Shaft Binding in General Electric Type Sbm Control SwitchesML031050156 |
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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
06/03/1998 |
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From: |
Roe J Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-98-019, NUDOCS 9805280259 |
Download: ML031050156 (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, 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 [[: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 [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
REVISED -TO ADD ATTA JENT 1'UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 June 3,1998 NRC INFORMATION
NOTICE 98-19: SHAFT BINDING IN GENERAL ELECTRIC TYPE St[ X CONTROL SWITCHES dX
Addressees
All holders of operating
licenses for nuclear power reactors.
Purpose
The U.S. Nuclear Regulatory
Commission (NRC) is issuing this information
notice (IN) to alert addressees
to the potential
for some General Electric (GE) Type SBM control switches with spring return function to fail to return to the normal position because the manufacturer
failed to account for shrinkage
of the phenolic material as a result of post-mold
curing. 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 are not NRC requirements;
therefore, no specific action or written response is required.Description
of Circumstances
In December 1997, the licensee for LaSalle County Station, Commonwealth
Edison Company (ComEd), was replacing
the GE Type SBM control switches at both units during a prolonged dual-unit
maintenance
outage. The licensee was replacing
more than 1,100 SBM switches because the switches were reaching the end of service life and because of concerns about cracking of the Lexan cam followers, which was originally
described
In NRC IN 80-13, "General Electric Type SBM Control Switches Defective
Cam Followers" (Accession
- 8002280650).
During the replacement
effort, the licensee discovered
that some of the new switches that had been installed
for about a year would not spring return to the reset (normal) position.
The licensee found that 21 out of the 246 Installed
replacement
switches exhibited
the binding. 0 In early January 1998, two of the failed switches were sent to GE-Nuclear
Energy (NE) for evaluation
to determine
the cause of the switch binding. On January 23, 1998, GE-NE issued a transfer of information
letter to affected customers
In accordance
with 10 CFR 21.21(b) to alert them to the possible failure of the SBM switches to return to the normal position after operation (Accession
- 9801280338).
Subsequently, ComEd determined
that the reported deviation represented
a substantial
safety hazard because various equipment
important
to plant safety ff ected, and submitted
a 10 CFR Part 21 notification
to the NRC on March, 16, 1998.*8.'052ll
IN 98-19 June 3.1998 Discussion
The SBM control switch Is manufactured
as a commercial
item by GE-Electrical
Distribution
and Control (GE-ED&C), Power Management
Division, In Malvem, Pennsylvania.
GE-NE dedicates the switches for nuclear safety applications.
The switches are used extensively
throughout
the nuclear power Industry as control board switches to actuate safety-related
pump motors, motor-operated valves, and circuit breakers.
Although GE-NE has informed Its customers
of record about the binding of the SBM switches, some licensees
may have procured the switches from third-party
dedicating
enUties that purchased
the switches as commercial-grade
components.
This Information
notice Is intended to alert all licensees
to the potential
binding Issue.The failure mode has been Identified
as binding caused by Interference
between the rear brass bearing and the phenolic rear bearing support. The exploded view of an SBM switch in the attached Figure 1 shows the rear bearing support plate (Item 30, also called the barrier) and the rear bearing (Item 32) on the switch shaft. The Interference
Is caused by post-mold
cure shrinkage
of the phenolic material, which takes place for up to 2 years after the phenolic material Is molded Into the bearing support. GE-ED&C found that the mold used to make the bearing support had worn over the years to the point that the diameter of the opening for the brass rear bearing was still within specifications
but near the minimum allowable
value. The original GE design did not account for the post-mold
cure shrinkage
of the phenolic material.The second contributing
factor to switch failure Is a brass rear bearing at Its maximum allowable diameter.
Only switches with both the undersized
hole In the bearing supports and bearings at the maximum tolerance
have experienced
failures.
Testing confirmed
that switches with bearings of nominal size functioned
properly, even with undersized
holes In the phenolic bearing support.The failed switches were manufactured
between November 1996 and February 1997. Although most of the post-mold
cure shrinkage
occurs within the first 12 to 18 months, GE conservatively
assumed that switches manufactured
after March 1996 may be susceptible.
