Distributor Modification to Certain Commercial-Grade Agastat Electrical RelaysML031200430 |
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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
03/30/1992 |
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From: |
Rossi C Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-92-024, NUDOCS 9203230145 |
Download: ML031200430 (13) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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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 [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
{{#Wiki_filter:UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 March 30, 1992 NRC INFORMATION NOTICE 92-24: DISTRIBUTOR MODIFICATION TO CERTAIN
COMMERCIAL-GRADE AGASTAT ELECTRICAL RELAYS
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice
to alert addressees to part modifications and serial number changes that
authorized distributors (ADs) have made to commercial-grade Agastat Series 7000
electrical relays. These alterations may affect the subsequent dedication of
the relays for safety-related use. It is expected that recipients will
review the information for applicability to their facilities and consider
actions, as appropriate. However, suggestions contained in this information
notice are not NRC requirements; therefore, no specific action or written
response is required.
Description of Circumstances
On April 22, 1991, after being informed by Spectrum Technologies USA, Incorpo- rated, (Spectrum) that nameplate labels for Agastat Series 7000 relays could
have been altered, the NRC staff performed a review of the manufacture and
distribution of those relays. Agastat relays are manufactured by the Amerace
Corporation (Amerace), Livingston, New Jersey, and its commercial-grade relays
are distributed by its authorized distributors. In early 1991, Spectrum
ordered six Agastat Model 7032 PBB commercial-grade relays from the
Westinghouse Electric Supply Company (WESCO). Spectrum specified in the
purchase order that the relays be traceable to the manufacturer Amerace and
that the relays be from the same lot and date code. Spectrum included these
requirements because Spectrum intended to dedicate the relays for safety- related use. WESCO ordered the relays from an authorized Amerace distributor, Control Components Supply (CCS), Short Hills, New Jersey. However, the relays
did not have the required traceability to Amerace because of modifications
that CCS made to the relays, and because of changes CCS made to the serial
number nameplates the relays may not have been from the same production lot.
Amerace representatives have told the NRC that its authorized distributors are
allowed to modify its commercial-grade relays to comply with a customer's
specific requirements. Those modifications may include changing the electrical
920323014 f A
I. S7/Af_.//
- A.N92-24 March 30, 1992 coil module for different voltage level applications, adding or changing the
electrical contact assembly module, or changing the time duration disc and
wafer.
Amerace personnel have also told the NRC that
(1) The first four digits of the serial number indicate the year and week of
manufacture. The next four digits in the serial number designate the
sequential order of relay assembly for a particular week. For example, Agastat Model 7012 PC, serial number (S/N) 91161875, was the 1,875th relay
to be assembled the 16th week of 1991 at the Amerace Corporation, Livingston, New Jersey facility. Amerace used similar marking systems for
its subassembly coil and contact modules.
(2) When an AD modifies a commercial-grade 7000 series relay, the AD should
install a new nameplate label with the original S/N containing an
"F" prefix. For example, an AD could change the contact and coil modules
appropriately in the above Model 7012 PC relay and yield a Model 7014 QE
relay. However, the S/N on the nameplate should be changed to F91161875.
The F designator would indicate that the relay had been "field'! modified.
The NRC staff determined that Amerace did not contractually state this
policy to its ADs (see NRC Inspection Report No. 99900296/91-01). After
the NRC performed its review, Amerace issued a notification letter to its
ADs stating this policy. Attachment 1 is a copy of the Amerace notifica- tion letter.
(3) Before performing the final calibration, test, and acceptance of the
7000 series relays, Amerace heat stabilizes each relay by maintaining it
"at a specific temperature for 4 hours. This heat stabilization mates the
timing disc with the ceramic timing wafer to prevent timing drift and to
ensure repeat accuracy. The process also stress-relieves the nonmetallic
parts. Amerace requires that its 7000 series relays be stabilized again
--after they are modified such as-by changing the timing disc. To comply
with the Agastat model number that was ordered, CCS changed the timing
discs of the six relays that were supplied to Spectrum. However, the
staff found no evidence that the relays had been restabilized.
