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| | issue date = 04/17/1986 | | | issue date = 04/17/1986 |
| | title = Potential Problems in Generators Manufactured by Electrical Products Incorporated | | | title = Potential Problems in Generators Manufactured by Electrical Products Incorporated |
| | author name = Jordan E L | | | author name = Jordan E |
| | author affiliation = NRC/IE | | | author affiliation = NRC/IE |
| | addressee name = | | | addressee name = |
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| | page count = 5 | | | page count = 5 |
| }} | | }} |
| {{#Wiki_filter:SSINS No.: 6835 IN 86-26 UNITED STATES NUCLEAR REGULATORY | | {{#Wiki_filter:SSINS No.: 6835 IN 86-26 UNITED STATES |
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| COMMISSION | | NUCLEAR REGULATORY COMMISSION |
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| OFFICE OF INSPECTION | | OFFICE OF INSPECTION AND ENFORCEMENT |
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| ===AND ENFORCEMENT===
| | WASHINGTON, D.C. 20555 April 17, 1986 INFORMATION NOTICE NO. 86-26: POTENT1AL PROBLEMS IN GENERATORS MANUFACTURED |
| WASHINGTON, D.C. 20555 April 17, 1986 INFORMATION | |
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| |
|
| NOTICE NO. 86-26: POTENT1AL
| | BY ELECTRICAL PRODUCTS INCORPORATED |
| | |
| PROBLEMS IN GENERATORS
| |
| | |
| ===MANUFACTURED===
| |
| BY ELECTRICAL | |
| | |
| ===PRODUCTS INCORPORATED===
| |
|
| |
|
| ==Addressees== | | ==Addressees== |
| : | | : |
| All nuclear power reactor facilities | | All nuclear power reactor facilities holding an operating license (OL) or a |
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| |
|
| holding an operating
| | construction permit (CP). |
| | |
| license (OL) or a construction
| |
| | |
| permit (CP). | |
|
| |
|
| ==Purpose== | | ==Purpose== |
| : This notice is to alert recipients | | : |
| | This notice is to alert recipients to a potentially significant problem involving |
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| |
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| to a potentially
| | the failure of Electrical Products Incorporated (EPI) diesel generators without |
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| significant
| | prior warning during an emergency demand. Actions taken by licensees to prevent |
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| problem involving the failure of Electrical
| | recurrence also are discussed. It is expected that recipients will review this |
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| |
|
| Products Incorporated (EPI) diesel generators
| | information for applicability to their facilities and consider actions, if |
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| |
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| without prior warning during an emergency
| | appropriate, to preclude a similar problem occurring at their facilities. |
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| |
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| demand. Actions taken by licensees
| | However, suggestions-contained in this information notice do not constitute NRC |
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| |
|
| to prevent recurrence
| | requirements; therefore, no specific action or written response is required. |
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| |
|
| also are discussed.
| | ==Description of Circumstances== |
| | | : |
| It is expected that recipients
| | Washington Public Power Supply System (WPPSS) Unit 2 On July 21, 1983, emergency diesel generator (DG) 1A had high vibration level |
| | |
| will review this information
| |
| | |
| for applicability
| |
| | |
| to their facilities
| |
| | |
| and consider actions, if appropriate, to preclude a similar problem occurring
| |
| | |
| at their facilities.
| |
| | |
| However, suggestions-contained
| |
| | |
| in this information
| |
| | |
| notice do not constitute
| |
| | |
| NRC requirements;
| |
| therefore, no specific action or written response is required.Description
| |
| | |
| of Circumstances: | |
| Washington | |
| | |
| Public Power Supply System (WPPSS) Unit 2 On July 21, 1983, emergency | |
| | |
| diesel generator (DG) 1A had high vibration | |
| | |
| level readings accompanied | |
| | |
| by sparks from the rotor shaft bearing area. Upon disas-sembly it was determined
| |
| | |
| that a shim, required to maintain clearance
| |
| | |
| at the thrust bearing, was missing. Inspection
| |
| | |
| of DG 1B showed that the same shim was missing. The two generators
| |
| | |
| were returned to EPI (Cleveland, Ohio) where the missing shim was installed
| |
| | |
| and the damaged areas refurbished.
