Failure of Motor-Operated Valve Electric Power Train Due to Sheared or Dislodged Motor Pinion Gear KeyML031060635 |
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: |
02/04/1994 |
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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-94-010, NUDOCS 9402010052 |
Download: ML031060635 (10) |
|
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>. |
4
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 February 4, 1994 NRC INFORMATION NOTICE 94-10: FAILURE OF MOTOR-OPERATED VALVE ELECTRIC POWER
TRAIN DUE TO SHEARED OR DISLODGED MOTOR PINION
GEAR KEY
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 motor-operated valve (MOV)
electric power train failures caused by structural failure or improper
installation of the motor pinion gear key. 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.
Background
The motor pinion gear is located on the shaft of the electric motor and
transmits motor torque to the worm shaft gear. The motor pinion gear is
connected to the motor shaft by means of a key which transfers rotary force
from the motor shaft to the gear. A set screw is used to prevent axial
movement of the motor pinion gear on the motor shaft.
In 1989, Limitorque Corporation issued Maintenance Update 89-1 which made
recommendations for securing the motor pinion gear key when replacing the
motor or the gears. The update stated that some users had not adequately
secured the key, permitting it to subsequently slide out of the keyway and
decouple the motor from the actuator. The update gave a procedure for staking
the motor shaft at the open end of the keyway to mechanically lock the key in
place.
In 1992, Limitorque issued Matntenance Update 92-2 which stated that the
material for motor pinion keys supplied with SMB-000 through -2 actuators had
recently been changed from American Iron and Steel Institute (AISI) 1018 to
AISI 4140 steel because of customer requests for the higher strength material.
Limitorque stated that all SMB-3 through -5 actuators with motors rated in
excess of 13.8 kg-m [100 ft-lbsJ and serial numbers greater than 12160 were
supplied with motor pinion keys of AISI 4140 steel. In the maintenance
' 9402010052 PDt 94-010 chqotpOL
WAPE & 1>'
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ll
94-10
K" Aruary 4, 1994 update, Limitorque recommended that, if not already done, the motor pinion key
be replaced with AISI 4140 steel for SMB-3 through -5 actuators with motors
rated in excess of 13.8 kg-m [100 ft-lbs].
Description of Circumstances
On August 30, 1993, the high-pressure coolant injection system pump discharge
isolation valve at the Cooper Nuclear Station failed to open during the
performance of a surveillance procedure, causing the valve to be declared
inoperable. Subsequent investigation revealed that the SB-3 Limitorque
actuator motor pinion gear key had migrated out of its keyway, allowing the
motor shaft to spin without transferring torque to the motor pinion gear. The
cause of this event was attributed to the failure to stake the motor shaft
keyway following a motor replacement in 1990.
The licensee for Cooper Nuclear Station incorporated the recommendations of
Limitorque Maintenance Update 89-1 in a 1991 revision to its MOV maintenance
procedures. However, at that time, the licensee did not investigate the
potential consequences of maintenance activities that had been performed
before the procedure was revised. During that time, staking of the motor
shaft had not been a requirement. Based on vendor contacts and independent
sampling, the licensee determined that the particular actuators at Cooper
initially procured from Limitorque were properly staked. Therefore, the
potential extent of the condition at Cooper was limited to actuators that had
received onsite maintenance (affecting the motor pinion gear set) before the
procedures were revised. The licensee further narrowed the scope of its
investigation based on a Limitorque assertion and industry information that
only larger size actuators (SMB/SB-0 and above) are susceptible to this
problem.
On October 8, 1993, the licensee of the Waterford Steam Electric Generating
Station, Unit 3, notified the NRC that the motor pinion keys in both MOVs used
for isolating the shutdown cooling system suction line were not staked to the
motor shaft. The actuators were size SMB-0.