Discussion
FromOctober 1991 through January 1992, the NRC staff conducted several meet- ings with representatives of Amerace and CCS. The NRC staff found that, when
CCS modifies an Agastat 7000 Series relay, CCS typically removes the Amerace
installed label, assigns the relay a new number, types the new serial number
and other relevant information on a blank label, and affixes the new label to
the modified relay. However, the blank labels that the NRC staff observed at
the CCS facility do not contain the F prefix to indicate that the 7000 Series
Agastat relays were modified. The NRC staff found that CCS had disassembled, modified, and reassembled the six relays discussed herein. However, the labels
affixed by CCS did not contain the required F prefix, and the labels did not
contain the original Amerace serial number. CCS had assigned new serial
numbers which indicated that the relays were manufactured in 1991 to reflect
IN 92-24 March 30, 1992 that the relays had been modified by CCS in 1991. However, Amerace personnel
informed the NRC that the six relays had been manufactured in 1989.
The NRC also found that CCS does not heat stabilize the 7000 Series Agastat
relays that it modifies, although Amerace has stated that the heat stabilization
treatment is necessary on modified 7000 series relays to ensure repeat accuracy
and to relieve the stress to nonmetallic parts. The NRC staff reviewed
CCS's customer list and found that the list contained the names of 25 NRC
nuclear power plant licensees and several other Amerace ADs.
This information suggests that consecutive serial numbers on commercial-grade
Agastat relays, obtained through an authorized distributor, may not ensure
traceability to a particular production lot. Amerace has stated that its ADs
do not heat stabilize the 7000 series relays after they are modified. *As
discussed in NRC Inspection Report No. 99900296/91-01, Amerace told the NRC
that there are differences between its Class 1E qualified relays and its
commercial-grade 7000 series relays, such as design control, internal components, and the level of inspection that is applied. Similar differences may exist
between commercial-grade components and the safety-related product line of
other manufacturers. The availability of a safety-related product line is
often an indicator of substantive differences from the commercial-grade product.
In any case, it is important that information relied on when upgrading com- mercial-grade components for use in safety-related applications be supported by
objective evidence of quality to support the suitability of use of the component.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact the
technical contact listed below or the appropriate Office of Nuclear Reactor
Regulation (NRR) project manager.
Char~les E. Rossi Erector
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contact: Joseph J. Petrosino, NRR
(301) 504-2979 Attachments:
1. Amerace Letter on Field Modifications of Agastat Relays
2. List of Recently Issued NRC Information Notices
ttachment 2 IN 92-24 March 30, 1992 LIST OF RECENTLY ISSUED
NRC -INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
Results of Validation Test- 03/27/92 All holders of OLs or CPs
92-23 for nuclear power reactors
ing of Motor-Operated Valve
Diagnostic Equipment and all vendors of motor- operated valve (MOV) diag- nostic equipment.
92-22 Criminal Prosecution and 03/24/92 All holders of OLs or CPs
Conviction of Wrongdoing for nuclear power reactors.
Committed by A Commercial- Grade Valve Supplier
92-21 Spent Fuel Pool Reactivity 03/24/92 All holders of OLs or CPs
Calculations for nuclear power reactors.
92-20 Inadequate Local Leak Rate 03/03/92 All holders of OLs or CPs
Testing for nuclear power reactors.
92-19 Misapplication of Potter & 03/02/92 All holders of OLs or CPs
Brumfield MDR Rotary Relays for nuclear power reactors.
92-18 Potential for Loss of Re- 02/28/92 All holders of OLs or CPs
mote Shutdown Capability for nuclear power reactors.
during A Control Room Fire
92-17 NRC Inspections of Pro- 02/26/92 All holders of OLs or CPs
grams being Developed at for nuclear power reactors.
Nuclear Power Plants in
Response to Generic
Letter 89-10
92-16 Loss of Flow from the 02/25/92 All holders of OLs or CPs
Residual Heat Removal for nuclear power reactors.
