ML20009C149: Difference between revisions

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{{Adams
#REDIRECT [[05000287/LER-1981-010, Forwards LER 81-010/03L-0.Detailed Event Analysis Encl]]
| number = ML20009C149
| issue date = 06/16/1981
| title = Forwards LER 81-010/03L-0.Detailed Event Analysis Encl
| author name = Parker W
| author affiliation = DUKE POWER CO.
| addressee name = Oreilly J
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| docket = 05000287
| license number =
| contact person =
| document report number = NUDOCS 8107200326
| package number = ML20009C150
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
}}
 
=Text=
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* O l' VICIA L g 0s p y DUKE POWER COMPANY Powra Dt : .uswo 422 SouTri Cittucu Starer. Ciunt.orTE. N. C. 2e24a
                                                                                                                    <I ,
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                '/ cr Persiergt                                                                                    TELEP*eONE; Antt 70 sec. P.ooucwo~                            June 16, 1981                                                        3 7 3. .o e s S:t    ,
Mr. James P. O'Reilly, Director                                                                  ,
U.S. Nuclear Regulatory Commission                                                    d Region II                                                                    h              '
I-          I3 101 Marietta Street, Suite 3100                                              --
JUL l 7 Jggyu h Atlanta, Georgia 30303                                                        6    ug                        ,
                                                                                            #                        '\
Re:      Oconee Nuclear Station                                                \
Docket No. 50-287                                                        k.    .
 
==Dear Mr. O'Reilly:==
 
Please find attached Reportable Occurrence Report R0-287/31-10. This report is submitted pursuant to Oconee Nuclear Station Technical Specification 6.6.2.1.b(2),
which concerns operation in a degraded mode permitted by a limiting ecndition for operation, and describes an incident which is considered to be of no significance with respect to its effect on the health and safety of the public.
Ve        truly yours,'
ps
                                                      \          '
A.Ly '              k/                    .
William O. Parker, Jr. )
JLJ:pw Attachment cc: Director                                                          Mr. Bill Lavallee Office of Management & Program Analysis                    Nuclear Safety Analysis Center U.S. Nuclear Regulatory Commission                          P. O. Box 10412 Washington, D. C. 20555                                    Palo Alto, CA 94303 l  j i
8107200326 810616 PDR ADOCK 05000287 S                            PDR
 
DUKE POWER COMPANY OCONEE UNIT 3 Report Number: R0-287/81-10 Report Date: June 16, 1981 Occurrence Date: May 17, 1981 Facility: Oconee Unit 3, Seneca, South Carolina Identification of Occurrence: Loss of One MDEFWP During Unt. Operation Conditions Prior to Occurrence:                                                              100% FP Description of Occurrence: At 2115 hours on hay 17, 1981, a broken airline to valve 3LPSW-525 was discovered. Valve 3LPSW-525 is a solenoid controlled, cool-ing water valve to the "3B" Motor-Driven Emergency Feedwater Pump (MDEFWP). The "3B" MDEFWP was declared inoperable. This constitutes operation in a degraded mode per Technical Specification 3.4.1.c and is thus reportable pursuant to                                                                                                                    '
Technical Specification 6.6.2.1.b(2).
Apparent Cause of Occurrence: This incident was due to the breakage of a brass nipple between the air supply isolation valve and the accumulator tank of 3LPSW-525.
Analysis of Occurrence:                          Both the "3A" MDEFWP and the Turbine Driven EFWP were operable during the inc,perability of the "3B" MDEFWP. These pumps are capable of supplying sufficient feedwater flow to the steam generators in an emergency situation. Thus this incident was of no significance with respect to safe ope-ration, and the health and safety of the public were not affected.
Corrective Action: The immediate corrective action, replacing the broken '"'ss nipple with a similar one, was effective in repairing the valve.                                                                                                                                .
_ _ _ _ _ . _ . - . -}}

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