Degraded Coatings and Corrosion of Steel Containment VesselsML031190084 |
Person / Time |
---|
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: |
12/01/1989 |
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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-89-079, NUDOCS 8911270001 |
Download: ML031190084 (8) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 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>. |
4-I UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 December 1, 1989 NRC INFORMATION
NOTICE NO. 89-79: DEGRADED COATINGS AND CORROSION
OF STEEL CONTAINMENT
VESSELS
Addressees
All holders of operating
licenses or construction
permits for light-water
reactors.
Purpose
- This information
notice is intended to alert addressees
to the discovery
of severely degraded coatings and the corrosion
of steel ice condenser
contain-ment vessels that are caused by boric acid and collected
condensation
in the annular space between the steel shell and the surrounding
concrete shield building.
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.Description
of Circumstances:
On August 24, 1989, Duke Power Company reported significant
coating damage and base metal corrosion
on the outer surface of the steel shell of the McGuire Unit 2 containment
which was discovered
during a pre-integrated
leak rate test inspection (as required by Appendix J to 10 CFR Part 50). Subsequently, Duke Power identified
similar degradation
of the McGuire Unit 1 containment, which is essentially
identical
to the Unit 2 structure.
Both units have ice condenser-type
containments
consisting
of a freestanding
steel shell surrounded
by a concrete shield building.
Between the shell and the shield building is a 6-foot-wide
annular space. The steel shells have a -nominal thickness
near the annulus floor of 1 inch. The degraded area on the shells of both units is limited to 30-foot circumferential
sections no higher than 1i inches above the annulus floors. The average depth of the corrosion is 0.1 inch with pits of up to 0.125 inch. Corrosion
that is up to 0.03 inch deep was also found in areas below the level of-the annulus floor on the Unit 2 shell, where concrete was removed to expose the shell surface. This below-floor
corrosion
is due to a lack of sealant at the interface
between the shell and the annulus floor.8911270001 IN 89-79 December 1, 1989 The probable cause of the degradation
is attack by condensed
boric acid coolant leaking from instrument
line compression
fittings.
Drains are provided in the annulus floor, but they are widely separated
and the floor is not sufficiently
graded to prevent pooling of the condensate
between the drain locations.
The current average thickness
of the corroded areas of the containment
shells of 0.9 inch is expected to be reduced to no less than 0.85 inch for Unit 1 and 0.88 inch for Unit 2 by the time they are repaired during the next planned outages for these units. These estimates
were made assuming the worst cor-rosion rates that could reasonably
be expected and are greater than the minimum thickness
allowed by the applicable
ASME Code.On September
21, 1989, Duke Power Company discovered
coating damage and base metal corrosion
during inspections
of the steel shells of its two Catawba con-tainments.
These containments
are also of the ice condenser
type and are very similar to the McGuire containments;
the nominal floor level shell thickness is 1 inch. Here also, the degradation
was located on the outer surfaces of the shells at the intersection
of the shell and the concrete annulus floor.At Catawba the damage was less extensive
and was limited to a circumference
of 15 feet, a height of 1 inch above the annulus floor, and an average depth of 0.03 inch. The cause is also believed to be attack by boric acid coolant, which had leaked from instrument
line compression
fittings, condensed, and collected
on the annulus floor.Duke Power Company plans to repair the steel shells of all four units during their next respective
refueling
outages. This will include weld repair and recoating
of the corroded areas.Discussion:
The degradation
of the containment
shells at the McGuire and Catawba plants is considered
significant
for several reasons. The fact that the corrosion affects four different
units indicates
that other steel containments
with similar configurations
may be susceptible
to the same problem. Furthermore, the observed rate of corrosion
far exceeds the allowance
made for corrosion in the containment
design. This condition
leads to the concern that such corrosion
could result in undetected
wall thinning to less than the minimum design thickness, accompanied
by a loss of leaktightness
or structural
inte-grity. This problem can be prevented
by a containment
inservice
inspection
program that is adequate to ensure early detection
and the maintenance
of design margins through proper corrosion
control.The NRC regulations (Appendix
J to 10 CFR Part 50) require that a general visual inspection
of the accessible
surfaces in the containment
be performed before each integrated
leak rate test. The purpose of this inspection
is to identify any evidence of structural
deterioration
or other problems that may affect containment
integrity
or leaktightness.
