Failures of Not-Locking Devices in Check ValvesML031080101 |
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 |
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Issue date: |
02/19/1993 |
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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-93-016, NUDOCS 9302120052 |
Download: ML031080101 (12) |
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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, D.C. 20555 February 19, 1993 NRC INFORMATION NOTICE 93-16: FAILURES OF NUT-LOCKING DEVICES IN CHECK VALVES
Addressees
power
All holders of operating licenses or construction permits for nuclear
reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information devices in
notice to alert addressees to problems found with the nut-locking the
certain check valves. It is expected that recipients will review as
information for applicability to their facilities and consider actions, in
appropriate, to avoid similar problems. However, suggestions contained
this information notice are not NRC requirements; therefore, no specific
action or written response is required.
Description of Circumstances
Trojan Nuclear Plant
shutdown, On December 20, 1991, the Trojan Nuclear Plant was in mode 5, cold licensee) was
for a refueling outage. Portland General Electric Company (the (RHR) pumps.
conducting routine inservice testing of the residual heat removal was lower
While testing the A RHR pump, operators noticed that indicated flow the B RHR
than expected and the B RHR pump was rotating backwards, indicating
pump discharge check valve was leaking.
check
On January 21, 1992, the licensee inspected the B RHR pump discharge fasten
valve. The licensee discovered the nut, washer, and lock wire which
On
the disk to the swing arm (see diagram, Attachment 1) were missing.check valve.
January 28, 1992, the licensee inspected the A RHR pump discharge
The licensee discovered the nut was loose and the lock wire was broken, although the disk nut and washer were in place.
could
The licensee reported this event to the NRC, as a condition that alone needed to
have prevented the fulfillment of the safety function of systems
mitigate the consequences of an accident. The licensee based this
disks
determination on the potential scenario of the discharge check valve valve bodies, for both trains separating from the swing arms, falling into the
and impeding RHR flow.
9302120052 P9 IPo*'ct4 t 9 '3in'/
Ace I//c 0\
IN 93-16 A
February 19, 1993 Vogtle Electric Generating Plant, Unit I
On April 2, 1992, the Vogtle Electric Generating
at 100 percent power. Georgia Power Company (the Plant, Unit 1, was operating
65 percent when the internals of the B" feedwater licensee) reduced power to
(FW) pump discharge
valve failed. The licensee inspected the check valve and discovered check
valve disk and hanger assembly were not in place. the
inspected the downstream piping and found the disk Subsequently, the licensee
wedged in a reducer section
of the pipe. The licensee retrieved two hangar capscrews
hanger capscrew locking device from a downstream and a portion of the
FW heater.
Discussion
Trojan Nuclear Plant
The Trojan Nuclear Plant licensee determined the
failures to be inadequate design of the valve diskroot cause of the check valve
Inadequate disk nut torquing had allowed the nut nut locking device.
to
forth. The free motion at the nut/lock wire interface rotate slightly back and
high cycle fatigue and eventual failure of the lock induced low stress, wire.
caused by flow induced vibration and by normal operational Nut motion had been
of the valve internal components. actuation movement
The licensee believes this problem is limited to
valves actuated frequently or
to cases where the associated piping has undesirable
The valves in question are Copes-Vulcan Model 8C74 flow characteristics.
believes this failure mechanism is not limited to valves. The licensee
similar nut locking device design (i.e., thin gauge Model 8C74 valves, as
model Copes-Vulcan check valves. Licensee repair lock wire) exist in other
consisted of torquing the disk retaining nut and of the check valves
a 1/8-inch cotter pin. replacing the lock wire with
The licensee examined five other Copes-Vulcan valves
had failed. In addition, the licensee torqued all but no other lock wires
all lock wires With cotter pins on the valves examined.retaining nuts and replaced
The licensee modified its check valve inspection
program to require
documentation of the type and condition of all valve
devices, including the extent to which retaining retaining nut locking
nut rotation was limited by
the locking device.