On October 8, 1993, the licensee of the Clinton Power Station, Unit 1, notified the NRC that the SB-3 Limitorque actuator motor pinion key to the
high-pressure core spray injection MOV had sheared. The actuator was attached
to a motor rated at 11 kg-m [80 ft-lbs]. The licensee determined that the key
material was AISI 1018 steel. This motor was rated lower than the threshold
for replacement recommended by Limotorque Maintenance Update 92-2 and is a
different actuator type.
Discussion
The NRC staff has reviewed information suggesting that a small, but not
inconsequential, number of MOV motor shaft keyways may be unstaked at various
nuclear power plants. Although a low incidence of motor pinion gear key
dislodgements has been observed, it is possible that an extended time period
may be necessary for axial migration of the key in a horizontally mounted
motor, suggesting the potential for additional failures of this type.
94-10
February 4, 1994 K. The incidence of motor pinion key failures may be increased as a result of the
higher thrust and torque found to be necessary to operate some valves under
dynamic conditions.
Related Generic Communications
NRC has issued other generic communications on MOV motor pinion keys, including NRC Office of Inspection and Enforcement Information Notices (INs)
81-08, 'Repetitive Failures of Limitorque Operator SMB-4 Motor-to-Shaft Key";
85-22, 'Failure of Limitorque Motor-Operated Valves Resulting From Incorrect
Installation of Pinion Gear'; and 85-67, "Valve-Shaft-to-Actuator Key May Fall
Out of Place When Mounted Below Horizontal Axis"; and NRC INs 88-84, Defective Motor Shaft Keys in Limitorque Motor Actuators"; and 90-37,
'Sheared Pinion Gear-to-Shaft Keys in Limitorque Motor Actuators.'
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: Thomas F. Westerman, RIV Thomas G. Scarbrough, NRR
(817) 860-8145 (301) 504-2794 John M. Jacobson, RIII
(708) 829-9736 Attachment:
List of Recently Issued NRC Information Notices
IN 94-10
"\-vFebruary 4, 1994 The incidence of motor pinion key failures may be increased as a result of the
higher thrust and torque found to be necessary to operate some valves under
dynamic conditions.
Related Generic Communications
NRC has issued other generic communications on MOV motor pinion keys, including NRC Office of Inspection and Enforcement Information Notices (INs)
81-08, "Repetitive Failures of Limitorque Operator SMB-4 Motor-to-Shaft Key";
85-22, "Failure of Limitorque Motor-Operated Valves Resulting From Incorrect
Installation of Pinion Gear"; and 85-67, "Valve-Shaft-to-Actuator Key May Fall
Out of Place When Mounted Below Horizontal Axis"; and NRC INs 88-84,
"Defective Motor Shaft Keys in Limitorque Motor Actuators"; and 90-37,
"Sheared Pinion Gear-to-Shaft Keys in Limitorque Motor Actuators."
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 signedly
Brian K. Grimel
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Thomas F. Westerman, RIV John M. Jacobson, RIII
(817) 860-8145 (708) 829-9736 Thomas G. Scarbrough, NRR
(301) 504-2794 Attachment:
List of Recently Issued NRC Information Notices
OFFICE [*EMEB/DE/NRR [*EMEB/DE/NRR *C:EMEB/DE/NRR D:DE/NRR
NAME TGScarbrough GJohnson JANorberg JTWiggins
DATE 11/30/93 11/30/93 11/30/93 12/ /93 OFFICE *OGCB/DORS/NRR *Tech Ed *EB/DRS/R3 *C:EB/DRS/R3 NAME RJKiessel RSanders JMJacobson GCWright
DATE 12/ 9/93 12/10/93 _ 12/16/93 12/22/93 OFFICE *D:DRS/R3 *DRS/R4 *D:DRS/R4 C:OGCB/DORS/NRR
NAME GEGrant TFWesterman SJCollins *GHMarcus
DATE 12/22i93 I 12/15/93 12/16/93 01/10/94 OFFICE D_ _ _ ___
NAME 4B E _I
DATE '02/1 /94 _
Document Name: 94-10.IN
\,_IN 93-xx
December xx, 1993 The instances of motor pinion key failures might be increased as a result of
the higher thrust and torque found to be necessary to operate some valves
under dynamic conditions.
