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| {{#Wiki_filter:4.UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555October 20, 1988NRC INFORMATION NOTICE NO. 88-84: DEFECTIVE MOTOR SHAFT KEYS IN LIMITORQUEMOTOR ACTUATORS | | {{#Wiki_filter:4.UNITED STATES NUCLEAR REGULATORY |
| | |
| | COMMISSION |
| | |
| | ===OFFICE OF NUCLEAR REACTOR REGULATION=== |
| | WASHINGTON, D.C. 20555 October 20, 1988 NRC INFORMATION |
| | |
| | NOTICE NO. 88-84: DEFECTIVE |
| | |
| | ===MOTOR SHAFT KEYS IN LIMITORQUE=== |
| | MOTOR ACTUATORS |
|
| |
|
| ==Addressees== | | ==Addressees== |
| :All holders of operating licenses or construction permits for nuclear powerreactors. | | : |
| | All holders of operating |
| | |
| | licenses or construction |
| | |
| | permits for nuclear power reactors. |
|
| |
|
| ==Purpose== | | ==Purpose== |
| :This information notice is being provided to alert recipients to potentialproblems from defective motor shaft keys installed in certain Limitorqueactuators. It is expected that recipients will review the information forapplicability to their facilities and consider actions, as appropriate, toavoid similar problems. However, suggestions contained in this informationnotice do not constitute NRC requirements; therefore, no specific action orwritten response is required. | | : This information |
| | |
| | notice is being provided to alert recipients |
| | |
| | to potential problems from defective |
| | |
| | motor shaft keys installed |
| | |
| | in certain Limitorque |
| | |
| | actuators. |
| | |
| | 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 do not constitute |
| | |
| | NRC requirements; |
| | therefore, no specific action or written response is required.Description |
| | |
| | of Circumstances: |
| | On October 15, 1987, the NRC received a report from Houston Lighting and Power Company concerning |
| | |
| | sheared motor shaft-to-pinion |
| | |
| | keys found in a Limitorque |
| | |
| | actuator at its South Texas Project, Unit 2, nuclear plant. A similar key'failure also occurred in April 1987. The sheared key from one of the valves.was sent to a metallurgical |
| | |
| | laboratory |
| | |
| | which found that the properties |
| | |
| | of the-.material were not consistent |
| | |
| | with those of American Iron and Steel Institute (AISI) type 1018 steel. AISI type 1018 steel is the material designated |
| | |
| | by Limitorque |
| | |
| | for these particular |
| | |
| | keys as specified |
| | |
| | in Limitorque |
| | |
| | design documents. |
| | |
| | In August 1987, three additional |
| | |
| | keys had been removed from similar actuators and sent to the laboratory |
| | |
| | for analysis. |
| | |
| | One of the removed keys was split and the other two showed signs of deformation. |
| | |
| | Laboratory |
| | |
| | analysis of these keys revealed that the properties |
| | |
| | of the key material were not consistent |
| | |
| | with those of AISI type 1018 steel. The metallurgical |
| | |
| | analysis revealed that the keys had failed longitudinally |
| | |
| | along manganese |
| | |
| | sulfide inclusions |
| | |
| | and that the key material was probably an AISI type 1118 or 1119 resulphurized |
| | |
| | steel. Addi-tionally, on March 16, 1983, Westinghouse |
| | |
| | had submitted |
| | |
| | a 10 CFR Part 21 report to the NRC concerning |
| | |
| | its discovery |
| | |
| | of sheared keys on six actuators. |
| | |
| | These keys were also analyzed and found to be made of other than AISI type 1018 steel.Discussion: |
| | During an NRC inspection |
| | |
| | at Limitorque |
| | |
| | in May 1988, inspectors |
| | |
| | found that at the time of the manufacture |
| | |
| | of the South Texas actuators, keys were purchased<0 At101t40018 IN 88-84 October 20, 1988 from a commercial |
| | |
| | vendor without certificates |
| | |
| | of conformance |
| | |
| | for the material type or properties. |
| | |
| | No checks were performed |
| | |
| | at Limitorque |
| | |
| | to verify that the proper key material was received. |
| | |
| | Keys purchased |
| | |
| | today are still bought as commercial |
| | |
| | grade; however, certified |
| | |
| | material test reports (CMTRs) are received from the vendor. Limitorque |
| | |
| | also performs hardness and dimensional |
| | |
| | checks of the keys upon receipt from the vendor.In a letter to the NRC dated May 19, 1988, Limitorque |
| | |
| | provided additional |
| | |
| | in-formation |
| | |
| | on this issue. Limitorque |
| | |
