ML20045E030

Addendum to Semiannual Radioactive Effluent Release Rept for Jul-Dec 1992.

ML20045E030
Person / Time
Site:	River Bend
Issue date:	12/31/1992
From:	GULF STATES UTILITIES CO.
To:
Shared Package
ML20045E029	List: ML20045E028 ML20045E030 ML20045E031
References
NUDOCS 9307010006
Download: ML20045E030 (10)

Text

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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM FACILITY: River Bend Station, Unit 1 LICENSEE: Gulf States Utilities REPORT PERIOD: July 1, 1992 Through December 31, 1992 Enclosed is the Semiannual Radioactive Effluent Release Report Addendum.for the period of July 1, 1992. through December 31, 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. Included is the information obtained from vendor-performed analysis of fourth quarter composite samples that was not available when the Quarter 3/4 RBS Semiannual Radioactive Effluent Release Report was being compiled. Ammendments to the 1/2 Quarters are also included. Updates are being provided for the following:

(1) Section VI - Radiological Impact on Man, Page 10.

(2) Table 3 Gaseous Effluents - Summation of all Releases; Items C.1 -C.3, page 14.

(3) Table 4 Gaseous Effluents - Conditionally Elevated Releases; Item 3, page 17.

(4) Table 5 Gaseous Effluents - Ground Level Releases; Item 3, page 20.

(5) Table 6 Liquid Effluents - Summation of all Releases; Items A.1 - A.3, page 22.

(6) Table 6 Liquid Effluents - Volume of Dilution; Item F, page 23.

(7) Table 6 Liquid Effluents - Summation of all Releases; Item G, pages 24 and 25.

(8) Table 6 Liquid Effluents - Summation of all Releases; Item G, pages 24 and 25, (Zn-65 typo), (1/2) Quarter Semi-Annual Report. These pages supersede the original 1st half submittal.

The revision to the Offsite Dose Calculation Manual (ODCM)

Procedure is attached for the same period, in accordance with River' ,

Bend Technical Specification 6.14.

An entry of "0.00e+0'0" Ci in the following tables indicates that the activity of a particular radionuclide was below the Lower Limit of Detection (LLD). .

9307010006 930624 I's PDR ADDCK 05000458 3 R PDR Q)

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RADIOLOGICAL IMPACT ON MAN The total body, skin, thyroid, and other organ doses to a member of -

the public from the uranium fuel cycle (40CFR190, ~ compliance) calculated-in accordance with the ODCM was < 1.0 mrem.

GASEOUS EFFLUENTS 5 Fourth quarter ' gaseous doses were calculated ' using . 3rd' quarter composite data for Sr-89 and Sr-90. Fourth quarter.Sr-89 and Sr-90 composite results were found to give an -increase less than one-percent (< 1.0 %) of the previously reported organ . doses from- '

particulates.

LIQUID' EFFLUENTS Fourth quarter liquid doses were calculated using 3rd quarter composite' data for Fe-55, Sr-89, and Sr-90. Fourth . quarter composite results were found to give an increase less .than one percent _ (<1. 0 %) of the previously report.ed organ doses from particulates.

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TABLE 3 ADDElmUM Effluent and. Waste Disposal Semi-Annual Report 1992 Year Gaseous Effluents - Summation of All Releases 3/4 Quarters

• Unit Quarter 3 -Quarter 4 Estimated Total Error % l-9 C. Particulates

1. Particulates with Ci PR 1.03E-04 1.86E+01 half lives of >8 days ,

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2. Average release uCi/sec PR 1.31E-05 jj"j,.g rate for period

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3. Percent of-  % PR 4.67E-02 '

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specification ~ ?? egg?^ 'sjs limit -

' #G PR - Previously Reported i

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l TABLE 4 - ADDENDUM EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT 1992 YEAR GASEOUS EFFLUENTS - CONDITIONALLY ELEVATED RELEASES 3/4 QUARTERS CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4

3. Particulates Strontium-89 Ci PR 4.93E-05 N/A N/A Strontium-90 Ci PR 4.93e-07 N/A N/A Total for Period Ci PR 1.01e-04 N/A N/A PR - Previously Reported NOTE: Main Plant Exhaust Duct is considered a conditionally elevated release point.

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TABLE 5 - ADDENDUM EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT 1992 YEAR GASEOUS EFFLUENTS - GROUND LEVEL RELEASES 3/4 QUARTERS Continuous Mode Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter'4

-3. Particulates Strontium-89 Ci PR 0.00E+00 N/A N/A Strontium-90 Ci PR 4.51E-08 N/A N/A Total for Period Ci PR 1.13E-04 N/A N/A PR - Previously Reported NOTE: Fuel Building Exhaust Vent and Radwaste Building Exhaust Vent are considered ground level release points.

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

SUMMATION OF ALL RELEASES Unit Quarter 3 Quarter 4 Est.

Total Error %

A. Fission and activation products ,

1. Total release (not including Ci PR 3.46E-01 1.42E+01 tritium, gases, alpha) ,

2. Average diluted concentration uCi/ml PR' 3.56E-07 during period -

3. Percent of applicable limit  % PR 2.77E+01 '< i PR.- Previously Reported 6

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TABLE 6 - ADDENDUM EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT 1992 YEAR LIQUID EFFLUENTS 3/4 QUARTERS

-F. Volume of dilution water E r .

Unit Quarter 3 Quarter 4 Est. Total Error's ,

. Liters 1.19E+09* PR PR-o This corrects a typographical error from the previous submittal

'PR - Previously Reported T

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I TABLE 6 ADDENDUM EFFLUENT AND WASTE DIFPOSAL SEMI-ANNUAL RENRT 1992 YEAR LIQUID EFFLUENTS 3/4 OUAETERS l

G. Particulates I Continuous Mode Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Strontium-89 Ci N/A N/A PR 0.00E+00 Strontium-90 Ci N/A N/A PR 1.92E-05 Iron-55 Ci N/A N/A PR 5.61E-02 P

Total for Period Ci N/A N/A PR 3.47E+00 PR - Previously Reported b

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i TABLE 6 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT 1992 YEAR LIQUID EFFLUENTS 1/2 QUARTERS G. Particulates Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Hydrogen-3 Ci N/A N/A 8.62E+00 8.55E+00 Arsenic-76 Ci N/A N/A 1.23E-04 3.70E-06 Strontium-89 Ci N/A N/A 2.34E-05 0.00E+00 Strontium-90 Ci N/A N/A 5.97E-04 0.00E+00 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 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-04 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 Iron-55 Ci N/A N/A 8.82E-04 1.76E-02 Iron-59 Ci N/A N/A 9.33E-03 1.39E-03 Zinc-65* Ci N/A N/A 4.41E-03 3.75E-03 Manganese-54 Ci N/A N/A 4.38E-02 1.65E-02 Manganeae-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' l N/A 2.11E-03 0.00E+00

• Corrected 2n-65

TABLE 6 Continuous Mode Batch Mode

-Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 ' Quarter 2-Technicium-99m Ci N/A N/A- 8.90E-04 9.07E Barium-140 Ci N/A. N/A 6.86E-04 0.00E+00 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 Cerium-144 Ci N/A N/A 3.13E-04 1.51E-04 Antimony-122 Ci N/A N/A 1.06E-05 0.00E+00 Antimony-124 Ci N/A N/A 2.96E-03 8.04E-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+00 Yttrium-91m Ci N/A N/A 6.34E-05 O.00E+00 Yttrium-92 Ci N/A N/A 1.87E-03 0.00E+00 -l 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 Total For Period Ci N/A N/A 8.92E+00 8.70E+00 1

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