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| {{#Wiki_filter:UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF INSPECTION AND ENFORCEMENTWASHINGTON, D.C. 20555March 21, 1979IE Information Notice No. 79-05USE OF IMPROPER MATERIALS IN SAFETY-RELATED COMPONENTSTwo instances of the addition of Improper materials to safety-relatedcomponents during maintenance have recently been identified by NRCinspections.Materials on Valve Seating SurfacesAn NRC inspector found that maintenance personnel at the Surry nuclearpower plant had added wax or grease to certain valve seating surfaces.These valves included the containment spray and recirculation sprayisolation valves. This material could have affected the measured leakrate through these containment penetrations. VEPCO personnel said thatthe material was believed to have been added to prevent damage to thevalve seating surfaces during dry valve testing. It had not been removedfollowing completion of the maintenance procedure. VEPCO personnel alsoreported that a lack of any definitive administrative guidance as towhat lubricants, if any, could be used during valve maintenance,contributed to this problem. The corrective action included modifica-tion of the procedures to include more precise Inspection by qualitycontrol personnel following valve maintenance.Grease in SnubbersAn NRC inspector found that maintenance personnel at the Browns Ferrynuclear power plant had added grease to the hydraulic fluid reservoirsof eight Bergen-Paterson snubbers. The grease had mistakenly beenadded, during a scheduled lubrication procedure, through the alemitetype fittings used for normal fluid addition. A similar error involvingthirteen snubbers had previously been made at this facility. At thattime the decision had been made to Install a different type of fittingon the snubbers. However, the replacement parts had not arrived in tinefor installation prior to the more recent lubrication. At the time ofthe earlier occurrence, TVA personnel had removed the affected snubbersand tested them for lock-up and bleed rate. The results had been withinspecification. Nevertheless, the units had been disassembled and cleanedprior to reinstallation. NRC inspectors witnessed the disassembly of oneof the later set of greased snubbers (a four-inch unit). Approximatelyone cubic inch of grease was found in the reservoir. Although the grease 9038001 80 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY |
| IE Information Notice No. 79-05March 21, 1979Grease in Snubbers (continued)had been in the reservoir for only four days, and stroking cf thesnubbers was limited to that which occurred during its removal,grease was found in the control valve assembly and the snubbercylinder. All of the recently greased snubbers were replaced byspare units.These two occurrences illustrate the necessity of controllingconstruction and maintenance practices through the use of care-fully developed procedures designed to prevent errors, such as theintroduction of foreign materials into safety-related components.This information is provided as a notification of a possibly significantmatter. It is expected that recipients will review the information forpossible applicability to their facilities. No specific action or responseis requested at this time. If further NRC evaluations so indicate, an IECircular or Bulletin will be issued to recommend or request soecific li-censee actions. If you have questions regarding this matter, pleasecontact the Director of the appropriate NRC Regional Office.Enclosure:Listing of IE InformationNotices Issued in 1979 IE InformationMarch 21, 1979Notice No. 79-05LISTING OF IE INFORMATION NOTICESISSUED IN 1979InformationNotice No.SubjectDateIssued79-0179-0279-0379-0479-05Bergen-Paterson HydraulicShock and Sway ArrestorAttempted Extortion -Low Enriched UraniumLimitorque Valve GearedLimit Switch LubricantDegradation ofEngineeredSafety FeaturesUse of Improper Materialsin Safety-RelatedComponents2/2/792/2/792/9/79Issued To .All power reactorfacilities with anOL or a CPAll Fuel FacilitiesAll power reactorfacilities with anOL or a CP2/16/79 All power reactorfacilities with anOL or a CP3/21/79 All power reactorfacilities with anOL or CP }} | | |
