ML20079L293

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RO 83-07 (U-2):on 830203,inadvertent Actuation of PORV Occurred.Caused When Operator Mistakenly de-energized Channel D of Reactor Protection Cabinet.Ruptured Disc in Pressurizer Quench Tank Replaced
ML20079L293
Person / Time
Site: Calvert Cliffs Constellation icon.png
Issue date: 02/04/1983
From: Russell L
BALTIMORE GAS & ELECTRIC CO.
To: Haynes R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
RO-83-07-(U-2), RO-83-7-(U-2), NUDOCS 8302230222
Download: ML20079L293 (2)


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e DESIC1!ATED ORIGINAL Cortified By h4[

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e e February 4. 1983 Mr. Ronald C. Haynes, Director Docket No. 50-318 U. S. Nuclear Regulatory Co M asion License No. DPR 69 Resian 1 631 Park Avenue King of Prussia, PA 19406

SUBJECT:

LER 83-07 (U-2) near nr. usynes:

This letter is to confirm our verbal notification of your Mr. Ralph Architsel of an i==Nertent actuation of the power operated relief valves (POEve).

Ifhile in Mode 3 on 2-3-83. testing was in progress on No. 21 inverter in the 1207 vital AC system. Prior to a test transfer of No. 21 l

inverter, the Shift Supervisor directed an Operator to d**n=rgize Chamael A of the Reactor Protective System (RPS) so that the test tremefer would not blow the fuses on Channel A of the RPS.

The Operator mistakenly deemergized Channel D of tbn RFS cabinet.

During the test transfer of No. 21 inverter, the switch haang up, thereby 5--.eizing ^===a1 A of the RPS.

The 2 of 4 coincidence of the presserizer pressure high modulas caused the PORVs to open at about 1803.

After about 25-30 seconds, the Operator overrode the PORVs shut.

Durias the transient. pressurizer pressure decreased to about 1520 psia, thereby initiating SIAS. No water was injected into the Reactor Coolant System by Engineered Safety Features equipment. Pressuriser Pr--a was returned to norest at about 1900. The pressure increase in the Pressurizer Quench Tank caused the rupture disk to openg it has since been replaced.

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8302230222 830204 PDR ADOCK 05000 gd l

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Page 2 Fettruary 4.1983 A complete description of this event and further corrective action will ha provided in a follow-up report.

Y trul yours. W 4e L. B. Russell Plant Superintendent LER:bsb cc J. A. Tiernan E. M. Douglass Director. Office of Management R. E. Architzel Information f Program Control L. B. Russell R. L. Hender11ch W. S. Gibson I

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