Degradation of Shutdown Cooling System PerformanceML031070480 |
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: |
06/16/1993 |
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From: |
Grimes B K Office of Nuclear Reactor Regulation |
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To: |
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References |
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IN-93-045, NUDOCS 9306090036 |
Download: ML031070480 (9) |
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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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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 [[: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 June 16, 1993 NRC INFORMATION
NOTICE 93-45: DEGRADATION
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 degradation
of shutdown cooling system performance
at the Oyster Creek Nuclear Generating
Station resulting
from inadequate
operating
procedures.
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
On January 23, 1993, the Oyster Creek Nuclear Generating
Station was in day 57 of the 14R refueling
outage. The plant was in a normal cold-shutdown
condition
with the primary containment
open and the reactor coolant system at about 43' C [110* F]. One reactor recirculation
loop was in service, one recirculation
loop was open, and the remaining
three recirculation
loops were either idled or isolated.
Two shutdown cooling loops were operating
with a combined flow rate of 11,735 liters per minute 13,100 gpm].In order to support the planned activities, the licensee elected to secure operation
of all recirculation
pumps and lower reactor water level. This configuration
would allow completion, in parallel, of recirculation
pump maintenance
activities
and main steam isolation
valve local leak rate testing.When the operators
lowered the reactor water level to approximately
419 cm (165 inches] above the top of active fuel and secured the running.recirculation
pump, the shutdown cooling water took the least resistance
path through the open recirculation
loop, and the majority of flow bypassed the core (see Attachment
1). During the time that the planned activities
were in progress, plant personnel
did not realize that shutdown cooling system performance
was degraded, allowing unmonitored
heatup of the reactor core.On January 25, 1993, after completing
the main steam isolation
valve local leak rate testing, an operations
engineer discovered
that the reactor vessel metal temperature
was about 109C 1228F] at the mid-vessel
point. Several 9306090036 PDI I.E No*[ct 3-. oj58 P ..'v1\
IN 93-45 June 16, 1993 Technical
Specifications
prerequisites
for exceeding
100. C [212 F] were not met, including
the requirement
to establish
primary containment
integrity.
After discovery, operators
took immediate
measures to reduce reactor coolant system water temperature
by first maximizing
flow in the two operating shutdown cooling loops and then placing a third shutdown cooling loop in service. Additionally, the reactor water level was raised to approximately
508 cm [200 inches] above the top of active fuel and a recirculation
pump was started.The immediate
cause of the event was determined
to be plant conditions
established
by a temporary
procedure
change to the shutdown cooling operating procedure
that failed to provide sufficient
forced flow through the reactor core to prevent thermal stratification.
The temporary
procedure
change had been implemented
to allow shutdown operations
with all recirculation
pumps secured and the nominal reactor water level less than the level at which spillover
from the core region to the annulus is assured (approximately
470 cm[185 inches] above the top of active fuel). The change had been developed from a draft engineering
evaluation, but did not include a requirement (stated in the body of the evaluation)
to maintain a specified
shutdown cooling flow of 22,712 liters per minute [6,000 gpm]. Instead, the usual shutdown cooling flow of about 11,735 liters per minute [3,100 gpm] was maintained
which, due to the specified
configuration, allowed the inadvertent
reactor heatup.Further details can be found in Licensee Event Report 50-219/93-002 and NRC Augmented
Inspection
Team Inspection
Report No. 50-219/93-80.
Discussion
This event at Oyster Creek indicated
that the temporary
procedure
change represented
a significant
procedure
revision and that the review process did not identify deficiencies
in the procedure
before it was implemented.
The temporary
procedure
change had been developed
from a draft engineering
evaluation
which concluded
that two shutdown cooling loops in operation
would adequately
cool the core. An additional
assumption
in the body of the evaluation
was that each loop of shutdown cooling would be operating
at its design flow rate of 11,356 liters per minute [3,000 gpm], for a total flow rate of 22,712 liters per minute [6,000 gpm]. This flow rate would be adequate to induce spillover
from the core region to the annulus at the reduced nominal water level. The temporary
procedure
change that implemented
the engineering
evaluation
did not require a minimum flow rate of 22,712 liters per minute [6,000 gpm]. As a result, the operators
following
the deficient
temporary
procedure
change placed two shutdown cooling loops in operation, but did not provide sufficient
shutdown cooling water to the reactor core to maintain reactor vessel temperatures.
In addition, the temporary
procedure
change contained
no provision
or guidance for monitoring
available
instruments
to ensure that decay heat was being adequately
removed from the reactor core.As part of the licensee corrective
actions, the licensee reviewed the effectiveness
of its safety review process concerning
temporary
changes and provided training on the subject of this event to all site personnel
who perform technical
and safety reviews.
