Inadequate Verification of Overcurrent Trip Setpoints in Metal-Clad, Low-Voltage Circuit BreakersML031130094 |
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: |
01/21/1998 |
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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-98-003, NUDOCS 9801200035 |
Download: ML031130094 (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, 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 [[: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>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 January21, 1998 NRC INFORMATION NOTICE 98-03: INADEQUATE VERIFICATION OF OVERCURRENT TRIP
SETPOINTS IN METAL-CLAD, LOW-VOLTAGE CIRCUIT
BREAKERS
Addressees
All holders of operating licenses for nuclear power reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to alert
addressees that inadequate verification of overcurrent trip setpoints for metal-clad, low-voltage
circuit breakers may result in the loss of multiple safety functions. 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
On September 16, 1996, an Asea Brown Boveri (ABB) Company type K600S 480-Vac circuit
breaker prematurely tripped on overcurrent at Centerior Energy Company's Perry Nuclear Power
Plant and de-energized a safety-related motor control center (MCC). The circuit breakers SS-5 solid-state trip device (Power Shield) sensed an overcurrent even though actual MCC current at
the time of the trip was well below the Power Shield's expected trip setpoint. Subsequent
inspection of the circuit breaker revealed that the leads from one of the three current
transformers (CTs) used to sense fault currents were reversed. The reversed CT leads caused
the Power Shield's long time overcurrent trip setpoint to shift downwards from 660 amps of
primary current to approximately 330 amps and caused the breaker to trip inadvertently on
overcurrent.
Discussion
Three-phase solid-state and microprocessor trip units are sensitive to the polarity (or phase) of
the signal from the phase sensor CTs. The signal can be effectively shifted 1800 out of phase if
the CT leads are reversed (or connections between the lower CT terminals and the Power Shield
unit terminals are reversed) or if the CT coil is installed upside down. Normally, the signals from
the three phase sensor CTs are separated by 1200 of phase. However, when a single 1800
phase shifted signal from an incorrectly wired or installed CT is combined in the processor with
ED as/ool/
IDe -//
IN 98-03 January 21, 1998 the other two, the sensed peak amplitude of the combined signal can be effectively
doubled. In
at least one instance, as described above, this condition has caused the solid-state
trip unit to
actuate at a primary current level significantly below the expected level.
However, such an unexpected phase shift in CT secondary output current is not
detected
during single-phase primary current calibration and testing. Therefore, additional
inspections or
tests may be necessary to adequately verify proper operation of circuit breakers
equipped with
solid-state trip units. ABB's procedure to check phase sensor polarity for solid-state
trip
devices, Types SS-3, -4, -5, -13, -14, and -15 is as follows:
1. On the static trip (Power Shield) unit terminal strip, connect an analog meter (i.e.,
conventional electromechanical d'Arsonval meter movement), set to measure
current
(100 mA scale) as follows to check the phase sensors for each pole: Negative
test lead
at Terminal 5, Positive test lead successively for each test at Terminals 6, 7, and
8 for
the left, center, and right poles respectively.
2. Connect the NEGATIVE (-) terminal of a 1.5-volt battery to the finger assemblies
of the
breaker's LOWER primary disconnects for each of the above corresponding
poles for
each test. Then while observing the meter, touch a test lead from the POSITIVE
(+)
battery terminal to the corresponding pole's UPPER primary disconnect successively
for
each test.
3. Check that there is a momentary deflection of the meter needle in the positive
direction
as the positive battery lead is touched to each upper primary disconnect. A positive
deflection indicates that the polarity of the signal from the CT as read at the static
trip
unit is correct.
Normally, this test will confirm that both the wiring and the Phase Sensor CT orientation
are
correct. However, it should be noted that if both the wiring and the CT orientation
on the same
pole are reversed, this will also produce a signal of the correct polarity or correct
phase
relationship to the other two poles, but this is not the preferred condition. The
factory uses this
test as a troubleshooting procedure, not a substitute for good visual inspection
of the assembly.
In addition, the test will confirm correct CT winding, internal lead-to-winding connections
cover marking, which would not otherwise be readily apparent if incorrect on new and
CTs from the
CT manufacturing facility.
The circuit breaker that tripped prematurely on overcurrent at Perry was a new
circuit breaker
supplied by ABB Power T&D Co., Inc. On March 26, 1997, ABB notified the
NRC in a 10 CFR
Part 21 report that a potential exists for new low-voltage, K-line circuit breakers, equipped with
the Power Shield solid-state trip device, to trip well below the device's trip setting
if the circuit
breakers overcurrent sensing CTs are incorrectly connected to the Power Shield
trip device.