| |
| | |
| The original design, which placed electrical
| |
| | |
| insulation
| |
| | |
| between the rotor shaft and the slip-ring
| |
| | |
| end bearing inner race, was maintained.
| |
| | |
| On July 9, 1984, during monthly surveillance
| |
| | |
| testing, a high vibration
| |
| | |
| alarm was observed on emergency
| |
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| DG 1B. Investigation
| |
| | |
| after completion
| |
| | |
| of the 4-hour test revealed that the slip-ring
| |
| | |
| end bearing had turned on the shaft insulation
| |
| | |
| destroying
| |
| | |
| 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.
| |
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| The insulation
| | readings accompanied by sparks from the rotor shaft bearing area. Upon disas- sembly it was determined that a shim, required to maintain clearance at the |
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| |
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| between the bearing and the shaft was removed and the bearing was mounted directly on the shaft. The bearing housing was insulated
| | thrust bearing, was missing. Inspection of DG 1B showed that the same shim was |
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| |
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| to provide the required electrical | | missing. The two generators were returned to EPI (Cleveland, Ohio) where the |
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| insulation.
| | missing shim was installed and the damaged areas refurbished. The original |
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| No failure has-been reported since the reported test failure in July 1984.8604150542
| | design, which placed electrical insulation between the rotor shaft and the |
| * IN 86-26 April 17. 19v6 Grand Gulf Unit 1 K>At Grand Gulf Unit 1, the high pressure core spray pump is powered by a dedicateu DG. On July 13, 1985, during surveillance
| |
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| testing, the generator
| | slip-ring end bearing inner race, was maintained. |
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| failed and was observed to be emitting sparks. Power Systems Division (PSD) of Morrison Knudsen, the supplier of the DG unit, determined
| | On July 9, 1984, during monthly surveillance testing, a high vibration alarm |
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| that the electrical
| | was observed on emergency DG 1B. Investigation after completion of the 4-hour |
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| insulation | | test revealed that the slip-ring end bearing had turned on the shaft insulation |
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| between the inner race of the cylindrical
| | destroying the insulation. The reduction in insulation cross sectional thick- ness allowed the rotor shaft to drop slightly and rub on the bearing housing. |
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| roller bearing at the slip-ring
| | The corrective action employed after this failure was a design modification. |
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| end and the rotor shaft had degraded.
| | The insulation between the bearing and the shaft was removed and the bearing |
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| The degradation | | was mounted directly on the shaft. The bearing housing was insulated to provide |
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| allowed the shaft to drop down and rub the inner and outer oil seals causing the sparks. EPI and PSD have developed a procedure
| | the required electrical insulation. No failure has-been reported since the |
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| to implement
| | reported test failure in July 1984. |
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| the same design modification
| | 8604150542 |
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|
| at Grand Gulf as used previously
| | * IN 86-26 April 17. 19v6 Grand Gulf Unit 1 K> |
| | At Grand Gulf Unit 1, the high pressure core spray pump is powered by |
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| at WPPSS.Watts Bar Unit 2 On June 10, 1983, during the performance
| | a dedicateu |
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| |
|
| of a test, the generator
| | DG. On July 13, 1985, during surveillance testing, the generator failed |
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| shaft was observed to be rubbing against the inner and outer oil seals at the slip-ring end. Examination
| | observed to be emitting sparks. Power Systems Division (PSD) of Morrison and was |
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| after disassembly
| | the supplier of the DG unit, determined that the electrical insulation Knudsen, the inner race of the cylindrical roller bearing at the slip-ring end between |
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| |
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| revealed that the thickness
| | rotor shaft had degraded. The degradation allowed the shaft to drop and the |
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| of the oil thrower was less than specified, causing a mismatch between the inner and outer races of the slip-ring
| | rub the inner and outer oil seals causing the sparks. EPI and PSD down and |
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| |
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| end bearing that resulted in the inner race breaking loose and turning on the underlying
| | a procedure to implement the same design modification at Grand Gulf have developed |
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| electrical
| | previously at WPPSS. as used |
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| |
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| insulation.