| | stated that the current material control procedures |
| | |
| | for key procurement |
| | |
| | were fully implemented |
| | |
| | in September |
| | |
| | 1983. At that time, the existing key inventory |
| | |
| | was scrapped and completely |
| | |
| | replaced with keys purchased |
| | |
| | under the new controls. |
| | |
| | It is estimated |
| | |
| | that all actuators |
| | |
| | from serial number 362735 onward were supplied with keys procured under the upgraded material controls. |
| | |
| | Additionally, Limitorque |
| | |
| | determined |
| | |
| | that only the following actuator-motor |
| | |
| | combinations |
| | |
| | could potentially |
| | |
| | experience |
| | |
| | similar key failures due to improper material.Unit Size Motor Size SMB-000 None SMB-OO 25-ft.lb 1800 rpm SMB-0 25-ft.lb 1800 rpm 25-ft.ThY |
| | |
| | -3600 rpm--40-ft.lb 1800 rpm SMB-1 60-ft.lb 1800 rpm 60-ft.lb 3600 rpm SMB-2 80-ft.lb 3600 rpm No specific action or written response is required by this information |
| | |
| | notice.If you have any questions |
| | |
| | about this matter, please contact the technical contact listed below or the Regional Administrator |
| | |
| | of the appropriate |
| | |
| | regional office.Division of Operational |
| | |
| | ===Events Assessment=== |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical |
| | |
| | Contact: Jeffrey B. Jacobson, NRR (301) 492-0996 Attachment: |
| | List of Recently Issued NRC Information |
| | |
| | Notices |
| | |
| | , 0 A -%If Attachment |
| | |
| | IN 88-84 October 20, 1988 LIST OF RECENTLY ISSUED NRC INFORMATION |
| | |
| | NOTICES Information |
| | |
| | Date of Notice No. Subject Issuance Issued to 88-83 88-82 88-81 88-80 88-79 Inadequate |
| | |
| | Testing of Relay Contacts in Safety-Related |
| | |
| | Logic Systems Torus Shells with Corrosion and Degraded Coatings in BWR Containments |
| | |
| | Failure of Amp Window Indent Kynar Splices and Thomas and Betts Nylon Wire Caps During Environmental |
| | |
| | Quali-fication Testing Unexpected |
| | |
| | Piping Movement Attributed |
| | |
| | to Thermal Stratification |
| | |
| | Misuse of Flashing Lights for High Radiation |
| | |
| | Area Controls 10/19/88 10/14/88 10/7/88 10/7/88 10/7/88 All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for BWRs.All holders of OLs or CPs for nuclear power, test, and research reactors.All holders of OLs or CPs for PWRs.All holders of OLs or CPs for nuclear power reactors.88-69, Supp 1 Movable Contact Finger Binding in HFA Relays Manufactured |
| | |
| | by General Electric (GE)9/29/88 All holders of OLs or CPs for nuclear power reactors.88-78 88-77 88-76 Implementation |
| | |
| | of Revised NRC-Administered |
| | |
| | Requali-fication Examinations |
| | |
| | Inadvertent |
| | |
| | Reactor Vessel Overfill Recent Discovery |
| | |
| | of a Phenomenon |
| | |
| | not Previously |
| | |
| | Considered |
| | |
| | in the Design of Secondary |
|
| |
|
| ==Description of Circumstances==
| | Containment |
| :On October 15, 1987, the NRC received a report from Houston Lighting and PowerCompany concerning sheared motor shaft-to-pinion keys found in a Limitorqueactuator at its South Texas Project, Unit 2, nuclear plant. A similar key'failure also occurred in April 1987. The sheared key from one of the valves.was sent to a metallurgical laboratory which found that the properties of the-.material were not consistent with those of American Iron and Steel Institute(AISI) type 1018 steel. AISI type 1018 steel is the material designated byLimitorque for these particular keys as specified in Limitorque design documents.In August 1987, three additional keys had been removed from similar actuatorsand sent to the laboratory for analysis. One of the removed keys was splitand the other two showed signs of deformation. Laboratory analysis of thesekeys revealed that the properties of the key material were not consistent withthose of AISI type 1018 steel. The metallurgical analysis revealed that thekeys had failed longitudinally along manganese sulfide inclusions and that thekey material was probably an AISI type 1118 or 1119 resulphurized steel. Addi-tionally, on March 16, 1983, Westinghouse had submitted a 10 CFR Part 21 reportto the NRC concerning its discovery of sheared keys on six actuators. Thesekeys were also analyzed and found to be made of other than AISI type 1018 steel.Discussion:During an NRC inspection at Limitorque in May 1988, inspectors found that atthe time of the manufacture of the South Texas