ML20114D070

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Semi-Annual Radioactive Effluent Release Rept for 920101 Through 920630
ML20114D070
Person / Time
Site: River Bend Entergy icon.png
Issue date: 06/30/1992
From: Cargill E, Fantacci C
GULF STATES UTILITIES CO.
To:
Shared Package
ML20114D066 List:
References
NUDOCS 9209040123
Download: ML20114D070 (30)
v • d • e


Text

s a RIVER BEND STATION, UNIT 1 SEMIA!MUAL RADIOACTIVE EFFLUENT RELEASE REPORT REPORT PERIOD: January 1, 1992 through June 30, 1992 Reviewed By Ud #*ha 6!7//77-C. 4'.Fa'n'tacci, Radiological Su15 ervisor

/

Approved By b k / b 2/

y r i-E. M. Cargill, Director - Radiological Programs a

9209040123 920031 gDR ADOCK0500g8

I l

e e 1 4

1 l

l TABLE OF CONTENTS EAGE I

4 I. INTRODUCTION 1 II. SUPPL : MENTAL INFORMATION l A. REGULATORY LIMITS 2 B. MAXIMUM PERMISSIBLE CONCENTRATIONS 6 C. AVERAGE ENERGY 6 D. MEASUREMENTS AND APPROXIMATIONS OF

> TOTAL RADIOACTIVITY 6 E. BATCH RELEASES 8 F.

2 ABNORMAL RELEASES 9 G. ESTIMATE OF TOTAL ERROR 9 III. GASEOUS EFFLUENTS

SUMMARY

INFORMATION 10 IV. LIQUID EFFLUENTS

SUMMARY

INFORMATION 10 V. SOLID WASTE 10 VI. RADIOLOGICAL IMPACT ON MAN 10 VII. METEOROLOGICAL DATA 10 VIII. RADIOACTIVE LIQUID BFFLUENT MONITORING INSTRUMENTATION OPERABILITY 11 IX. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRURENTATION OPERABILITY 11 X. LIQUID HOLD UP TANKS 11

! XI. RADIOLOGICAL ENVIRONMENTAL MONITORING 11 XII. LAND USE CENSUS 11 XIII, OFFSITE DOSE CALCULATION MANUAL (ODCM) 11 XIV. MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID Wh3TE TREATMENT SYSTS:MS 11 XV. PROCESS CONTROL PROGRAM (PCP) 11 a

PAGE XVI. TABLES TABLE 1 RADIOACTi1E GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM 12 TABLE 2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 13 TABLE 3 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 14 TABLE 4 GASEOUS EFFLUENTS - CONDITIONALLY ELEVATED RELEASES 16 TABLE 5 GASSOUS EFFLUENTS - GROUND LEVEL RELEASES 19 TABLE 6 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 22 TABLE 7 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 27 ATTACHMENT 1 OffsiLe Dose Calculation Manual Changen i

e

DEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FACILITY: River Bend Station, Unit 1 LICENSEE: Gulf States Utilities REPORT PERIOD: January 1, 1992 Through June 30, 1992 I. INTRODUCTION Enclosed is the . Semiannual Radioactive Effluent Release Report-for the period of January 1, 1992 through June 30, 1992. This report is submitted in accordance with Technical Specification 6.9.1.8 of Appendix A to River Bend Station (RBS) License Number NPF-47.

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. . i II. SUPPLEMENTAL INFORMATION i

A. Regulatory Limits i 3. 10CFR20 Limits

a. Fission and Activation Gagga In accordance with Technical Specification 3.11.2.1, the dose rate due to noble gases released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY  ;

shall be limited to less than or equal to 500 millirems / year (mremo/yr) to the total body and less than  ;

l or equal to 3000 mrems/yr to the skin:

DRn - Dose rate to the total body in mrems/yr n .

= 3.15E+07 l' K, (X/Q) 0, s 500 mrems/yr i=1 and DRsun = Dose rate to the skin in mrems/yr n .

- 3.15E+07 E (L + 1.1M,)

4 (X/Q) - O, s 3000 mrems/yr i=3 i

(above terms defined in RBS ODCM)

b. Radiolodines and Particulates .

In accordance with Technical Specification 3.11.2.1, 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 l to areas at and beyond the SITE BOUNDARY shall be limited to less than or equal to 1500 mrems/yr to any organ:

DRusop, = Dose rate to the organ 7 for the age group of interest from iodine, tritium,

l. and 8 day particulates via the inhalation i pathway in mrems/yr n .

- E Pi (X/Q)o Qi s ~1500 mrems/yr

, i=1 l

(above terms defined in RBS ODCM) 2-of 31 l

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

I 4 4

j i

c. higuid Effluenta l In accordance with Technical Specification 3.11.1.1, the

] concentration of radioactive material released in liquid I effluents to UNRESTRICTED AREAS shall be limited to the l concentrations specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than dissolved and entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 microcuries/ml total >

activity.

2. 10CFR50, Appendix I Limits
a. Fission and Activation Gatta l.

