Failure of Westinghouse W-2-Type Circuit Breaker Cell SwitchesML031130469 |
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: |
12/07/1987 |
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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-87-061, NUDOCS 8712010036 |
Download: ML031130469 (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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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>. |
4t --
IN 87-61 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 December 7, 1987 NRC INFORMATION NOTICE NO. 87-61: FAILURE OF WESTINGHOUSE W-2-TYPE
CIRCUIT BREAKER CELL SWITCHES
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 resulting from the failure of Westinghouse W-2-type circuit breaker
cell switches. 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 October 16, 1987, Westinghouse Electric Corporation notified the Nuclear
Regulatory Commission (NRC) staff, pursuant to the requirements of 10 CFR
Part 21, of the failure of a modified Westinghouse W-2-type switch that was
being utilized as a circuit breaker cell switch. The failure was identified
at Indian Point Station, Unit 3, on May 15, 1987, while the reactor was at
cold shutdown for a scheduled refueling outage. The output breaker for
emergency diesel generator (EDG) No. 31 was prevented from re-energizing
the 480-volt bus 2A after plant personnel had inadvertently de-energized
480-volt buses 2A and 5A. Subsequent investigation by the licensee determined
that an erroneous input to the EDG logic system had prevented the EDG output
breaker from closing. The licensee identified deformation of the spring
retainer in the spring-return mechanism of the cell switch in the 52/2A
breaker cell as the root cause of the erroneous input.
The spring retainer is continuously under stress whenever the breaker is
racked in (which it is,except when the breaker is racked out for testing
or maintenance) and releases whenever the breaker is racked out. Its
deformation allowed a loss of spring tension that rendered the cell switch
unable to spring-return to the racked out position when normal supply breaker
52/2A was racked out for maintenance. Thus, the EDG logic system received an
erroneous input indicating that breaker 52/2A was racked in and the main con- tacts were still closed. This erroneous input prevented the EDG No. 31 output
breaker from closing automatically in response to a loss of power. During
872106Z
IN 87-61 December 7, 1987 subsequent inspections by Indian Point personnel, 35 of a total of 37 similar
W-2-type switch spring retainers in the 480-volt system breakers exhibited
some sign of deformation.
All the cell switches had been shipped to Indian Point in 1971-1972 and all had
been in service for close to 15 years. The licensee reported the results of its
investigation to the NRC in Licensee Event Report 87-009-00 on October 2, 1987.
Discussion:
Westinghouse has determined (1) that the deformation of the spring retainer in
the spring-return mechanism of the cell switches was related to the aging of
the component and (2) that the failure mechanism was the continuous stress it
experiences while the breaker is racked in. The W-2-type cell switches are
available as optional equipment for all Westinghouse DS switchgear cabinets.
Westinghouse has indicated that inspection or testing performed. when the
breaker is racked out would determine if a failure has occurred. Where inspec- tions and/or testing have not been performed, the potential exists that if the
breaker is not racked in, a cell switch malfunction may prevent the completion
of safety-related functions dependent on cell switch indication of the breaker
being racked out or in the test position.
In the 10 CFR Part 21 notification submitted to the NRC, Westinghouse recommends
that proper cell switch operation'be verified through periodic inspections or
testing, or whenever the breaker is racked out. Proper operation of the spring
retainer- is only veriffable-when the-breaker--is-moved- fromr-ts-racked-iin-position.--
Visible inspection may be used to verify cell switch operation. However, it will
be necessary to move the breaker out on the rails to observe whether the switch
operating lever is in its proper position (30 degrees off. vertical for the W-2 cell switch). Any uncertainty in this observation may be resolved by manually
ensuring that the switch has returned to the proper position. Persons performing
this inspection should use caution not to contact any energized terminals.'
