Information Notice 1994-50, Failure of General Electric Contactors to Full in at Required Voltage
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 July 14, 1994 NRC INFORMATION NOTICE 94-50: FAILURE OF GENERAL ELECTRIC
CONTACT
ORS
TO PULL IN AT THE REQUIRED VOLTAGE
Addressees
All holders of operating licenses or construction permits for nuclear power
plants.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees that some full-voltage magnetic reversing
controllers manufactured by General Electric Electrical Distribution & Control
(GE ED&C) contained contactors with incorrect coils that would not close the
contacts under degraded voltage conditions. 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 November 1993, at Nine Mile Point Unit 2, as a result of testing certain
motor operated valves (MOVs) in the high pressure core spray system, plant
personnel found that the controllers for four of the MOV motors would not pull
in (contactors would not close) at 80 percent of rated voltage as specified in
the procurement documents. In all, six CR209D type controllers in the same
Division III motor control center were affected. The licensee determined that
this condition could have prevented the system from performing its safety
function and reported the circumstances to the NRC in accordance with Part 21 of Title 10 of the Code of Federal Regulations (10 CFR Part 21). These
controllers had a National Electrical Manufacturers Association (NEMA) rating.
Discussion
Niagara Mohawk Power Company, the licensee for Nine Mile Point, purchased the
high pressure core spray system and the associated electrical components from
GE Nuclear Energy (GE NE). This included the motor control center which was
manufactured for GE NE by GE ED&C. The requirement in-the GE NE purchase
specification, that NEMA size 1, 2 and 3 controllers in the switchgear should
be capable of closing at 80 percent of rated voltage, was a plant interface
requirement.
A test procedure performed during plant startup showed that the minimum
voltage at which the contactors in these controllers would pull in was greater
g7
94 070279 Pod, C-e jq - 50 c 4 Ozfq
July 14, 1994 than 80 percent of rated voltage, but the test procedure did not contain this
acceptance criterion and no corrective action was taken. Consequently, if a
design-basis accident occurred and system voltage was degraded, these
contactors may not have actuated and closed the contacts to operate the
affected valves. In this circumstance, the current drawn by the coils remains
high and may cause the control power fuse(s) to blow as happened during some
of the testing at Nine Mile Point Unit 2.
GE NE informed the NRC that the contactors for the six controllers at Nine
Mile Point Unit 2 had been assembled at the GE ED&C factory with standard
coils designed to close the contacts at 85 percent of rated voltage. The part
number for the standard coil is "15D222G22" which is the part number the
licensee reported stamped on the contactor coils. GE NE indicated that a
special coil with a 75-percent pull-in rating would have been needed to meet
the 80-percent pull-in rating specified in the procurement documents for the
affected NEMA size 2 contactors and that the part number for this special coil
would have been '55-523759G022." However, this part number is not (and was
not) listed in the applicable GE ED&C commercial catalog (currently Catalog
No. GEP-1260).
In the GE ED&C catalog, a two-digit suffix at the end of the part number for
NEMA-rated contactors, starters, or controllers, specifies the coil voltage
rating. At the time that the controllers for the affected MOVs were ordered, the suffix "22" indicated a standard coil for a voltage and frequency rating
of 115-120 Vac/60 hertz or 110 Vac/50 hertz that would pull in at 85 percent
of rated voltage. However, the suffix "22" is no longer used. Currently, this dual voltage and frequency rating is specified by the suffix "02" and
still refers to a standard coil designed to pull in at 85 percent of rated
voltage. The suffix "02" was formerly used to specify a nominal 120 Vac/60
hertz coil.
GE NE stated that, if a coil rated to pull in at 75 percent of rated voltage
is required, that requirement and the special coil part number or the coil
suffix to the catalog number of the contactor, starter, or controller being
procured from GE NE (if available) should be included in the procurement
documents sent to GE NE. GE NE also stated that GE ED&C does not normally
provide this information nor normally supply coils rated to pull in at
75 percent of rated voltage to its commercial customers. However, licensees
are responsible for ensuring that procurement documents specify or reference
applicable requirements and that purchased material and components conform to
the requirements in the procurement documents.
