United States Nuclear Regulatory Commission - Protecting People and the Environment

Morning Report for December 14, 1999

                       Headquarters Daily Report

                         DECEMBER 14, 1999

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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 - HEADQUARTERS DEC. 14, 1999

Licensee/Facility:                     Notification:

Public Service Electric & Gas Co.      MR Number: H-99-0105
Salem 2                                Date: 12/14/99
Hancocks Bridge,New Jersey
Dockets: 50-311
PWR/W-4-LP

Subject: Carbon Dioxide Leak
         (Reportable Event Number: 36502)


Discussion:

On December 11, 1999, at 02:26 EST, a tank level instrument line on a 10
ton Cardox unit broke off causing the carbon dioxide tank to discharge
into a storage area located in the auxiliary building. Nobody was in the
area when the instrument line broke. Responding to a system trouble
alarm, personnel entered the room wearing Self-Contained Breathing
Apparatus (SCBA) and isolated the leak. Nobody was injured by the
incident. Oxygen level in the 10 ton carbon dioxide storage area was back
to normal by 03:14 EST. PSEG surmised that the instrument line failure
was caused by excessive vibration of the line induced by the operation of
the gas compressor mounted on the unit. The NRC is issuing this report to
inform other licensees of the potential failure mechanism of the line.

Contact:    Eric Benner, NRR/DRIP/REXB
            (301) 415-1171
            Email: ejb1@nrc.gov
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HEADQUARTERS      MORNING REPORT     PAGE  2          DECEMBER 14, 1999

Licensee/Facility:                     Notification:

Part 21 Database                       MR Number: H-99-0106
Enertech                               Date: 12/14/99


Subject: Part 21 - Pressure switch indication problems on main steam
         isolation valve-actuator assemblies


Discussion:

VENDOR: Enertech                        PT21 FILE NO: 99-45-0

DATE OF DOCUMENT: 10/22/99              ACCESSION NUMBER:

SOURCE DOCUMENT: EN 36332               REVIEWER: REXB, V. Hodge


NEW ISSUE.  The vendor of electro-hydraulic actuators, Enertech, reports
pressure switch indication problems on testing assemblies of main steam
isolation valves with the actuators. The valves were supplied by Burns
and Roe, under contract with the Pacific Northwest National Laboratory
for installation in a foreign nuclear power plant. Enertech reports that
the problem resulted from changes in manufacturing methods implemented by
the switch supplier to Enertech. Enertech states that the immediate
problem was addressed by modifying the pressure switches using the
supplier's previous manufacturing methods and that the modified
valve-actuator assemblies passed all test requirements. Enertech
determined that this issue is limited to this case but continued its
review.  On December 1, 1999, Enertech concluded that a reportable
condition does not exist.
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HEADQUARTERS      MORNING REPORT     PAGE  3          DECEMBER 14, 1999

Licensee/Facility:                     Notification:

Part 21 Database                       MR Number: H-99-0107
Technology For Energy (Tec)            Date: 12/14/99


Subject: Part 21 - Uncertain Environmental Qualification of Valve Flow
         Monitoring System


Discussion:

VENDOR: Technology for Energy (TEC)     PT21 FILE NO: 99-46-0

DATE OF DOCUMENT: 10/26/99              ACCESSION NUMBER:

SOURCE DOCUMENT: EN 36350               REVIEWER: REXB, E. Benner

NEW ISSUE. The vendor, Technology for Energy (TEC), reports that RTV-738
sealant used in TEC Valve Flow Monitoring System cannot be demonstrated
to meet containment qualification conditions. The vendor states that the
recommended installation procedure was not used during a 1980
qualification test. A set of cable resistance measurements suggest that
the sealant was removed to perform the resistance testing. This renders
uncertain the qualified life of the system. In the absence of reported
failures of the accelerometer to hardline cable junction, except for
physical damage during outages, and in the absence of records of the
qualification testing, the vendor is conducting a new set of tests to
demonstrate that the accelerometer to hardline cable junction can be
qualified using RTV-738 sealant and also using Raychem heat shrink. The
thermal aging test is complete with no failure, irradiation testing is
underway, and loss-of-coolant accident testing is scheduled to begin
November 8, 1999. Completion of the full set of tests is expected by
December 23, 1999.
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HEADQUARTERS      MORNING REPORT     PAGE  4          DECEMBER 14, 1999