In accordance with Technical Specification 3.7.1.2.2, the

! air dose due to noble gases releaced in gaseous effluents to areas at or beyond the SITE BOITNDARY shall be limited to Do., u - The gamma air dose from radioactive noble gases in millrad (mrad) f

n

- E M, (X/Q) Q, c 5 mrads/qtr 1-1 s 10 mrads/yr Dan, - Beta air dose from radioactive noble gases in mrad n

. - E N, (X/Q) 0, s 10 mrads/qtr i=1 s 20 mrads/yr i

(above terms defined in RBS ODCM)

b. Raitoiodines and Particulat_eg In accordance with Technical Specification 3.11.2.3, the dose to a MEMB Q OF THE PUBLIC from iodine-131, iodine-133, tritium and i

all radio'1uclides in particulate form with half-lives greater

, than 8 days, in gaseous effluents releases to areas at and

, beyond the SITE BOUNDARY shall be limited to:

Da mi,,- -- Dose in arem to' the- organ (7) of a specified age grouo from radiciodines,.

tritium, and 8 day particulates.via the pathway of interest i

l l

l l

l 3 of 31 l

l

, , , , . . + . - - . - ..m., .L,_,--.- , , ,y, -,-,--n,,,-,w_.. -

J T 4 i

7 n

- 3.17E-08 E R ,, (X/Q)o Q,

! i-1 1

J and/or i

i n

= 3.17E-08 E R,, (D/Q) Q, 1-1 J

I RD.d i

D, - Dose in mrem to the organ (7) of a specified l age group from radiciodines, tritium, and 8

day particulates from all pathways

, n

= E Dame, s 7.5 mrem /qtr

z-1 s 15 mrem /yr l- (above terms defined RBS ODCM) l C. Liquid Effluents 4

In accordance with Technical Specification 3.11.1.2, the i dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials l'n liquid effluents released to

UNRESTRICTED AREAS shall be limited to

D,, = A,, a t Q,

"(DF) D, n

i DTotAt, = E D, 3

ial l Dwat, - Total dose commitment to the

. organ (7) due'to all releases during i the desired time interval in mrem-i i

l l

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

I and Dwm s 1.5 mrem /qtr 1 Total Body j s 3 mrem /yr

. Dung s 5 m: 1m/qtr 7.ny Organ

. s 10 mrem /yr 4

tabove terms defined in RBS ODCM) i

! 3. 40CFR190 Limits In accordance with Technical Specification 3.11.4, 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-l s 25 mrems to the total body or any organ (except the thyroid)

) s 75 mrems to the thyroid i

4

4. Miscellaneous Limits
a. Y.gntilation Exhaust Treatment Sysinm In accordance with Technical Specification 3.11.2.5, the i VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses, due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY would exceed 0.3 mrem to any organ in a 31 day pt.riod.
b. 1,iguid Radwaste Treatment Sygigm In accordance with Technical Specification 3.11.1.3, the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their

, discharge w'.len the projected doses, due to the liquid effluent, to UURESTRICTED AREAS would exceed 0.06 mram to the total body or 0.2 mrem to any organ in a 31 day period.

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

1 1

J B. Maximum Permissible Concentrations J

1. Gaseous Releases The RBS Radiological Effluents Technie:1 y ecifications (RETS) for gaseous releases are based on the dose rate restrictions of 10CFR20, rather than the Maximum Permissible
Concentrations (MPC) listed in 10CFR20 Appendix B, Table II,
Column I.

j 2. Liquid Releases 4

! The Maximum Permissible Concentration of radioactive

! materials in liquid effluents is limited by 10CFR20, Appendix t B, Table II, Column 2. The MPC chosen is the most

{ conservative value (i.e., the lowest) of either the soluble r or insoluble MPC for each radionuclide. .

j C. Average Energy  !

l .

Period E-Bar (MeV/ dis) 01/01/92 - 06/30/92 1.40

(

j D. Measurements and Approximations of Total Radioactivity t

1. Gaseous Effluents i j a. Eission and Activation Gaseg i
Periodic grab samples are obtained from the Main Plant l Exhaust Duct, Fuel Building Exhaust Vent and Radwaste
Building Exhaust Vent. These samples are analyzed t

utilizing high purity germanium detectors coupled to l computerized pulse height analyzers.- The sampling and 4 analysia frequencies are described in Table-1.. Sampling-j and analysis of thece effluent streams provide noble gas l l

i radionuclide relative abundances which can then be +

applied to the noble gas gross activity and gross

activity release' rate to obtain nuclide specific

! activities and release rates. The noble gas gross l activity released within a specific time pericd is determined by integrating the stack monitor release rate

! over the considered time period. _If no activity _was

, detected between stack grab samples and significant i -increase in-hourly averages were recorded, the nuclide ,

+

relative abundances of the last sample'which indicated the presence of activity was utilized to obtain nuclide specific.activitics. . Correction factors for the monitors are derived and applied for each sampling period whenever

! noble gas radionuclides are detected in the effluent stream.

P

  1. t 6 of 31

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

- ...- - - g

b. Birt _icnintes and Iocline Particulates and iodine are continuously sampled from each of the three release points utilizing a particulate filter and charcoal cartridge in line with a sample pump (stack monitor pump). These filters and charcoal cartridges are removed and analyzed in accordance with the frequencies specified in Table 1. Analysis is performed to identify and quantify radionuclides utilizing high purity germaaium detectors coupled to g computerized pulse height analyzers. Given the nuclide a specific activity concentrations, process flow rate, and time which the sample covered; the nuclide specific activity released to the environment can be obtained.

Due to the continuous sampling process, it is assumed that the radioactive material is released to the environment at a constant rate within the sampling period. Sr-99 and Sr-90 are quantitatively analyzed by counting s'.ie digested filter precipitate with a gas flow proportional counter. Gross alpha analysis is performed using a zinc sulfide scintillation counter.

c. IIltium Tritium grab samples are obtained from the three release points at the specified frequencies listed in Table 1 utilizing an ice bath condensation collection method.

