Information Notice 2000-14, Non-vital Bus Fault Leads to Fire and Loss of Offsite Power
ML003748744 | |
Person / Time | |
---|---|
Issue date: | 09/27/2000 |
From: | Marsh L Operational Experience and Non-Power Reactors Branch |
To: | |
Goodwin E | |
References | |
IN-00-014 | |
Download: ML003748744 (6) | |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D. C. 20555-0001 September 27, 2000
NRC INFORMATION NOTICE 2000-14: NON-VITAL BUS FAULT LEADS TO FIRE AND
LOSS OF OFFSITE POWER
Addressees
All holders of licenses for nuclear power reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to inform
addressees of equipment and design issues identified following a recent transient at the Diablo
Canyon nuclear power plant. The aspect of the transient considered noteworthy was the failure
of bus duct, a passive component of known high reliability which often receives little preventive
maintenance or attention. It is expected that recipients will review the information for
applicability to their facilities and consider actions, as appropriate, to avoid similar problems.
However, suggestions contained in this information notice are not NRC requirements; therefore, no specific actions or written response is required.
Description of Circumstances
On May 15, 2000, at Diablo Canyon Unit 1, a phase-to-phase electrical fault occurred in a
12-kV non-Class 1E electrical bus duct from the unit auxiliary transformer to the switchboards
that supplied the reactor coolant pumps and the circulating water pumps. The fault caused a
turbine trip and consequent reactor trip. As this section of bus could not be isolated from the
main generator, the fault lasted for 4 to 8 seconds until the main generator electrical field
voltage decayed. The 12-kV bus fault occurred at a point at which the bus duct passes under
the 4-kV non-Class 1E bus from the startup transformer. The original fault and the resultant
arcing and smoke caused another fault, this time in the 4-kV bus duct directly above the original
failure.
The 12-kV circuit breaker that supplied the 4-kV startup transformers and the faulted 4-kV bus
duct downstream of the transformer tripped in response to this second fault. This trip resulted
in a loss of power to all 4-kV vital (safety-related) and non-vital buses. All three diesel
generators started and all vital loads were re-energized. However, the combination of the two
faults disabled both power supplies to the non-vital 4-kV buses.
Besides de-energizing all non-vital 4-kV power within the plant, the loss of both sources of
non-vital power also caused a loss of the 480-Vac power supply to the switchyard control
building. This failure led to a loss of power to the charger for the switchyard batteries; the
eventual depletion of the switchyard batteries would have led to a loss of control power in the
switchyard serving both Diablo Canyon units. The loss of control power would have disabled
remote control of the switchyard high voltage circuit breakers.
The licensee installed a portable generator to restore power to the charger before the
switchyard batteries were depleted. On May 16, 2000, after 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br />, plant personnel
energized the 4-kV and 480-Vac non-vital buses by backfeeding through Auxiliary
Transformer 1-2.
Discussion
Switchgear Room Arrangement and Bus Duct Construction
The auxiliary and startup transformers are connected to the onsite distribution switchgear by
bus bars with a 1/2 - by 6-inch cross-sectional area. All three phases are enclosed in a single
aluminum duct (nonsegregated). The startup and auxiliary 12-kV and 4-kV non-vital switchgear
are located within a common room. To connect the two sources of offsite power to multiple
switch boards within the room, there are many crossing bus ducts above the switchgear. The
non-vital 4-kV bus ducts from both auxiliary and startup power are in close proximity for
extended runs. Since none of the bus ducts was designed as safety grade, no regulatory
separation criteria apply.
The bus work in the room was a combination of aluminum and copper bus bars connected with
aluminum splice plates secured by four 1/2-inch bolts. The bus bars and splice plates were
silver-plated at the connection points to ensure conductivity. The bus bars had a nominal
3/16-inch gap between them at the splice plate to allow for thermal expansion. The 12-kV bus
bars had a 6-inch air gap between phases, which is slightly below the required air gap for
uninsulated conductors, so bus bars and connections were insulated with a combination of
sleeves and wraps. The 4-kV bus bars were similarly insulated.
Root Cause
The licensees evaluation concluded that a center bus bar overheated at a splice joint, which
caused a polyvinyl chloride boot insulator over the splice joint to smoke. Eventually, heat-induced failure of fiberglass insulation on adjacent phases resulted in phase-to-phase
arcing. The fault and resultant fire destroyed any direct physical evidence of the root cause;
however, the factors discussed below could individually or jointly have led to the failure. They
include inconsistent silverplating, currents approaching bus capacity, undersized splice plates, torque relaxation of connecting bolts, and undetected damage from a 1995 explosion of
Auxiliary Transformer 1-1.
