Nuclear Power Plant Cold Weather Problems and Protective MeasuresML031050304 |
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-98-002, NUDOCS 9801200034 |
Download: ML031050304 (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>. |
K>
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, DC 20555-0001 January 21, 1998 NRC INFORMATION NOTICE 98-02: NUCLEAR POWER PLANT COLD WEATHER
PROBLEMS AND PROTECTIVE MEASURES
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 potential common-cause failure mechanisms of safety-related systems and will
systems important to safety caused by extremely cold weather. It is expected that recipients to
review the information for applicability to their facilities and consider actions, as appropriate,NRC
avoid similar problems. However, suggestions contained in this information notice are not
requirements; therefore, no specific action or written response is required.
Description of Circumstances
Wolf Creek
on
IN 96-36, "Degradation of Cooling Water Systems Due to Icing," described the effects of icing
intake trash racks and traveling screens which resulted in a manual reactor/turbine trip on
January 30, 1996, at Wolf Creek. In addition to the degradation of the circulating water and
essential service water systems, the turbine-driven auxiliary feedwater pump was degraded
during this event. The NRC identified the event as a precursor within the framework of the
NRC's accident sequence precursor program, and calculated a conditional core-damage
probability of 2.1 x 104.
Circulating water system degradation was initially attributed to water from the spray-wash system
freezing on the traveling screens, making them inoperable. To improve the reliability of the
circulating water system, the licensee revised plant procedures (1) to eliminate the requirement
to operate traveling screens continuously in slow manual mode during cold weather or underin
unusual icing conditions and (2) to allow the screens to be operated in the automatic mode
which the screens remained stationary without sprays until the system was started either by a
timer or a high differential level. The traveling screens were also enclosed in a heated
environment.
After IN 96-36 was issued, more information became available about the degradation of the
circulating water system. Specifically, on August 5, 1997, the licensee reported that during the
event, two of three air release valves on the circulating water warming line had been plugged.
A
Ppk TkE ODTe,9g--Oo JgolfI
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IN 98-02 January21, 1998 Failure of these valves caused air binding in the piping and caused the warming
flow to be
nearly zero.
The effect of the resultant air binding was demonstrated during a 5-day test
in January 1997 with 2.8 'C (37 °F) lake water, when warming line flow was reduced from
1388 liters per second
(22,000 gpm) to approximately 347 liters per second (5,500 gpm). This warming
flow
degradation would have been more pronounced during the event because
the temperature of
the lake water was approximately 0 OC (32 OF) during the event and, therefore, contained more
air in solution. Although air removal by the water box venting system should
have significantly
reduced the potential for air binding, approximately one-half of the water box
air release valves
had been isolated during the January. 1996 event.
In response to these findings, the three air release valves on the warming
line were replaced
and incorporated into the preventive maintenance program. The licensee
also revised
procedures to ensure (1) manual venting of the circulating water warming
line when the inlet
temperature fell below 1.1 'C (34 0F), and (2) verification of the presence
of circulating water
warming flow and the passing of air from the air release valves when the warming
line valve
was opened in the fall. A procedural step was also added to verify that the
water box air
release valves were not isolated.
Millstone Unit 2 On January 8, 1996, with the plant at 100-percent power, an ice plug formed
in a horizontal, common, service water (SW) strainer backwash drain line that ran through
the intake wall in a
trough toward a fish basket. This would have prevented automatic backwash
of the SW
strainers. This pipe had been welded onto the end of the original vertical discharge
leg in a
modification that had not undergone a formal engineering review. Minor leakage
through the
strainer backwash isolation valves and an unusually long period of subfreezing
temperatures
created the conditions needed to form the ice plug. Removal of the ice plug
restored the SW
strainer backwash capability and operators backwashed the strainers every
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to ensure
that another ice plug would not form until the horizontal pipe was eliminated.