The collected sample is then analyzed utilizing a Liquid Scintillation Counter. Given the tritium concentration, process flow rate, and time period for which the sample is obtained, the tritium activity released to the environment can be determined. rte to the frequency of sampling, i t is assumed that the tritium is released to the environment at e constant rate within the time period for which the sample is obtained.

2. Liquid Effluents Representative grab samples are obtained from the appropriate sample recovery tank and analyzed prior to release of the tank in aceordance with the frequencies listed in Table 2.

Analysis for gamma emitting nuclides (including dissolved and entrained noble gases) is performed utilizing a high resolution germanium detector coupled to a computerized pulse height analyzer. Tritium concentration is determined utilizing a Liquid Scintillation Counter. Sr-89 and Sr- 90 are quantitatively analyzed by counting the precipitate with a gas flow proportional counter. Fe-55 is counted with a Liquid Scintillation Counter after digestion of the iron.

Gross alpha analysis is performed using a zinc sulfide scintillation counter.

Given the nuclide specific activity concentration and total volume of the tank that was released, the activity of each nuclide released to the environment can be determined.

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E. Batch Releases

1. Liquid ist Ouartgr_1992
a. Number of batch releases  : 141
b. Total time period for batch releases  :-908.65 hr
c. Maximum time period for batch releases  : 18.78 hr
d. Average timo period for batch releases  : 6.56 hr
e. Minimum time period for a batch release  : 0.02 hr-
f. Average stream flow dung periods of

_ release of ef fluent irwo a _ flowing stream : 571,000 f t'/sec 2nd oua-ter_1222

a. Number of batch releases  : 179
b. Total _ time period for batch releases  : 1132.5 hr
c. Max!, mum time period for batch releases . 56.2 hr i d. Average time period-for batch releases  : 6.37 hr
e. Minimum time period for a batch release  : 0.133 hr
f. Average stream flow:during periods of-release of effluent into a flowing stream  : 473,000 f d/sec

(

2. Gaseous s-All gaseous releases from River Bend' Station are considered continuous releases.

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] F.- Abnormal Releases a

At approximately 02:00 on March 5, 1992, tornadic winds and heavy rain l were experienced at River Bend Station. These winds damaged the

southeast wall of the Turbine Building and scattered approximately  ;

j 2730 square feet of 1.5 inch thick fiberglass insulation and other

debris onto the buildings and grounds within the orotected Area and l into the parking lots, roadways and grounds outside and nort.h of the j Protected Area.

1

The conclusion of the event is that a small amount of Co-60 was washed 4

to the unrestricted area into East Creek. The amount of Co-60

! released outside the Protected Area was conservatively estimated to j be 1.29E 07 Curies.

1

1. Liquid Efi3uents j ist OupIT.er 1992 i a. Number of releases 0

{ b. Total Activity released 0 Curies 1

2nd Ouarter 1992 l a. Number of releases 0

b. Total activity released 0 Curies
2. Gaseous Effluents l 1st Ouan.gr 1992 a.

Number of releases 1

b. Total activity released 1.29E-07 Curies 2nd Ouarter 1992 i a. Number of releases- 0

, b. Total activity released 0 Curies i

j 4

G. Estimate of Total Error
1. Liquid l

l The maximum error associated 'J! .h samp" e collection,

laboratory analysis, and discharge volume are collectively estimated to bei Fission and Activation Products
1 14.2%

Tritium : i 14.2%

Dissolved and Entrained Noble Gases : A 14.2%

i Gross Alpha Radioactivity  : .i 14.2%

i 2. Gaseous l-The maximum errors (not including sample line loss) associated with sample--flow,-process flow, sample. collection,

-monitor accuracy and labgrg og analysis are collectively

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

estimated to.bei Fission and Activation Gases  : t 37.0%

Iodine  : 1 18.6%

Particulates 1 18.6%

Tritium  : 1 18.2%

3. Determination of Total Error The total error (i.e., collective error due to sample collection, laboratory analysic, sample flow, process flow, monitor accuracy, etc.) is esiculated using the following equation:

Er = \/ (E i )3 + ( 2 ) ' + . . . ( E,) 3 where:

Et = total error E,

i E . . . E, = individual errors due_ to sample collection, laboratory analysis, sample flow, process flow, monitor accuracy, etc.

III. GASEOUS EFFLUENTS

SUMMARY

INFORMATION Refer to Tables 3, 4 and 5 for Summation of All Releases and'Nuclidos Releesed, respectively. It should be noted that an entry of "0.00E+00" Curie (Ci) or' microcurie /second (uCi/sec) in this section does not indicate the absence of a radionuclide; but, rather, indicates that the concentration of the particular radionuclide was below the Lower Limit of Detect. ion- (LLD) as-listed-in Table 1.

IV. LIQUID EFFLUENTS SLAMARY INFORMATION Refer to Table 6 for Summation of All Releases and Nuclides Released.

It should be noted that -an entry or "0.00E+00" Ci or uCi/ml in this section does not indicate the absence of a radionuclide; but, rather indicates that the concentration of the particular radionuclide was i

below the Lower Limit of Detection _(LLD) as listed in Table 2.

y V. SOLID WASTE Refer to Table 7.

VI, RADIOLOGICAL IMPACT ON MAN '

This . information_ _ will be provided in the end-of year report as described in Technical Specification 6.9.1.8.

