RBG-24889, Addendum to Semiannual Radioactive Effluent Release Rept Jan-June 1986

Addendum to Semiannual Radioactive Effluent Release Rept Jan-June 1986

ML20215E184
Person / Time
Site:	River Bend
Issue date:	06/30/1986
From:	Booker J, Cargill E, Fantacci C GULF STATES UTILITIES CO.
To:	Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
RBG-24889, NUDOCS 8612170375
Download: ML20215E184 (7)

Text

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RIVIR BBW SmrIW - TERT I SBUJWBERL RADIOETIVE EFF11ENE REtJINiB REFGtt AEIMBERM REPORP PERICD: JANUARY 1,1986 'HIROUGH JUNE 30, 1986 PREPARED BY: _ g/V/-,

C. L. Fantacci, Radiological Engineering Supervisor APPROVED BY: ///// /

E. M. Cargill, JitIperviThr-Radiological Programs 1k) 8MS*IEcA R

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BEIRISERL IUIDI(ECTIVE EFFIAMff REIBM IWGtr puumawat FACILITY: River Bend Station - Unit I LICi:NSEE: Gulf States Utilities Ccmpany

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REPORT PERIOD: January 1, 1986 through June 30, 1986 This addendum is subnitted under River Bend Station (RBS) License Ntmber NPF-47 and provides information that was not available when the Quarter 1/2 1986 RBS \

Seniannual Radioactive Effluent Releaso Report was being ccmpiled. Specifically, this addendum provides information on updates of percent of Technical Specification limits sunination of all gaseous releases (page 15, item C.3) and Sr-89 and Sr-90 Gaseous Effluent Releases (pages 18 and 21 of the original report); and Sr-89, Sr-90 and Fe-55 Liquid Effluent Releases (page 25 and 26 of the original report) obtained frun vendor-performed analysis of quarterly ccmposite sanples. It should be noted that an entry of "0.00 +

00" Ci in the following tables does not represent the absence of a radionuclide; but, rather indicates that the concentration of a particular radienuclide was below the lower Limit of Detection (LID) .

m3N Efflussit and Waste Disposal Saniannual Report 1986 Year Camerus Effluents - Stagnation of all releases 1/2 Quarters Est.

Unit Quarter 1 Quarter 2 Total Error %

C. Particulates

3. Percent of Technical Specification Limit (2)  % N/A 1.28E-03 (2) Organ done limit of 7.5 mrans/qtr. (T.S. 3.11.2.3.a) .

' DELE 4 ADDENXM Effluent and Waste Disposal Saniannual Report 1986 Year Gaseous Effluents - Conditionally Elevated Peleases 1/2 Quarters Continuous Mode Batch Pode Nuclides Released Unit Quarter 1 Ouarter 2 Ouarter 1 Ouarter 2

3. Particulates Strontium-89 Ci N/A 2.18 E-06 N/A 4.82 E-08 Strontium-90 Ci N/A 0.00 E 00(2) N/A 0.00 E 00(2)

Total for Period Ci N/A 2.18 E-06 N/A 4.82 E-08 (2) Quarterly cmposite particulate filter analysis indicates a Mininum Detectable Activity (MDA) concentration of <7.0 E-16 tCi/cc for the Main Plant Ddiaust Duct. This value is less than the Iower Limit of Detection (IJD) of 1 x 10~II uCi/ml as upecified in table 4.11.2.1.2-1 of Ims Technical Specifications.

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. e TMEE 5 ADDEMIM Effluent and Waste Disposal Saniannual Report 1986 Year Gaseous Effluents - Ground IcVel Beleases 1/2 Quarters Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Ouarter 2 Ouarter 1 Ouarter 2

3. Particulates Strontium-89 Ci N/A 5.89 E-07 N/A 0.00 E 00 Strontium-90 Ci N/A 0.00 E 00(2) N/A 0.00 E 00 Total for Period Ci N/A 1.97 E-05 N/A 0.00 E 00 (2) Quarterly cmposite particulate filter analysis indicates a Mininun Detectable Activity (MDA) concentration of <5 E-16 uCi/cc for the Fuel Building Exhaust Vent and the 141dwaste Building Exhaust Vent. This value is less than the Iower Limit

-1I of Detection (LID) of 1 x 10 uCi/ml as specified in table 4.11.2.1.2-1 of PBS Technical Specifications.

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Effluent and Waste Disposal Seniannual Report '1986 Year G. Liquid Effluents 1/2 Quarters Nuclides Relaa==d Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Strontitan-89 Ci N/A N/A N/A 0.00 E 00(2)

Strcetian-90 Ci N/A N/A N/A 6.41 E-05

. Iron-55 Ci N/A N/A N/A 2.71 E-02 Total for Period Ci N/A N/A N/A 1.83 E 00 (2) Analysis of quarterly caposite indicates a Nin 4 == Detectable Activity (M[R) concentration of <2.0 E-09 uCi/ml. 'Ihis value is less than the Imer Limit of Detection (LID) of 5 x 10 -8 uC1/mi as specified in Table 4.11.1.1.1-1 of RBS Technical Specifications.

t_.-________--_-______----

s o GULF STATES UTELETIES COMPANY Rivf R SEND STAflON POST OFFICE BOX 220 57 FRA SCISVILLE. LOUIStANA 70775 AREA COCE 604 635 6094 "A6 865 6 Decemberyl, 1986 ~

RBC- 240d9 File Nos. G9.5, G9.25.1.5 Mr. Robert D. Martin, Regional Administrator U.S. Nuclear Regulatory Commission 1

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Region IV )

611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 g 5m

Dear Mr. Martin:

River Bend Station - Unit 1 Docket No. 50-458 Enclosed is the Addendum to the Semiannual Radioactive Effluent Release Report for the period of January 1, 1986 to June 30, 1986 submitted to you previously~ (ref. RBG-24299 dated August 28, 1986). This Addendum provides information on Sr-89, Sr-90 and Fe-55 releases which 'was not available at the time that the Semiannual Radioactive Effluent Release Report war being compiled. This Addendum is being submitted in accordance with Technical Specification 6.9.1.8 of - Appendix A to River Bend Station (RBS) License Number NPF-47.

Sincerely,

, f hYd/

J. E. Booker Manager-River Bend Oversight i

River Bend Nuclea'r Group JEB/ ERG / je Enclosure l

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