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| ==Description of Circumstances== | | ==Description of Circumstances== |
| :Washington Public Power Supply System (WPPSS) Unit 2On July 21, 1983, emergency diesel generator (DG) 1A had high vibration levelreadings accompanied by sparks from the rotor shaft bearing area. Upon disas-sembly it was determined that a shim, required to maintain clearance at thethrust bearing, was missing. Inspection of DG 1B showed that the same shim wasmissing. The two generators were returned to EPI (Cleveland, Ohio) where themissing shim was installed and the damaged areas refurbished. The originaldesign, which placed electrical insulation between the rotor shaft and theslip-ring end bearing inner race, was maintained.On July 9, 1984, during monthly surveillance testing, a high vibration alarmwas observed on emergency DG 1B. Investigation after completion of the 4-hourtest revealed that the slip-ring end bearing had turned on the shaft insulationdestroying the insulation. The reduction in insulation cross sectional thick-ness allowed the rotor shaft to drop slightly and rub on the bearing housing.The corrective action employed after this failure was a design modification.The insulation between the bearing and the shaft was removed and the bearingwas mounted directly on the shaft. The bearing housing was insulated to providethe required electrical insulation. No failure has-been reported since thereported test failure in July 1984.8604150542 | | :Washington Public Power Supply System (WPPSS) Unit 2On July 21, 1983, emergency diesel generator (DG) 1A had high vibration levelreadings accompanied by sparks from the rotor shaft bearing area. Upon disas-sembly it was determined that a shim, required to maintain clearance at thethrust bearing, was missing. Inspection of DG 1B showed that the same shim wasmissing. The two generators were returned to EPI (Cleveland, Ohio) where themissing shim was installed and the damaged areas refurbished. The originaldesign, which placed electrical insulation between the rotor shaft and theslip-ring end bearing inner race, was maintained.On July 9, 1984, during monthly surveillance testing, a high vibration alarmwas observed on emergency DG 1B. Investigation after completion of the 4-hourtest revealed that the slip-ring end bearing had turned on the shaft insulationdestroying the insulation. The reduction in insulation cross sectional thick-ness allowed the rotor shaft to drop slightly and rub on the bearing housing.The corrective action employed after this failure was a design modification.The insulation between the bearing and the shaft was removed and the bearingwas mounted directly on the shaft. The bearing housing was insulated to providethe required electrical insulation. No failure has-been reported since thereported test failure in July 1984.8604150542 |
| * IN 86-26April 17. 19v6 Grand Gulf Unit 1 K>At Grand Gulf Unit 1, the high pressure core spray pump is powered by a dedicateuDG. On July 13, 1985, during surveillance testing, the generator failed and wasobserved to be emitting sparks. Power Systems Division (PSD) of Morrison Knudsen,the supplier of the DG unit, determined that the electrical insulation betweenthe inner race of the cylindrical roller bearing at the slip-ring end and therotor shaft had degraded. The degradation allowed the shaft to drop down andrub the inner and outer oil seals causing the sparks. EPI and PSD have developeda procedure to implement the same design modification at Grand Gulf as usedpreviously at WPPSS.Watts Bar Unit 2On June 10, 1983, during the performance of a test, the generator shaft wasobserved to be rubbing against the inner and outer oil seals at the slip-ringend. Examination after disassembly revealed that the thickness of the oilthrower was less than specified, causing a mismatch between the inner and outerraces of the slip-ring end bearing that resulted in the inner race breakingloose and turning on the underlying electrical insulation.The repairs at a Tennessee Valley Authority (TVA) workshop consisted of rebuil-ding oil seals, polishing the shaft under the oil seals, replacing the insula-tion material under the bearing, machining the bearing housing cap to correctthe alignment, adding a shim to restrain the outer race, and installing