As a result of these and other inspections, several instances
of containment
wall thinning due to corrosion have been discovered
during the past 3 years at operating
power reactors.However, the visual inspections
done in connection
with the integrated
leak
IN 89-79 December 1, 1989 rate tests are only required to be performed
three times in each 10-year period.In addition, because of the physical arrangement
of plant systems, the steel surfaces in the annular spaces of some containments
may not be easily accessible
to the visual inspections
associated
with leak tests. Considering
the frequency and severity of recent instances
of containment
degradation
due to corrosion, additional
efforts to inspect steel containment
surfaces potentially
susceptible
to corrosion
may be prudent.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./'6 7A0 Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
Contacts:
Chen P. Tan, NRR (301) 492-0829 Keith R. Wichman, NRR (301) 492-0908 Attachment: -List of Recently Issued NRC Information
Notices
Attachment
IN 89-79 D*cUmb4t I 1959 Page I of I LIST OF RECENTLY ISSUED lRC INFODIATIOII
NOTICES-.,ant- Mate U T itcei No. Subject ilssunce 89-SI. Questionable
Certification
11/22/S9 Supp. I of material Supplied to the Defense Department
by Nuclear Supplirs 8t-78 Fel lure of Packing NutU 11/22t89 n One-Inch Uranium lexefluoride
Cylinder Valves 89-77 Debris In Contaienwnt
11/21/t89 Esergency
Sumps end Incorrect
Sreenn Configuretions
t9-7i S1ifouling
Agent, Zebra 11/21/t9 89.7S Felsification
of Holder 11/20/89 Quealifications
for Coetrector
Expleoys t-74 Clerification
of Traes- ll7/8 portsti1e
Rqrbments Applicable
to Return of Spent Radiopharraq
Dosages trom Users to Suppliers It-73 Potential
Owverenesrization
II/1/St of Low Pressure SyStaft lusued to All holders of Ots or CPa for nuclear power reactors.All ItC 11icnsees authorized
to possess and use source metarial end/or special nuclear material for the heating.ewptying, filling or shipping of uranium hexafluoride
In 30.and 48-inch diareter Cylinders.
All holden of OLs or CPs tor PaRs.All holders of OLs or CPS for nuclear power reactors.All holders of OLs or CPa tor nuclear power reactors.All munufecturern
and distributors
of radisphormecewticals
for sedical une nuclear phareacen.
and medical licensees.
All holders of OLs or Cfa for nuclear pOer reactors.All holders of OLs or CPs for nuclear power reactors.89-72 Failure of Licensed Senier Operntors
to Classify Emargeacy
Events Properly 10/24/8t OL
License CP
Permit UNITED STATES NUCLEAR REGULATORY
COMMISSION
WASHINGTON, D.C. 20555 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, *300 FIRST CLASS MAIL POSTA0IS FEES PAID USNRC PERIr No.Ale 4- t IN 89-79 December 1, 1989 rate tests are only required to be performed
three times in each 10-year period.In addition, because of the physical arrangement
of plant systems, the steel surfaces in the annular spaces of some containments
may not be easily accessible
to the visual inspections
associated
with leak tests. Considering
the frequency and severity of recent instances
of containment
degradation
due to corrosion, additional
efforts to inspect steel containment
surfaces potentially
susceptible
to corrosion
may be prudent.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: Chen P. Tan, NRR (301) 492-0829 Keith R. Wichman, NRR (301) 492-0908 Attachment:
List of Recently Issued NRC Information
Notices Document Name: IN 89-79*SEE PREVIOUS CONCURRENCES
CYCheng 11/22/89*OGCB:DOEA:NRR
DCKirkpatrick
11/15/89*EMlTB:DET:NRR
KWichman 11/22/89 D/DOEA:NRR%
CERossi A 11/2W89*ESGB:DET:NRR
CPTan 11/21/89*C/OGCB:DOEA:NRR
CHBerlinger
11/22/89*C/ESGB:DET:NRR
GBagchi 11/21/89*RPB:ARM TechEd 11/17/89*D/DET: NRR JRichardson
11/22/89 IN 89-XX November xx, 1989 accessible
to the visual Inspections
associated
with leak tests. Considering
the frequency
and severity of recent instances
of containment
degradation
due to corrosion, additional
efforts to inspect steel containment
surfaces poten-tially susceptible
to corrosion
may be prudent.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: Chen P. Tan (301) 492-0829 Keith R. Wichman, NRR (301) 492-0908 Attachment:
List of Recently Issued NRC Information
Notices Document Name: IN CONl*SEE PREYIQV CONCURRENCES
T/, :. 0Pz*OGCB: J0BA 4LRR i NRR DCKirkpatrck
KW man 11/15/89 11/12!89 rAINMENT CORROSION D/DOEA:NRR
CERossi 11/ /89*ESGB:DET:NRR
- (CPTan 11/21/89 C/OGCB:DOEA:NRR
CHBerlinger
11A918 C/ESGB:DET:NRR
Bagchi L1/21/89*RPB:ARM TechEd 11/17/89 D/DET: NRR V JRichardsW
11/Z;U89 M
IN 89-XX November xx, 1989 the frequency
and severity of recent instances
of containment
degradation
due to corrosion, additional
efforts to inspect steel containment
surfaces at some plants may be prudent.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: Chen P. Tan (301) 492-0829 Keith R. Wichman, NRR (301) 492-0908 Attachment:
List of Recently Issued NRC Information
Notices Document Name: IN CONTAINMENT
CORROSION*SEE PREVIOUS CONCURRENCES
EMTB:DET:NRR
DCKirkpatrick
KWichman 11/15/89 11/ /89 D/DOEA:NRR
CERossi 11/ /89 ESGB:DET:NRR
CPTan Aret 11/al /89 C/OGCB:DOEA:NRR
CHBerlinger
11/ /89 C/ESGJ -j~ hR GBag hi V 11/n /89*RPB:ARM TechEd 11/17/89 D/DET: NRR JRichardson
11/ /89
-vi instances
of containment
wall thinning due to corrosion
have been discovered
during the past three-years
at operating
power reactors.