| | Watts Bar Unit 2 On June 10, 1983, during the performance of a test, the generator |
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| |
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| The repairs at a Tennessee
| | observed to be rubbing against the inner and outer oil seals at theshaft was |
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| |
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| Valley Authority (TVA) workshop consisted
| | end. Examination after disassembly revealed that the thickness of slip-ring |
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| |
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| of rebuil-ding oil seals, polishing
| | thrower was less than specified, causing a mismatch between the innerthe oil |
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| the shaft under the oil seals, replacing | | races of the slip-ring end bearing that resulted in the inner race and outer |
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| the insula-tion material under the bearing, machining | | loose and turning on the underlying electrical insulation. breaking |
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| the bearing housing cap to correct the alignment, adding a shim to restrain the outer race, and installing
| | The repairs at a Tennessee Valley Authority (TVA) workshop consisted |
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| new bearings.
| | ding oil seals, polishing the shaft under the oil seals, replacing of rebuil- the |
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| TVA inspected
| | tion material under the bearing, machining the bearing housing cap to insula- the alignment, adding a shim to restrain the outer race, and installingcorrect |
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| four other generators | | bearings. TVA inspected four other generators and made similar modifications.new |
| | |
| and made similar modifications. | |
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| |
|
| Background: | | Background: |
| The failures occurred in electrical | | The failures occurred in electrical generators manufactured at EPI located |
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| generators
| | Cleveland, Ohio. EPI was a division of Portec from 1969-1979. In 1979, in |
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| manufactured
| | sold EPI to Northern Electrical Industries-Parsons Peebles (NEI-Peebles) Portec |
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| at EPI located in Cleveland, Ohio. EPI was a division of Portec from 1969-1979. | | Great Britain. The manufacturing operations at Cleveland ceased in of |
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| In 1979, Portec sold EPI to Northern Electrical
| | the |
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| |
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| Industries-Parsons
| | 1984. Currently, EPI furnishes spare parts and modifications to existing Fall of |
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|
| Peebles (NEI-Peebles)
| | units. |
| of Great Britain. The manufacturing
| |
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| |
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| operations
| | Discussion: |
| | The failures described above have all occurred at the slip-ring end |
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| at Cleveland
| | diesel engine configurations. Installation of the insulation betweenof the tandem |
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| ceased in the Fall of 1984. Currently, EPI furnishes
| | the rotor |
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| spare parts and modifications
| | shaft and the bearing also is used for single engine applications and |
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| to existing units.Discussion:
| | cases it is installed under the shaft bearing at the other end of the in some |
| The failures described
| |
|
| |
|
| above have all occurred at the slip-ring
| | as well. The purpose of the insulation (3M Scotchply brand, type 1009,generator |
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| |
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| end of the tandem diesel engine configurations.
| | composite tape) is to prevent circulating currents through the generator glass/epoxy |
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| |
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| Installation
| | This insulation method was limited by EPI to 8-pole 900-rpm machines. shaft. |
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| |
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| of the insulation | | initiating failure mechanism of the insulation has been attributed by The |
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| |
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| between the rotor shaft and the bearing also is used for single engine applications
| | sources to insulation creep fatigue, misalignment of the engines, poor various |
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| |
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| and in some cases it is installed | | workmanship, or inadequate original design. The first WPPSS and the insulation |
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| |
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| under the shaft bearing at the other end of the generator as well. The purpose of the insulation
| | failures appear-to be isolated cases of improperly machined pieces; Watts Bar |
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| |
|
| (3M Scotchply
| | however, the |
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| |
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| brand, type 1009, glass/epoxy
| | failures manifest themselves in a similar manner and may be discovered |
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| |
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| composite
| | checks for insulation damage. during the |
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| |
|
| tape) is to prevent circulating
| | IN 86-26 April 17, 1986 PSD has stated that a procedure to monitor shaft movement will have to be specific |
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| |
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| currents through the generator
| | for each plant because of design differences that impact the allowable movement |
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| |
|
| shaft.This insulation | | and the jacking force. Jacking the shaft up and down and recording the movement |
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| |
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| method was limited by EPI to 8-pole 900-rpm machines.
