Fires in Emergency Diesel Generator Exciters During Operation Following Undetected Fuse BlowingML031060118 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
04/22/1996 |
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From: |
Crutchfield D Office of Nuclear Reactor Regulation |
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To: |
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References |
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IN-96-023, NUDOCS 9604170169 |
Download: ML031060118 (10) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, DC 20555-0001 April 22, 1996 NRC INFORMATION NOTICE 96-23: FIRES IN EMERGENCY DIESEL GENERATOR EXCITERS
DURING OPERATION FOLLOWING UNDETECTED FUSE
BLOWING
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to the potential for damage (possibly fire) to
emergency diesel generator (EDG) exciters resulting from sustained high-power
operation after undetected blowing of a secondary fuse. 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 action or written response is required.
Description of Circumstances
On September 30, 1994, during refueling at the Wolf Creek Generating Station, the A train emergency diesel generator was undergoing post maintenance testing
and balancing. After about one hour of sustained operation above full diesel
generator power as part of a routine prolonged full and above full-power run, a fire occurred in the main power potential transformer of the static exciter- voltage regulator (exciter). The fire was extinguished quickly by deener- gizing the exciter and using a portable carbon dioxide fire extinguisher.
After the fire in the EDG-A exciter, the licensee performed electrical checks
on the EDG-B exciter and found no problems. On October 11, 1994, again after
about an hour of above full power operation of EDG-B, its exciter potential
transformer also caught fire. This fire was also quickly extinguished by
deenergizing the exciter and using a fire extinguisher. After each fire, the
licensee found that one of the 100-ampere fuses in the secondary circuits of
the respective exciter potential transformer had blown. It was later deter- mined that the fuses had not blown as a result of the fires, but that the
blown fuses were a contributing cause of the fires.
The phase B windings of the potential transformer removed from the exciter in
EDG-A were severely charred, and the primary and secondary cables were
blistered from the terminal lug back several inches. Some collateral damage
had occurred to the portions of the A- and C-phase windings closest to the
center, B-phase, windings. The condition of the damaged windings in both
cases was consistent with progressive insulation breakdown caused by sustained
xDR
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IN 96-23 April 22, 1996 current well in excess of the secondary winding ampacity. Even with lower
current in the primary, the primary and secondary windings being wound
together caused thermal damage to the primary insulation with its ultimate
electrical failure as well. The A-phase windings of the potential transformer
for EDG-B were similarly damaged.
The blown fuse in the exciter for EDG-A was a power amplifier fuse in the
phase C line of the secondary branch circuit supplying one of the power
amplifiers. The blown fuse in the exciter for EDG-B was the corresponding
fuse in its phase B line. The licensee determined that the fuses had blown in
each case as the result of manual engine shutdown without exciter shutdown.
This had occurred with the generators unloaded (output breakers open) at the
end of the EDG test run preceding the prolonged high-power runs during which
the exciter caught fire. The blown fuses were not detected at the time
because these fuses had no blown-fuse indication. The fires occurred in both
cases after about an hour of sustained operation above full power. Because
there was no blown-fuse indication, the normal full and above full-power runs
for routine testing were conducted subsequently without knowing that the fuses
had blown and "single phased" the potential transformers.
Discussion
Single-phasing the secondary windings of the delta-connected potential
transformers, as a result of the blown fuses, left them at about 58 percent of
rated capacity with one phase winding carrying two-thirds of the total load.
The other two windings were effectively put in series with each other;
together they were now in parallel with the first winding, but with twice the
total impedance and hence, only one-third total load. This effect is
illustrated in Figure 2 of Attachment 1 to this notice. Subsequent operation
with the undetected blown fuse for about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at or above full load severely
overloaded the affected windings. It is expected that prolonged operation at
any power level significantly above the reduced capacity of the single-phased
potential transformers would eventually cause damage. However, even with the
imbalanced load, total excitation current demand from the potential
transformer, being within expected limits, was not sufficient to blow either
or both of the other two fuses. Operation continued until the overloaded
windings overheated and suffered progressive insulation breakdown, internal
short circuiting of the windings, and the resultant fire.
