ML20043D546

Addendum to River Bend Station - Unit 1 Semiannual Radioactive Effluent Release Rept,Jul-Dec 1989.

ML20043D546
Person / Time
Site:	River Bend
Issue date:	12/31/1989
From:	Cargill E, Fantacci C GULF STATES UTILITIES CO.
To:
Shared Package
ML20043D543	List: ML20043D542 ML20043D546
References
NUDOCS 9006080210
Download: ML20043D546 (7)

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! . L RIbiR BEND STATION - UNIT I

• SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM REPORT PERIOD: JULY 1, 1989 THROUGH DECEMBER 31, 1989 PREPARED BY: ~

h'd!d ' > N t'.T~ TMtacci, Radiological Eng'ineeritig' Supervisor APPROVED BY: //d6

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E. M. 'Cargill . Director'Ridiological Programs t

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- - SEMIANNUAL RADIDACTIVE EFFLUENT F

. RELEASE REPORT ADDENDUM FACILITY: River Bend Station - Unit I LICENSEE: Gulf States Utilities Company REPORT PERIOD: July 1, 1989 through December 31, 1989 This addendum is submitted under River BendStation(RBS) License Number NPF-47. It provides information obtained from vendor-performed analysis of quarterly composite samples that was not available when the Quarter 3/4 1989 RBS Semiannual Radioactive Effluent Release Report was being compiled. Updates are provided for the following:

l (1) Section VI - Radiological Impact on Man. Page 10 (2) . Table 3 Gaseous Effluents - Summation of all Releases itemr C.1 -

C.3, page 15 (3) Table 4 Gaseous Effluents - Conditionally Elevated Releases. Item ,

3, page 18 (4) Table 5 Gaseous Effluents - Ground Level Releases item 3, page 21 (5) Table 6 Liquid Effluents - Summation of all Releases Items A.1 -

A.3, page 23 (6) Table 6 Liquid Effluents - Summation of all Releases Item G, pages L 25 and 26 An entry of "0.00E+00" Ci in the following tables indicates that the concet.tration of a particular radionuclide was below the Lower Limit of Detection (LLD).

RADIOLOGICAL IMPACT ON Mall The total body, skin, thyroid and other organ doses to a member of the public from the uranium fuel cycle (40 CFR 190 compliance) calculated  !

in accordanen with the ODCM was <1.0 mrem.

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

LIQUID EFFLUENTS .

Fourth quarter liquid doses were calculated using 3rd quarter composite l data for Fe-55. Composite results for fourth quarter Fe-55 were less i than the 3rd quarter results. Therefore, doses reported for the 4th  ;

quarter are more conservative.

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TABLE 3 ADDENDUM -

Effluent end Waste Disporal Semi-Annual Report 1989 Year f Gaseous Effluents - Summation of All Releases 3/FQEarters

~ ~ ~ ~

, Est. Total Unit Quarter 3 Quarter 4 Error, %

• i i C. Particulates F^

1. Particulates witTYall! l lives of >8 days Ci PR 1.24E-05 1.86E+01

2. Average release rate l for period uC1/sec PR 1.57E-06

3. Percent of technT6 T~~

specification limit  % PR 1.11E-01

'l . Gross alpha radioactivity __J Ci PR PR ,

PR - Previously Reported L

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. s TABLE 4 ADDENDUM Effluent and Waste Disposal Semiannual Report 1989 Year ,

! Gaseous Effluents - Conditionally Elevated Releases 3/4 Quarters Continuous Mode Batch Mode  ;

. _ _ _ _ _ = - . .

_ 3 __--

Nuclides Released l Unit-  ! Quarter 3  ! Quarter 4 Quarter 3 l Quarter 4 3.- Particulates

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q.. ; ,

I Strontium-89 Ci PR 6.54E-06 N/A N/A iStrontium-90  ! Ci l PR 0.00E+00(1) 1 N/A N/A y -

i e i Total for Period l Ci PR 1.12E-05 l N/A  ! N/A

'PR - Previously Reported (1) Quarterly composite particulate filter analysis indicates a Minimum Detectable. Activity (MDA) concentration of <2.0 E-16 uCi/cc for the Main Plant Exhaust Duct. This value is less than the' Lower Limit of Detection (LLD) of 1.0 E-11 uCi/mi as specified in table 4.11.2.1.2-1ofRBS!

Technical Specifications. ,

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TABLE 5 ADDENDUM

! Effluent and Waste Disposal Semiannual ~ Report 1989 Year l Gaseous Effluents - Ground Level Releases 3/4 QUirters Continuous Mode Batch Mode Nuclides Released l Unit Quarter 3 1 Quarter 4 ,uarter Q 3 l Quarter 4

3. Particulates i

! Strontium-89 Ci j PR 3.65E-07 N/A N/A

! 0.00E+00 I1)

Strontium-90__  ! Ci PR N/A N/A Total for Period Ci PR I 1.16E-06 l N/A l N/A PR - Previously Reported

'(1) Quarterly composite particulate filter analysis indicates a Minimum Detectable Activity (MDA)i concentration of <3.0 E-16 uCi/cc for the Fuel Building Exhaust Vent and the Radwaste Building l Exhaust Vent.. This value is less than the Lower Limit of Detection (LLD) of 1.0 E-11 uCi/mi as specified in table 4.11.2.1.2-1 of RBS Technical Specifications.

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TABLE 6 ADDENDUM Effluent and Waste Disposal Semi-Annual Report 1989 Year Liquid Effluents - Sunnation of All Releases 3/4 Quarters

_ _ _ _ _ . . . . . _ _ _ _  ! Unit Quarter 3 r Quarter 4 l Error, % l l A. Fission and activation products '

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l. TotaT'r~enis~e'Tnot in- ,

l [~ ~ j l l ciuding tritium, gases. Ci l PR l 1.90E-01 1.42E401 c1pha ___ _

2. Average diluted concen-tration during period uti/mi PR 1.53E-07 l

3. Percent of applicable l limit (1).  % PR ,

1.52E+01 l l

(1) One quarter of 5 Ci annual limit (1.25 Ci) for liquid releases except for tritium or entrained noble gases from 10CFR50 Appendix 1.

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r TABLE 6 ADDENDUM E

Lffluent and Waste Disposal Semiannual Report 1989 Year

G. Liquid Effluent 3]J Quarters s

j Continuous Mode Batch Mode i I I i 1 Nuclides Released l Unit i Quarter 3 l Quarter 4 l Quarter 3 l Quarter 4

( Strontium-89 Ci N/A N/A_._ PR 0.00E+00(1) i I i I L I Strontium-90  ! Ci  ! N/A l N/A PR !0.00E+00II)

= . l Ci l l i '

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[ 1ron-55 _ l N/A  ; _3' A PR l.84E-03,

_ i i i i 1 Total For Period '

l Ci l N/A l N/A PR l 6.84 a

< PR - Previously Reported

=

(1) Analysis of quarterly composite indicetes a M!nimum Detectable

Activity (MDAi concentration of <9.0 E-09 uCi/ml for Sr-69 and

<3.0 E-09 uCi/ml for Sr-90. These values are less than the Lower Limi+ of Detection (LLD) of 5.0 E-8 uCi/ml as specified in Table 4.11.1,1,1-1 of RBS Technical Specifications.

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