PNO-II-92-007, on 920202,plant Experienced Reactor Scram from 79% Power During Main Turbine Cv Testing.Licensee Actions Towards Determining/Correcting Root Cause of Scram Have Been Focused on EHC Sys

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PNO-II-92-007:on 920202,plant Experienced Reactor Scram from 79% Power During Main Turbine Cv Testing.Licensee Actions Towards Determining/Correcting Root Cause of Scram Have Been Focused on EHC Sys
ML20203F313
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 02/05/1992
From: Carroll R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
References
PNO-II-92-007, PNO-II-92-7, NUDOCS 9712170344
Download: ML20203F313 (1)


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h^,' ' ~1, f pcf February 5,1992 RELIMINARY NOTIFICAT10N 0F EVENT OR UNUSVAL OCCURRENCE PNG-II-92-07 This preliminary notification constitutes E*RLY notice of events of POSSIBLE safety or

. public interest significance. The information is as initially received without verifi-cation or evaluation, and is basically all that is known by the Region II staff on this date.

FACILITY: CP&L Licensee L.orgency Classification:

Brunswick Unit 2 Notification of Unusual Event Docket No. 50-324 Southport, NC Alert Site Area Emergency General Ese d,g(

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SUBJECT:

SHUTDOWN IN EXCESS OF 72 HOURS On february 2,1992, at 6:09 a.m. (EST), Brunswick Unit 2 experienced a reactor scram from 79 percent power during main turbine control valve (CV) testing. Just prior to the event, testing .of CV-2 had* gener~ated a half scram on Channel 81 due to the expected trip / actuation of CV-2's associated electro hydraulic control (EHC) fluid pressure switch.

  • Upon releasing the CV-2 test
  • push button, the associated CV-1 EHC fluid pressure switch momentarily tr.ipped/ actuated, generating a half scram on Channel A1. As the half a full reactor scram resulted. All safety scras systems on. functioned Channel B1 a.s had required, not yet andbeen the ugreset,l(presently remains in the hot shutdown condition. *

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'icensee' actions towards; determining / correcting the root cause of the scram have been 1cused .on the EHC . system. To date, in situ testing of the associated CV-1

.<l0 fluid pressure switch has been indeterminate. Additionally EHC fluid in-leukage was discovered in bcth nitrogen accumulators on the EHC system. Prior to restart the in-leakage problem on botn;EHC system nitrogen accumulatcrs will be correctt.d, Ek fluid pressure switches on all four CVs will be replaced, and the EHC system will be tested to ensure the initiating problem has been corrected.

Other work activities in progress include repairs to the 2A reactor feed pump (which bound up subsequent to the event) and copecting identified feedwater heater related hanger / support deficiencies.

Region I'I and the resit.ent inspectors have, and will continue to followup on the event and the work activities in progress.

The.NRC received initial. notification 'of this event by Telephone call to the Headquarters )

Duty Officer at 8:38 a.m. (EST), on Febru try 2,1992.

This inf wtion is current.as of 12:00 p.m. -(EST), on February 5,1992. ,

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9712170344 920205 //

PDR 18iE PNO-I1-92-007 PDR h N V{ /

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"0NTACT: R F. Carroll FTS: Bal-M4'I.

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