(1) Silverplating
Many of the bus bars and splice plates had only a thin layer of silverplating. Laboratory
analysis determined that the silverplating on one splice plate had partially separated from the
base aluminum, and corrosion products were found on the aluminum surface. If this separation
had existed at the point of the fault, it would have created higher resistance and, therefore, more heat at the connection. The laboratory stated that the most likely source of corrosive
compounds was the polyvinyl chloride insulating boot. Silverplating was also observed flaking
off the aluminum bus bars at two other splice joints not directly affected by the fault. (2) Heavy Bus Loading and Splice Joint Configuration
The 12-kV 6-inch aluminum bus bars were rated at 2250 amps. The bus was routinely loaded
to 2100 amps with an actual worst case operating load of about 2250 amps. The vendor stated
that all bus bars supplied to Diablo Canyon met the design requirements of Institute of Electrical
and Electronics Engineers (IEEE) 37.20-1969, IEEE Standard for Switchgear Assemblies
Including Metal-Enclosed Bus, which stipulates an operating temperature limit of 65 C.
Vendor-supplied test data reported a maximum temperature rise of 46 C at 2000 amps and
63 C at 2200 amps for the bus bar type that failed. Since the test temperature increased 17 C
for a current increase of 200 amps, a temperature increase of only 2 C for an additional load of
50 amps seems improbably low and it is reasonable that the bus and its insulation had
exceeded design conditions for some time. In addition, the vendor heat rise tests of aluminum
bus bars for 2200 amps were conducted with two splice plates at the splice joint. The vendor
test used 3 - by 4-inch copper splice plates instead of the 21/2 - by 4-inch aluminum splice plates
used at Diablo Canyon.
The inspectors noted that the splice plates connecting the bus bars were considerably smaller
than the bus bars themselves. Some splice joints had two aluminum plates on each phase
sized 21/2 inches by 4 inches by ÿ inch. Also, the splice plates were not always centered
between the bus bars. The lack of centering of splice plates and splice plates smaller than the
tested configuration reduced the contact area, causing increased heat generation.
(3) Torque Relaxation
The as-found torque values for many of the splice plate connecting bolts was 10 to
20 foot-pounds indicating that thermal relaxation had occurred since initial installation. The
bolts had an initial torque value of 40 foot-pounds. Torque relaxation on the bolts could have
allowed the splice plate to lose contact with the bus bar, leading to arcing and overheating.
(4) Undetected Damage from 1995 Auxiliary Transformer 1-1 Explosion
A 1995 explosion of Auxiliary Transformer 1-1 had displaced the 12-kV busing several feet into
the turbine building. Most of the bus bar connections upstream of the failed connection had
been disassembled and repaired where necessary. Records for the failed connection were
incomplete. The inspectors determined that the failed joint had been visually inspected and
micro-ohm tested; however, no evidence was found to verify that the joint had been torqued.
Inadequate torque could have resulted in increased resistance and heat generation if the joint
became loose.
Corrective Actions
All damaged components were repaired and refurbished, accessible splice joints on the 12-kV
auxiliary bus and 4-kV startup bus were inspected and torqued, and post-maintenance tests
were conducted to ensure that the bus bars were properly restored. The licensee concluded
that a similar defect was unlikely to occur on Unit 2 because the splice plates for the Unit 2 bus, although similar in construction to the one that failed in Unit 1, had previously been inspected and torqued. The licensee also tested the affected startup and auxiliary transformers to ensure
no breakdown had occurred in the winding insulation.
The licensee examined the various design issues associated with the 12-kV and 4-kV buses.
The buses with operating currents near design limits were judged to be operable because the
expected temperature at the Diablo Canyon site was considerably lower than the ambient
temperature assumed in the vendor heat rise test acceptance criteria. The licensee grouped
renovation and maintenance of the undamaged runs of bus into three groups by decreasing
order of failure susceptibility to prioritize remedial actions: (1) bus sections where normal load
has little margin relative to the continuous duty design rating, (2) bus sections in which the
auxiliary buses pass near the startup buses, and (3) bus sections that cannot be isolated from
the main generator (i.e., have no breaker to quickly sense and interrupt the fault).
