Morning Report for April 18, 2000

                       Headquarters Daily Report

                         APRIL 18, 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  APRIL 18, 2000

Licensee/Facility:                     Notification:

Nebraska Public Power District         MR Number: 4-00-0012
Cooper 1                               Date: 04/18/00
Brownville,Nebraska                    RIs by phone
Dockets: 50-298
BWR/GE-4

Subject: EQUIPMENT QUALIFICATION DEFICIENCIES WITH OKONITE TAPED SPLICES

Discussion:

On April 10, 2000, licensee management informed the resident inspectors
that drywell temperature profiles during design basis accidents may
exceed their equipment qualification test temperatures.  Subsequent
review by the licensee determined that the overall concern with the
environmental qualification of drywell equipment was bounded by existing
test results, as long as all electrical splices were in the configuration
bounded by the test.  To help confirm the actual configuratin, on April
14, a licensee electrician and the NRC's resident inspector entered the
containment to inspect a sample of splices.  The electrician and resident
inspector observed that, for most of the Okonite splices observed, the
outer tape was unraveling.  This called into question the overall
environmental qualification capability of all Okinite splices within the
containment.  Based upon these findings, the licensee is currently
considering the replacement, as needed, of all nonconforming splices with
qualified materials; however, they are also conducting evaluations in an
effort to qualify the as-found condition. The licensee is also reviewing
the equipment affected by the Okonite splices. Equipment already
identified as being affected includes motor-operated valves in the
reactor core isolation cooling and high pressure coolant injection
systems. Additionally, Regulatory Guide 1.97 instrumentation cables are
affected. Licensee personnel are continuing to evaluate the scope and
extent of this condition. Initial determination of risk significance is
at least a Green-White borderline condition.

Regional Action:

Supplemental inspection to be conducted, in accordance with Procedure
95001.

Contact:  David Loveless             (817)860-8161
          C. Marschall               (817)860-8185
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