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| {{#Wiki_filter:UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, January 21, 2004NRC INFORMATION NOTICE 2004-01:AUXILIARY FEEDWATER PUMPRECIRCULATION LINE ORIFICE FOULING - | | {{#Wiki_filter:UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, January 21, 2004NRC INFORMATION NOTICE 2004-01:AUXILIARY FEEDWATER PUMPRECIRCULATION LINE ORIFICE FOULING - |
| POTENTIAL COMMON CAUSE FAILURE | | |
| | ===POTENTIAL COMMON CAUSE FAILURE=== |
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| ==Addressees== | | ==Addressees== |
Revision as of 06:58, 19 February 2018
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Category:NRC Information Notice
MONTHYEARInformation Notice 2011-17, Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping2011-07-26026 July 2011 Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping Information Notice 2007-06, Potential Common Cause Vulnerabilities in Essential Service Water Systems2007-02-0909 February 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Information Notice 2006-31, Inadequate Fault Interrupting Rating of Breakers2006-12-26026 December 2006 Inadequate Fault Interrupting Rating of Breakers Information Notice 2004-01, Auxiliary Feedwater Pump Recirculation Line Orifice Fouling - Potential Common Cause Failure2004-01-21021 January 2004 Auxiliary Feedwater Pump Recirculation Line Orifice Fouling - Potential Common Cause Failure 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 2011-07-26
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UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, January 21, 2004NRC INFORMATION NOTICE 2004-01:AUXILIARY FEEDWATER PUMPRECIRCULATION LINE ORIFICE FOULING -
POTENTIAL COMMON CAUSE FAILURE
Addressees
- All holders of operating licenses or construction permits for nuclear power reactors, exceptthose that have permanently ceased operations and have certified that fuel has been permanently removed from the reactor.
Purpose
- The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to informaddressees of the potential common cause failure of auxiliary feedwater pumps because of fouling of pump recirculation line flow orifice 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 in this information notice are not NRC requirements; therefore no specific action or written response is required.Background:Point Beach Nuclear Plant (PBNP) is a two unit sit Each unit has a turbine-driven AFW pump(pumps 1P29 and 2P29) which can supply water to both steam generator Additionally, the plant has two motor-driven AFW pumps (pumps P38A and P38B) each of which can be aligned to a steam generator in each uni Each pump has a recirculation line back to the condensate storage tanks (CSTs) to ensure minimum flow to prevent hydraulic instabilities and dissipate pump hea The recirculation line contained a pressure reducing, flow restricting orific An arrow is pointing to the recirculation flow restricting orifice (RO) in the major flow path AFW diagram provided in Figure 1 and a picture of the RO is provided in Figure The RO used a multi-stage, anti-cavitation trim package installed in the body of a globe valve tolimit flo This style of orifice or flow restrictor was installed in the AFW recirculation lines at PBNP in the past few years to eliminate cavitation caused by the old orifice This type of flow restrictor used very small channels and holes in each stage combined with a tortuous path to limit flow and prevent cavitation. Figure AFW System - Major Flow PathsFigure Recirculation Flow Restricting Orifice
Description of Circumstances
- On October 24, 2002, during post-maintenance surveillance testing of the P38A motor-drivenAFW pump at PBNP, the licensee observed AFW recirculation line flow to be 64.5 gpm, which was less than the 70 gpm acceptance criterio Normal flow through the recirculation line was 75 gp Suspecting instrument error, plant personnel vented and recalibrated the flow instrumen The P38A AFW pump was then started and tested again; however, the observed recirculation flow was essentially unchange Following that test run, the recirculation flow orifice was removed and inspecte After removal of the orifice internals, partial blockage was observed in 24 of the 54 holes in theoutermost sleev No particles were found on any of the inner sleeve Samples of the particles removed from the orifice were retained