ML20077H014

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Special Rept 91-08:on 910618,fire Header to Emergency Diesel Generator Bldg Removed from Svc Due to Underground Pipe Rupture.On 910601,leak Noted on Fire Hydrant O-26-886. Header Isolated & Fire Hydrant Repaired & Replaced
ML20077H014
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 07/02/1991
From: Wallace E
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
91-08, 91-8, NUDOCS 9107050007
Download: ML20077H014 (4)


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JUL 021991 U.S. Nuclear Regulatory Commission ATTN Document Control Desk Washington, D.C. 20555 Centlement In the Matter of ) Docket Hos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) UNITS 1 AND 2 - DOCKET NOS. 50-327 AND 50-328 - FACILITY OPERATING LICENSES DPH-77 AND DpR SPECIAL REPORT 91-08 The enclosed special report provides details concerning the inoperability of the fire suppression header to the emergency diesel generator building that supplies the building corridor sprinkler and hose stations. This issue was initially reported by telephone notification at 2145 Eastern daylight time on June 18, 1991, and by facsimlie dated June 19, 1991.

The noncompliance conditions are applicable to both Unita 1 and 2. This report to being inade in accordance with Technical Specification 3.7.11.1 Action Statement b.2.c.

If you have any questions concerning this submittal, please telephono James W. Proffitt at (615) 843-6651.

Very truly yours, TENNESSEE VALt.EY AUTHORITY u

E. G. Wallace, Manager Nucioar Licensing and Regulatory Affairs Enclosure ec: See page 2 9107050007 910702 gDR ADOCK0500gj7 g[l g

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U.S. Nuclear Regulatory Commission JUL 021991 cc (Enclostfre):

Ms. 3. C. Black, Deputy Director Project Diructorate 11-4 U.S. Nuclear Regulatory Commission one White Flint, North 11555 Rockville Pike Rockvillo, Maryland 20852 Mr. D. E. LaBargo, Project Manager U.S. Nuclear Regulatory Commission One White Flint. North 11555 Rockvillo Pike Rockyll10 Maryland 20852 NRC Resident inspector Sequoyah Nucioar Plant 2600 Igou Ferry Road Soddy-Daisy, Tonnesoco 31379 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region 11 101 Mariotta Street, NW, Suite 2900 Atlanta, coorgia 30323 I

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hW l ENCLOSURE 14-Day Follow-Up Report SPECIAL REPORT 91-08 Description of Condition on June 18, 1991, at 1335 Eastern daylight time (EDT) with Units 1 and 2 operating at approximately 100 percent power, Limiting Conditions for Operation (LCOs) 3.7.11.1, 3.7.11.2, and 3.7.11.4 were entered as a result of the fire header to the emergency diesel generator building being removed f rom service. The fire heuder was isolated because of an underground p.;> yture of the fire protection system. This fire header is the supply to the diesel generator building corridor sprinkler and building hose stations. Upon entering the LCOs, a backup fire suppression system was established by routing fire hoses from nearby hose stations to the affected areas, and fire watches were established for the affected areas. NRC was notified at 2145 EDT on June 18, 1991, as required by LCO 3.7.11.1, Action Statement b.2.a.

On June 1, 1991, at 0345 EDT, Operations' personnel had identified a leak from Fire Hydrant 0-26-886. Upon investigation by Fire Operations' personnel, it was determined that because the hydrant would not open or close, the valve stem to the fire hydrant was not functioning properly. The fire hydrant was isolated by closing fire hydrant Isolation Valve 0-26-534. A work request to repair the hydrant and a Physical Security Instruction 13, Appendix C, " Fire Protection Program," were provided to document the identified problem.

Surveillance Instruction (SI) 0-SI-FPU-026-171.0, " Periodic Flushing and Chlorination of High-Pressure Fire Protection System," was being performed on June 18, 1991; and flushing of Fire Hydrant 0-26-886 was initiated. The SI is performed once every six months. The fire hydrant was placed in the full-open position with a discharge gated wye installed having a 2 1/2-inch valve patata.1'.y ?c+n and fire hydrant Isolation Valve 0-26-534 closed.

The fire hydrant isolation valve was slowly opened. The water coming out of the gated wye began to cicud with Valve 0-26-534 not fully opened. Fire Operatters' personnel observed a burst of dirty water followed by a 1 cud noise, which resulted in a loss of waterflow through the fire hydrant. The fire hydrant isolation valve was closed, and water was observed flowing from the ground.

The header was immediately isolated by closing Valves 0-26-1618 and 0-26-683.

Operations' personnel entered LCOs 3. 7.11.1, 3. 7.11. 2, and 3. 7.11.4 ; and appropriate actions were taken to comply with the requirements of the LCOs.

Cause of Condition A portion of six-inch fire protection system yard pipe that had been isolated and the fire hydrant were removed for analysis _ The fire header contained a crack that was approximately 46 inches in length and ran anially along the bottom of the pipe. The cracking of the pipe apparently occurred when the fire hydrant valve closed suddenly.

An analysis of the valve stem of the fire hydrant indicated that the safety stem coupling was damaged (broken) and decoupled the upper stem f rom the lower stem. It could not be vetermined when or how the safety stem coupling was damaged. It is considered that during the operation of the fire hydrant, it may have been over torqued, which could have caused the safety stem coupling to be damaged. It is believed that this condition resulted in the the fire

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Sydrant valve becoming loose and acting as a " check valve." It is concluded that the loud noise that the Fire Operations' persor.nel heard was the fire hydrant valve suddenly slamming closed, which was caused by the flow of water striking the bottom of the lower salve plate and the cracking of the pipe.

The valve was free to move because of the damaged brass safety stem coupilng.

The sudden closure of the fire hydrant valve resulted in a water hammer that exerted significant force on the piping apparently sufficient to crack the pipe.

Corrective Action Immediate corrective action was taken to stop the leak by isolating the fire protection header to the emergency diesel generator building and complying with the LCO action, which requires backup fire suppression and the establishment of a fire watch for the affected area. NRC was notified of this condition at 2145 EDT on June 18, 1991, followed by a facsimile dated Jane 19, 1991.

The appropriate portions of the fire protection header and fire hydrant have been removed, analyzed, and repaired and/or replaced.

The investigation into the cause of this event is ongoing; a supplemental report will be issued by August 7, 1991.

Commitment l

A supplemental report will be issued by August 7, 1991.

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