Adequacy of Emergency and Essential LightingML031130214 |
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: |
10/31/1990 |
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From: |
Rossi C Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-90-069, NUDOCS 9010250054 |
Download: ML031130214 (10) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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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 October 31, 1990 NRC INFORMATION
NOTICE NO. 90-69: ADEQUACY OF EMERGENCY
AND ESSENTIAL
LIGHTING
Addressees
All holders of operating
licenses or construction
permits for nuclear power reactors.
Purpose
- This information
notice is intended to alert addressees
to a possible problem concerning
the adequacy of emergency
and essential
lighting at commercial
power reactor facilities.
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 do not constitute
NRC requirements;
therefore, no specific action or written response is required.
i Description
of Circumstances:
On March 3, 1989, Unit 3 at the Palo Verde Nuclear Generating
Station experi-enced a reactor/turbine
trip, main steam isolation, containment
isolation, and safety injection
as a result of a grid-induced
load rejection
event. This event included three significant
system failures:
(1) half of the steam bypass control system malfunctioned;
(2) the atmospheric
dump valves (ADYs) failed to operate from the control room and the remote shutdown panel; and (3) the emergency
lighting in the main steam support structure (MSSS) failed, hampering the operators
in their attempt to cope with the ADY failures.
Being unable to maintain pressure control on the secondary
side by operating
the ADVs from the control room or the remote shutdown panel, plant personnel
attempted
to establish local (manual) control of the ADYs in the MSSS. When operators
first entered the MSSS, they found no direct lighting.
Normal lighting was lost due to the loss of power to the non-Class
1E electrical
busses in the plant. The emergency lighting was not properly positioned
in the north MSSS room (containing
the ADVs for the No. 1 steam generator)
to provide adequate lighting for the operators
to perform their required activities
and was not functioning
at all in the south MSSS room (containing
ADVs for the No. 2 steam generator).
Because of a burned-out
light bulb, plant personnel
could not restore essential lighting (from Class 1E power sources) in the south MSSS room."C-( 01200543 IN 90-69 October 31, 1990 During the NRC inspection
(50-530/89-13)
conducted
by an augmented
inspection
team (AIT) sent to examine the event at Palo Verde, the staff found deficien-cies in the licensee's
maintenance
and testing of emergency
and essential lighting.
The team discovered
that plant personnel
had waived the quarterly preventive
maintenance (PM) tasks on the MSSS emergency
and essential
lights for five consecutive
quarters.
By grouping the lights in the MSSS with the lights in the containment
building, which were inaccessible
during power operations, the PM tasks were waived for the MSSS lights during each of these periods along with the containment
lights. NRC inspections
further revealed that the licensee, prior to the performance
of the 8-hour lighting unit dis-charge test, performed
preventive
maintenance (i.e., battery replacement, addition of electrolyte, cleaning of battery terminals, and battery charging)on the lighting unit battery. This preventive
maintenance
practice resulted in not verifying
the performance
of the 8-hour emergency
lighting units in the Was found" condition.
The inspections
also revealed that the licensee had failed to implement
the relevant portions of its quality assurance
program for emergency
lighting.
Because of these failures, the emergency
lighting was not properly tested, and deficiencies
were not properly corrected.
After the event, plant personnel
reconstructed
the design bases of the lighting system and conducted
walkdown inspections
of the emergency
and essen-tial lighting in the plant. In some instances, the licensee found the lighting to be inadequate
to perform the required tasks because the original design did not require emergency
lights or because the emergency
lights provided inade-quate illumination.
In addition, the licensee identified
many areas that required the installation
of or modification
to lighting to meet the licensee's
design bases and the requirements
in 10 CFR Part 50 Appendix R.Background:
At Palo Verde, the essential
lighting system is an integral part of the normal lighting system that provides illumination
if the normal lighting system fails.The essential
lighting system is rated non-Class
lE but is powered from Class lE sources. The system provides lighting in the control room, in the shutdown panel area, in the main walkways and stairs, in the Class lE switchgear
rooms, in areas having Class lE equipment, and in areas used for the safe shutdown of the reactor. Upon loss of the normal lighting system, the essential lighting system provides adequate illumination
for the safe shutdown of the reactor. The system receives power from two redundant
and independent
Class 1E ac busses. Each redundant
Class 1E ac bus supplies power to 50 percent of the essential
lighting in the vital areas. The diesel generators
provide backup power.
