ML18283B109
| 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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Ltr trans the following:
Abnormal Occurrence AO-50-260/753W on 1-19-75 re relief valve PCV-1-4 operated spuriously several times....'LANT NAb;1"=:
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4 TENNESSEE VALLEYAVTHORITY 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 VAIZZYAUTHORITY - BROWNS FERRY NUCLEAR PLANT UNIT 2-DOCKET NO. 50-260 - FACILITY OPERATING LICENSE DPR 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 VALLEYAUTHORITY E. F. Thomas Director of Power. Production Damp@
upped 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 willbe 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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