ML20059E028

Addendum to, Semiannual Radioactive Effluent Release Rept, Jul-Dec 1989

ML20059E028
Person / Time
Site:	Rancho Seco
Issue date:	12/31/1989
From:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20059E008	List: ML20059E003 ML20059E009 ML20059E014 ML20059E019 ML20059E024 ML20059E028 ML20059E031 ML20059E035
References
NUDOCS 9009100007
Download: ML20059E028 (3)

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RSNGS SEMnANNUAL RADCACTfvE EFFLUENT RELEASE REPORT

.W JANUARY. JUNE 1900 t

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I ADDENDUM CORRECTIONS TO THE JULY TO DECEM'ER 1989 GRERR I

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I 9009100007 900830 PDR ADOCK 05000312 PDC R

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RsNos SEM6 ANNUAL RADioACTNE EFFLUENT REL EASE REPORT JULY DEcEMaERisee E.

UNPLANNED fELEASES This section describes unplanned releases of radioactivky in liquid and gaseous effluent.

I Normally, expected plant evolutions described in the Updated Safety Analysis Report (USAR) which may happen without notice such as Main Steam Safety Relief lifts following a plant trip are considered ' planned

• and will not be discussed Gaseous There were two instances where ventilation samples from the Interim Onsite Storage I

Facliity (IOS) contained radio 6odine. The activity in the sampios was the resun of segregating contaminated trash. The total activity released was 5.60E-06 Curies.

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The resulting organ dose to the critical receptor (infant thyroid) wals 3.62E 3 mrom I

or 0.02 % of the applicable annual limit. Action to prevent reoccurrence will be to evaluate the IOS as a routine discharge pathway as part of the design and modification effort to improve the IOS gaseous effluent radiation monitoring system.

LiQvid A leak of approximately 20 gpd developed on the B RHUT liner and tank resulting in I

a discharge to the sample sump and eventually to the plant offiuent. The leak was stopped by placing absorbent material around the drain. The leal: was estimated to have occurred between 8/13/89 and 8/23/89, The release volume was conservatively estimated to be 4016 gallons based on the RHUT level difference.

I The emount of activty was estimated as:

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?.62Ea8 Ci I

Cs 134 1.20E-Oi Cl Cs 137 7.66E 07 Li The cause of the event was equipment degradation. Action taken to prevent recurrence is to repair the liner and tank.

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RADIOACTIVE EFFLUENT MONfiORING INSTRUMENTATION INOPERABLE FOR I

GREATER THAN 30 DAYS The liquid effluent radiation monitor (R15017A) was out of service from 7/31/89 through the I

end of the reporting period. The monitor was removed from service for repair because electronic noise and grounding problems were causing spurious alarms. The estimated repair completion date is 3/1/90.

Flow Element FE 15044 (for monitor R16044) remained inoperable for the entire reporting period. Flow Element FE 15045 was inoperable from 8/21/89 through the end of the reporting Period. Flow Element FE 15546A was inoperable from 8/25/89 through the end I

of the reporting period. The flow elements remained inoperable because of conthual problems with meeting the acceptance criteria of the quarterly surveillance procedu:9.

The flow elements are a thermal anemometer type and produce inconsistent results due to turbulent flow through the effluent exhaust stacks.

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9 RsNOS SEMANNUAL RAD 60ACTNE FFLUENT RELEASE REW JULY DECEMBER 1900

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TABLE V-A LOM EFFLLENTS SUMMATO4 OF ALL FtEASES Est. Total yn.11 Quarter 3 Quarter 4 Error. %

A. Fission & Activation Products

1. Total Release (not including tritium, gases, alpha)

Ci 5.34 E-04 2.22 E-04 2.3 E + 01

2. Average diluted concentration during period pCL/ml 1.19 E-10 4.95 E-11

3. Percent of applicable limit 1.03 E-03 2.50 E-04 B. Tritium

1. Total Release Cl 1.66 E-02 6.93 E-03 2.3 E + 01

2. Average diluted concentration 1

during period pCl/mi 3.71 E-09 1.54 E-09

3. Percent of applicable limit 1.24 E-04 5.14 E-05 I

C. Dissolved and Entrained Gases (i.e., Noble Gases)

1. Total Release Cl 0.00 E + 00 0.00 E + 00 2.3 E + 01 i

2. Average diluted concentration during period pCl/mi 0.00 E + 00 0.00 E + 00

3. Percent of applicable limit 0.00 E + 00 0.00 E+00 D. Gross Alpha radioactivity 1, Total Release Ci 0.00 E + 00 0.00 E+00 N/A

. 1 E. Volume of waste released Retention Basins (prior to dilution)

Liters 2.84 E + 06 1.37 E+07 5.0 E+00 I

RHUTs (prior to dilution)

Liters 7.91 E + 06 3.86 E + 06 5.0 E + 00 F Volume of dilution water used during period Liters 4.48 E+09 4.49 E+09 1.0 E+01 14 1