newbearings. TVA inspected four other generators and made similar modifications.Background:The failures occurred in electrical generators manufactured at EPI located inCleveland, Ohio. EPI was a division of Portec from 1969-1979. In 1979, Portecsold EPI to Northern Electrical Industries-Parsons Peebles (NEI-Peebles) ofGreat Britain. The manufacturing operations at Cleveland ceased in the Fall of1984. Currently, EPI furnishes spare parts and modifications to existing units.Discussion:The failures described above have all occurred at the slip-ring end of the tandemdiesel engine configurations. Installation of the insulation between the rotorshaft and the bearing also is used for single engine applications and in somecases it is installed under the shaft bearing at the other end of the generatoras well. The purpose of the insulation (3M Scotchply brand, type 1009, glass/epoxycomposite tape) is to prevent circulating currents through the generator shaft.This insulation method was limited by EPI to 8-pole 900-rpm machines. Theinitiating failure mechanism of the insulation has been attributed by varioussources to insulation creep fatigue, misalignment of the engines, poor insulationworkmanship, or inadequate original design. The first WPPSS and the Watts Barfailures appear-to be isolated cases of improperly machined pieces; however, thefailures manifest themselves in a similar manner and may be discovered during thechecks for insulation damag IN 86-26April 17, 1986 PSD has stated that a procedure to monitor shaft movement will have to be specificfor each plant because of design differences that impact the allowable movementand the jacking force. Jacking the shaft up and down and recording the movementwill determine the vertical play between the shaft and bearing housing, out careshould be taken to use a load cell or circle force gauge between the jack andthe generator shaft to prevent damage.Other suppliers that have used EPI generators include Stewart & Stevenson, Alcoand Bruce GM (EMD). See Attachment 1 for a list of facilities identified oyEPI and PSD as recipients of the subject generators. Some of the generatorsnave been resold from the original customer or user and some have been cancelled;therefore specific plant applications may be different than originally supplied.No specific action or written response is required by this notice. If you naveany questions regarding this notice, please contact the Regional Aaministratorof the appropriate NRC regional office or this office.X\visli/fEdward L ordan, DirectorDivisior of Emergency Preparednessand Engineering ResponseOffice of Inspection and EnforcementTecnnical Contacts: James C. Stewart, IE(301) 492-9061K.R. Naidu, IE(301) 492-4179 | | * IN 86-26April 17. 19v6 Grand Gulf Unit 1 K>At Grand Gulf Unit 1, the high pressure core spray pump is powered by a dedicateuDG. On July 13, 1985, during surveillance testing, the generator failed and wasobserved to be emitting sparks. Power Systems Division (PSD) of Morrison Knudsen,the supplier of the DG unit, determined that the electrical insulation betweenthe inner race of the cylindrical roller bearing at the slip-ring end and therotor shaft had degraded. The degradation allowed the shaft to drop down andrub the inner and outer oil seals causing the sparks. EPI and PSD have developeda procedure to implement the same design modification at Grand Gulf as usedpreviously at WPPSS.Watts Bar Unit 2On June 10, 1983, during the performance of a test, the generator shaft wasobserved to be rubbing against the inner and outer oil seals at the slip-ringend. Examination after disassembly revealed that the thickness of the oilthrower was less than specified, causing a mismatch between the inner and outerraces of the slip-ring end bearing that resulted in the inner race breakingloose and turning on the underlying electrical insulation.The repairs at a Tennessee Valley Authority (TVA) workshop consisted of rebuil-ding oil seals, polishing the shaft under the oil seals, replacing the insula-tion material under the bearing, machining the bearing housing cap to correctthe alignment, adding a shim to restrain the outer race, and installing newbearings. TVA inspected four other generators and made similar modifications.Background:The failures occurred in electrical generators