| | will determine the vertical play between the shaft and bearing housing, out care |
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| |
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| The initiating
| | should be taken to use a load cell or circle force gauge between the jack and |
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| failure mechanism
| | the generator shaft to prevent damage. |
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| of the insulation
| | Other suppliers that have used EPI generators include Stewart & Stevenson, Alco |
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| |
|
| has been attributed
| | and Bruce GM (EMD). See Attachment 1 for a list of facilities identified oy |
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| by various sources to insulation
| | EPI and PSD as recipients of the subject generators. Some of the generators |
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| creep fatigue, misalignment
| |
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| of the engines, poor insulation
| |
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| workmanship, or inadequate
| |
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| original design. The first WPPSS and the Watts Bar failures appear-to
| |
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| be isolated cases of improperly
| |
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| |
| machined pieces; however, the failures manifest themselves
| |
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| in a similar manner and may be discovered
| |
|
| |
| during the checks for insulation
| |
|
| |
| damage.
| |
|
| |
| IN 86-26 April 17, 1986 PSD has stated that a procedure
| |
|
| |
| to monitor shaft movement will have to be specific for each plant because of design differences
| |
|
| |
| that impact the allowable
| |
|
| |
| movement and the jacking force. Jacking the shaft up and down and recording
| |
|
| |
| the movement will determine
| |
|
| |
| the vertical play between the shaft and bearing housing, out care should be taken to use a load cell or circle force gauge between the jack and the generator
| |
|
| |
| shaft to prevent damage.Other suppliers
| |
|
| |
| that have used EPI generators
| |
|
| |
| include Stewart & Stevenson, Alco and Bruce GM (EMD). See Attachment
| |
|
| |
| 1 for a list of facilities
| |
|
| |
| identified
| |
|
| |
| oy EPI and PSD as recipients
| |
|
| |
| of the subject generators.
| |
|
| |
| ===Some of the generators===
| |
| nave been resold from the original customer or user and some have been cancelled; | | nave been resold from the original customer or user and some have been cancelled; |
| therefore | | therefore specific plant applications may be different than originally supplied. |
| | |
| specific plant applications | |
| | |
| may be different | |
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| |
|
| than originally
| | No specific action or written response is required by this notice. If you nave |
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| |
|
| supplied.No specific action or written response is required by this notice. If you nave any questions
| | any questions regarding this notice, please contact the Regional Aaministrator |
|
| |
|
| regarding
| | of the appropriate NRC regional office or this office. |
|
| |
|
| this notice, please contact the Regional Aaministrator
| | X\visli/f |
|
| |
|
| of the appropriate
| | Edward L ordan, Director |
|
| |
|
| NRC regional office or this office.X\visli/f Edward L ordan, Director Divisior of Emergency
| | Divisior of Emergency Preparedness |
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| |
|
| ===Preparedness===
| | and Engineering Response |
| and Engineering | |
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| |
|
| Response Office of Inspection
| | Office of Inspection and Enforcement |
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| |
|
| and Enforcement
| | Tecnnical Contacts: James C. Stewart, IE |
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| |
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| Tecnnical
| | (301) 492-9061 K.R. Naidu, IE |
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| |
|
| Contacts:
| | (301) 492-4179 Attachments: |
| James C. Stewart, IE (301) 492-9061 K.R. Naidu, IE (301) 492-4179 Attachments:
| |
|
| |
|
| ===I. List of EPI 900 RPM Generators=== | | ===I. List of EPI 900 RPM Generators=== |
| 2. List of Recently Issued IE Information | | 2. List of Recently Issued IE Information Notices |
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| |
|
| Notices
| | Attachment 1 IN 86-26 April 17, 1986 Domestic EPI 900 RPM Generators |
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| |