for analysi A boroscope inspection of the recirculation piping at the orifice location revealed no evidence of debri Following cleaning and reassembly, the orifice was reinstalled and the P38A AFW pump was successfully reteste Testing was successfully completed on the other three AFW pumps to verify acceptable recirculation flow by October 25, 2002.During the next several days, PBNP personnel evaluated the implications of the orifice pluggingeven An apparent cause evaluation was initiated with specific directions to assess and evaluate the potential extent of conditio An action plan was developed to identify the source of the debris found in the orifice and to determine what other testing or flushing would be required to assure that future plugging did not occur. As the investigations continued, questions developed concerning the operability of the AFWsystem while supplied by its safety-related water supply, the service water (SW) syste Although the service water supply was provided through a basket strainer, it was recognized that the strainer mesh was larger than the much finer RO channel holes and could allow debris to pass that could clog the R These concerns culminated in a meeting on October 29, 2002, at which PBNP personnel concluded that there was no longer a reasonable assurance that operation of the AFW system using its safety-related suction source of service water would not result in potential AFW recirculation line orifice clogging.In a worst case scenario, Point Beach personnel determined that it may be possible, althoughunlikely, for each of the four flow control orifices, each associated with one of the four AFW pumps, to restrict the flow through the associated recirculation lin Under such conditions, it was hypothesized that if the discharge valves for the AFW pumps were throttled, adequate flow might be unavailable through the recirculation line and pump damage could occur due to overheating.On October 29, 2002, all four AFW pumps were declared inoperabl Both units entered theirtechnical specification action statements and required actions which directs immediate action to restore an AFW system to operable statu Immediate corrective actions consisted of briefing the on-shift crew of the potential consequences of restricted recirculation flow and initiating procedure change The operators were also directed to secure a running AFW pump if the pump discharge flows should be decreased to less than 50 gpm for the motor-driven pumps or 75 gpm for the turbine-driven pump These flow rates were substantially above the point at which pump damage could occur. Information tags were placed at the AFW pump flow indicators on the main control boards to convey that informatio With these administrative controls in place, operations declared the AFW system operable, about four hours after the pumps had been declared inoperabl An incident investigation was initiated to collect andconfirm the facts of this event description beginning with the discovery of the P-38A AFW pump degraded recirculation flow during post-maintenance testing and concluding with the decision to declare the AFW system inoperable.In accordance with 10 CFR 50.72(b)(3)(v), an eight-hour ENS notification (EN #39330) wasmade on October 29, 200 The LER is available in ADAMS (Accession Number ML032890115).A PBNP multi-discipline event resolution team was formed to identify and resolve the issuesassociated with the discovery of this conditio Activities included initiation of a root cause evaluation (RCE) to determine the root and contributing causes for the postulated common-mode failure that would render all AFW pump recirculation lines with restricted flow rate The RCE concluded that this event had a direct root cause and an organizational root caus The direct root cause was the failure by design engineering to properly evaluate the potential for orifice plugging within the design proces Instead of revisiting the design for adequacy and evaluating the potential for plugging of the proposed orifices within the rigor of the design process, the 10 CFR 50.59 safety evaluation was revised to justify the proposed desig The organizational root cause was less than adequate management oversight of the design modification proces Also, in January and February 2003, a specially fabricated orifice was tested at a contractorlaboratory in an effort to determine a plugging probability with service