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.
ares E.Rossi, Director
Division of 'Operational Events Assessment
Office of Nuclear Reactor'Regulation
Technical Contacts: K. R. Naidu, NRR
(301) 492-9656 Jaime Guillen, NRR
(301) 492-8933 Attachment: List of Recently Issued NRC Information Notices
Attachment
IN 87-61 December 7, 1987 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES 1987 Information Date of
Notice No. Subject Issuance Issued to
87-60 Depressurization of Reactor 12/4/87 All holders of OLs
Coolant Systems in or CPs for PWRs.
Pressurized-Water Reactors86-108, Degradation of Reactor 11/19/87 All holders of OLs
Supp. 2 Coolant System Pressure or CPs for nuclear
Boundary Resulting from power reactors.
Boric Acid Corrosion
87-59 Potential RHR Pump Loss 11/17/87 All holders of OLs
or CPs for nuclear
power reactors.
87-58 Continuous Communications 11/16/87 All nuclear power
Following Emergency reactor facilities
Notifications holding an OL and
the following fuel
facilities that have
Emergency Notification
!: -~ .: -, .- Systems: Nuclear
Fuel Services, Erwin, TN; General Atomics, San Diego, CA; UNC,
Montville, CT; and
B & W LRC and B & W
Navy, Lynchburg, VA.
87-57 Loss of Emergency Boration 11/6/87 All holders of OLs
Capability Due to Nitrogen or CPs for nuclear
Gas Intrusion power reactors.
87-56 Improper Hydraulic Control 11/4/87 All holders of OLs
Unit Installation at BWR or CPs for boiling
Plants. water reactors (BWRs).
87-55 Portable Moisture/Density 10/29/87 All NRC licensees
Gauges: Recent Incidents authorized to
of Portable Gauges Being possess portable
Stolen or Lost gauges.
87-54 Emergency Response Exercises 10/23/87 All holders of OLs
or CPs for nuclear
power reactors.
OL = Operating License
CP = Construction Permit
IN 87-61 December 7, 1987 subsequent inspections by Indian Point personnel, 35 of a total of 37 similar
W-2-type switch spring retainers in the 480-volt system breakers exhibited
some sign of deformation.
All the cell switches had been shipped to Indian Point in 1971-1972 and all had
been in service for close to 15 years. The licensee reported the results of its
investigation to the NRC in Licensee Event Report 87-009-00 on October 2, 1987.
Discussion:
Westinghouse has determined (1) that the deformation of the spring retainer in
the spring-return mechanism of the cell switches was related to the aging of
the component and (2) that the failure mechanism was the continuous stress it
experiences while the breaker is racked in. The W-2-type cell switches are
available as optional equipment for all Westinghouse DS switchgear cabinets.
Westinghouse has indicated that inspection or testing performed when the
breaker is racked out would determine if a failure has occurred. Where inspec- tions and/or testing have not been performed, the potential exists that if the
breaker is not racked in, a cell switch malfunction may prevent the completion
of safety-related functions dependent on cell switch indication of the breaker
being racked out or in the test position.
In the 10 CFR Part 21 notification submitted to the NRC, Westinghouse recommends
that proper cell switch operation be verified through periodic inspections or
testing, or whenever the breaker is racked out. Proper operation of the spring
retainer is only verifiable when the breaker is moved from its racked in position.
Visible inspection may be used to verify cell switch operation. However, it will
be necessary to move the breaker out on the rails to observe whether the switch
operating lever is in its proper position (30 degrees off vertical for the W-2 cell switch). Any uncertainty in this observation may be resolved by manually
ensuring that the switch has returned to the proper position. Persons performing
this inspection should use caution not to contact any energized terminals.
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 Contacts: K. R. Naidu, NRR
(301) 492-9656 Jaime Guillen, NRR
(301) 492-8933 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
- OGCB:DOEA:NRRtVIB:DRIS:NRR *SELB:DEST:NRR*PPMB:ARM*C/OGCB:DOEA:NRR NR
JGuillen KNaidu FRosa TechEd CHBerlinger CERossi
11/03/87 11/ /87 11/06/87 10/31/87 11/20/87 12// /87
IN 87-XX
November xx, 1987 All the cell switches had been shipped to Indian Point In 1971-1972 and all had
been in service for close to 15 years. The licensee reported the results of
its investigation to the NRC in Licensee Event Report 87-009-00 on October 2,
1987.