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| Attachment
| | Customer/Site No. Units D/G Supplier |
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| 1 IN 86-26 April 17, 1986 Domestic EPI 900 RPM Generators | | Arkansas P&L/Nuclear 1 2 Stewart & Stevenson |
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| Customer/Site
| | Boston Edison/Pilgrim 1 2 ALCO |
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| No. Units D/G Supplier Arkansas P&L/Nuclear
| | Duke Power/Oconee 1 PSD |
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| 1 Boston Edison/Pilgrim
| | Florida P&L/St. Lucie 2 PSD |
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| 1 Duke Power/Oconee | | Houston L&P/Allens Creek 1 (See Note 1) PSD |
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| Florida P&L/St. Lucie Houston L&P/Allens
| | Jersey Central P&L/Oyster Creek 2 (See Note 2) PSD |
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| Creek Jersey Central P&L/Oyster
| | Mississippi P&L/Grand Gulf 2 PSD |
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| Creek Mississippi
| | Mississippi P&L/Grand Gulf 2 Bruce GM (EMD) |
| | New York State Power 4 Bruce GM (EMD) |
| | Authority/FitzPatrick |
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| P&L/Grand
| | Pacific G&E/Diablo Canyon 5 ALCO |
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| Gulf Mississippi
| | Portland G&E/Trojan 2 PSD |
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| P&L/Grand
| | Public Service of Oklahoma/Black Fox 2 (See Note 3) PSD |
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| Gulf New York State Power Authority/FitzPatrick
| | Puget Sound/Skaggit 1 PSD |
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| Pacific G&E/Diablo
| | SMUD/Rancho Seco 2 Bruce GM (EMD) |
| | TVA/Hartsville, Phipps Bend 6 (See Note 4) PSD |
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| |
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| Canyon Portland G&E/Trojan
| | TVA/Sequayah 4 Bruce GM (EMD) |
| | TVA/Sequayah 1 PSD |
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|
| Public Service of Oklahoma/Black
| | TVA/Watts Bar 6 PSD |
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| |
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| Fox Puget Sound/Skaggit
| | Vepco/North Anna 4 Stewart & Stevenson |
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| |
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| SMUD/Rancho
| | WPPSS/Hanford 1 2 Stewart & Stevenson |
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| |
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| Seco TVA/Hartsville, Phipps Bend TVA/Sequayah
| | Notes: 1. Generator returned to PSD |
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| |
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| TVA/Sequayah | | 2. Obtained from TVA |
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| TVA/Watts
| | 3. One unit sent to foreign plant, one unit spare |
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| Bar Vepco/North
| | 4. Two units to Oyster Creek, three units sent to foreign plants, one unit sent to NASA |
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| |
|
| Anna WPPSS/Hanford
| | Attachnient 2 IIN 86-26 April 17, 1986 LIST OF RECENTLY ISSUED |
|
| |
|
| 1 2 2 1 2 1 2 2 2 4 5 2 2 1 2 6 4 1 6 4 2 (See Note 1)(See Note 2)(See Note 3)(See Note 4)Stewart & Stevenson ALCO PSD PSD PSD PSD PSD Bruce GM (EMD)Bruce GM (EMD)ALCO PSD PSD PSD Bruce GM (EMD)PSD Bruce GM (EMD)PSD PSD Stewart & Stevenson Stewart & Stevenson Notes: 1. Generator
| | IE INFORMATION NOTICES |
|
| |
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| returned to PSD 2. Obtained from TVA 3. One unit sent to foreign plant, one unit spare 4. Two units to Oyster Creek, three units sent to foreign plants, one unit sent to NASA
| | Information Date of |
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| |
|
| Attachnient
| | Notice No. Subject Issue __Issued to- |
| | 86-25 Traceability And Material 4/11/86 All power reactor |
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| |
|
| 2 IIN 86-26 April 17, 1986 LIST OF RECENTLY ISSUED IE INFORMATION
| | Control Of Material And facilities holding |
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| |
|
| NOTICES Information
| | Equipment, Particularly an OL or CP |
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| |
|
| Date of Notice No. Subject Issue __Issued to-86-25 Traceability
| | Fasteners |
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| |
|
| And Material Control Of Material And Equipment, Particularly
| | 86-24 Respirator Users Notice: 4/11/86 All power reactor |
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| |
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| Fasteners 4/11/86 86-24 Respirator
