Information Notice 1998-19, Shaft Binding in General Electric Type Sbm Control Switches: Difference between revisions

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| issue date = 06/03/1998
| issue date = 06/03/1998
| title = Shaft Binding in General Electric Type Sbm Control Switches
| title = Shaft Binding in General Electric Type Sbm Control Switches
| author name = Roe J W
| author name = Roe J
| author affiliation = NRC/NRR
| author affiliation = NRC/NRR
| addressee name =  
| addressee name =  
Line 14: Line 14:
| page count = 7
| page count = 7
}}
}}
{{#Wiki_filter:REVISED -TO ADD ATTA JENT 1' June 3,1998NRC INFORMATION NOTICE 98-19: SHAFT BINDING IN GENERAL ELECTRIC TYPE St[ XCONTROL SWITCHESdX
{{#Wiki_filter:REVISED - TO ADD ATTA JENT 1
'
                                            UNITED STATES
 
NUCLEAR REGULATORY COMMISSION
 
OFFICE OF NUCLEAR REACTOR REGULATION
 
WASHINGTON, D.C. 20555-0001 June 3,1998 NRC INFORMATION NOTICE 98-19: SHAFT BINDING IN GENERAL ELECTRIC TYPE St[ X
 
CONTROL SWITCHES
 
dX


==Addressees==
==Addressees==
Line 20: Line 32:


==Purpose==
==Purpose==
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice (IN) to alertaddressees to the potential for some General Electric (GE) Type SBM control switches withspring return function to fail to return to the normal position because the manufacturer failed toaccount for shrinkage of the phenolic material as a result of post-mold curing. It is expected thatrecipients will review the information for applicability to their facilities and consider actions, asappropriate, to avoid similar problems. However, suggestions contained in this informationnotice are not NRC requirements; therefore, no specific action or written response is required.
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice (IN) to alert
 
addressees to the potential for some General Electric (GE) Type SBM control switches with
 
spring return function to fail to return to the normal position because the manufacturer failed to
 
account for shrinkage of the phenolic material as a result of post-mold curing. It is expected that
 
recipients will review the information for applicability to their facilities and consider actions, as
 
appropriate, to avoid similar problems. However, suggestions contained in this information
 
notice are not NRC requirements; therefore, no specific action or written response is required.