Although an undetected blown fuse for any reason could cause potential
transformer single-phasing and subsequent sustained high-power operation could
lead to fires, the reason for the blown fuses at Wolf Creek revealed another
apparent design deficiency. In both cases, the exciters were not shut down
automatically when the engines shut down due to mechanical causes not
accompanied by any of the normal electrical signals that would have otherwise
automatically shut down the exciters. On a normal manual shutdown from the
control panel, the exciter is turned off automatically as part of the normal
shutdown sequence of relay actuations. Similarly, in the event of one of the
standard alarm conditions that require immediate EDG shutdown, such as low
lube oil pressure, the system automatically shuts down the exciter.
IN 96-23 April 22, 1996 However, in both cases at Wolf Creek in which fuses were blown, the engines
had been shut down mechanically in a manner in which there were no attendant
electrical signals to the system to automatically shut down the exciters. In
the first instance, after it appeared that control of EDG-A may have been lost
upon a failed attempt at a normal shutdown (the unit tried to resume speed due
to an unrelated malfunction), the unit was shut down manually at the engine by
the operator shifting the engine manual control lever to the stop position
which shuts the fuel racks. In the second event, EDG-B shut itself down due
to a mechanical failure associated with the governor and the mechanical
overspeed trip device, but without an actual overspeed alarm condition
occurring. In systems equipped with underfrequency and/or voltz-per-hertz
protective features, this contingency is provided for, but the system at Wolf
Creek had no such features. Therefore, when the engines stopped in both cases
under the circumstances described, there was no electrical signal generated to
effect automatic exciter shutdown.
Engine shutdown without exciter shutdown caused a potential transformer
secondary fuse to blow in each case as follows: The exciters at Wolf Creek
(and Callaway) are type WNR manufactured by the Applied Products Division of
Westinghouse Electric Corporation (Westinghouse). Figure 1 of Attachment 1 to
this notice is a simplified functional block diagram of the affected static
exciter-voltage regulator design. The potential transformers that caught fire
(designated "PT" in Attachment 1) are Model 26616, delta-connected, 3-phase, step down 4160-Vac to 480-Vac, 45-kVA, 60-hz transformers, manufactured by the
NWL Transformer Company in Bordentown, New Jersey. The primary windings of
the PT are connected to the 4160-Vac, 3-phase generator output busses. The PT
secondary windings supply a portion of the generator DC field excitation
through power amplifiers. A major portion of the generator field excitation
with the generator under load is supplied by current transformers (designated
"CT" in Attachment 1) from the generator output through rectifiers. However, with a generator unloaded and its output breaker open, only a minimal amount
of excitation is provided by the current transformers; most of it being
provided by the potential transformers.
Expanded safety parameter display system trace printouts of EDG voltage, speed, and load for both events showed that as the generator slowed and
produced less output voltage (in both cases the generator was already unloaded
with its output circuit breaker open), the exciter, not having been turned
off, sensed this and demanded more generator field excitation current to
attempt to compensate. In both cases, the exciters attempted to maintain
voltage for about 20 seconds during engine coastdown, after which voltage
decayed rapidly. Attempting to maintain voltage with the generator slowing
caused excessive current in the potential transformer secondary (now the sole
source of excitation power with the generator breaker open) which blew one of
the fuses. With the resultant reduction in generator field excitation, coupled with the collapsing stator (armature) induced voltage as the machine
slowed, the available current was insufficient to blow either of the remaining
fuses. Although these Westinghouse exciters are used at the Standard Nuclear
Unit Power Plant System (SNUPPS) plants, Wolf Creek and Callaway, their
general features are not uncommon and other designs including Basler Electric
Type SB (series boost) exciters (without underfrequency or volts-per-hertz
IN 96-23 April 22, 1996 protection), are potentially susceptible to problems similar to those
described herein.
The licensee has installed blown fuse indication on the EDG exciter cabinets.
Prior to the installation of the blown fuse indication, the licensee
established procedures and trained operators to verify the condition of the
potential transformer secondary fuses following all EDG shutdowns, particularly those in which there are indications (such as no exciter shutdown
light) that the exciter was not turned off automatically. Procedures and
training also covered the conditions under which the exciter shutdown
pushbutton is to be actuated and under which the alternate power amplifier is
to be selected to maintain operability, e.g., in case an EDG demand signal is
received during the fuse verification, or in case a fuse should blow during
operation with or without an attendant fault or overload condition.