However, the visual inspections
done in connection
with the integrated
leak rate tests are only required to be performed
three times in each a year period. In addition, because of the physical arrangement
of plant systems, the steel surfaces in the annular spaces of some containments
may fall outside o the usual scope of the lektt-i LLret ted visual inspectionv'
Considering
the frequency
and severity of recent instances
of containment
degradation
due to corrosion, additional
efforts to inspect steel containment
surfaces at some plants may be prudent.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:
Chen P. Tan (301) 492-0829 Keith R. Wichman, NRR (301) 492-0908 Attachment:
List of Recently Issued NRC Information
Notices Document Name: IN CONTAINMENT
CORROSION D/DOEA:NRR
C/OGCB:DOEA:NRR
CERossi CHBerlinger
11/ /89 11/ /89 OGCB:DOEA:NRR
EMTB:DET:NRR
ESGB:DET:NRR
C/ESGB:DET:NRR
RPB:ARM DCKirkpatrick
KWichman CPTan GBagchi TechEdM X 1114AWDe 11/ /89 11/ /89 11/ /89 11//9 /89
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list | - Information Notice 1989-01, Valve Body Erosion (4 January 1989)
- Information Notice 1989-02, Criminal Prosecution of Licensee'S Former President for Intentional Safety Violations (9 January 1989)
- Information Notice 1989-03, Potential Electrical Equipment Problems (11 January 1989, Topic: Overexposure)
- Information Notice 1989-04, Potential Problems from the Use of Space Heaters (17 January 1989)
- Information Notice 1989-05, Use of Deadly Force by Guards Protecting Nuclear Power Reactors Against Radiological Sabotage (19 January 1989)
- Information Notice 1989-06, Bent Anchor Bolts in Boiling Water Reactor Torus Supports (24 January 1989)
- Information Notice 1989-07, Failures of Small-Diameter Tubing in Control Air, Fuel Oil & Lube Oil Systems Render Emergency Diesel Generators Inoperable (25 January 1989, Topic: Overspeed)
- Information Notice 1989-08, Pump Damage Caused by Low-Flow Operation (26 January 1989, Topic: Integrated leak rate test)
- Information Notice 1989-09, Credit for Control Rods Without Scram Capability in the Calculation of Shutdown Margin (26 January 1989, Topic: Shutdown Margin)
- Information Notice 1989-10, Undetected Installation Errors in Main Steam Line Pipe Tunnel Differential Temperature-Sensing Elements at Boiling Water Reactors (27 January 1989)
- Information Notice 1989-11, Failure of DC Motor-Operated Valves to Develop Rated Torque Because of Improper Cable Sizing (2 February 1989, Topic: Shutdown Margin)
- Information Notice 1989-12, Dose Calibrator Quality Control (9 February 1989)
- Information Notice 1989-13, Alternative Waste Management Procedures in Case of Denial of Access to Low-Level Waste Disposal Sites (8 February 1989, Topic: Shutdown Margin, Authorized possession limits)
- Information Notice 1989-15, Second Reactor Coolant Pump Shaft Failure at Crystal River (16 February 1989, Topic: Shutdown Margin)
- Information Notice 1989-16, Excessive Voltage Drop in DC Systems (16 February 1989, Topic: Shutdown Margin, Battery sizing)
- Information Notice 1989-17, Contamination and Degradation of Safety-Related Battery Cells (22 February 1989)
- Information Notice 1989-18, Criminal Prosecution of Wrongdoing Committed by Suppliers of Nuclear Products or Services (24 August 1990, Topic: Stress corrosion cracking)
- Information Notice 1989-20, Weld Failures in a Pump of Byron-Jackson Design (24 February 1989, Topic: Health Physics Network)
- Information Notice 1989-21, Changes in Performance Characteristics of Molded-Case Circuit Breakers (27 February 1989, Topic: Health Physics Network)
- Information Notice 1989-23, Environmental Qualification of Litton-Veam Cir Series Electrical Connectors (3 March 1989, Topic: Health Physics Network)
- Information Notice 1989-24, Nuclear Criticality Safety (6 March 1989, Topic: Health Physics Network)
- Information Notice 1989-25, Unauthorized Transfer of Ownership or Control of Licensed Activities (7 March 1989, Topic: Health Physics Network)
