View source for PNO-V-82-046, on 821117,steam Generator Water Chemistry Analyses Identified Chloride Levels Near 250 Ppm.Caused by One or More Tubes Rupturing in Main Condenser.Power Level Ramped Down.Ruptured Tubes Plugged within 4 H

{{Adams
| number = ML20204F091
| issue date = 11/17/1982
| title = PNO-V-82-046:on 821117,steam Generator Water Chemistry Analyses Identified Chloride Levels Near 250 Ppm.Caused by One or More Tubes Rupturing in Main Condenser.Power Level Ramped Down.Ruptured Tubes Plugged within 4 H
| author name = 
| author affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION V)
| addressee name = 
| addressee affiliation = 
| docket = 05000361
| license number = 
| contact person = 
| document report number = PNO-V-82-046, PNO-V-82-46, NUDOCS 8304280400
| document type = PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO,, TEXT-INSPECTION &amp; AUDIT &amp; I&amp;E CIRCULARS
| page count = 1
}}
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PRELIMINARY NOTIFICATION OF E. NT OR UNUSUAL OCCURRENCE--PNO-\             82-46      Datb:
ll/13f8g      .
This preliminary notification. constitutes EARLY natice of events.of POSSIBLE safety or publi interest significance. The information is as initially received without verification or               #
evaluation and is basically all that is known by IE staff on this date.
i                                                                      Licensee Emergency Classification:
I Facility:    Southern California Edison Company                          Notification of Unusual Event San Onofre Nuclear Generating                               Alert Station Unit 2                                            Site Area Emergency San Clemente, California Docket No. 50-361                                           General Emergency X Not Applicable

==Subject:==
OUTAGE GREATER THAN 48 HOURS
(   While at 50% power, during the performance of the power ascension test program, steam generator water chemistry analyses, performed at 9:30 a.m. on 11/17/82, identified chloride levels near 250 ppm in each steam generator. The licensee determined that one or more tubes in the main condenser had ruptured causing seawater introduction into the condensate stream. The licensee took immediate action to ramp power level down and following the trip of the main turbir.e, at about 5% power, was feeding the steam generators in automatic on the feedwater regulating valve bypass valves.
Cycling.of the mini-flow recirculation valve on the main feedpunips caused feed flow and steam generator level oscillations. At 10:55 a.m. cn 11/17/82, the reactor tripped due to a-high level in steam generator 089. All plant systems operated normally and the reactor remains shutdown.
The licensee is in the process of cooling down the plant and blowing down steam generators using the Auxiliary Feedwater System for steam generator inventory makeup.
The licensee estimates that about a two-day delay will be incurred in the power ascension test program while reestablishing satisfactory steam generator chemistry conditions. The ruptured main condenser tube (s) should be plugged within about four hours.
This Preliminary Notification is issued for information only.                                                 l Media interest is not expected. Neither the licensee nor the NRC plans to issue a news release. Region V (San Francisco) received notification of this occurrence from                          l the Senior Resident Inspectcr at 11:10 a'.m. on 11/17/82. This informatipp is_ current                  __
as of 12:30 p.m. on 11/17/82.
DCC G ATED ORIGINAL Cortificd By i
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Comm. Roberts          ELD                                       830428g4co821t17 SECY                             Air _ Rights A RS                             SP J:oy INPO,typ         M h B2-046           PDR PDR NSAC
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