In other designs, such as newer Basler equipment, underfrequency protection is
often available that will independently shut down the exciter upon loss of the
prime mover. The licensee has installed volts-per-hertz protection to avoid
the conditions in question. However, EDG exciter systems of other designs
that remain on, either through a system design flaw or malfunction, after
engine mechanical shutdown may behave in a similar manner.
No specific action or written response is required by this information notice.
If you have any questions regarding this matter, please contact one of the
technical contacts listed below or the appropriate Office of Nuclear Reactor
Regulation (NRR) project manager.
4 tet- Dennis M. Crutche irector
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Stephen D. Alexander, NRR
(301) 415-2995 Internet:sda@nrc.gov
John Whittemore, RIV
(817) 860-8294 Internet:jcw@nrc.gov
Attachments:
1. Exciter Block Diagram and Blown Fuse Effect Diagram
2. List of Recently Issued NRC Information Notices
d44o fi-tX
Attachment 1 IN 96-23 April 22, 1996 Figure 1: Emergency aiesel Genertr Static Eaei-Voltage Regulator
SfrnpIlIled Functional Block Diagram
F1 Phnao A
St l £7 -it
With F2 blown, whi rigs Xl and X3 xi Sare X2 put in sedes an*dtogether, put In
o ~wbal <parallel with Xi. Thia capacity of the
Transformer PT Isthen reduced to about 58%.
6ftandsry t Powvr
PhaseD Amplfier
n
The erips Impadence of X2 and XS Istwice that of Xi. so
tht Xi must cauy twios the curent.
.s
Phase C
U-J
Foire 2: Effect on Potential Transfromr Sewondary Windings of Single-Pasing
Due to Blown Fum
Attachment 2 IN 96-23 April 22, 1996 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
96-22 Improper Equipment Set- 04/11/96 All holders of OLs or CPs
tings Due to the Use of for nuclear power reactors
Nontemperature-Compensated
Test Equipment
96-21 Safety Concerns Related 04/10/96 All U.S. NRC Medical to the
to the Design of the Door Licensees authorized to use
Interlock Circuit on brachytherapy sources in
Nucletron High-Dose Rate high- and pulsed-dose-rate
and Pulsed Dose Rate remote afterloaders
Remote Afterloading
Brachytherapy Devices
96-20 Demonstration of Associ- 04/04/96 All industrial radiography
ated Equipment Compliance licensees and radiography
with 10 CFR 34.20 equipment manufacturers
96-19 Failure of Tone Alert 04/02/96 All holders of OLs or CPs
Radios to Activate When for nuclear power reactors
Receiving a Shortened
Activation Signal
96-18 Compliance with 10 CFR 03/25/96 All material licensees
Part 20 for Airborne authorized to possess and
Thorium use thorium in unsealed
form
95-03 Loss of Reactor Coolant 03/25/96 All holders of OLs or CPs
Supp. 1 Inventory and Potential for PWR power plants
Loss of Emergency Mitiga- tion Functions While in a
Shutdown Condition
96-17 Reactor Operation Incon- 03/18/96 All holders of OLs or CPs
sistent with the Updated for nuclear power reactors
Final Safety Analysis
Report
96-16 BWR Operation with 03/14/96 All holders of OLs or CPs
Indicated Flow Less Than for boiling-water reactors
Natural Circulation
OL - Operating License
CP - Construction Permit
IN 96-23 April 22, 1996 protection), are potentially susceptible to problems similar to those
described herein.
The licensee has installed blown fuse indication on the EDG exciter cabinets.
Prior to the installation of the blown fuse indication, the licensee
established procedures and trained operators to verify the condition of the
potential transformer secondary fuses following all EDG shutdowns, particularly those in which there are indications (such as no exciter shutdown
light) that the exciter was not turned off automatically. Procedures and
training also covered the conditions under which the exciter shutdown
pushbutton is to be actuated and under which the alternate power amplifier is
to be selected to maintain operability, e.g., in case an EDG demand signal is
received during the fuse verification, or in case a fuse should blow during
operation with or without an attendant fault or overload condition.
In other designs, such as newer Basler equipment, underfrequency protection is
often available that will independently shut down the exciter upon loss of the
prime mover. The licensee has installed volts-per-hertz protection to avoid
the conditions in question. However, EDG exciter systems of other designs
that remain on, either through a system design flaw or malfunction, after
engine mechanical shutdown may behave in a similar manner.
