Unrecognized Loss of Control Room AnnunciatorsML031070477 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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, 05000370 |
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Issue date: |
06/18/1993 |
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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-93-047, NUDOCS 9306150062 |
Download: ML031070477 (8) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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, 05000370 |
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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 [[: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]] OR [[:05000370]] </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 [[: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]] OR [[:05000370]] </code>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 June 18, 1993 NRC INFORMATION NOTICE 93-47: UNRECOGNIZED LOSS OF CONTROL
ROOM ANNUNCIATORS
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
notice to alert addressees to the potential problem of unrecognized loss of
control room annunciators. 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
Callaway
On October 16, 1992, while the Callaway Plant was operating at 100 percent
power, approximately 75 annunciators on the main control board illuminated.
After verifying that the annunciators were not valid, the shift supervisor
(SS) notified the plant manager and the engineering duty officer of the
condition and requested instrumentation and control (I&C) technicians to begin
repairs. The I&C technicians found that one of four field power supplies for
the annunciators had failed. The failed power supply was replaced and the
annunciators appeared to return to normal. Two minutes later, while removing
jumper cables installed during the replacement, an electrical short occurred.
In the control. room, 371 of the 463 main control board annunciators
illuminated and remained lit. The I&C technicians inspected the power
supplies and determined that the output fuses for all four field power
supplies had blown. The blown fuses resulted in the loss of all main control
board annunciators. This was not recognized by the plant staff.
Callaway procedure EIP-ZZ-00101, "Classification of Emergencies," describes
those conditions which constitute entry into established emergency action
levels (EALs). The procedure states that, for an initiating condition of
"Most or All Alarms (Annunciators) Lost," the proper emergency classification
is an Alert.
9306150062 eb9q Q 9 _ i
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IN 93-47 June 18, 1993 Approximately one hour after the loss of all annunciators, the blown
fuses were replaced and power was restored to the annunciator system. output
personnel verified that power was available to the annunciators by depressing Plant
test switches in the control room. However, this did not test the annunciator
logic circuitry and, as a result, the operating crew was unaware that
164 annunciators with re-flash capability were completely inoperable.
Apparently, the short that blew the output fuses in the field power supplies
also blew fuses in eight annunciator logic power supplies. Later, while
investigating problems with the annunciators, the I&C engineer found
and
replaced the blown fuses in the eight logic power supplies and an appropriate
test was performed. However, there was not an approved procedure for
test nor was it properly documented. By 7:37 p.m. on October 17 the this
control board annunciators had been restored to fully operable status.main
Because the SS failed to recognize that all of the main control board
annunciators were inoperable after the four field power supply output
fuses
had blown, an Alert was not declared on October 17, 1992. On October
licensee determined that an Alert should have been declared and notified 19, the
and local authorities and the NRC of the event. State
Inspection of this event by an NRC Augmented Inspection Team (AIT) found
following weaknesses: (1) insufficient knowledge of the annunciator the
system by
the plant staff, (2) poor communications and inadequate teamwork, (3)
a questioning attitude, and (4) inadequate work performance. Contributing lack of
the insufficient- knawledge--of-the--annuncl-ator- system wa-rthbefattir to
an off-normal operating procedure or other procedure that addressed e6td-Vhave
annunciators. loss of
Salem Unit 2
On December 13, 1992, control room operators at Salem Unit 2 Nuclear
discovered that the overhead annunciators had been inoperable for about Station
90 minutes. The inoperable condition was detected when an alarm printer
printed a change in alarm status which was not reflected by the overhead
annunciators. The operators reset the annunciator system and restored
operable status within two minutes. Subsequent inspection of the event it to
NRC AIT identified several weaknesses that contributed to the problem. by an
operators were not adequately trained to verify proper operation of The
installed micro-processor based annunciator system. The new system a recently
designed with annunciation as a priority task and therefore it did not was not
indicate a critical mispositioned switch. Attempts by the operators
files, despite a procedure caution, contributed to locking up the system. to enter
plant staff delayed in notifying plant management and the NRC. The The
did not have a procedure to deal with the loss of annunciators. The licensee
concluded that the overall knowledge of the system was inappropriate AIT
system that, if lost, required the declaration of an Alert. for a
IN 93-47 June 18, 1993 Discussion
Although plant annunciators are not considered safety
related, they are
important for the safe operation of a nuclear power plant.
unrecognized loss of annunciators may increase the difficultyFurther, an
problems in plant operations and equipment. In order of diagnosing
for plant operators to
recognize and respond properly to a loss of annunciators, have clear procedures, appropriate training, and effective it is important to
between operators and plant support personnel. For the communications
above, an off-normal operating procedure that clearly events described
would have significantly aided the operators to diagnosestated required actions
problem, take necessary response actions, and make requiredthe extent of the
notifications.