| | COMMISSION |
| | |
| | OFFICE OF INSPECTION |
| | |
| | ===AND ENFORCEMENT=== |
| | WASHINGTON, D.C. 20555 March 21, 1979 IE Information |
| | |
| | Notice No. 79-05 USE OF IMPROPER MATERIALS |
| | |
| | IN SAFETY-RELATED |
| | |
| | COMPONENTS |
| | |
| | Two instances |
| | |
| | of the addition of Improper materials |
| | |
| | to safety-related |
| | |
| | components |
| | |
| | during maintenance |
| | |
| | have recently been identified |
| | |
| | by NRC inspections. |
| | |
| | Materials |
| | |
| | on Valve Seating Surfaces An NRC inspector |
| | |
| | found that maintenance |
| | |
| | personnel |
| | |
| | at the Surry nuclear power plant had added wax or grease to certain valve seating surfaces.These valves included the containment |
| | |
| | spray and recirculation |
| | |
| | spray isolation |
| | |
| | valves. This material could have affected the measured leak rate through these containment |
| | |
| | penetrations. |
| | |
| | VEPCO personnel |
| | |
| | said that the material was believed to have been added to prevent damage to the valve seating surfaces during dry valve testing. It had not been removed following |
| | |
| | completion |
| | |
| | of the maintenance |
| | |
| | procedure. |
| | |
| | VEPCO personnel |
| | |
| | also reported that a lack of any definitive |
| | |
| | administrative |
| | |
| | guidance as to what lubricants, if any, could be used during valve maintenance, contributed |
| | |
| | to this problem. The corrective |
| | |
| | action included modifica-tion of the procedures |
| | |
| | to include more precise Inspection |
| | |
| | by quality control personnel |
| | |
| | following |
| | |
| | valve maintenance. |
| | |
| | Grease in Snubbers An NRC inspector |
| | |
| | found that maintenance |
| | |
| | personnel |
| | |
| | at the Browns Ferry nuclear power plant had added grease to the hydraulic |
| | |
| | fluid reservoirs |
| | |
| | of eight Bergen-Paterson |
| | |
| | snubbers. |
| | |
| | The grease had mistakenly |
| | |
| | been added, during a scheduled |
| | |
| | lubrication |
| | |
| | procedure, through the alemite type fittings used for normal fluid addition. |
| | |
| | A similar error involving thirteen snubbers had previously |
| | |
| | been made at this facility. |
| | |
| | At that time the decision had been made to Install a different |
| | |
| | type of fitting on the snubbers. |
| | |
| | However, the replacement |
| | |
| | parts had not arrived in tine for installation |
| | |
| | prior to the more recent lubrication. |
| | |
| | At the time of the earlier occurrence, TVA personnel |
| | |
| | had removed the affected snubbers and tested them for lock-up and bleed rate. The results had been within specification. |
| | |
| | Nevertheless, the units had been disassembled |
| | |
| | and cleaned prior to reinstallation. |
| | |
| | NRC inspectors |
| | |
| | witnessed |
| | |
| | the disassembly |
| | |
| | of one of the later set of greased snubbers (a four-inch |
| | |
| | unit). Approximately |
| | |
| | one cubic inch of grease was found in the reservoir. |
| | |
| | Although the grease 29038001 80 |
| | IE Information |
| | |
| | Notice No. 79-05 March 21, 1979 Grease in Snubbers (continued) |
| | had been in the reservoir |
| | |
| | for only four days, and stroking cf the snubbers was limited to that which occurred during its removal, grease was found in the control valve assembly and the snubber cylinder. |
| | |
| | All of the recently greased snubbers were replaced by spare units.These two occurrences |
| | |
| | illustrate |
| | |
| | the necessity |
| | |
| | of controlling |
| | |
| | construction |
| | |
| | and maintenance |
| | |
| | practices |
| | |