No specific action or written response is required by this information notice.
If you have any questions regarding this matter, please contact one of the
technical contacts listed below or the appropriate Office of Nuclear Reactor
Regulation (NRR) project manager.
original signed by
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Stephen D. Alexander, NRR
(301) 415-2995 Internet:sda@nrc.gov
John Whittemore, RIV
(817) 860-8294 Internet:jcw@nrc.gov
Attachments:
1. Exciter Block Diagram and Blown Fuse Effect Diagram
2. List of Recently Issued NRC Information Notices
DOCUMENT NAME: 96-23.IN Tech Editor reviewed 11/10/94
To receive a copy of this document, Indicate In the box: ACT - Copy without enclosures E - Copy with enclosures _N No copy
OFFICE Cntacts* IE C IB* I CPECB* D/DPAMM
NAME SAlexander IRGallo AChaffee DC eld
_JWhittemore /
DATE 4/11/96 4/15/96 4/16/96 _ 4_ 96 OFFICIAL RECORD COPY
IN 96-XX
April XX, 1996 The licensee has installed blown fuse indication on the EDG exciter cabinets.
Prior to the installation of the blown fuse indication, the licensee
established procedures and trained operators to verify the condition of the
potential transformer secondary fuses following all EDG shutdowns, particularly those in which there are indications (such as no exciter shutdown
light) that the exciter was not turned off automatically. Procedures and
training also covered the conditions under which the exciter shutdown
pushbutton is to be actuated and under which the alternate power amplifier is
to be selected to maintain operability, e.g., in case an EDG demand signal is
received during the fuse verification, or in case a fuse should blow during
operation with or without an attendant fault or overload condition.
In other designs, such as newer Basler equipment, underfrequency protection is
often available that will independently shut down the exciter upon loss of the
prime mover. The licensee has installed volts-per-hertz protection to avoid
the conditions in question. However, EDG exciter systems of other designs
that remain on, either through design flaw or malfunction, after engine
mechanical shutdown may behave in a similar manner.
No specific action or written response is required by this information notice.
If you have any questions regarding this matter, please contact one of the
technical contacts listed below or the appropriate Office of Nuclear Reactor
Regulation (NRR) project manager.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Stephen D. Alexander, NRR John Whittemore, RIV
(301) 415-2995 (817) 860-8294 Internet:sda~nrc.gov Internet:jcw~nrc.gov
Attachments:
1. Exciter Block Diagram and Blown Fuse Effect Diagram
2. List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\IN\EDGFIRE.REV Tech Editor reviewed 11/10/94
Ca - Copy without enclosures 'E - Copy with enclosures ND- No copy
To receive a copy of this document, indicate hIthe box:
OFFICE Contacts* l E C/SIB* l C/PECB I D/DRPM I
NAME SAlexander RGallo ACh~tee DCrutchfield
JWhittemore I I /96 DATE 4/11/96 4/15/96 41 /96 M4/
It
10" v 5to
nrrlTAIRrr~n opyI *ow
to .t~ . s.Je .. _ *-%c$
'0b
¢ # jalW'est Cad dolo < ~
lacke he1.1ss?
IN 95-XX
April XX, 1996 The licensee has installed blown fuse indication on the EDG exciter cabinets.
Prior to the installation of the blown fuse indication, the licensee
established procedures and trained operators to verify the condition of the
potential transformer secondary fuses following all EDG shutdowns, particularly those in which there are indications (such as no exciter shutdown
light) that the exciter was not turned off automatically. Procedures and
training also covered the conditions under which the exciter shutdown
pushbutton is to be actuated and under which the alternate power amplifier is
to be selected to maintain operability, e.g., in case an EDG demand signal is
received during the fuse verification, or in case a fuse should blow during
operation with or without an attendant fault or overload condition.
In other designs, such as newer Basler equipment, underfrequency protection is
often available that will independently shut down the exciter upon loss of the
prime mover. The licensee has installed volts-per-hertz protection to avoid
the conditions in question. However, EDG exciter systems of other designs
that remain on, either through design flaw or malfunction, after engine
mechanical shutdown may behave in a similar manner.
No specific action or written response is required by this information notice.
