ML20028G830

From kanterella
Jump to navigation Jump to search
Semiannual Radioactive Effluent Release Rept for 900430- 0630.
ML20028G830
Person / Time
Site: Comanche Peak Luminant icon.png
Issue date: 06/30/1990
From: Kay D, Manfield C, Robert Prince
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20028G829 List:
References
NUDOCS 9009050094
Download: ML20028G830 (17)
v • d • e


Text

. . .

t i f '.. f .

Vj.. . - Enclosurejo TXX-90299:- ,

g;m ,

l .

> . 'u '

i Xi

'i

.r:

f

.i

' Comanche Peak Steam Electric Station Unit l'.

Semiannual Radioactive Effluent Release Report April 3, 1990 - June 30, 1990 i: .

-1 1

1 1

1 l

l 1

' Prepared-By: - -

Date: O!/6/90 C.L. Mansfield, Staff Health Physicist Reviewed By: -

  • Date: 8//6 /'?D D.C. Kay, Colporate Health Physics

-- O Approved By: [_ omb Sh et ~/. /'b_m o Date: 8!/6 /90

-R.J. Pfinde', Radiation Protection Manager 1

p?g9050094 900829 pg ADOCK 0500o443 i PilC

b- ,

s P

' 5 m ,

TABLE OF: CONTENTS g ACRONYMS AND ABBREVIATIONS

1.0 INTRODUCTION

r

' 2.0 SUPPLEMENTAL INFORMATION ,

2.1 Regulatory Limits t

2.2 Maximum Permissible Concentrations 2.3 Average Energy ,

2.4 Measurements And Approximations of Total Radioactivity 1

2.5 Batch Releases' t 2.6 Abnormal Releases-  ;

. 3.0 GASEOUS EFFLUENTS l' 4.0 LIQUID EFFLUENTS

~5.0 ~ SOLID WASTES l> 6.0 REIATED INFORMATION L

i 6.1 Operability of Liquid and Gaseous Monitoring Instrumentation L 6.2 Changes to the Process Control Program '

I 6.3 Changes to the Offsite Dose Calculation Manual 6.4 New Locations for Dose Calculations or Environmental Monitoring 6.5 Liquid Holdup and Gas Storage Tanks 6.6 Tritium Discharged Due to Turbine Generator Primary Water Cooling System Leakage.

6.7 Violations of the Radioactive Effluent Sampling and Analysis Program 6.8 . Batch Releases to the Evaporation Pond i

i i

TABLE OF CONTENTS 7.0 TABLES l

7.1- Batch Liquid and Gaseous Release Summary 7.2 Abnormal Batch Liquid and Gaseous Release Summary 7.3 Gaseous Effluents Summation of All Releases 7.4 ' Gaseous Effluents--Ground Level Releases 7.5 Liquid Effluents Sumnation of-All Releases 7.6 Liquid Effluents 8.0 ATTACHMENTS 8.1 ODCM for CPSES Unit 1, current as of June 30, 1990 11 4

ACRONYMS AND ABBREVIATIONS CFR Code of Federal Regulations CPSES Co:nanche Peak Steam Electric Station IRMT Laundry Holdup and Monitor Tanks MPC Maximum Permissible Concentration ODCM Offsite Dose Calculation Manual PCP Process Control Program REC Radiological Effluent Control TGPWCS Turbine Generator Primary Water Cooling System WHUT Wastewater Holdup Tanks WM1 Waste Monitor Tanks iii

l l CPSESiUnit 1- ..

~

Semiannual-Radioactive Effluent Release Report April;3,' 1990 -' June 30, 1990 1.0~ INTRODUCTION LThis Semiannual Radioactive Effluent Release Report _ for Comanche Peak Steam Electric Station Unit 1, is submitted as required by Technical Specification 6.9.1.4 and Offsite Dose Calculation Manual (00CM) Administrative Control <

6.9.1.4 for the period- April 3,1990 (the date of' initial criticality- for Unit .

1) through June 30, 1990.