| | through the use of care-fully developed |
| | |
| | procedures |
| | |
| | designed to prevent errors, such as the introduction |
| | |
| | of foreign materials |
| | |
| | into safety-related |
| | |
| | components. |
| | |
| | This information |
| | |
| | is provided as a notification |
| | |
| | of a possibly significant |
| | |
| | matter. It is expected that recipients |
| | |
| | will review the information |
| | |
| | for possible applicability |
| | |
| | to their facilities. |
| | |
| | No specific action or response is requested |
| | |
| | at this time. If further NRC evaluations |
| | |
| | so indicate, an IE Circular or Bulletin will be issued to recommend |
| | |
| | or request soecific li-censee actions. If you have questions |
| | |
| | regarding |
| | |
| | this matter, please contact the Director of the appropriate |
| | |
| | NRC Regional Office.Enclosure: |
| | |
| | ===Listing of IE Information=== |
| | Notices Issued in 1979 IE Information |
| | |
| | March 21, 1979 Notice No. 79-05 LISTING OF IE INFORMATION |
| | |
| | ===NOTICES ISSUED IN 1979 Information=== |
| | Notice No.Subject Date Issued 79-01 79-02 79-03 79-04 79-05 Bergen-Paterson |
| | |
| | Hydraulic Shock and Sway Arrestor Attempted |
| | |
| | Extortion |
| | |
| | -Low Enriched Uranium Limitorque |
| | |
| | Valve Geared Limit Switch Lubricant Degradation |
| | |
| | of Engineered |
| | |
| | Safety Features Use of Improper Materials in Safety-Related |
| | |
| | Components |
| | |
| | 2/2/79 2/2/79 2/9/79 Issued To .All power reactor facilities |
| | |
| | with an OL or a CP All Fuel Facilities |
| | |
| | All power reactor facilities |
| | |
| | with an OL or a CP 2/16/79 All power reactor facilities |
| | |
| | with an OL or a CP 3/21/79 All power reactor facilities |
| | |
| | with an OL or CP }} |
|
| |
|
| {{Information notice-Nav}} | | {{Information notice-Nav}} |
|
---|
Category:NRC Information Notice
MONTHYEARInformation Notice 2006-04, Design Deficiency in Pressurizer Heaters for Pwrs2006-02-13013 February 2006 Design Deficiency in Pressurizer Heaters for Pwrs Information Notice 2006-04, Design Deficiency in Pressurizer Heaters for PWRs2006-02-13013 February 2006 Design Deficiency in Pressurizer Heaters for PWRs Information Notice 1999-28, Recall of Star Brand Fire Protection Sprinkler Heads1999-09-30030 September 1999 Recall of Star Brand Fire Protection Sprinkler Heads Information Notice 1999-27, Malfunction of Source Retraction Mechanism in Cobalt-60 Teletherapy Treatment Units1999-09-0202 September 1999 Malfunction of Source Retraction Mechanism in Cobalt-60 Teletherapy Treatment Units Information Notice 1999-26, Safety and Economic Consequences of Misleading Marketing Information1999-08-24024 August 1999 Safety and Economic Consequences of Misleading Marketing Information Information Notice 1999-25, Year 2000 Contingency Planning Activities1999-08-10010 August 1999 Year 2000 Contingency Planning Activities Information Notice 1999-24, Broad-Scope Licensees' Responsibilities for Reviewing and Approving Unregistered Sealed Sources and Devices1999-07-12012 July 1999 Broad-Scope Licensees' Responsibilities for Reviewing and Approving Unregistered Sealed Sources and Devices Information Notice 1999-23, Safety Concerns Related to Repeated Control Unit Failures of the Nucletron Classic Model High-Dose-Rate Remote Afterloading Brachytherapy Devices1999-07-0606 July 1999 Safety Concerns Related to Repeated Control Unit Failures of the Nucletron Classic Model High-Dose-Rate Remote Afterloading Brachytherapy Devices Information Notice 1999-20, Contingency Planning for the Year 2000 Computer Problem1999-06-25025 June 1999 Contingency Planning for the Year 2000 Computer Problem Information Notice 1999-21, Recent Plant Events Caused by Human Performance Errors1999-06-25025 June 1999 Recent Plant Events Caused by Human Performance Errors Information Notice 1999-22, 10CFR 34.43(a)(1); Effective Date for Radiographer Certification and Plans