VII.-METEOROLOGI' CAL DATA This information will be provided in the end-of-year report as described-in Technical Specification 6.9.1.8.

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d a . .

1 1

, VIII. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERABILITY  !

j The minimum number of channels required to be OPERABLE as d(escribed  !

in Table 3.3.7.10-1 of Technical Specification 3.3.7.10 were, if

inoperable at any time in the period 1/1/92 through 6/30/92, restored i to operable status within the required time. Reporting of these ,

i inoperable channels in this report is, therefore, not required. '

l 1 IX. RADIOACTIVE GASEOUS EFFLUENT _ MQhLTTORIMG INSTRUMENTATION OPER1WlM.TX 1

, The minimum number of channels requirod to be OPERABLE as described in Table 3.3.7.11-1 of Technical Specification 3.3.7.11 were, if inoperab30 at any time in the period 1/1/92 throagh 6/30/92,

restored to operable status within the required time. Reporting i of these inoperable channels in this report is therefore, not

. required.

) X. MQUID HOLD UP TANKS t

t The maximum quantity of radioactive material, excluding tritium and i dissolved or entrained noble gases, contained in any unpreterted ,
outdoor tank during the period of 1/1/92 through 6/30/92 was less l than or equal to the 10 curie limit as required by Technical 1

Specification 3.11.1.4.

j XI. RADIOLOGICAL ENVIRONMENTAL MONITORING I There were no changes in sampling locations for the Radiological j Environmental Monitoring Program (REMP) during the reporting ,

period 1/1/92 through 6/30/92.

l XII. LAND USE CENSUS l

1 This information will be presented in the end-of-year report. The Land Use Census results will be available in September, 1992.

l XIII. QFFSITE DOSE CALCULATION MANUAL (ODCM)

! See Attachment One for changes made to the_ODCM for the period of

_ 1/1/92 through 6/30/92.

XIV. MJOR CHANGES TO RADIOACTIVE LIOUID, GASEOUS, AND SOLID WASTE 1

TREATMENT SYSTEMS 4

There were no major changes to the radioactive liquid, gaseous, and -

solid waste treatment systems for the period of 1/1/92 through 6/30/92.

i

! XV. PROCESS CONTROL PROGRAM (PCP)

I No changes were made to the RBS Process Control Program (PCP) -for the '

period 1/1/92 through 6/30/92. l 11 of-31 y -y+rw- v,--r y v-wirv vv e -re-7w,w w v-TwF- e- n w -r e w +wt M -r- + --w - or , 7 vw v ~ - - y v.e,- -vr, wr- =-+,as--*-vyrv,- v-me-w*

  • c -% w v- vt ,-'e -

y w=rn--'**--twy---*

TABLE 1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM

=::= _e -

.- -- - _ - . - . . = - - _ . - - - _.

-..--:--.,.--w+

GASEOUS SAMPLING MINIMUM TYPE OF LOWER RELEASE FREQUENCY ANALYSIS ACTIVITY ANALYSIS LIMIT OF TYPE FREQUENCY DETECTION (LLD) uCi/ml A. Main Plant M M Principal Gamma Exha'ast Grab Emicters 1.00E-04 Duct Sample 11- 3 1.00E-06 1

! B. Fuel M M Principal Gamms 3

Building Grab Emittera 1.00E-04 Vantilation Sample

Exhaust j

Duct  !!- 3 1.00E-06 I

i C. Radwaste M M Principal Gamma 1.00E-04 1

Building Grab Emitters j Ventilation Sample j Exhaust Duct

, D. All Release Continuous W I-131 1.00E-12 Types as Charcoal _,

j listed in Sample 1.00E-1 .

A, B, &C I 133 Above

. Continuous W Principal Gamma 1.00E-11

Particulate Emitters (I-131,Others)

Sample

! Continuous M Gross Alpha 1.00E-11 Composite Particulate i Sample i Continuous Q Sr-89, Sr-90 1.00E-11 l Composite l Particulate i Sample Continuous Noble Gas Noble Gases 1.00E-06 Monitor Gross Beta or Gamma i

l W = AT LEAST ONCE PER 7 DAYS M = AT LEAST ONCE PER 31 DAYS Q = AT LEAST ONCE PER 92 DAYS 12 of 31

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

am_.-- .- , _

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

TABLE 2 g RADIOACTIVE LIQUID WASTE SAMPLING AND MALYSIS PROGRAM

= 22 = =============== - -

-- __ .-_...=T --- =r z==:-

LIQUID RELEASE SAMPLING MINIMUM TYPE OF ACTIVITY LOWER LIMIT TYPE FREQUENCY ANALYSIS ANALYSIS OF DETECTION FREQUENCY (LLD) uCi/ml A. Batch Waste P P Principal Gamma 5.00E-07 Release Each Batch Each Batch Emitte m _pspepi _

(Liquid for Ce-144 5.00E-06 Radwaste Recovery '

5 Sample I-131 1.00E-06 Tanks i

P M Dissolved and 1.00E-05 One Batch /M Entrained Gases (Gamma Emitters)

P M H-3 1.00E-05 Each Batch Composite _

Gross Alpha 1.00E-07 P Q Sr-89, Sr-90 5.00E-08 Each Batch Composite c

Fe-55 1.00E-06

. he g P= Prior to each radioactive release M = At least once per 31 days Q = At least once per 92 days 13 of 31

TABLE 3 Effluent and Waste Dicposal Semi Annual Report 1931 Year Gaseous Effluents - Summation of All Releases 1/2 Quarters Unit Quarter 1 Quarter 2 Estimated Total Error % ,