The information contained in this report includes:

(1) A summary of the quantities of radioactive liquid and gaseous effluents released from Unit I during the reporting period in the= format outlined in-

- Appendix B.of Regulatory Guide 1.21, Revision 1. June 1974.

(2) A summary of solid waste shipped from Unit 1 in the format shown in Appendix B of Regulatory 1.21, Revision 1. June, 1974, supplemented with-three additional categories: class of waste (per 10CFR61). type of container (LSA, Type A, Type B Large Quantit3 ), and solidification agent-or absorbent.

(3) A list and description of unplanned releases of radioactive material from-the site to unrestricted areas.

(4) A listing of new locations for dose calculations and/or environmental monitoring that might be identified by.the Land Use Census.

(5) An explanation should the liquid or gaseous effluent monitoring instrumentation become inoperable and not be corrected within 30 days.

(6) A description of the events should the concentration of radioactive materials in the liquid holdup-tanks or gas' storage tanks exceed Technical Specification limits.

(7) Changes to the ODCM in the form of a complete, legible copy of the entire-ODCH.

(8) The total amount of tritium discharged due to Turbine Generator. Primary Water Cooling System (TGPWCS) leakage as required by ODCM Supplemental Guidance Number 3.

-As will be seen, the discharge of radioactive materials did not exceed the limits specified in the ODCH.

2.0 SUPPLEMENTAL INFORMATION 2.1 Reaulatory Limits The ODCM Radiological Effluent Control limits applicable to the release of radioac ive material in liquid and gaseous effluents are described in the following sections.

1

ny y<r -

tc

~ ~. - ^

3;; ;b -

(ChSESUnit:1 . . ,

Sealannual Radioactive Effluent Release' Report April 3,01990.- June 30, 1990 2 .1.1: Fission and Activation Cases (Noble Cases) f of The dose rate due to radioactive materials' released in gaseous' ,

effluents'from the site to areas at and beyond thefsite boundary-q' shall be limited to less than or equal'to 500 arems/yr-to the i

whole body and less than or equal to 3000 mrems/yr to the skin. ,

The air dose due to noble gases-released in gaseous effluents,-

from each unit, to areas at and beyond the site boundary shall be' ~

k limited to the following:

  • ti
a. During any calendar quarter: Less than or equal to'5:wrads for gamma -radiation and less than or-equal to 10 mrads 'for' l beta radiation, and t

. b. During_any calendar year: Less than or equal to 10 mrads- ,  !

for gamma radiation and less than or-equal to 20 mrads for-beta.radiatten.

2.1.2 Iodine-131. Iodine 133. Tritium and Radioactive' Material in W Particulate Form.

The dose rate due to Iodine-131, Iodine-133,. tritium and all ,

- radionuclides-in particulate form-with half lives-greater than 8.

days, released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to less than or equal- -l to 1500 mrem /yr to any organ. .;

The dose to a member of the public from Iodine-131, Iodine-13', 3 tricium and all radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents released, from each unit, to areas at and beyond the site boundary, shall be limited

- to the following:

' a) During any calendar quarter: Less than or equal to 7.5 arems to any organ and,  !

l b) During any calendar year: Less than or equal to 15 mrems to any organ.

2.1.3 Liould Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations 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-04 pCi/ml total activity.

I The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released, from each l unit, to unrestricted areas shall be limited:

L 2 w --- = - -4 _ _ _ - - _ _ _ _ _ _ _ - - _ . _ - _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ - - . _ _ _ __ -_

[CPSESUnit'11 Semiannual Radioactive' Effluent Release Report- -

- April 3, 1990 - June 30,-1990 a) During any calendar quarter to less than or equal:to 1.5" arems-to the whole body and to less than 5 areas to any

~

organ, and b) During any calendar year to less than or equalito 3 mrems to the whole body and to less than'or equal,to 10 mrems to-any organ.

