Distribution of Revision 7 of NUREG-1021, Operation Licensing Examiner StandardsML031080029 |
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: |
03/31/1993 |
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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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NUREG-1021 IN-93-024, NUDOCS 9303250008 |
Download: ML031080029 (6) |
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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 March 31, 1993 NRC INFORMATION NOTICE 93-24: DISTRIBUTION OF REVISION 7 OF NUREG-1021,
"OPERATOR LICENSING EXAMINER STANDARDS"
Addressees
All holders of operator and senior operator licenses at nuclear power
reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to inform all holders of operator and senior operator licenses at
nuclear power reactors that the NRC issued Revision 7 of NUREG-1021, "Operator
Licensing Examiner Standards." Revision 7 of NUREG-1021 contains changes to
the processes for licensing operators and conducting NRC initial licensing and
requalification examinations. It is expected that recipients will review the
information for applicability and consider actions, as appropriate, to their
licensed activities. However, suggestions contained in this information
notice are not NRC requirements; therefore, no specific action or written
response is required.
Discussion
In 1991, the staff proposed to evaluate a crew-based grading method for
dynamic simulator tests that would reduce examination stress, encourage
operator teamwork, and minimize the regulatory impact of NRC requalification
examinations on facility licensees and licensed operators. With the
concurrence of the Commission, the staff wrote a crew-based simulator test
procedure and, in 1992, tested the procedure in a pilot program by examining
over 100 licensed operators at 6 facilities. After completing the pilot
program, the staff incorporated the crew-based simulator test procedure into a
draft Revision 7 of NUREG-1021.
In July 1992, the staff sent copies of the draft revision of NUREG-1021 to the
Professional Reactor Operator Society (PROS) and the Nuclear Management and
Resources Council (NUMARC) for comment, and placed a copy in the NRC Public
Document Room. NUMARC distributed the draft NUREG-1021 to facility licensees
and sponsored a meeting at which the NRC staff discussed the draft revision
with industry representatives. NUMARC consolidated the facility comments and
forwarded them to the NRC. The PROS organization also forwarded comments on
the draft revision to the NRC. The staff evaluated the comments and made
appropriate changes to the draft revision. In January 1993, the staff sent
Revision 7 of NUREG-1021 to all holders of operating licenses or construction
permits. A copy is also available in the NRC Public Document Room.
9303250008 P4D 03 qE - CAiD0o E
IN 93-24 March 31, 1993 Changes made to Revision 7 of NUREG-1021 include
and structure of the initial and requalification refinements to the content
will enhance the validity of the examination as wellexaminations; these changes
administrative efficiency and consistency. Significant as improve its
requalification examination include (1) condensing changes in the
performance measures with no prescripted questions, the walkthrough to five job
crew-based dynamic simulator evaluations and (3) (2) incorporating the
using low-power and shutdown
Job performance measures and low-power scenarios
from.facility reference
material in the operating test. Examples of specific
NRC initial examinations include (1) use of only changes affecting the
objectively
on the initial written examination and (2) a decrease scored questions
prescripted follow-up questions related to Job performancein the number of
walkthrough portion of the operating test. Revision measures on the
an Executive Summary which summarizes all of the 7 of NUREG-1021 contains
Revision 7. non-editorial changes made to
In February 1993, the NRC published in the Federal
the public of the revision. As indicated in the Register a notice informing
Federal
NRC will use Revision 7 of NUREG-1021 for all initial Register notice, the
examinations scheduled to be conducted after August and requalification
9, 1993.
This information notice requires no specific action
you have any questions about the information in or written response. If
one of the technical contacts listed below-orm thethis notice, please contact
Nuclear Reactor Regulation (NRR) project manager. appropriate Office-of
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Fred Guenther, NRR
(301) 504-1056 Christopher Gratton, NRR
(301) 504-1055 Attachment:
List of Recently Issued NRC Information Notices
I.
Attachment
IN 93-24 March 31, 1993 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
93-23 Weschler Instruments 03/31/93 All holders of OLs or CPs
Model 252 Switchboard for nuclear power reactors.
Meters
93-22 Tripping of Klockner- 03/26/93 All holders of OLs or CPs
Moeller Molded-Case for nuclear power reactors.
