Potential Loss of Required Shutdown Margin During Refueling OperationsML031180659 |
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: |
05/31/1989 |
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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-89-051, NUDOCS 8905240229 |
Download: ML031180659 (5) |
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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 May 31, 1989 NRC INFORMATION NOTICE NO. 89-51: POTENTIAL LOSS OF REQUIRED SHUTDOWN
MARGIN DURING REFUELING OPERATIONS
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
This information notice Is being'provided to alert addressees to the potential
loss of required shutdown margin during the movement and placement of highly
reactive fuel during refueling operations. It is expected that recipients will
review the information for applicability to their facilities and consider
actions, as approprlate,-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
Baltimore Gas-and-Electric Company (BG&E) submitted a10 CFR Part 21 report
to the NRC on. March 15, 1989, regarding the potential loss of shutdown margin
during refueling operations at its Calvert Cliffs Nuclear Power Plant, Units 1 and 2. BG&E reported that it had increased the fuel enrichment during the last
several fuel cycles. Inthe current cycle, 4.3 weight percent U-235 fuel was
loaded into the core. During a review of NRC Information Notice No. 88-21,
"Inadvertent Criticality Events at Oskarshamn and U.S. Nuclear Power Plants,"
BG&E discovered that the Calvert Cliffs refueling procedures allowed the
placement of fuel assemblies in-intermediate positions during core alterations.
Inaddition, BG&E determined that the potential existed for placing several
fresh 4.3 weight percent reload assemblies together and losing some of the
required 5 percent shutdown margin. Calculations also showed that under
extreme conditions an inadvertent criticality could occur ifa number of highly
reactive assemblies were grouped together and no credit was taken for control
rods or burnable poisons.
BG&E has revised the Calvert Cliffs refueling procedures to ensure that fuel
assemblies will not be placed in intermediate positions during core alterations
without first verifying their potential reactivity. The revised procedures
allow fuel to be positioned only in intermediate core locations that will
contain fuel of equal or greater reactivity in the final core configuration.
8905240229
. . -
IN 89-51 May 31, 1989 Discussion:
As a result of longer fuel operating cycles, utilities have been increasing
the enrichment of reload fuel. Some of these fresh reload assemblies may be
highly reactive under refueling conditions. Although analyses are performed
to confirm that the refueling boron concentration is sufficient to maintain
the required shutdown margin (subcriticality) for the final core configuration, these analyses may not be sufficient to assure that the shutdown margin will be
maintained for all intermediate fuel assembly positions. In addition, explicit
procedural controls may not exist to control the location and movement of highly
reactive fuel assemblies during refueling. Because a significant amount of
reactivity can be added to subcritical configurations by the addition of a
single highly reactive assembly, it is possible that an inadvertent criticality
could occur if a number of such assemblies are grouped together. With this
highly reactive fuel, subcritical multiplication-(inverse count rate) may not
provide adequate warning of an approach to criticality.
Combustion Engineering, Inc. (CE), the nuclear fuel design consultant for
Calvert Cliffs, recognized this potential problem and recently issued an
information bulletin regarding shutdown margin during refueling to all utili- ties with CE-designed plants. These utilities have been advised to review
their fuel shuffle procedures that control the location of highly reactive
fuel and to be aware that the refueling boron concentration' necessary to
maintain the required shutdown margin, which is based on the final core
conf -gu a--I maT nut bersufftwa-to-ass re'that-the-r-requtred shutduwui -
margin will be maintained for all intermediate-fuel assembly positions. In
circumstances in which explicit analyses areinot available for each inter- mediate fuel assembly position, CE recommends positioning fuel only in
intermediate core locations that will contain fuel of equal or greater
reactivity in the final core configuration.
No specific action or written response is required by this information notice.
If you have any questions regarding 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:
Laurence I. Kopp, NRR
(301) 492-0879 Attachment: List of Recently Issued NRC Information Notices
I . - ,
'Attachment
IN 89-51 May 31, 1989 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
88-88, Degradation of Westinghouse 5/31/89 All holders of OLs
Supp. 1 ARD Relays or CPs for nuclear
power reactors.
89-50 Inadequate Emergency 5/30/89 All holders of OLs
Diesel Generator Fuel or CPs for nuclear
Supply power reactors.
89-49 Failure to Close Service 5/22/89 All holders of OLs
Water Cross-Connect or CPs for nuclear
Isolation Valves power reactors.
89-48 Design Deficiency in the 5/22/89 All holders of OLs
Turbine-Driven Auxiliary or CPs for nuclear
Feedwater Pump Cooling power reactors.
Water System
_ 89-47 tntll_ .roblc-mEl ~+-5l8/aS -lA.1,,bol depr if s,,,
Worn or Dlstorted Hose; or CPs for nuclear
Clamps'on. Self-Contained power reactors and
Breathing Apparatus fuel facilities.
89-46 Confidentiality of 5/11/89 All holders of licenses
Exercise Scenarios for fuel cycle facilities
and byproduct material
licensees having an
approved emergency
response plan.