During upcoming refueling outages, planned actions to prevent recurrence include the
following: (1) inspect and torque the booted connections on the 3750-amp bus for Startup
Transformer 1-1 and replace splice plates on the booted connections with full-face copper
splice plates; (2) inspect and torque splice plate connections on the 4-kV auxiliary buses; and
(3) upgrade the 2250-amp 12-kV buses from aluminum to copper bars. The same inspection
and replacement activities will occur on taped connections during the subsequent Unit 1 refueling outage.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact one of the technical contacts
listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
/RA/Marvin M. Mendonca FOR
Ledyard B. Marsh, Chief
Events Assessment, Generic Communications
and Non-Power Reactors Branch
Division of Regulatory Improvement Programs
Office of Nuclear Reactor Regulation
Technical contacts: Edward Goodwin, NRR Dyle Acker, Region IV
301-415-1154 805-595-2354 E-mail: efg@nrc.gov E-mail: dga@nrc.gov
Gregory Pick, Region IV
817-860-8270
E-mail: gap@nrc.gov
Attachment: List of Recently Issued NRC Information Notices and torqued. The licensee also tested the affected startup and auxiliary transformers to ensure
no breakdown had occurred in the winding insulation.
The licensee examined the various design issues associated with the 12-kV and 4-kV buses.
The buses with operating currents near design limits were judged to be operable because the
expected temperature at the Diablo Canyon site was considerably lower than the ambient
temperature assumed in the vendor heat rise test acceptance criteria. The licensee grouped
renovation and maintenance of the undamaged runs of bus into three groups by decreasing
order of failure susceptibility to prioritize remedial actions: (1) bus sections where normal load
has little margin relative to the continuous duty design rating, (2) bus sections in which the
auxiliary buses pass near the startup buses, and (3) bus sections that cannot be isolated from
the main generator (i.e., have no breaker to quickly sense and interrupt the fault).
During upcoming refueling outages, planned actions to prevent recurrence include the
following: (1) inspect and torque the booted connections on the 3750-amp bus for Startup
Transformer 1-1 and replace splice plates on the booted connections with full-face copper
splice plates; (2) inspect and torque splice plate connections on the 4-kV auxiliary buses; and
(3) upgrade the 2250-amp 12-kV buses from aluminum to copper bars. The same inspection
and replacement activities will occur on taped connections during the subsequent Unit 1 refueling outage.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact one of the technical contacts
listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
/RA/Marvin M. Mendonca FOR
Ledyard B. Marsh, Chief
Events Assessment, Generic Communications
and Non-Power Reactors Branch
Division of Regulatory Improvement Programs
Office of Nuclear Reactor Regulation
Technical contacts: Edward Goodwin, NRR Dyle Acker, Region IV
301-415-1154 805-595-2354 E-mail: efg@nrc.gov E-mail: dga@nrc.gov
Gregory Pick, Region IV
817-860-8270
E-mail: gap@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
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OFFICE REXB:DRIP Tech Editor RIV/RPB-E DLPM/LPD4 C:REXB:DRIP
NAME EGoodwin* BCalure* GPick* SBloom* LMarsh
DATE 9/10/00 9/14/00 9/18/00 9/25/00 9/26/00
OFFICIAL RECORD COPY
Attachment LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
_____________________________________________________________________________________
Information Date of
Notice No. Subject Issuance Issued to
______________________________________________________________________________________
2000-13 Review of Refueling Outage 9/27/2000 All holders of OL for nuclear
Risk power reactors
2000-12 Potential Degradation of 9/21/2000 All holders of licenses for nuclear
Firefighter Primary Protective power, research, and test
Garments reactors and fuel cycle facilities
2000-11 Licensee Responsibility for 8/7/2000 All U.S. NRC 10 CFR Part 50 and
Quality Assurance Oversight of Part 72 licensees, and Part 72 Contractor Activities Regarding Certificate of Compliance holders
Fabrication and Use of Spent
Fuel Storage Cask Systems
2000-10 Recent Events Resulting in 7/18/2000 All material licensees who
Extremity Exposures prepare or use unsealed
Exceeding Regulatory Limits radioactive materials, radio- pharmaceuticals, or sealed
sources for medical use or for
research and development
95-03, Supp 2 Loss of Reactor Coolant 7/03/2000 All holders of OL for nuclear
Inventory and Potential Loss of power reactors except those who
Emergency Mitigation have ceased operations and have
Functions While in a Shutdown certified that fuel has been
Condition permanently removed from the
reactor vessel
2000-09 Steam Generator Tube Failure 6/28/2000 All holders of OL for nuclear
at Indian Point Unit 2 power reactors, except those who
have permanently ceased
operations and have certified that
fuel has been permanently
removed from the reactor vessel
2000-08 Inadequate Assessment of the 5/15/2000 All holders of operating licensees
Effect of Differential for nuclear power reactors
Temperatures on Safety- Related Pumps
____________________________________________________________________________________
OL = Operating License
CP = Construction Permit