==Description of Circumstances==
==Description of Circumstances==
In December 1997, the licensee for LaSalle County Station, Commonwealth Edison Company(ComEd), was replacing the GE Type SBM control switches at both units during a prolongeddual-unit maintenance outage. The licensee was replacing more than 1,100 SBM switchesbecause the switches were reaching the end of service life and because of concerns aboutcracking of the Lexan cam followers, which was originally described In NRC IN 80-13, "GeneralElectric Type SBM Control Switches Defective Cam Followers" (Accession #8002280650).During the replacement effort, the licensee discovered that some of the new switches that hadbeen installed for about a year would not spring return to the reset (normal) position. Thelicensee found that 21 out of the 246 Installed replacement switches exhibited the binding. 0In early January 1998, two of the failed switches were sent to GE-Nuclear Energy (NE) forevaluation to determine the cause of the switch binding. On January 23, 1998, GE-NE issued atransfer of information letter to affected customers In accordance with 10 CFR 21.21(b) to alertthem to the possible failure of the SBM switches to return to the normal position after operation(Accession #9801280338). Subsequently, ComEd determined that the reported deviationrepresented a substantial safety hazard because various equipment important to plant safetyff ected, and submitted a 10 CFR Part 21 notification to the NRC on March, 16, 1998.*8.'052ll IN 98-19June 3.1998 DiscussionThe SBM control switch Is manufactured as a commercial item by GE-Electrical Distribution andControl (GE-ED&C), Power Management Division, In Malvem, Pennsylvania. GE-NE dedicatesthe switches for nuclear safety applications. The switches are used extensively throughout thenuclear power Industry as control board switches to actuate safety-related pump motors, motor-operated valves, and circuit breakers. Although GE-NE has informed Its customers of recordabout the binding of the SBM switches, some licensees may have procured the switches fromthird-party dedicating enUties that purchased the switches as commercial-grade components.This Information notice Is intended to alert all licensees to the potential binding Issue.The failure mode has been Identified as binding caused by Interference between the rear brassbearing and the phenolic rear bearing support. The exploded view of an SBM switch in theattached Figure 1 shows the rear bearing support plate (Item 30, also called the barrier) and therear bearing (Item 32) on the switch shaft. The Interference Is caused by post-mold cureshrinkage of the phenolic material, which takes place for up to 2 years after the phenolicmaterial Is molded Into the bearing support. GE-ED&C found that the mold used to make thebearing support had worn over the years to the point that the diameter of the opening for thebrass rear bearing was still within specifications but near the minimum allowable value. Theoriginal GE design did not account for the post-mold cure shrinkage of the phenolic material.The second contributing factor to switch failure Is a brass rear bearing at Its maximum allowablediameter. Only switches with both the undersized hole In the bearing supports and bearings atthe maximum tolerance have experienced failures. Testing confirmed that switches withbearings of nominal size functioned properly, even with undersized holes In the phenolicbearing support.The failed switches were manufactured between November 1996 and February 1997. Althoughmost of the post-mold cure shrinkage occurs within the first 12 to 18 months, GE conservativelyassumed that switches manufactured after March 1996 may be susceptible. These switchescan be Identified by the last two characters on the green quality control acceptance sticker. Theaffected date codes are PL, RL, SL, TL, UL, VL, WL, XL, YL, ZL, NM, OM, PM, RM, SM, TM,UM, VM, WM, XM, YM, ZM, NN, and ON. The manufacturer has improved the SBM switchmanufacturing process to allow for phenolic post-mold cure shrinkage, and switchesmanufactured as of March 1, 1998, should no longer be susceptible to the failure mode.There are two safety concerns regarding the switch binding: (1) possible control circuit damagecaused by energizing the momentary circuit for a prolonged period and (2) possible preventionof control circuits from performing their function because of the failure of the switch contacts toreturn to the normal position. GE recommends that licensees with SBM switches manufacturedafter March 1996 advise operators to return the switch to the normal position after operation topreclude any circuit malfunctions. Ucensees should also note that susceptible switches mostlikely will fall after about 12 to 18 months after the date of manufacture. Switches more than 2years old are not thought to be susceptible to binding caused by post-mold cure shrinkag IN 98-19June 3, 1998Page 3 eT 3This IN requires no specific action .or written response. However, recipients are reminded thatthey are required to consider industry-wide operating experience (including NRC INs) wherepractical, when setting goals and performing periodic evaluations under Section 50.65,Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," ofPart 50 of Title 10 of the Code of Federal Regulations. If you have any questions about theinformation In this notice, please contact one of the technical contacts listed below or theappropriate Office of Nuclear Reactor Regulation (NRR) project manager.\N /s/tdJack W. Roe, Acting DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contacts: Stephen Alexander, NRR301-415-2995E-mail: sda~nrc.govDavid Skeen, NRR301-415-1174E-mail:dls@nrc.gov
In December 1997, the licensee for LaSalle County Station, Commonwealth Edison Company
 
(ComEd), was replacing the GE Type SBM control switches at both units during a prolonged
 
dual-unit maintenance outage. The licensee was replacing more than 1,100 SBM switches
 
because the switches were reaching the end of service life and because of concerns about
 
cracking of the Lexan cam followers, which was originally described In NRC IN 80-13, "General
 
Electric Type SBM Control Switches Defective Cam Followers" (Accession #8002280650).
 