for Enforcement Discretion1999-06-25025 June 1999 10CFR 34.43(a)(1); Effective Date for Radiographer Certification and Plans for Enforcement Discretion Information Notice 1999-19, Rupture of the Shell Side of a Feedwater Heater at the Point Beach Nuclear Plant1999-06-23023 June 1999 Rupture of the Shell Side of a Feedwater Heater at the Point Beach Nuclear Plant Information Notice 1999-18, Update on Nrc'S Year 2000 Activities for Material Licensees and Fuel Cycle Licensees and Certificate Holders1999-06-14014 June 1999 Update on Nrc'S Year 2000 Activities for Material Licensees and Fuel Cycle Licensees and Certificate Holders Information Notice 1999-17, Problems Associated with Post-Fire Safe-Shutdown Circuit Analyses1999-06-0303 June 1999 Problems Associated with Post-Fire Safe-Shutdown Circuit Analyses Information Notice 1999-16, Federal Bureau of Investigation'S Nuclear Site Security Program1999-05-28028 May 1999 Federal Bureau of Investigation'S Nuclear Site Security Program Information Notice 1999-15, Misapplication for 10CFR Part 71 Transportation Shipping Cask Licensing Basis to 10CFR Part 50 Design Basis1999-05-27027 May 1999 Misapplication for 10CFR Part 71 Transportation Shipping Cask Licensing Basis to 10CFR Part 50 Design Basis Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick1999-05-0505 May 1999 Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick Information Notice 1999-13, Insights from NRC Inspections of Low-and Medium-Voltage Circuit Breaker Maintenance Programs1999-04-29029 April 1999 Insights from NRC Inspections of Low-and Medium-Voltage Circuit Breaker Maintenance Programs Information Notice 1999-12, Year 2000 Computer Systems Readiness Audits1999-04-28028 April 1999 Year 2000 Computer Systems Readiness Audits Information Notice 1999-11, Incidents Involving the Use of Radioactive Iodine-1311999-04-16016 April 1999 Incidents Involving the Use of Radioactive Iodine-131 Information Notice 1999-08, Urine Specimen Adulteration1999-03-26026 March 1999 Urine Specimen Adulteration Information Notice 1999-09, Problems Encountered When Manually Editing Treatment Data on the Nucletron Microselectron-HDR (New) Model 105-9991999-03-24024 March 1999 Problems Encountered When Manually Editing Treatment Data on the Nucletron Microselectron-HDR (New) Model 105-999 Information Notice 1999-07, Failed Fire Protection Deluge Valves & Potential Testing Deficiencies in Preaction Sprinkler Systems1999-03-22022 March 1999 Failed Fire Protection Deluge Valves & Potential Testing Deficiencies in Preaction Sprinkler Systems Information Notice 1999-06, 1998 Enforcement Sanctions as a Result of Deliberate Violations of NRC Employee Protection Requirements1999-03-19019 March 1999 1998 Enforcement Sanctions as a Result of Deliberate Violations of NRC Employee Protection Requirements Information Notice 1999-06, 1998 Enforcement Sanctions As a Result of Deliberate Violations of NRC Employee Protection Requirements1999-03-19019 March 1999 1998 Enforcement Sanctions As a Result of Deliberate Violations of NRC Employee Protection Requirements Information Notice 1999-05, Inadvertent Discharge of Carbon Dioxide Fire Protection System and Gas Migration1999-03-0808 March 1999 Inadvertent Discharge of Carbon Dioxide Fire Protection System and Gas Migration Information Notice 1999-04, Unplanned Radiation Exposures to Radiographers, Resulting from Failures to Follow Proper Radiation Safety Procedures1999-03-0101 March 1999 Unplanned Radiation Exposures to Radiographers, Resulting from Failures to Follow Proper Radiation Safety Procedures Information Notice 1999-03, Exothermic Reactors Involving Dried Uranium Oxide Powder (Yellowcake)1999-01-29029 January 1999 Exothermic Reactors Involving Dried Uranium Oxide Powder (Yellowcake) Information Notice 1999-02, Guidance to Users on the Implementation of a New Single-Source Dose-Calculation Formalism and Revised Air-Kerma Strength Standard for Iodine-125 Sealed Sources1999-01-21021 