Related Generic Communications
NRC has issued other generic communications on MOV motor pinion keys, including NRC Office of Inspection and Enforcement Information Notices (INs)
81-08, 'Repetitive Failures of Limitorque Operator SMB-4 Motor-to-Shaft Key";
85-22, "Failure of Limitorque Motor-Operated Valves Resulting From Incorrect
Installation of Pinion Gear"; and 85-67, "Valve-Shaft-to-Actuator Key May Fall
Out of Place When Mounted Below Horizontal Axis"; and NRC INs 88-84,
"Defective Motor Shaft Keys in Limitorque Motor Actuators"; and 90-37,
"Sheared Pinion Gear-to-Shaft Keys in Limitorque Motor Actuators."
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: Thomas F. Westerman, RIV John M. Jacobson, RIII
(817) 860-8145 (708) 829-9736 Thomas G. Scarbrough, NRR
(301) 504-2794 Attachment:
List of Recently Issued NRC Information Notices
- see Drevious concurrence 62 OFFICE *EMEB/DE/NRR *EMEB/DE/NRR *C:EMEB/DE/NRR D:DE/
6
41 NAME TGScarbrough GJohnson JANorberg %*WiggiAs
DATE 11/30/93 11/30/93 11/30/93 12A/93 OFFICE *OGCB/DORS/NRR *Tech Ed *EB/DRS/R3 *C:EB/DRS/R3 NAME RJKiessel RSanders JMJacobson GCWright
DATE 17/ 9/93 12/10/93 12/16/93 12/22/93 OFFICE *D:DRS/R3 *DRS/R4 *D:DRS/R4 C:OGCB/DORS/NRR
NAME GEGrant TFWesterman SJCollins GHMarcus
DATE 12/22/93 12/15/93 12/16/93 I ________
OFFICE D:DORS/NRR l
NAME BKGrime__
DATE 12/ /93 l
Document Name: nrcin.3cl
0
.1 . -,. .
OFFICE *EMEB/DE/NRR *EMEB/DE/NRR *C:EMEB/DE/NRR D:DE/NRR
NAME TGScarbrough GJohnson JANorberg JTWiggins
DATE 1 11/30/93 1 1/30/93 11/30/93 12/ /93 OFFICE *OGCB/DORS/NRR *Tech Ed *EB/DRS/R3 *C:EB/DRS/R3 NAME RJKiessel RSanders JMJacobson GCWright
DATE , 12/ 9/93 12/10/93 12/16/93 12/22/93 OFFICE *D:DRS/R3 *DRS/R4 *D:DRS/R4 C:OGCB/DORS/NRR
NAME GEGrant TFWesterman SJCollins GHMarcus
DATE 12/22/93 12/15/93 12/16/93 12/ /93 OFFICE D:DORS/NRR
NAME IIrimes l
DATE 12/ /93 Document Name: nrcin.3cl
"Defective Motor Shaft Keys in Limitorque Motor Actuators"; and 90-37,
"Sheared Pinion Gear-to-Shaft Keys in Limitorque Motor Actuators."
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 'v
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Thomas F. Westerman, Region IV
(817) 860-8145 John M. Jacobson, Region III
(708) 829-9736 Thomas G. Scarbrough, NRR
(301) 504-2794 Attachment: List of Recently Issued NRC Information Notices
Transmitted by JANorberg memorandum dated November 30. 1993
OFFICE *EMEB/DE/NRR *EMEB/DE/NRR *C:EMEB/DE/NRR I D:DE/NRR
NAME TGScarbrough GJohnson JANorberg I JTWiggins
DATE 11/30/93 11130/93 11/30/93 1 12/ /93 It
- - - . -- . . -- -M- - --allP
IW.