The six controllers whose contactors would not close under the degraded
voltage conditions required in the purchase specification had been installed
at Nine Mile Point Unit 2 during initial plant construction. Because test
procedures failed to verify that the contactors would close at the minimum
expected voltage for design basis conditions, this condition remained
uncorrected for several years. Testing these or other electromagnet-operated
devices at minimum expected voltage (and under certain circumstances, maximum
expected temperature) should detect incorrect or inadequately wound coils and
also coils that are degraded. GE ED&C stated that all of their contactors with
standard coils are tested at 85 percent of rated voltage. However, that
July 14, 1994 testing may not verify individual plant requirements. Further, not all
manufacturers of electromagnet-operated devices test all production units.
Some manufacturers may test on a random sample basis and only at nominal or
rated voltage. The licensee for Nine Mile Point Unit 2 has replaced the
controllers in the four affected MOYs with Gould controllers designed to pull
in at 75 percent of rated voltage.
The condition described above may affect other plants. In NRC Generic Letter 89-10, "Safety-Related Motor-Operated Valve Testing and Surveillance," the NRC
requested licensees and holders of construction permits to conduct reviews
and verifications of the design and performance of certain MOYs and to take
appropriate corrective actions. As part of their response to GL 89-10, some
licensees have found that the degraded voltage condition for certain MOYs is
less than 80 percent of rated voltage, which is lower than the capability of
the GE standard 85 percent coil. Contactors that are not designed to close at
the appropriate degraded voltage and tested to verify that capability may be
unable to operate those MOVs if degraded voltage conditions occur.
This information notice requires no specific action or written response. 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.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Kamalakar Naidu, NRR
(301) 504-2980
Stephen Alexander, NRR
(301) 504-2995 Leonard Cheung, RI
(610) 337-5296 Attachment:
List of Recently Issued NRC Information Notices
a. -'- Attachment
July 14, 1994 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
94-49 Failure of Torque 07/06/94 All holders of OLs or CPs
Switch Roll Pins for nuclear power reactors.
94-48 Snubber Lubricant 06/30/94 All holders of OLs or CPs
Degradation in High- for nuclear power reactors.
Temperature Environments
94-13, Unanticipated and Unin- 06/28/94 All holders of OLs or CPs
Supp. 1 tended Movement of Fuel for nuclear power reactors.
Assemblies and other
Components due to Improper
Operation of Refueling
Equipment
94-47 Accuracy of Information 06/21/94 All U.S. Nuclear Regulatory
Provided to NRC during Commission Material
the Licensing Process Licensees.
94-46 NonConservative Reactor 06/20/94 All holders of OLs or CPs
Coolant System Leakage for nuclear power reactors.
Calculation
94-45 Potential Common-Mode 06/17/94 All holders of OLs or CPs
Failure Mechanism for for nuclear power reactors.
Large Vertical Pumps
94-44 Main Steam Isolation 06/16/94 All holders of OLs or CPs
Valve Failure to Close for nuclear power reactors.
on Demand because of
Inadequate Maintenance
and Testing
94-43 Determination of Primary- 06/10/94 All holders of OLs or CPs
to-Secondary Steam for pressurized water
Generator Leak Rate reactors.
94-42 Cracking in the Lower 06/07/94 All holders of OLs or CPs
Region of the Core for boiling-water reactors
Shroud in Boiling-Water (BWRs).
Reactors
OL = Operating License
CP = Construction Permit
July 14, 1994 testing may not verify individual plant requirements. Further, not all
manufacturers of electromagnet-operated devices test all production units.
Some manufacturers may test on a random sample basis and only at nominal or
rated voltage. The licensee for Nine Mile Point Unit 2 has replaced the
controllers in the four affected MOVs with Gould controllers designed to pull
in at 75 percent of rated voltage.
The condition described above may affect other plants. In NRC Generic Letter 89-10, "Safety-Related Motor-Operated Valve Testing and Surveillance," the NRC
requested licensees and holders of construction permits to conduct reviews
and verifications of the design and performance of certain MOVs and to take
appropriate corrective actions. As part of their response to GL 89-10, some
licensees have found that the degraded voltage condition for certain MOVs is
less than 80 percent of rated voltage, which is lower than the capability of
the GE standard 85 percent coil. Contactors that are not designed to close at
the appropriate degraded voltage and tested to verify that capability may be
unable to operate those MOVs if degraded voltage conditions occur.
