Misadjustment Between General Electric 4.16-kV Circuit Breakers & Their Associated CubiclesML031070173 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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: |
12/03/1993 |
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From: |
Grimes B Office of Nuclear Reactor Regulation |
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To: |
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References |
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IN-93-091, NUDOCS 9311190456 |
Download: ML031070173 (11) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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 [[: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 [[: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, D.C. 20555 December 3, 1993 NRC INFORMATION NOTICE 93-91: MISADJUSTMENT BETWEEN GENERAL ELECTRIC 4.16-KY
CIRCUIT BREAKERS AND THEIR ASSOCIATED CUBICLES
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 multiple common-cause failures
of logic functions due to misadjustment between General Electric (GE) 4.16-kv
Magne-Blast circuit breakers and their associated cubicles. It is expected
that recipients will review the information for applicability to their
facilities and considei 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
During surveillance testing at the Duane Arnold Energy Center on
September 16, 1993, the "B"standby diesel generator output breaker (1A411) to
essential bus 1A4 failed to close after simulation of a loss of offsite power
(LOOP) and loss of coolant accident (LOCA) signal. During normal plant
operation, the normally closed feeder breaker (1A402) from the startup
transformer and the normally open feeder breaker (1A401) from the standby
transformer provide essential bus 1A4 with two offsite sources of power. One
of the "b"contacts (closed when the breaker is open) from each offsite power
feeder breaker stationary auxiliary switch (mounted in the breaker cubicle) is
used in the diesel generator output breaker automatic close-permissive circuit
to indicate whether the two offsite power feeder breakers are open or closed.
A closed indication from either breaker 1A401 or IA402 will prevent the diesel
generator output breaker from closing automatically (unsynchronized) onto
essential bus 1A4. Breakers 1A401, IA402, and IA411 are GE Magne-Blast types.
Troubleshooting revealed that the auto-closing logic for the diesel generator
output breaker was not being completed because a lb" contact from breaker
IA401 was open, indicating that the breaker was closed when the breaker was
actually open. When the breaker 1A401 is open and in its fully elevated
operating position in the cubicle, there is supposed to be a small gap or
clearance between the breaker plunger and the stationary auxiliary switch
9311190456 PtR tE Nok'cxe qL
9 oC A3 120 3
KAIN 93-91 December 3, 1993 operating rod (see Attachment 1, Figure 2) to ensure positive closure of all
lb" contacts in the stationary auxiliary switch. However, the plunger of
breaker IA401 was found to be actually pushing its stationary auxiliary switch
operating rod up about 4.8 mm [3/16 inch] with the breaker open. This
apparently occurred when the breaker was last elevated into its operating
position which then opened one or more lb' contacts (including the one in the
diesel generator breaker control circuit) from their normally closed position.
The misalignment rendered the "B*diesel generator inoperable from
July 21, 1993, to September 25, 1993, because it was not capable of
automatically closing onto the 1A4 bus.
Upon investigation, the licensee determined that it had performed routine
preventive maintenance on breaker IA401 (a vertically racking, GE model
AM-4.16-350-2H) on July 21, 1993, which consisted essentially of lowering the
breaker to the bottom of the cubicle, inspecting and lubricating it, and
cycling the breaker after elevating it to its test position. However, cycling
the breaker in the test position does not operate the stationary auxiliary
switch unless a special test link is fitted. Therefore, this action alone
does not verify the various control functions performed by the stationary
auxiliary switch contacts. The wB" diesel generator monthly tests were
completed satisfactorily during the operating cycle, but these tests use a
synchronized manual closure of the diesel generator output breaker, which
bypasses the breaker automatic close permissive (dead bus) circuit. Even
though the once-per-operating-cycle integrated LOOP/LOCA test detected the
failure, the potential existed for the "B"diesel generator to be inoperable
for an entire operating cycle, or when required during an outage. The
periodic routine preventive maintenance performed on breaker IA401, which may
have resulted in the breaker misadjustment and opening of a stationary
auxiliary switch contact, was not scheduled in conjunction with a surveillance
test (such as the integrated LOOP/LOCA test) that would verify proper
operation of the auxiliary switch contacts.
Discussion
Misadjustment between the stationary auxiliary switch and the breaker plunger
on 4.16-kv breakers has the potential to cause multiple common-cause failures
of many different logic functions that rely on these auxiliary switch
contacts. The circuit breaker plunger to auxiliary switch operating rod
adjustment may be affected by breaker maintenance, switchgear maintenance, differences in operating plunger height of interchangeable breakers, differences in breaker cubicles and breaker position switches, and non- repeatability in breaker height when racking in breakers.