January 1999 Guidance to Users on the Implementation of a New Single-Source Dose-Calculation Formalism and Revised Air-Kerma Strength Standard for Iodine-125 Sealed Sources Information Notice 1999-01, Deterioration of High-Efficiency Particulate Air Filters in a Pressurized Water Reactor Containment Fan Cooler Unit1999-01-20020 January 1999 Deterioration of High-Efficiency Particulate Air Filters in a Pressurized Water Reactor Containment Fan Cooler Unit Information Notice 1998-45, Cavitation Erosion of Letdown Line Orifices Resulting in Fatigue Cracking of Pipe Welds1998-12-15015 December 1998 Cavitation Erosion of Letdown Line Orifices Resulting in Fatigue Cracking of Pipe Welds Information Notice 1998-44, Ten-Year Inservice Inspection (ISI) Program Update for Licensees That Intend to Implement Risk-Informed ISI of Piping1998-12-10010 December 1998 Ten-Year Inservice Inspection (ISI) Program Update for Licensees That Intend to Implement Risk-Informed ISI of Piping Information Notice 1998-43, Leaks in Emergency Diesel Generator Lubricating Oil & Jacket Cooling Water Piping1998-12-0404 December 1998 Leaks in Emergency Diesel Generator Lubricating Oil & Jacket Cooling Water Piping Information Notice 1998-42, Implementation of 10 CFR 55.55a(g) Inservice Inspection Requirements1998-12-0101 December 1998 Implementation of 10 CFR 55.55a(g) Inservice Inspection Requirements Information Notice 1998-41, Spurious Shutdown of Emergency Diesel Generators from Design Oversight1998-11-20020 November 1998 Spurious Shutdown of Emergency Diesel Generators from Design Oversight Information Notice 1998-41, Spurious Shutdown of Emergency Diesel Generators From Design Oversight1998-11-20020 November 1998 Spurious Shutdown of Emergency Diesel Generators From Design Oversight Information Notice 1998-39, Summary of Fitness-for-Duty Program Performance Reports for Calendar Years 1996 and 19971998-10-30030 October 1998 Summary of Fitness-for-Duty Program Performance Reports for Calendar Years 1996 and 1997 Information Notice 1998-40, Design Deficiencies Can Lead to Reduced ECCS Pump Net Positive Suction Head During Design-Basis Accidents1998-10-26026 October 1998 Design Deficiencies Can Lead to Reduced ECCS Pump Net Positive Suction Head During Design-Basis Accidents Information Notice 1990-66, Incomplete Draining and Drying of Shipping Casks1998-10-25025 October 1998 Incomplete Draining and Drying of Shipping Casks Information Notice 1998-38, Metal-Clad Circuit Breaker Maintenance Issues Identified by NRC Inspections1998-10-15015 October 1998 Metal-Clad Circuit Breaker Maintenance Issues Identified by NRC Inspections Information Notice 1998-37, Eligibility of Operator License Applicants1998-10-0101 October 1998 Eligibility of Operator License Applicants Information Notice 1998-36, Inadequate or Poorly Controlled, Non-Safety-Related Maintenance Activities Unnecessarily Challenged Safety Systems1998-09-18018 September 1998 Inadequate or Poorly Controlled, Non-Safety-Related Maintenance Activities Unnecessarily Challenged Safety Systems Information Notice 1998-34, Configuration Control Errors1998-08-28028 August 1998 Configuration Control Errors Information Notice 1998-33, NRC Regulations Prohibit Agreements That Restrict or Discourage an Employee from Participating in Protected Activities1998-08-28028 August 1998 NRC Regulations Prohibit Agreements That Restrict or Discourage an Employee from Participating in Protected Activities Information Notice 1998-31, Fire Protection System Design Deficiencies and Common-Mode Flooding of Emergency Core Cooling System Rooms at Washington Nuclear Project Unit 21998-08-18018 August 1998 Fire Protection System Design Deficiencies and Common-Mode Flooding of Emergency Core Cooling System Rooms at Washington Nuclear Project Unit 2 Information Notice 1998-30, Effect of Year 2000 Computer Problem on NRC Licensees and Certificate Holders1998-08-12012 August 1998 Effect of Year 2000 Computer Problem