This information notice requires no specific action or written response. 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.Odg~nahs1gnedbW
Brian K.Grime
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Kamalakar Naidu, NRR
(301) 504-2980
Stephen Alexander, NRR
(301) 504-2995 Leonard Cheung, RI
(610) 337-5296 Attachment:
List of Recently Issued NRC Information Notices
- See Drevious concurrence I
OFFICE RVIB:DRIL RVIB:DRIL RVIB:DRIL C/VIB:DRIL D/DRIL:NRR
NAME KNaidu* SAlexander* GCwalina* LNorrholm* CERossi*
DATE 02/03/94 06/02/94 02/04/94 0 02/04/94 .02/07/94 OFFICE TECHED C/EELB:DE OGCB:DORS C/OGCB:DORS 0
NAME RSanders* CBerlinger* JBirmingham* RDennig* rKGrimes
DATE j06/14/94
-- ---
.
06/09/94 06/22/94 ALir- ITL~~iar
AO/7
06/22/94 QA CA TLI
/94 OFFICIAL RECORD COPY uUtluritri 1 114MME; ZrtUV. 111
0
IN 94-XX
June XX, 1994 This information notice requires no specific action or written response. 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.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Kamalakar Naidu, NRR
(301) 504-2980
Stephen Alexander, NRR
(301) 504-2995 Leonard Cheung, Region I
(610) 337-5296
(
Attachment:
List of Recently Issued NRC Information Notices
- See previous concurrence
OFFICE RVIB:DRIL RVIB:DRIL RVIB:DRIL C/VIB:DRIL D/DRIL:NRR
NAME KNaidu* SAlexander* GCwalina* LNorrholm* CERossi*
DATE 02/03/94 06/02/94 02/04/94 02/04/94 02/07/94 OFFICE l TECHED C/EELB:DE OGCB:D D/DORS:NRR
NAME RSanders* CBerlinger* JBi am BKGrimes
DATE 1 06/14/94 I 06/09/94 06/4U/94 06/21/94 06/ /94 WI I PFTrTAI DFrnDn
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"'e IN 94-XX
May XX, 1994 temperature) woul not only fail to detect an incorrect coil, but may also
fail to detect inad uately wound or degraded coils, even if the correct coils
were ordered and coil of the correct part number were received. Although GE
ED&C has stated that al of their contactors with standard coils are tested at
85 percent of rated volta , this may not verify individual plant require- ments. Also, not all manufaturers of electromagnet-operated devices test all
production units. Some testihq is on a random sample basis and then only at
nominal or rated voltage. Niag'aa Howhawk has since replaced the GE
controllers for HPCS loads that m t operate in an accident (the four MOVs)
with the type of Gould controllers ed elsewhere in the plant that are
designed to pull in at 75 percent of ated voltage.
In addition, in NRC Generic Lett 89-10, "Safety-Related Motor-Operated
Valve Testing and Surveillance," the NRC equested licensees and holders of
construction permits to conduct reviews a verifications of the design and
performance of certain MO s and to take app priate corrective actions. As
part of their response to GL 89-10, some lic sees have found that the
degraded voltage condition for certain MOYs is less than 80 percent of rated
voltage. Various conditions have been discover that could render safety
systems inoperable under degraded voltage conditi ns, including excessive
voltage drop over long cable runs and power supply r control power trans- former taps set incorrectly. Contactors that are n designed to close at the
minimum voltage expected and tested to verfiy that ca ability may be unable to
operate those MOVs if degraded voltage conditions occu
This information notice requires no specific acti or written response.
If you have any questions and the information in this not ce, please contact
one of the persons listed below or the appropriate Office f Nuclear Reactor
Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Sup ort
Office of Nuclear Reactor Regulati n
Technical contacts: Kamalakar Naidu, NRR
(301) 504 2980
Stephen Alexander, NRR
(301) 504-2995 Leonard Cheung, Region I
(610) 337 5296 Attachment:
List of Recently Issued NRC Information Notices
- See previous concurrence
OFFICE RVIB:DRIL RVIB:DRIL RVIB:DRIL C/VIB:DRIL D/DRIL:NRR
NAME KNaidu* SAlexander* GCwalina* LNorrholm* CERossi*
DATE [02/03/94 106/02/94 I02/04/94 02/04/94 J02/Q7/94 OFFICE TECHED _ C/EELB:DE OGCB:DORS jC/OGCB:DORS D/DORS:NRR 1 NAME jJA > }CBerlinger* JBirmingham BKGrimes
DATE 06//4/94 106/09/94 106/ /94 06/
U-NIrRIIt
/94 L(LI
--
106/
_.