manufactured at EPI located inCleveland, Ohio. EPI was a division of Portec from 1969-1979. In 1979, Portecsold EPI to Northern Electrical Industries-Parsons Peebles (NEI-Peebles) ofGreat Britain. The manufacturing operations at Cleveland ceased in the Fall of1984. Currently, EPI furnishes spare parts and modifications to existing units.Discussion:The failures described above have all occurred at the slip-ring end of the tandemdiesel engine configurations. Installation of the insulation between the rotorshaft and the bearing also is used for single engine applications and in somecases it is installed under the shaft bearing at the other end of the generatoras well. The purpose of the insulation (3M Scotchply brand, type 1009, glass/epoxycomposite tape) is to prevent circulating currents through the generator shaft.This insulation method was limited by EPI to 8-pole 900-rpm machines. Theinitiating failure mechanism of the insulation has been attributed by varioussources to insulation creep fatigue, misalignment of the engines, poor insulationworkmanship, or inadequate original design. The first WPPSS and the Watts Barfailures appear-to be isolated cases of improperly machined pieces; however, thefailures manifest themselves in a similar manner and may be discovered during thechecks for insulation damage. |
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| ===Attachments:===
| | IN 86-26April 17, 1986 PSD has stated that a procedure to monitor shaft movement will have to be specificfor each plant because of design differences that impact the allowable movementand the jacking force. Jacking the shaft up and down and recording the movementwill determine the vertical play between the shaft and bearing housing, out careshould be taken to use a load cell or circle force gauge between the jack andthe generator shaft to prevent damage.Other suppliers that have used EPI generators include Stewart & Stevenson, Alcoand Bruce GM (EMD). See Attachment 1 for a list of facilities identified oyEPI and PSD as recipients of the subject generators. Some of the generatorsnave been resold from the original customer or user and some have been cancelled;therefore specific plant applications may be different than originally supplied.No specific action or written response is required by this notice. If you naveany questions regarding this notice, please contact the Regional Aaministratorof the appropriate NRC regional office or this office.X\visli/fEdward L ordan, DirectorDivisior of Emergency Preparednessand Engineering ResponseOffice of Inspection and EnforcementTecnnical Contacts: James C. Stewart, IE(301) 492-9061K.R. Naidu, IE(301) 492-4179Attachments:I. List of EPI 900 RPM Generators2. List of Recently Issued IE Information Notices |
| I. List of EPI 900 RPM Generators2. List of Recently Issued IE Information Notices Attachment 1IN 86-26April 17, 1986 Domestic EPI 900 RPM GeneratorsCustomer/SiteNo. UnitsD/G SupplierArkansas P&L/Nuclear 1Boston Edison/Pilgrim 1Duke Power/OconeeFlorida P&L/St. LucieHouston L&P/Allens CreekJersey Central P&L/Oyster CreekMississippi P&L/Grand GulfMississippi P&L/Grand GulfNew York State PowerAuthority/FitzPatrickPacific G&E/Diablo CanyonPortland G&E/TrojanPublic Service of Oklahoma/Black FoxPuget Sound/SkaggitSMUD/Rancho SecoTVA/Hartsville, Phipps BendTVA/SequayahTVA/SequayahTVA/Watts BarVepco/North AnnaWPPSS/Hanford 122121222452212641642(See Note 1)(See Note 2)(See Note 3)(See Note 4)Stewart & StevensonALCOPSDPSDPSDPSDPSDBruce GM (EMD)Bruce GM (EMD)ALCOPSDPSDPSDBruce GM (EMD)PSDBruce GM (EMD)PSDPSDStewart & StevensonStewart & StevensonNotes: 1. Generator returned to PSD2. Obtained from TVA3. One unit sent to foreign plant, one unit spare4. Two units to Oyster Creek, three units sent to foreign plants,one unit sent to NASA Attachnient 2IIN 86-26April 17, 1986LIST OF RECENTLY ISSUEDIE INFORMATION NOTICESInformation Date ofNotice No. Subject Issue __Issued to-86-25Traceability And MaterialControl Of Material AndEquipment, ParticularlyFasteners4/11/8686-24Respirator Users Notice: 4/11/86Increased Inspection FrequencyFor Certain Self-ContainedBreathing Apparatus AirCylinders86-2386-2286-21Excessive Skin Exposures DueTo Contamination With HotParticlesUnderresponse Of RaditionSurvey Instrument To HighRadiation FieldsRecognition Of