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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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SSINS No.: 6835 Accession No.:
8008220249 UNITED STATES IN 80-37 NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND.ENFORCEMENT
'HASHINGTON, D.C. 20555 October 24, 1980
IE Information Notice Mo. 80-37: CONTAINMENT COOLER LEAKS AND REACTOR CAVITY
FLOODING AT INDIAN POINT UNIT 2 Discription of Circumstances:
This Notice contains information regarding multiple service water leaks into
containment with resulting damage to reactor instrumentation and potential
damage to the reactor pressure vessel.
a
Upon-containment entry on October 17, 1980 at Indian Point Unit 2, toa repair significant
malfunctioning power range nuclear detector, it was discovered that
amount of water was collected (approximately 100,000 gal) on the containment pressure
floor, in the containment sumps, and in the cavity under the reactor
vessel (RPV). This collected water probably caused the detector malfunction, and the water in the cavity under the RPV is believed to have been deep enough
to wet several feet of the pressure vessel lower head, causing an unanalyzed
thermal stress condition of potential safety significance.
This condition resulted from the following combination of conditions: from an
(1) Both containment sump pumps were inoperable, one due to blown fuses(2) The
unknown cause and the other due to binding of its controlling float;
two containment sump level indicating lights which would indicate increasing stuck
water level over the water level range present in the containment wereoperable
(on) and may have been for several days, leaving the operator with no
instrumentation to measure water level in the containment; (3) The moisture
level indicators in the containment did not indicate high moisture levels, or steam
apparently because they are designed to detect pressurized hot water moisture levels
leaks (i.e., a LOCA), and are not sensitive to the lower airborne
leaks; (4) The hold-up tanks which
resulting from relatively small cold water Unit 1 ultimately receive water pumped from the containment sump also receive the effect
process water, lab drain water, etc. These other water sources masked
of cessation of water flows from the Unit 2 sump; (5) There were significant, multiple service water leaks from the containment fan cooling units directlywhich
onto the containment floor. These coolers have a history of such leakage, cannot be detected by supply inventory losses since the supply systemin(service the cavity
water system) is not a closed system; (6) The two submersible pumps the con- under the Reactor Pressure Vessel were ineffective since they pump onto
containment sump pumps.
tainment floor for ultimate removal by the (inoperable) nor was
There is no water level instrumentation in the cavity under the RPV,
there any indication outside the containment when these pumps are running.
The licensee has installed redundant sump level annunciated alarms in theto
control room and has installed an annunciated alarm in the control roomThe
indicate if either submersible pump in the reactor cavity activates. bushings
licensee has also repaired the service water leaks, installed guide
on the sump pump control floats to prevent their binding, and has repaired
the containment sump water level indicators.
j ^ - f - W
IN 80-37 October 24, 1980 The licensee plans in the loncer term to replace the containment fan unit
cooling coils.
It is anticipated that results of a continuing NRC investigation into this
incident will result in issuance of an IE Bulletin and/or an NRR Generic
Letter in the near future which will recommend or require specific licensees
and applicant actions. In the interim, we recommend that all licensee
ascertain that the potential does not exist for undetected water accumulation
in the containment.
This Information Notice is provided to inform licensees of a possibly significat
matter. No written resoonse to this Information Notice is required.
4' - v I
IN 80-37 October 24, 1980
RECENTLY ISSUED
TE INFORMATION NOTICES
Information Date of
Notice No. Subject Issue Issued to
80-36 Failure of steam 10/10/80 All nuclear power
generator support bolting reactor facilities
holding OLs or CPs
80-35 Leaking and dislodged 10/10/80 All categories G and
Iodine-124 implant seeds G1 medical licensees
80-34 Boron dilution of reactor 9/26/80 All pressurized water
coolant during steam reactor facilities
generator decontamination holding power reactor OLs
80-33 Determination of teletherapy 9/15/80 All teletherapy
timer accuracy (G3) licensees
80-32 Clarification of certain 8/12/80 All NRC and agreement
requirements for Exclu- state licensees
sive-use shipments of
radioactive materials
80-31 Maloperation of Gould- 8/27/80 All light water reactor
Brown Boveri Type 480 facilities holding OLs
volt type K-600S and or CPs
K-DON 600S circuit
breakers
80-30 Potential for unaccept- 8/19/80 All boiling water reactor
able interaction between facilities holding power
the control rod drive scram reactor OLs or CPs.
