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.
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 Inthe box C=Copy wlo attachmentlenclosure E=Copy with attachmentlenclosure N = No copy
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 A?
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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 Federal Bureau of Investigations 5/7/98 All U.S. Nuclear Regulatory
(FBI) Awareness of National Commission fuel cycle and power
Security Issues and Responses and non-power reactor licensees
(ANSIR) Program
98-16 Inadequate Operational Checks 4/30198 All Industrial Radiography
of Alarm Ratemeters Licensees
98-15 Intergrity of Operator Licensing 4120/98 All holder of operating licenses
Examinations for nuclear power reactors except
those that have permanently
ceased operations and have
certified that fuel has been
permanently removed from the
reactor vessel
98-14 Undocumented Changes to 4/20/98 All holders of operating licenses
Non-Power Reactor Safety or construction permits for test
System Wiring research reactors
98-13 Post-Refueling Outage Reactor 4/20/98 All holders of operating licenses
Pressure Vessel Leak Testing for nuclear power reactors except
Before Core Criticality those that have permanently
ceased operations and have
certified that fuel has been
permanently removed from the
reactor vessel
OL = Operating License
CP = Construction Permit
IN 98WXX
MayXX, 1998 Wth information notice requires no specific action or written response.
reminded that they are required to consider Industry-wide operating experience However, recipients are
Information notices) where practical, when setting goats and performing (including NRC
under Section 50.65, Requirements for Monitoring th Effectiveness of periodic evaluations
Maintenance at Nuclear
Power Plants.' of Part 50 of Title 10 of the Code of Federal Regulations.
questions about the Information Ints notice, please contact one of the If you have any
below or the appropriate Office of Nuclear Reactor Regulation (NRR) technical contacts listed
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
E=Copy with attacelntendcosure N u No copy
FICE PECB:DRPM L HQMB/:DRCH D:DRCH _ C:PECBJP
ME D. SkeAI r R. Spessard J. Stolz J. Roe
rE 05//98 Om$ 05/ /98 05/98 05/ /98 OFFICIAL RECORD COPY
IN08,X I
MayXX, 1 8ai This IN requires no specific action or written response. However, they uo required to consider Industrywlde operating experience recipients are reminded that
practical, when setting goals and performing periodic evaluations (Including NRC INs) where
4nder Section 60.65, aRequirements for Monitoring tho Effectiveness of Maintenance
Part 50 of Title 10 of te Code of Federat Reguation . If you have at Nuclear Power Planta. of
Information Inthis notice, please contact one of the technical contacts any questions about the
appropriate Office of Nuclear Reactor Regulation (NRR) project listed below or the.
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
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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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