IN 90-69 October 31, 1990 The emergency
lighting system receives dc power from two redundant
Class lE batteries
through inverters
and provides illumination
for the control room, the auxiliary
electrical
equipment
rooms, the stairways, and the points leading to plant exits. The system is normally deenergized
and is automatically
energized
upon loss of ac power to the normal system. The emergency
lighting system is also composed of 8-hour and li-hour (individually
battery-powered)
emergency
lighting units. The 8-hour emergency
lighting units are designed to meet the technical
requirements
of 10 CFR 50 Appendix R, Section III.J which requires that emergency
lighting units with at least an 8-hour battery power supply be provided in all areas needed for operation
of safe shutdown equipment and in access and egress routes thereto. The li-hour emergency
lighting units are installed
to meet the requirements
of the Life Safety Code. These lighting units are generally
installed
in plant locations
to accommodate
the safe evacuation
of personnel
in the event of a fire in such areas.Discussion:
During the Palo Verde event, the inadequate
lighting conditions
significantly
complicated
the licensee's
efforts to cope with the initial failure of the ADVs, which delayed the commencement
of the controlled
removal of decay heat as called for by the emergency
operating
procedures.
It is important
to note that adequate PM and routine testing programs for essential
and emergency
lighting systems are helpful in ensuring adequate illumination
for the operation
of safe shutdown equipment.
Emergency
lighting is a key fire protection
feature associated
with supporting
post-fire
safe shutdown operations.
The exercise of good engineering
design practices
that conform to industry standards
ensures the ability of the lighting system to provide adequate station lighting in all vital areas during all types of accident or transient
conditions.
The implementation
of an effective
PM and testing program which demonstrates
lighting system operability
is important.
Emergency
lighting PM programs recommended
by manufacturers
generally
include routine monitoring
of the battery condition
for each lighting unit, periodic load testing to verify that the lighting unit and its associated
charger are functioning
properly, and a periodic "as found" 8-hour lighting unit discharge test. In addition, the Palo Verde event identified
that the inadvertent
repositioning
of the emergency
lighting fixtures can cause inadequate
illumina-tion and that routine verification
of emergency
lighting fixture orientation
can ensure that emergency
lighting is effective.
IN 90-69 October 31, 1990 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
NRR project manager.Charles E. Rossi,'rectoor
Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
Contacts:
N. K. Trehan, NRR (301) 492-0777 S. R. Peterson, NRR (301) 492-3062 Attachment:
List of Recently Issued NRC Information
Notices
Attachment
1 IN 90-69 October 31, 1990 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 90-68 90-67 90-66 Stress Corrosion
Cracking of Reactor Coolant Pump Bolts Potential
Security Equipment Weaknesses
Incomplete
Draining and Drying of Shipping Casks High Radiation
Hazards From Irradiated
Incore Detectors
and Cables Recent Orifice Plate Problems Potential
for Common-Mode
Failure Of High Pressure Safety Injection
Pumps or Release of Reactor Coolant Outside Containment
During A Loss-Of-Coolant
Accident Management
Attention
to the Establishment
and Main-tenance of A Nuclear Criticality
Safety Program 10/30/90 10/29/90 10/25/90 10/5/90 10/5/90 10/4/90 10/3/90 88-63, Supp. 1 90-65 90-64 90-63 All holders of OLs or CPs for pres-surized water reactors (PWRs).All holders of OLs or CPs for nuclear power reactors and Category I fuel facilities.
All holders of OLs for nuclear power reactors and all registered
users of NRC approved waste shipping packages.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 pres-surized-water
reactors.All fuel cycle licensees
possess-ing more than critical mass quantities
of special nuclear material.OL = Operating
License CP = Construction
Permit
IN 90-69 October 31, 1990 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
NRR project manager.Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
Contacts: N. K. Trehan, NRR (301) 492-0777 S. R. Peterson, NRR (301) 492-3062 Attachment:
List of Recently Issued NRC Information
Notices*SEE PREVIOUS CONCURRENCES
C/OGCB:DOEA:NRR
10/18/90 RPB:ADM*TechEd 10/18/90 AD/AD45*BABoger 10/09/90 D/PD5 PD5:DRSP:NRR
10/09/90 09/24/90 OGCB:DOEA:NRR
- PCWen 09/24/90 SELB:DST:NRR
- NKTrehan 09/24/90 C/SELB:DST:NRR
- FRosa 09/25/90 C/SPLB:DST:NRR
10/03/90 D/DST: NRR*AThadani 10/03/90 DOCUMENT NAME: IN 90-69 IN 90-XX October xx, 1990 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
NRR project manager.Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
Contacts: N. K. Trehan, NRR (301) 492-0777 S. R. Peterson, NRR (301) 492-3062 Attachment:
List of Recently Issued NRC Information
Notices Document Name: INADQUATE
LIGHTING*SEE PREVIOUS CONCURRENCES
D/DOEA:NRR
CERossitt col/o9 J I RPB:AD A D/A5A 9"e CHB e TEd j h ABoger EDyer 10/10/990
O M l 91O/q /9,*OGC :DOEA:F R *SELB:DST:NRR
/SPLB:DST:NRR
PCWen NKTrehan FRosa ( IWCMcCracken
09/24/90 09/24/90 09/25/90 ' 1 og /90*PD5:DRSP:NRR
SRPeterson
09/24/90 /t10(s
IN 90-XX September
xx, 1990 Discussion:
During the Palo Verde event, the inadequate
lighting conditions
significantly
complicated
the licensee's
efforts to cope with the initial ADVs failure.However, the plant personnel
were eventually
able to open two ADVs and, thereby, commence a controlled
removal of decay heat as called for by the emergency
operating
procedures.