wate Definitive testing occurred on February 21 when a debris mixture of sand, silt, and zebra mussel shells, representative of what would exist in the Point Beach SW system, was injected into a closed loop configuration of piping, an orifice, and a centrifugal pum The orifice plugged in much less than one minute after the mixture was injected into the loo These results were contrary to those of a previously performed computational particle fouling model analysis that indicated that plugging was unlikely because of the particle size distribution of debris in SW and the shear forces in the holes and channels of the orifices developed with the minimum flow required through the orifice for pump coolin Discussion:A special inspection was conducted by the NRC to evaluate the facts, circumstances, andlicensee actions, and documented in NRC Inspection Report 50-266/02-15 and 50-301/02-15 (Accession Number ML030920128). This issue was determined to be of Yellow risk significance for Unit 1, an issue with substantial importance to safety, and Red risk significance for Unit 2, an issue of high importance to safet The difference in significance between the Units was a result of the longer period of time that the AFW recirculation line pressure reduction orifices were installed in Unit (See Final Determination Letter, dated December 11, 2003,Accession Number ML033490022). This information notice requires no specific action or written respons If you have anyquestions regarding the information notice, please contact the technical contacts listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager./Original signed by: Terrence Reis/William D. Beckner, Chief Reactor Operations Branch Division of Inspection Program Management Office of Nuclear Reactor RegulationTechnical contacts:Jerry Dozier, NRRPaul Krohn, Region III(301) 415-1014(920) 755-2309 E-mail: jxd@nrc.govE-mail: pgk1@nrc.gov
Attachment:
List of Recently Issued NRC Information Notices This information notice requires no specific action or written respons If you have anyquestions regarding the information notice, please contact the technical contacts listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager./Original signed by: Terrence Reis/William D. Beckner, Chief Reactor Operations Branch Division of Inspection Program Management Office of Nuclear Reactor RegulationTechnical contacts:Jerry Dozier, NRRPaul Krohn, Region III(301) 415-1014(920) 755-2309 E-mail: jxd@nrc.govE-mail: pgk1@nrc.gov
Attachment:
List of Recently Issued NRC Information NoticesDISTRIBUTION:ADAMS IN FileDOCUMENT NAME: G:\RORP\OES\Staff Folders\Dozier\InformationNoticeonPointBeachOrifice.wpdAdams Accession No.:ML040140460OFFICEOES:IROB:DIPMTech EditorDLPMSRI:RIIINAMEIJDozierPKleeneDWSpauldingPKrohnDATE12/03/200312/09/200301/14/200401/13/2004OFFICEBC:RIIISC:OES:IROB:DIPMC:IROB:DIPMNAMEAVegelTReisWDBecknerDATE01/13 /200401/14/200401/21/2004OFFICIAL RECORD COPY
______________________________________________________________________________________OL = Operating License CP = Construction PermitAttachment LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICES_____________________________________________________________________________________InformationDate of Notice N SubjectIssuanceIssued to_____________________________________________________________________________________2002-26, Sup 2Additional Failure of SteamDryer After A Recent Power Uprate01/09/2004All holders of an operating licenseor a construction permit for nuclear power reactors, except those that have permanently ceased operations and have certified that fuel has been permanently removed from the reactor.2003-11, Sup 1Leakage Found on Bottom-Mounted Instrumentation Nozzles01/08/2004All holders of operating licensesor construction permits for nuclear power reactors, except those that have permanently ceased operations and have certified that fuel has been permanently removed from the reactor.2003-22Heightened Awareness forPatients Containing Detectable Amounts of Radiation from Medical Administrations12/09/2003All medical licensees and NRCMaster Materials License medical use permittees.2003-21High-Dose-Rate-Remote-Afterloader Equipment Failure11/24/2003All medical licensees.2003-20Derating Whiting CranesPurchased Before 198010/22/2003All holders of operating licensesfor nuclear power reactors, except those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel; applicable decommissioning reactors, fuel facilities, and independent spent fuel storage installations.Note:NRC generic communications may be received in electronic format shortly after they areissued by subscribing to the NRC listserver as follows:To subscribe send an e-mail to <listproc@nrc.gov >, no subject, and the followingcommand in the message portion:subscribe gc-nrr firstname lastname
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list | - Information Notice 2004-01, Auxiliary Feedwater Pump Recirculation Line Orifice Fouling - Potential Common Cause Failure (21 January 2004, Topic: Zebra Mussel)