AmericanSociety Of MechanicalEngineers AccreditationProgram For N Stamp HoldersLow-Level Radioactive WasteScaling Factors, 10 CFRPart 61Reactor Coolant Pump ShaftFailure At Crystal RiverNRC On-Scene Response DuringA Major Emergency4/9/863/31/863/31/863/28/863/21/863/26/86All power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL or CP; researchand test reactorfacilities; fuelcycle licensees andPriority 1 materiallicenseesAll power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL or CP andresearch and testreactorsAll power reactorfacilities holdingan OL or CP and allrecipients of NUREG-0040 (white book)All power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL or CP86-2086-1986-18OL = Operating LicenseCP = Construction Permit}} | | |
| | Attachment 1IN 86-26April 17, 1986 Domestic EPI 900 RPM GeneratorsCustomer/SiteNo. UnitsD/G SupplierArkansas P&L/Nuclear 1Boston Edison/Pilgrim 1Duke Power/OconeeFlorida P&L/St. LucieHouston L&P/Allens CreekJersey Central P&L/Oyster CreekMississippi P&L/Grand GulfMississippi P&L/Grand GulfNew York State PowerAuthority/FitzPatrickPacific G&E/Diablo CanyonPortland G&E/TrojanPublic Service of Oklahoma/Black FoxPuget Sound/SkaggitSMUD/Rancho SecoTVA/Hartsville, Phipps BendTVA/SequayahTVA/SequayahTVA/Watts BarVepco/North AnnaWPPSS/Hanford 122121222452212641642(See Note 1)(See Note 2)(See Note 3)(See Note 4)Stewart & StevensonALCOPSDPSDPSDPSDPSDBruce GM (EMD)Bruce GM (EMD)ALCOPSDPSDPSDBruce GM (EMD)PSDBruce GM (EMD)PSDPSDStewart & StevensonStewart & StevensonNotes: 1. Generator returned to PSD2. Obtained from TVA3. One unit sent to foreign plant, one unit spare4. Two units to Oyster Creek, three units sent to foreign plants,one unit sent to NASA |
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| | Attachnient 2IIN 86-26April 17, 1986LIST OF RECENTLY ISSUEDIE INFORMATION NOTICESInformation Date ofNotice No. Subject Issue __Issued to-86-25Traceability And MaterialControl Of Material AndEquipment, ParticularlyFasteners4/11/8686-24Respirator Users Notice: 4/11/86Increased Inspection FrequencyFor Certain Self-ContainedBreathing Apparatus AirCylinders86-2386-2286-21Excessive Skin Exposures DueTo Contamination With HotParticlesUnderresponse Of RaditionSurvey Instrument To HighRadiation FieldsRecognition Of AmericanSociety Of MechanicalEngineers AccreditationProgram For N Stamp HoldersLow-Level Radioactive WasteScaling Factors, 10 CFRPart 61Reactor Coolant Pump ShaftFailure At Crystal RiverNRC On-Scene Response DuringA Major Emergency4/9/863/31/863/31/863/28/863/21/863/26/86All power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL or CP; researchand test reactorfacilities; fuelcycle licensees andPriority 1 materiallicenseesAll power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL or CP andresearch and testreactorsAll power reactorfacilities holdingan OL or CP and allrecipients of NUREG-0040 (white book)All power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL or CP86-2086-1986-18OL = Operating LicenseCP = Construction Permit |
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Potential Problems in Generators Manufactured by Electrical Products IncorporatedML031220661 |
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, Skagit, Marble Hill |
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Issue date: |
04/17/1986 |
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From: |
Jordan E L NRC/IE |
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To: |
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References |
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IN-86-026, NUDOCS 8604150542 |
Download: ML031220661 (5) |
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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 |
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Category:NRC Information Notice
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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>. |
SSINS No.: 6835IN 86-26UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF INSPECTION AND ENFORCEMENTWASHINGTON, D.C. 20555April 17, 1986INFORMATION NOTICE NO. 86-26: POTENT1AL PROBLEMS IN GENERATORS MANUFACTUREDBY ELECTRICAL PRODUCTS INCORPORATED
Addressees
- All nuclear power reactor facilities holding an operating license (OL) or aconstruction permit (CP).