A. Noble Gases

1. Total Release Ci 8.27E+01 0.00E+00 3.70E+01
2. Average release uCi/sec 1.05E+01 0.00E+00 rate for period
3. Percent of  % 2.18E+00 0.00E400 technical specification limit (1)

B. Iodine

1. Total I-131 and 1-131 1.86E+01-Ci I-133 5.30E 03 1.18E-04

~

I-133 Ci 5.11E-02 --

0.00E+00

2. Average release I-131 7.00E-04 1.50E-05 rate for period uCi/sec I-133 6.50E-03 0.00E400
3. I-131 + I-133  % 2.40E+00 4.62E-02 centribution percent of technical specification limit C. Particulates
1. Particulates with Ci 9.29E-04 (2) 1.86E+01 half lives of > 8 days

__. m

2. Average release uCi/sec 1.18E-04 (2) rate for period

-3. Percent of  % 5.13E-02 (2) technical specification limit

4. Gro- alpha Ci 0.00E+00 0.00E+00 radioactivity 14 of 31-

s i

J i _

Unit Quarter i Quarter 2 Estimated Total l Error t  ;

]

1 i D. Tritium i

j _ _ _ _ _ _

! 1. Total Release Cl 7.69E-01 3.03E-01 1.82E+01

! 2. Average release uCi/sec 9.75E-02 3.85E-02  ;

! rate for period -

3 t 3. Percent of  % 3.70E-03 1.90E-03

! technical -

! Specification  !

l limit l I ,

l (1) Either the gamma air dose limit of. 5 mrads/qtr or beta air dose limit j of 10 mrads/qtr '(T.S. 3.11.2.2.a), which ever is most limiting. ,

i (2) Data is not available for submission at this time, supplemental report i will follow.

i i

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l I

t l

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. - . -- _ . . - - - - . - _ _ _ . . - . - - - . - . . . . - -- . = . - _ _-

TABLE 4 EFPLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT 1992 YEAR GASEOUS EFFLUENTS - CONDITIONALLY ELEVATED RELEASES 1/2 QUARTERS CONTINUOUS MODE BATCH MODE

, Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission Gases Argon-41 Ci 0.00E+00 0.00E+00 N/A N/A Krypton-85m Ci 5.84E+00 0.00E+00 N/A N/A Krypton-85 Ci 0.00E+00 0.00E+00 N/A N/A Krypton-87 C1 1.30E+00 0.00E+00 N/A N/A Krypton-88 C1 4.87E+00 0.00E+00 N/A N/A Xcnon-133m Ci 0.00E+00 0.00E+00 N/A N/A Xenon-133 Ci 8.91E+00 0.00E+00 N/A N/A Xcnon _'35m Ci 7.69E+00 0.00E+00- N/A N/A Xcnon-135 Ci 1.17E+01 0.00E+00 N/A N/A

, Xenon-137 Ci 0.00E+00 0.00E+00 N/A N/A Xcnon-138 Ci 1.01E+0i 0.00E+00 N/A N/A Unidentified Ci N/A N/A N/A N/A Total For Period Ci 5.04E+01 0.00E+00 N/A N/A l l

l 2. Gaseous Iodine l

l Iodine-131 Ci 5.21E-03 1.00E N/A N/A Iodin'e-132 Ci 0.00E+00 0.00E+00 N/A _

N/A j Iodine-133 Ci 5.08E-02 0.00E+00 N/A N/A Iodine-134 Ci 0.00E+00 0.00E+00 N/A N/A Iodine-135 Ci 0.00E+00 0.00E+00 N/A N/A L

Total Ci 5.60E-02 _

1.00E-04 -N/A N/A 1

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Continuous Mode Batch Mode c=wNuclides Released 1

Unit Quarter 1 Quarter 2 Ouarter 1 Quarter 2

3. Particulates

_ n -. .n_.--- . . . .

Strontium-89 Ci 3.68E-04 (1) N/A N/A Strontium-90 Ci 1.24E-06 (1) N/A N/A Cesium-134 Ci 0.00E+00 0.00E+00 N/A N/A Cesium-137 Ci 0.00E+00 0.00E+00 N/A N/A Barium-140 Ci 5.55E-04 0.00E400 N/A N/A i Cobalt-60 Ci 0.00E+00 0.00E+00 N/A N/A l, i Chromium-51 Ci 0 . (. J E + U D 0.00E+00 N/A N/A Zirconium-95 Ci .c Niobium-95 Ci 0.00F400 0.00E+00 N/A N/A g' 0.00E+00 0.00E+00 N/A N/A I

Zinc 65 Ci 0.00E+00 0_0y 400 N/A N/A Iron-59 Ci 0.00E400 0. 0 iW C 0 N/A N/A Manganese-54 Ci 0.00E+00 0.00E+0G N/A N/A i

, Iodine-131 Ci 0.00E400 0.00E+00 N/A N/A Lantaanum-140 Ci 0.00E+00 0.00E+00 N/A N/A Cerium-141 Ci 2.81E-0E 0.00E+00 N/A N/A Cerium-144 Ci 0.00E+00 0.00E+00 N/A N/A Cobalt-58 Ci 0.00E+00 0.00E^00 N/A N/A _

Silver-110m Ci 0.00E+00 0.00E400 N/A N/A 1

Molybdenum-99 Ci 0.00E+00 0.00E+00 N/A N/A Unidentified Ci N/A N/A N/A N/A Total For Period Ci 9.27E-04 (1) N/A N/A 17 of 31

Nuclides Released Unit Quarter 1 Quarter 2 -Quarter 1 Quarter 2 __

4. Tritium Hydrogen-3 Ci 6.26E-01 2.10E-01 N/A N/A

- (1) Data is not available for submission at this time, supplemental report-will follow.