Pump during Refueling
Cavity Draindown
92-15 Failure of Primary System 02/24/92 All holders of OLs or CPs
Compression Fitting for nuclear power reactors.
OL = Operating License
CP = Construction Permit
92-1 Attachment 1 NO:
IN 92-24 ! January 1992 March 30, 1992 DATE: PAGE NO: 1 01 1 Industrial
Controls
TO: AUTHORIZED AGASTAT DISTRIBUTORS
FROM: MIKE BHOJWANI
SUBJECT: AGASTAT 7000 SERIES - FIELD MODIFICATIONS
Occasionally, coils or switchblock assemblies on AGASTAT Series 7000
timers are changed in the field. These field changes by our
authorized distributors are necessary to better service our end
customers. Instructions for changing coils, etc. are clearly defined
on Installation and Operation Data Sheet P/N 39999-03. Please ensure
the label P/N 38010-01 enclosed with the replacement kits is filled
out correctly to reflect the new catalog number. Please note, the
serial number must be exactly the same as on the original unit except
the number will be prefixed by an "F" indicating field modifications
were made. Non-adherence of this procedure will void all factory
warranties.
Mike R. Bhojwani
Senior Product/Market Manager
MRB:cip
cc: Internal Distribution
" f INDUSTRIAE EtECTRiCAE l
o [ PRODUCTS
AMERACE COPORATON
INDUSIAt EtECMRCA. PrCOJCTS
533W MT PLEASWATAVENU
lMNGSTOR NJ 07039
(2011992-8i00
IN 92-24 March 30, 1992 that the relays had been modified by CCS in 1991. However, Amerace personnel
informed the NRC that the six relays had been manufactured in 1989.
The NRC also found that CCS does not heat stabilize the 7000 Series Agastat
relays that it modifies, although Amerace has stated that the heat stabilization
treatment is necessary on modified 7000 series relays to ensure repeat accuracy
and to relieve the stress to nonmetallic parts. The NRC staff reviewed
CCS's customer list and found that the list contained the names of 25 NRC
nuclear power plant licensees and several other Amerace ADs.
This information suggests that consecutive serial numbers on commercial-grade
Agastat relays, obtained through an authorized distributor, may not ensure
traceability to a particular production lot. Amerace has stated that its ADs
do not heat stabilize the 7000 series relays after they are modified. As
discussed in NRC Inspection Report No. 99900296/91-01, Amerace told the NRC
that there are differences between its Class lE qualified relays and its
commercial-grade 7000 series relays, such as design control, internal components, and the level of inspection that is applied. Similar differences may exist
between commercial-grade components and the safety-related product line of
other manufacturers. The availability of a safety-related product line is
often an indicator of substantive differences from the commercial-grade product.
In any case, it is important that information relied on when upgrading com- mercial-grade components for use in safety-related applications be supported by
objective evidence of quality to support the suitability of use of the component.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact the
technical contact listed below or the appropriate Office of Nuclear Reactor
Regulation (NRR) project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contact: Joseph J. Petrosino, NRR
(301) 504-2979 Attachments:
1. Amerace Letter on Field Modifications of Agastat Relays
2. List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
D/D *C/OGCB:DOEA:NRR*RPB:ADM
CE ( CHBerlinger TechEd
03/ '2 03/13/92 03/04/92
- OGCB:DOEA:NRR*VIB:DRIS:NRR *SC/VIB:DRIS:NRR *C/VIB:DRIS:NRR *D/DRIS:NRR
JBirmingham JPetrosino UPotapovs LNorrholm BGrimes
03/10/92 02/19/92 02/20/92 02/24/92 02/26/92 DOCUMENT NAME: IN 92-24
IN 92-XX
March xx, 1992 The NRC also found that CCS does not heat stabilize the-7000 Series Agastat
relays that it modifies. Amerace has stated that the heat stabilization
treatment is necessary on modified 7000 series relays to ensure repeat accuracy
and to relieve the stress to nonmetallic parts. The NRC staff reviewed
CCS's customer list and found that the list contained the names of 25 NRC
nuclear power plant licensees and several other Amerace ADs.