Purpose
- This notice is to alert recipients to a potentially significant problem involvingthe failure of Electrical Products Incorporated (EPI) diesel generators withoutprior warning during an emergency demand. Actions taken by licensees to preventrecurrence also are discussed. It is expected that recipients will review thisinformation for applicability to their facilities and consider actions, ifappropriate, to preclude a similar problem occurring at their facilities.However, suggestions-contained in this information notice do not constitute NRCrequirements; therefore, no specific action or written response is required.
Description of Circumstances
- Washington Public Power Supply System (WPPSS) Unit 2On July 21, 1983, emergency diesel generator (DG) 1A had high vibration levelreadings accompanied by sparks from the rotor shaft bearing area. Upon disas-sembly it was determined that a shim, required to maintain clearance at thethrust bearing, was missing. Inspection of DG 1B showed that the same shim wasmissing. The two generators were returned to EPI (Cleveland, Ohio) where themissing shim was installed and the damaged areas refurbished. The originaldesign, which placed electrical insulation between the rotor shaft and theslip-ring end bearing inner race, was maintained.On July 9, 1984, during monthly surveillance testing, a high vibration alarmwas observed on emergency DG 1B. Investigation after completion of the 4-hourtest revealed that the slip-ring end bearing had turned on the shaft insulationdestroying the insulation. The reduction in insulation cross sectional thick-ness allowed the rotor shaft to drop slightly and rub on the bearing housing.The corrective action employed after this failure was a design modification.The insulation between the bearing and the shaft was removed and the bearingwas mounted directly on the shaft. The bearing housing was insulated to providethe required electrical insulation. No failure has-been reported since thereported test failure in July 1984.8604150542
- IN 86-26April 17. 19v6 Grand Gulf Unit 1 K>At Grand Gulf Unit 1, the high pressure core spray pump is powered by a dedicateuDG. On July 13, 1985, during surveillance testing, the generator failed and wasobserved to be emitting sparks. Power Systems Division (PSD) of Morrison Knudsen,the supplier of the DG unit, determined that the electrical insulation betweenthe inner race of the cylindrical roller bearing at the slip-ring end and therotor shaft had degraded. The degradation allowed the shaft to drop down andrub the inner and outer oil seals causing the sparks. EPI and PSD have developeda procedure to implement the same design modification at Grand Gulf as usedpreviously at WPPSS.Watts Bar Unit 2On June 10, 1983, during the performance of a test, the generator shaft wasobserved to be rubbing against the inner and outer oil seals at the slip-ringend. Examination after disassembly revealed that the thickness of the oilthrower was less than specified, causing a mismatch between the inner and outerraces of the slip-ring end bearing that resulted in the inner race breakingloose and turning on the underlying electrical insulation.The repairs at a Tennessee Valley Authority (TVA) workshop consisted of rebuil-ding oil seals, polishing the shaft under the oil seals, replacing the insula-tion material under the bearing, machining the bearing housing cap to correctthe alignment, adding a shim to restrain the outer race, and installing newbearings. TVA inspected four other generators and made similar modifications.Background:The failures occurred in electrical generators manufactured at EPI located inCleveland, Ohio. EPI was a division of Portec from 1969-1979. In 1979, Portecsold EPI to Northern Electrical Industries-Parsons Peebles (NEI-Peebles) ofGreat Britain. The manufacturing operations at Cleveland ceased in the Fall of1984. Currently, EPI furnishes spare parts and modifications to existing units.Discussion:The failures described above have all occurred at the slip-ring end of the tandemdiesel engine configurations. Installation of the insulation between the rotorshaft and the bearing also is used for single engine applications and in somecases it is installed under the shaft bearing at the other end of the generatoras well. The purpose of the insulation (3M Scotchply brand, type 1009, glass/epoxycomposite tape) is to prevent circulating currents through the generator shaft.This insulation method was limited by EPI to 8-pole 900-rpm machines. Theinitiating failure mechanism of the insulation has been attributed by varioussources to insulation creep fatigue, misalignment of the engines, poor insulationworkmanship, or inadequate original design. The first WPPSS and the Watts Barfailures appear-to be isolated cases of improperly machined pieces; however, thefailures manifest themselves in a similar manner and may be discovered during thechecks for insulation damage.
