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Morning Report for September 12, 2002



                       Headquarters Daily Report

                         SEPTEMBER 12, 2002

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                    REPORT             NEGATIVE
                    ATTACHED           INPUT RECEIVED

HEADQUARTERS        X
REGION I                               X
REGION II                              X
REGION III                             X
REGION IV                              X





PRIORITY ATTENTION REQUIRED  MORNING REPORT - HEADQUARTERS SEP. 12, 2002

Licensee/Facility:                     Notification:

Part 21 Database                       MR Number: H-02-0071
Abb                                    Date: 09/12/02


Subject: Part 21 - Test failure of a power shield trip device
         manufactured before March 1991


Discussion:

VENDOR: ABB                         PT21 FILE NO: m2-22-0

DATE OF DOCUMENT: 08/26/02          ACCESSION NUMBER: ml022410017

SOURCE DOCUMENT: LETTER             REVIEWER: RORP, C. Petrone

ABB, a vendor of electrical equipment, reported being notified by the
Summer licensee of a failure of a power shield trip device during
surveillance testing. Two of the three phases tripped at more than 20
percent above the nominal set point. The failed device, a 225 Amp model,
serial number 32301, was being used in a non-safety related application.

The licensee indicated that during single phase testing with maximum amp
tap and instantaneous tap settings (225 amp and 12X, respectively), the
transformer board current transformer would saturate, causing the trip
point to be out of specification. Lower settings resulted in trip points
within tolerance.

In March 1991, the vendor discontinued manufacture of the current
transformer design used in the failed device. Power shield trip devices
that were dedicated as 1E nuclear safety related devices and manufactured
before March 1991 have the transformer that may saturate at the highest
instantaneous tap setting. Products with a serial number of 82019 and
below also may have the transformer affected by this notice. The vendor
recommends that customers use lower than maximum instantaneous tap
settings or replace the transformer board with one that has the improved
transformer design.

Contact:    C. Petrone, NRR
            301-415-1027
            E-mail: cdp@nrc.gov
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HEADQUARTERS      MORNING REPORT     PAGE  2          SEPTEMBER 12, 2002

Licensee/Facility:                     Notification:

Part 21 Database                       MR Number: H-02-0072
Rosemount                              Date: 09/12/02


Subject: Part 21 - Test failures of capacitors in damping circuits of
         certain Models 1153 and 1154 pressure transmitters


Discussion:

VENDOR: Rosemount                       PT21 FILE NO: m2-23-0

DATE OF DOCUMENT:  08/30/02             ACCESSION NUMBER: ml022470359

SOURCE DOCUMENT: LETTER                 REVIEWER: RORP, R. Caldwell

The vendor, Rosemount Nuclear Instrumentation, reported that capacitors
supplied to it from December 2000 until July 2002 were inadequately
tested for conformance to the vendor's specification for high temperature
insulation resistance. Vendor testing demonstrated significant insulation
breakdown which may cause transmitter failure at temperatures greater
than the normal operating temperatures. Instruments of concern are Model
1153 and 1154 pressure transmitters with optional adjustable circuits to
damp voltage swings from pressure oscillations. Affected domestic nuclear
power plant licensees include Amergen Energy, Carolina Power and Light,
Constellation Nuclear, Dominion Generation, Entergy, Exelon Generation,
FirstEnergy, PECO Energy, and Public Service Electric and Gas.

Contact:    R. Caldwell, NRR
            301-415-1243
            E-mail: rkc1@nrc.gov

_
HEADQUARTERS      MORNING REPORT     PAGE  3          SEPTEMBER 12, 2002

Licensee/Facility:                     Notification:

Part 21 Database                       MR Number: H-02-0073
Rosemount                              Date: 09/12/02


Subject: Part 21-Certain Model 1153 differential pressure transmitters &
         spare sensor modules may not meet the published temp effect spec


Discussion:

VENDOR: Rosemount                       PT21 FILE NO: m2-24-0

DATE OF DOCUMENT: 09/09/02              ACCESSION NUMBER:

SOURCE DOCUMENT: EN 39178               REVIEWER: RORP, J. Foster

The vendor, Rosemount Nuclear Instrumentation, reported that certain
Model 1153 differential pressure transmitters and spare sensor modules
may not meet the published temperature effect specification. This
specification establishes an expected analog output error interval during
normal ambient temperature variations occurring between 40 F and 200 F.
The root cause of the potential nonconformance has been narrowed to the
effect of temperature changes on the transmitter module. Instruments of
concern are certain Model 1153 differential pressure transmitters with
model codes beginning with 1153D or 1153H shipped between March 2001 and
August 2002 and spare sensor modules shipped between March 2001 and
August 2002 with kit part numbers:

01153-0320-0232
01153-0320-0352
01153-0320-0252

Affected domestic nuclear power plant licensees include Carolina Power
and Light, Constellation Nuclear, Detroit Edison, Dominion Generation,
Duke Energy, Entergy, Exelon Generation, FirstEnergy, Florida Power and
Light, Georgia Power, North Atlantic Energy Service, Pacific Gas and
Electric, Public Service Electric and Gas, Southern California Edison,
and TXU Electric and Gas.

Contact:    J. Foster, NRR
            301-415-3647
            E-mail: jwf@nrc.gov
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HEADQUARTERS      MORNING REPORT     PAGE  4          SEPTEMBER 12, 2002

MR Number: H-02-0074

                           NRR DAILY REPORT ITEM
                           GENERIC COMMUNICATIONS


Subject: Issuance of Information Notice 2002-26

Information Notice 2002-26: Failure of Steam Dryer Cover Plate After
a Recent Power Uprate dated September 11, 2002

The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to a recent failure of a steam dryer cover
plate during operations following a power uprate at a boiling water
reactor (BWR).

ADAMS Accession No.:  ML022530291

Contacts:   Karla Stoedter, Region III      Robert Caldwell, NRR
            (309) 654-2227                  (301) 415-1243
            E-mail: kkb@nrc.gov             E-mail: rkc1@nrc.gov

            Carl Lyon, NRR
            (301) 415-2296
            E-mail: cfl@nrc.gov
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