This information suggests that consecutive serial numbers on commercial-grade
Agastat relays, obtained through an authorized distributor, may not ensure
traceability to a particular production lot. Amerace also stated that heat
restabilization of modified relays is important to stress relieve nonmetallic
parts and to ensure the repeat accuracy of the 7000 Series Agastat relays.
However, Amerace stated that its ADs do not heat stabilize the 7000 series
relays after they are modified. As discussed in NRC Inspection Report
No. 99900296/91-01, Amerace told the NRC that there are differences between its
Class 1E qualified relays and its commercial-grade 7000 series relays, such as
design control, internal components, and the level of inspection that is
applied. Licensees are reminded that information relied on to upgrade compo- nents for use in safety-related applications must be supported by objective
evidence of quality to support the suitability of use of the component. The
NRC will examine closely the basis for using commercial-grade components in
safety-related applications, particularly when a safety-related product line is
available from the manufacturer.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please call the
technical contact listed below or the appropriate Office of Nuclear Reactor
Regulation (NRR) project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contact: Joseph J. Petrosino, NRR
(301) 504-2979 Attachments:
1. Amerace Letter on Field Modifications of Agastat Relays
2. List of Recently Issued NRC Information Notices
Document Name: AGASTAT IN
- SEE PREVIOUS CONCURRENCES
D/DOEA:NRR C/OGCB:DOEA: tRPB:ADM
CERossi Add CHBerlinger TechEd
03/ /9Z-{ 03/)3/92 03/04/92
- OGCB:DOEA:NRR*VIB:DRIS:NRR *SC/VIB:DRIS:NRR *C/VIB:DRIS: R *D/DRIS:NRR
JBirmingham JPetrosino UPotapovs LNorrholm BGrimes
03/10/92 02/19/92 02/20/92 02/24/92 02/26/92
IN 92-XX
March xx, 1992 The NRC also found that CCS does not heat stabilize the 7000 Series Agastat
relays that it modifies. Amerace has stated that the heat stabilization
treatment is necessary on modified 7000 series relays to ensure repeat accuracy
and to relieve the stress to nonmetallic parts. The NRC staff reviewed CCS's
customer list and found that the list contained the names of 25 NRC nuclear
power plant licensees and several other Amerace ADs.
This information suggests that consecutive serial numbers on commercial-grade
Agastat relays, obtained through an authorized distributor, may not ensure
traceability to a particular production lot. Amerace also stated that heat
restabilization of modified relays is important to stress relieve nonmetallic
parts and to ensure the repeat accuracy of the 7000 Series Agastat relays.
However, Amerace stated that its ADs do not heat stabilize the 7000 series
relays after they are modified. Amerace told the NRC that there are differ- ences in the manufacturing processes for its Class lE qualified relays and its
commercial-grade 7000 series relays such as design control, internal com- ponents, and the level of inspection that is applied. Licensees are reminded
that information relied on to upgrade components for use in safety-related
applications must be supported by objective evidence of quality to support the
suitability of use of the component. The NRC will examine closely the basis
for using commercial-grade components in safety-related applications, particu- larly when a safety-related product line is available from the manufacturer.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please call the
technical contact listed below or the appropriate Office of Nuclear Reactor
Regulation (NRR) project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contact: Joseph J. Petrosino, NRR
(301) 504-2979 Attachments:
1. Amerace Letter on Field Modifications of Agastat Relays
2. List of Recently Issued NRC Information Notices
Document Name: AGASTAT IN
- SEE PREVIOUS CONCURRENCES
D/DOEA:NRR C/OGCB:DOEA:NRR*RPB:ADM
CERossi CHBerlinger TechEd
03/ /92 03/ /92 03/04/92 OGCB:DOEA:NRR *VIB:DRIS:NRR *SC/VIB:DRIS:NRR *C/VIB:DRIS:NRR *D/DRIS:NRR
JBirmingham JPetrosino UPotapovs LNorrholm BGrimes
03//*/92 9It~ 02/19/92 02/20/92 02/24/92 02/26/92
"'Mod'e.
