ML18283B109

Abnormal Occurrence Report BFA0-50-260/753W on 1/19/75 Relief Valve PCV 1-4 Operated Spuriously Several Times

ML18283B109
Person / Time
Site:	Browns Ferry
Issue date:	01/29/1975
From:	Eric Thomas Tennessee Valley Authority
To:	Case E Office of Nuclear Reactor Regulation
References
BFA0-50-260/753W
Download: ML18283B109 (6)

Text

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CHATTANOOGA TENNESSEE STAOI glGgojgollt O'-CIiet Fll8 January 29, 1975 Mr. Edson G. Case Acting Director of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20545

Dear Mr. Case:

TENNESSEE VAIZZY AUTHORITY - BROWNS FERRY NUCLEAR PLANT UNIT 2-DOCKET NO. 50-260 - FACILITY OPERATING LICENSE DPR-52 - ABNORMAL OCCURRENCE REPORT BFAO-50-260/753W The enclosed report is to provide details concerning relief valve PCV-1-4 which operated. spurious several times and. is submitted.

in accordance with Appendix A to Regulatory Guide 1.16, Revision 1, October 1973. This event occurred on Browns Ferry Nuclear Plant unit 2 on January 19, 1975.

Very truly yours, TENNESSEE VALLEY AUTHORITY Damp@

E. F. Thomas upped Director of Power. Production Enclosure CC (Enclosure):

Mr. Norman C. Moseley, Director U.S. Nuclear Regulatory Commission Regional Office 230 Peachtree Street, NW., Suite 818 Atlanta, Georgia 30303

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Report No.: BFAO-50-260/753W Report Date: January 29, 3.975 Occurrence Date: January 19, 1975 Facility: Browns Ferry-Nuclear Plant unit 2

'jo-hya.;wjuc.naive W8~7f Identification of Occurrence On January 19, 3.975, beginning at approximate3y 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, relief va1ve PCV-1-4 operated. spurious+ several times.

Conditions Prior to Occurrence The reactor was operating at approximate~ 340 MWe Descri tion of Occurrence During power ascension, the main steam relief valve PCV-1-4 operated several times while reactor pressure was normal.

Desi ation of A arent Cause of'ccurrence Disassemb~ and. inspection of the relief valve revealed both second.-stage and.

pilot-stage leakage. The pilot>>stage leakage resulted. from an indentation in both the seat and. disc. It appears that closure of the pilot on a foreign object caused. the indentation. No foreign material was found. in the valve.

It is concluded that pilot leakage caused. the spurious valve actuation.

An~sis of'ccurrence There were no adverse effects to the public health and. safety or damage to systems, components, or structures as a result of this occurrence. An orders unit shutdown was conducted. No extended blowdown occurred..

Corrective Action The relief valve was replaced. Post-maintenance functional tests at approximate+

250 psi and at rated pressure were satisfactori3y performed,. Repairs were made to the valve that was removed., and 'steam setpoint tests will be conducted. A torus inspection conducted subsequent to this event confirmed normal conditions.

Failure Data Previous failures are reported on Abnormal Occurrence Reports BFAO-50-260/7430W; BFAO-50-260/7429W; BFAO-7426W) unit 1; BFAO-749W) unit 3.) BFAO-7349W) unit 1) and.

BFA0-7314W, unit 1.

Valve Data Manufacturer - Target Rock Corporation Mod.e3. - 67F

. Design Pressure - 3.,200 psi Setpoint - 1,080 psig Capacity - 800,000 lb/hr saturated, steam Serial No. - '57

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