Pump Damage Caused by Low-Flow OperationML031180506 |
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: |
01/26/1989 |
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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-89-008, NUDOCS 8901190418 |
Download: ML031180506 (7) |
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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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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>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 January 26, 1989 NRC INFORMATION NOTICE NO. 89-08: PUMP DAMAGE CAUSED BY LOW-FLOW OPERATION
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
This information notice is being provided to alert addressees to potential
problems that may result from operation of centrifugal pumps at flows that
can cause severe pump component damage. 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
Two events which resulted in pump damage are described below. Operations for
extended periods at low-flow conditions apparently created hydraulic instability, resulting in pump damage from cavitation, pressure pulsation, and/or vibration.
These events occurred at the Haddam Neck Plant and Susquehanna Steam Electric
Station, Unit 1 (Susquehanna 1). The pump damage at the Haddam Neck plant was
attributed to pressure pulsation and pump vibration, while at Susquehanna 1 it
was the result of cavitation.
Haddam Neck Plant Event:
On February 4, 1988, an electric-driven fire pump was declared inoperable
during a routine surveillance test when a high-amperage condition was noted.
The normal indication of 200 amps initially increased to between 340 and 360
amps. The indication further increased to 1000 amps during a subsequent
manual restart. The cause of the high amperage was attributed to physical
damage to the stuffing box brass bushing in the upper shaft area. On the
basis of the licensee's evaluation and its discussions with the manufacturer, the licepsee concluded that prolonged operation of the pump at low flow may
have caused the problem. Operation of the pump at or near the shut-off head
had occurred during the containment integrated leak rate test. During the
test, the fire pump operated in a low-flow mode, providing cooling water to
the air compressors.
8901190418 Zfr 1= -/ /C
AS_
-IN89-08 January 26, 1989 Susquehanna 1 Event:
While the plant was operating at full power on May 22, 1986, an over-current
alarm for an emergency service water (ESW) pump was received in the control
room. The pump was declared inoperable, placing the plant in a limiting
condition for operation. Subsequent disassembly of the pump revealed that
the bottom portion of the pump suction bell had separated from the pump body
and fallen into the pump pit. In addition, the pump's impeller vanes were
eroded through. Similar, but less severe, damage was found on the three
other ESW pumps. A subsequent inspection of the residual heat removal
service water (RHRSW) pumps found similar damage. The licensee determined
that the damage to the ESW and RHRSW pumps was caused by recirculation
cavitation, caused by operation of the pumps at flows significantly below
their design flow rates.
The ESW pumps are normally operated at 60 percent or less of their design flow
of approximately 6,000 gallons per minute (gpm) per pump. When the loop sup- plying cooling water to the diesels is run with two operating pumps, each pump
delivers approximately 3500 to 3900 gpm. The other loop, that does not serve
the diesels is normally run with only one pump providing approximately 1000
to 1500 gpm. Operation at these conditions is believed by the pump vendor
to cause recirculation cavitation. In addition, the RHRSW pumps are believed
to have been operated at less than 50 percent of design flow most of the time.
The licensee indicated that the cavitation damage can be avoided by operating
the pumps at higher flows; specifically, operation at 75 to 100 percent of
design flow is desirable.
Discussion:
These events illustrate that pump damage, caused by operating pumps at flows
significantly below their design flow rates, has resulted, with slow deteri- oration of pump internals occurring over a long period. During the early
phases of degradation, the pumps were still functional and remained operable.
The pumps had to be disassembled before damage to the pump internals could be
seen. Therefore, the routine pump surveillance tests, provided in the plant
inservice test programs, may not be capable of detecting early component de- gradation. In addition, while operating the pumps in their normal, specified
system operating ranges, plant personnel were not aware of a problem until
actual failure of a pump occurred. It is most likely that pump degradation
caused by low-flow operation will go undetected until total failure of the
pump occurs, preventing the associated system from performing its safety
function.
IN 89-08 January 26, 1989 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate regional
office.
aLzi lorj
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Chuck Hsu, AEOD
(301) 492-4443 Attachment: List of Recently Issued NRC Information Notices
IN 89-08 January 26, 1989 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the techntcal
contact listed below or the Regional Administrator of the appropriate regional
office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Chuck Hsu, AEOD
(301) 492-4443 Attachment: List of Recently Issued NRC Information Notices
The draft of this information notice was transmitted to DOEA by AEOD in a
memorandum from Thomas M. Novak dated October 18, 1988.
The results of the review and recommendation for issuance of this draft infor- mation notice was transmitted to OGCB In a memorandum from M. Wayne Hodges
dated November 17, 1988.
- SEE PREVIOUS CONCURRENCES
- C/OGCB: DOEA:NRR*PPMB:ARM *OGCB:DOEA:NRR *AD/SAD:DEST:NRR
CHBerlinger TechEd RJKiessel ACThadani
01/11/89 12/22/88 12/06/88 12/09/88 D *ROAB:DSP:AEOD *C/ROAB:DSP:AEOD *DSP:AEOD *D/DSP:AEOD
CHsu MChiramal JERosenthal VBenoroya TMNovak
10/18/88 10/18/88 10/18/88 10/18/88 10/18/88
IN 89-XX
January xx, 1989 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate regional
office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Chuck Hsu, AEOD
(301) 492-4443 Attachment: List of Recently Issued NRC Information Notices
The draft of this information notice was transmitted to DOEA by AEOD in a
memorandum from Thomas M. Novak dated October 18, 1988.
