ML20082F901

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Addendum to River Bend Station Unit 1 Semiannual Radioactive Effluent Release Rept,Jul-Dec 1990
ML20082F901
Person / Time
Site: River Bend Entergy icon.png
Issue date: 12/31/1990
From: Cargill E, Fantacci C
GULF STATES UTILITIES CO.
To:
Shared Package
ML20082F898 List:
References
NUDOCS 9108160110
Download: ML20082F901 (8)
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Text

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4 RIVER BEND STATION - UNIT I SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT ADDENDUM

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REPORT PERIOD: JULY 1, 1990 THROUGH DECEMBER 31, 1990 I

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PREPARED BY: -h C L. Fantacci, Radiological Er:gir:eering Stfer~v'lYoV L .. . . - .

APPROVED BY: ['[ M /b b/

E. K. Cargill(Director-Radiologrcpl Programs

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! o108160110 91080?

PDR ADOCK 05000458 R PDR

T SEMIANNUAL RAD 10AC11VE EFFLUENT RELEASE REPORT ADDENDUM FAClllTY: River Bend Station - Unit 1 LICENSEE: Gulf States Utilities Company REPORT PERIOD: July 1, 1990 through December 31, 1990 l

This addendum is submitted under River Bend Station (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 1990 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 items C.1 -  !

C.3, page 14 (3) Table 4 Gaseous Effluents - Conditionally Elevated Releases. Jtem 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 Ef fluents - Summation of all Release: Item G, pages 24 and 25 An entry of "O,00E+00" Ci in the following tables indicates that the concentration of a particular radionuclide was below the Lower Limit of Detection (LLD).

RADIOLOGICAL IMPACT ON MAN 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 accordance with the ODCM was <l.0 mrem.

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I GASEOUS EFFLUENTS Fourth quarter gaseous doses were calculated using 3rd quarter composite date 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.

Therefore, no recalculation of fourth quarter doses was performed.

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 (<l.01) of the previously reported organ doses from particulates. Therefore, no recalculation of fourth quarter doses was performed.

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d TABLE 3 ADDENDUM Effluent and Waste Disposal Semi-Annual Report 1990 Year Gaseous Effluents - Sumation of All Releases 3/Tl)iiarters

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j l . l l l Est. Total l l__ l Unit jouarty 3l Quarter 4 l Error, i l C. Particulates l 1. Particulates witY half- l l l l l lives c,f >8 days l Ci j PR l 1.04E-03 ' 1.86E401 j j 2. Average release rate I -l l l 1.31E-04 '

l for period luCi/sec l PR l

! 3. Percent of technical l 1  ! i-l specification limit  !  % l PR l 9.47E-02 l l 4. Gross alpha l l l l l radioactivity _ __, l Ci j. PR l PR j PR - Previously Reported e - - , - , ,, .

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i l TABLE 4 ADDENDUM Effluent and Waste Disposal Semiannual Report 1990 Year Gascous Effluents - Conditionally llevated Releases 3/4 Quarters Continuous Mode Batch Mode l l  ! l l Nuclides Released i Unit l Quarter 3 l Quarter 4 __L Quarter 3 l Quarter 4 *?

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3. Particulates

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1 I i l I t i f 4 4 Strontium-89 l Ci l PR l 5.56E-04 l N/A l N/A l l  !  !  !

Strontium-90 l Ci l PR l 2.97f-08 l N/A l N/A i i i r i i t  ! t 1 Total for Period l Ci l PR l 1.03E-03 l N/A ,_ l N/A PR - Previously Poported

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TABLE 5 ADDENDUM l Effluent and Waste Disposal Semiannual Report 1990 Year Gaseous Effluents - Ground Level Releases 3/4 Quarters Continuous t' ode Batch l' ode i i i i j

Nuclides Released , Unit  ! Quarter 3 l Quarter 4 l_ Quarter 3  ! Quarter 4 3.- Particulates I

l l l l l Strontium-89 l Ci l PR l 9.65E-06  ! N/A l N/A

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-Strontium-90 l Ci l PR  ! 1.03E-06 l N/A I -N/A l 1 l l 1 i Total for Period l Ci  ! PR. l 1.07E-05 l N/A l N/A  :

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-PR - Previously Reported

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TABLE 6 ADDENDUM Effluent and Waste Disposal Semi-Annual Report 1990 Year Liquid Effluents - Summation of All Releases 3/4 Quarters

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! l l l l Est. Total l l l Unit l Quarter 3i Quarter 4 l Error, % __,j A. Fission and activation products l 1. Total release (not in- l  !  ! l l l cluding, tritium, gases,l Ci l PR l 1.72E-01 l 1.42E401 l l a1pha l

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l  ! l l l 2. Average diluted concen- l l l l

-! tration during period juCi/ml l PR l 1.59E-07  !

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c l 3. Percent of applicable l l l l l limit (1)l  % l PR l 1.375E+01 l

, PR - Previously Reported 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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I TABLE 6 ADDENDUM Effluent and Waste Disposal Semiannual Report J_990 Year G. Liquid Effluent 3/4 Quarters t

Continuous l' ode Batch Mode i l l  !  ! l l

Nuclides Released l Unit j Quarter 3 l Ouarter 4 l Quarter 3 l Quarter 4 I l I I i l Strontium-89 l Ci l N/A l N/A l PR l 3.10E-04 i l l l l l l Strontium-90 l Ci l N/A l_ N/A l PR li 8.36E-05 i ~l i I l 1 ( l (

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Iron-55 l Ci l N/A l N/A l PR l ,?.66E-02 l I l l l i l

I Total For Period l Ci l N/A l N/A l PR l 1.72E-01 l

PR - Previously Peported 1 l

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