/94
IAL KLLUKU
UrrL~LAL -----
LUFY UUWAMtN NAME: LW1K61K3.bUA
IN 94-XX
May XX, 1994 Also, not all manufacturers of electromagnet-operated devices test all
production units. Some testing is on a random sample basis and then only at
nominal or rated voltage. Niagara Mowhawk has since replaced the GE
controllers for HPCS loads that must operate in an accident (the four MOVs)
with the type of Gould controllers used elsewhere in the plant that are
designed to pull in at 75 percent of rated voltage.
In addition, in NRC Generic Letter 89-10, "Safety-Related Motor-Operated Valve
Testing and Surveillance," the NRC requested licensees and holders of
construction permits to conduct reviews and verifications of the design and
performance of certain MOVs and to take appropriate corrective actions. As
part of their response to GL 89-10, some licensees have found that the
degraded voltage condition for certain MOVs is less than 80 percent of rated
voltage. Various conditions have been discovered that could render safety
systems inoperable under degraded voltage conditions, including excessive
voltage drop over long cable runs and power supply or control power trans- former taps set incorrectly. Contactors that are not designed to close at the
minimum voltage expected and tested to verfiy that capability may be unable to
operate those MOVs if degraded voltage conditions occur.
This information notice requires no specific action or written response. If
you have any questions and the information in this notice, please contact one
of the persons listed below or the appropriate Office of Nuclear Reactor
Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Kamalakar Naidu, NRR
(301) 504 2980
Stephen Alexander, NRR
(301) 504-2995 Leonard Cheung, Region I
(610) 337 5296 Attachment:
List of Recently Issued NRC Information Notices
- See previous concurrence o oi6eso
k4~c&'
OFFICE RVIB:DRIL RVIB:DRIL RVIB:DRIL C/VIB:DRIL D/DRIL:NRR
NAME KNaidu* SAlexande GCwalina* LNorrholm* CERossi*
DATE 02/03/94 X /07/94 02/04/94 02/ 02/07/94 OFFICE TECHED CB:DORS C/OGCB:DORS D/DORS:NRR
NAME RSanders* C rli er JBirmingham AKugler BKGrimes
DATE 01/28/94 ii /94 05/ /94 05/ /94 05/ /94 OFFICIAL
COY----~iNAL
RE-ORD COPY
OFFICIAL RECORD DOCUMEN NAME: UNTCTR8b.bUA
IN 94-XX
March XX, 1994 voltage condit o It was determined that the contactor coils do not conform
to paragraph 4.1.2. of Purchase Specification 21A9301AZ in which GE specifies
the technical require nts of the size 1, 2 and 3 contactors in the HPCS
switchgear. This parag ph states that the coils of the contactors should be
capable of pulling in wit no more than 80 percent of the rated voltage
applied. GE informed the that coils designed to pull in at 75 percent of
the rated voltage are availab e for its NEMA Size 2 contactors. NMP2 has
since replaced the GE NEMA Siz 2 contactors.
The contactors with coils that we unable to pull in at degraded voltage
conditions as required by the purch e specifications had been installed to
operate safety-related MOVs during intial construction. This condition
remained undetected for many years an ould exist at other plants. This
situation could have beeen avoided if ( the coil catalog specification had
been compared to the purchase specificati and the appropriate coil had been
chosen as part of the review for the suita lity of application required by
Appendix B of Title 10 of the Code of Federa Regulations, Part 50, (10 CFR
Part 50, Appendix B), Criterion III, "Design ntrol," and (2)the correct
coils were verified to be installed and then be ch tested to verify
performance at degraded voltage conditions in ac rdance with Criterion VII of
10 CFR Part 50, Appendix B, "Control of Purchased quipment and Services."
This information notice requires no specific action written response. If
you have any questions and the information in this not ce, please contact one
of the technical contacts listed below or the appropria Office of Nuclear
Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Re tor Support
Office of Nuclear Reactor Regula on
Technical contact: Kamalakar R. Naidu, NRR
(301) 504 2980
Stephen D. Alexander, NRR
(301) 504 2995 Leonard S. Cheung, Region I
(215) 337 5296 Attachment: List of Recently Issued NRC Information Notices
- See previous concurrence
OFFICE VIB/DRIL VIB/DRIL VIB/DRIL DRIL/NRR TECH EDITOR GCB
NAME KNaidu* GCwalina LNorrholm CERossi Ray Sanders
DATE 2/3/94 2/4/94 2/4/94 2/7/94 1 /28 /94 I /94 COPY YES NO YES NO YES NO YES NO NO YES NO
OFFICE IDOR/NRR
NAME BGrimes
DATE /94 COPY YES NO
r -- a ---- -- prn
fhtsnb G:\NAIDU/GE
ktI l1AL KLUIKU D EGY NAME:
DOCUMENT
It
IN 94-XX
May XX, 1994 This infor atio otice requires no specific action or written response. If
you have any ques ons and the information in this notice, please contact one
of the persons list below or the appropriate Office of Nuclear Reactor
Regulation (NRR) proj t manager.