During breaker maintenance on July 21, 1993, the licensee for the Duane Arnold
plant checked and adjusted the height between the breaker lifting rail and the
operating plunger in accordance with the applicable GE breaker technical
manual (GEK-7320F, Revision 2/80, 'Magne-Blast Circuit Breakers Types AM-4.16-
350-2C and -2H"). However, the licensee did not verify the open breaker
plunger-to-operating-rod clearance of 0 to 3.2 mm [O to 1/8 inch] as
recommended in the applicable GE switchgear technical manual (GEH-1802,
"Instructions - Metal-Clad Switchgear Types M26 and M36 for Magne-Blast
- v VIN 93-91 December 3, 1993 Circuit Breakers Types AM-4.16 and AM-13.8"). In order to ensure a minimum
gap for positive 3b' contact closure, the manufacturer (now called the GE
Specialty Breaker product department) provided additional guidance in its
Service Advice Letter (SAL) 073-323.1, issued February 1, 1978, specifying a
gap of 1.6 mm [1/16 inch] to 3.2 mm (1/8 inch]. This SAL also provides the
recommended sequence of adjustments.
Further conversations between the licensee and GE determined that there are
additional dimensional checks (not contained in either the breaker or
switchgear technical manual) which would provide additional assurance of
proper auxiliary contact operation after breaker maintenance. These
additional dimensional checks for a closed breaker (see Attachment 1, Figure 1) are:
- 7.9 +/- 1.6 mm [5/16 +/- 1/16 inch] from the top of the circuit breaker
plunger nut to the bottom of the auxiliary switch operating rod casing.
- All law contacts are closed with at least 23.8 mm [15/16 inch] travel of
the operating rod.
NOTE: Total specified travel of the plunger is 27 +/- 1.6 mm
[1 1/16 +/- 1/16 inch]. If the total plunger travel is set at
the minimum specified value of 25.4 mm [1 inch] and the
plunger-to-operating-rod gap is set at the maximum specified
value of 3.2 mm [1/8 inch], the amount of travel of the
operating rod would only be 22.2 mm [7/8 inch], or less than
the required 23.8 mm [15/16 inch] necessary to fully ensure
closure of the Oa" auxiliary contacts when the breaker
closes.
For an open breaker (see Attachment 1, Figure 2) the additional dimensional
check is:
- The operating rod collar should rest on the operating rod casing, and
the operating rod should not be displaced by the plunger of an open
breaker.
GE stated that it will issue a SAL to clarify the instructions and dimensions
contained in the previous publications. Meanwhile, licensee inquiries on this
subject may be directed to GE Nuclear Energy Power Delivery Services in
King of Prussia, Pennsylvania (Phone: 215-992-6049/Fax: 215-992-6191.)
Related Generic Communications
Test Link in 4.16 KV General Electric Switchgear, dated
September 16, 1991.
IN 93-91 December 3, 1993 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 clear Reactor
Regulation (NRR) project manager. e
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Jay A. Hopkins, RIII
(319) 851-5111 David S. Butler, RIII
(708) 790-5796 Stephen D. Alexander, NRR
(301) 504-2995 Attachments:
1. Magne-Blast Circuit Breaker Plunger and
Stationary Auxiliary Switch Adjustments
2. List of Recently Issued NRC Information Notices
Attachment 1
,V~ xIN 93-91 Decembr 3, 1993 MAGNE-BLAST CIRCUIT BREAKER PLUNGER - STATIONARY
AUXILIARY SWITCH ADJUSTMENTS (ADAPTED FROM GE
MVSD FIELD INSTALLATION DRAWING 0172C7558)
(Not to Scale)
a, (MINIMUM TRAVEL
"116'J TO ENSURE ALL
"A"
CONTACT
S
I L 'CLOSE
SWITCH
OPERATING'
WITH BREAKER OPEN:
MINIMUM GAP
GAP: I TO ENSURE ALL "By
0-NO"PER GE-1802
CONTACT
S CLOSED
PER SAL. 073-323.1 [To
1 SET BY ADDING OR MAXIMUM GAP
REMOVING PWNGER TO ENSURE FULL
SHIMS (WASHERS) SWITCH ROD
TRAVEL FOR
"A"
CONTACT
CLOSURE WHEN
BREAKER CLOSES
i
Figure 1 Figure 2 BREAKER CLOSED BREAKER OPEN
At^,thment 2 IN 93-91 December 3, 1993 Page 1 of I
LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
93-90 Unisolatable Reactor 12/01/93 All holders of OLs or CPs
Coolant System Leak for nuclear power reactors.