actuators, keys were purchased<0 At101t40018 IN 88-84October 20, 1988 from a commercial vendor without certificates of conformance for the materialtype or properties. No checks were performed at Limitorque to verify that theproper key material was received. Keys purchased today are still bought ascommercial grade; however, certified material test reports (CMTRs) are receivedfrom the vendor. Limitorque also performs hardness and dimensional checks ofthe keys upon receipt from the vendor.In a letter to the NRC dated May 19, 1988, Limitorque provided additional in-formation on this issue. Limitorque stated that the current material controlprocedures for key procurement were fully implemented in September 1983. Atthat time, the existing key inventory was scrapped and completely replaced withkeys purchased under the new controls. It is estimated that all actuators fromserial number 362735 onward were supplied with keys procured under the upgradedmaterial controls. Additionally, Limitorque determined that only the followingactuator-motor combinations could potentially experience similar key failuresdue to improper material.Unit Size Motor SizeSMB-000 NoneSMB-OO 25-ft.lb 1800 rpmSMB-0 25-ft.lb 1800 rpm25-ft.ThY -3600 rpm--40-ft.lb 1800 rpmSMB-1 60-ft.lb 1800 rpm60-ft.lb 3600 rpmSMB-2 80-ft.lb 3600 rpmNo specific action or written response is required by this information notice.If you have any questions about this matter, please contact the technicalcontact listed below or the Regional Administrator of the appropriate regionaloffice.Division of Operational Events AssessmentOffice of Nuclear Reactor Regulation
| |
|
| |
|
| ===Technical Contact:===
| | Pressure Control 9/22/88 9/22/88 9/19/88 All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for BWRs.All holders of OLs or CPs for nuclear power reactors.OL = Operating |
| Jeffrey B. Jacobson, NRR(301) 492-0996Attachment: List of Recently Issued NRC Information Notices
| |
|
| |
|
| , 0 A -%IfAttachmentIN 88-84October 20, 1988 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to88-8388-8288-8188-8088-79Inadequate Testing of RelayContacts in Safety-RelatedLogic SystemsTorus Shells with Corrosionand Degraded Coatings inBWR ContainmentsFailure of Amp WindowIndent Kynar Splicesand Thomas and BettsNylon Wire Caps DuringEnvironmental Quali-fication TestingUnexpected Piping MovementAttributed to ThermalStratificationMisuse of Flashing Lightsfor High Radiation AreaControls10/19/8810/14/8810/7/8810/7/8810/7/88All holders of OLsor CPs for nuclearpower reactors.All holders of OLsor CPs for BWRs.All holders of OLsor CPs for nuclearpower, test, andresearch reactors.All holders of OLsor CPs for PWRs.All holders of OLsor CPs for nuclearpower reactors.88-69, Supp 1Movable Contact FingerBinding in HFA RelaysManufactured by GeneralElectric (GE)9/29/88All holders of OLsor CPs for nuclearpower reactors.88-7888-7788-76Implementation of RevisedNRC-Administered Requali-fication ExaminationsInadvertent ReactorVessel OverfillRecent Discovery of aPhenomenon not PreviouslyConsidered in the Designof Secondary ContainmentPressure Control9/22/889/22/889/19/88All holders of OLsor CPs for nuclearpower reactors.All holders of OLsor CPs for BWRs.All holders of OLsor CPs for nuclearpower reactors.OL = Operating LicenseCP = Construction Permit
| | License CP = Construction |
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| }} | | Permit}} |
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| {{Information notice-Nav}} | | {{Information notice-Nav}} |
Defective Motor Shaft Keys in Limitorque Motor ActuatorsML031150062 |
Person / Time |
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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 |
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Issue date: |
10/20/1988 |
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From: |
Rossi C E Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-88-084, NUDOCS 8810140018 |
Download: ML031150062 (3) |
|
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Category:NRC Information Notice
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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]] </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]] </code>. |
4.UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 October 20, 1988 NRC INFORMATION
NOTICE NO. 88-84: DEFECTIVE
MOTOR SHAFT KEYS IN LIMITORQUE
MOTOR ACTUATORS
Addressees
All holders of operating
licenses or construction
permits for nuclear power reactors.