- Information Notice 1989-26, Instrument Air Supply to Safety-Related Equipment (7 March 1989, Topic: Health Physics Network)
- Information Notice 1989-27, Limitations on the Use of Waste Forms and High Integrity Containers for the Disposal of Low-Level Radioactive Waste (8 March 1989, Topic: Process Control Program)
- Information Notice 1989-28, Weight and Center of Gravity Discrepancies for Copes-Vulcan Air-Operated Valves (14 March 1989)
- Information Notice 1989-29, Potential Failure of Asea Brown Boveri Circuit Breakers During Seismic Event (15 March 1989, Topic: Commercial Grade)
- Information Notice 1989-30, High Temperature Environments at Nuclear Power Plants (1 November 1990, Topic: Stress corrosion cracking)
- Information Notice 1989-31, Swelling and Cracking of Hafnium Control Rods (22 March 1989)
- Information Notice 1989-32, Surveillance Testing of Low-Temperature Overpressure-Protection Systems (23 March 1989, Topic: Stroke time)
- Information Notice 1989-33, Potential Failure of Westinghouse Steam Generator Tube Mechanical Plugs (23 March 1989)
- Information Notice 1989-34, Disposal of Americium Well-Logging Sources (30 March 1989)
- Information Notice 1989-35, Loss & Theft of Unsecured Licensed Material, Attachment 1 to NRC Information Notice 1990-014: Accidental Disposal of Radioactive Materials. (Also includes Attachments 2 & 3) (30 March 1989)
- Information Notice 1989-35, Loss & Theft of Unsecured Licensed Material, Attachment 1 to NRC Information Notice 1990-014: Accidental Disposal of Radioactive Materials. (Also Includes Attachments 2 & 3) (30 March 1989, Topic: Moisture-Density Gauge, Uranium Hexafluoride)
- Information Notice 1989-36, Excessive Temperatures in Emergency Core Cooling System Piping Located Outside Containment (4 April 1989)
- Information Notice 1989-37, Proposed Amendments to 40 CFR Part 61, Air Emission Standards for Radionuclides (4 April 1989)
- Information Notice 1989-38, Atmospheric Dump Valve Failures at Palo Verde Units 1, 2, and 3 (5 April 1989, Topic: Emergency Lighting)
- Information Notice 1989-39, List of Parties Excluded from Federal Procurement or Non-Procurement Programs (5 April 1989)
- Information Notice 1989-40, Unsatisfactory Operator Test Results and Their Effect on the Requalification Program (14 April 1989)
- Information Notice 1989-41, Operator Response to Pressurization of Low-Pressure Interfacing Systems (20 April 1989)
- Information Notice 1989-42, Failure of Rosemount Models 1153 and 1154 Transmitters (21 April 1989)
- Information Notice 1989-43, Permanent Deformation of Torque Switch Helical Springs in Limitorque SMA-Type Motor Operators (1 May 1989)
- Information Notice 1989-44, Hydrogen Storage on the Roof of the Control Room (27 April 1989, Topic: Coatings)
- Information Notice 1989-45, Metalclad, Low-Voltage Power Circuit Breakers Refurbished with Substandard Parts (8 May 1989, Topic: Commercial Grade Dedication, Coatings, Commercial Grade)
- Information Notice 1989-46, Confidentiality of Exercise Scenarios (11 May 1989, Topic: Coatings)
- Information Notice 1989-47, Potential Problems with Worn or Distorted Hose Clamps on Self-Contained Breathing Apparatus (18 May 1989, Topic: Coatings, Fatality)
- Information Notice 1989-48, Design Deficiency in the Turbine-Driven Auxiliary Feedwater Pump Cooling Water Systems (22 May 1989, Topic: Coatings, Temporary Modification)
- Information Notice 1989-49, Failure to Close Service Water Cross-Connect Isolation Valves (22 May 1989, Topic: Coatings)
- Information Notice 1989-50, Inadequate Emergency Diesel Generator Fuel Supply (30 May 1989)
- Information Notice 1989-51, Potential Loss of Required Shutdown Margin During Refueling Operations (31 May 1989, Topic: Shutdown Margin, Coatings)
- Information Notice 1989-52, Potential Fire Damper Operational Problems (8 June 1989, Topic: Safe Shutdown, Shutdown Margin, Fire Barrier, Fire Protection Program)
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