Although the circuit breaker that tripped prematurely at Perry was a new circuit
breaker, the
I
IN 9803 January 21, 1998 NRC is aware of
potential exists for refurbished breakers to have a similar wiring defect. The
service centers for
instances in which ABB K-line circuit breakers have been sent to ABB
breakers to the licensee with the CTs
refurbishment, and the service center returned the circuit
incorrectly wired.
these six CTs are referred
A typical metal-clad ABB K-line circuit breaker has six CTs. Three of
remaining three CTs are
to as "phase sensors," and are used to detect fault currents. The within the Power
signal
referred to as "power sensors," and are used.to develop a trip reference
on each phase of
Shield trip unit. Two CTs, a phase sensor and a power sensor, are installed
terminal blocks attached
the circuit breaker. The leads from all six CTs are terminated on three
of the circuit breaker. These
to the front of the moulded CT mounting board near the bottom
trip unit by a
three terminal blocks, in turn, are connected to the Power Shield solid-state
ABB Wiring Diagram
multiconductor wiring harness. Attachment I to this notice is a copy of of the CT
709551, Revision 16, for reference. Attachment 2 to this notice is a photograph Typical
the drawing.
mounting board at the bottom of a K-line breaker to aid in interpreting include the
breakers
wiring and assembly errors that have been discovered in ABB K-line circuit
following:
blocks.
- CT leads were terminated on the wrong terminals of the lower terminal
of the lower
- Multiconductor cable conductors were terminated on the wrong terminals
terminal blocks, or on the wrong terminals of the Power Shield Trip Unit.
terminal
- CTs were installed upside down but were correctly terminated on the lower
blocks (same effect as reversing the leads).
lifted to perform
- After the wires on terminals 6, 7, and 8 of the Power Shield trip unit are
11, 12, 13, and 14 are
continuity checks of the phase sensors, or the wires on terminals
lifted to conduct calibration tests, the wires are relanded incorrectly.
equipment
Circuit breaker wiring or assembly errors can be introduced by the original
services, or utilities during
manufacturer, companies performing circuit breaker refurbishment
in service or stored in
testing. Incorrectly wired or assembled circuit breakers may be currently cannot detect
testing
a warehouse for service at a later date. Because single-phase calibration
for incorrectly wired or
the CT wiring or installation errors described herein, the potential exists
but to trip load
assembled circuit breakers to pass normal single-phase calibration testing
safety-related load
currents less than the desired trip setpoint (e.g., on startup of the breaker's
during a design-basis accident) resulting in a loss of safety functions.
IN 98-03 January 21, 1998 This information notice establishes no new NRC requirements; therefore, no specific action or
written response is required by this notice. However, recipients are reminded that they are
required by 10 CFR 50.65 to take industry-wide operating experience (including information
presented in NRC information notices) into consideration, where practical, when setting goals
and performing periodic evaluations. If you have any questions about the information in this
notice, please contact one of the technical contacts listed below or the appropriate NRR project
manager.
fa Jack W. Roe, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Donald Kosloff, RIII Stephen Alexander, NRR
440-259-3610 301-415-2995 E-mail: dck@nrc.gov E-mail: kmenrc.gov
Virgil Beaston, NRR David Skeen, NRR
301-415-5774 301-415-1174 E-mail: vlbenrc.gov E-mail: dls@nrc.gov
Attachments:
1. ABB K-Line Power Shield Auxiliary Wiring Diagram 709551, Revision 16
2. Photograph of the CT Mounting Board at the Bottom of a K-Line Breaker
. List of Recently Issued NRC Information Notices
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Attachment 2 IN 98-03 January 21. 1998 PHOTOGRAPH OF CT MOUNTING BOARD AT BOTTOM OF K-LINE BREAKER
4 Attachment 3 IN 98-03 January 21, 1998 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
98-02 Nuclear Power Plant Cold 1/21/98 All holders of operating licenses
Weather Problems and for nuclear power reactors
Protective Measures
98-01 Thefts of Portable Gauges 1/15/98 All portable gauge licensees
97-91 Recent Failures of Control 12/31/97 All industrial radiography
Cables Used on Amersham licensees
Model 660 Posilock Radiography
Systems
97-90 Use of Nonconservative 12/30/97 All holders of OLs for nuclear
Acceptance Criteria in power reactors except those
Safety-Related Pump who have ceased operations
Surveillance Tests and have certified that fuel has
been permanently removed from
the vessel
97-89 Distribution of Sources and 12/29/97 All sealed source and device
Devices Without Authorization manufacturers and distributors
97-88 Experiences During Recent 12/16/97 All holders of OLs for pressurized- Steam Generator Inspections water reactors except those who
have permanently ceased
operations and have certified that
fuel has been permanently
removed from the reactor
97-87 Second Retrofit to 12/12/97 All industrial radiography
Industrial Nuclear Company licensees
IR 100 Radiography Camera, to Correct Inconsistency in
10 CFR Part 34 Compatibility
OL = Operating License
CP = Construction Permit
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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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