IN 93-16 February 19, 1993 Vogtle Electric Generating Plant
The Vogtle Unit 1 licensee determined the root cause of the check valve
failure to be inadequate procedural guidance on check valve maintenance.
Procedural deficiencies identified included lack of specifications for
(1) capscrew torque requirements; (2) the correct number of hangar capscrews
to be used; and (3) the correct use and/or reuse of hangar capscrew locking
devices. The hangar capscrew locking device, shown in Attachment 2, is a
stainless steel plate used to prevent the inadvertent loosening of the hanger
capscrews. The locking devices undergo plastic deformation during
installation. Reuse of the locking devices results in work hardening of the
material, making it more susceptible to unacceptable levels of cracking. As a
result of procedural deficiencies, some valves were reassembled without
locking devices, or with used locking devices. Locking device failure can
allow the hanger capscrews to loosen and the hanger to separate from the body
of the valve.
Valve failure may also have been partially caused by the use of an incorrect
number of capscrews. The valve body is drilled and tapped to accept three
capscrews. The locking device and hanger shims are predrilled for use with
three capscrews. The disk hangers (also illustrated on Attachment 1) removed
from the Vogtle Unit 1 check valves were drilled for use with only two
capscrews. Both Unit I check valves had previously undergone hanger
replacement, as evidenced by warehouse records. The disk hangers supplied by
Pacific Valve, as stock spares, are blanks which must be drilled at the time
of installation to ensure proper disk/seat alignment. The licensee believes
Pacific Valve may have originally supplied check valves with disk hangers
drilled for use with only two capscrews. This belief was based on an
inspection of a Vogtle Unit 2 check valve. The original disk hanger for the
pre-assembled valve was drilled for use with only two capscrews.
The licensee is revising its check valve maintenance procedure to ensure the
hanger capscrews are adequately torqued and the required locking device is
correctly installed. In addition, Pacific Valve Engineering is being asked to
specify the correct number of capscrews required for integrity of the
hangar/body bolted joint, and to identify any differences between design and
installation configurations.
Related Generic Communication
In Information Notice 81-35, "Check Valve Failures," the NRC discussed an
event similar to the failure at Trojan involving Anchor Darling check valves.
The Anchor Darling check valve failures were attributed to the valve being
assembled with lock wire used as the retaining nut locking device, rather than
a locking pin as shown on the design drawing.
r
IN 93-16 February 19, 1993 This information notice requires no specific action or written response.
you have any questions about the information in this notice, please contactIf
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: Eric J. Benner, NRR
(301) 504-1171 Francis Grubelich, NRR
(301) 504-2784 Attachments:.
1. -Copes-Vulcan Check Valve Internals
2. Copes-Vulcan Hanger Capscrew Locking Device
3. List of Recently Issued NRC Information Notices
\ Attachment 1 IN 93-16 February 19, 1993 HANGER CAPSCREWS
DISK HANGER
SWING ARM
DISK
WASHER
LOCK WIRE
NUT
COPES-VULCAN CHECK VALVE INTERKALS
1, b
I
LOCKING TAB
_TX
C
/3oides: IT6L CQL
(
K>
Attachment 3 IN 93-16 February 19, 1993 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
93-15 Failure to Verify the 02/18/93 All holders of OLs or CPs
Continuity of Shunt Trip for nuclear power reactors.
Attachment Contacts in
Manual Safety Injection
and Reactor Trip Switches
93-14 Clarification of 02/18/93 All licensees who possess
10 CFR 40.22, Small source material.
Quantities of Source
Material
93-13 Undetected Modification 02/16/93 All holders of OLs or CPs
of Flow Characteristics for nuclear power reactors.
in the High Pressure
Safety Injection System
93-12 Off-Gassing in Auxiliary 02/11/93 All holders of OLs or CPs
Feedwater System Raw for nuclear power reactors.
Water Sources
93-11 Single Failure Vulner- 02/04/93 All holders of OLs or CPs
ability of Engineered for nuclear power reactors.
