Operational Experience Involving Losses of Electrical InvertersML031150304 |
Person / Time |
---|
Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill |
---|
Issue date: |
06/04/1987 |
---|
From: |
Rossi C Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
References |
---|
IN-87-024, NUDOCS 8705290040 |
Download: ML031150304 (9) |
|
Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill |
---|
Category:NRC Information Notice
MONTHYEARInformation Notice 2020-02, Flex Diesel Generator Operational Challenges2020-09-15015 September 2020 Flex Diesel Generator Operational Challenges ML20225A0322020-09-0303 September 2020 NRC Choice Letter to NAC International with Attached Safety Inspection Report, IR 0721015/2020201, February 24-27, 2020 and July 22, 2020, Inspection of NAC International in Norcross, Georgia Information Notice 2012-09, PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs.2019-11-30030 November 2019 PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs. Information Notice 2011-20, NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011)2019-07-24024 July 2019 NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011) ML19196A2452019-07-15015 July 2019 Public Notice - Sequoyah Nuclear Plant, Unit 2 - Exigent Amendment to Facility Operating License Information Notice 2019-01, Inadequate Evaluation of Temporary Alterations2019-03-12012 March 2019 Inadequate Evaluation of Temporary Alterations ML16028A3082016-04-27027 April 2016 NRC Information Notice; IN 2016-05: Operating Experience Regarding Complications From a Loss of Instrumentation Air Information Notice 2015-05, Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps Information Notice 2015-05, Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps 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 2013-20, 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 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Contain2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Con2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notic2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2012-13, Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool Information Notice 2012-13, Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool Information Notice 2012-11, Age Related Capacitor Degradation2012-07-23023 July 2012 Age Related Capacitor Degradation ML12031A0132012-02-0606 February 2012 U.S. Nuclear Regulatory Commission Investigation Report No. 2-2010-058, Cpn International, Inc Information Notice 2011-19, Licensee Event Reports Containing Information Pertaining to Defects to Basic Components2011-09-26026 September 2011 Licensee Event Reports Containing Information Pertaining to Defects to Basic Components Information Notice 2011-15, Steel Containment Degradation and Associated License Renewal Aging Management Issues2011-08-0101 August 2011 Steel Containment Degradation and Associated License Renewal Aging Management Issues Information 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 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 2011-04, IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-262010-12-21021 December 2010 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 ML13066A1872009-12-16016 December 2009 Draft NRC Information Notice 2009-xx - Underestimate of Dam Failure Frequency Used in Probabilistic Risk Assessments ML1007804482009-11-23023 November 2009 Email from Peter Bamford, NRR to Pamela Cowan, Exelon on TMI Contamination Control Event Information Notice 2009-11, NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-112009-07-0707 July 2009 NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-11 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 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify2009-06-19019 June 2009 Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify Information Notice 2008-12, Reactor Trip Due to Off-Site Power Fluctuation2008-07-0707 July 2008 Reactor Trip Due to Off-Site Power Fluctuation Information Notice 2008-11, Service Water System Degradation at Brunswicksteam Electric Plant Unit 12008-06-18018 June 2008 Service Water System Degradation at Brunswicksteam Electric Plant Unit 1 Information Notice 2008-04, Counterfeit Parts Supplied to Nuclear Power Plants2008-04-0707 April 2008 Counterfeit Parts Supplied to Nuclear Power Plants Information Notice 1991-09, Counterfeiting of Crane Valves2007-09-25025 September 2007 Counterfeiting of Crane Valves Information Notice 2007-28, Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls2007-09-19019 September 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls Information Notice 2007-29, Temporary Scaffolding Affects Operability of Safety-Related Equipment2007-09-17017 September 2007 Temporary Scaffolding Affects Operability of Safety-Related Equipment Information Notice 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station2007-03-30030 March 2007 Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station 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 2007-05, Vertical Deep Draft Pump Shaft and Coupling Failures2007-02-0909 February 2007 Vertical Deep Draft Pump Shaft and Coupling Failures Information Notice 2006-31, Inadequate Fault Interrupting Rating of Breakers2006-12-26026 December 2006 Inadequate Fault Interrupting Rating of Breakers Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear 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 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] </code>. |
r
.. ; I -
W
SSINS No.: 6835 ItN 87-24 UIN ITED STATES
FUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
VASHINGTON, D.C. 20555 June A, l9R7 NRC INFORMATION NOTICE NO. 87-24: OPERATIONAL EXPERIENCE INVOLVING LOSSES
OF ELECTRICAL INVERTERS
Addressees
- j
All nuclear power reactor facilities holding an operating license or a con- struction permit.
