

Search