Other plants may also have inadequate
PM programs for the emergency
and the essential
lighting systems and may provide inadequate
illumination
for the operation
of safe shutdown equipment.
This event also points out that the inadvertent
repositioning
of emergency
lighting units can cause inadequate
illumination.
By verifying
the orientation
of these units, the licensees
can ensure that the lights are positioned
properly.Emergency
lighting is a key fire protection
feature for the operation
of the safe shutdown equipment.
Appendix R to 10 CFR Part 50 requires 8-hour emergency
lighting units in areas used for the operation
of safe shutdown equipment
and in access and egress routes thereto. The staff relies on the exercise of good engineering
design practice and design criteria that conform to industry standards
to ensure the ability of the lighting system to provide adequate station lighting in all vital areas during all types of accident or transient
conditions
and in the access routes to and from these areas.This information
notice requires you have any questions
about the of the technical
contacts listed no specific action or written response.
If information
in this notice, please contact one below or the appropriate
NRR project manager.Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
Contacts: N. K.(301)Trehan, NRR 492-0777 S. R. Peterson, NRR (301) 492-3062 Attachment:
List of Recently Issued NRC Information
Notices Document Name: INADQUATE
LIGHTING D/DOEA:NRR
CERossi 09/ /90 OGCB:DOEA:NRR
PCWen Fcv'09/a4/9 O C/OGCB:DOEA:NRR
CHBerlinger
09/ /90 SELB:DST:NRR
NKTrehanJLS
09/ A/90 RPB:ADM TechEd 09/ /90 C/SELB : IRR FRo 094S9 AD/AD45 BABoger 09/ /9OqJ2s D/DST:NRRrt
t'AThadani 09/ /90 D/PD5 JEDyer 09/ /90 PD5:DRSP:NRR
SRPeterso
e o9,o/90 C/S P s13 sT :PJR Ce EmcctfcKW
Document Name: INADQUATE
LIGHTING Requestor's
ID: WERTMAN Author's Name: peter wen Document Comments: S34 information
notice
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list | - Information Notice 1990-01, Importance of Proper Response to Self-Identified Violations by Licensees (12 January 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-02, Potential Degradation of Secondary Containment (22 January 1990)
- Information Notice 1990-03, Malfunction of Borg-Warner Bolted Bonnet Check Valves Caused by Failure of the Swing Arm (23 January 1990, Topic: Liquid penetrant)
- Information Notice 1990-04, Cracking of the Upper Shell-to-Transition Cone Girth Welds in Steam Generators, (26 January 1990, Topic: Nondestructive Examination)
- Information Notice 1990-05, Inter-System Discharge of Reactor Coolant (29 January 1990)
- Information Notice 1990-06, Potential for Loss of Shutdown Cooling While at Low Reactor Coolant Levels (29 January 1990)
- Information Notice 1990-07, New Information Regarding Insulation Material Performance and Debris Blockage of PWR Containment Sumps (30 January 1990)
- Information Notice 1990-08, KR-85 Hazards from Decayed Fuel (1 February 1990)
- Information Notice 1990-08, KR-85 Hazards From Decayed Fuel (1 February 1990)
- Information Notice 1990-09, Extended Interim Storage of Low-Level Radioactive Waste by Fuel Cycle and Materials Licensees (5 February 1990, Topic: Decommissioning Funding Plan)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking (PWSCC) of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Liquid penetrant)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Nondestructive Examination, Liquid penetrant)
- Information Notice 1990-11, Maintenance Deficiency Associated with Solenoid-Operated Valves (28 February 1990)
- Information Notice 1990-12, Monitoring or Interruption of Plant Communications (28 February 1990)
- Information Notice 1990-13, Importance of Review and Analysis of Safeguards Event Logs (5 March 1990)
- Information Notice 1990-14, Accidental Disposal of Radioactive Materials (6 March 1990, Topic: Brachytherapy)
- Information Notice 1990-15, Reciprocity Notification of Agreement State Radiation Control Directors Before Beginning Work in Agreement States (17 March 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-16, Compliance with New Decommissioning Rule (7 March 1990)