function and non-essential
control air at certain GE BWR
facilities
80-29 Broken studs on Terry 8/7/80 All light water reactor
turbine steam inlet facilities holding
flange power reactor OLs or CPs*
Supplement to Notification of 7/29/80 All holders of reactor
80-06 significant events at and near-term OL
operating power reactor applicants
facilities
80-23 Prompt reporting of 6/13/80 All applicants for and
required information holders of nuclear power
to NRC reactor CPs
- Operating Licenses or Construction Permits
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list | - Information Notice 1980-03, Main Turbine Electrohydraulic Control System (31 January 1980, Topic: Water rod)
- Information Notice 1980-05, Chloride Contamination of Safety Related Piping & Components (8 February 1980, Topic: Water rod)
- Information Notice 1980-06, Notification of Significant Events at Operating Power Reactor Facilities (29 July 1980, Topic: Earthquake, Fatality)
- Information Notice 1980-07, Pump Shaft Fatigue Cracking (29 February 1980, Topic: Water rod)
- Information Notice 1980-08, the States Company Sliding Link Electrical Terminal Block (7 March 1980, Topic: Water rod)
- Information Notice 1980-08, The States Company Sliding Link Electrical Terminal Block (7 March 1980, Topic: Water rod)
- Information Notice 1980-09, Possible Occupational Health Hazard Associated with Closed Cooling Systems for Operating Power Plants (7 March 1980, Topic: Water rod)
- Information Notice 1980-10, Partial Loss of Non-Nuclear Instrument System Power Supply During Operation (7 March 1980, Topic: Core Exit Thermocouple, Water rod)
- Information Notice 1980-11, Generic Problems with Asco Valves in Nuclear Applications Including Fire Protection Systems (14 March 1980, Topic: Water rod)
- Information Notice 1980-12, Instrument Failure Causes Opening of Porv & Block Valve (31 March 1980, Topic: Water rod)
- Information Notice 1980-13, General Electric Type Sbm Control Switches Defective CAM Followers (2 April 1980, Topic: Water rod)
- Information Notice 1980-14, Safety Suggestions from Employees (2 April 1980)
- Information Notice 1980-15, Axial (Longitudinal) Oriented Cracking in Piping (21 April 1980, Topic: Liquid penetrant)
- Information Notice 1980-15, Axial (longitudinal) Oriented Cracking in Piping (21 April 1980, Topic: Liquid penetrant)
- Information Notice 1980-16, Shaft Seal Packing Causes Binding in Main Steam Swing Disc Check & Isolation Valves (29 April 1980)
- Information Notice 1980-19, Niosh Recall of Recirculating-Mode (Closed Circuit) Self-Contained Breathing Apparatus (Rebreather) (6 May 1980)
- Information Notice 1980-19, Niosh Recall of Recirculating-Mode (closed Circuit) Self-Contained Breathing Apparatus (rebreather) (6 May 1980)
- Information Notice 1980-20, Loss of Decay Heat Removal Capability at Davis-Besse Unit 1 While in a Refueling Mode (8 May 1980)
- Information Notice 1980-21, Anchorage & Support of Safety-Related Electrical Equipment (16 May 1980, Topic: Earthquake)
- Information Notice 1980-22, Breakdowns in Contamination Control Programs (28 May 1980)
- Information Notice 1980-25, Transportation of Pyrophoric Uranium (30 May 1980)
- Information Notice 1980-26, Evaluation of Contractor QA Programs (10 June 1980)
- Information Notice 1980-27, Degradation of Reactor Coolant Pump Studs (11 June 1980, Topic: Boric Acid)
- Information Notice 1980-29, Broken Studs on Terry Turbine Steam Inlet Flange (7 August 1980, Topic: Overspeed trip)
- Information Notice 1980-31, Maloperation of Gould-Brown Boveri 480 Volt-Type K-6005 & K-Don 6005 Circuit Breakers (27 August 1980)
- Information Notice 1980-34, Boron Dilution of Reactor Coolant During Steam Generator Decontamination (26 September 1980, Topic: Boric Acid, Shutdown Margin, Eddy Current Testing)
- Information Notice 1980-37, Containment Cooler Leaks & Reactor Cavity Flooding at Indian Point Unit 2 (24 October 1980)
- Information Notice 1980-38, Cracking in Charging Pump Casing Cladding (30 October 1980, Topic: Boric Acid, Nondestructive Examination)
- Information Notice 1980-39, Malfunction of Solenoid Valves Manufactured by Valcor Engineering Corp (31 October 1980)
- Information Notice 1980-40, Excessive Nitrogen Supply Pressure Actuates Safety-Relief Valve Operation to Cause Reactor Depressurization (7 November 1980)
- Information Notice 1980-41, Failure of Swing Check Valve in Decay Heat Removal System at Davis Besse Unit No.1 (10 November 1980)
- Information Notice 1980-42, Effect of Radiation on Hydraulic Snubber Fluid (24 November 1980)
- Information Notice 1980-43, Failures of Continuous Water Level Monitor for Scram Discharge Volume at Dresden Unit No.2 (5 December 1980, Topic: Scram Discharge Volume)
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