Purpose
This notice is provided to alert recipients of potential problems involving
electrical inverter losses that have led to unplanned plant transients and/or
inoperability or improper functioning of safety-related and other important
plant equipment. It is expected that recipients will review this information
for applicability to their facilities and consider actions, as appropriate, to
preclude similar problems from occurring at their facilities. However, sugges- tions contained in this notice do not constitute NRC requirements; therefore, no specific action or written response is required.
Past Related Correspondence:
IE Information Notice 84-80, "Plant Transients Induced By Failure of
Non-Nuclear Instrumentation Power," November 8, 1984 IE Bulletin 79-27, 'Loss of Non-Class lE Instrumentation and Control Power
System BUS During Operation,' November 30, 1979 IE Information Notice 79-29, "Loss of Nonsafety-Related Reactor Coolant
System !nstrumentation During Operation," November 16, 1979 IE Circular 79-02, "Failure of 120 Volt Vital AC Power Supplies,"
January 11, 1979 Background:
Inverters in nuclear power plants provide "uninterruptible" vital ac electrical
power to safety- and non-safety-related instrumentation and control systems.
Generally, loss of this function results in some type of undesirable system
condition and/or plant transient, including unnecessary actuation of safety
systems such as reactor protection and engineered safeguards systems; loss of
indicators that provide plant status information; system disturbances,
87052
IN 87-2A
June 4, 1987 including reactor coolant system transients; improper response of the feedwater
and steam generator water level control systems; loss of safety-related elec- trical equipment functions; damage to mechanical equipment; and challenges to
operators and the remaining functional equipment. Such conditions and/or 4 transients clearly have significant safety implications since they result n
challenges to safety equipment and plant operations and/or a degradation of
plant equipment.
The NRC case study report, AEOD/C605 dated December 1986, "Operational Experi- ence Involving Losses of Electrical Inverters," includes the review of 94 licensee event reports (LERs), totaling 107 events %nvolving inverter losses
that occurred during 1982 through 1984. The study includes 35 additional
events from the Nuclear Plant Reliability Data System (NPRDS) that occurred in
the same timeframe. These 142 events occurred at 51 distinct plants: 26 designed by Westinghouse, 11 by General Electric, 9 by Combustion Engineering,
4 by Babcock & Wilcox, and 1 by General Atomic. The total number of events
included in the study for each of the 3 years along with the number of reactor
units which were operating during each of those years is summarized below.
Parameter 1982 1983 1984 Operating Reactor Units 72 74 82 Inverter Loss Events 34 51 57 Losses/Operating Reactor .47 .69 .70
As indicated above, the NRC has issued information on inverter losses since
1979; and industry groups have issued approximately 14 reports related to this
issue.
Description of Circumstances
The NRC case study report identified three potential failure mechanisms for
inverters. One of these involves relatively high ambient temperature and/or
humidity within inverter enclosures. This condition appears to result in
accelerated aging of components that form a part of the inverter circuitry
causing a significant reduction in component life expectancy and inverter loss.
Another mechanism for inverter failure involves the electrical interconnecting
and physical arrangements for the inverter circuitry components. In some
installations, these arrangements are such that when certain components fail, other components also may fail or degrade.
The third failure mechanism involves voltage spikes and perturbations. Many of
the electrical loads in a plant have inductive characteristics. During plant
operations that involve energizing and deenergizing these loads, voltage spikes
and perturbations are generated. The solid-state devices in the inverter cir- cuitry are sensitive to these voltage spikes, and this has resulted in component
failure, blown fuses, and inverter losses. Additionally, secondary voltage per- turbations caused by lightning strikes or switching surges can have an adverse
effect on inverter operation.
IN 87-24 June 4, 1987 Discussion:
The NRC case study report indicates that the failure mechanisms involving
service condition parameters (e.g., ambient temperature and/or humidity and
voltage spikes and perturbations) have common-cause implications. However, none of the events reviewed and evaluated in the report involved the simulta- neous loss of redundant inverter-powered buses.
The dominant cause of inverter losses was attributed to component failures.
Such components include diodes, fuses, silicon controlled rectifiers, capacitors, transistors, resistors, printed circuit boards, transformers and inductors. It
also appears that major contributing factors for the occurrence of component
failure events are high ambient temperature and/or humidity within inverter
enclosures and electrical disturbances at the Inverter input/output terminals.