If you have any questions regarding this matter, please contact one of the
technical contacts listed below or the appropriate Office of Nuclear Reactor
Regulation (NRR) project manager.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Stephen D. Alexander, NRR John Whittemore, RIV
(301) 415-2995 (817) 860-8294 Attachments: I
1. Exciter Block Diagram and Blown Fuse Effect Diagram
2. List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\IN\EDGFIRE.REV Tech Editor reviewed 11/10/94 To receive a copy of this document, Indicate In the box: 'C - Copy Without enclosures 'E' - Copy with enclosures _N" = No copy
OFFICE Contacts E C/SI [C/PECB D
NAME exanderf xfRG %-' AChaffee DCrutchfield
JWhittemore-i j I
DATE 4/11/96 4/16/96 4/ /96 4/ /96 OFFICIAL RECORD COPY
MA+
IN 95-XX
September XX, 1995 The licensee is evaluating installation of blown fuse indication on the EDG
exciter cabinets, but as a temporary measure, the licensee established
procedures and trained operators to verify the condition of the PT secondary
fuses following all EDG shutdowns, particularly those in which there are
indications (such as no exciter shutdown light) that the exciter was not
turned off automatically. Procedures and training will also cover the
conditions under which the exciter shutdown pushbutton is to be actuated and
under which the alternate power amplifier is to be selected to maintain
operability, e.g., in case an EDG demand signal is received during the fuse
verification, or in case a fuse should blow during operation with or without
an attendant fault or overload condition.
The licensee, in consultation with Westinghouse (and Cutler-Hammer, which now
owns the exciter design), the architect/engineer (Bechtel), and the EDG system
supplier (Coltec), is evaluating the design of this EDG system in terms of
ensuring automatic exciter shutdown in case of a manual or other mechanical
engine shutdown without electrical signals, including development of such a
provision if required. The licensee is also evaluating procedures and
operator training to prevent blowing the exciter potential transformer power
amplifier fuses under the condition in question. In other designs, such as
newer Basler equipment, underfrequency protection is often available that will
independently shut down the exciter upon loss of the prime mover. Volts-per- hertz protection can also serve to avoid the conditions in question. However, EDG exciter systems of other designs that remain on, either through design
flaw or malfunction, after engine mechanical shutdown could typically be
expected to behave in a similar manner.
No specific action or written response is required by this information notice.
If you have any questions regarding this matter, please contact one of the
technical contacts listed below or the appropriate Office of Nuclear Reactor
Regulation (NRR) project manager.
/ /
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Stephen D. Alexander, NRR, (301) 415-2995 John Whittemore, RIV, (817) 860-8294 Attachments:
1. Exciter Block Diagram and Blown Fuse Effect Diagram
2. List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\IN\EDGFIRE.REV *See previous concurrence.
To receive a copy of this document, Indicate Inthe box: 'C . Copy without enclosures SEw - Copy with enclosures N *- No copy
OFFICE VIS/SIB I E SC:VIS/SIB I N TECHED I N C:SIB/DOTSI C D:DRIL I N
NAME SAlexander* GCwalina* MMejac* RGallo* RLSpessard*
DATE 10/26/94 10/27/94 11/10/94 12/27/94 12/27/94 OFFICE RIV/DRS I E PECB/DRPM I E SC:OECB/DOPS I N OECB/DOPS I IC/EEL
I
NAME JWhittemore* TKoshy* EGoodwin* ,,- ) JRKiessel* IJCalvo*
DATE
.
10/27/94 E-mail 09/08/95 01/05/95
.
2&&222@03/02/95 I -. .
