ML19290C148
| ML19290C148 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/26/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8001100149 | |
| Download: ML19290C148 (1) | |
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UNITED STATES CENTRAL FILES NUCLEAR REGULATORY COMMISSION PDR:HQ y
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611 RY AN PLAZA DRIVE, SUITE 1000
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'o, NSIC November 26, 1979 Docket Nos.
50-313 50-368 Arkansas Power and Light Company ATTN:
Mr. William Cavanaugh III Vice President of Generation and Construction P. O. Box 551 Little Rock, Arkansas 72203 Gentlemen:
The enclosed IE Circular No. 79-24 is forwarded to you for information.
No written response is required.
Should you have any questions related to your-understanding of the reco==endations on this matter, please contact this office.
Sincerely, r1 V. Seyfrit Director
Enclosures:
1.
IE Circular No. 73-24 2.
List of Recently Issued IE Circulars James P. O'Hanlon, Plant Manager cc:
Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 1726 314 Q
8001100 ;qg
Accession No: 7910250492 SSINS No. 6830 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Circular No. 79-24 Date: November 26, 1979 Page 1 of 3 PRO?ER INSTALLATION AND CALIBRATION OF CORE SPRAY PIPE BREAK DETECTION EQUIPMENT ON BWRs Description of Circumstances:
During 1976 the Iowa Elcetric 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 negative 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 connectio..
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. With a break in CS piping in the annulus area the instrument then senses the additional pressure drop across the separators (dp % 7 psi additional) 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 alarm 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 hot conditi was determined to be about 3.5 psid fo discussed below.
DUPLICATE DOCUMENT Entire document previously entered into system under:
1726 515 ANo W/6KdN No. of pages:
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