Purpose
- This information
notice is being provided to alert recipients
to potential problems from defective
motor shaft keys installed
in certain Limitorque
actuators.
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 do not constitute
NRC requirements;
therefore, no specific action or written response is required.Description
of Circumstances:
On October 15, 1987, the NRC received a report from Houston Lighting and Power Company concerning
sheared motor shaft-to-pinion
keys found in a Limitorque
actuator at its South Texas Project, Unit 2, nuclear plant. A similar key'failure also occurred in April 1987. The sheared key from one of the valves.was sent to a metallurgical
laboratory
which found that the properties
of the-.material were not consistent
with those of American Iron and Steel Institute (AISI) type 1018 steel. AISI type 1018 steel is the material designated
by Limitorque
for these particular
keys as specified
in Limitorque
design documents.
In August 1987, three additional
keys had been removed from similar actuators and sent to the laboratory
for analysis.
One of the removed keys was split and the other two showed signs of deformation.
Laboratory
analysis of these keys revealed that the properties
of the key material were not consistent
with those of AISI type 1018 steel. The metallurgical
analysis revealed that the keys had failed longitudinally
along manganese
sulfide inclusions
and that the key material was probably an AISI type 1118 or 1119 resulphurized
steel. Addi-tionally, on March 16, 1983, Westinghouse
had submitted
a 10 CFR Part 21 report to the NRC concerning
its discovery
of sheared keys on six actuators.
These keys were also analyzed and found to be made of other than AISI type 1018 steel.Discussion:
During an NRC inspection
at Limitorque
in May 1988, inspectors
found that at the time of the manufacture
of the South Texas actuators, keys were purchased<0 At101t40018 IN 88-84 October 20, 1988 from a commercial
vendor without certificates
of conformance
for the material type or properties.
No checks were performed
at Limitorque
to verify that the proper key material was received.
Keys purchased
today are still bought as commercial
grade; however, certified
material test reports (CMTRs) are received from the vendor. Limitorque
also performs hardness and dimensional
checks of the keys upon receipt from the vendor.In a letter to the NRC dated May 19, 1988, Limitorque
provided additional
in-formation
on this issue. Limitorque
stated that the current material control procedures
for key procurement
were fully implemented
in September
1983. At that time, the existing key inventory
was scrapped and completely
replaced with keys purchased
under the new controls.
It is estimated
that all actuators
from serial number 362735 onward were supplied with keys procured under the upgraded material controls.