During the replacement effort, the licensee discovered that some of the new switches that had
 
been installed for about a year would not spring return to the reset (normal) position. The
 
licensee found that 21 out of the 246 Installed replacement switches exhibited the binding.           0
  In early January 1998, two of the failed switches were sent to GE-Nuclear Energy (NE) for
 
evaluation to determine the cause of the switch binding. On January 23, 1998, GE-NE issued a
 
transfer of information letter to affected customers In accordance with 10 CFR 21.21(b) to alert
 
them to the possible failure of the SBM switches to return to the normal position after operation
 
(Accession #9801280338). Subsequently, ComEd determined that the reported deviation
 
represented a substantial safety hazard because various equipment important to plant safety
 
ff ected, and submitted a 10 CFR Part 21 notification to the NRC on March, 16, 1998.
 
*8.'052ll
 
IN 98-19 June 3.1998 Discussion
 
The SBM control switch Is manufactured as a commercial item by GE-Electrical Distribution and
 
Control (GE-ED&C), Power Management Division, In Malvem, Pennsylvania. GE-NE dedicates
 
the switches for nuclear safety applications. The switches are used extensively throughout the
 
nuclear power Industry as control board switches to actuate safety-related pump motors, motor- operated valves, and circuit breakers. Although GE-NE has informed Its customers of record
 
about the binding of the SBM switches, some licensees may have procured the switches from
 
third-party dedicating enUties that purchased the switches as commercial-grade components.
 
This Information notice Is intended to alert all licensees to the potential binding Issue.
 
The failure mode has been Identified as binding caused by Interference between the rear brass
 
bearing and the phenolic rear bearing support. The exploded view of an SBM switch in the
 
attached Figure 1 shows the rear bearing support plate (Item 30, also called the barrier) and the
 
rear bearing (Item 32) on the switch shaft. The Interference Is caused by post-mold cure
 
shrinkage of the phenolic material, which takes place for up to 2 years after the phenolic
 
material Is molded Into the bearing support. GE-ED&C found that the mold used to make the
 
bearing support had worn over the years to the point that the diameter of the opening for the
 
brass rear bearing was still within specifications but near the minimum allowable value. The
 
original GE design did not account for the post-mold cure shrinkage of the phenolic material.
 
The second contributing factor to switch failure Is a brass rear bearing at Its maximum allowable
 
diameter. Only switches with both the undersized hole In the bearing supports and bearings at
 
the maximum tolerance have experienced failures. Testing confirmed that switches with
 
bearings of nominal size functioned properly, even with undersized holes In the phenolic
 
bearing support.
 
The failed switches were manufactured between November 1996 and February 1997. Although
 
most of the post-mold cure shrinkage occurs within the first 12 to 18 months, GE conservatively
 
assumed that switches manufactured after March 1996 may be susceptible. These switches
 
can be Identified by the last two characters on the green quality control acceptance sticker. The
 
affected date codes are PL, RL, SL, TL, UL, VL, WL, XL, YL, ZL, NM, OM, PM, RM, SM, TM,
UM, VM, WM, XM, YM, ZM, NN, and ON. The manufacturer has improved the SBM switch
 
manufacturing process to allow for phenolic post-mold cure shrinkage, and switches
 
manufactured as of March 1, 1998, should no longer be susceptible to the failure mode.
 
There are two safety concerns regarding the switch binding: (1) possible control circuit damage
 
caused by energizing the momentary circuit for a prolonged period and (2) possible prevention
 
of control circuits from performing their function because of the failure of the switch contacts to
 
return to the normal position. GE recommends that licensees with SBM switches manufactured
 
after March 1996 advise operators to return the switch to the normal position after operation to
 
preclude any circuit malfunctions. Ucensees should also note that susceptible switches most
 
likely will fall after about 12 to 18 months after the date of manufacture. Switches more than 2 years old are not thought to be susceptible to binding caused by post-mold cure shrinkage.
 
