ML19260B975

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Forwards IE Circular 79-24, Proper Installation & Calibr of Core Spray Pipe Break Detection Equipment on Bwrs. No Written Response Required
ML19260B975
Person / Time
Site: Waterford Entergy icon.png
Issue date: 11/26/1979
From: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Aswell D
LOUISIANA POWER & LIGHT CO.
References
NUDOCS 7912180055
Download: ML19260B975 (1)


Text

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NUCLEAR REGULATORY COMMISSION 3%

REGION IV E I ff'I o

611 RYAN PLAZA DRIVE, SUITE 1000

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ARLINGTON, TEXAS 76012 November 26, 1979 In Reply Refer To:

RIV Docket No.

50 382/IE Circular No. 79-24 Louisiana Power and Light Co.

ATTN:

Mr. D. L. Aswell Vice President of Power Production 142 D21aronde Street New Orleans, Louisiana 70174 Gentlemen:

The enclosed IE Circular No. 79-24 is forwarded to you for inforraation. No written response is required.

Should you have any questions related to your understanding of the reco=mendations on this matter, please contact this office.

Sincerely,

(

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' Karl V. Seyfrit /

Director

Enclosures:

1.

IE Circular No. 79-24 2.

List of Recently Issued IE Circulars

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1600 086 Q

7912180

Accession No: 7910250492 SSINS No. 6830 UNITED STATES NUCLEAR REGULATORY CO>D11SSION OFFICE OF INSPECTION AND ENFORCDIENT WASilINGTON, D.C.

20555 IE Circular No. 79-24 Date: November 26, 1979 Page 1 of 3 PROPER INSTALLATION AND CALIBRATION OF CORE SPRAY PIPE BREAK DETECTION EQUIPMENT ON BWRs Description of Circunstances:

During 1976 the Iowa Electric Light and Power Company identified and corrected a potential problem involving the Core Spray (CS) pipe break detection system at the Duane Arnold Energy Center (DAEC). The problem relates to the setpoint, function, and installation of the differential pressure (dp) instrument which monitors for a CS pipe break that is located in the annulus area of the reactor vessel (i.e., located outside the core shroud but inside the reactor vessel).

The installed instrument, range of 0 - 24 psid, was found deflecting downscale (i.e., reading negar.ive psid) during operation.

The licensee's investigation of the downscale deflection revealed that the original piping arrangement and calibration did not adequately take into account the effect of density changes of the water in the pressure leg connections.

The original installation had the high pressure side of the dp instrument (see attached Figure 1) connected to the reference leg in the vessel (Figure 1 Connection X) and the low pressure side to the core spray piping outside the vessel but inside the drywell (Figure 1 Connection Y).

With the piping intact, this arrangement senses the pressure difference between bottom and top of core. Wi,th a break in CS piping in the annulus area the instrument then senses the additional pressure drop across the separators (dp N 7 psi addicional) and dryers (dp % 7 inches water).

This installation was in accordance with GE. design requirements.

Also in accordance with GE instructions the calibration of the dp instrument was performed with the reactor in the cold condition and the alarn was set to trip at 5 psid increasing. Because of this cold calibration the dp instrument then indicated full downscale negative during operation.

This negative dp was due to the heat up of the reference leg (Figure 1 Connection X) which caused the fluid density to decrease as the plant reached e

a -ha^

c m-was determined to be about 3.5 psid foll

'4WD b'm discussed below.

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ANO 16M 087 No. of pages:

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