Additionally, Limitorque
determined
that only the following actuator-motor
combinations
could potentially
experience
similar key failures due to improper material.Unit Size Motor Size SMB-000 None SMB-OO 25-ft.lb 1800 rpm SMB-0 25-ft.lb 1800 rpm 25-ft.ThY
-3600 rpm--40-ft.lb 1800 rpm SMB-1 60-ft.lb 1800 rpm 60-ft.lb 3600 rpm SMB-2 80-ft.lb 3600 rpm No specific action or written response is required by this information
notice.If you have any questions
about this matter, please contact the technical contact listed below or the Regional Administrator
of the appropriate
regional office.Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
Contact: Jeffrey B. Jacobson, NRR (301) 492-0996 Attachment:
List of Recently Issued NRC Information
Notices
, 0 A -%If Attachment
IN 88-84 October 20, 1988 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 88-83 88-82 88-81 88-80 88-79 Inadequate
Testing of Relay Contacts in Safety-Related
Logic Systems Torus Shells with Corrosion and Degraded Coatings in BWR Containments
Failure of Amp Window Indent Kynar Splices and Thomas and Betts Nylon Wire Caps During Environmental
Quali-fication Testing Unexpected
Piping Movement Attributed
to Thermal Stratification
Misuse of Flashing Lights for High Radiation
Area Controls 10/19/88 10/14/88 10/7/88 10/7/88 10/7/88 All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for BWRs.All holders of OLs or CPs for nuclear power, test, and research reactors.All holders of OLs or CPs for PWRs.All holders of OLs or CPs for nuclear power reactors.88-69, Supp 1 Movable Contact Finger Binding in HFA Relays Manufactured
by General Electric (GE)9/29/88 All holders of OLs or CPs for nuclear power reactors.88-78 88-77 88-76 Implementation
of Revised NRC-Administered
Requali-fication Examinations
Inadvertent
Reactor Vessel Overfill Recent Discovery
of a Phenomenon
not Previously
Considered
in the Design of Secondary
Containment
Pressure Control 9/22/88 9/22/88 9/19/88 All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for BWRs.All holders of OLs or CPs for nuclear power reactors.OL = Operating
License CP = Construction
Permit
|
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|
list | - Information Notice 1988-01, Safety Injection Pipe Failure (27 January 1988, Topic: Unidentified leakage, Water hammer)
- Information Notice 1988-03, Cracks in Shroud Support Access Hole Cover Welds (2 February 1988, Topic: Intergranular Stress Corrosion Cracking, Stolen)
- Information Notice 1988-04, Inadequate Qualification and Documentation of Fire Barrier Penetration Seals (5 February 1988, Topic: Fire Barrier, Fire Watch, Stolen)
- Information Notice 1988-05, Fire in Annunciator Control Cabinets (12 February 1988, Topic: Stolen)
- Information Notice 1988-06, Foreign Objects in Steam Generators (29 February 1988, Topic: Eddy Current Testing, Stolen)
- Information Notice 1988-07, Inadvertent Transfer of Licensed Material to Uncontrolled Locations (7 March 1988, Topic: Stolen, Overexposure)
- Information Notice 1988-08, Chemical Reactions with Radioactive Waste Solification Agents (14 March 1988, Topic: Process Control Program, Stolen)
- Information Notice 1988-09, Reduced Reliability of Steam-Driven Auxiliary Feedwater Pumps Caused by Instability of Woodward PG-PL Type Governors (18 March 1988, Topic: Overspeed trip, Overspeed)
- Information Notice 1988-10, Memo of Understanding Between NRC and OSHA Relating to NRC-Licensed Facilities (53 FR 43950, October 31, 1988) (23 December 1988, Topic: Fatality, Overexposure)
- Information Notice 1988-10, Memo of Understanding Between NRC and OSHA Relating to NRC-Licensed Facilities (53 Fr 43950, October 31, 1988) (23 December 1988, Topic: Fatality, Overexposure)
- Information Notice 1988-10, Memorandum of Understanding Between NRC and Osha Relating to NRC-Licensed Facilities (53 Fr 43950, October 31, 1988. (23 December 1988, Topic: Fatality, Overexposure)
- Information Notice 1988-11, Potential Loss of Motor Control Center And/Or Switchboard Function Due to Faulty Tie Bolts (7 April 1988)
- Information Notice 1988-12, Overgreasing of Electric Motor Bearings (12 April 1988, Topic: Hardened grease)
- Information Notice 1988-13, Water Hammer & Possible Piping Damage Caused by Misapplication of Kerotest Packless Metal Diaphragm Globe Valves (18 April 1988, Topic: Water hammer)
- Information Notice 1988-14, Potential Problems with Electrical Relays (18 April 1988, Topic: Water hammer)