Discussion:
Westinghouse has determined (1) that the deformation of the spring retainer in
the spring-return mechanism of the cell switches was related to the aging of
the component and (2) that the failure mechanism was the continuous stress it
experiences while the breaker is racked in. The W-2-type cell switches are
available as optional equipment for all Westinghouse DS switchgear cabinets.
Westinghouse has indicated that inspection or testing performed when the
breaker is racked out would determine if a failure has occurred. Where inspec- tions and/or testing have not been performed, the potential exists that if the
breaker is not racked in, a cell switch malfunction may prevent the completion
of safety-related functions dependent on cell switch indication of breaker
racked out or test position.
In the 10 CFR Part 21 notification submitted to the NRC, Westinghouse recom- mends that proper cell switch operation be verified through periodic inspec- tions or testing, or whenever the breaker is racked out. Proper operation of
the spring retainer is only verifiable when the breaker is moved from its
racked in position. Visible inspection may be used to verify cell switch
operation. However, it will be necessary to move the breaker out on the rails
to observe whether the switch operating level is in its proper position (30
degrees off vertical for the W-2 cell switch). Any uncertainty in this obser- vation may be resolved by manually ensuring that the switch has returned to the
proper position. Persons performing this inspection should use caution not to
contact any energized terminals.
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 Contacts: K. R. Naidu, NRR
(301) 492-9656 Jaime Guillen, NRR
(301) 492-8933 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES 0
- OGCB:DOEA:NRR RVIB:DRIS:NRR *SELB: ET:NRR*PPMB:ARM C/OG :NRR D/DOEA:NRR
JGuillen KNaidu FRosa 4<-TechEd CHBerlinger CERossi
11/03/87 11/ /87 11/06/ 7ifr-10/31/87 11//87 11/ /87
IN 87-XX
November xx, 1987 All the cell switches had been shipped to Indian Point in 1971-1972 and all had
been in service for close to 15 years. The licensee reported the results of
its investigation to the NRC in Licensee Event Report 87-009-00 on October 2,
1987.
Discussion:
Westinghouse has determined (1) that the deformation of the spring retainer in
the spring-return mechanism of the cell switches was related to the aging of
the component and (2) that the failure mechanism was the continuous stress it
experiences while the breaker is racked-in. The W-2-type cell switches are
available as optional equipment for all Westinghouse DS switchgear cabinets.
Westinghouse has indicated that inspection or testing performed when the
breaker is moved from the "connected" position would determine if a failure has
occurred. Where inspections and/or testing has not been performed, the poten- tial exists that if the breaker is not racked in, a cell switch malfunction may
prevent the completion of safety-related functions dependent on cell switch
indication of breaker position.
In the 10 CFR Part 21 notification submitted to the NRC, Westinghouse recom- mends that proper cell switch operation be verified through periodic inspec- tions or testing, or whenever the breaker is removed from its connected"
position. Proper operation of the spring retainer is only verifiable when the
breaker is moved from its racked in position. Visible inspection may be used
to verify cell switch operation. However, it will be necessary to move the
breaker out on the rails to observe whether the switch operating level is In
its proper position (30 degrees off vertical for the W-2 cell switch). Any
uncertainty in this observation may be resolved by manually ensuring that the
switch has returned to the proper position. Persons performing this Inspection
should use caution not to contact any energized terminals.