| | Increased Inspection Frequency facilities holding |
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| |
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| Users Notice: 4/11/86 Increased
| | For Certain Self-Contained an OL or CP; research |
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| |
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| Inspection
| | Breathing Apparatus Air and test reactor |
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| |
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| Frequency For Certain Self-Contained
| | Cylinders facilities; fuel |
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| |
|
| Breathing
| | cycle licensees and |
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| |
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| Apparatus
| | Priority 1 material |
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| |
|
| Air Cylinders 86-23 86-22 86-21 Excessive
| | licensees |
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| |
|
| Skin Exposures | | 86-23 Excessive Skin Exposures Due 4/9/86 All power reactor |
|
| |
|
| Due To Contamination
| | To Contamination With Hot facilities holding |
|
| |
|
| With Hot Particles Underresponse
| | Particles an OL or CP |
|
| |
|
| Of Radition Survey Instrument | | 86-22 Underresponse Of Radition 3/31/86 All power reactor |
|
| |
|
| To High Radiation | | Survey Instrument To High facilities holding |
|
| |
|
| Fields Recognition | | Radiation Fields an OL or CP and |
|
| |
|
| ===Of American Society Of Mechanical===
| | research and test |
| Engineers
| |
|
| |
|
| ===Accreditation===
| | reactors |
| Program For N Stamp Holders Low-Level
| |
|
| |
|
| Radioactive
| | 86-21 Recognition Of American 3/31/86 All power reactor |
|
| |
|
| Waste Scaling Factors, 10 CFR Part 61 Reactor Coolant Pump Shaft Failure At Crystal River NRC On-Scene Response During A Major Emergency 4/9/86 3/31/86 3/31/86 3/28/86 3/21/86 3/26/86 All power reactor facilities
| | Society Of Mechanical facilities holding |
|
| |
|
| holding an OL or CP All power reactor facilities
| | Engineers Accreditation an OL or CP and all |
|
| |
|
| holding an OL or CP; research and test reactor facilities;
| | Program For N Stamp Holders recipients of NUREG- |
| fuel cycle licensees
| | 0040 (white book) |
| | 86-20 Low-Level Radioactive Waste 3/28/86 All power reactor |
|
| |
|
| and Priority 1 material licensees All power reactor facilities
| | Scaling Factors, 10 CFR facilities holding |
|
| |
|
| holding an OL or CP All power reactor facilities
| | Part 61 an OL or CP |
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| |
|
| holding an OL or CP and research and test reactors All power reactor facilities
| | 86-19 Reactor Coolant Pump Shaft 3/21/86 All power reactor |
|
| |
|
| holding an OL or CP and all recipients | | Failure At Crystal River facilities holding |
|
| |
|
| of NUREG-0040 (white book)All power reactor facilities
| | an OL or CP |
|
| |
|
| holding an OL or CP All power reactor facilities
| | 86-18 NRC On-Scene Response During 3/26/86 All power reactor |
|
| |
|
| holding an OL or CP All power reactor facilities | | A Major Emergency facilities holding |
|
| |
|
| holding an OL or CP 86-20 86-19 86-18 OL = Operating
| | an OL or CP |
|
| |
|
| License CP = Construction | | OL = Operating License |
|
| |
|
| Permit}} | | CP = Construction Permit}} |
|
| |
|
| {{Information notice-Nav}} | | {{Information notice-Nav}} |
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 NRC/IE |
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To: |
|
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References |
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IN-86-026, NUDOCS 8604150542 |
Download: ML031220661 (5) |
|
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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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). 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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.: 6835 IN 86-26 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C. 20555 April 17, 1986 INFORMATION NOTICE NO. 86-26: POTENT1AL PROBLEMS IN GENERATORS MANUFACTURED
BY ELECTRICAL PRODUCTS INCORPORATED
Addressees
All nuclear power reactor facilities holding an operating license (OL) or a
construction permit (CP).
Purpose
This notice is to alert recipients to a potentially significant problem involving
the failure of Electrical Products Incorporated (EPI) diesel generators without
prior warning during an emergency demand. Actions taken by licensees to prevent
recurrence also are discussed. It is expected that recipients will review this
information for applicability to their facilities and consider actions, if
appropriate, to preclude a similar problem occurring at their facilities.