IN 93-45 June 16, 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
Offic of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts:
James S. Stewart, RI (215) 337-5240 Peter C. Wen, NRR (301) 504-2832 Attachments:
1. Figure 1, *Oyster Creek Shutdown Cooling System Flow With Open Recirculation
Loop" 2. List of Recently Issued NRC Information
Notices
K. /I'l I Steam Flow *-4-TO Recirculation
- ~Loop Shutdown Cooling System (3 Cooling Loops)Figure 1 Attachment
1 1iK 93-45 June 16, 1993 Open Recirculation
Loop Oyster Creek Shutdown Cooling System Flow With Open Recirculation
Loop
I Attachment
2 IN 93-45 June 16, 1993 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 93-44 93-43 93-42 Operational
Challenges
During A Dual-Unit Transient Use of Inappropriate
Lubrication
Oils in Safety-Related
Applications
Failure of Anti-Rotation
Keys in Motor-Operated
Valves Manufactured
by Velan 06/15/93 06/10/93 06/09/93 All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.93-41 One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Barrier Systems 05/28/93 All holders for nuclear of OLs or CPs power reactors.93-40 ,93-39 93-38 Fire Endurance
Test Results for Thermal Ceramics FP-60 Fire Barrier Material Radiation
Beams from Power Reactor Biolog-ical Shields Inadequate
Testing of Engineered
Safety Features Actuation System 05/26/93 05/25/93 05/24/93 All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders for nuclear of OLs or CPs power reactors.93-37 Eyebolts with Indeter-minate Properties
In-stalled in Limitorque
Valve Operator Housing Covers 05/19/93 All holders of OLs or CPs for nuclear power reactors.0L -Operating
License CP -Construction
Permit
IN 93-45 June 16, 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 !1gnd by Brian K. Gdmeg Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: James S. Stewart, RI (215) 337-5240 Peter C. Wen, NRR (301) 504-283], Attachments:
6 1. Figure 1, "Oyster Creek Shutdown Cooling System Flow With Open Recirculation
Loop'2. List of Recently Issued NRC Information
Notices*rFF pRmVrnus CONCURRFNCF
OFFICE *OGCB:DORS
NAME PCWen/vsb
JSStewart
PKEapen JPDurr MWHodges DATE 04/29/93 05/03/93 03/19/93 03/19/A3 .03/19/93_______- _ .*Tech Ed. I *C:OGCB:DORS--
RSanders I GHMarcus ACThadani 04/29/93 05/10 05/24/93.=DOCUMENT NAME: 93-45.IN**SEE MEMO FROM M.. HODGES TO B.K. GRIMES DATED 3/19/93 PM (A. Dromerick), EAB (J. Carter) and AIT Team Leader (J. Beall) were consulted
during the development
of this IN.
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 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: James S. Stewart, Region I (215) 337-5240 Peter C. Wen, NRR (301) 504-2832 Attachments:
1. Oyster Creek Shutdown Cooling System Flow With Open Recirculation
Loop 2. List of Recently Issued NRC Information
Notices*SEE PREVIOUS CONCURRENCE
OFFICE *OGCB:DORS
NAME PCWen/vsb
JSStewart
PKEapen JPDurr MWHodges DATE l04/29/93 l05/03/93 I 03/19/93 l 03/19/93 l03/19/93*Tech Ed.*C:OGCB:DORS
D:DORS:NRR
I RSanders GHMarcus 04/29/93 _ 05/10/93 ;onf~~~l ----1F o I~tsPIm BKGrimes UULUIMNI NAMI: UIIrMUN .PW)05/ /93 4 xk)**SEE MEMO FROM M.W. HODGES TO B.K. GRIMES DATED 3/19/93 PM (A. Dromerick), EAB (J. Carter) and AIT Team Leader (J. Beall) were consulted
during the development
of this IN.530 ACiwAt #f A);mli v-AV'I/tllos
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 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: James S. Stewart, Region I (215) 337-5240 Peter C. Wen, NRR (301) 504-2832 Attachments:
1.2.Oyster Creek Shutdown Cooling System Flow With Open Recirculation
Loop List of Recently Issued NRC Information
Notices*SEE PREVIOUS CONCURRENCE
.OFFICE *OGCB:DORS
DRS:RI SC:DRS:RI
BC:DRS:RI
D:DRS:RI NAME PCWen/vsb
4SStewart
PKEapen JPDurr MWHodges DATE 04/29/93 05/3,0 Cal P/1/93 0/ l/9 3 I__ 1_/93_J*Tech Ed.C:OGCB:DORS
D:DORS:NRR
4xx %E memo Fizz MYS 144 RSanders GHMarcus Ci~l BKGrimes 04/29/93 05/ 1q 9 93 1 05/ /93 44 1/1 A/ 3 DOUUMENT NAME: OCTPCIN.PW
PA (A 'rolnerlk&) , 1 (. Covte). t AlT Team Leader (J. &3eA.A) LxQe cuAJX4A Alxrzrl t. 4JeLt"e'4
.tk& z4 BJ
IN 93-XX May xx, 1993 Page 2 of 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: James S. Stewart, Region I (215) 337-5240 Peter (301)C. Wen, NRR 504-2832 Attachments:
1.2.Oyster Creek Shutdown Cooling System Flow With Open Recirculation
Loop List of Recently Issued NRC Information
Notices OFFICE OBORS DRS:RI SC:DRS:RI
BC:DRS:RI
D:DRS:RI NAME PCWen/vsb
JSStewart
PKEapen JPDurr MWHodges DATE _/aq/93_ 05/ /93 05/ /93 05/ /93 105/ /93 Tech Ed.C:OGCB:DORS
D: DORS:NR RI flU"AJA& GHMarcus BKGrimes ON/.11/93
05/ /93 05/ /93%^rrlT scur -rnT -ab UUUMt Ii NAMt: ULIrMLIN.fW
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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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