2.1.4 Evaooration Pond The quantity of radioactive material contained in the-evaporation pond shall be limited by the following expression:

264/V

  • I A J/CJ < 1.0 J

vhere:

AJ - pond inventory limit for a single radionuclide j (Curies).

CJ - 10CFR20, Appendix B, Table II Column 2, concentration for a single radionuclide j (pci/cc),

V - design volume of liquid and slurry in the pond (gallons), and 246 - conversion unit (pC1/Ci per al/ gal) 2.1.5 Total Dose The annual (calendar year) dose or dose commitment to any member of the public due to releases of radioactivity and to radiation-from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

2.2 Maximum Permissible Concentrations 2.2.1 Gaseous Effluents For gaseous effluents, maximum permissible concentration (MPC) values are not directly used in release rate calculations-since the applicable limits are expressed in terms of dose rate lat the site boundary, 2.2.2 Liauld Effluents The values specified in 10CFR Part 20, Appendix B, Table II, Column 2 are used as the maximum permissible concentrations of liquid radioactive effluents released to unrestricted areas. A value of 2.0E-04 pCi/ml is used as the MPC for dissolved and entrained noble gases in liquid effluents.

3

CPSES Unit'11 '

Semiannual Radioactive = Effluent Release Report April 3, 1990 - June 30,' 1990 2.3 Average ^ Energy j This section-is not applicable to the Radiological Effluent. Controls of Part I of the 0DCM for Comanche Peak, Unit 1.

s 2.4 Measurements and Anoroximations of Total Radioactivity "

Measurements total radioactivity in liquid and gaseous radioactive effluents were accomplished in accordance with the sampling and analysis' requirements of Tables 4.11-1 and 4.11-2, respectively, of the CPSES ,

ODCM.

  • 2.4.1 Liould Radioactive Effluents l Each batch release was sampled and analyzed for gamma emitting <

radionuclides using gamma spectroscopy, prior to release.

Composite samples were analyzed monthly and quarterly for-the Waste Monitor Tanks, Laundry Holdup and Monitor Tanks and Wastewater Holdup Tanks. Composite samples were analyzed monthly for tritium and gross alpha radioactivity in the on site laboratory using liquid scintillation and gas flow proportional counting techniques, respecti.ely. Composite. samples were '7 analyzed quarterly for Sr-89, Sr 90, and Fe 55 by a contract laboratory (Teledyne Isotopes). The results of the analyses from the previous month or quarter were used to estimate the quantities of these radionuclides in liquid effluents during the current month or quarter. The total radioactivity in liquid effluent releases was-determined from the measured and estimated

  • concentrations of each radionuclide present and the total volume 1 of the effluent released during periods of discharge. ,

For releases of tritium via the TGPWCS, samples were analyzed for tritium, using liquid scintillation counting techniques, prior to  !

system drainage. The concentration of tritium in the effluent e-d r the volume of coolant drained were used to determine the amount of

, tritium released. Leakage of. tritium from the system was also -

tracked by comparing system tritium inventory at the beginning of the month to end of the month.

For batch releases of powdex resin to the Evaporation Pond, samples were analyzed for Samma emmitting radionuclides, using Eamma spectroscopy techniques, prior to release. Composite samples were analyzed quarterly, for Sr-89 and Sr-90, by an offsite laboratory (Teledyne Isotopes) .

2.4.2 Caseous Radioactive Effluents Each gaseous batch release was sampled and analyzed for radioactivity prior to release. For releases from Waste Gas Storage Tanks, noble gas grab samples were analyzed for gamma emitting radionuclides using gamma spectroscopy. For releases 4

V CPSES Unit 1-Semiannual Radioactive Effluent' Release Report April 3,1 1990 . June 30,1990 y '

i c from the Containment Building,-samples were taken using' charcoal.

and particulate filters,.in addition to noble gas and tritium grab  ;

samples,,and analyzed for, gamma emitting radionuclides prior.to i each release with the exception of Containment vents made as a' precursor to a Containment purge. .. In these cases, samples

, ' collected and analyzed as a prerequisite to the vent.were used'to estimate total radioactivity released during the subsequent purge. j The results of the analyses and the total. volume of effluent'  ;

.. released were used to determine the total amount of radioactivity released in the batch mode.