IN 98-19 June 3, 1998 Page 3 eT 3 This IN requires no specific action .or written response. However, recipients are reminded that
 
they are required to consider industry-wide operating experience (including NRC INs) where
 
practical, when setting goals and performing periodic evaluations under Section 50.65, Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," of
 
Part 50 of Title 10 of the Code of Federal Regulations. If you have any questions about the
 
information In this notice, please contact one of the technical contacts listed below or the
 
appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
 
\N /s/ t d
 
Jack W. Roe, Acting Director
 
Division of Reactor Program Management
 
Office of Nuclear Reactor Regulation
 
Technical contacts:         Stephen Alexander, NRR
 
301-415-2995 E-mail: sda~nrc.gov
 
David Skeen, NRR
 
301-415-1174 E-mail:dls@nrc.gov
 
Attachment: Figure 1 - Exploded View of Type SBM Switch
 
List of Recently Issued NRC Information Notices
 
DOCUMENT NAME: G:\DLS\IN97-XX.SBM
 
To receive a copy of this document, indicate Inthe box C=Copy wlo attachmentlenclosure E=Copy with attachmentlenclosure N = No copy
 
*See previous concurrence
 
OFFICE        PECB:DRPM            E HQMB/:DRCH _            D:DRCH                C:PECBDRPM          _D:DRPM
 
NAME          D. Skeen*                S. Alexander*          R. Spessard*          J. Stolz*                  J. Roe*
  DATE          05/14/98                05/12/98              05/19/98              05/21/98                  05/26/98 OFFICIAL RECORD COPY
 
I
 
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11 A?
 
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                                                                                              I-h%a
 
KjAttachment 2 IN 98-19 June 3, 1998 LIST OF RECENTLY ISSUED
 
NRC INFORMATION NOTICES
 
Information                                        Date of
 
Notice No.            Subject                      Issuance    Issued to
 
98-18            Recent Contamination Incidences    5113/98    Part 35 Medical Licensees
 
Resulting from Failure to Perform
 
Adequate Surveys
 
98-17            Federal Bureau of Investigations  5/7/98    All U.S. Nuclear Regulatory
 
(FBI) Awareness of National                  Commission fuel cycle and power
 
Security Issues and Responses                and non-power reactor licensees
 
(ANSIR) Program
 
98-16            Inadequate Operational Checks    4/30198    All Industrial Radiography
 
of Alarm Ratemeters                          Licensees
 
98-15            Intergrity of Operator Licensing  4120/98    All holder of operating licenses
 
Examinations                                  for nuclear power reactors except
 
those that have permanently
 
ceased operations and have
 
certified that fuel has been
 
permanently removed from the
 
reactor vessel
 
98-14            Undocumented Changes to          4/20/98    All holders of operating licenses
 
Non-Power Reactor Safety                      or construction permits for test
 
System Wiring                                  research reactors
 
98-13            Post-Refueling Outage Reactor      4/20/98    All holders of operating licenses
 
Pressure Vessel Leak Testing                  for nuclear power reactors except
 
Before Core Criticality                      those that have permanently
 
ceased operations and have
 
certified that fuel has been
 
permanently removed from the
 
reactor vessel
 
OL = Operating License
 
CP = Construction Permit
 
IN 98WXX
 
MayXX, 1998 Wth information notice requires no specific action or written response.
 
reminded that they are required to consider Industry-wide operating experience  However, recipients are
 
Information notices) where practical, when setting goats and performing                  (including NRC
 
under Section 50.65, Requirements for Monitoring th Effectiveness of            periodic  evaluations
 
Maintenance at Nuclear
 
Power Plants.' of Part 50 of Title 10 of the Code of Federal Regulations.
 
questions about the Information Ints notice, please contact one of the If you have any
 
below or the appropriate Office of Nuclear Reactor Regulation (NRR) technical contacts listed
 
project manager.
 