Nonetheless, the
open end of the line was still susceptible to ice buildup. The licensee later
reported that the
operators had failed to recognize that the ice plug that made the backwash
functions of the SW
strainers inoperable also made both SW system trains inoperable. The
licensee should have
declared the SW system inoperable during the event and entered Technical
Specification
Limiting Condition for Operation 3.0.3, which required a plant shutdown.
On February 29, 1996, the licensee reported that the SW strainer backwash
system was also
susceptible to a common-mode failure if the intake structure's nonvital
heating system failed to
operate. The licensee changed an operating procedure to require (1)
monitoring of the intake
structure temperature when temperature fell below 4.4 OC (40 OF) and (2)
using portable space
heaters or manual operation of the strainers to prevent freezing. The licensee
also proposed
replacing the common line with three independent backwash lines, locating
the discharge points
to minimize the effect of outdoor weather conditions, and protecting differential
pressure
instrumentation from freezing.
IN 98-02 January 21, 1998 LaSalle Unit 2 On February 4, 1996, operators shut the plant down manually when the oil temperature in the
main transformer could not be maintained within design limits because of the loss of the
transformer cooling fan and cooling pump. Ice severed the transformer cooling logic cable in its
conduit where it entered the underground cable trough. Licensee corrective actions included
inspecting other transformer conduits, clearing water and ice from conduits, and sealing the
conduits.
McGuire Unit 2
On February 8, 1996, with the plant at 100 percent power, two of three refueling water storage
tank (RWST) level transmitters were found to be inoperable because of frozen impulse lines.
The lines froze because thermostat setpoints for the strip heaters were set too low for cold
weather conditions. The frozen impulse lines affected control room RWST level indication and
the ability to automatically switch to the emergency core cooling system sump. To correct this
problem, the licensee increased the thermostat setpoint and added inspection of the level
transmitter panels to its cold weather preventive maintenance procedure.
Discussion
The January 1996 event at Wolf Creek, described above, led the NRC Office for the Analysis
and Evaluation of Operational Data (AEOD) to review the extent of cold weather-related
problems at U.S. nuclear power plants over the past 6 years. The results of this study are
given in Engineering Evaluation Report AEOD/E97-03, "Nuclear Power Plant Cold Weather
Problems and Protective Measures." It contains a compendium of recent cold weather-related
events and corrective actions, as well as design, operations, and training lessons learned by
the nuclear industry and the U.S. Army Corps of Engineers Cold Regions Research and
Engineering Laboratory. The report noted 37 cold weather related events at 23 different sites
between 1991 and 1997. The study also reported an increasing trend in the number of these
events.
Licensees continue to find that icing and freezing from extreme cold weather conditions is a
common-cause failure mechanism that can quickly affect a variety of systems unless mitigating
actions are taken in a timely manner. The recent operating experience described in this study
suggests that, despite NRC and industry communications on this subject, some licensees have
not effectively protected components whose failure could degrade safety-related systems and
systems important to safety. Extreme cold weather conditions continued to affect intake
structures; process lines; instrument lines; emergency diesel generator oil and grease
viscosities; essential chillers; electrical systems; and heating, ventilation, and air conditioning
systems. Lack of design oversight, incomplete review of operating experience, and insufficient
attention to cold weather preparations were responsible for most of the events.
IN 98-02 January 21, 1998 This information notice requires no specific action or written response. 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 Office of Nuclear Reactor Regulation project manager.
Jack W. Roe, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contacts: John R. Tappert, NRR
301- 415-1167 E-mail: jrt@nrc.gov
L. Mark Padovan
301- 415-1423 E-mail: Imp@nrc.gov
Robert A. Spence
301- 415-6346 E-mail: ras2@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
"-S 98-02 January 21, 1998 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
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
97-86 Additional Controls for 12/12/97 Registered users of the Model
Transport of the Amersham No. 660 series packages, and
Model No. 660 Series Nuclear Regulatory Commission
Radiographic Exposure Devices industrial radiography licensees
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, Failure to Scram)
- 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, Topic: Water hammer)
- 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, Reactive Inspection)
- 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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