In addition, incorrectly operating circuit breakers, improperly setting up test
equipment, removing the wrong inverter unit from service, and improperly
transferring power sources for a bus are some personnel actions that make them
the second largest contributor to inverter losses.
It is suggested that licensees consider monitoring of temperature and/or humidity
internal to inverter enclosures and evaluating input and output voltages of the
inverter unit during steady-state and transient conditions to assure that manu- facturer's recommendations are being considered. Additionally, to minimize the
number of inverter loss events resulting from personnel actions, licensees might
consider reviewing related maintenance and testing procedures and practices for
inverters. Further, specialized training and practice sessions with involved
plant personnel and verification of appropriate sequence of'steps to achieve
desired related maintenance and testing activities also may be considered.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the Regional
Administrator of the appropriate regional office or this office.
.ossi, Director
es Rhar
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Vincent D. Thomas, NRR
(301)492-4414 Attachment: List of Recently Issued NRC Information Notices
IN 87-24 June 4, 1987 Discussion:
The NRC case study report indicates that the failure mechanisms involving
service condition parameters (e.g., ambient temperature and/or humidity and
voltage spikes and perturbations) have common-cause implications. However, none of the events reviewed and evaluated in the report involved the simulta- neous loss of redundant inverter-powered buses.
The dominant cause of inverter losses was attributed to component failures.
Such components include diodes, fuses, silicon controlled rectifiers, capacitors, transistors, resistors, printed circuit boards, transformers and inductors. It
also appears that major contributing factors for the occurrence of component
failure events are high ambient temperature and/or humidity within inverter
enclosures and electrical disturbances at the inverter input/output terminals.
In addition, incorrectly operating circuit breakers, improperly setting up test
equipment, removing the wrong inverter unit from service, and improperly
transferring power sources for a bus are some personnel actions that make them
the second largest contributor to inverter losses.
It is suggested that licensees consider monitoring of temperature and/or humidity
internal to inverter enclosures and evaluating input and output voltages of the
inverter unit during steady-state and transient conditions to assure that manu- facturer's recommendations are being considered. Additionally, to minimize the
number of inverter loss events resulting from personnel actions, licensees might
consider reviewing related maintenance and testing procedures and practices for
inverters. Further, specialized training and practice sessions with involved
plant personnel and verification of appropriate sequence of steps to achieve
desired related maintenance and testing activities also may be considered.
No specific action or written response Is required by this information notice.
If you have any questions about this matter, please contact the Regional
Administrator of the appropriate regional office or this office.
Original Signed by
Charles E Ross
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Vincent D. Thomas, NRR
(301)492-4414 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
Dlj' K *C/OGCB:DOEA:NRR
CEos'l 'V CHBerlinger
05 7 05/27/87
- DEPER:IE *ROAB:AEOD *DEPER:IE WMARM *DEPER:IE
VDThomas FAshe AWDromerick Tech Ed RLBaer
2/13/87 2/13/87 2/13/87 05/24/87 2/25/87
IN 87-XX
May xx, 1987 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the Regional
Administrator of the appropriate regional office or this office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Vincent D. Thomas, NRR
(301)492-4414 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
D/DOEA:NRR C/OGCB:DOEA:NRR
CERossi CHBerlinger
05/ /87 05/97/87
- DEPER:IE *ROAB:AEOD *DEPER: IE APPMB:ARM *DEPER:IE
VDThomas FAshe AWDromerick Tech Ed RLBaer
2/13/87 2/13/87 2/13/87 05/24/87 2/25/87
K) KJ IN 87-XX
February , 1987 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the Regional
Administrator of the appropriate regional office or this office.
Edward L. Jordan, Director
Division of Emergency Preparedness
and Engineering Response
Office of Inspection and Enforcement
Technical Contacts: Vincent D. Thomas, IE
(301)492-4755 Frank Ashe, AEOD
(301)492-4442 Attachment: List of Recently Issued IE Information Notices
- SEE PREVIOUS CONCURRENCES
-:DEPER:+B -SDEPER-IE-
Ert SASehWtrt7
/--tS'-
PB f8PEkL IEPEiflE
VDThomas
FAshe
AWDromerick DGable 61V0A ~ ERmnthai-
2/13/87 2/13/87 2/13/87 2/2h/87 2>/--87
IN 87-XX
February , 1987 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the Regional
Administrator of the appropriate regional office or this office.