Jack W. Roe, Acting Dfrector
 
Division of Reactor Program Management
 
Office of Nuclear Reactor Regulation
 
Technical contacts:      Stephen Alexander, NRR
 
301-415-2995 E-mall: sda~nrc.gov
 
David Skeen, NRR
 
301-415-1174 E-mail:disenrc.gov
 
Attachment: Ust of Recently Issued NRC Information Notices
 
DOCUMENT NAME: G:\DLSUN97-XX.SBM
 
ohro a copy of NIs docwnmnt Indicste In ft box CxCopy wo attachmoentnclosure
 
E=Copy with attacelntendcosure N  u No copy
 
FICE      PECB:DRPM L HQMB/:DRCH                      D:DRCH          _ C:PECBJP
 
ME        D. SkeAI                            r      R. Spessard          J. Stolz                  J. Roe
 
rE        05//98                Om$                  05/ /98              05/98                    05/ /98 OFFICIAL RECORD COPY
 
IN08,X      I
 
MayXX, 1      8ai This IN requires no specific action or written response. However, they uo required to consider Industrywlde operating experience recipients are reminded that
 
practical, when setting goals and performing periodic evaluations (Including NRC INs) where
 
4nder Section 60.65, aRequirements for Monitoring tho Effectiveness of Maintenance
 
Part 50 of Title 10 of te Code of Federat Reguation . If you have  at Nuclear Power Planta. of
 
Information Inthis notice, please contact one of the technical contacts any questions about the
 
appropriate Office of Nuclear Reactor Regulation (NRR) project            listed below or the.
 
manager.
 
Jack W. Roe, Acting Director
 
Dvislon of Reactor Program Management
 
Office of Nuclear Reactor Regulation
 
Technical contacts:    Stephen Alexander, NRR
 
301-415-2995 E-mail: sdaenrc.gov
 
David Skeen, NRR
 
301-416-1174 E-mail:dlsonrc.gov
 
Atachment: Figure 1 - Exploded View of Type SBM Switch
 
List of Recently Issued NRC Information Notices
 
DOCUMENT NAME: G:%DLSIN97XXS6BM
 
gv a wpy of efl documwt kxat hIto box CzCopy W/o 8fcnw~cdobw
 
E-Copy wMlatowhmn/doune N a No copy


===Attachment:===
FICE    PECB:DRPM           HQMS:DRCH             D:DRC              C:F        RPM          D:RP
Figure 1 -Exploded View of Type SBM SwitchList of Recently Issued NRC Information NoticesDOCUMENT NAME: G:\DLS\IN97-XX.SBMTo receive a copy of this document, indicate In the box C=Copy wlo attachmentlenclosure E=Copy with attachmentlenclosure N = No copy*See previous concurrenceOFFICE PECB:DRPM E HQMB/:DRCH _ D:DRCH C:PECBDRPM _D:DRPMNAME D. Skeen* S. Alexander* R. Spessard* J. Stolz* J. Roe*DATE 05/14/98 05/12/98 05/19/98 05/21/98 05/26/98OFFICIAL RECORD COPY I4311MS WSS edAj lo ma!A popoldx3 -I OJnflq!udnS BumM J)je9e et11ID00 rt03 '0 03o %O 'I-h %aA?ft,Nuotlo8 wnaej-Supds aiM S"tmi!MS joi POsnAN _/* I-
KjAttachment 2IN 98-19June 3, 1998 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to98-18 Recent Contamination Incidences 5113/98 Part 35 Medical LicenseesResulting from Failure to PerformAdequate Surveys98-1798-1698-1598-14Federal Bureau of Investigations(FBI) Awareness of NationalSecurity Issues and Responses(ANSIR) ProgramInadequate Operational Checksof Alarm RatemetersIntergrity of Operator LicensingExaminationsUndocumented Changes toNon-Power Reactor SafetySystem WiringPost-Refueling Outage ReactorPressure Vessel Leak TestingBefore Core Criticality5/7/984/301984120/984/20/984/20/98All U.S. Nuclear RegulatoryCommission fuel cycle and powerand non-power reactor licenseesAll Industrial RadiographyLicenseesAll holder of operating licensesfor nuclear power reactors exceptthose that have permanentlyceased operations and havecertified that fuel has beenpermanently removed from thereactor vesselAll holders of operating licensesor construction permits for testresearch reactorsAll holders of operating licensesfor nuclear power reactors exceptthose that have permanentlyceased operations and havecertified that fuel has beenpermanently removed from thereactor vessel98-13OL = Operating LicenseCP = Construction Permit IN 98WXXMayXX, 1998 Wth information notice requires no specific action or written response. However, recipients arereminded that they are required to consider Industry-wide operating experience (including NRCInformation notices) where practical, when setting goats and performing periodic evaluationsunder Section 50.65, Requirements for Monitoring th Effectiveness of Maintenance at NuclearPower Plants.' of Part 50 of Title 10 of the Code of Federal Regulations. If you have anyquestions about the Information In ts notice, please contact one of the technical contacts listedbelow or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.Jack W. Roe, Acting DfrectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contacts: Stephen Alexander, NRR301-415-2995E-mall: sda~nrc.govDavid Skeen, NRR301-415-1174E-mail:disenrc.gov


