Motor-Operated Valve Actuator Thrust Variations Measured with a Torque Thrust Cell and a Strain GageML031210125 |
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: |
07/20/1993 |
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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-93-054, NUDOCS 9307140106 |
Download: ML031210125 (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, D.C. 20555 July 20, 1993 NRC INFORMATION NOTICE 93-54: MOTOR-OPERATED VALVE ACTUATOR THRUST VARIATIONS
MEASURED WITH A TORQUE THRUST CELL AND A STRAIN
GAGE
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 a possible error in their diagnostic evaluation
of motor-operated valve (MOV) actuators. 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
Diagnostic testing of MOVs is performed to satisfy the commitments made in
response to NRC Generic Letter (GL) 89-10, "Safety-Related Motor-Operated
Valve Testing and Surveillance," and its supplements. Actuator output thrust
is measured by a combination of transducers. The transducers include, but are
not limited to, the ITI MOVATS torque thrust cell (thrust cell) and the
Teledyne quick stem sensor (stem sensor).
On November 9, 1992, ITI MOVATS engineers working at the Turkey Point plant
noticed that thrust measurements taken with the torque thrust cell were
different from the stem-mounted strain gage readings after the thrust cell was
removed. Review showed that all of the readings of the valves that had been
tested using the stem sensor changed somewhat when the thrust cell was removed
from the valve. Data indicated that thrust readings degraded by approximately
20 percent when the thrust cell was removed.
On November 10, 1992, ITI MOVATS management and a licensee engineer began to
investigate the cause.
Discussion
As discussed above, to meet the commitments made in response to GL 89-10, most
licensees rely on MOV diagnostic equipment to set the thrust delivered by the
actuator in opening or closing its valve. Failure to properly account for
inaccuracies introduced by the use of diagnostic equipment could result in
9307140106 (ID 13 X 05af 3al
.IN 93-54 July 20, 1993 either the MOV not being able to perform its intended safety function because
of inadequate actuator output or the failure of a component in either the
valve or the actuator because of excessive motor torque.
The devices discussed in the
Description of Circumstances
operate on the
following principles:
- The ITI MOVATS torque thrust cell is a radial web calibrated load cell.
The inner ring of the cell is bolted to the top of the valve yoke and
the outer ring to the bottom of the actuator. The rings are connected
by eight webs that have strain gages to measure actuator torque and
thrust simultaneously. Installation of the thrust cell requires that
the actuator be raised a distance equal to the thickness of the thrust
cell. This means that the actuator stem nut is in a new position on the
valve stem.
- The Teledyne quick stem sensor is a strain gage mounted on a strip of
foil with tabs on each end to facilitate Installation on the valve stem.
The sensor comes with leads preconnected to the gage. Epoxy is used to
install the stem sensor on the valve stem.
During the test, the valve is stroked and the thrust cell is used as a
calibration reference for the stem sensor. Once the stem sensor is
calibrated, it can be used for future MOV tests without using the thrust cell.
The Limitorque actuator torque switch is then set to produce the required
valve stem thrust. After the thrust cell is removed, a full valve stroke
signature is obtained to evaluate overall actuator performance.
As a result of their review, ITI MOVATS and licensee personnel concluded that
the most significant contributors to the observed changes in thrust when the
thrust cell was removed are stem engagement and stem lubricant.
- Stem engagements of less than one stem diameter tend to increase the
thrust at torque switch trip by improving the stem factor. This effect
is more pronounced when Neolube is used than when EP-O is used as a stem
lubricant.
- Test results indicate that stroke-to-stroke variations in thrust at
torque switch trip are greater with Neolube than with EP-O. For
Neolube, the variations tend to be high on initial lubrication and then
decrease as the valve is stroked.
In January 1993, ITI MOVATS engineers issued the attached report of their
investigation of the discrepancies in thrust measurements which confirms that
the primary causes are stem lubrication and stem nut wear.
' IN 93-54 July 20, 1993 Related Generic Communications
NRC has issued a number of information notices pertaining to the accuracy of
MOV diagnostic equipment. Most recently, these have included NRC Information
Notice (IN)93-01, "Accuracy of Motor-Operated Valve Diagnostic Equipment
Manufactured by Liberty Technologies;" IN 92-23, "Results of Validation
Testing of Motor-Operated Diagnostic Equipment;" and IN 91-61, "Preliminary
Results of Validation Testing of Motor-Operated Valve Diagnostic Equipment."
NRC also issued Supplement 5 to GL 89-10, "Inaccuracy of Motor-Operated Valve
Diagnostic Equipment," on June 28, 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 project manager.
rian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Francis Jape, RII
(404) 331-5607 Thomas G. Scarbrough, NRR
(301) 504-2794 Attachments:
1. ITI MOVATS Report dated January 1993
2. List of Recently Issued NRC Information Notices
I I At achment 2 IN 93-54 July 20, 1993 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
93-53 Effect of Hurricane 07/20/93 All holders of OLs or CPs
Andrew on Turkey Point for nuclear power reactors.