Safety Features
Actuation Systems
93-10 Dose Calibrator Quality 02/02/93 All Nuclear Regulatory Com- Control mission medical licensees.
93-09 Failure of Undervoltage 02/02/93 All holders of OLs or CPs
Trip Attachment on for nuclear power reactors.
Westinghouse Model DB-50
Reactor Trip Breaker
93-08 Failure of Residual 02/01/93 All holders of OLs or CPs
Heat Removal Pump for nuclear power reactors.
Bearings due to High
Thrust Loading
93-07 Classification of Trans- 02/01/93 All Licensees required to
portation Emergencies have an emergency plan.
OL = Operating License
CP = Construction Permit
K)
IN 93-16 February 19, 1993 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.
Original signed by
Brian K. Grime3 Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Eric J. Benner, NRR
(301) 504-1171 Francis Grubelich, NRR
(301) 504-2784 Attachments:
1. Copes-Vulcan Check Valve Internals
2. Copes-Vulcan Hanger Capscrew Locking Device
3. List of Recently Issued NRC Information Notices
Reviewed by J. Main, Technical Editor
on 04/24/92 DOCUMENT NAME: 93-16.IN
- SEE PREVIOUS CONCURRENCES
OFC :OEAB:DORS :EMEB:DE :PM:PDV:DRP :PM:PDII:DRP
_____ ____________- ____________- - - ------- :-- - -- - -
NAME :DGarcia* :FGrubelich* :LKokajko* :DHood*
____________ _ _ ___
_---------- : :
DATE :09/24/92 :10/07/92 :10/09/92 :10/09/92 :
OFC :SC/OEAB:DORS:C/OEAB:DORS :C/OGCB:DWORS D9S,77:
_____ ___________--:----------- -- :------------- ,
NAME :TKoshy* :AChaffee* :.GMarcus* :
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DATE :11/05/92 :12/07/92 : 02/09/93 : WI/Z/93 :
NECampbell
02/09/93 OFFICIAL RECORD COPY
IN 93-XX
February xx, 1993 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.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Eric J. Benner, NRR
(301) 504-1171 Francis Grubelich, NRR
(301) 504-2784 Attachments:
1. Copes-Vulcan Check Valve Internals
2. Copes-Vulcan Hanger Capscrew Locking Device
3. List of Recently Issued NRC Information Notices
Reviewed by J. Main, Technical Editor
on 04/24/92
- SEE PREVIOUS CONCURRENCES
OFC :OEAB:DORS :EMEB:DE :PM:PDV:DRP :PM:PDII:DRP
_____ ____________ _________ _: _ ----- :- :
NAME :DGarcia* :FGrubelich* :LKokajko* :DHood*
_____ ____________- __________--- :------- - - :-- - -- - -
DATE :09/24/92 :10/07/92 :10/09/92 :10/09/92 OFC :SC/OEAB:DORS:C/OEAB:DORS :C/OGCB:DORS :D/DORS
____. ____________: ----- :-:
NAME :TKoshy* :AChaffee* :GMarcus J1i:BGrimet-, :
_____-__ _ __ _- -
__ _ __ __-.-__ -- - _- - -
- - __----
__ - - -
DATE :11/05/92 :12/07/92 2//93 V: ://93 :
OFFICIAL RECORD # PY
Document Name: oNCHKVX.EJB
Francis Grubelich, NRR
(301) 504-2784 Attachments:
1. Copes-Vulcan Check Valve Internals
2. Copes-Vulcan Hanger Capscrew Locking Device
3. List of Recently Issued NRC Information Notices
Reviewed by J. Main, Technical Editor
on 04/24/92
- SEE PREVIOUS CONCURRENCES
OFC :OEAB:DORS :EMEB:DE :PM:PDV:DRP :PM:PDII:DRP
_- __ - -- __
__ ___-
__-___
- - -- __ - _------
__ :-- - -- - -
NAME :DGarcia* :FGrubelich* :LKokajko* :DHood*:
_____ ___________- __________--- :---- - - - - :- - - -- - -
DATE :09/2492 :10/07/92 :10/09/92 :10/09/92 OFC :SC/OEAB:DORS:C/OEAB:DORS :C/OGCB:DORS :D/DORS
