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Category:NRC Information Notice
MONTHYEARInformation Notice 2013-20, Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-20, OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-11, Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2013-11, OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2011-13, Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-13, Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13)2011-06-29029 June 2011 Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13) Information Notice 2011-13, OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2009-10, Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10)2009-07-0707 July 2009 Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10) Information Notice 2006-13, E-mail from M. 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 Information Notice 2006-13, Ground-Water Contamination Due To Undetected Leakage of Radioactive Water2006-07-10010 July 2006 Ground-Water Contamination Due To Undetected Leakage of Radioactive Water Information Notice 2005-09, Official Exhibit - ENT000527-00-BD01 - NRC Information Notice 2005-09, Indications in Thermally Treated Alloy 600 Steam Generator Tubes and Tube-to Tubesheet Welds (Apr. 7, 2005)2005-04-0707 April 2005 Official Exhibit - ENT000527-00-BD01 - NRC Information Notice 2005-09, Indications in Thermally Treated Alloy 600 Steam Generator Tubes and Tube-to Tubesheet Welds (Apr. 7, 2005) 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 Sta2004-03-0303 March 2004 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 Station)(Mar. 3, 2004) (NRC in 2004 Information Notice 2000-09, Steam Generator Tube Failure at Indian Point Unit 22000-06-28028 June 2000 Steam Generator Tube Failure at Indian Point Unit 2 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 2013-07-03
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cc: Holody Urban UNITED STATES Nick NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555-0001 June 28, 2000 NRC INFORMATION NOTICE 2000-09: STEAM GENERATOR TUBE FAILURE AT INDIAN POINT UNIT 2
Addressees
All holders of operating licenses for nuclear power reactors except those who have ceased operations and have certified that fuel has been permanently removed from the reactor vessel.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to inform addressees of a steam generator tube failure at Indian Point Unit 2. NRC investigations of the licensee's steam generator inspection program are ongoing and any potentially generic issues identified will be communicated in a separate generic communication. However, the investigations to date re-emphasize the importance of licensee involvement with ongoing industry efforts to understand and detect steam generator degradation. It is expected that recipients will review the information for applicability to their facilities and consider actions, as appropriate, to avoid similar problems. However, suggestions contained in this information notice are not NRC requirements; therefore, no specific action or written response is required.
Description of Circumstances
On February 15, 2000, at 7:17 p.m., the Indian Point Unit 2 nuclear plant experienced a steam generator tube failure,, which required the declaration of an Alert at 7:29 p.m., and a manual reactor trip at 7:30 p.m. The operators identified that the #24 steam generator was the source of the leak and completed isolation of the #24 steam generator by 8:31 p.m. At 9:02 p.m., the operator opened the high-pressure steam dump valves and established an excessive primary plant cooldown rate that caused a rapid reduction in the pressurizer level and required the operators to manually initiate safety injection. The operators reset the safety injection at 9:21 p.m., reduced the reactor coolant system pressure to about 970 psig at 9:32 p.m., and re-commenced a plant cooldown at 11:35 p.m. The residual heat removal (RHR) system was placed in service on February 16, 2000, at 12:38 p.m., and primary plant pressure was reduced below the #24 steam generator pressure to terminate the steam generator tube leakage at 2:20 p.m. The plant cooldown continued, and the plant entered cold shutdown at 4:57 p.m. The licensee exited the Alert at 6:50 p.m. The NRC sent an Augmented Inspection Team (AIT) on February 18, 2000, to review the causes, safety implications, and licensee actions associated with the event. The AIT developed a sequence of events, determined the risk significance of the event, and assessed the response by the plant staff and management. The cause of the tube failure was outside the scope of this inspection and is currently being reviewed separately by the NRC. The AIT's report is presented in Inspection Report 05000247/2000-02, dated April 28, 2000 (Accession Number ML003710036). Discussion The event was risk significant. It involved a steam generator tube failure that resulted in an initial primary-to-secondary leak of reactor coolant of approximately 146 gallons per minute and required an "Alert" declaration (the second level of emergency action in the NRC-required emergency response plan). The event resulted in a minor radiological release to the environment that was well