IN 86-26April 17, 1986 PSD has stated that a procedure to monitor shaft movement will have to be specificfor each plant because of design differences that impact the allowable movementand the jacking force. Jacking the shaft up and down and recording the movementwill determine the vertical play between the shaft and bearing housing, out careshould be taken to use a load cell or circle force gauge between the jack andthe generator shaft to prevent damage.Other suppliers that have used EPI generators include Stewart & Stevenson, Alcoand Bruce GM (EMD). See Attachment 1 for a list of facilities identified oyEPI and PSD as recipients of the subject generators. Some of the generatorsnave been resold from the original customer or user and some have been cancelled;therefore specific plant applications may be different than originally supplied.No specific action or written response is required by this notice. If you naveany questions regarding this notice, please contact the Regional Aaministratorof the appropriate NRC regional office or this office.X\visli/fEdward L ordan, DirectorDivisior of Emergency Preparednessand Engineering ResponseOffice of Inspection and EnforcementTecnnical Contacts: James C. Stewart, IE(301) 492-9061K.R. Naidu, IE(301) 492-4179Attachments:I. List of EPI 900 RPM Generators2. List of Recently Issued IE Information Notices
Attachment 1IN 86-26April 17, 1986 Domestic EPI 900 RPM GeneratorsCustomer/SiteNo. UnitsD/G SupplierArkansas P&L/Nuclear 1Boston Edison/Pilgrim 1Duke Power/OconeeFlorida P&L/St. LucieHouston L&P/Allens CreekJersey Central P&L/Oyster CreekMississippi P&L/Grand GulfMississippi P&L/Grand GulfNew York State PowerAuthority/FitzPatrickPacific G&E/Diablo CanyonPortland G&E/TrojanPublic Service of Oklahoma/Black FoxPuget Sound/SkaggitSMUD/Rancho SecoTVA/Hartsville, Phipps BendTVA/SequayahTVA/SequayahTVA/Watts BarVepco/North AnnaWPPSS/Hanford 122121222452212641642(See Note 1)(See Note 2)(See Note 3)(See Note 4)Stewart & StevensonALCOPSDPSDPSDPSDPSDBruce GM (EMD)Bruce GM (EMD)ALCOPSDPSDPSDBruce GM (EMD)PSDBruce GM (EMD)PSDPSDStewart & StevensonStewart & StevensonNotes: 1. Generator returned to PSD2. Obtained from TVA3. One unit sent to foreign plant, one unit spare4. Two units to Oyster Creek, three units sent to foreign plants,one unit sent to NASA
Attachnient 2IIN 86-26April 17, 1986LIST OF RECENTLY ISSUEDIE INFORMATION NOTICESInformation Date ofNotice No. Subject Issue __Issued to-86-25Traceability And MaterialControl Of Material AndEquipment, ParticularlyFasteners4/11/8686-24Respirator Users Notice: 4/11/86Increased Inspection FrequencyFor Certain Self-ContainedBreathing Apparatus AirCylinders86-2386-2286-21Excessive Skin Exposures DueTo Contamination With HotParticlesUnderresponse Of RaditionSurvey Instrument To HighRadiation FieldsRecognition Of AmericanSociety Of MechanicalEngineers AccreditationProgram For N Stamp HoldersLow-Level Radioactive WasteScaling Factors, 10 CFRPart 61Reactor Coolant Pump ShaftFailure At Crystal RiverNRC On-Scene Response DuringA Major Emergency4/9/863/31/863/31/863/28/863/21/863/26/86All power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL or CP; researchand test reactorfacilities; fuelcycle licensees andPriority 1 materiallicenseesAll power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL or CP andresearch and testreactorsAll power reactorfacilities holdingan OL or CP and allrecipients of NUREG-0040 (white book)All power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL or CP86-2086-1986-18OL = Operating LicenseCP = Construction Permit
