Operational Challenges During a Dual-Unit TransientML031070483 |
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, 05000355, 05000204, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
06/15/1993 |
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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-93-044, NUDOCS 9306080170 |
Download: ML031070483 (8) |
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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, 05000355, 05000204, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Category:NRC Information Notice
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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 [[:05000355]] OR [[:05000204]] 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 [[:05000355]] OR [[:05000204]] 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 June 15, 1993 NRC INFORMATION NOTICE 93-44: OPERATIONAL CHALLENGES DURING A DUAL-UNIT
TRANSIENT
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
PurDose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information shift
notice to inform addressees of an event during which an atypical in that
staffing level and lack of familiarity with the tasks to be performed
control room operating shift
shift configuration affected the ability of the review the
to respond to the event. It is expected that recipients will
information for applicability to their facilities and consider contained actions, as
suggestions in
appropriate, to avoid similar problems. However, no specific
this information notice are not NRC requirements; therefore, action or written response is required.
DescriDtion of Circumstances
On December 31, 1992, a dual-unit reactor trip initiated by an electrical Units 1 and 2 fault in the switchyard occurred at the Sequoyah Nuclear Plant, event the control
at Sequoyah share a common control room. At the time of the
room reactor operator staffing was the minimum allowed by the plant Technical
Specifications (TS); shift staffing consisted of five licensed senior
operators (the shift operations supervisor, one assistant shift operations
supervisor for each unit, the shift technical advisor, and an additional
senior operator) and three reactor operators - two assigned to Unit 1 and one
assigned to Unit 2. The NRC inspection team investigating the event concluded
that the Unit 2 response to the event, with one reactor operator, was hampered
by lack of adherence to procedures, operator errors, and an unnecessary
cooldown of the reactor coolant system (RCS) after the reactor trip. The
event, with two reactor operators, was normal.
Unit 1 response to the same
Discussion
An NRC inspection team reviewed the effects of the Unit 2 staffing level
during the event with regard to the crew's ability to stabilize the unit after
2 the reactor trip occurred. The inspection team concluded that the toUnit erroneous
staffing level delayed the recovery of plant systems, contributed
decisions made by the assistant shift operations supervisor (ASOS), and
93060801VO f33o(JISo
SIle-/
t/r,0t
IN 93-44 June 15, 1993 overburdened and challenged the crew's ability to perform tasks in the manner
in which it was trained. Control room simulator training scenarios had not
been conducted using only one reactor operator.
Although the normal shift staffing and training consisted of two
reactor operators for each unit, licensee operational staffing practices
resulted in the frequent use of one reactor operator for one of the units.
The licensee used this reduced staffing configuration 12 times in
December 1992. In this configuration, with the dual-unit transient, the
single reactor operator performed all of the recovery evolutions for the unit
as directed by the ASOS in charge of the unit.
Because of delays caused by the one reactor operator performing primary and
secondary system recovery evolutions, as required by the applicable recovery
procedures, an RCS cooldown resulted. This was a direct result of the crew
not adequately controlling auxiliary feedwater after the reactor
atypical staffing level also contributed to problems involving thetrip. The
decision
the assistant shift operations supervisor to use the normal-batch borate of
process in response to the cooldown rather than the emergency borate process
as required by the emergency procedure. The decision not to use the emergency
borate process was made, in part, because of the reluctance of the assistant
shift operations supervisor to commit the one reactor operator to the
emergency borate process, which restricts the operator's attention to
monitoring only that activity.
As a corrective action to prevent recurrence, the licensee implemented revised
administrative controls to ensure that the control room staffing
maintained at two reactor operators for each operating unit. The will
need
be
additional training at minimum staffing levels is being evaluated by thefor
licensee.
Related Generic Communications
1. IN 85-80, "Timely Declaration of an Emergency Class, Implementation of
an Emergency Plan, and Emergency Notifications," dated October 15, 1985
2. IN 91-77, "Shift Staffing at Nuclear Power Plants," dated November 26,
1991
IN 93-44 June 15, 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: S. M. Shaeffer, RII
(615) 842-8001 D. R. Desaulniers, NRR
(301) 504-1043 Attachment: a dgtil0l5
List of Recently Issued NRC Information Notices
LIST OFRECENTLY ISSUED \_2 NRCINFORMATION NOTICES I' a
--
Notice Ib. Subject Issua ssued to I
93-43 Use of Inappro te 06/10/93 All holders of OLsor CPs
Lubrication OI s in for nuclear power reactors.