89-45 Metalclad, Low-Voltage. 5/8/89 All holders of OLs
Power Circuit Breakers or CPs for nuclear
Refurbished with Sub- power reactors.
standard Parts
89-44 Hydrogen Storage on the 4/27/89 All holders of OLs
Roof of the Control Room or CPs for nuclear
power reactors.
88-82, Torus Shells with Corrosion 5/2/89 All holders of OLs
Supp. 1 and Degraded Coatings in or CPs for BWRs.
BWR Containments
OL = Operating License
CP = Construction Permit
IN 89-51 May 31, 1989 Discussion:
As a result of longer fuel operating cycles, utilities have been increasing
the enrichment of reload fuel. Some of these fresh reload assemblies may be
highly reactive under refueling conditions. Although analyses are performed
to confirm that the refueling boron concentration is sufficient to maintain
the required shutdown margin (subcriticality) for the final core configuration, these analyses may not be sufficient to assure that the shutdown margin will be
maintained for all Intermediate fuel assembly positions. In addition, explicit
procedural controls may not exist to control the location and movement of highly
reactive fuel assemblies during refueling. Because a significant amount of
reactivity can be added to subcritical configurations by the addition of a
single highly reactive assembly, it is possible that an inadvertent criticality
could occur if a number of such assemblies are grouped together. With this
highly reactive fuel, subcritical multiplication (inverse count rate) may not
provide adequate warning of an approach to criticality.
Combustion Engineering, Inc. (CE), the nuclear fuel design consultant for
Calvert Cliffs, recognized this potential problem and recently issued an
information bulletin regarding shutdown margin during refueling to all utili- ties with CE-designed plants. These utilities have been advised to review
their fuel shuffle procedures that control the location of highly reactive
fuel and to be aware that the refueling boron concentration necessary to
maintain the required shutdown margin, which is based on the final core
configuration, may not be sufficient to assure that their required shutdown
margin will be maintained for all intermediate fuel assembly positions. In
circumstances in which explicit analyses are not available for each inter- mediate fuel assembly position, CE recommends positioning fuel only in
intermediate core locations that will contain fuel of equal or greater
reactivity in the final core configuration.
No specific action or written response is required by this information notice.
If you have any questions regarding 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:
Laurence I.Kopp, NRR
(301) 492-0879 C 4 2 Attachment: List of Recently Issued NRC Informat on 5
- SEE PREVIOUS PAGE FOR CONCURRENCE
D/ A *C/OGCB:DOEA:NRR*RPB:ARM
C CHBerlinger TechEd
05/ i9H 05/23/89 05/17/89
- OGCB:DOEA:NRR *SRXB:DEST:NRR *C/S XB:DEST:NRR *SAD/DEST:NRR *D/DEST:NRR
JGuillen LKopp WHodges AThadani LCShao
05/17/89 05/18/89 05/19/89 05/17/89 05/22/89
I . ~ ~
-
IN 89-XX
May xx, 1989 Discussion:
As a result of longer fuel operating cycles, utilities have been increasing the
enrichment of reload fuel. Some of these fresh reload assemblies may be highly
reactive under refueling conditions. Although analyses are performed to
confirm that the refueling boron concentration is sufficient to maintain the
required shutdown margin (subcriticality) for the final core configuration, these analyses may not be sufficient to assure that the shutdown margin will be
maintained for all intermediate fuel assembly positions. In addition, explicit
procedural controls may not exist to control the location and movement of
highly reactive fuel assemblies during refueling. Because a significant amount
of reactivity can be added to subcritical configurations by the addition of a
single highly reactive assembly, it is possible that an inadvertent criticality
could occur if a number of such assemblies are grouped together. With this
highly reactive fuel, subcritical multiplication (inverse count rate) may not
provide adequate warning of an approach to criticality.
Combustion Engineering, Inc. (CE), the nuclear fuel design consultant for
Calvert Cliffs, recognized this potential problem and recently issued an
information bulletin regarding shutdown margin during refueling to all utili- ties with CE-designed plants. These utilities have been advised to review
their fuel shuffle procedures that control the location of highly reactive fuel
and to be aware that the refueling boron concentration necessary to maintain
the required shutdown margin, which is based on the final core configuration, may not be sufficient to assure that their required shutdown margin will be
maintained for all intermediate fuel assembly positions. In circumstances in
which explicit analyses are not available for each intermediate fuel assembly
position, CE recommends positioning fuel only in intermediate core locations
that will contain fuel of equal or greater reactivity in the final core
configuration.
No specific action or written response is required by this information notice.
If you have any questions regarding 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:
Laurence I. Kopp, NRR
(301) 492-0879 Attachment: List of Recently Issued NRC Informationoti
D/DOEA:NRR C/OG X 'EA:NRR RPB:ARM
CERossi CHBerlinger TechEd
05/ /89 05/ /89 05/ FV8 OG SRXB:D J NRR C/SRXB:D T R SAD DEST D/DEST: NRR,0 .
JGu en LKopp WHodges AThajani LCShao
05 89 05/fa/89 05/( /8 05/ 89 05J / 8;9t
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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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