RQTK1 Main Plant Exhaust Duct is considered a conditionally elevated release point.

-d 4

1 18 of 31

TABLE 5 '

I EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT 1992 YEAR GASEOUS EFFLUENTS - GROUND LEVEL RELEASES 1/2 QUARTERS Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission Gaees

-u-Argon-41 Ci 0.00E+00 0.0(ip+00 N/A N/A Krypton-85m Ci 0.00E+00 0.00E+00 N/A N/A Krypton-85 Ci 0.00E+00 0.03E+00 N/A N/A i Krypton-87 Ci 0.00E+00 0.(j0E+00 N/A N/A Krypton-88 Ci 0.00E+00 0.,00E+00 N/A N/A {

Xenon-133m Ci 0.00E+00 0.00E+00 N/A N/A )

Xenon-133 C1 1.910401 C.00E+00 N/A N/A Xenon-135m Ci 2.00E+00 0.00E+00 N/A N/A Xenon-135 Ci 1.12E+01 0.00E+00 N/A N/A Xenon-137 Ci 0.00E+00 0.00E+00 N/A N/A Xenon-138 Ci 0.00E+00 0.00E+00 N/A N/A Unidentified Ci N/A N/A N/A

, N/A Total For Period Ci 3.23E+01 0.00E+00 N/A N/A l

2. Gaseous Iodine Iodine-131 Ci 7.18E-05 1.81E-05 N/A N/A Iodine-132 Ci 0.00E+00 0.00E+00 N/A N/A Iodine-133 Ci 2.76E-04 0.00E+00 N/A N/A

, Indine-134 Cf 0.00E+00 0.00E+00 N/A N/A Iodine-135 Ci 0.00E+00 0.00E+00 N/A N/A _

Total Ci 1.81E-05 3.49E-03 N/A N/A 19 of 31 2 ________--_m. - - - - - - - - - - - - - - - - - - ' - - - -

. - . . . . .._= - -. - . _ - - _- .. . . . . .. . - . - . - _ . - . - . . . . . . -

i

Continuous Mode Batch Mode l ,

j- Nuclides Reles 'ed Unit Quarter 1 Quarter 2 Quarter 1- Quarter 2 i

j 3. Particulates 4 N;7

.y utinm-89 C1 2.29E-06 (1) N/A N/A Strontium-90 Ci 8.39E-08 (1) N/A N/A j Cesium-134 Ci 0.00E+00 0.00E+00 N/A N/A

! Cesium-137 Ci 0.00E+00 5.32E-07 N/A N/A i

l Barium Ci 0.00E+00 0.00E+00 N/A ,

N/A Lanthanum 140 C1 0.00E+00 0.00E+00 N/A N/A j -

Cobalt-60 Ci 0.00E400 8.69E-06 N/A N/A Chromium-51 Ci 0.00E+00 0.00E+00 N/A N/A 1 Zircenium-niobium- Ci 0.00E+00 0 JUA 4 0 N/A N/A I 95 Zinc-65 Ci ^

_de00 0.00E+00 N/A N/A Iron-59 Ci 0.00E+00 0.00E+00 N/A N/A

! Manganese-54 -

Ci 0.00E+00 1.53E-06 N/A N/A 4

Iodine-131 Ci 0.00E+00 0.00E+00 N/A N/A Todine-132 Ci 0.00E+00 0.00E+00- N/A N/A i lodine-133 Ci 0.00E+00 0.00E+00 N/A N/A t

Cerium-141 Ci 0.00E+00 0.00E+00 N/A N/A 1

Cerium-144 Ci 0.00E+00 0.00E+00 N/A N/A Cobalt-58 Ci -0.00E+00- 0.00E+00 N/A N/A

, Silver-110m Ci 0.00E+00 0.00E+00 N/A N/A i Molybdenum-99 Ci 0.00E+00 0.00E+00 N/A N/A 4

l Unidentified Ci N/A N/A W/A N/A

, TotalForPerjod Ci 2.37E-06 (1) N/A N/A i

i t

4 i

20 of 31

{

i

Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 4.0 Tritium Hydrogen-3 Ci 1.42E-01 9.30E-0? N/A N/A _

(1) Data is not available for submission at this time, supplemental report will follow, NOTFa Fuel Building Exhaust Vent and Radwaste Building Exhaust Vent are considered ground level release points, l

l l

21 of 31

TABLE 6 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT 1992 YEAR

LIQUID EFFLUENTS -

SUMMATION OF ALL RELEASES

Unit Quarter 1 Quarter 2 Est.