However, suggestions-contained in this information notice do not constitute NRC
requirements; therefore, no specific action or written response is required.
Description of Circumstances
Washington Public Power Supply System (WPPSS) Unit 2 On July 21, 1983, emergency diesel generator (DG) 1A had high vibration level
readings accompanied by sparks from the rotor shaft bearing area. Upon disas- sembly it was determined that a shim, required to maintain clearance at the
thrust bearing, was missing. Inspection of DG 1B showed that the same shim was
missing. The two generators were returned to EPI (Cleveland, Ohio) where the
missing shim was installed and the damaged areas refurbished. The original
design, which placed electrical insulation between the rotor shaft and the
slip-ring end bearing inner race, was maintained.
On July 9, 1984, during monthly surveillance testing, a high vibration alarm
was observed on emergency DG 1B. Investigation after completion of the 4-hour
test revealed that the slip-ring end bearing had turned on the shaft insulation
destroying 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 bearing
was mounted directly on the shaft. The bearing housing was insulated to provide
the required electrical insulation. No failure has-been reported since the
reported test failure in July 1984.
8604150542
- IN 86-26 April 17. 19v6 Grand Gulf Unit 1 K>
At Grand Gulf Unit 1, the high pressure core spray pump is powered by
a dedicateu
DG. On July 13, 1985, during surveillance testing, the generator failed
observed to be emitting sparks. Power Systems Division (PSD) of Morrison and was
the supplier of the DG unit, determined that the electrical insulation Knudsen, the inner race of the cylindrical roller bearing at the slip-ring end between
rotor shaft had degraded. The degradation allowed the shaft to drop and the
rub the inner and outer oil seals causing the sparks. EPI and PSD down and
a procedure to implement the same design modification at Grand Gulf have developed
previously at WPPSS. as used
Watts Bar Unit 2 On June 10, 1983, during the performance of a test, the generator
observed to be rubbing against the inner and outer oil seals at theshaft was
end. Examination after disassembly revealed that the thickness of slip-ring
thrower was less than specified, causing a mismatch between the innerthe oil
races of the slip-ring end bearing that resulted in the inner race and outer
loose and turning on the underlying electrical insulation. breaking
The repairs at a Tennessee Valley Authority (TVA) workshop consisted
ding oil seals, polishing the shaft under the oil seals, replacing of rebuil- the
tion material under the bearing, machining the bearing housing cap to insula- the alignment, adding a shim to restrain the outer race, and installingcorrect
bearings. TVA inspected four other generators and made similar modifications.new
Background:
The failures occurred in electrical generators manufactured at EPI located
Cleveland, Ohio. EPI was a division of Portec from 1969-1979. In 1979, in
sold EPI to Northern Electrical Industries-Parsons Peebles (NEI-Peebles) Portec
Great Britain. The manufacturing operations at Cleveland ceased in of
the
1984. Currently, EPI furnishes spare parts and modifications to existing Fall of
units.
Discussion:
The failures described above have all occurred at the slip-ring end
diesel engine configurations. Installation of the insulation betweenof the tandem
the rotor
shaft and the bearing also is used for single engine applications and
cases it is installed under the shaft bearing at the other end of the in some
as well. The purpose of the insulation (3M Scotchply brand, type 1009,generator
composite tape) is to prevent circulating currents through the generator glass/epoxy
This insulation method was limited by EPI to 8-pole 900-rpm machines. shaft.
initiating failure mechanism of the insulation has been attributed by The
sources to insulation creep fatigue, misalignment of the engines, poor various
workmanship, or inadequate original design. The first WPPSS and the insulation
failures appear-to be isolated cases of improperly machined pieces; Watts Bar
however, the
failures manifest themselves in a similar manner and may be discovered
checks for insulation damage. during the
IN 86-26 April 17, 1986 PSD has stated that a procedure to monitor shaft movement will have to be specific
for each plant because of design differences that impact the allowable movement
and the jacking force. Jacking the shaft up and down and recording the movement
will determine the vertical play between the shaft and bearing housing, out care
should be taken to use a load cell or circle force gauge between the jack and
the generator shaft to prevent damage.