rian K. Grimes, Director
Dvision of Operating Reactor Support
Of ce of Nuclear Reactor Regulation
Technical contacts: Kamalakar Naidu, NRR
(301) 504 2980
Stephen Alexander, R
(301) 504-2995 Leonard Cheung, Region
(610) 337 5296 Attachment:
List of Recently Issued NRC Information Notices
- See previous concurrence
OFFICE RVIB:DRIL RVIB:DRIL RVIB:DRIL C/VIB:DRIL D/DRIL:NRR
NAME KNaidu* SAlexand S GCwalina* LNorrholm* CERossi*
DATE 02/03/94 0516A94 02/04/94 0 2/04/94 02/07/94 OFFICE TECHED C/EELB:DE OGCB:DORS _ C/OGCB:DORS D/DORS:NRR
NAME RSanders* CBerlinger JBirmingham AKugler BKGrimes
DATE 01/28/94 05/ /94 05/ /94 05/ /94 05/ /94 UII-ILIAL KLUUKU LUUFY UUUUMthl NAM: tN1WK03.-bUR
N~ \ VIN 94-XX
March xx, 1994 This information not requires no specific action or written response. If
you have any questions nd the information in this notice, please contact one
of the persons listed betbw or the appropriate Office of Nuclear Reactor
Regulation (NRR) project mipager.
Briad K. Grimes, Director
Diviston of Operating Reactor Support
Office f Nuclear Reactor Regulation
Technical contacts: Kamalakar Naidu, NRAR Leonard Cheung, Region I
(301) 504 2980 \\ (215) 337 5296 Stephen Alexander, NRR
(301) 504-2995 Attachment:
List of Recently Issued NRC Information Not ices
4^e __ .^. ^-l ae
bee previOub IuncIILuEIVII'
OFFICE RVIB:DRIL:NRR RVIB:DRIL:NRR C/VIB:DRIL:NRR D/DRIL:NRR
NAME KNaidu* GCwalina* LNorrholm* CERossi*
DATE 02/03/94 02/04/94 0 2/04/94 02/07/94 TECHED C/EELB:DE:NRR OGCB:DORS:NRR C/OGCB:DORS:NRR D/DORS:NRR
RSanders CHBerlinger JLBirmingham AJKugler BKGrimes
01/28/94 03/ /94 03/. 9403/ /94 03/ .94 l~ILftLIT unurU. i-nIkTArTD -1I R
OFFICIAL RECORD COPY UMUUPl0lL I NArtC.; VuIA In%. IFn .% &LO
a I
IN 94-XX
March xx, 1994 This in rmation notice requires no specific action or written response. If
you have questions and the information in this notice, please contact one
of the persb s listed below or the appropriate Office of Nuclear Reactor
Regulation (R) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: Kamilakar R. Naidu, NRR
(301),504-2980
Stepheh.D. Alexander, NRR
(301) 504-2995 Leonard S.t Cheung, Region I
(215) 337-'296 Attachment:
List of Recently Issued NRC Infor ation Notices
- See previous concurrence
OFFICE RVIB:DRIL:NRR RVIB:DRIL:NRR l C/VIB:DRIL:NRR D/DRIL:NRR
NAME KNaidu* GCwalina* LNorrholm* CERossi*
DATE 02/03/94 102/04/94 002/04/94 02/07/94 TECHED I OGCB:WORS:JIRRjl C/OGCB:DORS:NRR I D/DORS:NRR
Rianders JL.iI AJKugl er I ______ ______
101/28/94 1 03/ /;94 1 03/ /94 1 03/ /941 OFFICIAL RECORD COPY DOCUMENT NAME:
CONTACT
R.JLB
e00 g o , g o e0-5ZS.4Ad~
IN 94-XX
> <_March XX, 1994 Page JLof 2 raded voltage conditions; It was determined that the contactor coils do
not nform to paragraph 4.1.2.3 of Purchase Specification 21A9301AZ in which
GE spe fies the technical requirements of the size 1, 2 and 3 contactors in
the HPCS itchgear. This paragraph states that the coils of the contactors
should be c able of pulling in with no more than 80 percent of the rated
voltage appi . GE informed the NRC that coils designed to pull in at 75 percent of the ated voltage are available for its NEMA Size 2 contactors.
