Potential Degradation of Secondary ContainmentML031130355 |
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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
01/22/1990 |
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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-90-002, NUDOCS 9001160420 |
Download: ML031130355 (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, 05000000, Zimmer, 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 [[:05000000]] OR [[:Zimmer]] 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 [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
I ft I i-UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 January 22, 1990 NRC INFORMATION
NOTICE NO. 90-02: POTENTIAL
DEGRADATION
OF SECONDARY CONTAINMENT
Addressees
All holders of operating
licenses or construction
permits for boiling water reactors (BWRs).
Purpose
- This information
notice is intended to alert addressees
to potential
problems involving
degradation
of secondary
containment
as a result of unforeseen
inter-actions with various normal plant ventilation
systems and inadequate
surveillance
testing of secondary
containment
integrity.
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.Detcription
of Circumstances:
Duane Arnold Energy Center During a reactor building exhaust ventilation
inspection, an Iowa Electric system engineer discovered
a large hole in the duct work (see Figure 1).This hole allowed the main plant ventilation
system to communicate
directly with the reactor building ventilation
system, thus bypassing
the standby gas treatment
system (SGTS) and providing
a direct path for an untreated
release of radioactive
effluents
to the environment.
This pathway would have existed even with an automatic
Engineered
Safety Feature (ESF) isolation
of the reactor building ventilation
system and an autostart
of the SGTS. The licensee dis-covered that .its normal secondary
containment
integrity
surveillance
test (which requires a measurement
of 0.25 inch water vacuum with one train of SGTS operating)
was still apparently
satisfied
with the main plant ventilation
fans running. This has been the test configuration
used at the plant since initial startup in 1974. However, upon conducting
the test with the SGTS operating
as designed and the main plant ventilation
secured, the 0.25-inch vacuum could not be achieved because of numerous secondary
containment
leaks.A 10 CFR 50.72 4-hour notification
was made to the NRC upon this discovery.
The licensee determined
that during the performance
of the secondary
contain-ment integrity
surveillance
as it was previously
conducted, the main plant 9001160420
Zjl_ _v c
IN 90-02 January 22, 1990 ventilation, turbine building ventilation, and the radwaste building ventila-tion exhaust fans had aided the SGTS in drawing the required vacuum. Because surveillance
tests performed
since initial unit startup usually indicated
that the required negative pressure had been obtained, numerous secondary
contain-ment integrity
deficiencies
went undetected
and uncorrected.
The maintenance
to correct this overall degradation
of the secondary
containment
required more than 3 weeks of effort to locate and repair numerous door seals, electrical
penetrations, steam tunnel boot seals, dampers, building seals, and duct systems.These repairs resulted in an improvement
in the measured secondary
containment
vacuum from less than 0.08 inch of water to greater than 0.25 inch of water, as determined
by retesting
with a new surveillance
test procedure.
This test now requires all major plant exhaust ventilation
fans that potentially
communicate
with secondary
containment
to be secured.Continued
testing after repairs has shown that one main plant exhaust ventilation
fan can still draw an approximate
500 to 1000 standard cubic feet-per-minute (SCFM)volume' from the reactor building ventilation
system (the secondary
containment
boundary)
when the ESF-required
isolation
is in effect. As this circumstance
could result in an untreated
ground-level
release under certain accident scenarios, the licensee developed
alarm response procedures
designed to secure the main plant ventilation
fans when secondary
containment
isolation
is initiated
and main plant exhaust ventilation
radiation
monitors reach specified
values. Iowa Electric is also considering
long-term
corrective
action involving
hardware modifications
that would prevent main plant ventilation
from drawing air out of the reactor building under accident conditions.
Monticello
As a result of the secondary
containment
deficiencies
identified
at Duane Arnold, the NRC resident inspector
contacted
the licensee for the Monticello
plant con-cerning the procedures
and practices
for testing the secondary
containment
system.The licensee had normally tested the secondary
containment
integrity
with the main plant exhaust fans running and isolated both supply and exhaust fans in the reactor building.
However, on October 14, 1989, the licensee conducted the secondary
containment
integrity
test with the main plant exhaust fans secured and was not able to maintain the 0.25-inch
water vacuum required by the technical
specifications.
The vacuum reached in the reactor building was only 0.1 inch of water. Preliminary
investigation
revealed that failure of the test was due to leaks in the reactor building supply and exhaust system dampers and various other secondary
containment
leaks. The licensee also believes that the operation
of the main plant exhaust fans assisted the SGTS in drawing the required vacuum on the secondary
containment, thus establishing
a path that bypassed the SGTS. A 10 CFR 50.72 notification
was made to the NRC.Discussion
of Safety Significance:
Plant heating, ventilation, and air conditioning (HVAC) systems are diverse among boiling water reactors.