===Attachment:===
VIE      D. S                S . Ahxae            R. tSpmard          J. 8U              -
Ust of Recently Issued NRC Information NoticesDOCUMENT NAME: G:\DLSUN97-XX.SBMohro a copy of NIs docwnmnt Indicste In ft box CxCopy wo attachmoentnclosure E=Copy with attacelntendcosure N u No copyFICE PECB:DRPM L HQMB/:DRCH D:DRCH _ C:PECBJPME D. SkeAI r R. Spessard J. Stolz J. RoerE 05//98 Om$ 05/ /98 05/98 05/ /98OFFICIAL RECORD COPY IN 08,X IMayXX, 1 8ai }}
rE    ._5i%8                05P418                0&8                05P198                  051 198 OFFICIAL RECORD COPY}}


{{Information notice-Nav}}
{{Information notice-Nav}}

Latest revision as of 04:45, 24 November 2019

Shaft Binding in General Electric Type Sbm Control Switches
ML031050156
Person / Time
Site: Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant  Entergy icon.png
Issue date: 06/03/1998
From: Roe J
Office of Nuclear Reactor Regulation
To:
References
IN-98-019, NUDOCS 9805280259
Download: ML031050156 (7)


REVISED - TO ADD ATTA JENT 1

'

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555-0001 June 3,1998 NRC INFORMATION NOTICE 98-19: SHAFT BINDING IN GENERAL ELECTRIC TYPE St[ X

CONTROL SWITCHES

dX

Addressees

All holders of operating licenses for nuclear power reactors.

Purpose

The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice (IN) to alert

addressees to the potential for some General Electric (GE) Type SBM control switches with

spring return function to fail to return to the normal position because the manufacturer failed to

account for shrinkage of the phenolic material as a result of post-mold curing. It is expected that

recipients will review the information for applicability to their facilities and consider actions, as

appropriate, to avoid similar problems. However, suggestions contained in this information

notice are not NRC requirements; therefore, no specific action or written response is required.

Description of Circumstances

In December 1997, the licensee for LaSalle County Station, Commonwealth Edison Company

(ComEd), was replacing the GE Type SBM control switches at both units during a prolonged

dual-unit maintenance outage. The licensee was replacing more than 1,100 SBM switches

because the switches were reaching the end of service life and because of concerns about

cracking of the Lexan cam followers, which was originally described In NRC IN 80-13, "General

Electric Type SBM Control Switches Defective Cam Followers" (Accession #8002280650).

During the replacement effort, the licensee discovered that some of the new switches that had

been installed for about a year would not spring return to the reset (normal) position. The

licensee found that 21 out of the 246 Installed replacement switches exhibited the binding. 0

In early January 1998, two of the failed switches were sent to GE-Nuclear Energy (NE) for

evaluation to determine the cause of the switch binding. On January 23, 1998, GE-NE issued a

transfer of information letter to affected customers In accordance with 10 CFR 21.21(b) to alert

them to the possible failure of the SBM switches to return to the normal position after operation

(Accession #9801280338). Subsequently, ComEd determined that the reported deviation

represented a substantial safety hazard because various equipment important to plant safety

ff ected, and submitted a 10 CFR Part 21 notification to the NRC on March, 16, 1998.