These switches can be Identified
by the last two characters
on the green quality control acceptance
sticker. The affected date codes are PL, RL, SL, TL, UL, VL, WL, XL, YL, ZL, NM, OM, PM, RM, SM, TM, UM, VM, WM, XM, YM, ZM, NN, and ON. The manufacturer
has improved the SBM switch manufacturing
process to allow for phenolic post-mold
cure shrinkage, and switches manufactured
as of March 1, 1998, should no longer be susceptible
to the failure mode.There are two safety concerns regarding
the switch binding: (1) possible control circuit damage caused by energizing
the momentary
circuit for a prolonged
period and (2) possible prevention
of control circuits from performing
their function because of the failure of the switch contacts to return to the normal position.
GE recommends
that licensees
with SBM switches manufactured
after March 1996 advise operators
to return the switch to the normal position after operation
to preclude any circuit malfunctions.
Ucensees should also note that susceptible
switches most likely will fall after about 12 to 18 months after the date of manufacture.
Switches more than 2 years old are not thought to be susceptible
to binding caused by post-mold
cure shrinkage.
IN 98-19 June 3, 1998 Page 3 eT 3 This IN requires no specific action .or written response.
However, recipients
are reminded that they are required to consider industry-wide
operating
experience (including
NRC INs) where practical, when setting goals and performing
periodic evaluations
under Section 50.65, Requirements
for Monitoring
the Effectiveness
of Maintenance
at Nuclear Power Plants," of Part 50 of Title 10 of the Code of Federal Regulations.
If you have any questions
about the information
In this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.\N /s/t d Jack W. Roe, Acting Director Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical
contacts:
Stephen Alexander, NRR 301-415-2995 E-mail: sda~nrc.gov
David Skeen, NRR 301-415-1174 E-mail:dls@nrc.gov
Attachment:
Figure 1 -Exploded View of Type SBM Switch List of Recently Issued NRC Information
Notices DOCUMENT NAME: G:\DLS\IN97-XX.SBM
To receive a copy of this document, indicate In the box C=Copy wlo attachmentlenclosure
E=Copy with attachmentlenclosure
N = No copy*See previous concurrence
OFFICE PECB:DRPM
E HQMB/:DRCH
_ D:DRCH C:PECBDRPM
_D:DRPM NAME D. Skeen* S. Alexander*
R. Spessard*
J. Stolz* J. Roe*DATE 05/14/98 05/12/98 05/19/98 05/21/98 05/26/98 OFFICIAL RECORD COPY
I 4311MS WSS edAj lo ma!A popoldx3 -I OJnflq!udnS BumM J)je9e et 11 ID00 rt 03 '0 03 o %O 'I-h %a A?ft ,N uotlo8 wnaej-Supds aiM S"tmi!MS joi POsn AN _/* I-
KjAttachment
2 IN 98-19 June 3, 1998 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 98-18 Recent Contamination
Incidences
5113/98 Part 35 Medical Licensees Resulting
from Failure to Perform Adequate Surveys 98-17 98-16 98-15 98-14 Federal Bureau of Investigations (FBI) Awareness
of National Security Issues and Responses (ANSIR) Program Inadequate
Operational
Checks of Alarm Ratemeters
Intergrity
of Operator Licensing Examinations
Undocumented
Changes to Non-Power
Reactor Safety System Wiring Post-Refueling
Outage Reactor Pressure Vessel Leak Testing Before Core Criticality
5/7/98 4/30198 4120/98 4/20/98 4/20/98 All U.S. Nuclear Regulatory
Commission
fuel cycle and power and non-power
reactor licensees All Industrial
Radiography
Licensees All holder of operating
licenses for nuclear power reactors except those that have permanently
ceased operations
and have certified
that fuel has been permanently
removed from the reactor vessel All holders of operating
licenses or construction
permits for test research reactors All holders of operating
licenses for nuclear power reactors except those that have permanently
ceased operations
and have certified
that fuel has been permanently
removed from the reactor vessel 98-13 OL = Operating
License CP = Construction
Permit
IN 98WXX MayXX, 1998 Wth information
notice requires no specific action or written response.
However, recipients
are reminded that they are required to consider Industry-wide
operating
experience (including
NRC Information
notices) where practical, when setting goats and performing
periodic evaluations
under Section 50.65, Requirements
for Monitoring
th Effectiveness
of Maintenance
at Nuclear Power Plants.' of Part 50 of Title 10 of the Code of Federal Regulations.