series relays after medificetiene Amerace told the NRC thatthere-a"re- C rc17gs 2re dik4mt is- -t:h
iffefffrees-betweefnits Class lE quali idl commercial-grade 7000 series
relays. Licensees are reminded that information relied on to upgrade compo- nents for use in safety-related applications must be supported by objective
evidence of quality to support the suitability of use of the component. The
NRC will examine closely the basis for ! commercial-grade components in
is
safety-related applications, particularly when a safety-related product line
available from the manufacturer.
If
This information notice requires no specific action or written response. the
you have any questions about the information in this notice, please call
technical contact listed below or the appropriate Office of Nuclear Reactor
Regulation (NRR) project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contact: Joseph J. Petrosino, NRR
(301) 504-2979 Attachments:
1. Amerace Letter on Field Modifications of Agastat Relays
2. List of Recently Issued NRC Information Notices
Document Name: AGASTAT IN
- SEE PREVIOUS CONCURRENCES
D/DOEA:NRR C/OGCB:DOEA:NRR RPB:ADM
CERossi CHBerlinger TechEd 7Ma;nj9r
03/ /92 03/ /92 03/L/92 OGCB:DOEA:NRR *VIB:DRIS:NRR *SC/VIB:DRIS:NRR *C/VIB:DRIS:NRR *D/DRIS:NRR
JBirmingham JPetrosino UPotapovs LNorrholm BGrimes
03/ /92 02/19/92 02/20/92 02/24/92 02/26/92
IN 92-XX
February xx, 1992 This information notice requires no specifip action or written
response. If you have any questions about the information in
this notice, please call the technical contact listed below or
the appropriate Office of Nuclear Reactor Regulation (NRR)
project manager.
Charles E. Rossi, Director
Division of Operational Events
Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Joseph J. Petrosino, NRR:DRIS
(301) 504-2979 Attachments:
1. Amerace Letter
2. List of Recently Issued NRC
Information Notices
OFF CfIAL RECORD COPY
DOCUMENT NAME: A:\AGASTAT.IN:WP50
OFC: RIS-1:VIB SC RIS-1:VIB BC VIB:DRIS
NAME: JPetrosino UPotapovs LNorrholm B
DATE: 2/19/92* 2/20/92* 2/24/92* 6,/92 OFC: BC OGCB:DOEA DIR:DOEA
NAME: CBerlinger CERossi
DATE: 2/ /92 2/ /92
IC
February XX, 1992 This information notice requires no specific action or written
response. If you have any questions about the information in
this notice, please call the technical contact listed below or
the appropriate Office of Nuclear Reactor Regulation (NRR)
project manager.
Charles E. Rossi, Director
Division of Operational Events
Assessment
Office of Nuclear Reactor
Regulation
Technical Contact:
Joseph J. Petrosino, NRR:DRIS
(301) 504-2979
AttachmentsW
1. Amerac& Letter
2. Listpf Recently Issued NRC
In~formation Notices
D, + ENT NAME: A:\AGASTAT.IN:WP50
OFC: RIS-1:VIB SC RIS-1:VIB BC IS DIR:DRIS
NAME: JPetrosino UPotadovs 2/24'/9lm BGrimes a<
DATE: 2/19/92* 2/20/92* 2/2 492 2/ /92
Technical Contact:
Joseph J. Petrosino, NRR:DRIS
(301) 504-2979 Attachments:
1. Amerace Letter
2. List of Recently Issued NRC
Information Notices
OFFICIAL RECORD COPY
DOCUMENT NAME: A:\AGASTAT.IN:WP50
OFC: SC Fd-1:VIB BC VIB:DRIS DIR:DRIS
NAME: sino UPotadovs LNorrholm BGrimes
DATE: 2/ 2-Q/92 2/ /92 2/ /92 I IS2-.