Circuit Breakers due to
Support Level Failure
93-21 Summary of NRC Staff 03/25/93 All holders of OLs or CPs
Observations Compiled for light water nuclear
during Engineering Audits power reactors.
or Inspections of Licen- see Erosion/Corrosion
Programs
93-20 Thermal Fatigue Cracking 03/24/93 All holders of OLs or CPs
of Feedwater Piping to for PWRs supplied by
Steam Generators Westinghouse or Combustion
Engineering.
93-19 Slab Hopper Bulging 03/17/92 All nuclear fuel cycle
licensees.
93-18 Portable Moisture-Density 03/10/93 All U.S. Nuclear Regulatory
Gauge User Responsibilities Commission licensees that
during Field Operations possess moisture-density
gauges.
93-17 Safety Systems Response 03/08/93 All holders of OLs or CPs
to Loss of Coolant and for nuclear power reactors.
Loss of Offsite Power
93-16 Failures of Nut-Locking 02/19/93 All holders of OLs or CPs
Devices in Check Valves for nuclear power reactors.
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
OL = Operating License
CP - Construction Permit
IN 93-24 March 31, 1993 Changes made to Revision 7 of NUREG-1021 include refinements to the content
and structure of the initial and requalification examinations; these changes
will enhance the validity of the examination as well as improve its
administrative efficiency and consistency. Significant changes in the Job
requalification examination include (1)condensing the walkthrough to five the
performance measures with no prescripted questions, (2) incorporating
crew-based dynamic simulator evaluations and (3)using low-power and shutdown
job performance measures and low-power scenarios from facility reference the
material in the operating test. Examples of specific changes affecting
NRC initial examinations include (1)use of only objectively scored questions
on the initial written examination and (2)a decrease in the number of
prescripted follow-up questions related to Job performance measures on the
walkthrough portion of the operating test. Revision 7 of NUREG-1021 containsto
an Executive Summary which summarizes all of the non-editorial changes made
Revision 7.
In February 1993, the NRC published in the Federal Register a notice informing
the public of the revision. As indicated in the Federal Register notice, the
NRC will use Revision 7 of NUREG-1021 for all initial and requalification
examinations scheduled to be conducted after August 9, 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.
orig /s/'d by BKGrimes
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Fred Guenther, NRR
(301) 504-1056 Christopher Gratton, NRR
(301) 504-1055 Attachment: J
k/_J
List of Recently Issued NRC Information Notices
- OGCB:DJORS:NRR *TECHED:ADM *C/OGCB:ORS:NRRt
JBirmingham JMain GHMarcus
03/18/93 02/18/93 03/23/93 9303/Z/
- HOLB:DRCH:NRR *AC/HOLB:DORS:NRR *D/DRCH:NRR
CGratton DJLange BABoger
03/12/93 03/22/93 03/22/93 DOCUMENT NAME: 93-24.IN
IN 93- March, , 1993 The staff issued Revision 7 of NUREG-1021 to all holders of operating licenses
or construction permits. Copies of the revision should be available through
facility training departments. Copies of the revision are also available in
the NRC Public Document Room. Attachment 1 of this notice is a summary of the
significant changes in Revision 7 of NUREG-1021.
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: Fred Guenther, NRR
(301) 504-1056 Christopher Gratton, NRR
(301) 504-1055 Attachments:
1. Summary of Significant Changes
2. List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCE DOCUMENT NAME: EXAM.IN
OGCB:DORS:NRR *TECHED:ADM C/OGCB:DORS:NRR D/DORS:NRR
JBirmingham JMain GHMarcus BKGrimes
03//t/93 rV46 087193 03/ /93 3 3 fss
HOLB:DRC N R HOLB:DRC tR AC/H NRR D]DRCH:NRRI \
CGratto r FGuep r DJLangez Bogarr \'
03/#l-/93 0ur /93 03/12,/93 !,,1 03/1{?93$*
A I/i&.
K>
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: Fred Guenther, NRR
(301) 504-1056 Christopher Gratton, NRR
(301) 504-1055 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCE DOCUMENT NAME: EXAM. IN
- OGCB:DORS:NRR *TECHED:ADM C/OGCB:DORS:NRR D/DORS:NRR
JBirmingham JMain GHMarcu§60M BKGrimes L
03/18/93 02/18/93 03/.?Z/93- 03/ /93 v~
- HOLB:DRCH:NRR *AC/HOLB:DORS:NRR *D/DRCH:NRR
CGratton DJLange BABoger
03/12/93 03/22/93 03/22/93
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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)
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