United States Nuclear Regulatory Commission - Protecting People and the Environment

Morning Report for December 4, 2000

                       Headquarters Daily Report

                         DECEMBER 04, 2000

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                    REPORT             NEGATIVE            NO INPUT
                    ATTACHED           INPUT RECEIVED      RECEIVED

HEADQUARTERS                           X
REGION I                               X
REGION II                              X
REGION III                             X
REGION IV           X
PRIORITY ATTENTION REQUIRED  MORNING REPORT - REGION IV  DEC. 04, 2000

Licensee/Facility:                     Notification:

Omaha Public Power District            MR Number: 4-00-0019
Ft Calhoun 1                           Date: 12/04/00
Fort Calhoun,Nebraska                  Resident Inspectors
Dockets: 50-285
PWR/CE

Subject: REACTOR COOLANT SYSTEM LEAK IDENTIFIED AND REPAIRED
         (Event No. 37560)


Discussion:

On December 1, 2000, at approximately 5:30 a.m., the licensed operators
determined that approximately a 1 gallon per minute leak from the reactor
coolant system existed inside containment. Technical Specification 2.1.4
directed the operators to initiate a shutdown within 12 hours if the
source of leakage could not be identified. Licensed operators began
reducing reactor power at approximately 7 a.m.

The licensee notified the NRC in accordance with 10 CFR 50.72 that they
had initiated a Technical Specification required shutdown (Event
Notification 37560). Subsequently plant personnel identified that the
source of leakage was from the charging line, upstream of the
regenerative heat exchanger. At 8:38 a.m. on December 1, Technical
Specification 2.1.4 was exited, because the source of the leakage had
been identified.  Operators secured the charging system, thus isolating
the leak.

Operators maintained reactor power level at 88 percent while repairs were
made.  The leak came from a cracked socket weld in an elbow joint on the
2-inch charging pump discharge piping, upstream of the regenerative heat
exchanger.  Maintenance personnel performed a repair of the cracked weld
in accordance with ASME Code Section XI.  Following the repair,
maintenance personnel also reinforced the weld on the opposite side of
the elbow from the crack.  Licensee personnel then performed inspections
of charging system piping and found no additional indications of
degradation or leakage.

Following piping performance testing, operators returned the charging and
letdown system to service at approximately 1:30 a.m. on December 2, 2000.
Licensed operators then increased reactor power, achieving 100 percent
power at approximately 8 p.m. on December 3, 2000.

Regional Action:

Routine resident inspector followup.

Contact:  David Loveless             (817)860-8161
          Wayne Sifre                (817)860-8193
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