Nuclear Generating
Station and Lessons
Learned
93-52 Draft NUREG-1477, 07/14/93 All holders of OLs or CPs
"Voltage-Based Interim for pressurized water
Plugging Criteria for reactor (PWRs).
Steam Generator Tubes"
93-51 Repetitive Overspeed 07/09/93 All holders of OLs or CPs
Tripping of Turbine- for nuclear power reactors.
Driven Auxiliary Feed- water Pumps
93-50 Extended Storage of 07/08/93 All licensees authorized
Sealed Sources to possess sealed sources.
93-49 Improper Integration of 07/08/93 All holders of OLs or CPs
Software into Operating for nuclear power reactors.
Practices
93-48 Failure of Turbine- 7/6/93 All holders of OLs or CPs
Driven Main Feedwater for nuclear power reactors.
Pump to Trip Because of
Contaminated Oil
92-06, Reliability of ATWS 07/01/93 All holders of OLs or CPs
Supp. 1 Mitigation Systems and for nuclear power reactors.
Other NRC-Required Equip- ment not Controlled by
Plant Technical Specifica- tion
93-47 Unrecognized Loss of 06/18/93 All holders of OLs or CPs
Control Room Annunciators for nuclear power reactors.
93-46 Potential Problem with 6/10/93 All holders of OLs or CPs
Westinghouse Rod Control for Westinghouse (W)-
System and Inadvertent designed nuclear power
Withdrawal of A Single reactors.
Rod Control Cluster Assembly
OL = Operating License
CP = Construction Permit
IN 93-xx
April xx, 1993 Manufactured by Liberty Technologies"; IN 92-23, "Results of Validation
Testing of Motor-Operated Diagnostic Equipment"; and IN 91-61, "Preliminary
Results of Validation Testing of Motor-Operated Valve Diagnostic Equipment."
In addition, NRC is preparing a supplement to GL 89-10 to request that
licensees address potential accuracy problems with MOV diagnostic equipment.
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 project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact(s): Francis Jape, Region II
(404) 331-5540
Thomas G. Scarbrough, NRR
(301) 504-2794 Attachments:
1. ITI MOVATS Report dated January 1993
2. List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCE love,+
OFFICE *OGCB:DORS:NRR *TECH ED. *RII *RII X E .
NAME RJKiessel DGable AGibson FJape TGScarbrough
DATE 05/04/93 _Q5/10/93 03/30/93__ 03/30/93 05/19/93
. { , . . .]
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W er AERR o GHMarcus BKGrimes
05/10/93 05z /93 / 05/ /93 05/ /93 fldr,,..r..- laar A
UuMtUMI NAM: JARV.1IN
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IN 93-xx
April 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 project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact(s): Francis Jape, Region II
(404) 331-5540
Thomas G. Scarbrough, NRR
(301) 504-2794 Attachments:
1. ITT MOVATS Report dated January 1993
2. List of Recently Issued NRC Information Notices
OFFICE OGCB:DORS: TECH ED. *RII *RII EMEB:DET
NRR
NAME RJKiesse AGibson FJape TGScarbrou
DATE 05/u /93 05//0/93 03/30/93 03/30/93 05/ /93 j
C:EMEB:DET D:EMEB:DET C:OGCB:DORS D:DORS:NRR
JANorberg JERichardson GHMarcus BKGrimes
U U LPI
M U MML WW . ir
I ULUMLN I NAML: JArL. IN
\%- I
IN 93-xx
June xx, 1993 Related Generic Communications
NRC has issued a number of information notices pertaining to the accuracy of
MOV diagnostic equipment. Most recently, these have included NRC Information
Notice (IN)93-01, Accuracy of Motor-Operated Valve Diagnostic Equipment
Manufactured by Liberty Technologies;" IN 92-23, 'Results of Validation
Testing of Motor-Operated Diagnostic Equipment;" and IN 91-61, "Preliminary
Results of Validation Testing of Motor-Operated Valve Diagnostic Equipment."
NRC is also preparing Supplement 5 to GL 89-10, "Inaccuracy of Motor-Operated
Valve Diagnostic Equipment."
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 project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact(s): Francis Jape, Region II
(404) 331-5540
Thomas G. Scarbrough, NRR
(301) 504-2794 Attachments:
1. ITI MOVATS Report dated January 1993
2. List of Recently Issued NRC Information Notices
OFFICE *OGCB:DORS:NRR *TECH ED. *RII I *RII *EMEB:DET
NAME RJKiessel DGable AGibsori FJape TGScarbrough
DATE IC5/04/93 [05/10/93 103/30/93 03/30/93 I05/19/93
- C:EMEB:DET *D:EMEB:DET C:OGCB:DORS D:DORS:NRR
JANorberg JERichardson lGHMarcus C tl}BKGrimes
05/20/93 05/21/93 06/i7/93 06/ /93
_W.L_ J'.N.