Sefety-Rolat d Applications
93-42 Failure of Anti-Rotation 06/09/93 All holders of OLsor CPs
Keys in Motor-Operated for nuclear Power reactors.
FVaTes Manufactured by
93-41 One Hour Fire Endurance 05/28/93 All holders of OLsor CPs
Test Results for Thermal for nuclear power reactors.
Ceramics Kaowool3M
Ctany FS-195 and
311Company Intern E-SO
Barrier Systoes
93-40 Fire Endurance Test 0O/26/93 All holders of OLsor CPs
Results for Thereal for nuclear power reactors.
Ceramics FP-60 Fire
Barrier Material
93-39 Radiation Beas from 09/25/93 All holders of OLsor CPs
Power Reactor Dialog- for nuclear power reactors.
1csl Shields
93-38 Imedequote Testing of 05/24/3 All holders of OLsor CPs
Engineered Safety for nucleur power reactors.
Featurs Actuation
Systmn
93-31 Eyobolts with Indeter- 05/19/93 All holders of OLsor CPi
Minote Properties In- for nuclear power reactors.
stalled In tleitorque
Valve Operator Housing
Covers
93-36 Nortifications, Reports OS/07/93 All U.S. Nuclear Regulatory
andRecords of Nisd1ni- Cosmission Medical
istrations licensees.
93-3S Insights from Comon- OS/12/93 All holders of OLsor CPs
Cause Failure Events for nuclear power plants
(UPP)'.
OL* Oper Lcense
LIog
tP - Construction Per1it
UNITED STATES
NUCLEAR REGULATORY COMMISSION FIRST CLASS MAIL
WASHINGTON, D.C. 20555-0001 POSTAGE AND FEES PAID
USNRC
PERMIT NO. G-67 OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE, $300
PFUNTED ON RECYCLED PAPER
IN 93-44 June 15, 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 Isgned by
Brian K. Grime§
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: S. M. Shaeffer, RII
(615) 842-8001 D. R. Desaulniers, NRR
(301) 504-1043 Attachment:
List of Recently Issued NRC Information Notices
- DD:DRCH *D:DRCH *PD2-4:DRPE *DRP:RII RVC
RGallo BBoger FHebdon for EMerschoff
05/21/93 05/21/93 06/02/93 05/28/93
- OGCB:DORS *TechEd *OGCB:DORS
TJKim MMejac GMarcus '9
05/28/93 05/24/93 06/04/93 06// o/93 DOCUMENT NAME: 93-44.IN
IN 93-XX
June 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: S. M. Shaeffer, Region II
(615) 842-8001 D. R. Desaulniers, NRR
(301) 504-1043 Attachment:
List of Recently Issued NRC Information Notices
- DD:DRCH *D:DRCH *PD2-4:DRPE *DRP:RII RVC
RGallo BBoger FHebdon for EMerschoff
05/21/93 05/21/93 06/02/93 05/28/93
- OGCB:DORS *TechEd OGCB:DORS DORS:NRR
TJKim MMejac GMarcus qW4 BGrimes
05/28/93 05/24/93 06/+ /93-- 06/ /93 DOCUMENT NAME: SEQUOYAH.INF
IN 93-XX
May 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
the technical contact 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 contact: S. M. Shaeffer, Region II
(615) 842-8001 D. R. Desaulniers, NRR
(301) 504-1043 Attachment: List of Recently Issued NRC Information Notices
File Name: SEJWOYAH.INF
ConcurentU
PD z:DRPE DRP: RII ARC,
eu'2~4 iip FHegion $ EMerschoff
o~fiO 9 /57L493 05/ae/93 OGCB:DQjRS TechEd OGCB:DORS DORS:NRR
TJKim'J GMarcus BGrimes
O5/;?S/9 05p//93 05/ /93 05/ /93
From: Richard V. Crlenjak (RVC)
To: TJK3 Date: Friday, May 28, 1993 1:01 pm
Subject: RII CONCURRENCE OF PROPOSED IN
Region II has completed a review of the proposed Information
Notice, OPERATIONAL CHALLENGES DURING A DUAL-UNIT TRANSIENT. We
have no further comments and concur with the proposed IN.
Should you need any additional info let me know.
Thanks, Jack
cc: WEH, PJK1, SMS, AFG, JRJ, TAP, EWM
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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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