The results of the review and recommendation for issuance of this draft infor- mation notice was transmitted to OGCB in a memorandum from M. Wayne Hodges
dated November 17, 1988.
- SEE PREVIOUS CONCURRENCES
D/DOEA:NRR *C/OGCB:DOEA:NRR*PPMB:ARM *OGCB:DOEA:NRR *AD/SAD:DEST:NRR
CERossi CHBerlinger TechEd RJKiessel ACThadani
01/ /89 01/11/89 12/22/88 12/06/88 12/09/88
- ROAB:DSP:AEOD *ROAB:DSP:AEOD *C/ROAB:DSP:AEOD *DSP:AEOD *D/DSP:AEOD
CHsu MChiramal JERosenthal VBenoroya TMNovak
10/18/88 10/18/88 10/18/88 10/18/88 10/18/88
IN 89-XX
January xx, 1989 Discussion:
These events illustrate that pump damage, caused by operating pumps at flows
significantly below their design flow rates, has resulted with slow deteriora- tion of pump internals occurring over a long period. During the early phases
of degradation, the pumps were still functional and remained operable. The
pumps had to be disassembled before damage to the pump internals could be seen.
Therefore, the routine pump surveillance tests, provided in the plant inservice
test programs, may not be capable of detecting early component degradation. In
addition, while operating the pumps in their normal, specified operating
ranges, plant personnel were not aware of a problem until actual failure of the
pump occurred. It is most likely that pump degradation caused by low-flow
operation will go undetected until total failure of the pump occurs, preventing
the associated system from performing its safety function.
The information herein is being provided as an early notification of a poten- tially significant matter that is under further consideration by the NRC staff.
If NRC evaluation so indicates, further licensee action may be requested.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate regional
office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Chuck Hsu, AEOD
(301) 492-4443 Attachment: List of Recently Issued NRC Information Notices
The draft of this information notice was transmitted to DOEA by AEOD in a
memorandum from Thomas M. Novak dated October 18, 1988.
The results of the review and recommendation for issuance of this draft infor- mation notice was transmitted to OGCB in a memorandum from M. Wayne Hodges
dated November 17, 1988.
- PPMB:ARM C/OGCB D~t4NRR D/DOEA:NRR
TechEd CHBerl hIer CERossi
12/22/88 01/1//89 01/ /89
- OGCB:DOEA:NRR *AD/SAD:DEST:NRR*C/SRXB:DEST:NRR *SRXB:DEST:NRR*SRXB:DEST:NRR
RJKiessel ACThadani MWHodges TECollins MMcCoy
12/06/88 12/09/88 12/17/88 12/17/88 12/17/88
- ROAB:DSP:AEOD *ROAB:DSP:AEOD *C/ROAB:DSP:AEOD *DSP:AEOD *D/DSP:AEOD
CHsu MChiramal JERosenthal VBenoroya TMNovak
10/18/88 10/18/88 10/18/88 10/18/88 10/18/88
IN 88-XX
December xx, 1988 during which the pumps were still functional and remained operable at early
degradation. Damage indication on the pumps' internals can only be observed by
disassembly of the pumps. The routine surveillance tests of the pumps provided
in the plant inservice test programs may not be capable of detecting early
component degradation. In addition, since the pumps operated in the specified
operating ranges, the plants were not aware of the problem until the occur- rences of pump failure. There is the potential that pump degradation due to
low flow operation could go undetected until total failure of the pump occurs.
Such failures could prevent the associated system from performing its safety
function.
The information herein is being provided as an early notification of a possibly
significant matter that is still under consideration by the NRC staff. Recipi- ents should review the information for possible applicability to their facili- ties. If NRC evaluation so indicates, further licensee action may be
requested.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate regional
office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Chuck Hsu, AEOD
(301) 492-4443 Attachment: List of Recently Issued NRC Information Notices
The draft of this information notice was transmitted to DOEA by AEOD in a
memorandum from Thomas M. Novak dated October 18, 1988.
The results of the review and recommendation for issuance of this draft infor- mation notice was transmitted to OGCB in a memorandum from M. Wayne Hodges
dated November 17, 1988.
PPMB:ARMitiv C/OGCB:DOEA:NRR D/DOEA:NRR
TechEd CHBerlinger CERossi
12/fe/88 12/ /88 12/ /88 OGCB:DOEA:IRI AD/SAD:DESI:PRR *C/SRXB:DEST:NRR *SRXB:DEST:NRR*SRXB:DEST:NRR
RJKiessel ACThgdani / MWHodges TECollins MMcCoy
12/6/88 12/ 1/88 12/17/88 12/17/88 12/17/88
- ROAB:DSP:AEOD *ROAB:DSP:AEOD *C/ROAB:DSP:AEOD *DSP:AEOD *D/DSP:AEOD
CHsu MChiramal JERosenthal VBenoroya TMNovak
10/18/88 10/18/88 10/18/88 10/18/88 10/18/88
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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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