Other suppliers that have used EPI generators include Stewart & Stevenson, Alco
and Bruce GM (EMD). See Attachment 1 for a list of facilities identified oy
EPI and PSD as recipients of the subject generators. Some of the generators
nave 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 nave
any questions regarding this notice, please contact the Regional Aaministrator
of the appropriate NRC regional office or this office.
X\visli/f
Edward L ordan, Director
Divisior of Emergency Preparedness
and Engineering Response
Office of Inspection and Enforcement
Tecnnical Contacts: James C. Stewart, IE
(301) 492-9061 K.R. Naidu, IE
(301) 492-4179 Attachments:
I. List of EPI 900 RPM Generators
2. List of Recently Issued IE Information Notices
Attachment 1 IN 86-26 April 17, 1986 Domestic EPI 900 RPM Generators
Customer/Site No. Units D/G Supplier
Arkansas P&L/Nuclear 1 2 Stewart & Stevenson
Boston Edison/Pilgrim 1 2 ALCO
Duke Power/Oconee 1 PSD
Florida P&L/St. Lucie 2 PSD
Houston L&P/Allens Creek 1 (See Note 1) PSD
Jersey Central P&L/Oyster Creek 2 (See Note 2) PSD
Mississippi P&L/Grand Gulf 2 PSD
Mississippi P&L/Grand Gulf 2 Bruce GM (EMD)
New York State Power 4 Bruce GM (EMD)
Authority/FitzPatrick
Pacific G&E/Diablo Canyon 5 ALCO
Portland G&E/Trojan 2 PSD
Public Service of Oklahoma/Black Fox 2 (See Note 3) PSD
Puget Sound/Skaggit 1 PSD
SMUD/Rancho Seco 2 Bruce GM (EMD)
TVA/Hartsville, Phipps Bend 6 (See Note 4) PSD
TVA/Sequayah 4 Bruce GM (EMD)
TVA/Sequayah 1 PSD
TVA/Watts Bar 6 PSD
Vepco/North Anna 4 Stewart & Stevenson
WPPSS/Hanford 1 2 Stewart & Stevenson
Notes: 1. Generator returned to PSD
2. Obtained from TVA
3. One unit sent to foreign plant, one unit spare
4. Two units to Oyster Creek, three units sent to foreign plants, one unit sent to NASA
Attachnient 2 IIN 86-26 April 17, 1986 LIST OF RECENTLY ISSUED
IE INFORMATION NOTICES
Information Date of
Notice No. Subject Issue __Issued to-
86-25 Traceability And Material 4/11/86 All power reactor
Control Of Material And facilities holding
Equipment, Particularly an OL or CP
Fasteners
86-24 Respirator Users Notice: 4/11/86 All power reactor
Increased Inspection Frequency facilities holding
For Certain Self-Contained an OL or CP; research
Breathing Apparatus Air and test reactor
Cylinders facilities; fuel
cycle licensees and
Priority 1 material
licensees
86-23 Excessive Skin Exposures Due 4/9/86 All power reactor
To Contamination With Hot facilities holding
Particles an OL or CP
86-22 Underresponse Of Radition 3/31/86 All power reactor
Survey Instrument To High facilities holding
Radiation Fields an OL or CP and
research and test
reactors
86-21 Recognition Of American 3/31/86 All power reactor
Society Of Mechanical facilities holding
Engineers Accreditation an OL or CP and all
Program For N Stamp Holders recipients of NUREG-
0040 (white book)
86-20 Low-Level Radioactive Waste 3/28/86 All power reactor
Scaling Factors, 10 CFR facilities holding
Part 61 an OL or CP
86-19 Reactor Coolant Pump Shaft 3/21/86 All power reactor
Failure At Crystal River facilities holding
an OL or CP
86-18 NRC On-Scene Response During 3/26/86 All power reactor
A Major Emergency facilities holding
an OL or CP
OL = Operating License
CP = 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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