05000395/LER-1983-002, Forwards Updated LER 83-002/03L-1.Detailed Event Analysis Encl: Difference between revisions

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{{Adams
#REDIRECT [[05000395/LER-1983-002]]
| number = ML20071B905
| issue date = 02/22/1983
| title = Forwards Updated LER 83-002/03L-1.Detailed Event Analysis Encl
| author name = Dixon O
| author affiliation = SOUTH CAROLINA ELECTRIC & GAS CO.
| addressee name = Oreilly J
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| docket = 05000395
| license number =
| contact person =
| document report number = NUDOCS 8303010283
| package number = ML20071B906
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
}}
{{LER
| Title = Forwards Updated LER 83-002/03L-1.Detailed Event Analysis Encl
| Plant =
| Reporting criterion =
| Power level =
| Mode =
| Docket = 05000395
| LER year = 2083
| LER number = 2
| LER revision =
| Event date =
| Report date =
| ENS =
| abstract =
}}
 
=text=
{{#Wiki_filter:,                                                                  *                        ;
.                                                                                                1
  %,  o SOUTH CAROLihlA,ELgcTalc:& GAS COMPANY
                                          ,Nh*iyyc5ZMJ n'M                                        j COLUMaiA. south CAROUNA 29218
: o. W. DixON, JR.                                  n      .                            j v.c passioant suctuan onannous g g g y ]a;19g Mr. James P. O'Reilly, Director U.S. Nuclear Regulatory Commission Region II, Suite 3100 101 Marietta Street,        N.W.
Atlanta, Georgia 30303
 
==SUBJECT:==
Virgil C.      Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Thirty Day Written Report LER 83-002, Revision 1
 
==Dear Mr. O'Reilly:==
 
Please find attached Licensee Event Report #83-002, Revision 1, for Virgil C. Summer Nuclear Station. This Thirty Day Report is required by Technical Specification 6.9.1.13.(b) as a result of entry into Action Statement (b) of Technical Specification 3.3.3.9, " Radioactive Gaseous Effluent Monitoring Instrumentation," on January 9, 1983.
Revision 1 to this LER corrects an administrative error discovered by the Licensee. Should there be any questions, please call us at your convenience.
Very truly yours, sg$
O. W. Di on, Jr.
CJM:OWD:dwf/fjc Attachment cc:      V. C. Summer                              A. R. Koon T. C. Nichols, Jr.                        G. D. Moffatt E. C. Roberts                            Site QA O. W. Dixon, Jr.                          C. L. Ligon (NSRC)
H. N. Cyrus                              G. J. Braddick H. T. Babb                                J. L. Skolds D. A. Nauman                              J. B. Knotts, Jr.
M. B. Whitaker, Jr.                      B. A. Bursey W. A. Williams, Jr.                        I&E (Washington)
            .        O. S. Bradham                            Document Management Branch R. B. Clary                                INPO Records Center C. A. Price                                NPCF File 8303010283 830222                                                                          -
PDR ADOCK 05000395 S                      PDR
* Ger O, Ia'COEY)^
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    ._. e Mr. James P. O'Reilly LER No. 83-002, Revision 1 Page Two February 22, 1983 DETAILED DESCRIPTION OF EVENT On January 9, 1983, at 0010 hours with the Plant in Mode 1, the Main Plant Vent Exhaust System flow rate indication failed low. The flow rate channel is required to be operable at all times per Technical Specification 3.3.3.9, Table 3.3-13, Item 3d. The Plant was prepared to estimate the flow rate on a
            --four (4) hour basis in compliance with Action Statement 39 if the channel remained inoperable.
PROBABLE CONSEQUENCES There were no adverse consequences in regards to this event.
The flow rate indication was returned to operable status within 2 hours and 20 minutes of the event occurrence. The Plant was prepared to monitor the flow rate on a four (4) hour basis in compliance with the Technical Specification Action Statement.
CAUSE(S) OF THE OCCURRENCE-The cause of this occurrence is attributed to corrosion on either the card edge connector or the fuse block of the Mixing Amplifier Circuit Board FY-9697.
IMMEDIATE CORRECTIVE ACTIONS TAKEN Maintenance personnel cleaned the card edge connector and the fuse block of Mixing Amplifier Circuit Board FY-9697. The channel was returned to service at 0230 hours on January 9, 1983, when flow rate indication returned to normal.
ACTION TAKEN TO PREVENT RECURRENCE Since this is an isolated incident, the licensee plans no additional action other than the normal surveillance testing.
                                                  -
}}
 
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