_____ ____________- __________---:----- - - - :-- - -- - -
NAME :TKoshy* :AC)W e :GMarcus :BGrimes
_-& _______-- :-- - ----- -- -- -- --
_____ ____________-
DATE :11/05/92 : AZ/7192 : I /92 : I /92 OFFICIAL RECORD COPY
Document Name: G:\EJB1\INCHKVLV.EJB
Reviewed by J. Main, Technical Editor
on 04/24/92
- SEE PREVIOUS CONCURRENCES
OFC :OEAB:DORS :EMEB:DE :PM:PDV:DRP :PM:PDII:DRP :
_____ ____________-- _- _____-_--- -:----- - - - :-- - -- - -
NAME :DGarcia* :FGrubelich* :LKokajko* :DHood*
_____ ____________ ______
-- --- ___-_:
-- ---- :-- - -- - -
DATE :09/2492 :10/07/92 :10/09/92 :10/09/92 OFC :SC/OEAB:DORS:C/OEAB:DORS :C/OGCB:DORS :D/DORS
_____ __ __---- _ _---- __ _ __ -:- - - - - - :-- - -- - -
NAME :: :AChaffee :GMarcus :BGrimes
_____ j A -------------____-- :- --
DATE :fg/9/92 : / /92 : / /92 : / /92 OFFICIAL RECORD COPY
Document Name: G:\DMG\INCHKVLV.DMG
Reviewed by J. Main, Technical Editor
on 04/24/92 OFC :OEABfDOEA :EME :DET :PM: V:DRP :PM:PDII:DRP
; ------ d ----- -:--------- -:
NAME toa : F G66belich
Kokajko :DHood-DSj :
DATE :' /2192 :0 /7 /92 tl'9 /92 :lO/ g/92 OFC :SC/OEAB:DOEA:C/OEAB:DOEA :C/OGCB:DOEA :D/DOEA :
_ _ _ _ :_ :-
NAME :AGautam :AChaffee :GMarcus :CRossi
DATE : / /92 :/ /92 : / /92 OFFICIAL RECORD COPY
Document Name: G:\INCHKVLV.DMG
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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, Topic: Uranium Hexafluoride, Overexposure)
- Information Notice 1993-05, Locking of Radiography Exposure Devices (14 January 1993, Topic: Uranium Hexafluoride, Inattentive)
- 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, Topic: Uranium Hexafluoride)
- 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, Topic: Commercial Grade)
- Information Notice 1993-10, Dose Calibrator Quality Control (2 February 1993, Topic: Uranium Hexafluoride)
- 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, Water hammer)
- 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, Topic: Thermal fatigue)
- 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, Thermal fatigue, Reactive Inspection)
- Information Notice 1993-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers Due to Support Lever Failure (26 March 1993, Topic: Commercial Grade, Thermal fatigue)
- Information Notice 1993-23, Weschler Instruments Model 252 Switchboard Meters (31 March 1993, Topic: Commercial Grade, Thermal fatigue)
- Information Notice 1993-24, Distribution of Revision 7 of NUREG-1021, Operation Licensing Examiner Standards (31 March 1993, Topic: Job Performance Measure, Thermal fatigue)
- Information Notice 1993-25, Electrical Penetration Assembly Degradation (1 April 1993, Topic: Thermal fatigue)
- 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, Thermal fatigue)
- 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, Thermal fatigue)
- 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, Topic: Commercial Grade)
- 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, Topic: Local Leak Rate Testing)
- 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, Topic: Water hammer)
- Information Notice 1993-49, Improper Integration of Software Into Operating Practices (8 July 1993)
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