  • 8.'052ll

IN 98-19 June 3.1998 Discussion

The SBM control switch Is manufactured as a commercial item by GE-Electrical Distribution and

Control (GE-ED&C), Power Management Division, In Malvem, Pennsylvania. GE-NE dedicates

the switches for nuclear safety applications. The switches are used extensively throughout the

nuclear power Industry as control board switches to actuate safety-related pump motors, motor- operated valves, and circuit breakers. Although GE-NE has informed Its customers of record

about the binding of the SBM switches, some licensees may have procured the switches from

third-party dedicating enUties that purchased the switches as commercial-grade components.

This Information notice Is intended to alert all licensees to the potential binding Issue.

The failure mode has been Identified as binding caused by Interference between the rear brass

bearing and the phenolic rear bearing support. The exploded view of an SBM switch in the

attached Figure 1 shows the rear bearing support plate (Item 30, also called the barrier) and the

rear bearing (Item 32) on the switch shaft. The Interference Is caused by post-mold cure

shrinkage of the phenolic material, which takes place for up to 2 years after the phenolic

material Is molded Into the bearing support. GE-ED&C found that the mold used to make the

bearing support had worn over the years to the point that the diameter of the opening for the

brass rear bearing was still within specifications but near the minimum allowable value. The

original GE design did not account for the post-mold cure shrinkage of the phenolic material.

The second contributing factor to switch failure Is a brass rear bearing at Its maximum allowable

diameter. Only switches with both the undersized hole In the bearing supports and bearings at

the maximum tolerance have experienced failures. Testing confirmed that switches with

bearings of nominal size functioned properly, even with undersized holes In the phenolic

bearing support.

The failed switches were manufactured between November 1996 and February 1997. Although

most of the post-mold cure shrinkage occurs within the first 12 to 18 months, GE conservatively

assumed that switches manufactured after March 1996 may be susceptible. These switches

can be Identified by the last two characters on the green quality control acceptance sticker. The

affected date codes are PL, RL, SL, TL, UL, VL, WL, XL, YL, ZL, NM, OM, PM, RM, SM, TM,

UM, VM, WM, XM, YM, ZM, NN, and ON. The manufacturer has improved the SBM switch

manufacturing process to allow for phenolic post-mold cure shrinkage, and switches

manufactured as of March 1, 1998, should no longer be susceptible to the failure mode.

There are two safety concerns regarding the switch binding: (1) possible control circuit damage

caused by energizing the momentary circuit for a prolonged period and (2) possible prevention

of control circuits from performing their function because of the failure of the switch contacts to

return to the normal position. GE recommends that licensees with SBM switches manufactured

after March 1996 advise operators to return the switch to the normal position after operation to

preclude any circuit malfunctions. Ucensees should also note that susceptible switches most

likely will fall after about 12 to 18 months after the date of manufacture. Switches more than 2 years old are not thought to be susceptible to binding caused by post-mold cure shrinkage.

IN 98-19 June 3, 1998 Page 3 eT 3 This IN requires no specific action .or written response. However, recipients are reminded that

they are required to consider industry-wide operating experience (including NRC INs) where

practical, when setting goals and performing periodic evaluations under Section 50.65, Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," of

Part 50 of Title 10 of the Code of Federal Regulations. If you have any questions about the

information In this notice, please contact one of the technical contacts listed below or the

appropriate Office of Nuclear Reactor Regulation (NRR) project manager.

\N /s/ t d

Jack W. Roe, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: Stephen Alexander, NRR

301-415-2995 E-mail: sda~nrc.gov

David Skeen, NRR

301-415-1174 E-mail:dls@nrc.gov

Attachment: Figure 1 - Exploded View of Type SBM Switch

List of Recently Issued NRC Information Notices

DOCUMENT NAME: G:\DLS\IN97-XX.SBM

To receive a copy of this document, indicate Inthe box C=Copy wlo attachmentlenclosure E=Copy with attachmentlenclosure N = No copy