If you have any questions
about the Information
In ts notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Jack W. Roe, Acting Dfrector Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical
contacts:
Stephen Alexander, NRR 301-415-2995 E-mall: sda~nrc.gov
David Skeen, NRR 301-415-1174 E-mail:disenrc.gov
Attachment:
Ust of Recently Issued NRC Information
Notices DOCUMENT NAME: G:\DLSUN97-XX.SBM
ohro a copy of NIs docwnmnt Indicste In ft box CxCopy wo attachmoentnclosure
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IN 08,X I MayXX, 1 8ai This IN requires no specific action or written response.
However, recipients
are reminded that they uo required to consider Industrywlde
operating
experience (Including
NRC INs) where practical, when setting goals and performing
periodic evaluations
4nder Section 60.65, aRequirements
for Monitoring
tho Effectiveness
of Maintenance
at Nuclear Power Planta. of Part 50 of Title 10 of te Code of Federat Reguation
.If you have any questions
about the Information
In this notice, please contact one of the technical
contacts listed below or the.appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Jack W. Roe, Acting Director Dvislon of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical
contacts:
Stephen Alexander, NRR 301-415-2995 E-mail: sdaenrc.gov
David Skeen, NRR 301-416-1174 E-mail:dlsonrc.gov
Atachment:
Figure 1 -Exploded View of Type SBM Switch List of Recently Issued NRC Information
Notices DOCUMENT NAME: G:%DLSIN97XXS6BM
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D:DRC D:RP C:F RPM VIE D. S S .Ahxae R. tSpmard J. 8U -rE ._5i%8 05P418 0&8 05P198 051 198 OFFICIAL RECORD COPY
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list | - Information Notice 1998-01, Thefts of Portable Gauges (15 January 1998, Topic: Shutdown Margin, Moisture Density Gauge, Stolen)
- Information Notice 1998-02, Nuclear Power Plant Cold Weather Problems and Protective Measures (21 January 1998)
- Information Notice 1998-03, Inadequate Verification of Overcurrent Trip Setpoints in Metal-Clad, Low-Voltage Circuit Breakers (21 January 1998)
- Information Notice 1998-04, 1997 Enforcement Sanctions for Deliberate Violations of NRC Employee Protection Requirements (9 February 1998)
- Information Notice 1998-05, Criminal History Record Information (11 February 1998)
- Information Notice 1998-06, Unauthorized Use of License to Obtain Radioactive Materials, and Its Implication Under the Expanded Title 18 of the U.S. Code (19 February 1998)
- Information Notice 1998-07, Offsite Power Reliability Challenges from Industry Deregulation (27 February 1998)
- Information Notice 1998-08, Information Likely to Be Requested If an Emergency is Declared (2 March 1998)
- Information Notice 1998-08, Information Likely to Be Requested If an Emergency Is Declared (2 March 1998)
- Information Notice 1998-09, Collapse of an Isocam II, Dual-Headed Nuclear Medicine Gamma Camera (5 March 1998)
- Information Notice 1998-10, Probable Misadministrations Occurring During Intravascular Brachytherapy with Novoste Beta-cath System (9 March 1998, Topic: Brachytherapy)
- Information Notice 1998-11, Cracking of Reactor Vessel Internal Baffle Former Bolts in Foreign Plants (25 March 1998, Topic: Fire Barrier, Brachytherapy)
- Information Notice 1998-12, Licensees' Responsibilities Regarding Reporting & Follow-up Requirements for Nuclear-Powered Pacemakers (3 April 1998, Topic: Fire Barrier, Brachytherapy, Stolen)
- Information Notice 1998-13, Post-Refueling Outage Reactor Pressure Vessel Leak Testing Before Core Criticality (20 April 1998, Topic: Fire Barrier, VT-2, Pressure Boundary Leakage, Brachytherapy)
- Information Notice 1998-14, Undocumented Changes to Non-Power Reactor Safety System Wiring (20 April 1998, Topic: Brachytherapy)
- Information Notice 1998-15, Integrity of Operator Licensing Examinations (20 April 1998, Topic: Fire Barrier, Job Performance Measure)
- Information Notice 1998-16, Inadequate Operational Checks of Alarm Ratemeters (30 April 1998, Topic: Brachytherapy)
