Implementation of 10 CFR 55.55a(g) Inservice Inspection RequirementsML031040543 |
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 ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
12/01/1998 |
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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-98-042, NUDOCS 9811240114 |
Download: ML031040543 (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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Category:NRC Information Notice
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. 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>. |
J
i -
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 December 1, 1998 NRC INFORMATION NOTICE 98-42: IMPLEMENTATION OF 10 CFR 50.55a(g) INSERVICE
INSPECTION REQUIREMENTS
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 to certain aspects of requesting relief from American Society of Mechanical
Engineers Boiler and Pressure Vessel Code (ASME Code) examinations that received less than
essentially 100 percent" coverage. ("Essentially 100 percent" examination is defined as more
than 90 percent of the specified examination volume.) 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 inthis Information notice are not NRC
requirements; therefore, no specific action or written response is required.
Description of Circumstances
It became evident to the NRC staff while it was conducting Inservice inspections (ISI) reviews of
licensees' 90-day ISI reports that some licensees were unaware of, uncertain of, or had
misinterpreted the Title 10 of the Code of Federal Regulations 50.55a(g)(4) (10 CFR
50.55a(g)(4)) requirements regarding the examination of components to the extent practical
within the limitations of design, geometry, and materials of construction of the components.
Licensees should be cognizant of 10 CFR 50.55a(g)(5)(iii) which requires submittal of requests
for relief from paragraph 50.55a(g)(4) when complete examination coverage(s) Is impractical.
Because of the scope and extent of ISI examinations, significant planning Is necessary to
address the technical and regulatory Issues associated with the examinations required by the
ASME Code, to the extent practical, of Class 1, 2, and 3 systems and components.
This information notice contains a discussion of certain areas of misinterpretation that the NRC
staff has dealt with In the Implementation of the 10 CFR 50.55a(g)(4) rule.
98 ) A2li/ ADD In K 58 -oo' 1 14m
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 December 1, 1998 NRC INFORMATION NOTICE 98-42: IMPLEMENTATION OF 10 CFR 50.55a(g) INSERVICE
INSPECTION REQUIREMENTS
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 to certain aspects of requesting relief from American Society of Mechanical
Engineers Boiler and Pressure Vessel Code (ASME Code) examinations that received less than
essentially 100 percent" coverage. ("Essentially 100 percent" examination Is defined as more
than 90 percent of the specified examination volume.) 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
It became evident to the NRC staff while it was conducting inservice Inspections (ISI) reviews of
licensees' 90-day ISI reports that some licensees were unaware of, uncertain of, or had
misinterpreted the Title 10 of the Code of Federal Regulations 50.55a(g)(4) (10 CFR
50.55a(g)(4)) requirements regarding the examination of components to the extent practical
within the limitations of design, geometry, and materials of construction of the components.
Licensees should be cognizant of 10 CFR 50.55a(g)(5)(iii) which requires submittal of requests
for relief from paragraph 50.55a(g)(4) when complete examination coverage(s) Is impractical.
Because of the scope and extent of ISI examinations, significant planning is necessary to
address the technical and regulatory Issues associated with the examinations required by the
ASME Code, to the extent practical, of Class 1, 2, and 3 systems and components.
This information notice contains a discussion of certain areas of misinterpretation that the NRC
staff has dealt with In the Implementation of the 10 CFR 50.55a(g)(4) rule.
- .) ~ IN 98-42 December 1, 1998 Discussion
In 10 CFR 50.55a(g)(5)(iil), It is requested that requests for relief from limited
submitted when it Is Impractical to complete the examination coverage requirements examinations be
Xl of the ASME Code. Recent NRC reviews found that several licensees did of Section
requests for relief from examinations of less than essentially 100 percent coverage.not submit
licensees correctly interpreted 10 CFR 50.55a(g)(4) for Class 1,2, and 3 componentsThe
that they were required to perform the ASME Code examinations to the extent to mean
However, the licensees misinterpreted the requirement to mean that they were practical.
submit requests for relief from examinations that received less than essentially not required to
coverage because they had examined the component to the extent practical. 100 percent
At least one licensee quoted 10 CFR 50.55a(g)(4) as a basis for not seeking
to obtain the required examination coverage. In 10 CFR 50.55a(g)(4) it Isstated, relief when unable
in part, that
components... must meet the requirements... to the extent practical within
design, geometry and materials of construction of the components." However, the limitations of
incomplete or partial ISI examination coverage required by the ASME Code when
Is obtained, NRC
relief Is required pursuant to 10 CFR 50.55a(g)(5)(iii).
During discussions with the NRC staff regarding Its review of a 90-day
was determined that a licensee had obtained "essentially 100 percent" ISI summary report, It
coverage for most
examinations but had obtained coverage of 90 percent or less on several components.