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 Contacts: K. R. Naidu, NRR
(301) 492-9656 Jaime Guillen, NRR
(301) 492-8933 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
- OGCB:DOEA:NRR RVIB:DRIS:NRR *Sw ~jbT:NRR*PPMB:ARM C/OGCB:DOEA:NRR D/DOEA:NRR
JGui KNaidu FR. TechEd CHBerlinger CERossi
11/0I3 11/ /87 7/!7 10/31/87 11/ /87 11/ /87
I . . I
IN 87-XX
October xx, 1987 Page 2 of
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 Contacts: K~a+m R. Naidu, NRR
(301) 492-9656 Jaime Guillen, NRR
(301) 492-8933 Attachment: List of Recently Issued NRC Information Notices
OGCB:DOEA:NRR RVIB:DRIS:NRR SELB:DEST:NRR PPMB:ARM C/OGCB: DOEA:NRR D/DOEA:NRR
JGuillen KNaidu FRosa TechEdat tCHBerlinger CERossi
10/ /87 10/ /87 10/ /87 10/3//87 10/ /87 10/ /87
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list | - Information Notice 1987-02, Inadequate Seismic Qualification of Diaphragm Valves by Mathematical Modeling and Analysis (13 January 1987, Topic: Boric Acid)
- Information Notice 1987-03, Segregation of Hazardous and Low-Level Radioactive Wastes (15 January 1987, Topic: Boric Acid)
- Information Notice 1987-04, Diesel Generator Fails Test Because of Degraded Fuel (16 January 1987, Topic: Boric Acid, Coatings)
- Information Notice 1987-05, Miswiring in a Westinghouse Rod Control System (2 February 1987, Topic: Unanalyzed Condition, Boric Acid)
- Information Notice 1987-06, Loss of Suction to Low-Pressure Service Water System Pumps Resulting from Loss of Siphon (30 January 1987, Topic: Boric Acid)
- Information Notice 1987-07, Quality Control of Onsite Dewatering/Solidification Operations by Outside Contractors (3 February 1987, Topic: Boric Acid, Process Control Program)
- Information Notice 1987-08, Degraded Motor Leads in Limitorque DC Motor Operators (4 February 1987, Topic: Boric Acid, Anchor Darling)
- Information Notice 1987-09, Emergency Diesel Generator Room Cooling Design Deficiency (5 February 1987, Topic: Probabilistic Risk Assessment)
- Information Notice 1987-10, Potential for Water Hammer During Restart of Residual Heat Removal Pumps (11 February 1987)
- Information Notice 1987-11, Enclosure of Vital Equipment within Designated Vital Areas (13 February 1987, Topic: Contraband)
- Information Notice 1987-11, Enclosure of Vital Equipment Within Designated Vital Areas (13 February 1987, Topic: Contraband)
- Information Notice 1987-12, Potential Problems with Metal Clad Circuit Breakers, General Electric Type AKF-2-25 (13 February 1987)
- Information Notice 1987-13, Potential for High Radiation Fields Following Loss of Water from Fuel Pool (24 February 1987)
- Information Notice 1987-14, Actuation of Fire Suppression System Causing Inoperability of Safety-Related Ventilation Equipment (23 March 1987, Topic: Water hammer)
- Information Notice 1987-15, Compliance with the Posting Requirements of Subsection 223b of the Atomic Energy Act of 1954, as Amended (25 March 1987)
- Information Notice 1987-15, Compliance with the Posting Requirements of Subsection 223B of the Atomic Energy Act of 1954, As Amended (25 March 1987)
- Information Notice 1987-16, Degradation of Static O Ring Pressure Switches (2 April 1987)
- Information Notice 1987-17, Response Time of Scram Instrument Volume Level Detectors (7 April 1987, Topic: Scram Discharge Volume)
- Information Notice 1987-18, Unauthorized Service on Teletherapy Units by Nonlicensed Maintenance Personnel (8 April 1987)
- Information Notice 1987-19, Perforation and Cracking of Rod Cluster Control Assemblies (9 April 1987)
- Information Notice 1987-20, Hydrogen Leak in Auxiliary Building (20 April 1987, Topic: Excess Flow Check Valve)