within regulatory limits. No radioactivity was measured offsite above normal background levels, and the event did not adversely impact the public health and safety. The licensee performed the necessary actions to protect the health and safety of the public. Specifically, the operators promptly and appropriately took those actions in the emergency operating procedures to trip the reactor, isolate the affected steam generator, and depressurize the reactor coolant system. Additionally, the necessary event mitigation systems worked properly. Notwithstanding the above actions, the AIT identified performance problems in several broad areas that challenged operators, complicated the event response, delayed achieving the cold shutdown condition, and affected the radiological release. The problems involved operator performance, procedure quality, equipment performance, technical support, and emergency response. Operator Performance Some operator performance problems were noted during the plant cooldown phase involving the following: While attempting to cool down the reactor coolant system (RCS), the reactor operator initiated an excessive cooldown rate that exceeded procedural and Technical Specification limits. The excessive cooldown led to several conditions that complicated the subsequent event response and delayed the RCS cooldown. Operators were slow to recognize configuration lineup problems that (1) prevented successful operation of the auxiliary spray system to lower RCS pressure and (2) delayed heatup of the RHR system. Procedure Quality The procedures adequately guided the initial operator response; however, several procedure problems were identified that delayed the cooldown and depressurizing of the RCS. Procedure deficiencies affected Standard Operating Procedures, Emergency Operating Procedures, and Emergency Plan Implementing Procedures. Specific activities included initiation of RHR cooling, initiation of component cooling water alignment, use of auxiliary pressurizer spray, use of methods to monitor RCS temperature to maintain cold shutdown conditions, and initiation of emergency response organization (ERO) notifications. Station personnel were previously aware of the procedure issue involving initiation of RHR cooling but had not corrected the problem before this event. Equipment Performance The necessary event mitigation systems, including the reactor protection system, the auxiliary feedwater system, and the safety injection system, functioned properly. However, several longstanding equipment performance problems were identified that challenged operators during this event: Two losses of condenser vacuum resulted from problems with the operation of the automatic steam supply pressure control valve to the steam jet air ejectors, and the #22 condenser vacuum pump. The isolation valve seal water system became inoperable during the event and required operator action and an entry into a Technical Specification Limiting Condition for Operation Action Statement. A containment entry was required to install a temporary nitrogen supply to the pressurizer power-operated relief valve to compensate for a design deficiency. This action was required before placing the overpressure protection system in service. The steam generator leak rate monitoring equipment had been degraded for an extended period, and limited the amount of steam generator leak rate information available to the operators before the event. The AIT determined that the number and duration of the equipment problems reflected weaknesses in engineering, corrective action processes, and operational support at the station. The licensee's response to a number of the equipment problems identified during the event reflected an acceptance of "working around" the problem rather than fixing it. Emergency Response The ERO took the necessary steps to ensure the protection of public health and safety. The operators properly classified the event, and the licensee implemented a thorough peer review of the emergency response to this event. The AIT identified several emergency plan and implementing procedure problems similar to those identified by the licensee's peer review team, including the following: The emergency response staff was slow to activate the emergency facilities.
- The licensee was slow to establish accountability (i.e., identify the location) of emergency response personnel. The emergency response data system -(ERDS) was inoperable for the first several hours of the event as a result of a pre-existing equipment problem. Problems were noted in the implementation of the media response plan. Problems were identified involving the timeliness and quality of technical support provided to the operators. The licensee developed and was in the process of implementing an emergency response improvement plan before the event. 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) when practical when setting goals and performing periodic evaluations under Section 50.65, "Requirements for monitoring the effectiveness of maintenance at nuclear power plants," of Part 50 of Title 10 of the Code of Federal Regulations. If you have any questions about the information in this notice, please contact the one of the technical contacts listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager. /Ledyard B. Mars , Chief Events Assessment, Generic Communications and Non-Power Reactors Branch Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Technical contacts: Eric Benner, NRR Lawrence Doerflein, Region I 301-415-1171 610-337-5378 E-mail: eibl0.nrc..qov E-mail: ltdOnrc.gov Peter Eselgroth, Region I Raymond Lorson, Region I 610-337-5234 603-474-3589 E-mail: pwemnrc.aov E-mail: rklO.nrc.aovAttachment: List of Recently Issued NRC Information Notices