For continuous effluent release pathways, noble gas-and tritium. i grab samples were collected and analyzed weekly forLgamma emitting-radionuclides by gamma spectroscopy and~1iquid scintillation t counting techniques, respectively.- Continuous release pathways ,

were continuously sampled using radiciodine adsorbers and 4 particulate filters. The filters were analyzed weekly for I-131 '

and gamma emitting radionuclides using gamma spectroscopy.

Results of the noble-gas-and tritium grab samples, radioiodine adsorber.and particulate filter analyses from.the curront week and the average effluent flow rate for the previous week-were used to' determine the total amount of radioactivity released in the continuous mode. Monthly composites-of particulate falters were.

analyzed for gross alpha activity, in.the on-site laboratory using the gas flow proportional counting technique. Quarterly composites of particulate filters were analyzed for Sr 89 and Sr- -'

90 by an offsite laboratory (Teledyne Isotopes).

2.5 Batch Releases A summary of information for gaseous.and liquid batch releases is included in Table 7.1.

2.6 Abnormal Releases '

Abnormal releases are defined as unplanned or' uncontrolled releases of radioactive material from the site boundary. There were two unplanned or uncontrolled liquid effluent releases made during the period covered by this report, however, no radioactivity was present in either release. i A summary of information for gaseous and liquid abnormal releases is included in Table 7.2. .

3.0 GASEOUS EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables 7.3 and 7.4. All releases of radioactive material in gaseous form are considered to be ground level releases.

L 5

3: - .

- 1

.) N".ES UM.$ 1 23estapr. cal. Radioactive Effluent Release' Report April'3,L1990 -~ June 30,fl990-4.0 -~ Q*)UID EFFLUENTS 1

Tbs quantities of radioactive material released in liquid effluents are '

summarized in Tables 7.5 and 7.6.

5.0 SOLID WASTES There were no. shipments of_ solid radioactive materials for disposal made during the period covered by this report.

6.0 REIATED INFORMATION-6.1 Ooerability of Liauld and Gaseous Monitorine Instrumentation ODCM Radiological Effluent Controls 3.3.3.4 and 3.3.3.5: require an

- explanation of why designated inoperable liquid and gaseous monitoring instrumentation was not restored to operable status.within thirty days.

During the reporting period covered by this report, there were no- '

instances where this instrumentation was inoperable for more than thirty days.

6.2 Channes to the' Process Control Prorram ,

There were no changes.to the Process Control Program for the period covered by this report.

6.3 Channes to the Offsite Dose Calculation Manual During the period covered by this report, there was one change to the-ODCM, effective on April 10, 1990. The change involved Table 4.11-1,

" Radioactive Liquid Waste Sampling and Analysis Program", the associated '

table notations and Figure 1.1, " Liquid Effluent Discharge Pathways". In accordance with ODCH Administrative control 6.14.c, this change-is submitted in the form of a complete copy of the entire ODCM, current as ,

of June 30, 1990. '!

6.4 New Locations for Dose Calculations or Environmental Monitoring ODCM Administrative Control 6.9.1.4 requires any new locations for dose calculations or environmental monitoring, identified by the Land Use Census, to be included in the Semiannual Radioactive Effluent Release Report. The 1989 Land Use Census, included in the 1989 Annt'l Radiological Environmental Operating Report, did not identify any such locations.

6.5 Liould Holduo and Gas Storare Tanks ODCM Administrative Control 6.9.1.4 requires a description of the events leading t> liquid holdup or gas storage tanks exceeding the Technical Specification limits. Technical Specification 3.11.1 limits the quantity of radioactive material contained in each unprotected outdoor tank to l 1ess than or equal to ten curies, excluding tritium and dissolved or 6

IU

-CPSES Unit-1 Semiannual Radioactive Effluent Release Report April 3,1990 : June' 30,1990~

entrained noble gases. ' Technical Specification 3.11.2.2.11mits'the.

quantity of radioactive material contained in each' gas storage tank'to less than or equal to 200,000 Curies of noble gases (considered as Xe 133 equivalent) . - These limits were not exceeded during the period covered by;

.this report.