_ OFFICE
_* _*_ *OGCB/DORS/NRR
____ *Tech Ed
- r EB/DRS/R3
- Aft
__-____
___
NAME RJKiessel RSanders JMJacobson; GCWrght
DATE 12/ 9/93 12/10/93 12/- /93 Vi I_ _ 93_gg
OFFICE D:DRS/R3 - DRS/R4 D:DR j I C:OGCB/DORS/NRR-
NAME GEGrant, TFWesterman SJCollins GHMarcus
DATE 12 12/ /93
12/ /932 93 OFFICE D:DORS/NRR
NAME BKGrimes
DATE 12/ /93 Document Name: nrcln.3cl
12/16 1U936/5 U
R IV NRC FTS 044
"Defective Yvbtor Shaft Keys in Limi torque IVbtor Actuators"; and 90-37,
"Sheared Pinion Gear-to-Shaft Keys in LImitorque Mbtor Mctuators."
If
This intorretion notice requires no specific action or written response. contact
you have any questions about the infonnotIon in this notice, please
one of the technical contacts listed belIo or the appropriate Office of
Niclear Reactor Regulation (N1R) project rranager.
Brian K. Grirres, Director 'V
Division of Cperating Reactor Support
Office of NUclear Reactor Regulation
Technical contacts: Thoras F. Vbstenran, Region IV
(817) 860-8145 John M. Jacobson, Rogion IlIl
(708) 829-9736 Thors G. Scarbrough, NRR
(301) 504-2794 Attact'rmnt: List of Recently issued NC Informntion Nbtices
Transnitted by JW'brberg rniurrandun dated Nbvfto _i._29 ses previous concurrence __ _
OFFICE *EB/VMDE/Nfi "EAEB/EE/Nfl C:/VEB/DE/NR D:DE/WN
NM'E TXfcarbro2Vi GWohnson JPbrberg J1Mggins
DMTE 111/30193 11/30/93 11130/93 12/ 193 CFFICE 'B/W1 NIR *Tech Ed lEB/176IP3 C:EBI/CS/R3 N -& RJiessel IFanders l IVUacobson G3MI ht
12/ 9/93 12110/93 12/ /93 121 /93 IXTE
S
OFFICE D:;S/IR3 CRS/P4 DOW C:Q03/ICM/NM
NME GB3rant Tgb stemen 1 1 ins Gfbrcus
EA)TE 12/ 193 1 12/15/93 _12/v O 1 Z/_Ir
OFFICE 1_:_ __ _ __ _ _
NTE BKr Imns
CATE 12/ /93 __ . _. _
bCumnt Name: nrcin,3cl
.....
"Sheared Pinion Gear-to-Shaft Keys in Limitorque Motor Actuators."
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: Thomas F. Westerman, Region IV
(817) 860-8145 John M. Jacobson, Region III
(708) 790-5267 Thomas G. Scarbrough, NRR
(301) 504-2794 Attachment: List of Recently Issued NRC Information Notices
Transmitted by JANorberg memorandum dated November 30. 1993
OFFICE *EMEB/DE/NRR *EMEB/DE/NRR *C:EMEB/DE/NRR D:DE/NRR
NAME TGScarbrough GJohnson JANorberg JTWiggins
DATE 11/30/93 11/30/93 11/30/93 12/ /93 OFFICE OGCB/DORS/NRRl Tech Ed EB/DRS/R3 l C:EB/DRS/R3 NAME RJKiesse 1 Mp JMJacobson GCWright
DATE 12/L/93 12/10/93 12/ /93 12/ /93 OFFICE D:DRS/R3 DRS/R4 D:DRS/R4 C:OGCB/DORS/NRR
NAME GEGrant TFWesterman SJCollins GHMarcus
DATE 12/ /93 12/ /93 12/ /93 12/ /93 OFFICE D:DORS/NRR l l l
NAME BKGrimes
DATE 12/ /93 Document Name: nrcin.3cl
.,*-/
& AttJinent
IN 94-10
February 4, 1994 Page I of 1 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
94-09 Release of Patients with 02/03/94 All U.S. Nuclear Regulatory
Residual Radioactivity Commission medical
from Medical Treatment and licensees.