on NRC Licensees and Certificate Holders Information Notice 1998-29, Predicted Increase in Fuel Rod Cladding Oxidation1998-08-0303 August 1998 Predicted Increase in Fuel Rod Cladding Oxidation Information Notice 1998-28, Development of Systematic Sample Plan for Operator Licensing Examinations1998-07-31031 July 1998 Development of Systematic Sample Plan for Operator Licensing Examinations Information Notice 1998-26, Settlement Monitoring and Inspection of Plant Structures Affected by Degradation of Porous Concrete Subfoundations1998-07-24024 July 1998 Settlement Monitoring and Inspection of Plant Structures Affected by Degradation of Porous Concrete Subfoundations Information Notice 1998-27, Steam Generator Tube End Cracking1998-07-24024 July 1998 Steam Generator Tube End Cracking 2006-02-13
[Table view] |
UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF INSPECTION
AND ENFORCEMENT
WASHINGTON, D.C. 20555 March 21, 1979 IE Information
Notice No. 79-05 USE OF IMPROPER MATERIALS
IN SAFETY-RELATED
COMPONENTS
Two instances
of the addition of Improper materials
to safety-related
components
during maintenance
have recently been identified
by NRC inspections.
Materials
on Valve Seating Surfaces An NRC inspector
found that maintenance
personnel
at the Surry nuclear power plant had added wax or grease to certain valve seating surfaces.These valves included the containment
spray and recirculation
spray isolation
valves. This material could have affected the measured leak rate through these containment
penetrations.
VEPCO personnel
said that the material was believed to have been added to prevent damage to the valve seating surfaces during dry valve testing. It had not been removed following
completion
of the maintenance
procedure.
VEPCO personnel
also reported that a lack of any definitive
administrative
guidance as to what lubricants, if any, could be used during valve maintenance, contributed
to this problem. The corrective
action included modifica-tion of the procedures
to include more precise Inspection
by quality control personnel
following
valve maintenance.
Grease in Snubbers An NRC inspector
found that maintenance
personnel
at the Browns Ferry nuclear power plant had added grease to the hydraulic
fluid reservoirs
of eight Bergen-Paterson
snubbers.
The grease had mistakenly
been added, during a scheduled
lubrication
procedure, through the alemite type fittings used for normal fluid addition.
A similar error involving thirteen snubbers had previously
been made at this facility.
At that time the decision had been made to Install a different
type of fitting on the snubbers.
However, the replacement
parts had not arrived in tine for installation
prior to the more recent lubrication.
At the time of the earlier occurrence, TVA personnel
had removed the affected snubbers and tested them for lock-up and bleed rate. The results had been within specification.
Nevertheless, the units had been disassembled
and cleaned prior to reinstallation.
NRC inspectors
witnessed
the disassembly
of one of the later set of greased snubbers (a four-inch
unit). Approximately
one cubic inch of grease was found in the reservoir.
Although the grease 29038001 80
IE Information
Notice No. 79-05 March 21, 1979 Grease in Snubbers (continued)
had been in the reservoir
for only four days, and stroking cf the snubbers was limited to that which occurred during its removal, grease was found in the control valve assembly and the snubber cylinder.
All of the recently greased snubbers were replaced by spare units.These two occurrences
illustrate
the necessity
of controlling
construction
and maintenance
practices
through the use of care-fully developed
procedures
designed to prevent errors, such as the introduction
of foreign materials
into safety-related
components.
This information
is provided as a notification
of a possibly significant
matter. It is expected that recipients
will review the information
for possible applicability
to their facilities.