Loss of annunciator events were covered by the emergency
procedures of both licensees, premised upon guidance of classification
Appendix 1 of
NUREG-0654/FEMA-REP-1, "Criteria for Preparation and Evaluation
Radiological Emergency Response Plans and Preparedness of.
Power Plants," (November 1980). The NRC recently issued in Support of Nucleae
Revision
Regulatory Guide 1.101, "Emergency Planning and Preparedness 3 to
Reactors" (August 1992). That revision endorsed NUMARC/NESP-007,for Nuclear Power
"Methodology for Development of Emergency Action Levels," Revision 2, (January
an acceptable alternative. With respect to loss of annunciators, 1992), as
NUMARC/NESP-007 guidance provides an alternative delineation the
declaring an Unusual-Event, Alert or-Site Area Emergency. of thresholds for
This information notice requires no specific action or
written response. If
you have any questions about the information in this notice, one of the technical contacts listed below or the appropriate please contact
Nuclear Reactor Regulation (NRR) project manager. Office of
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Bruce L. Bartlett, RIII
(314) 676-3181 Rolf A. Westberg, RIII
(708) 790-5776 Scott A. Boynton, NRR
(301) 504-2926 Attachment:
List of Recently Issued NRC Information Notices
It ' Attachment
J. s t IN 93-47 June 18, 1993 Page I of 1 LIST OF RECENTLY ISSUED
NRC IHFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
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
93-45 Degradation of Shutdown 06/16/93 All holders of OLs or CPs
Cooling System Performance for nuclear power reactors.
93-44 Operational Challenges 06/15/93 All holders of OLs or CPs
During A Dual-Unit for nuclear power reactors.
Transient
93-43 Use of Inappropriate 06/10/93 All holders of OLs or CPs
Lubrication Oils In for nuclear power reactors.
Safety-Related Applications
93-42 Failure of Anti-Rotation 06/09/93 All holders of OLs or CPs
Keys in Motor-Operated for nuclear power reactors.
Valves Manufactured by
Velan
93-41 One Hour Fire Endurance 05/28/93 All holders of OLs or CPs
Test Results for Thermal for nuclear power reactors.
Ceramics Kaowool, 3N
Company FS-195 and
3M Company Interam E-50 2 Barrier Systems 2
93-40 Fire Endurance Test 05/26/93 All holders of OLs or CPs
Results for Thermal for nuclear power reactors. 0
0
Ceramics FP-60 Fire
Barrier Material (n IN0)
05/25/93 All holders of OLs or CPs (n0 too
93-39 Radiation Beams from
Power Reactor Biolog- for nuclear power reactors.
ical Shields _ U,
0o
-o
oL - Operating License 'hi
CP - Construction Permit
49a.
z
z
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: Bruce L. Bartlett, Region III
(314) 676-3181 Rolf A. Westberg, Region III
(708) 790-5776 Scott A. Boynton, NRR
(301) 504-2926 Attachment: List of Recently Issued NRC Information Notices
- RPB:ADM *OGCB:DORS:NRR C/OGCB:DORS:NRR D/DORS/NRR
RSanders JBirmingham GHMarcusgil BKGrimes /
03/17/93 05/06/93 05/.2'7/93 05/ /93 tW
- R/RIII *RIII *PEPB:DRSS:NRR *OEAB:DORS:NRR
BBartlett RWestberg SABoynton TKoshy
04/21/93 04/22/93 05/04/93 05/05/93 DOCUMENT NAME: ANNUNCEB.JLB
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: Bruce L. Bartlett, Region III
(314) 676-3181 Rolf A. Westberg, Region III
(708) 790-5776 Scott A. Boynton, NRR
,,n1n % CAA _nnn
Lt Rcl I d NUR-CT i N e
Attachment: List of Recently Issued NRC Information Notices PA A /4 4)
- RPB:ADM OGCB:DORS:NRR C/OGCB:DORS:NRR D/DORS/NRR
RSanders JBirmingham. GHMarcus BKGrimes
03/17/93 05/ a /93 /: 05/ /93 05/ /93
- R/RIII RI IJ})M' P 4NRR: OEAB:DO :NRR
BBartlett RWestbeVg TKoshydi
04/21/93 05/& /93 05/5 /9 DOCUMENT NAME: ANNUNCE8.JLB
..... .....I
3 have clear procedures, appropriate training, and effective communications
between operators and plant support personnel. For the events described
above, an off-normal operating procedure that clearly stated required actions
would have significantly aided the operators to diagnose the extent of the
problem, take necessary response actions, and make required notifications.