Control of Areas due to
Presence of Patients Con- taining Radioactivity
Following Implementation
of Revised 10 CFR Part 20
94-08 Potential for Surveil- 01/01/94 All holders of OLs or CPs
lance Testing to Fail for nuclear power reactors.
to Detect an Inoperable
Main Steam Isolation Valve
93-26, Grease Solidification 01/31/94 All holders of OLs or CPs
Supp. 1 Causes Molded-Case for nuclear power reactors.
Circuit Breaker Failure
to Close
94-07 Solubility Criteria for 01/28/94 All byproduct material and
Liquid Effluent Releases fuel cycle licensees with
to Sanitary Sewerage Under the exception of licensees
the Revised 10 CFR Part 20 authorized solely for
sealed sources.
94-06 Potential Failure of 01/28/94 All holders of OLs or CPs
Long-Term Emergency for boiling water reactors.
Nitrogen Supply for the
Automatic Depressurization
System Valves
93-85, Problems with X-Relays 01/20/94 All holders of OLs or CPs
Rev. 1 in DB- and DHP-Type for nuclear power reactors.
Circuit Breakers Manu- factured by Westinghouse
94-05 Potential Failure of 01/19/94 All holders of OLs or CPs
Steam Generator Tubes for pressurized water
with Kinetically Welded reactors (PWRs).
Sleeves
OL - Operating License
CP = Construction Permit
|
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|
list | - Information Notice 1994-01, Turbine Blade Failures Caused by Torsional Excitation from Electrical System Disturbance (7 January 1994)
- Information Notice 1994-02, Inoperability of General Electric Magne-Blast Breaker Because of Misalignment of Close-Latch Spring (7 January 1994)
- Information Notice 1994-03, Deficiencies Identified During Service Water System Operational Performance Inspections (11 January 1994, Topic: Biofouling)
- Information Notice 1994-04, Digital Integrated Circuit Sockets with Intermittent Contact (14 January 1994)
- Information Notice 1994-05, Potential Failure of Steam Generator Tubes with Kinetically Welded Sleeves (19 January 1994)
- Information Notice 1994-06, Potential Failure of Long-Term Emergency Nitrogen Supply for the Automatic Depressurization System Valves (28 January 1994)
- Information Notice 1994-07, Solubility Criteria for Liquid Effluent Releases to Sanitary Sewerage Under the Revised 10 CFR Part 20 (28 January 1994)
- Information Notice 1994-08, Potential for Surveillance Testing to Fail to Detect an Inoperable Main Steam Isolation Valve (1 February 1994)
- Information Notice 1994-09, Release of Patients with Residual Radioactivity from Medical Treatment & Control of Areas Due to Presence of Patients Containing Radioactivity Following Implementation of Revised 10 CFR Part 20 (3 February 1994, Topic: Brachytherapy)
- Information Notice 1994-10, Failure of Motor-Operated Valve Electric Power Train Due to Sheared or Dislodged Motor Pinion Gear Key (4 February 1994)
- Information Notice 1994-11, Turbine Overspeed and Reactor Cooldown During Shutdown Evolution (8 February 1994)
- Information Notice 1994-12, Insights Gained from Resolving Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment (9 February 1994)
- Information Notice 1994-13, Unanticipated and Unintended Movement of Fuel Assemblies and Other Components Due to Improper Operation of Refueling Equipment (28 June 1994)
- Information Notice 1994-14, Failure to Implement Requirements for Biennial Medical Examinations and Notification to the NRC of Changes in Licensed Operator Medical Conditions (24 February 1994)
- Information Notice 1994-15, Radiation Exposures During an Event Involving a Fixed Nuclear Gauge (2 March 1994)
- Information Notice 1994-16, Recent Incidents Resulting in Offsite Contamination (3 March 1994)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (QMP), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (Qmp), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- Information Notice 1994-18, Accuracy of Motor-Operated Valve Diagnostic Equipment (Responses to Supplement 5 to Generic Letter 89-10) (16 March 1994)