  • See previous concurrence

OFFICE PECB:DRPM E HQMB/:DRCH _ D:DRCH C:PECBDRPM _D:DRPM

NAME D. Skeen* S. Alexander* R. Spessard* J. Stolz* J. Roe*

DATE 05/14/98 05/12/98 05/19/98 05/21/98 05/26/98 OFFICIAL RECORD COPY

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KjAttachment 2 IN 98-19 June 3, 1998 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

98-18 Recent Contamination Incidences 5113/98 Part 35 Medical Licensees

Resulting from Failure to Perform

Adequate Surveys

98-17 Federal Bureau of Investigations 5/7/98 All U.S. Nuclear Regulatory

(FBI) Awareness of National Commission fuel cycle and power

Security Issues and Responses and non-power reactor licensees

(ANSIR) Program

98-16 Inadequate Operational Checks 4/30198 All Industrial Radiography

of Alarm Ratemeters Licensees

98-15 Intergrity of Operator Licensing 4120/98 All holder of operating licenses

Examinations for nuclear power reactors except

those that have permanently

ceased operations and have

certified that fuel has been

permanently removed from the

reactor vessel

98-14 Undocumented Changes to 4/20/98 All holders of operating licenses

Non-Power Reactor Safety or construction permits for test

System Wiring research reactors

98-13 Post-Refueling Outage Reactor 4/20/98 All holders of operating licenses

Pressure Vessel Leak Testing for nuclear power reactors except

Before Core Criticality those that have permanently

ceased operations and have

certified that fuel has been

permanently removed from the

reactor vessel

OL = Operating License

CP = Construction Permit

IN 98WXX

MayXX, 1998 Wth information notice requires no specific action or written response.

reminded that they are required to consider Industry-wide operating experience However, recipients are

Information notices) where practical, when setting goats and performing (including NRC

under Section 50.65, Requirements for Monitoring th Effectiveness of periodic evaluations

Maintenance at Nuclear

Power Plants.' of Part 50 of Title 10 of the Code of Federal Regulations.

questions about the Information Ints notice, please contact one of the If you have any

below or the appropriate Office of Nuclear Reactor Regulation (NRR) technical contacts listed

project manager.

Jack W. Roe, Acting Dfrector

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: Stephen Alexander, NRR

301-415-2995 E-mall: sda~nrc.gov

David Skeen, NRR

301-415-1174 E-mail:disenrc.gov

Attachment: Ust of Recently Issued NRC Information Notices

DOCUMENT NAME: G:\DLSUN97-XX.SBM

ohro a copy of NIs docwnmnt Indicste In ft box CxCopy wo attachmoentnclosure

E=Copy with attacelntendcosure N u No copy

FICE PECB:DRPM L HQMB/:DRCH D:DRCH _ C:PECBJP

ME D. SkeAI r R. Spessard J. Stolz J. Roe

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IN08,X I

MayXX, 1 8ai This IN requires no specific action or written response. However, they uo required to consider Industrywlde operating experience recipients are reminded that

practical, when setting goals and performing periodic evaluations (Including NRC INs) where

4nder Section 60.65, aRequirements for Monitoring tho Effectiveness of Maintenance

Part 50 of Title 10 of te Code of Federat Reguation . If you have at Nuclear Power Planta. of

Information Inthis notice, please contact one of the technical contacts any questions about the

appropriate Office of Nuclear Reactor Regulation (NRR) project listed below or the.

manager.

Jack W. Roe, Acting Director

Dvislon of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: Stephen Alexander, NRR

301-415-2995 E-mail: sdaenrc.gov

David Skeen, NRR

301-416-1174 E-mail:dlsonrc.gov

Atachment: Figure 1 - Exploded View of Type SBM Switch

List of Recently Issued NRC Information Notices

DOCUMENT NAME: G:%DLSIN97XXS6BM

gv a wpy of efl documwt kxat hIto box CzCopy W/o 8fcnw~cdobw

E-Copy wMlatowhmn/doune N a No copy

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VIE D. S S . Ahxae R. tSpmard J. 8U -

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