Interactions
between these systems and the standby gas treatment
system could mask degradation
of the secondary
contain-ment boundary during surveillance
testing and could exacerbate
such degradatiof+t'
by diverting
flow from the SGTS following
an accident.
-
K>IN 90-02 January 22, 1990 For those plants discussed
above, a portion of the secondary
containment
boundary is formed by the ductwork and isolation
dampers of the reactor build-ing ventilation
system. This system exhausts to a common plenum area within the reactor building, but outside secondary
containment, where ventilation
flows from other plant HVAC systems are also directed.
The high-capacity
main plant ventilation
exhaust fans take suction from the plenum area and discharge the flow through the reactor building roof stacks. Because of the high capa-city of the main plant exhaust fans and their proximity
to the reactor building ventilation
system components
that form part of the secondary
containment
boundary, the potential
exists for air flow to bypass the SGTS even when the secondary
containment
is isolated.
Further, if the main plant ventilation
fans are operated during surveillance
testing, degradation
of secondary
containment
could go undetected
as the main plant fans and the SGTS fans could collectively
draw the required vacuum.In view of the possibility
of the main plant ventilation
systems masking deficiencies
in SGTS and/or secondary
containment
integrity
and of creating possible untreated
release paths under accident conditions, licensees
for other BWR plants may wish to review the design and operation
of major plant ventila-tion systems and to review their secondary
containment
integrity
surveillance
procedures.
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:
William L. Axelson, Region III (708) 790-5574 John A. Kudrick, NRR (301) 492-0871 James R. Hall, NRR (301) 492-1391 Attachments:
1. Figure 1 -Reactor Building Ventilation
2. List of Recently Issued NRC Information
Notices
Attachment
1 IN 90-02 January 22, 1990 Failed DucUng Isolatlon
Dampers Reactor Buiding VentShaft Fgure 1 Reactor Building Ventilation
Iw/I1-89 A1087 K>Attachment
2 IN 90-02 January 22, 1990 ti e.-..11 -1..,-1-LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 90-01 89-90 89-89 89-88 89-87 89-45, Supp. 2 89-86 89-85 89-84 Importance
of Proper Response to Self-Identified
Violations
by Licensees Pressurizer
Safety Valve Lift Setpoint Shift Event Notification
Worksheets
Recent NRC-Sponsored
Testing of Motor-Operated
Valves Disabling
of Emergency Diesel Generators
by Their Neutral Ground-Fault
Protection
Circuitry Metalclad, Low-Voltage
Power Circuit Breakers Refurbished
with Substandard
Parts Type HK Circuit Breakers Missing Close Latch Anti-Shock Springs.EPA's Interim Final Rule on Medical Waste Tracking and Management
Failure of Ingersoll
Rand Air Start Motors as a Result of Pinion Gear Assembly Fitting Problems 1/12/90 12/28/89 12/26/89 12/26/89 12/19/89 12/15/89 12/15/89 12/15/89 12/12/89 All holders of NRC materials
licenses.All holders of OLs or CPs for PWRs.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.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All medical, academic, industrial, waste broker, and waste disposal site licensees.
All holders of OLs or CPs for nuclear power reactors.OL = Operating
License CP = Construction
Permit
IN 90-02 January 22, 1990 For those plants discussed
above, a portion of the secondary
containment
boundary is formed by the ductwork and isolation
dampers of the reactor build-ing ventilation
system. This system exhausts to a common plenum area within the reactor building, but outside secondary
containment, where ventilation
flows from other plant HVAC systems are also directed.
The high-capacity
main plant ventilation
exhaust fans take suction from the plenum area and discharge the flow through the reactor building roof stacks. Because of the high capa-city of the main plant exhaust fans and their proximity
to the reactor building ventilation
system components
that form part of the secondary
containment
boundary, the potential
exists for air flow to bypass the SGTS even when the secondary
containment
is Isolated.
Further, if the main plant ventilation
fans are operated during surveillance
testing, degradation
of secondary
containment
could go undetected
as the main plant fans and the SGTS fans could collectively
draw the required vacuum.In view of the possibility
of the main plant ventilation
systems masking deficiencies
in SGTS and/or secondary
containment
integrity
and of creating possible untreated
release paths under accident conditions, licensees
for other BWR plants may wish to review the design and operation
of major plant ventila-tion systems and to review their secondary
containment
integrity
surveillance
procedures.