- Information Notice 2004-02, Strontium-90 Eye Applicators: New Calibration Values and Use (5 February 2004, Topic: Brachytherapy)
- Information Notice 2004-04, Fuel Damage During Cleaning at a Foreign Pressurized Water Reactor (24 February 2004, Topic: Shutdown Margin, Fuel cladding, Recently irradiated fuel)
- Information Notice 2004-04, Fuel Damage During Cleaning At a Foreign Pressurized Water Reactor (24 February 2004, Topic: Shutdown Margin, Fuel cladding, Recently irradiated fuel)
- Information Notice 2004-05, Official Exhibit - NYS000190-00-BD01 - NRC Information Notice 2004-05, NRC Office of Nuclear Reactor Regulation, Spent Fuel Pool Leakage to Onsite Groundwater, (Salem, New Jersey, Nuclear Power Generating Sta (3 March 2004, Topic: Boric Acid, Through-Wall Leak)
- Information Notice 2004-05, Spent Fuel Pool Leakage To Onsite Groundwater (3 March 2004, Topic: Boric Acid, Through-Wall Leak)
- Information Notice 2004-06, Loss of Feedwater Isokinetic Sampling Probes At Dresden Units 2 and 3 (26 March 2004)
- Information Notice 2004-06, Loss of Feedwater Isokinetic Sampling Probes at Dresden Units 2 and 3 (26 March 2004)
- Information Notice 2004-07, Plugging of Safety Injection Pump Lubrication Oil Coolers with Lakeweed (7 April 2004)
- Information Notice 2004-08, Reactor Coolant Pressure Boundary Leakage Attributable to Propagation of Cracking In Reactor Vessel Nozzle Welds (22 April 2004, Topic: Weld Overlay, Hydrostatic, Nondestructive Examination, Pressure Boundary Leakage, Through-Wall Leak, Dissimilar Metal Weld)
- Information Notice 2004-08, Reactor Coolant Pressure Boundary Leakage Attributable to Propagation of Cracking in Reactor Vessel Nozzle Welds (22 April 2004, Topic: Weld Overlay, Hydrostatic, Nondestructive Examination, Pressure Boundary Leakage, Through-Wall Leak, Dissimilar Metal Weld)
- Information Notice 2004-09, Corrosion of Steel Containment and Containment Liner (27 April 2004, Topic: Coatings, Moisture barrier)
- Information Notice 2004-10, Loose Parts in Steam Generators (4 May 2004)
- Information Notice 2004-11, Cracking in Pressurizer Safety and Relief Nozzles and in Surge Line Nozzle (6 May 2004, Topic: Boric Acid, Weld Overlay, Dissimilar Metal Weld)
- Information Notice 2004-13, Registration, Use, and Quality Assurance Requirements for NRC-Certified Transportation Packages (30 June 2004)
- Information Notice 2004-14, Use of Less Then Optimal Bounding Assumptions In Criticality Safety Analysis at Fuel Cycle Facilities (19 July 2004)
- Information Notice 2004-14, Use of Less Then Optimal Bounding Assumptions in Criticality Safety Analysis at Fuel Cycle Facilities (19 July 2004)
- Information Notice 2004-15, Dual-Unit Scram At Peach Bottom Units 2 and 3 (22 July 2004, Topic: Hydrostatic, Condition Adverse to Quality, Significance Determination Process)
- Information Notice 2004-15, Dual-Unit Scram at Peach Bottom Units 2 and 3 (22 July 2004, Topic: Hydrostatic, Condition Adverse to Quality, Significance Determination Process)
- Information Notice 2004-18, Recent Safety Related Event at Panaromic Wet-Source-Storage Irradiator (26 October 2004)
- Information Notice 2004-19, Problems Associated with Back-up Power Supplies to Emergency Response Facilities and Equipment (4 November 2004)
- Information Notice 2004-20, Recent Issues Associated with NRC Medical Requirements for Licensed Operators (24 November 2004)
- Information Notice 2004-21, Additional Adverse Effect of Boric Acid Leakage: Potential Impact on Post-Accident Coolant pH (24 November 2004, Topic: Boric Acid)
- Information Notice 2004-21, Additional Adverse Effect of Boric Acid Leakage: Potential Impact on Post-Accident Coolant Ph (24 November 2004, Topic: Boric Acid, Pressure Boundary Leakage)
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