Following Repeated
Applications of Leak
Sealant
93-89 Potential Problems with 11/26/93 All holders of OLs or CPs
BWR Level Instrumentation for boiling water reactors.
Backfill Modifications
93-88 Status of Motor-Operated 11/30/93 Al 1 holders of OLs or CPs
Valve Performance Pre- for nuclear power reactors.
diction Program by the
Electric Power Research
Institute
93-87 Fuse Problems with 11/04/93 All holders of OLs or CPs
Westinghouse 7300 for nuclear power reactors.
Printed Circuit Cards
Identification of Iso- 10/29/93 All holders of OLs or CPs
topes in the Production for test and research
and Shipment of Byproduct reactors.
Material at Non-power
Reactors
93-85 Problems with X-Relays 10/20/93 All holders of OLs or CPs
in D8- and DHB-Type for nuclear power reactors.
Circuit Breakers Manu- factured by Westinghouse
93-84 Determination of Westing- 10/20/93 All holders of OLs or CPs
house Reactor Coolant for pressurized water
Pump Seal Failure reactors (PWRs).
93-83 Potential Loss of Spent 10/07/93 All holders of OLs or CPs
Fuel Pool Cooling for boiling water reactors
Following A Loss of (BWRs).
Coolant Accident (LOCA)
OL = Operating License
CP - Construction Permit
-'-' IN 93-91 December 3, 1993 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.
orig /s/'d by BKGrimes
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Jay A. Hopkins, RIII
(319) 851-5111 David S. Butler, RIII
(708) 790-5796 Stephen D. Alexander, NRR
(301) 504-2995 Attachments:
1. Magne-Blast Circuit Breaker Plunger and
Stationary Auxiliary Switch Adjustments
2. List of Recently Issued NRC Information Notices
- Crr PDFVTflhIZ rnNCIIRRNFCF
OFFICE *OEAB:NH RS *OGCB:DORS *Tech. Ed. I *RGN-III *RGN-III
NAME NHunemuller PWen DGable I JHopkins DButler
nATr
I
Ilf/lh/3 IA /15K/Q93 10/18193 10/21/93 10/21/93 I I
- RGN-III *OEAB:DORS *OEAB:DORS *C:EELB:DWRS *C:RVIB:DORS C:OGCB:DORS
RGreger RDennig AChaffee CBerlinger LNorrholm *GMarcus
10/21/93 /25/93 10/27/93 10/27/93 11/17/93 11/18/93 i
1ALY93_
DOCUMENT NAME: 93-91.IN
K>
IN 93-xx
November xx, 1993 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.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Jay A. Hopkins, RIII
(319) 851-5111 David S. Butler, RIII
(708) 790-5796 Stephen D. Alexander, NRR
(301) 504-2995 Attachments:
1. Magne-Blast Circuit Breaker Plunger and Stationary Auxiliary
Switch Adjustments
2. List of Recently Issued NRC Information Notices
OFFICE *OEAB:DORS *OGCB:DORS *Tech Ed._ *RGNIII *RGN1III
NAME NHunemuller PWen DGable JHopkins DButler
DATF 10/15/91 10/15/93 10/18/93 I 10/21/93 10/21/93
_1 -i . . ._ ._ _ . ,, _ _ _, _, _ I _ ,I , I -_,
- RGN-III *OEAB:DORS *OEAB:DORS *C:EELB:DORS *C:RVIB:DORS C:OGCB:DORS
RGreger RDennig AChaffee CBerlinger LNorrholm LGMarcus
10/21/93 10/25/93 10/27/93 I, -_
10/27/93
_9__3_
11/17/93 11/l&/93 j
D:DORS:NRR
BKGrimes
I 11/ /93 i
DOCUMENT NAME: ADJGEBKR.WEN
K>
IN 93-xx
November xx, 1993 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.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Jay A. Hopkins, RIII
(319) 851-5111 David S. Butler, RIII
(708) 790-5796 Stephen D. Alexander, NRR
(301) 504-2995 Attachments:
1. -1 4h16 Circuit Breaker Plunger and Stationary Auxiliary
Switch Operating-Red- Adjustments
2. List of Recently Issued NRC Information Notices
OFFICE *OEAB:DORS *OGCB:DORS I *Tech. Ed. I *RGN-III I *RGN-III
NAME NHunemuller PWen DGable I JHopkins I DButler
,,
DATE
__
10/15/93
_,__,__ 10/15/93
,__,___ , 10/18/93
__,__,__ , 10121/931 10/1i Al
- RGN-III *OEAB:DORS *OEAB:DORS *C:EELB:DORS f :DORS C:OGCB:DORS
RGreger RDennig AChaffee CBeringer No lm GMarcus
10/21/93 _ 10/25/93 110/27/93 110/27/93 10/1 7/93 it/ /93 D:DORS:NRR
BKGrimes
iI/ /93 DOCUMENT NAME: ADJGEBKR.WEN
IN 93-xx
November xx, 1993 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.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Jay A. Hopkins, RIII