- Information Notice 1994-19, Emergency Diesel Gemerator Vulnerability to Failure from Cold Fuel Oil (16 March 1994)
- Information Notice 1994-20, Common-Cause Failures Due to Inadequate Design Control and Dedication (17 March 1994)
- Information Notice 1994-21, Regulatory Requirements When No Operations Are Being Performed (18 March 1994)
- Information Notice 1994-22, Fire Endurance & Ampacity Derating Test Results for 3-Hour Fire-Rated Thermo-Lag 330-1 Fire Barriers (16 March 1994, Topic: Fire Barrier)
- Information Notice 1994-23, Guidance to Hazardous, Radioactive and Mixed Waste Generators on the Elements of a Waste Minimization Program (25 March 1994, Topic: Fire Barrier)
- Information Notice 1994-24, Inadequate Maintenance of Uninterruptible Power Supplies & Inverters (24 March 1994, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1994-25, Failure of Containment Spray Header Valve to Open Due to Excessive Pressure from Inertial Effects of Water (15 March 1994, Topic: Fire Barrier)
- Information Notice 1994-26, Personnel Hazards and Other Problems from Smoldering Fire-Retardant Material in the Drywell of a Boiling-Water Reactor (28 March 1994, Topic: Fire Barrier)
- Information Notice 1994-27, Facility Operating Concerns Resulting from Local Area Flooding (31 March 1994, Topic: Fire Barrier)
- Information Notice 1994-28, Potential Problems with Fire-Barrier Penetration Seals (5 April 1994, Topic: Fire Barrier)
- Information Notice 1994-29, Charging Pump Trip During a Loss-of-Coolant Event Caused by Low Suction Pressure (11 April 1994, Topic: Boric Acid)
- Information Notice 1994-30, Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear Station (19 August 1994, Topic: Fire Barrier)
- Information Notice 1994-31, Potential Failure of Wilco, Lexan-Type HN-4-L Fire Hose Nozzles (14 April 1994, Topic: Hydrostatic)
- Information Notice 1994-32, Revised Seismic Estimates (29 April 1994, Topic: Earthquake)
- Information Notice 1994-33, Capacitor Failures in Westinghouse Eagle 21 Plant Protection Systems (9 May 1994)
- Information Notice 1994-34, Thermo-LAG 330-660 Flexi-Blanket Ampacity Derating Concerns (13 May 1994, Topic: Fire Barrier)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(Mmr) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(MMR) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System (24 May 1994, Topic: Reactor Vessel Water Level)
- Information Notice 1994-37, Misadministration Caused by a Bent Interstitial Needle During Brachytherapy Procedure (27 May 1994, Topic: Brachytherapy)
- Information Notice 1994-38, Results of Special NRC Inspection at Dresden Nuclear Power Station, Unit 1 Following Rupture of Service Water Inside Containment (27 May 1994)
- Information Notice 1994-39, Identified Problems in Gamma Stereotactic Radiosurgery (31 May 1994)
- Information Notice 1994-40, Failure of a Rod Control Cluster Assembly to Fully Insert Following a Reactor Trip at Braidwood, Unit 2 (26 May 1994)
- Information Notice 1994-41, Problems with General Electric Type Cr124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-41, Problems with General Electric Type CR124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-42, Cracking in the Lower Region of the Core Shroud in Boiling-Water Reactors (7 June 1994)
- Information Notice 1994-43, Determination of Primary-to-Secondary Steam Generator Leak Rate (10 June 1994, Topic: Grab sample)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand Because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-45, Potential Common-Mode Failure Mechanism for Large Vertical Pumps (17 June 1994, Topic: Biofouling)
- Information Notice 1994-46, Nonconservative Reactor Coolant System Leakage Calculation (20 June 1994)
... further results |
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