The NRC recently issued Revision 3 to Regulatory Guide 1.101, "Emergency
Planning and Preparedness for Nuclear Power Reactors." That revision
endorsed NUMARC/NESP-007, Revision 2, "Methodology for Development of
Emergency Action Levels," as an acceptable alternative to the method described
in Appendix 1 of NUREG-0654/FEMA REP-1, "Criteria for Preparation and
Evaluation of Radiological Emergency Response Plans and Preparedness in
Support of Nuclear Power Plants." NUMARC/NESP-007 provides guidance that more
clearly delineates the thresholds for declaration of an Unusual Event, Alert
and Site Area Emergency.
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: Bruce L. Bartlett, Region III
(314) 676-3181 Rolf A. Westberg, Region III
(708) 790-5776 Scott A. Boynton, NRR
(301) 504-2926 Attachment: List of Recently Issued NRC Information Notices
- RPB:ADM OGCB:DORS:NRR C/OGCB:DORS:NRR D/DORS/NRR
RSanders JBirmingham GHMarcus BKGrimes
03/17/93 04/ /93 04/ /93 04/ /93
- R/RI II /4 RlIl m PEPB:DRSS:NRR OEAB:DORS:NRR
BBartlett RWest erg SABoynton TKoshy
04/21/93 04/XR./93 04/ /93 04/ /93 DOCUMENT NAME: ANNUNCE8.JLB
IN 93-47
-~ ~ June 18, 1993 Discussion
Although plant annunciators are not considered safety related, they are
important for the safe operation of a nuclear power plant. Further, an
unrecognized loss of annunciators may increase the difficulty of diagnosing
problems in plant operations and equipment. In order for plant operators to
recognize and respond properly to a loss of annunciators, it is important to
have clear procedures, appropriate training, and effective communications
between operators and plant support personnel. For the events described
above, an off-normal operating procedure that clearly stated required actions
would have significantly aided the operators to diagnose the extent of the
problem, take necessary response actions, and make required notifications.
Loss of annunciator events were covered by the emergency classification
procedures of both licensees, premised upon guidance of Appendix 1 of
NUREG-0654/FEMA-REP-1, "Criteria for Preparation and Evaluation of
Radiological Emergency Response Plans and Preparedness in Support of Nuclear
Power Plants," (November 1980). The NRC recently issued Revision 3 to
Regulatory Guide 1.101, "Emergency Planning and Preparedness for Nuclear Power
Reactors" (August 1992). That revision endorsed NUMARC/NESP-007, Revision 2,
"Methodology for Development of Emergency Action Levels," (January 1992), as
an acceptable alternative. With respect to loss of annunciators, the
NUMARC/NESP-007 guidance provides an alternative delineation of thresholds for
declaring an Unusual Event, Alert or Site Area Emergency.
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 signed by
MI-(. 'rimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Bruce L. Bartlett, RIII
(314) 676-3181 Rolf A. Westberg, RIII
(708) 790-5776 Scott A. Boynton, NRR
(301) 504-2926 Attachment:
List of Recently Issued NRC Information Notices
- RPB:ADM *OGCB:DORS:NRR *C/OGCB:DORS:NRR
RSanders JBirmingham GHMarcus mes
03/17/93 05/06/93 05/27/93 05,/l 93
- R/RIII *RIII *PEPB:DRSS:NRR *OEAB:DORS:NRR
BBartlett RWestberg SABoynton TKoshy
04/21/93 04/22/93 05/04/93 05/05/93 DOCUMENT NAME: 93-47.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, Topic: Uranium Hexafluoride, Overexposure)
- Information Notice 1993-05, Locking of Radiography Exposure Devices (14 January 1993, Topic: Uranium Hexafluoride, Inattentive)
- 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, Topic: Uranium Hexafluoride)
- 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, Topic: Uranium Hexafluoride)
- 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, 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, Topic: Thermal fatigue)
- 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, Thermal fatigue)
- Information Notice 1993-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers Due to Support Lever Failure (26 March 1993, Topic: Commercial Grade, Thermal fatigue)
- Information Notice 1993-23, Weschler Instruments Model 252 Switchboard Meters (31 March 1993, Topic: Commercial Grade, Thermal fatigue)
- Information Notice 1993-24, Distribution of Revision 7 of NUREG-1021, Operation Licensing Examiner Standards (31 March 1993, Topic: Job Performance Measure, Thermal fatigue)
- Information Notice 1993-25, Electrical Penetration Assembly Degradation (1 April 1993, Topic: Thermal fatigue)
- 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, Topic: Commercial Grade)
- 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, Topic: Water hammer)
- Information Notice 1993-49, Improper Integration of Software Into Operating Practices (8 July 1993)
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