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list | - Information Notice 1986-01, Failure of Main Feedwater Check Valves Causes Loss of Feedwater System Integrity and Water-Hammer Damage (6 January 1986)
- Information Notice 1986-02, Failure of Valve Operator Motor During Environmental Qualification Testing (6 January 1986)
- Information Notice 1986-03, Potential Deficiencies in Enviromental Qualification of Limitorque Motor Valve Operator Wiring (14 January 1986)
- Information Notice 1986-04, Transient Due to Loss of Power to Intergrated Control System at a Pressurized Water Reactor Designed by Babcock & Wilcox (31 January 1986)
- Information Notice 1986-05, Main Steam Safety Valve Test Failures and Ring Setting Adjustments (31 January 1986)
- Information Notice 1986-06, Failure of Lifting Rig Attachment, While Lifting Upper Guide Structure at St. Lucie Unit 1 (3 February 1986, Topic: Control of Heavy Loads)
- Information Notice 1986-06, Failure of Lifting Rig Attachment, while Lifting Upper Guide Structure at St. Lucie Unit 1 (3 February 1986)
- Information Notice 1986-07, Lack of Detailed Instruction & Inadequate Observance of Precautions During Maintenance & Testing of Diesel Generator Woodward Governors (3 February 1986)
- Information Notice 1986-08, Licensee Event Report (LER) Format Modification (3 February 1986)
- Information Notice 1986-09, Failure of Check & Stop Check Valves Subjected to Low Flow Conditions (3 February 1986)
- Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion. (5 January 1995, Topic: Boric Acid)
- Information Notice 1986-10, Feedwater Line Break (10 November 1988, Topic: Coatings, Anchor Darling)
- Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion. (5 January 1995, Topic: Boric Acid)
- Information Notice 1986-11, Anomalous Behavior of Recirculation Loop Flow in Jet Pump BWR Plants (31 December 1986)
- Information Notice 1986-13, Standby Liquid Control System Squib Valves Failure to Fire (21 February 1986, Topic: Squib)
- Information Notice 1986-13, Standby Liquid Control Squib Valves Failure to Fire (5 August 1986, Topic: Squib)
- Information Notice 1986-14, Overspeed Trips of AFW, HPCI & RCIC Turbines (26 August 1991, Topic: Fire Barrier)
- Information Notice 1986-14, Overspeed Trips of Afw, HPCI & RCIC Turbines (26 August 1991)
- Information Notice 1986-15, Loss of Offsite Power Caused by Problems in Fiber Optics Systems (10 March 1986, Topic: Squib)
- Information Notice 1986-16, Failures to Identify Containment Leakage Due to Inadequate Local Testing of BWR Vacuum Relief System Valves (11 March 1986, Topic: Squib)
- Information Notice 1986-17, Update of Failure of Automatic Sprinkler System Valves to Operate (24 March 1986, Topic: Squib)
- Information Notice 1986-18, NRC On-Scene Response During a Major Emergency (26 March 1986, Topic: Squib, Backfit)
- Information Notice 1986-19, Reactor Coolant Pump Shaft Failure at Crystal River (21 March 1986, Topic: Squib)
- Information Notice 1986-20, Low-Level Radioactive Waste Scaling Factors, 10 CFR Part 61 (28 March 1986, Topic: Squib)