- Information Notice 1987-21, Shutdown Order Issued Because Licensed Operators Asleep While on Duty (11 May 1987)
- Information Notice 1987-22, Operator Licensing Requalification Examinations at Nonpower Reactors (22 May 1987, Topic: License Renewal)
- Information Notice 1987-23, Loss of Decay Heat Removal During Low Reactor Coolant Level Operation (27 May 1987, Topic: Boric Acid)
- Information Notice 1987-24, Operational Experience Involving Losses of Electrical Inverters (4 June 1987)
- Information Notice 1987-25, Potentially Significant Problems Resulting from Human Error Involving Wrong Unit, Wrong Train, or Wrong Component Events (11 June 1987, Topic: Boric Acid, Fire Watch, Overspeed trip)
- Information Notice 1987-25, Potentially Significant Problems Resulting From Human Error Involving Wrong Unit, Wrong Train, or Wrong Component Events (11 June 1987, Topic: Boric Acid, Fire Watch)
- Information Notice 1987-26, Cracks in Stiffening Rings on 48-Inch-Diameter UF6 Cylinders (11 June 1987, Topic: Boric Acid)
- Information Notice 1987-26, Cracks in Stiffening Rings on 48-Inch-Diameter Uf6 Cylinders (11 June 1987)
- Information Notice 1987-27, Iranian Official Implies Vague Threat to U.S. Resources (10 June 1987, Topic: Boric Acid)
- Information Notice 1987-28, Air Systems Problems at U.S. Light Water Reactors (28 December 1987, Topic: Boric Acid)
- Information Notice 1987-29, Recent Safety-Related Incidents at Large Irradiators (26 June 1987, Topic: Coatings, Temporary Modification, Biofouling, Uranium Hexafluoride)
- Information Notice 1987-30, Cracking of Surge Ring Brackets in Large General Electric Company Electric Motors (2 July 1987)
- Information Notice 1987-31, Blocking Bracing, and Securing of Radioactive Materials Packages in Transportation (10 July 1987, Topic: Uranium Hexafluoride)
- Information Notice 1987-32, Deficiencies in the Testing of Nuclear-Grade Activated Charcoal (10 July 1987)
- Information Notice 1987-33, Applicability of 10 CFR Part 21 to Nonlicensees (24 July 1987, Topic: Commercial Grade)
- Information Notice 1987-34, Single Failures in Auxiliary Feedwater Systems (24 July 1987)
- Information Notice 1987-35, Reactor Trip Breaker, Westinghouse Model DS-416, Failed to Open on Manual Initiation from the Control Room (30 July 1987)
- Information Notice 1987-36, Significant Unexpected Erosion of Feedwater Lines (4 August 1987)
- Information Notice 1987-37, Compliance with the General License Provisions of 10 CFR Part 31 (10 August 1987)
- Information Notice 1987-39, Control of Particle Contamination at Nuclear Power Plants (21 August 1987, Topic: Fuel cladding, Overexposure)
- Information Notice 1987-40, Backseating Valves Routinely to Prevent Packing Leakage (31 August 1987, Topic: Packing leak)
- Information Notice 1987-41, Failures of Certain Brown Boveri Electric Circuit Breakers (31 August 1987)
- Information Notice 1987-42, Diesel Generator Fuse Contacts (4 September 1987)
- Information Notice 1987-43, Gaps in Neutron-Absorbing Material in High-Density Spent Fuel Storage Racks (8 September 1987)
- Information Notice 1987-44, Thimble Tube Thinning in Westinghouse Reactors (16 September 1987)
- Information Notice 1987-45, Recent Safety-Related Violations of NRC Requirements by Industrial Radiography Licensees (25 September 1987, Topic: High Radiation Area)
- Information Notice 1987-46, Undetected Loss of Reactor Coolant (30 September 1987)
- Information Notice 1987-48, Information Concerning the Use of Anaerobic Adhesive/Sealants (9 October 1987, Topic: Loctite)
- Information Notice 1987-49, Deficiencies in Outside Containment Flooding Protection (9 October 1987, Topic: Safe Shutdown)
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