(319) 851-5111 David S. Butler, RIII
(708) 790-5796 Stephen D. Alexander, NRR
(301) 504-2995 Attachments:
1. Magne-Blast Circuit Breaker Plunger and Stationary Auxiliary
Switch Adjustments
2. List of Recently Issued NRC Information Notices
OFFICE *OEAB:DORS *OGCB:DORS *Tech. Ed. *RGN-III *RGN-III
NAME NHunemuller PWen I DGable JHopkins DButler
DATE 10/15/93 10/15/93 10/18/93 I 10/21/93 10/21/93
, , . , , , , , I
- RGN-III *OEAB:DORS *OEAB:DORS *C:EELB:DWORS 1 *C:RVIB:DORS C:OGCB:DORS
RGreger RDenng AChaffee CBerlinger LNorrholm GMarcus
10/21/93 10/25/93 10/27/93 10/27/93 11/17/93 11/ /93 D:DORS:NRR
BKGrimes
11/ /93
.. . - --...---..
_.
DOCUMENT NAME: ADJGEBKR.WEN Mm:
A
a 5ffe atn# co"Mwtef- AA dVe
11/17/43 ,
I
1. Closed Circuit Breaker Operating Plunger and Auxiliary Switch Mechanism
Operating Rod Configuration
2. Open Circuit Breaker Operating Plunger and Auxiliary Switch Mechanism
Operating Rod Configuration
3. List of Recently Issued NRC Information Notices
CONCURRENCE:
OEAB V *sM$ OGCB RGN--III
NHune Iller lo18/q3, JHopkins IDButler RGrieger Tech. Ed.
OEAB~ij& OEA"'4 EELB(M RVIB OGCB
IV%
RDen i g/ t> AChgfI
lo It1 CBeriiner
'°[1 in LNorrholm GMarcus
DORS
BGrimes
|
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|
list | - Information Notice 1993-01, Accuracy of Motor-Operated Valve Diagnostic Equipment Manufactured by Liberty Technologies (4 January 1993)
- Information Notice 1993-02, Malfunction of a Pressurizer Code Safety Valve (4 January 1993, Topic: Loop seal)
- Information Notice 1993-04, Investigation and Reporting of Misadministrations by the Radiation Safety Officer (7 January 1993)
- Information Notice 1993-05, Locking of Radiography Exposure Devices (14 January 1993, Topic: Uranium Hexafluoride)
- Information Notice 1993-06, Potential Bypass Leakage Paths Around Filters Installed in Ventilation Systems (22 January 1993)
- Information Notice 1993-07, Classification of Transportation Emergencies (1 February 1993)
- Information Notice 1993-08, Failure of Residual Heat Removal Pump Bearings Due to High Thrust Loading (1 February 1993, Topic: Probabilistic Risk Assessment)
- Information Notice 1993-09, Failure of Undervoltage Trip Attachment on Westinghouse Model DB-50 Reactor Trip Breaker (2 February 1993)
- Information Notice 1993-10, Dose Calibrator Quality Control (2 February 1993)
- Information Notice 1993-11, Single Failure Vulnerability of Engineered Safety Features Actuation Systems (4 February 1993)
- Information Notice 1993-12, Off-Gassing in Auxiliary Feedwater System Raw Water Sources (11 February 1993)
- Information Notice 1993-13, Undetected Modification of Flow Characteristics in High Pressure Safety Injection System (16 February 1993)
- Information Notice 1993-14, Clarification of 10 CFR 40.22, Small Quantities of Source Material (18 February 1993)
- Information Notice 1993-15, Failure to Verify the Continuity of Shunt Trip Attachment Contacts in Manual Safety Injection and Reactor Trip Switches (18 February 1993)
- Information Notice 1993-16, Failures of Not-Locking Devices in Check Valves (19 February 1993, Topic: Anchor Darling, Flow Induced Vibration)
- Information Notice 1993-17, Safety Systems Response to Loss of Coolant and Loss of Offsite Power (25 March 1994, Topic: Fire Barrier, Backfit)
- Information Notice 1993-18, Portable Moisture-Density Gauge User Responsibilities During Field Operations (10 March 1993, Topic: Moisture Density Gauge, Moisture-Density Gauge, Stolen)
- Information Notice 1993-19, Slab Hopper Bulging (17 March 1993, Topic: Hydrostatic)
- Information Notice 1993-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators (24 March 1993)
- Information Notice 1993-21, Summary of NRC Staff Observations Compiled During Engineering Audits or Inspections of Licensee Erosion/Corrosion Programs (25 March 1993, Topic: Weld Overlay)
