ML20009C170: Difference between revisions

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{{Adams
#REDIRECT [[05000270/LER-1981-008, Forwards LER 81-008/03L-0.Detailed Event Analysis Encl]]
| number = ML20009C170
| issue date = 06/08/1981
| title = Forwards LER 81-008/03L-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 = 05000270
| license number =
| contact person =
| document report number = NUDOCS 8107200343
| package number = ML20009C171
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
}}
 
=Text=
{{#Wiki_filter:#
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Mr. James P. O'Reilly, Director U.S. Nuclear Regulatory Commission                                                                  Gf                -~
Region II                                                            / //> 77 101 Marieti.a Street, Suite 3100                                    /Q' g**      .
Atlanta, Georgia 30303                                                                  JL      .
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__      - JUL 17'1981*b v,,,mu mxess A Re: Oconee Nuclear Station                                        . 6~    ,
ewmot Docket No. 50-270                                          \ry
 
==Dear Mr. O'Reilly:==
y , cs Please find attached Reportable Occurrence Report R0-270/31-08. This report is submitted pursuant to Oconee Nuclear Station Technic:a1 Specification 6.6.2.1.b(2), which concerns operation in a degraded rode permitted by a limiting condition for operation, and describes an ticident which is con-sidered to be of no sigriificance with res;ect to its effect on the health and safety of the public.
Very truly yours, I
h              jw h                      n  r -i  er William O. Parker, Jr.                      /
JLJ:pw Atxachment cc: Director                                                          Mr. Bill Lavallee Office of Management & Program Analysis                        Nuclear Safety Analysis Center U.S. Nuclear Regulatory Commission                            P. O. Box 10412 j
i                    Washington, D. C. 20555                                        Palo Alto, CA 94303
                                                                                    * * * *      *9h-"    N  -=au    w,          m          ,      ,
4 8107200343 810608 PDR ADOCK 05000270                                                                                                                  ..
PDR S
 
DUKE POWER COMPANY OCONEE UNIT 2 i
  !                        Report Number: R0-270/81-08 i                        Report Date: June 8, 1981 Occurrence Date: May 8, 1981 j=
Facility: Oconee Unit 2, Seneca, South Carolina
        ' ~ "              ~'~
,                          IdentlEicationofOccurrence:    Solenoid Valve 2FDW-316 Inoperable conditions Prior to occurrence:    100% FP Description of Occurrence: At approximately 0830 hours on M ay 8, 1981 the " Auto /
Manual Select" solenoid valve for 2FDW-316 was discovered stuck in the manual position, thus disabling automatic level control of the B "0TSG" from the Emer-
;                          gency Feedwater (EFW) system. This constitutes operation in a degraded mode per Technical Specification 3.4.1.c, and is thus reportable pursuant to Technical Specifica'ti6h'6. 6T2.1.b(2) .
Apparent Cause of Occurrence:  The cause of this incident was the stuck Valcor
{                          solenoid valve.
;                          Valcor solenoid valves have exhibited a generic design flaw which causes coil l                          overheating and/or valve failure. Until a suitable replacement is found con-l                          tinued weekly testing will be required to identify failures as they occur.
f                          Analysis of Occurrence: Only one steam generator is required for a safe cool down of the RC System. This requirement was met by the operability of 2FDW-315 to "0TSG A". Additionally, manual operation of 2FDW-316 was not affected and operator control of EFW to Steam Generator was available. Thus, this incident was of no significance with respect to safe operation, and the health and safety of the public were not affected.
Corrective Action: The solenoid valve was replaced and functionally verified per procedure. All functions were normal.
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