108/10/95 OFFICE C/OECB ;9PS I N DIDRPM l [Y(> I (
NAME ACtiffe* AT(U DCrutchfield A f
DATE 103/1U/9514'1" / /95
COPY
OFFICIAL RECORD -----
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list | - Information Notice 1996-01, Potential For High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-01, Potential for High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-02, Inoperability of Power-Operated Relief Valves Masked by Downstream Indications During Testing (5 January 1996, Topic: Stroke time)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation as a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation As a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-04, Incident Reporting Requirements for Radiography Licensees (10 January 1996, Topic: Brachytherapy)
- Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel (18 January 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-06, Design & Testing Deficiencies of Tornado Dampers at Nuclear Power Plants (25 January 1996)
- Information Notice 1996-07, Slow Five Percent Scram Insertion Times Caused by Viton Diaphragms in Scram Solenoid Pilot Valves (26 January 1996)
- Information Notice 1996-08, Thermally Induced Pressure Locking of a High Pressure Coolant Injection Gate Valve (5 February 1996, Topic: Anchor Darling, Cold shutdown justification)
- Information Notice 1996-09, Damage in Foreign Steam Generator Internals (12 February 1996, Topic: Earthquake)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which Is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential For Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential for Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996)
- Information Notice 1996-12, Control Rod Insertion Problems (15 February 1996)
- Information Notice 1996-13, Potential Containment Leak Paths Through Hydrogen Analysis (26 February 1996)
- Information Notice 1996-14, Degradation of Radwaste Facility Equipment at Millstone Nuclear Power Station, Unit 1 (1 March 1996)
- Information Notice 1996-15, Unexpected Plant Performance During Performance of New Surveillance (8 March 1996)
- Information Notice 1996-16, BWR Operation with Indicated Flow Less than Natural Circulation (14 March 1996)
- Information Notice 1996-17, Reactor Operation Inconsistent with the Updated Final Safety Analysis Report (18 March 1996)
- Information Notice 1996-18, Compliance with 10 CFR Part 20 for Airborne Thorium (25 March 1996, Topic: Brachytherapy)
- Information Notice 1996-19, Failure of Tone Alert Radios to Activate When Receiving a Shortened Activation Signal (2 April 1996)
- Information Notice 1996-20, Demonstration of Associated Equipment Compliance with 10 CFR 34.20 (4 April 1996, Topic: Brachytherapy)
- Information Notice 1996-21, Safety Concerns Related to the Design of the Door Interlock Circuit on Nucletron High-Dose Rate and Pulsed Dose Rate Remote Afterloading Brachytherapy Devices (10 April 1996, Topic: Brachytherapy)
- Information Notice 1996-22, Improper Equipment Settings Due to Use of Nontemperature-Compensated Test Equipment (11 April 1996, Topic: Brachytherapy)
- Information Notice 1996-23, Fires in Emergency Diesel Generator Exciters During Operation Following Undetected Fuse Blowing (22 April 1996, Topic: Brachytherapy)
- Information Notice 1996-24, Preconditioning of Molded-Case Circuit Breakers Before Surveillance Testing (25 April 1996, Topic: Brachytherapy)
- Information Notice 1996-25, Traversing In-Core Probe Overwithdrawn at Lasalle County Station, Unit 1 (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems with Overhead Cranes (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems With Overhead Cranes (30 April 1996)
- Information Notice 1996-27, Potential Clogging of High Pressure Safety Injection Throttle Valves During Recirculation (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-28, Suggested Guidance Relating to Development and Implementation of Corrective Action (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-29, Requirements in 10 CFR Part 21 for Reporting and Evaluating Software Errors (20 May 1996, Topic: Brachytherapy)
- Information Notice 1996-30, Inaccuracy of Diagnostic Equipment for Motor-Operated Butterfly Valves (21 May 1996)
- Information Notice 1996-31, Cross-Tied Safety Injection Accumulators (22 May 1996)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (II) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Non-Destructive Examination)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (ii) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Nondestructive Examination)
- Information Notice 1996-33, Erroneous Data From Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-33, Erroneous Data from Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-34, Hydrogen Gas Ignition During Closure Welding of a VSC-24 Multi-Assembly Sealed Basket (31 May 1996)
- Information Notice 1996-35, Failure of Safety Systems on Self-Shielded Irradiators Because of Inadequate Maintenance and Training (11 June 1996)
- Information Notice 1996-36, Degradation of Cooling Water Systems Due to Icing (12 June 1996, Topic: High winds, Ultimate heat sink, Frazil ice)
- Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown (18 June 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-38, Results of Steam Generator Tube Examinations (21 June 1996)
- Information Notice 1996-39, Estimates of Decay Heat Using ANS 5.1 Decay Heat Standard May Vary Significantly (5 July 1996)
- Information Notice 1996-40, Defciencies in Material Dedication and Procurement Practices and in Audits of Vendors (7 October 1996, Topic: Coatings, Troxler Moisture Density Gauge)
- Information Notice 1996-41, Effects of a Decrease in Feedwater Temperature on Nuclear Instrumentation (26 July 1996)
- Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves (5 August 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-43, Failures of General Electric Magne-Blast Circuit Breakers (2 August 1996)
... further results |
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