Total Error %

A. Fission and activation products l 1. Total release (not including Ci 2.97E-01 (4) 1.42E+01 tritium, gases, alpha)

2. Average diluted conccntration uCi/ml 2.94E-07 (4) during period
3. Percent of applicable limit (1)  % 2.38E+01 (4)

B. Tritium

1. Total R.elease Ci 6.3PR+00 9.61E+00 1.42E+01
2. Average diluted concentration uCi/ml 6.30E-06 1.19E-05 J

during period

3. Percent of applicable limit (2)  % 2.10E-01 3.98E-01

. C. Dissolved and entrained gases

1. Total Release Ci 2.17E-01 7.47E-05 1.42E+01
2. Average diluted concentration uCi/ml 2.14E-07 9.28E-11

, during period

3. Percent of applicable limit (3)  % 1.07E-01 4.64E-5 i

1 22 of 31

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

-f l-..

i Unit Quarter 1 Quarter 2- Est.

i Total

- Error %

i

D. Gross alpha radioactivity i

!. 1. Total release Ci 0.00E+00 0.00E+00 1. 4 2 E + 01.. _

l' i Unit Quarter 3 Quarter 4 Est. Total I Error %

j -.

j E. -Volume of waste released (prior to dilution) 1 -Liters 7.54E+06 9.59E+06 8.73E-01 f F. Votume of dilution water Liters 1.12E+09 8.05E+08 5.70E-01 (1) One . quarter of 5 Ci annual limit -(1.25 Ci) for -liquid . releases is the applicable limit from 10CFR50 Appendix I, except for tritium and dissolved

or entrained noble gases.
'(2) 10CFR20, Appendix B, Table II, Column 2 MPC' limit of 3.00-03 uCi/ml for tritium'.

4 l (3) Technical Specification 3.11.1.1 limit of 2.00E-04 uCi/ml for dissolved or

! entrained noble gases in liquid effluents.

, (4) Data is not available at this time,-supplemental report will follow, i

i 4

i 5-i i

i-4 4

N J

, 23 of 31 J

.a._. -

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT 1992 YEAR LIQUID EFFLUENTS 1/2 QUARTERS G. Particulates Continuous Mode Batch Mode Nuclides Released Unit Quartnr 1 Quarter 2 Quarter 1 Quarter 2 Hydrogen-3 Ci N/A N/A 6.38E+00 9.61E+00 Arsenic-76 Ci N/A N/A 1.23E-04 3.70E-06 Strontium-89 Ci N/A N/A 2.34E-05 (1)

Strontium-90 Ci N/A N/A 5.97E-04 (1)

Strontium-91 Ci N/A N/A 5.78E-05 0.00E+00 Strontium-92 Ci N/A N/A 2.22E-04 1.21E-04 i Cesium-134 Ci N/A N/A 0.00E+00 0.00E+00 Cesium-137 Ci N/A N/A 3.35E-04 4.87E-05 Iodine-131 Ci N/A N/A 9.76E 0.00E+00 Iodine-132 Ci N/A N/A 0.00E+00 0.00E+00 Iodine-133 Ci N/A N/A 3.72E-04 0.00E+00 Iodine-134 Ci N/A N/A 0.00E+00 0.00E+00 Iodine-135 Ci N/A N/A 0.00E+00 0.00E+00 Sodium-24 Ci N/A N/A 1.87E-05 0.00E+00 Cobalt-57 Ci N/A N/A 0.00E+00 0.00E+00 Cobalt-58 Ci N/A N/A 9.20E-03 3.17E-03 Cobalt-60 Ci N/A N/A 1.17E-01 8.85E-02 Iron-55 Ci N/A N/A 8.82E-04 (1)

Iron-59 Ci N/A N/A 9.33E-03 1.39E-03 Zinc-65 Ci N/A N/A 7.06E-04 2.83E-05 Manganese-54 Ci N/A N/A 4.36E-02 1.65E-02 Manganese-56 Ci N/A N/A 0.00E+00 0.00E+00 Chromium-51 Ci N/A N/A 7.66E-02 1.84E-02 Zirconium-95 Ci N/A N/A 7.06E-04 2.83E-05 Niobium-95 Ci N/A N/A 1.32E-03 4.01E-04 Niobium-97 Ci N/A N/A 6.85E-04 5.27E-04 Molybdenum-99 Ci N/A N/A 2.11E-03 ,0.00E+00 24 of 31

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

i-i i Continuous Mode Bn ch Mode j _Naclides Released Unit Quarter 2 Quarter 2 Quarter 1 Quarter 2 lechnicium 99m Ci N/A N/A 8.90E-04 9.07E-07 I Barium-140 Ci N/A N/A 6.86E-04 0.00E+00 1

! Lanthanum-140 Ci N/A N/A 1.35E-02 0.00E+00 Cerium-141 Ci N/A N/A 2.78E-03 6.99E-04 i

! Cerium-144 Ci N/A N/A 3.13E-04 1.51E-04 1

Antimony-122 Ci N/A N/A _ 1.06E-05 0,00E+00 l Antimony-124 Ci N/A N/A 2.96E-03 E. 04E-04 Rhodium-105 Ci N/A N/A 6.35E-04 0.00E+00
Bromine-82 Ci N/A N/A 0.00E+00 0.00E+00 Neptunium-239 Ci N/A N/A 7.17E-04 0.00E+0L j Yttrium-91m Ci N/A N/A 6.34E-05 0.00,R+00 Yttrium-92 Ci N/A N/A 1.87E-03 0.00E+00 Silver-110m Ci N/A N/A 9.17E-04 5.87E-04 Tungsten-187 Ci N/A N/A 0.00E+00 0.00E+00
Copper-64 Ci N/A N/A 0.00E+00 0.00E+00 Tin-113 Ci N/A N/A 2.63E-04 0.00E+00 Tellurium-132 Ci N/A N/A 7.72E-05 0.00E+00 Ruthenium-103 Ci N/A N/A 1.51E-03 3.25E-04 Ruthenium-105 Ci N/A N/A 6.35E-04 0.00E+00 f Total For Period Ci N/A N/A 6.67E+00 _

(1) l-(1) Data is not available at this time, supplemental report will follow, a

j.