- Information Notice 1990-17, Weight and Center of Gravity Discrepancies for Copes-Vulcan Valves (8 March 1990, Topic: Earthquake)
- Information Notice 1990-18, Potential Problems with Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990)
- Information Notice 1990-18, Potential Problems With Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990)
- Information Notice 1990-19, Potential Loss of Effective Volume for Containment Recirculation Spray at PWR Facilities (14 March 1990)
- Information Notice 1990-20, Personnel Injuries Resulting from Improper Operation of Radwaste Incinerators (22 March 1990)
- Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction was Underestimated (22 March 1990)
- Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction Was Underestimated (22 March 1990)
- Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units (23 March 1990, Topic: Reactor Vessel Water Level)
- Information Notice 1990-23, Improper Installation of Patel Conduit Seals (4 April 1990)
- Information Notice 1990-24, Transportation of Model Spec 2-T Radiographic Exposure Device (10 April 1990)
- Information Notice 1990-24, Transportation of Model SPEC 2-T Radiographic Exposure Device (10 April 1990)
- Information Notice 1990-25, Loss of Vital AC Power With Subsequent Reactor Coolant System Heat-Up (16 April 1990)
- Information Notice 1990-25, Loss of Vital AC Power with Subsequent Reactor Coolant System Heat-Up (16 April 1990)
- Information Notice 1990-26, Inadequate Flow of Essential Service Water to Room Coolers and Heat Exchangers for Engineered Safety-Feature Systems (24 April 1990)
- Information Notice 1990-27, Clarification of the Recent Revisions to the Regulatory Requirements for Packaging of Uranium Hexafluoride (UF6) for Transportation (30 April 1990)
- Information Notice 1990-28, Potential Error In High Steamline Flow Setpoint (30 April 1990)
- Information Notice 1990-28, Potential Error in High Steamline Flow Setpoint (30 April 1990)
- Information Notice 1990-29, Cracking of Cladding and Its Heat-Affected Zone in the Base Metal of a Reactor Vessel Head (30 April 1990, Topic: Nondestructive Examination, Liquid penetrant)
- Information Notice 1990-30, Ultrasonic Inspection Techniques for Dissimilar Metal Welds (1 May 1999, Topic: Dissimilar Metal Weld)
- Information Notice 1990-31, Update on Waste Form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990, Topic: Process Control Program)
- Information Notice 1990-31, Update on Waste form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990, Topic: Process Control Program)
- Information Notice 1990-32, Surface Crack and Subsurface Indications in the Weld of a Reactor Vessel Head (3 May 1990)
- Information Notice 1990-33, Sources of Unexpected Occupational Radiation Exposures at Spent Fuel Storage Pools (9 May 1990)
- Information Notice 1990-34, Response to False Siren Activations (10 May 1990)
- Information Notice 1990-35, Transportation of Type a Quantities of Non-Fissile Radioactive Materials (24 May 1990)
- Information Notice 1990-37, Sheared Pinion Gear-To-Shaft Keys in Limitorque Motor Actuators (24 May 1990)
- Information Notice 1990-38, License and Fee Requirements for Processing Financial Assurance Submittals for Decommissioning (6 November 1990, Topic: Authorized possession limits)
- Information Notice 1990-39, Recent Problems with Service Water Systems (1 June 1990)
- Information Notice 1990-40, Results of NRC-Sponsored Testing of Motor-Operated Valves (5 June 1990, Topic: Weak link)
- Information Notice 1990-41, Potential Failure of General Electric Magne-Blast Circuit Breakers and Ak Circuit Breakers (12 June 1990)
- Information Notice 1990-42, Failure of Electrical Power Equipment Due to Solar Magnetic Disturbances (19 June 1990)
- Information Notice 1990-43, Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit Breakers (29 June 1990)
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