RBG-37649, Addendum Semiannual Radioactive Effluent Release Rept for 920101 Through 920630

Addendum Semiannual Radioactive Effluent Release Rept for 920101 Through 920630

ML20116C156
Person / Time
Site:	River Bend
Issue date:	06/30/1992
From:	Odell W GULF POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RBG-37649, NUDOCS 9211030233
Download: ML20116C156 (8)

Text

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. . i c 4; GULF S2VATX2S UTILITEX2S COMIVA NY ~ '

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October 28, 1992 RBG-37640 .

File Nos. G9.5 G9.25.1.5  :

U.S. Nuclear Regulatory Commission Document Control Desk l

Washington, D.C. 20555 ,

Gentlemen:

River Bend Station - Unit 1 Docket No. 50-458 l

i Enclosed is the Addendum to the Semiannual Radioactive -

( Effluent Release Report for the period.of January 1 to June 30, 1992, submitted to you previously (reference '

l RBG 37420 dated August 31, 1992). This addendum provides information which was not available at the time that the Semiannual Radioactive Effluent Release Report was compiled. This Addendum is submitted in accordance with Technical Specification 6.9'.1.8 of Appendix A.to' River

( Bend Station (RBS) License Nomber NPF-47.

Sincerely, ,

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.H. Odell 1 Manager-Oversight i River Bend Nuclear Group h,$b Nhh LA DNL C/KDG/kvm Enclosure cc U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NPi Resident Inspector P.O. Box 1051 St. Francisville, LA 70775 03013v -

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ADDENDUM SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE RRORT REPORT PERIOD: January 1, 1992 through June 30, 1992 j -

._. m Reviewed By h- _,6 C k 6 _ er- '

C. L '. Fnntacci, Radiological Supervisor '

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Approved By 2 4 6 d ,-> N- W b ' _ ._,

E. M. Carg 1, Director - Radiological Programs.

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RIVER HEND STATION, UNIT 1 SEhllANNUAL RADIOACTIVE EITLUENT i RELEASE REPORT ADDENDUAf 1 i

l FACILITY: River Bend Station, Unit 1 LICENSEE: Gulf States Utiliths REPORT PERIOD: January 1,1992 Through June 30,1992 I

Enclosed is the Semlannual Radioactive Effluent Release Report Addendum for the period of January 1,1992 through June 30,1992. This report is suinnitted in accordance with Technical - j Specification 6.9.1.8 of Appendix A to River Bend Station (RBS) License Number NPF-47. j Included is the information obtained from vendor-perfonned analysis of second quarter '

composite samples that was not available when the Quarter 1/2 RBS Semlannual Radioactive Effluent Release Report was being compiled. Updates are being provided for the following: l q

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

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

I

- (3) Table 5 Gaseous Ef0uents - Ground Level Releases; Item 3, page 20.  ;

- (4) Table 6 Liquid Ef0uents - Summation of all Releases; Items.A.1 - A.3, page 22.

L - (5) Table 6 Liquid Ef0uents - Summation of all Releases; Item G, pages 24 and 25.

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An entry of "0.00c+00" Cl in the following tables indicates that the activity of a particular radionuclide was below the Lower Limit of Detection (LLD).

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i TAlli,E 3 - ADDENDUM Effluent and Waste Disposal Serni Annual Report 1222 Year Gaseous Effluents - Sumination 01 All Releases 112 Quarters Unit Quarter ! Quarter 2 Estimated -

Total Error %

C. Particulates 1.Particulates with Ci PR 1 J 5E-05 1.86E+ 01 half lives of > 8 days

2. Average release uCi/sec PR 1.46E-06 mte for period

3. Percent of  % PR 3.16E-03 technical specification limit i PR - Previously Reported 2 of 6

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4 TAllLE 4 - ADDENDUA!

EITLUENT AND WASTE DISPOSAL SEA 11-ANNUAL REPORT 1292 YEAR GASEOUS EFFLUENTS - CONDITIONALLY ELEVATED RELEASES lil QUARTERS CONTINUOUS NIODE IIATCll AIODE Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 3, Particulates Strontium-89 Ci PR 0.00E+ 00 N/A N/A Strontium 90 Ci PR 3.49E-07 N/A N/A Total for Perimi Ci PR 3.49E-07 N/A N/A PR - Previously Reported

.NQJE; hiain Plant Exhaust Duct is considered a conditionally elevated tricase point.

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4 TAllLE !- ADDENDUM EFFLUENT AND WASTE DISMEAL SEMI-ANNUAL REPOltT 1992 YEAR GASEOUS EFFLUENTS - GROUND LEVEL RELEASES IL2 QUARTERS v

Continuous Mode Itatch Mode 5

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Nuclides Released Unit Qua.rter i Quarter 2 Quarter ! Quaner 2

3. Particulates

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Strontium-89 Ci PR 0.00E+00 N/A N/A Strontium-90 Ci PR 2.68E-08 N/A Nia Total for Period Ci PR __

L12E-05 N/A N/A h PR - Previously Reponed KOIfa 1 uel Building Exhaust Vent and Radwaste Building Exhat s'ent are considered ground level 1 lcase points.

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TAllLE 6 - ADDENDUA1 EFFLUENT AND WASTE DISIOSAl, SEM1-ANNUAL REIORT 1911_2 YEAR LIQUID EFFLUENTS - SUMMATION OF ALL RELi,ASES l_

Unit Quaner 1 Quarter 2 Est. Total Error %

.- ,n A. Fission and activation prcxlucts I. Total release (not including in.:um, gasci, Ci PR 1.59E-01 1.42E+01 alpha)

2. Avenge dileted concentration during period uCi/m) PR I .91 E-07

3. Percent of applicable limit  % PR I .23E+ 01 PR - Previously Reponed l

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5 of 6

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9 TAHLE 6 - ADDENDUM : -

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REM)RT 1292 YEAR. .

LIQUID EFFLUENTS 1/2 QUARTERS -

G. Particulates Continuous Afode Hatch Afode.-

Nuclides Released bnit Quaner 1 Quarter 2 Quarter ! Quarter 2 l

Strontium-89 Ci N/A N/A PR 0.00E+00 -

Strontium-90 Ci N/A N/A PR - 0.00E+00 Iron-55 Ci N/A N/A PR 1.76E-02.

Total for Period Ci N/A N/A PR 9.76E+00 PR - Previously Reported 6 of 6 r

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