NMP2 has since re laced the GE NEMA-Size 2-cantagtors.
TheQnidriZ49 sxArdzhe con '9l1!--that
h t were unable to pull in at
degraded voltage condi ions and that did not mcet the purchase specifications
had been installed to op ate safety-related MOVs during initial construction, and.thet fhis condition re ined undetected for many years and could exist at
other plants. This situatio could have beeen avoided if (1)the coil catalog
specification had been compare to the purchase specification and the
appropriate coil had been chose as part of the review for the suitability of
application required by Appendix of Title 10 of the Code of Federal
Regulations, Part 50, (10 CFR Part 0, Appendix B), Criterion III, "Design
Control," and (2)the correct coils re verified to be installed and then
bench tested to verify performance at graded voltage conditions in
accordance with Criterion VII of 10 CFR art 50, Appendix B, 'Control of
Purchased Equipment and Services."
This information notice requires no specifi c ction or written response. If
you have any questions and the information in is notice, please contact one
of the technical contacts listed below or the a ropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
Brian K. Grimes, Direc or
Division of Opera ng Reactor Support
Office of Nuclear Reactor egulation
Technical contact: Kamalakar R. Naidu, NRR
(301) 504 2980
Stephen D. Alexander, NRR
(301) 504 2995 Leonard S. Cheung, Region I
(215) 337 5296 Attachment: List of Recently Issued NRC Information Notices
- See previous concurrence waves =
OFFICE VIB/DRIL VIHDRIL VIWRIL DRIL/NRR TECH EDITOR GCB
NAME KNaidu* aw a L m Ray Sanders
DATE 2/3/94 8 94 /9 1 /28 /94 / /94 COPY YES NO YES NO YES NO YES NO NO YES NO
OFFICE IDOR/NRR
NAME BGrimes
DATE I /94 COPY jYES NO
OFFICIAL RECORD COPY DOCUMENT NAME: G:\NAIDU/GE
IN 94-XX
March XX, 1994 deg ded voltage conditions. It was determined that the contactor coils do not
con to paragraph 4.1.2.3 of Purchase Specification 21A9301AZ in which GE
specifie the technical requirements of the size 1, 2 and 3 contactors in the
HPCS switc ear. This paragraph states that the coils of the contactors
should be ca ble of pulling in with no more than 80 percent of the rated
voltage applie GE informed the NRC that coils designed to pull in at 75 percent of the ted voltage are available for its NEMA Size 2 contactors.
NMP2 has since re aced the GE NEMA Size 2 contactors.
The NRC is concerned hat contactors with coils that were unable to pull in at
degraded voltage condi ons and that did not meet the purchase specifications
had been installed to op rate safety-related MOVs during initial constuction, and that this condition reained undetected for many years and could exist at
other plants. This situat n could have beeen avoided if (1)the coil
catalogue specification had en compared to the purchase specification and
the appropriate coil had been hosen as part of the review for the suitability
of application required by Appe ix B of Title 10 of the Code of Federal
Regulations, Part 50, (10 CFR Pa 50, Appendix B), Criterion III, "Design
Control," and (2)the correct coi were verified to be installed and then
bench tested to verify performance t degraded voltage conditions in
accordance with Criterion VII of 10 R Part 50, Appendix B, "Control of
Purchased Equipment and Services."
This information notice requires no spec fic action or written response. If
you have any questions and the informati in this notice, please contact one
of the technical contacts listed below or e appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
Brian K. Grimes Director
Division o Operating Reactor Support
Office of Nuclear R ctor Regulation
Technical contact: Kamalakar R. Naidu, NRR
(301) 504 2980
Stephen D. Alexander, NRR
(301) 504 2995 Leonard S. Cheung, Region I
(215) 337 5296 Attachment: List of Recently Issued NRC Information Notices
OFFICE VIB/DRIL VI D= VIB/DRIL DRIL/NRR TECH EDITOR GCB
NAME KNaft . GC Ut a LNorrholm CERossi f4yr~z r42 DATE 2/ 4 / /94 / /94 I/Z4'/94 / /94 COPY YES NO YES NO I YES NO YES NO NO YES NO
.1 OFFICE IDOR/NRR
NAME BGrimes
DATE /94 COPY [YES NO
v_, --- .-.------ -- d
UIMLIAL KELUKR LUPY DOCUMENT NAME: G:\NAIDU/GE