Attachment LIST OF RECENTLY ISSUED NRC INFORMATION NOTICESInformation Date of Notice No. Subject Issuance Issued to 2000-08 Inadequate Assessment of the 5/15/2000 All holders of operating licenseesEffect of Differential Temperatures on SafetyRelated Pumps National Institute for Occupational Safety and Health Respirator User Notice: Special Precaustions for Using Certain Self-Contained Breathing Apparatus Air Cylinders Offsite Power Voltage Inadequacies Recent Medical Misadministrations Resulting from Inattention to Detail 1999 Enforcement Sanctions for Deliberate Violations of NRC Employee Protection Requirements High-Efficiency Particulate Air Filter Exceeds Mass Limit Before Reaching Expected Differential Pressure Failure of Criticality Safety Control to Prevent Uranium Dioxide (U02) Powder Accumulation4/10/2000 3/22/2000 3/06/20002/25/20002/22/2000 2/22/2000for nuclear power reactorsAll holders of operating licenses for nuclear power reactors,nonpower reactors, and all fuel cycle and materiallicensees required to have an NRC-approved emergency plan All holders of operating licenses for nuclear power reactors, except those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor All medical licenseesAll NRC licenseesAll NRC licensed fuel-cycled conversion, enrichment, and fabrication facilities All NRC licensed fuel-cycled conversion, enrichment, and fabrication facilitiesOL = operating License CP = Construction Permit2000-07 2000-06 2000-052000-042000-03 2000-02
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list | - Information Notice 2000-01, Operational Issues Identified in Boiling Water Reactor Trip and Atransient (11 February 2000)
- Information Notice 2000-02, Failure of Criticality Safety Control to Prevent Uranium Dioxide UO2 Powder Accumulation (22 February 2000)
- Information Notice 2000-02, Failure of Criticality Safety Control to Prevent Uranium Dioxide Uo2 Powder Accumulation (22 February 2000)
- Information Notice 2000-03, High-efficiency Particulate Air Filter Exceeds Mass Limit Before Reaching Expected Differential Pressure (22 February 2000)
- Information Notice 2000-04, 1999 Enforcement Sanctions for Deliberate Violations of NRC Employee Protection Requirements (25 February 2000)
- Information Notice 2000-05, Recent Medical Misadministrations Resulting from Inattention to Detail (6 March 2000, Topic: Brachytherapy, Overdose, Underdose)
- Information Notice 2000-06, Offsite Power Voltage Inadequacies (27 March 2000, Topic: Exemption Request)
- Information Notice 2000-07, National Institute for Occupational Safety and Health Respirator User Notice: Special Precaustions Using Certain Self-Contained Breathing Apparatus Air Cylinders (10 April 2000)
- Information Notice 2000-08, Inadequate Assessment of the Effect of Differential Temperatures on Safety-Related Pumps (15 May 2000)
- Information Notice 2000-09, Steam Generator Tube Failure at Indian Point Unit 2 (28 June 2000)
- Information Notice 2000-10, Recent Events Resulting in Extremity Exposures Exceeding Regulatory Limits (18 July 2000)
- Information Notice 2000-12, Potential Degradation of Fire Fighter Primary Protective Garments (21 September 2000, Topic: Moisture barrier)
- Information Notice 2000-14, Non-vital Bus Fault Leads to Fire and Loss of Offsite Power (27 September 2000)
- Information Notice 2000-15, Recent Events Resulting In Whole Body Exposures Exceeding Regulatory Limits (29 September 2000)
- Information Notice 2000-15, Recent Events Resulting in Whole Body Exposures Exceeding Regulatory Limits (29 September 2000, Topic: Overexposure)
- Information Notice 2000-16, Volatilization of Radionuclides and Emergency Procedures (5 October 2000)
- Information Notice 2000-17, Crack in Weld Area of Reactor Coolant System Hot Leg Piping at V.C. Summer (28 February 2001, Topic: Boric Acid, Non-Destructive Examination, Stress corrosion cracking, Eddy Current Testing)
- Information Notice 2000-18, Substandard Material Supplied by Chicago Bullet Proof Systems (29 November 2000)
- Information Notice 2000-19, Implementation of Human Use Research Protocols Involving U.S. Nuclear Regulatory Commission Regulated Materials (5 December 2000, Topic: Brachytherapy)
- Information Notice 2000-20, Potential Loss of Redundant Safety Related Equipment Due to Lack of a High-Energy Line Break Barriers (11 December 2000)
- Information Notice 2000-21, Detached Check Valve Disc Not Detected by Use of Acoustic and Magnetic Nonintrusive Test Techniques (15 December 2000)
- Information Notice 2000-22, Medical Misadministrations Caused by Human Errors Involving Gamma Stereotactic Radiosurgery (Gamma Knife) (18 December 2000)
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