Edward L. Jordan, Director
Division of Emergency Preparedness
and Engineering Response
Office of Inspection and Enforcement
Technical Contacts: Vincent D. Thomas, IE
(301)492-4755 Frank Ashe, AEOD
(301)492-4442 Attachment: List of Recently Issued IE Information Notices
- SEE PREVIOUS CONCURRENCES
D:DEPER: IE DD:DEPER:IE
ELJordan SASchwartz
2/ /87 2/ /87
- DEPER:IE *ROAB:AEOD *DEPEF)IE PSB:I E DEPER:IE DEPER:IE
VDThomas FAshe e4 rick DGable RLBaer JERosent~hal
2/13/87 2/13/87 ' 0i3 8 2/ /87 2/ /87 2/ /87"
-IuiV IN 87-XX
February , 1987 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the Regional
Administrator of the appropriate regional office or this office.
Edward L. Jordan, Director
Division of Emergency Preparedness
and Engineering Response
Office of Inspection and Enforcement
Technical Contacts: Vincent D. Thomas, IE
(301)492-4755 Frank Ashe, AEOD
(301)492-4442 Attachment: List of Recently Issued IE Information Notices
D:DEPER:IE DD:DEPER:IE
ELJordan SASchwartz
2/ /87 2/ /87- DEPER:IE ROAB:AEOD D IE PSB:IE DEPER:IE DEPER:IE
VDThomas Kf FAshe roer eri/ck DGable RLBaer JERosenthal
2//1/87 2/13/87 h9a 2$ /87 2/ /87 2/ /87 2/ /87
S . I Document Name: i-'
INFO NOTICE - V THOMAS
Requestor's ID:
WERTMAN
Author's Name:
Vince Thomas
Document Comments:
FIO Operational Experience Involving Losses of Inverters
|
---|
|
list | - Information Notice 1987-02, Inadequate Seismic Qualification of Diaphragm Valves by Mathematical Modeling and Analysis (13 January 1987, Topic: Boric Acid, Overspeed trip)
- Information Notice 1987-03, Segregation of Hazardous and Low-Level Radioactive Wastes (15 January 1987, Topic: Boric Acid, Overspeed trip)
- Information Notice 1987-04, Diesel Generator Fails Test Because of Degraded Fuel (16 January 1987, Topic: Boric Acid, Coatings)
- Information Notice 1987-05, Miswiring in a Westinghouse Rod Control System (2 February 1987, Topic: Unanalyzed Condition, Boric Acid)
- Information Notice 1987-06, Loss of Suction to Low-Pressure Service Water System Pumps Resulting from Loss of Siphon (30 January 1987, Topic: Boric Acid)
- Information Notice 1987-07, Quality Control of Onsite Dewatering/Solidification Operations by Outside Contractors (3 February 1987, Topic: Boric Acid, Process Control Program)
- Information Notice 1987-08, Degraded Motor Leads in Limitorque DC Motor Operators (4 February 1987, Topic: Boric Acid, Anchor Darling)
- Information Notice 1987-09, Emergency Diesel Generator Room Cooling Design Deficiency (5 February 1987, Topic: Probabilistic Risk Assessment)
- Information Notice 1987-10, Potential for Water Hammer During Restart of Residual Heat Removal Pumps (11 February 1987, Topic: Water hammer)
- Information Notice 1987-11, Enclosure of Vital Equipment within Designated Vital Areas (13 February 1987, Topic: Contraband, Water hammer)
- Information Notice 1987-11, Enclosure of Vital Equipment Within Designated Vital Areas (13 February 1987, Topic: Contraband, Water hammer)
- Information Notice 1987-12, Potential Problems with Metal Clad Circuit Breakers, General Electric Type AKF-2-25 (13 February 1987, Topic: Water hammer)
- Information Notice 1987-13, Potential for High Radiation Fields Following Loss of Water from Fuel Pool (24 February 1987, Topic: Water hammer)
- Information Notice 1987-14, Actuation of Fire Suppression System Causing Inoperability of Safety-Related Ventilation Equipment (23 March 1987, Topic: Water hammer)
- Information Notice 1987-15, Compliance with the Posting Requirements of Subsection 223b of the Atomic Energy Act of 1954, as Amended (25 March 1987)
- Information Notice 1987-15, Compliance with the Posting Requirements of Subsection 223B of the Atomic Energy Act of 1954, As Amended (25 March 1987)
- Information Notice 1987-16, Degradation of Static O Ring Pressure Switches (2 April 1987, Topic: Commercial Grade)
- Information Notice 1987-17, Response Time of Scram Instrument Volume Level Detectors (7 April 1987, Topic: Scram Discharge Volume, Water hammer)