- Information Notice 1993-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers Due to Support Lever Failure (26 March 1993)
- Information Notice 1993-23, Weschler Instruments Model 252 Switchboard Meters (31 March 1993)
- Information Notice 1993-24, Distribution of Revision 7 of NUREG-1021, Operation Licensing Examiner Standards (31 March 1993, Topic: Job Performance Measure)
- Information Notice 1993-25, Electrical Penetration Assembly Degradation (1 April 1993)
- Information Notice 1993-26, Grease Soldification Causes Molded-Case Circuit Breaker Failure to Close (31 January 1994)
- Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization (8 April 1993, Topic: Reactor Vessel Water Level)
- Information Notice 1993-28, Failure to Consider Loss of DC Bus in the Emergency Core Cooling System Evaluation May Lead to Nonconservative Analysis (9 April 1993, Topic: Fuel cladding)
- Information Notice 1993-29, Problems with the Use of Unshielded Test Leads in Reactor Protection System Circuitry (12 April 1993)
- Information Notice 1993-30, NRC Requirements for Evaluation of Wipe Test Results; Calibration of Count Rate Survey Instruments (12 April 1993)
- Information Notice 1993-31, Training of Nurses Responsible for the Care of Patients with Brachytherapy Implants (13 April 1993, Topic: Brachytherapy)
- Information Notice 1993-32, Nonconservative Inputs for Boron Dilution Events Analysis (21 April 1993, Topic: Shutdown Margin)
- Information Notice 1993-33, Potential Deficiency of Certain Class Ie Instrumental and Control Cables (28 April 1993)
- Information Notice 1993-33, Potential Deficiency of Certain Class IE Instrumental and Control Cables (28 April 1993, Topic: Brachytherapy)
- Information Notice 1993-34, Potential for Loss of Emergency Cooling Function Due to a Combination of Operational and Post-LOCA Debris in Containment (6 May 1993, Topic: Brachytherapy)
- Information Notice 1993-35, Insights from Common-Cause Failure Events (12 May 1993, Topic: Brachytherapy)
- Information Notice 1993-36, Notifications, Reports, and Records of Misadministrations (7 May 1993, Topic: Brachytherapy)
- Information Notice 1993-37, Eyebolts with Indeterminate Properties Installed in Limitorque Valve Operator Housing Covers (19 May 1993, Topic: Brachytherapy)
- Information Notice 1993-38, Inadequate Testing of Engineered Safety Features Actuation Systems (24 May 1993)
- Information Notice 1993-39, Radiation Beams From Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-39, Radiation Beams from Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-40, Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material (26 May 1993, Topic: Safe Shutdown, Fire Barrier, Fire Protection Program)
- Information Notice 1993-41, One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Fire Barrier Systems (28 May 1993, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1993-42, Failure of Anti-Rotation Keys in Motor-Operated Valves Manufactured by Yelan (9 June 1993)
- Information Notice 1993-43, Use of Inappropriate Lubrication Oils in Satety-Related Applications (10 June 1993)
- Information Notice 1993-44, Operational Challenges During a Dual-Unit Transient (15 June 1993)
- Information Notice 1993-45, Degradation of Shutdown Cooling System Performance (16 June 1993)
- Information Notice 1993-46, Potential Problem with Westinghouse Rod Control System and Inadvertent Withdrawal of Single Rod Control Cluster Assembly (10 June 1993)
- Information Notice 1993-47, Unrecognized Loss of Control Room Annunciators (18 June 1993)
- Information Notice 1993-48, Failure of Turbine-Driven Main Feedwater Pump to Trip Because of Contaminated Oil (6 July 1993)
- Information Notice 1993-49, Improper Integration of Software Into Operating Practices (8 July 1993)
... further results |
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