- Information Notice 1988-15, Availability of Us Food & Drug Administration (FDA) Approved Potassium Iodide for Use in Emergencies Involving Radioactive Iodine (18 April 1988, Topic: Water hammer, Potassium iodide)
- Information Notice 1988-15, Availability of Us Food & Drug Administration (Fda) Approved Potassium Iodide for Use in Emergencies Involving Radioactive Iodine (18 April 1988, Topic: Water hammer, Potassium iodide)
- Information Notice 1988-16, Identify Waste Generators in Shipments of Low-Level Waste to Land Disposal Facilities (22 April 1988, Topic: Water hammer)
- Information Notice 1988-17, Summary of Responses to NRC Bulletin 87-01, Thinning of Pipe Walls in Nuclear Power Plants. (22 April 1988, Topic: Safe Shutdown, Weld Overlay, Feedwater Heater, Through-Wall Leak, Water hammer)
- Information Notice 1988-18, Malfunction of Lockbox on Radiography Device (25 April 1988, Topic: Overexposure)
- Information Notice 1988-19, Questionable Certification of Class Ie Components (26 April 1988, Topic: Water hammer)
- Information Notice 1988-19, Questionable Certification of Class IE Components (26 April 1988)
- Information Notice 1988-20, Unauthorized Individuals Manipulating Controls and Performing Control Room Activities (5 May 1988)
- Information Notice 1988-21, Inadvertent Criticality Events at Oskarshamn and at U.S. Nuclear Power Plants (9 May 1988, Topic: Shutdown Margin)
- Information Notice 1988-22, Disposal of Sludge from Onsite Sewage Treatment Facilities at Nuclear Power Stations (12 May 1988)
- Information Notice 1988-23, Potential for Gas Binding of High-Pressure Safety Injection Pumps During a Loss-Of-Coolant Accident (12 May 1988)
- Information Notice 1988-24, Failures of Air-Operated Valves Affecting Safety-Related Systems (13 May 1988)
- Information Notice 1988-25, Minimum Edge Distance for Expansion Anchor Bolts (16 May 1988, Topic: Earthquake)
- Information Notice 1988-26, Falsified Pre-Employment Screening Records (16 May 1988)
- Information Notice 1988-27, Deficient Electrical Terminations Identified in Safety-Related Components (18 May 1988)
- Information Notice 1988-28, Potential for Loss of Post-Loca Recirculation Capability Due to Insulation Debris Blockage (19 May 1988, Topic: Coatings)
- Information Notice 1988-29, Deficiencies in Primary Containment Low-Voltage Electrical Penetration Assemblies (24 May 1988)
- Information Notice 1988-30, Target Rock Two-State SRV Setpoint Drift Update (25 May 1988)
- Information Notice 1988-31, Steam Generator Tube Rupture Analysis Deficiency (25 May 1988)
- Information Notice 1988-32, Prompt Reporting to NRC of Significant Incidents Involving Radioactive Material (25 May 1988, Topic: Overexposure)
- Information Notice 1988-33, Recent Problems Involving the Model Spec 2-T Radiographic Exposure Device (27 May 1988, Topic: Depleted uranium)
- Information Notice 1988-34, Nuclear Material Control & Accountability of Non-Fuel Special Nuclear Material at Power Reactors (31 May 1988)
- Information Notice 1988-36, Possible Sudden Loss of RCS Inventory During Low Coolant Level Operation (8 June 1988)
- Information Notice 1988-37, Flow Blockage of Cooling Water to Safety System Components (14 June 1988, Topic: Ultimate heat sink)
- Information Notice 1988-38, Failure of Undervoltage Trip Attachment of General Electric Circuit Breakers (15 June 1988)
- Information Notice 1988-39, Loss of Recirculation Pumps with Power Oscillation Event (15 June 1988, Topic: Feedwater Heater)
- Information Notice 1988-40, Examiners' Handbook for Developing Operator Licensing Examinations (22 June 1988)
- Information Notice 1988-41, Physical Protection Weaknesses Identified Through Regulatory Effectiveness Reviews (RERs) (22 June 1988)
- Information Notice 1988-41, Physical Protection Weaknesses Identified Through Regulatory Effectiveness Reviews (Rers) (22 June 1988)
- Information Notice 1988-42, Circuit Breaker Failures Due to Loose Charging Spring Motor Mounting Bolts (23 June 1988, Topic: Locktite)
- Information Notice 1988-43, Solenoid Valve Problems (23 June 1988, Topic: Stroke time)
- Information Notice 1988-44, Mechanical Binding of Spring Release Device in Westinghouse Type DS-416 Circuit Breakers (24 June 1988)
- Information Notice 1988-45, Problems in Protective Relay & Circuit Breaker Coordination (7 July 1988, Topic: Safe Shutdown)
- Information Notice 1988-46, Licensee Report of Defective Refurbished Circuit Breakers (8 July 1988)
- Information Notice 1988-47, Slower-than-Expected Rod-drop Times (14 July 1988)
... further results |
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