Licensee/Facility:                     Notification:

Part 21 Database                       MR Number: H-99-0108
Scientech                              Date: 12/14/99


Subject: Part 21 - Potential Deviation in Low Level Amplifiers

Discussion:

VENDOR: Scientech                       PT21 FILE NO: 99-47-0

DATE OF DOCUMENT: 10/29/99              ACCESSION NUMBER:

SOURCE DOCUMENT: EN 36374               REVIEWER: REXB, C. Petrone

NEW ISSUE. The vendor, Scientech, reports a potential deviation in
low-level amplifiers manufactured by its subsidiary, NUS Instruments, and
delivered to the Robinson nuclear power plant. The Robinson licensee is
aware of this deviation and has removed the components from service.
These components are specified as follows:

Model Number RTL850, Part Number NUS-A002PA-1/3, Revision 1
Model Number RTL850, Part Number NUS-A002PA-1, Revision 0

The vendor states that it has not supplied these components to any other
utility for use in safety-related systems.

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HEADQUARTERS      MORNING REPORT     PAGE  5          DECEMBER 14, 1999

Licensee/Facility:                     Notification:

Part 21 Database                       MR Number: H-99-0109
Teledyne                               Date: 12/14/99


Subject: Part 21 - Nonlinear Oxygen Readings of a Containment
         Monitoring System


Discussion:

VENDOR: Teledyne                        PT21 FILE NO: 99-48-0

DATE OF DOCUMENT: 10/21/99              ACCESSION NUMBER: 9910280183

SOURCE DOCUMENT: LETTER                 REVIEWER: REXB, E. Benner

NEW ISSUE. The vendor, Teledyne Analytical Instruments, reports that the
Brunswick licensee observed nonlinear oxygen readings with Model 225
CMA-X containment monitoring systems (oxygen application only) during a
routine calibration after replacing an old fuel cell with a new fuel
cell. The vendor states that it has not received any similar reports. The
vendor's investigation revealed that the nonlinear response is caused by
a high gain produced by a 10K resistor, part number R311, across the
second-stage amplifier. This anomaly occurs if the fuel cell output is
close to 50 microamps. The vendor plans to revise engineering drawings to
reflect replacement of the 10K resistor with a 7.5K resistor, part number
R406, to reduce the gain by 25 percent and to notify the following
affected nuclear utilities: Carolina Power and Light, Niagara Mohawk
Power Corporation, and Vermont Yankee Nuclear Power Corporation.

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HEADQUARTERS      MORNING REPORT     PAGE  6          DECEMBER 14, 1999

Licensee/Facility:                     Notification:

Part 21 Database                       MR Number: H-99-0110
Nuclear Logistic                       Date: 12/14/99


Subject: Part 21 - DC Power Supply Overvoltage Protection Actuation
         During Start of Diesel Generator


Discussion:

VENDOR: Nuclear Logistics               PT21 FILE NO: 99-49-0

DATE OF DOCUMENT: 09/20/99              ACCESSION NUMBER: 9910270120

SOURCE DOCUMENT: LETTER                 REVIEWER: REXB, V. Hodge

NEW ISSUE. The vendor, Nuclear Logistics, Inc. (NLI), submits a final
report on an over voltage protection actuation of a direct current power
supply, part number NLI-LGS-G-24-OV-R8018, at Hope Creek. The Hope Creek
licensee was starting a diesel generator from the remote engine control
panel. NLI was unable to duplicate the actuation during laboratory
testing. To gain additional information regarding the behavior of the
power supply, NLI personnel traveled to Hope Creek to witness a start-up
sequence of the diesel generator. The vendor and the licensee concur that
the actuation at the plant was caused by the electrical circuit
conditions unique to the remote engine control panel.

The vendor states that power supplies with similar over voltage
protection circuitry have been supplied as safety-related components to
the following nuclear utilities: Public Service Electric and Gas Company,
Florida Power and Light Company, Baltimore Gas and Electric Company,
Omaha Public Power District, and Virginia Power Company. A listing of
affected customers and part numbers is given at
http://www.nrc.gov/NRC/PUBLIC/PART21/1999/1999490.html

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