_O~rN
DOCUMENT NAM.t: JAPt.IN / 0j0J&
IN 93-54 July 20, 1993 Related Generic Communications
NRC has issued a number of information notices pertaining to the accuracy of
MOV diagnostic equipment. Most recently, these have included NRC Information
Notice (IN)93-01, "Accuracy of Motor-Operated Valve Diagnostic Equipment
Manufactured by Liberty Technologies;" IN 92-23, "Results of Validation
Testing of Motor-Operated Diagnostic Equipment;" and IN 91-61, "Preliminary
Results of Validation Testing of Motor-Operated Valve Diagnostic Equipment."
NRC also issued Supplement 5 to GL 89-10, "Inaccuracy of Motor-Operated Valve
Diagnostic Equipment," on June 28, 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 project manager.
orig /s/'d by BKGrimes
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Francis Jape, RII
(404) 331-5540
Thomas G. Scarbrough, NRR
(301) 504-2794 Attachments:
1. ITI MOVATS Report dated January 1993
2. List of Recently Issued NRC Information Notices
OFFICE *OGCB:DORS:NRR *TECH ED. *RII *RII *EMEB:DET
NAME RJKiessel DGable AGibson FJape TGScarbrough
DATE 05/04/93 ae05/10/93 A03/30/93 l 03/2P 3 1 a05/19/93l
. _-J i t
- C:EMEB:DET *D:EMEB:DET *C:OGCB:DORS D-J4'9%N
JANorberg JERichardson GHMarcus II
05/20/93 05/21/93 06/17/93 01// /93 DOCUMENT NAME: 93-54.IN
IN 93-xx
April xx, 1993 Manufactured by Liberty Technologies;" IN 92-23, "Results of Validation
Testing of Motor-Operated Diagnostic Equipment;" and IN 91-61, "Preliminary
Results of Validation Testing of Motor-Operated Valve Diagnostic Equipment."
In addition, NRC is preparing a supplement to GL 89-10 to request that
licensees address potential accuracy problems with MOY diagnostic equipment.
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 project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact(s): Francis Jape, Region II
(404) 331-5540
Thomas G. Scarbrough, NRR
(301) 504-2794 Attachments:
1. ITI MOVATS Report dated January 1993
2. List of Recently Issued NRC Information Notices
OFFICE *OGCB:DORS:NRR *TECH ED. *RII *RII XMEB:DET
NAME RJKiessel DGable TAGibson FJape TGScarbrough
DATE l 05/04/93 l05/10/93 l 03/30/93 , 03/30/93 J 05//J1/93_ l
- C:EMEB:DET *D:EMEB:DET C:OGCB:DORS D:DORS:NRR
JANorberg JERichardson GHMarcus BKGrimes
05/20/93 05/21/93 05/ /93 05/ /93 DOCUMENT NAME: JAPE.IN
0
IN 93-xx
April xx, 1993 licensees are adequately addressing the problems associated with MOV
diagnostic equipment inaccuracies, NRC is preparing Supplement 5 to GL 89-10,
"Inaccuracy of Motor-Operated Valve Diagnostic Equipment."
Related Generic Communications
NRC has issued a number of information notices pertaining to the accuracy of
MOV diagnostic equipment. Most recently, these have included NRC Information
Notice (IN)93-01, "Accuracy of Motor-Operated Valve Diagnostic Equipment
Manufactured by Liberty Technologies;" IN 92-23, 'Results of Validation
Testing of Motor-Operated Diagnostic Equipment;" and IN 91-61, "Preliminary
Results of Validation Testing of Motor-Operated Valve Diagnostic Equipment."
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 project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact(s): Francis Jape, Region II
(404) 331-5540
Thomas G. Scarbrough, NRR
(301) 504-2794 Attachments:
1. ITI MOVATS Report dated January 1993
2. List of Recently Issued NRC Information Notices
OFFICE *OGCB:DORS:NRR *TECH ED. *RII *RII *EMEB:DET l
NAME RJKiessel DGable AGibson FJape TGScarbrough
DATE , 05/04/93 . 05/10/93 103/30/93 03/30/93 05/19/93 I*C:EMEB:DET I *D:EMEB:DET
JANorberg
05/20/93 JERichardson
05/21/93 IC:OGCB: DORS
GHMarcus
106/ /93 I D: DORS:NRR
BKGrimes
06/ /93 UDOUMENT NAML: JAL. IN
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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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