IN 92-XX
January XX, 1992 DISTIMMON I
VIB/DRIS R/F
Central Files I
PDR
jpetrosino (2)
UPotapovs
INorrholm
BKGrines
5atthews
BLetts
CBerlirner
RIS-1/VIB: SC:RIS-1/VIB :BC:VIB/MUIS :DIRt:MIS: OI/NRR :DDEP/NRR
OFC :
:INorrholm : BEGrimes: tetts : linger
NME: JPetrosino: LPotapovs
- / /92 : / /92 : / /92: i/10/92 : / /92 DATE:/61L27/92 kC1tQ Awdc(A
oFCIAL MOM CPY Dis<= ves
DO=ENI NNME: A: \NOIICE.WP mvd k1-,' 19'
GSo~bl i}}
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list | - Information Notice 1992-01, Cable Damage Caused by Inadequate Cable Installation Procedures and Controls (3 January 1992, Topic: Overspeed)
- Information Notice 1992-02, Relap5/MOD3 Computer Code Error Associated with the Conservation of Energy Equation (3 January 1992, Topic: Overspeed)
- Information Notice 1992-02, Relap5/Mod3 Computer Code Error Associated with the Conservation of Energy Equation (3 January 1992)
- Information Notice 1992-03, Remote Trip Function Failures in General Electric F-Frame Molded-Case Circuit Breakers (6 January 1992, Topic: Overspeed)
- Information Notice 1992-04, Potter and Brumfield Model Mdr Rotary Relay Failures (6 January 1992, Topic: Probabilistic Risk Assessment, Commercial Grade, Overspeed)
- Information Notice 1992-04, Potter and Brumfield Model MDR Rotary Relay Failures (6 January 1992, Topic: Probabilistic Risk Assessment, Commercial Grade)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs RXMH2 Relays (8 January 1992, Topic: Commercial Grade, Overspeed)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs Rxmh2 Relays (8 January 1992, Topic: Commercial Grade)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in ABS RXMH2 Relays (8 January 1992, Topic: Commercial Grade)
- Information Notice 1992-06, Reliability of ATWS Mitigation System and Other NRC Required Equipment Not Controlled by Plant Technical Specifications (15 January 1992)
- Information Notice 1992-06, Reliability of ATWS Mitigation System and Other NRC Required Equipment not Controlled by Plant Technical Specifications (15 January 1992)
- Information Notice 1992-07, Rapid Flow-induced Erosion/Corrosion of Feedwater Piping (9 January 1992)
- Information Notice 1992-08, Revised Protective Action Guidance for Nuclear Incidents (23 January 1992)
- Information Notice 1992-09, Overloading and Subsequent Lock Out of Electrical Buses During Accident Conditions (30 January 1992)
- Information Notice 1992-10, Brachytherapy Incidents Involving Iridium-192 Wire Used in Endobronchial Treatments (31 January 1992, Topic: Brachytherapy)
- Information Notice 1992-10, Brachytherapy Incidents Involving Iridium-192 Wire used in Endobronchial Treatments (31 January 1992, Topic: Brachytherapy)
- Information Notice 1992-11, Soil and Water Contamination at Fuel Cycle Facilities (5 February 1992, Topic: Brachytherapy)
- Information Notice 1992-12, Effects of Cable Leakage Currents on Instrument Settings and Indications (10 February 1992, Topic: Brachytherapy)
- Information Notice 1992-13, Inadequate Control Over Vehicular Traffic at Nuclear Power Plant Sites (18 February 1992, Topic: Brachytherapy)
- Information Notice 1992-14, Uranium Oxide Fires at Fuel Cycle Facilities (21 February 1992, Topic: Brachytherapy)
- Information Notice 1992-15, Failure of Primary Systems Compression Fitting (24 February 1992, Topic: Unidentified leakage)
- Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown (25 February 1992, Topic: Reactor Vessel Water Level, Temporary Modification, Brachytherapy)
- Information Notice 1992-17, NRC Inspections of Programs Being Developed at Nuclear Power Plants in Response to Generic Letter 89-10 (26 February 1992, Topic: Stroke time)
