ML19253C642
| ML19253C642 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/26/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Hancock J FLORIDA POWER CORP. |
| References | |
| NUDOCS 7912060614 | |
| Download: ML19253C642 (1) | |
Text
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UNITED STATES o,,
NUCLEAR REGULATORY COMMISSION 3
{
M).. o.E REGION ll
! d'f'[f 101 MARIETTA ST., N.W., SulTE 3100 o
Q4 ATLANTA, GEORGIA 30303 NOV 2 61979 In Reply Refer To:
RII:JPO Florida Power Corporation Attn:
J. A. Hancock, Director Nuclear Operations P. O. Box 14042, Mail Stop C-4 St. Petersburg, Florida 33733 Gentlemen:
The enclosed 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 recommendations on this matter, please contact this office.
Sincerely,
/
a o
f James P. O' e111 Director
Enclosures:
1.
IE Circular No. 79-24 2.
List of IE Circulars Issued in the Last Eix Months i 540 065 7 912060
NOV 2 61979 Florida Power Corporation,
cc w/ encl:
G. P. Beatty, Jr.
Nuclear Plant Superintendent Post Office Box 1240 Crystal River, Florida 32629 1540 066
Accession No: 7910250492 SSINS No. 6830 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 November 26, 1979 IE Circular No. 79-24 PROPER INSTALLATION AND CALIBRATION OF CORE SPRAY PIPE BREAK DETECTION EQUIPMENT ON BWRs Description of Circumstances:
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 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 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. With a break in CS piping in the annulus area the instrument then senses the additional pressure drop across the separators (dp g 7 psi additional) and dryers (dp g 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 conditions. The magnitude of this dp was determined to be about 3.5 psid following completion of the modification discussed below.
1540 067 DUPLICATE DOCUMENT Entire document previously entered into system under:
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