No specific action or response is requested
at this time. If further NRC evaluations
so indicate, an IE Circular or Bulletin will be issued to recommend
or request soecific li-censee actions. If you have questions
regarding
this matter, please contact the Director of the appropriate
NRC Regional Office.Enclosure:
Listing of IE Information
Notices Issued in 1979 IE Information
March 21, 1979 Notice No. 79-05 LISTING OF IE INFORMATION
NOTICES ISSUED IN 1979 Information
Notice No.Subject Date Issued 79-01 79-02 79-03 79-04 79-05 Bergen-Paterson
Hydraulic Shock and Sway Arrestor Attempted
Extortion
-Low Enriched Uranium Limitorque
Valve Geared Limit Switch Lubricant Degradation
of Engineered
Safety Features Use of Improper Materials in Safety-Related
Components
2/2/79 2/2/79 2/9/79 Issued To .All power reactor facilities
with an OL or a CP All Fuel Facilities
All power reactor facilities
with an OL or a CP 2/16/79 All power reactor facilities
with an OL or a CP 3/21/79 All power reactor facilities
with an OL or CP
|
---|
|
list | - Information Notice 1979-01, Bergen-Paterson Hydraulic Shock & Sway Arrestors (Hssa) (2 February 1979)
- Information Notice 1979-01, Bergen-Paterson Hydraulic Shock & Sway Arrestors (HSSA) (2 February 1979)
- Information Notice 1979-03, Limitorque Valve Geared Limit Switch Lubricant (9 February 1979)
- Information Notice 1979-04, Degradation of Engineered Safety Features (16 February 1979)
- Information Notice 1979-05, Use of Improper Materials in Safety-Related Components (21 March 1979)
- Information Notice 1979-06, Stress Analysis of Safety-Related Piping (23 March 1979, Topic: Earthquake)
- Information Notice 1979-07, Rupture of Radwaste Tanks (26 March 1979)
- Information Notice 1979-08, Interconnection of Contaminated Systems with Service Air Systems Used as Source of Breathing Air (28 March 1979)
- Information Notice 1979-08, Interconnection of Contaminated Systems With Service Air Systems Used As Source of Breathing Air (28 March 1979)
- Information Notice 1979-09, Spill of Radioactively Contaminated Resin (30 March 1979, Topic: Hydrostatic)
- Information Notice 1979-19, Pipe Cracks in Stagnant Borated Water Systems at PWR Plants (17 July 1979, Topic: Boric Acid, Hydrostatic, Liquid penetrant)
- Information Notice 1979-20, NRC Enforcement Policy - NRC Licensed Individuals (7 September 1979)
- Information Notice 1979-21, Transportation & Commercial Burial of Radioactive Material (7 September 1979)
- Information Notice 1979-22, Qualification of Control Systems (14 September 1979)
- Information Notice 1979-24, Overpressurization of Containment of a PWR Plant After a Main Steam Line Break (1 October 1979)
- Information Notice 1979-25, Reactor Trips at Turkey Point Units 3 & 4 (1 October 1979)
- Information Notice 1979-26, Breach of Containment Integrity (5 November 1979)
- Information Notice 1979-28, Overloading of Structural Elements Due to Pipe Support Loads (16 November 1979)
- Information Notice 1979-29, Loss of Nonsafety-Related Reactor Coolant System Instrumentation During Operation (16 November 1979)
- Information Notice 1979-30, Reporting of Defects & Noncompliances, 10 CFR Part 21 (6 December 1979)
- Information Notice 1979-31, Use of Incorrect Amplified Response Spectra (13 December 1979)
- Information Notice 1979-32, Separation of Electrical Cables for HPCI and ADS (21 December 1979, Topic: Fire Watch)
- Information Notice 1979-33, Improper Closure of Primary Containment Equipment Access Matches (21 December 1979)
- Information Notice 1979-34, Inadequate Design of Safety-Related Heat Exchangers (27 December 1979)
- Information Notice 1979-35, Control of Maintenance & Essential Equipment (31 December 1979)
- Information Notice 1979-36, Computer Code Defect in Stress Analysis of Piping Elbow (31 December 1979)
- Information Notice 1979-37, Cracking in Low Pressure Turbine Discs (28 December 1979, Topic: Turbine Missile)
|
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