.I 25 of 31

l 1

1 H. DISSOLVED AND ENTRAINED GASES Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Argon-41 Ci N/A N/A 0.00E+00 0.00E+00 Krypton-85m Ci N/A N/A 0.00E+00 0.00E+00 Krypton-85 Ci N/A N/A 0.00E+00 0.00E+00 _

Krypton-87 Ci N/A N/A 0.00E+00 0.00E+00 Krypton-88 Ci N/A N/A 0.00E+00 0.00E+00 Xenon-131m Ci N/A N/A 0.00E+00 0.00E+00 Xenon-133m Ci N/A N/A 3.08E-03 0.00E+00 Xenc a-13 3 Ci N/A N/A 7.40E-02 7.47E-05 Xenon-135m Ci N/A N/A 3.91E-05 0.00E+00 Xenon-135 Ci N/A N/A 1.39E-01 0.00E+00-Xenon-137 Ci N/A N/A 0.00E+00 0.00E+00 Xenon-138 Ci N/A N/A 0.00E+00 0.00E+00 Unidentified Ci N/A N/A N/A N/A Total For Period Ci N/A N/A 2.17E-01 7.47E-05 26 of 31

TABLE 7 Effluent and Waste Disposal Semiannual Report 1992 Year Solid Waste und Irradiated Fuel Shipments i Peporting Period January 1, 1992 to June 30, 1992 Qtr 1/2 A. SOLID WASTE SHIPPED FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) 6-Month Waste Est. Total Type of waste Unit Period Class Error, %

) 1.

a. Spent resin, filters, **m3 111.8 A-U See sludges, evaporator Ci 304.0 A-S Below bottoms, ect. B
b. Dry compressible wastes, **m3 83.60 A-U See l contaminated equip., etc. C1 1.13 Below
c. Irradiated components, **m3 0.0 N/A N/A control rods, etc. Ci 0.0
d. Other (None) *+m3 0.0 N/A N/A Ci 0.0 Radwaste Estimated Total Error (%)

Waste types considered are processed solid wastes (i.e. resins, filter media, ect.) and Dry Active Waste (DAW) - Compactable/Non-compactable.

1. Possible Errors
a. Volume
b. Representative Sampling
c. Instrument / Counting
d. Dese to Curie calculations
2. Volume Error
Radwaste vendor personnel have stated that level indication can be determined to 10.5 inches. This correlates to approximately 1.0%. Container manufacturer stated design tolerance' allows for 1.0% deviation from container-dimensions.
3. Representative Sampling Error Sampling error for processed resins is based upon obtaining a representative sample from the waste being processed using an

, iso-lock sampler. Sampling error for Dry Active-Wastes is based upon obtaining a representative cample from the material being packaged. This error is assumed to be 10%, which is consistent with industry standards.

4. Instrument / Counting Error Error caused by the sample geometry, counting time,. sample activity,'and instrument background is estimated by Chemistry to be 10%. The error for radiological survey instruments is estimated by Radiation Protection to be i20%.
5. Dose to Curie Calculations The Dose to Curie methods used to calculate activity suffer analytical inaccuracies in that certain important parameters i are neglected. These parameters- are . geometry of package, measuring instrumant characteristics, build-up, internal attenuation effect, and external -media attenuation. An I activity correction factor is applied to provide-adjustment l for these factors.

l

    • - Volume considered to be the-total disposal volume of the container.

27 of-31 l

_, , ,2 . , ESTIMATES OF MAJOR NUCLIDES BY WASTE STREAM Type of Waste Spent resin, filters Dry: compressible _ Irradiated 'Othef sludges, evaporator waste, contamineted components, (None) bottoms, etc. equipment, etc. control ,

rods, ctc.

Principle Percent Percent N/A N/A Radionuclides Isotope Abundance Isotope Abundance Identity and

% Abundance Co-60 65.994%' Fe-55 51.420%

Fe-55 15.658% Co-60 26.460%

Mn-54 6.790% Cr-51 6.860%

Cs-137 2.689% Mn-54 5.000%

Zn-65 2.249% Zn-65 3.030%

Sr-89 1.773% Sr-89 2.860%

Cs-134 1.671% Cs-137 2.420%

Co-58 1.102% Co-58 1.270%

Sr-90 0.924% Fe-59 0.680%

Ni-63 0.432% Sr-90 0.020%

Ba/La Pu-238 0.000%

-140 0.220% Pu-Cr-51 0.201% _239/40 0.000%

Nb-95 0.085% Cm-242 0.000%

Ce-144 0.053% Cm-H-3 0.040% 243/44 0.000%

I-131 0.000%

Pu-238 0.000%

Pu-

, 239/40 0.000%

Cm-242 0.000%

Pu-241 0.000%-

I-129 0.000%

Tc-99 0.000%

Nb-94 0.000%

Ni-59 0.000%

Determined by:- C C. N/A N/A A. measurement B. estimation

' C. measurement /

correlation Type of Strong, Tight Strong, Tight

_ N/A N/A g Container Liners Containers v

Solidification Cement - 2_ Liners None Agent or and N/A N/A Absorbant None - 18 Liners

3. SOLID = WASTE DISPOSITION Number of Shipments Mode of Transportation Destination

_33_ Truck Barnwell, S.C.

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination Zero (0) N/A N/A-28 of 31

_ _ - - _

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