- Information Notice 1992-18, Potential for Loss of Remote Shutdown Capability During a Control Room Fire (28 February 1992, Topic: Hot Short, Safe Shutdown)
- Information Notice 1992-19, Misapplication of Potter and Brumfield Mdr Rotary Relays (2 March 1992)
- Information Notice 1992-19, Misapplication of Potter and Brumfield MDR Rotary Relays (2 March 1992)
- Information Notice 1992-20, Inadequate Local Leak Rate Testing (3 March 1992, Topic: Local Leak Rate Testing)
- Information Notice 1992-21, Spent Fuel Pool Reactivity Calculations (24 March 1992)
- Information Notice 1992-23, Results of Validation Testing of Motor-Operated Valve Diagnostic Equipment (27 March 1992)
- Information Notice 1992-24, Distributor Modification to Certain Commercial-Grade Agastat Electrical Relays (30 March 1992)
- Information Notice 1992-25, Pressure Locking of Motor-Operated Flexible Wedge Gate Valves (2 April 1992, Topic: Stroke time, Hydrostatic)
- Information Notice 1992-27, Thermally Induced Accelerated Aging and Failure of ITE/Gould A.C. Relays used in Safety-Related Applications (3 April 1992, Topic: Commercial Grade)
- Information Notice 1992-27, Thermally Induced Accelerated Aging and Failure of Ite/Gould A.C. Relays Used in Safety-Related Applications (3 April 1992, Topic: Commercial Grade)
- Information Notice 1992-28, Inadequate Fire Suppression System Testing (8 April 1992, Topic: Safe Shutdown)
- Information Notice 1992-29, Potential Breaker Miscoordination Caused by Instantaneous Trip Circuitry (17 April 1992)
- Information Notice 1992-30, Falsification of Plant Records (23 April 1992)
- Information Notice 1992-31, Electrical Connection Problem in Johnson Yokogawa Corporation YS-80 Programmable Indicating Controllers (27 April 1992)
- Information Notice 1992-32, Problems Identified with Emergency Ventilation Systems for Near-Site (Within 10 Miles) Emergency Operations Facilities and Technical Support Centers (29 April 1992)
- Information Notice 1992-32, Problems Identified with Emergency Ventilation Systems for Near-Site (within 10 Miles) Emergency Operations Facilities and Technical Support Centers (29 April 1992)
- Information Notice 1992-33, Increased Instrument Response Time When Pressure Dampening Devices Are Installed (30 April 1992)
- Information Notice 1992-33, Increased Instrument Response Time When Pressure Dampening Devices are Installed (30 April 1992)
- Information Notice 1992-34, New Exposure Limits for Airborne Uranium and Thorium (6 May 1992)
- Information Notice 1992-35, Higher than Predicted Erosion/Corrosion in Unisolable Reactor Coolant Pressure Boundary Piping Inside Containment at a Boiling Water Reactor (6 May 1992)
- Information Notice 1992-35, Higher than Predicted Erosion/Corrosion in Unisolable Reactor Coolant Pressure Boundary Piping inside Containment at a Boiling Water Reactor (6 May 1992)
- Information Notice 1992-36, Intersystem LOCA Outside Containment (7 May 1992)
- Information Notice 1992-37, Implementation of the Deliberate Misconduct Rule (8 May 1992)
- Information Notice 1992-38, Implementation Date for the Revision to the EPA Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (26 May 1992, Topic: Brachytherapy)
- Information Notice 1992-39, Unplanned Return to Criticality During Reactor Shutdown (13 May 1992, Topic: Fuel cladding)
- Information Notice 1992-40, Inadequate Testing of Emergency Bus Undervoltage Logic Circuitry (27 May 1992)
- Information Notice 1992-41, Consideration of Stem Rejection Load In Calculation of Required Valve Thrust (29 May 1992, Topic: Anchor Darling)
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