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:
William L. Axelson, Region III (708) 790-5574 John A. Kudrick, NRR (301) 492-0871 James R. Hall, NRR (301) 492-1391 Attachments:
1. Figure 1 -Reactor Building Ventilation
2. List of Recently Issued NRC Information
Notices Document Name: INFO NOTICE -JACKIW, KIESSEL*SEE PREVIOUS CONCURRENCES
D *C/OGCB:DOEA:NRR
E CHBerlinger
TechEd AThadani 01//190 01/10/90 12/21/89 12/18/89*OGCB:DOEA:NRR*RIII
- SPLB:DST:NRR*C/SPLB:DST:NRR
RJKiessel
EGGreenman
JRHall JKudrick CEMcCracken
11/16/89 11/21/89 11/16/89 12/12/89 12/12/89 IN 90-XX January xx, 1990 For those plants discussed
above, a portion of the secondary
containment
boundary is formed by the ductwork and isolation
dampers of the reactor build-ing ventilation
system. This system exhausts to a common plenum area within the reactor building, but outside secondary
containment, where ventilation
flows from other plant HVAC systems are also directed.
The high-capacity
main plant ventilation
exhaust fans take suction from the plenum area and discharge the flow through the reactor building roof stacks. Because of the high capa-city of the main plant exhaust fans and their proximity
to the reactor building ventilation
system components
that form part of the secondary
containment
boundary, the potential
exists for air flow to bypass the SGTS even when the secondary
containment
is isolated.
Further, if the main plant ventilation
fans are operated during surveillance
testing, degradation
of secondary
containment
could go undetected
as the main plant fans and the SGTS fans could collectively
draw the required vacuum.In view of the possibility
of the main plant ventilation
systems' masking deficiencies
in SGTS and/or secondary
containment
integrity
and of creating possible untreated
release paths under accident conditions, licensees
for other BWR plants may wish to review the design and operation
of major plant ventila-tion systems and to review their secondary
containment
integrity
surveillance
procedures.
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
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:
William L. Axelson, Region III (708) 790-5574 John A. Kudrick, NRR (301) 492-0871 James R. Hall, NRR (301) 492-1391 Attachments:
1. Figure 1 -Reactor Building Ventilation
2. Figure 2 -Exhaust Fan Room 3. List of Recently Issued NRC Information
Notices Document Name: INFO NOTICE -JACKIW, KIESSEL*SEE PREVIOUS CONCURRENCES
D/DOEA:NRR
C/OGCB:D C Byt;*RPB:ARM
CERossi CHBerline
j) TechEd AThadani 01/ /90 01/Y,/90-
' 12/21/89 12/18/89*OGCB:DOEA:NRR*RIII
- SPLB:DST:NRR*C/SPLB:DST:NRR
RJKiessel
EGGreenman
JRHall -lf JKudrick CEMcCracken
11 11/21 11/16/8w 12/12/89 12/12/89 441/44s~4 IN 89-XX%2 ~November
xx, 1989 standby gas treatment
system could mask degradation
of the secondary
contain-ment boundary during surveillance
testing and could exacerbate
such degradation
by diverting
flow from the SGTS following
an accident.For those plants discussed
above, a portion of the secondary
containment
boundary is formed by the ductwork and isolation
dampers of the reactor build-ing ventilation
system. This system exhausts to a common plenum area within the reactor building, but outside secondary
containment, where ventilation
flows from other plant HVAC systems are also directed.
The high capacity main plant ventilation
exhaust fans take suction from the plenum area and discharge the flow out through the reactor building roof stacks. Due to the high capa-city of the main plant exhaust fans and their proximity
to the reactor building ventilation
system components
that form part of the secondary
containment
boundary, the potential
exists for air flow to bypass the SGTS even when the secondary
containment
is isolated.
Further, if the main plant ventilation
fans are operated during surveillance
testing, degradation
of secondary
containment
could go undetected
as the main plant fans and SGTS fans could collectively
draw the required vacuum.In view of the possibility
of main plant ventilation
systems masking deficien-cies in SGTS and/or secondary
containment
integrity
and of creating possible untreated
release paths under accident conditions, other BWR plants may wish to review the design and operation
of major plant ventilation
systems and to review their secondary
containment
integrity
surveillance
procedures.
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
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: William L. Axelson, Region III (708) 790-5574 John A. Kudrick, NRR (301) 492-0871 James R. Hall, NRR (301) 492-1391 Attachments:
1. Figure 1 -Reactor Building Ventilation
2. Figure 2 -Exhaust Fan Room 3. List of Recently Issued NRC Information
Notices Document Name: INFO NOTICE -JACKIW, KIESSEL*SEE PREVIOUS CONCURRENCES
sit D/DOEA:NRR
C/OGCB:DOEA:NRR
RPB:ARO'CERossi CHBerlinger
TechEd 11/ /89 11/ /89 ftH/.Zf/*OGCB:DOEA:NRR*RIII
SPLB: R RJKiessel
EGGreenman
JRHall *udri 11/16/89 11/21/89 11/16/89 WMI Al'D/DST:NRR ni MAK /89 C/SPLB:DST:
WG9 CEMcCracken,_
--/d 89
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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)
... further results |
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