- Information Notice 1998-17, Federal Bureau of Investigation'S (FBI) Awareness of National Security Issues and Response (ANSIR) Program (7 May 1998)
- Information Notice 1998-17, Federal Bureau of Investigation'S (FBI) Awareness of National Security Issues and Response (Ansir) Program (7 May 1998, Topic: Brachytherapy)
- Information Notice 1998-18, Recent Contamination Incidences Resulting from Failure to Perform Adequate Surveys (13 May 1998, Topic: Brachytherapy)
- Information Notice 1998-19, Shaft Binding in General Electric Type Sbm Control Switches (3 June 1998)
- Information Notice 1998-20, Problems with Emergency Preparedness Respiratory Protection Programs (3 June 1998, Topic: Brachytherapy)
- Information Notice 1998-21, Potential Deficiency of Electrical Cable/Connection Systems (4 June 1998)
- Information Notice 1998-22, Deficiencies Identified During NRC Design Inspections (17 June 1998, Topic: Stroke time, Tornado Missile)
- Information Notice 1998-23, Crosby Relief Valve Setpoint Drift Problems Caused by Corrosion of Guide Ring (23 June 1998, Topic: Loop seal, Condition Adverse to Quality)
- Information Notice 1998-25, Loss of Inventory from Safety-Related Closed-Loop Cooling Water Systems (8 July 1998, Topic: Ultimate heat sink)
- Information Notice 1998-26, Settlement Monitoring and Inspection of Plant Structures Affected by Degradation of Porous Concrete Subfoundations (24 July 1998, Topic: Condition Adverse to Quality)
- Information Notice 1998-27, Steam Generator Tube End Cracking (24 July 1998)
- Information Notice 1998-28, Development of Systematic Sample Plan for Operator Licensing Examinations (31 July 1998)
- Information Notice 1998-29, Predicted Increase in Fuel Rod Cladding Oxidation (3 August 1998, Topic: Fuel cladding)
- Information Notice 1998-30, Effect of Year 2000 Computer Problem on NRC Licensees and Certificate Holders (12 August 1998, Topic: Brachytherapy)
- Information Notice 1998-31, Fire Protection System Design Deficiencies and Common-Mode Flooding of Emergency Core Cooling System Rooms at Washington Nuclear Project Unit 2 (18 August 1998)
- Information Notice 1998-33, NRC Regulations Prohibit Agreements That Restrict or Discourage an Employee from Participating in Protected Activities (28 August 1998, Topic: Brachytherapy)
- Information Notice 1998-34, Configuration Control Errors (28 August 1998)
- Information Notice 1998-36, Inadequate or Poorly Controlled, Non-Safety-Related Maintenance Activities Unnecessarily Challenged Safety Systems (18 September 1998)
- Information Notice 1998-37, Eligibility of Operator License Applicants (1 October 1998)
- Information Notice 1998-38, Metal-Clad Circuit Breaker Maintenance Issues Identified by NRC Inspections (15 October 1998, Topic: Overtravel)
- Information Notice 1998-39, Summary of Fitness-for-Duty Program Performance Reports for Calendar Years 1996 and 1997 (30 October 1998, Topic: Fitness for Duty)
- Information Notice 1998-40, Design Deficiencies Can Lead to Reduced ECCS Pump Net Positive Suction Head During Design-Basis Accidents (26 October 1998)
- Information Notice 1998-41, Spurious Shutdown of Emergency Diesel Generators From Design Oversight (20 November 1998)
- Information Notice 1998-41, Spurious Shutdown of Emergency Diesel Generators from Design Oversight (20 November 1998)
- Information Notice 1998-42, Implementation of 10 CFR 55.55a(g) Inservice Inspection Requirements (1 December 1998)
- Information Notice 1998-43, Leaks in Emergency Diesel Generator Lubricating Oil & Jacket Cooling Water Piping (4 December 1998)
- Information Notice 1998-44, Ten-Year Inservice Inspection (ISI) Program Update for Licensees That Intend to Implement Risk-Informed ISI of Piping (10 December 1998, Topic: Probabilistic Risk Assessment)
- Information Notice 1998-45, Cavitation Erosion of Letdown Line Orifices Resulting in Fatigue Cracking of Pipe Welds (15 December 1998)
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