6.6 Tritium Discharred Due to Turbine Generator Primary Water Cooline System Leakage.

ODCM Supplemental Guidance Number 3 requires-the total amount of tritium discharged due to TCPWCS leakage to be reported in the Semiannual Radioactive Effluent Release Report. This activity is determined as described in section 2.4.1. The total amount of tritium discharged due to TCPWCS leakage was 2.2E05 pC1. This is in addition to the values reported in Tables 7.3 through 7.6.

6.7 Violations of the Radioactive Effluent Samtline and Analysis Program This section provides a listing of violations of the Radioactive Effluent Sampling and Analysis Program as defined by ODCM Tables 4.11-1 and 4.11

2. Documentation concerning evaluations of these events and corrective actions, if necessary, is maintained on site.

6.7,1 ODCM Table 4.11-2, " Radioactive Gaseous Waste Sampling and Analysis Program," requires sampling of the plant vent at least once per twenty four hours for at least seven days following each.

shutdown, startup or thermal. power change exceeding fifteen-percent of rated thetual power within a one hour period. This juirement does not apply if: (1) analysis shows that the Dose-Equivalent I-131 concentration in the reactor coolant has not-increased more thi- -actor of three; and (2) the noble gas monitor shows thr affluent activity has not increased more than a factor of three. On May 20, 1990, during testing of the Steam Dump System, Unit 1 experienced power changes, greater than fifteen percent cf rated thermal power, seven times. Contrary to the sampling requirement of Table 4.11-2, plant vent samples were not taken within twenty four hours of any of these power changes.

On May 25, 1990, Unit 1 experienced a reactor startup. Contrary to the campling requirements of ODCM Table 4.11-2, the plant vent was not sampled until May 28, 1990.

6.7.2 ODCM Table 4.11-2, " Radioactive Gaseous Waste Sampling and Analysis Program," requires tritiuc. samples of the plant vent etack effluent, every thirty one days. Contrary to this requirement, the tritium sample for April 1990 was not taken althin the prescribed time limit, including the twenty five percent extension allowed by ODCM Curveillance Requirement 4.0.2.

7

i

q. I CPSES Unit 1 Semiannual Radioactive/ 'ifluent Reliase Report April 3 '1990 - June 30, 1990 l

6.7.3 ODCM Table 4.11 1, ' Radioactive liquid Waste Sampling and Analysis Program," reqettes composite samples from the Waste Water Holdup Tanks be acquired and analyzed for tr. tium on a monthly basis.  ;

Contrary to this requirement, a sample taken from Waste Water 1 Holdup Tank I was discarded prior to performance of the composite ,

tritium analysis.

l 6.8 Batch Releases to the Evaporation Pond A total of 2289 ft3 of resin was transferred to cna Evaporation Pond in '

seventeen batch releases during the period covered by this report. The results of the sample analyses indicate no radioactive material was j transferred to the Evaporation Pond. 'l 7.0 TABLES 7.1 Batch Liquid and Caseous Release Summary 7.2 Abnormal Batch Liquid And Caseous Release Summary 7.3 Gaseous Effluents Summatica of All Releases 7.4 Caseous Effluents Ground Level Releases '

7.5 Liquid Effluents Summation of All Releases 7.6 Liquid Effluents 8.3 ATTACHMENTS ,

8.1 ODCM for CPSES Unit 1, current as of June 30, 1990.

1 i

8

+

Tcblo 7.1 [

RATCH LIOUID AND CASE 00S PELEASI'

SUMMARY

Quarter 1 Quarter 2 A. Liquid Releases All Sources Number Of Batch Releases 0.00E+00 1.41E+02 Total Time Period For Batch Releases (Min) 0.00E+00 9.15E+03 Maximum Time Period For A Batch Release (Min) 0.00E+00 2.31E+02 Average Time Period For A Patch Release (Min) 0.008&OO 6.50E+01 i Minimum Time Period For A Batch Release (Min) 0.00E+0c 3.10E+01 Average Stream Flow During Periods Of Release (Ft3 /s) 0.00E+00 1.11E+03 i Caseous Releases All Sources B.