- Information Notice 1987-18, Unauthorized Service on Teletherapy Units by Nonlicensed Maintenance Personnel (8 April 1987, Topic: Water hammer)
- Information Notice 1987-19, Perforation and Cracking of Rod Cluster Control Assemblies (9 April 1987)
- Information Notice 1987-20, Hydrogen Leak in Auxiliary Building (20 April 1987, Topic: Excess Flow Check Valve)
- Information Notice 1987-21, Shutdown Order Issued Because Licensed Operators Asleep While on Duty (11 May 1987, Topic: Inattentive)
- Information Notice 1987-22, Operator Licensing Requalification Examinations at Nonpower Reactors (22 May 1987, Topic: License Renewal)
- Information Notice 1987-23, Loss of Decay Heat Removal During Low Reactor Coolant Level Operation (27 May 1987, Topic: Boric Acid)
- Information Notice 1987-24, Operational Experience Involving Losses of Electrical Inverters (4 June 1987)
- Information Notice 1987-25, Potentially Significant Problems Resulting from Human Error Involving Wrong Unit, Wrong Train, or Wrong Component Events (11 June 1987, Topic: Boric Acid, Fire Watch, Overspeed trip)
- Information Notice 1987-25, Potentially Significant Problems Resulting From Human Error Involving Wrong Unit, Wrong Train, or Wrong Component Events (11 June 1987, Topic: Boric Acid, Fire Watch, Overspeed)
- Information Notice 1987-26, Cracks in Stiffening Rings on 48-Inch-Diameter UF6 Cylinders (11 June 1987, Topic: Boric Acid)
- Information Notice 1987-26, Cracks in Stiffening Rings on 48-Inch-Diameter Uf6 Cylinders (11 June 1987)
- Information Notice 1987-27, Iranian Official Implies Vague Threat to U.S. Resources (10 June 1987, Topic: Boric Acid)
- Information Notice 1987-28, Air Systems Problems at U.S. Light Water Reactors (28 December 1987, Topic: Boric Acid)
- Information Notice 1987-29, Recent Safety-Related Incidents at Large Irradiators (26 June 1987, Topic: Coatings, Temporary Modification, Biofouling, Uranium Hexafluoride)
- Information Notice 1987-30, Cracking of Surge Ring Brackets in Large General Electric Company Electric Motors (2 July 1987)
- Information Notice 1987-31, Blocking Bracing, and Securing of Radioactive Materials Packages in Transportation (10 July 1987, Topic: Uranium Hexafluoride)
- Information Notice 1987-32, Deficiencies in the Testing of Nuclear-Grade Activated Charcoal (10 July 1987)
- Information Notice 1987-33, Applicability of 10 CFR Part 21 to Nonlicensees (24 July 1987, Topic: Commercial Grade)
- Information Notice 1987-34, Single Failures in Auxiliary Feedwater Systems (24 July 1987)
- Information Notice 1987-35, Reactor Trip Breaker, Westinghouse Model DS-416, Failed to Open on Manual Initiation from the Control Room (30 July 1987)
- Information Notice 1987-36, Significant Unexpected Erosion of Feedwater Lines (4 August 1987)
- Information Notice 1987-37, Compliance with the General License Provisions of 10 CFR Part 31 (10 August 1987)
- Information Notice 1987-39, Control of Particle Contamination at Nuclear Power Plants (21 August 1987, Topic: Fuel cladding, Overexposure)
- Information Notice 1987-40, Backseating Valves Routinely to Prevent Packing Leakage (31 August 1987, Topic: Packing leak)
- Information Notice 1987-41, Failures of Certain Brown Boveri Electric Circuit Breakers (31 August 1987)
- Information Notice 1987-42, Diesel Generator Fuse Contacts (4 September 1987)
- Information Notice 1987-43, Gaps in Neutron-Absorbing Material in High-Density Spent Fuel Storage Racks (8 September 1987)
- Information Notice 1987-44, Thimble Tube Thinning in Westinghouse Reactors (16 September 1987)
- Information Notice 1987-45, Recent Safety-Related Violations of NRC Requirements by Industrial Radiography Licensees (25 September 1987, Topic: High Radiation Area, Overexposure)
- Information Notice 1987-46, Undetected Loss of Reactor Coolant (30 September 1987)
- Information Notice 1987-48, Information Concerning the Use of Anaerobic Adhesive/Sealants (9 October 1987, Topic: Loctite)
- Information Notice 1987-49, Deficiencies in Outside Containment Flooding Protection (9 October 1987, Topic: Safe Shutdown)
... further results |
---|