- Information Notice 1986-21, Recognition of American Society of Mechanical Engineers Accreditation Program for N Stamp Holders (31 March 1986, Topic: Squib)
- Information Notice 1986-22, Underresponse of Radiation Survey Instrument to High Radiation Fields (31 March 1986, Topic: High Radiation Area, Squib)
- Information Notice 1986-23, Excessive Skin Exposures Due to Contamination with Hot Particles (9 April 1986)
- Information Notice 1986-23, Excessive Skin Exposures due to Contamination with Hot Particles (9 April 1986)
- Information Notice 1986-24, Respirator Users Notice: Increased Inspection Frequency for Certain Self-Contained Breathing Apparatus Air Cylinders (11 April 1986, Topic: Hydrostatic)
- Information Notice 1986-25, Traceability and Material Control of Material and Equipment, Particularly Fasteners (11 April 1986)
- Information Notice 1986-26, Potential Problems in Generators Manufactured by Electrical Products Incorporated (17 April 1986)
- Information Notice 1986-27, Access Control at Nuclear Facilities (21 April 1986, Topic: Contraband)
- Information Notice 1986-28, Telephone Numbers to the NRC Operations Center and Regional Offices (24 April 1986)
- Information Notice 1986-29, Effects of Changing Valve Moter-Operator Switch Settings (25 April 1986)
- Information Notice 1986-30, Design Limitations of Gaseous Effluent Monitoring Systems (29 April 1986)
- Information Notice 1986-31, Unauthorized Transfer and Loss of Control of Industrial Nuclear Gauges (14 July 1986)
- Information Notice 1986-32, Request for Collection of Licensee Radioactivity Measurements Attributed to Chernobyl Nuclear Plant Accident (2 May 1986, Topic: Chernobyl)
- Information Notice 1986-33, Information for Licensee Regarding the Chernobyl Nuclear Plant Accident (6 May 1986, Topic: Chernobyl)
- Information Notice 1986-34, Improper Assembly, Material Selection, & Test of Valves & Their Actuators (13 May 1986)
- Information Notice 1986-34, Improper Assembly, Material Selection, & Test of Valves & their Actuators (13 May 1986)
- Information Notice 1986-35, Fire in Compressible Material at Dresden Unit 3 (15 May 1986, Topic: Chernobyl)
- Information Notice 1986-36, Change in NRC Practice Regarding Issuance of Confirming Letters to Principal Contractors (16 May 1986, Topic: Chernobyl)
- Information Notice 1986-37, Degradation of Station Batteries (16 May 1986, Topic: Chernobyl)
- Information Notice 1986-38, Deficient Operator Actions Following Dual Function Valve Failures (20 May 1986, Topic: Chernobyl)
- Information Notice 1986-39, Failures of RHR Pump Motors and Pump Internals (20 May 1986, Topic: Chernobyl)
- Information Notice 1986-40, Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in Bwrs (5 June 1986, Topic: Chernobyl)
- Information Notice 1986-40, Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in BWRs (5 June 1986, Topic: Chernobyl)
- Information Notice 1986-41, Evaluation of Questionable Exposure Readings of Licensee Personnel Dosimeters (9 June 1986, Topic: Chernobyl)
- Information Notice 1986-42, Improper Maintenance of Radiation Monitoring Systems (9 June 1986, Topic: Temporary Modification, Chernobyl)
- Information Notice 1986-43, Problems with Silver Zeolite Sampling of Airborne Radioiodine (10 June 1986, Topic: Chernobyl)
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