Number Of Batch Releases 0.00E+00 1.70E+01 Total Time Period For Batch Releases (Min) 0.00E+00 4.84E+03 Maximum Time Period For A Batch Release (Min) 0.00E+00 6.26E+02 Average Time Period For A Batch Release (Min) 0.00E+00- 2.85E+02 Minimum Time Period For L Batch Release (Min) 0.00E+00 9.00E+01 Table 7.2 ABNORMAL SATCH LIOUID AND CASEOUS RELEASE

SUMMARY

A. Liquids j

Number Of Releases 0.00E+00 2.09E+00 Total Accivity Released 0.00E+00 0.00E+00 B. Cases Number Cf Releases 0.00E+00 0.00E+00 Total Activity Released 0.00E+00 0.00E+00 1

V a

l l

l

Tchla 7.3 CASEOUS EFFLUENTS. SUMMATION OF At1. RELEASES i

Units euerter Guerter' Est. fotel 1 2 trror, 1 A. Fission and Activatf m Cases

1. YetaL reieene CI 0.00t+00 1.53t+02 2.12t+01l
2. Aversee release rete for period scl/6ec 0.00t+00 1.95t+01
3. Percent of ODCM REC llelt (fotel Body  % 0.00t+00 4.55t 03
4. Percent of ODCM REC Llelt (Skin) X 0.00t+00 2.25E 03 t

B. Iodines

1. Total lodine 131 Cl 0.00E+00 0.00t+00 kote 1 l
2. Average release rete for period pCl/sec 0.00t+00 0.00E+00 ,
3. Percent of ODCM Ric llelt (orpen) X 0.00E+00 0.00t+00 C. Particulates
1. Particulates with half lives > 8 Days Cl 0.00E+00 3.86t 05 3.13t+01l
2. Average release rete for period pCl/sec 0.00t+00 4.91t 06

~

3. Percent of ODCM REC llait (Orpen) 1 0.00t+00 0.00t+00 4$Grosealpheredfonctivity Cl 0.00E+00 0.00E+00 D. Tritium
1. Total release Cl 0.00E+00 9.44t 04 1.14E+01
2. Aversee release rate for period #C1/sec 0.00t+00 1.07E 04
3. Percent of ODCM ktc tielt (0reen) X 0.00E+00 3.00E 07 Note is to lodine activity le reported for pessous ef thsects, therefore errort for these veLues are not reported.

i l

l l

l l-

Tcblo 7,4 CASEOUS EFFLUENTS -GROUND LEVEL RELEASES Contfruous stede totch leade Nuctides teleased unt.e Guerter Guerter Duarter Duarter 1 2 1 2

1. Fission and Activation Cases Ar 41 Cl 0.00E+00 0.00t+00 0.00E+00 6.85t 03 Kr 854 Cl 0.00E+00 0.00t+00 0.00E+00 4.20t 06 ke*133M Cl 0.00E+00 0 00t+00 0.00E+00 4.37t 02 ke 133 Cl 0.00E+00 1.50f+02 0.00E+00 3.78t+00 xe 135 Cl 0.00t+00 0.00t+00 0.00E+00 2.44t 02 Total for period Cl 0.00t+00 1.50t+02 0.00E+00 3.66t+00  ?
2. Iodines i 1 131 Cl 0.00t+00 0.00E+00 0.00t+00 0.00t+00 1 133 Cl 0.00E+00 0.00E+00 0.00t+00 0.00t+00 1*135 CI 0.00t+00 0.00t+00 0.0M ,00 0.00E+00 total for period Cl 0.00t+00 0.00t+00 0.00t+Lt 0.00t+00
3. Particulates H3 Cl 0.00E+00 0.00t+00 0.00C+00 8.44t 04 1 Br 82 Cl 0.00E+00 0.00t+00 0.00E+00 3.86E 05 s

totet for period Cl 0.00t+00 0.00t+00 0.00E*00 8.82E 04

!1! -

T:blo 7.5 LIOUID EFFLUEFTS- StMMATION OF All RELEASES Units , leuerter'euerter ist. Total 1 2 trror, 1 A. Fission and Activation Products -

