ML20072N027

Ro:On 830313,standby Gas Train Deluge Sys Isolation Valve WW-V207 Found in Closed Position During Fire Suppression Equipment Surveillance.Caused by Failure to Establish Continuous Fire Watch W/Backup Fire Suppression Equipment

ML20072N027
Person / Time
Site:	Brunswick
Issue date:	03/21/1983
From:	Dietz C CAROLINA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
BSEP-83-936, NUDOCS 8304010428
Download: ML20072N027 (2)

Text

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.a NTA. 6L OF ra a Carolina Power & Light Company e--m ,r,gm__ - em, Brunswick Steam Electric Plant g3

• MAR 25 A10 24 P. O. Box 10429

• Southport, NC 28461-0429 March 21, 1983 FILE: B09-13510C SERIAL: BSEP/83-936 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Region II, Suite 3100 101 Marietta Street N.W.

Atlanta, GA 30303 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 1 DOCKET NO. 50-325 LICENSE NO. DPR-71 i

CONFIRMATION FACSIMILE OF AN IMMEDIATELY REPORTABLE EVENT (1-83-15)

Dear Mr. O'Reilly:

This confirms the telephone conversation at 1600 on March 18, 1983, between Mr. R. M. Poulk, Jr., and Mr. C. W. Hehl concerning an immediately reportable event per Technical Specification 6.9.1.8b.

While performing surveillance on fire suppression equipment per PT-35.7 on March 13, 1983, standby gas train deluge system isolation valve WW-V207 was found in the closed position. This valve isolates well water to both deluge systems on both standby gas trains for Unit No. 1. Preliminary investigation of this event has determined that this valve was closed on February 11, 1983, which made these deluge systems inoperable. Actions required by technical specifications, a continuous fire watch with backup fire suppression equipment, were not taken until it was identified on March 13, 1983. In addition to the failure to follow the action-statement from February 11 to March 13, 1983, the plant failed to properly identify its failure to meet those action statements and thus failed to make a prompt report by March 14, 1983.

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Mr. James P. O'Reilly March 21, 1983 Preliminary investigations indicate that PT-35.7 was performed four times between February 11 and March 13, 1983. A review of these completed pts indicate that the valve was locked open.- This valve is located in a dark recessed area within a piping run in.the Reactor Building; therefore, it is believed that the position of this valve was incorrectly determined during those four previous surveillances. An investigation of this event is continuing.

Very truly yours, wp C. R. Dietz, General Manager Brunswick Steam Electric Plant RMP/mcg/LETCG1 Enclosure cc: Mr. R. C. DeYoung NRC Document Control Desk A

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