Contrary to the requirements of the rule, the licensee did not submit requests
NRC on the basis of Impracticality before 1 year after the end of the effective for relief to the
required by 10 CFR 50.55a(g)(5)(iv), unti the NRC pointed out this omission. Interval as
'Essentially100 Percent" Examination Standard
After many inquiries and interpretations, ASME Issued ASME Code Case N-460,
Examination Coverage for Class 1 and 2 Welds," Section Xi, Division 1,dated "Alternative
ASME Code Case N-460 states, Inpart, that "when the entire examination July 27, 1988.
volume
cannot be examined. . . a reduction Inexamination coverage ... may be accepted or area
reduction in coverage for that weld Is less than 10 percent. The NRC has adopted provided the
refined the definition of "essentially 100 percent" to mean 'greater than 90 and further
percent" in 10 CFR
50.55a(g)(6)(ii)(A)(2) for required examination coverage of reactor pressure
standard has been applied to all examinations of welds or other areas required vessel welds. This
Section Xi. by ASME
Most licensees are finding that although the overall average examination coverage
may be more than 90 percent, examination coverage for other Individual welds for all welds
substantially less than 90 percent. When a licensee Is unable to examine "essentiallybe may
percent" of each weld, It must seek relief frorn the NRC Inaccordance with 100
50.55a(g)(5)(iii). 10 CFR
- ActIN 98-42 December 1, 1998 This Information notice requires no specific action or written
reminded that they are required to consider Industry-wide response. However, recipients are
Information notices), where practical, when setting goals operating experience (including NRC
and performing periodic evaluations
under 10 CFR 50.65, Requirements for monitoring the
effectiveness
power plants." If you have any questions about the Information of maintenance at nuclear
the technical contact listed below or the appropriate Office In this notice, please contact
of Nuclear Reactor Regulation
(NRR) project manager.
Jt W. Roe, Acting Director
!on of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: Thomas K. McLellan, NRR
301- 415-2716 E-mail: tkm@nrc.gov
Attachment: List of Recently Issued NRC Information
Notices
/jhAi}g> jet
,-Attachment
IN 98-42 December 1, 1998 Page 1 of I
LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
98-41 Spurious Shutdown of Emergency 11/20/98 All holders of operating licenses
Diesel Generators from Design for nuclear power reactors, except
Oversight for those who have ceased
operations and have certified that
fuel has been permanently
removed from the reactor vessel
98-40 Design Deficiencies Can Lead 10/26/98 All holders of operating licenses
Reduced ECCS Pump Net Positive for nuclear power reactors, except
Suction Head During Design-Basis those licensees who have
Accidents permanently ceased operations
and have certified that fuel has
bee permanently removed from
the vessel
98-39 Summary of Fitness-for-Duty 10124/98 All holders of operating licenses
Program Performance Reports for for nuclear power reactors
Calendar Years 1996 and 1997
98-38 Metal-Clad Circuit Breaker 10/15/98 All holders of operating licenses
Maintenance Issued Identified for nuclear power reactors.
By NRC Inspections
98-37 Eligibility of Operator License 10/01/98 All holders of operating licenses
Applicants for nuclear power reactors, except those who have
permanently ceased operations
and have certified that fuel has
been permanently removed from
the reactor vessel.
98-36 Inadequate or Poorly Controlled 9/18198 All holders of operating licenses
Non-Safety-Related Maintenance for nuclear power reactors
Activities Unnecessarily Challenged
Safety Systems
OL = Operating License
CP = Construction Permit
IN 98-42 December 1, 1998 This 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 goals and performing periodic evaluations
under 10 CFR 50.65, Requirements for monitoring the effectiveness of maintenance at nuclear
power plants." If you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear Reactor Regulation
(NRR) project manager
Original signed by
Jack W. Roe, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: Thomas K. McLellan, NRR
301- 415-2716 E-mail: tkm@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME: S:\drpmsec\98-42.in
- - See previous concurrence No copy
Axrg-~S 9 - -4nethi-n rn
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OFFICE PECB:DRPM I TECH ED* I N ECGB:DE Il C:ECGB:DE D:DE l
NAME TGreene* BCalure* TMcLellan* GBagchi* GLainas*
DATE j 11/12198 10/30/98 11/12/98 111/13/98 I II
11/18/98JSfor
T- I I
OFFICF I. PFCR
.________,______.
I C:PECB I D/DRPIA I
NAME RDennig* JStolz* JRoe( LS '
DATE 11/23/98 11/24/98 11 215 /98 AcJ
UOFIUIAL Ktti.UKU oUIrT
IN 98-XX
November XX, 1998 This 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 goals and performing periodic evaluations
under 10 CFR 50.65, Requirements for monitoring the effectiveness of maintenance at nuclear
power plants." If you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear Reactor Regulation
(NRR) project manager
Jack W. Roe, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: Thomas K. McLellan, NRR
301- 415-2716 E-mail: tkm@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\TAGINISI e kt
To receive a coDY of this document. indicate in the box C=Coov wlo attachmentlenclosure E=Copwwith ditachmentlenclosure N = No copy
OFFICE PECB:DRPMl TECH ED* IN ECGB:DE l C D:DE
NAME TGreene (9 BCalure TMcLellan* ) Bagchi GLainap
DATE on /_
OI 98 10/30 /X1_____98
/98 _h J 1598 - 1 /98 .
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OFFICE PECB _,
ni I C:RECB I D1DRPM I
NAME RDennj _
tL) JSto0J-JRoe
DATE {l / 1"-/98 1lI/IL[I98 I /98
- See previous concurrence
OFFICIAL RECORD COPY
- DOCUMENT NAME:
To receive a copy of this document, indicate in the box C=Copy wlo attachment/enclosure E=Copy with attachment/enclosure N = No copy
[OFFICE
NAME
DATE
PECB:DRPM I
T. Greene
I/ /98
_
TECH
ljECGGB:
gi
/6 1/1I98 ED
A T. McLellan
I /98 f[ G. Bagchi
I /98 DE/DEDI
G. Lainas
I /98 OFFICIAL RECORD COPY
OFFICE SC/PECB:DRPM I BC/PECB:DRPM I DIDRPM l
NAME R. Dennig J. Stolz J ..Roe
DATE 1/ 98 I /98 I /98 OFFICIAL RECORD COPY
DOCUMENT NAME: G:\TAG\INISI
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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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