1. total release (not including tritium, Cl 0.00t+00 6.01t 04 1.60t+01 poses, alpha)
2. Averrge diluted conrentration Wring period scl/mL 0.00t+00 2.42E 12
3. Perrent of QDCet ett limit X 0.00t+00 1.17t 04 B. Tritium
1. Total reteese Cl 0.00t+00 6.itt 02 1.02t+01
2. Average diluted concentration kring period s 1/ ' O.00t+00 2.49t 10
3. Percent of ODCM ktC limit 1 0.00t+40 8.31t 06 C. Dissolved and Entrained Cases
1. Total rolesee Cl 0.00t+00 1.59t 02 1.14t+01
2. Average diluted concentration kring period scl/ml 0.00t+0C 6.42t 11
3. Percent of GDCM Rtc limit 1 0.00E+00 3.216 05 D. Cross Alpha Radioactivity
1. fotst release Cl 0.00t+00 0.00t+00 Note 1 E. Volume of weste reteosed (prior to dilution) Liters 0.00E+00 2.52E4 06 2.20t+00 F. Volune dilution of water used &rbs period Litere 0.00t+00 2.48t+11 1.00E+01 Note in No groes alphe activity la reported for ligsid effluents, therefore errors for these values are not reported, l

1 l

t l

l

[

l l

.  ?

i' T.blo 7.6 LICUID EFFLUENTS Contfruous Mode Betc% norr Nuclides Relected Units Guerter Guerter Guerter Duarter 1 2 1 2 N3 Cl 0.00t +00 0.00t+00 0.00t+00 6.18E 02 ha 24 Cl 0.00t +00 0.00t+00 0.00t+00 2.52t 05 Cr 51 Cl 0.00t+00 0.00t+00 0.00t+00 2.44t 05 Mn 54 Cl 0.00t+00 0.00E+00 0.00t+00 4.67t 05 Co 58 Cl 0.00t+00 0.00t +00 0.00t+00 3.98E 04 Co 60 Cl 0.00t+00 0.00t+00 0.00t+00 7.39t 06 2r 95 Cl 0.00t+00 0.00t+00 0.00t+00 4.81E 06 kb 95 Cl 0.00t+00 0.00t+00 0.00t+00 4.24t 06 No 99 Cl 0.00t+00 0.00t+00 0.00t+00 3.05t 07 Tc 99M Cl 0.00t+00 0.00E+00 0.00t+00 6.70E 07 1 131 Cl 0.00t+00 0.00t+00 0.00t+00 8.40E 05 1 133 CI 0.00E+00 0.00t+00 0.00t+00 3.58E 06 to 140 Cl 0.00E+00 0.00t+00 0.00t+00 1.06E 06 Total for period Cl 0.00t+00 0.00t+00 0.00E+00 6.24t 02 tr 85M Cl 0.00t+00 0.00t+00 0.00t+00 4.3t' 06 Me-133M Cl 0.00E+00 0.00t+00 0.00t+00 1.07t 04 Xe 133 Cl 0.00t+00 0.00t+00 0.00t+00 1.56E 02 Xe 135 Cl 0.00t+00 0.00t+00 0.00t+00 2.00E 04 Total for perlod Cl 0.00t+00 0.00t+00 0.00t+00 1.59t 02 l

l l

i

Retrieved from "https://kanterella.com/w/index.php?title=ML20028G830&oldid=2492270"