Information Notice 1992-27, Thermally Induced Accelerated Aging and Failure of Ite/Gould A.C. Relays Used in Safety-Related Applications: Difference between revisions
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===UNITED STATES=== | |||
NUCLEAR REGULATORY COMMISSION | NUCLEAR REGULATORY COMMISSION | ||
OFFICE OF NUCLEAR REACTOR REGULATION | ===OFFICE OF NUCLEAR REACTOR REGULATION=== | ||
WASHINGTON, D.C. | |||
20555 | |||
===April 3, 1992=== | |||
NRC INFORMATION NOTICE 92-27: THERMALLY INDUCED ACCELERATED AGING AND | |||
FAILURE OF ITE/GOULD A.C. RELAYS USED | FAILURE OF ITE/GOULD A.C. RELAYS USED | ||
| Line 38: | Line 47: | ||
failure of 120Y ac relays manufactured by the ITE/Gould Manufacturing Company | failure of 120Y ac relays manufactured by the ITE/Gould Manufacturing Company | ||
(currently Telemecanique). The relay failures rendered portions of the associ- ated safety-related systems inoperable. It is expected that recipients will | (currently Telemecanique). | ||
The relay failures rendered portions of the associ- ated safety-related systems inoperable. It is expected that recipients will | |||
review the information for applicability to their facilities and consider | review the information for applicability to their facilities and consider | ||
| Line 53: | Line 64: | ||
features operability test, the licensee for the Millstone Nuclear Power | features operability test, the licensee for the Millstone Nuclear Power | ||
Station, Unit 3, noted that control power was interrupted to three safety- related motor operated valves (MOYs). The valves were located in the charging, component cooling water, and steam generator atmospheric dump systems. The | Station, Unit 3, noted that control power was interrupted to three safety- related motor operated valves (MOYs). The valves were located in the charging, component cooling water, and steam generator atmospheric dump systems. | ||
The | |||
licensee inspected the valves' control power circuitry and determined that | licensee inspected the valves' control power circuitry and determined that | ||
three normally energized auxiliary relays had failed. | three normally energized auxiliary relays had failed. | ||
===These relays provided=== | |||
control power alarms and thermal overload protection for the MOYs. The relay | control power alarms and thermal overload protection for the MOYs. The relay | ||
| Line 66: | Line 80: | ||
relays with J20M magnet block assemblies and standard G1OJA126, 120V, 60 cycle | relays with J20M magnet block assemblies and standard G1OJA126, 120V, 60 cycle | ||
coil assemblies manufactured by the ITE/Gould Manufacturing Company. Inspection | coil assemblies manufactured by the ITE/Gould Manufacturing Company. | ||
Inspection | |||
of the relays revealed that the movable plastic armature carrier, which surrounds | of the relays revealed that the movable plastic armature carrier, which surrounds | ||
the core and coil, and the retainer for the magnet yoke assembly were discolored, brittle and severely cracked. | the core and coil, and the retainer for the magnet yoke assembly were discolored, brittle and severely cracked. | ||
===Insulation degradation was severe, allowing=== | |||
electrical shorts to develop within the coils. The licensee concluded that the | electrical shorts to develop within the coils. The licensee concluded that the | ||
| Line 87: | Line 104: | ||
cluster. The relays were originally qualified, individually, for the life of | cluster. The relays were originally qualified, individually, for the life of | ||
the plant. However, the qualification process did not account for the use of | the plant. | ||
However, the qualification process did not account for the use of | |||
the relays in the ganged arrangement. The licensee stated that the potential | the relays in the ganged arrangement. The licensee stated that the potential | ||
| Line 151: | Line 170: | ||
of the failure of any of the other J-class relays, these relays could be suscep- tible to similar heat induced degradation when gang mounted. | of the failure of any of the other J-class relays, these relays could be suscep- tible to similar heat induced degradation when gang mounted. | ||
IN 92-27 April 3, 1992 This information notice requires no specific action or written response. If | IN 92-27 April 3, 1992 This information notice requires no specific action or written response. | ||
If | |||
you have any questions about the information in this notice, please contact | you have any questions about the information in this notice, please contact | ||
| Line 159: | Line 180: | ||
Reactor Regulation (NRR) project manager. | Reactor Regulation (NRR) project manager. | ||
Charles E. Rossi, Director | ===Charles E. Rossi, Director=== | ||
Division of Operational Events Assessment | Division of Operational Events Assessment | ||
Office of Nuclear Reactor Regulation | ===Office of Nuclear Reactor Regulation=== | ||
Technical contacts: N. Fields, NRR | |||
(301) 504-1173 | |||
(301) 504-1173 | |||
===K. Naidu, NRR=== | |||
(301) 504-2980 | (301) 504-2980 | ||
===R. Spence, AEOD=== | |||
(301) 492-8609 Attachment: List of Recently Issued NRC Information Notices | (301) 492-8609 Attachment: List of Recently Issued NRC Information Notices | ||
m | |||
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%MM | %MM | ||
Attachment | *0 | ||
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IN 92-27 | |||
===April 3, 1992 LIST OF RECENTLY ISSUED=== | |||
NRC INFORMATION NOTICES | |||
Information | |||
Date of | |||
Notice No. | |||
Subject | |||
Issuance | |||
Issued to | |||
92-26 | 92-26 Pressure Locking of Motor- | ||
04/02/92 | |||
===All holders of OLs or CPs=== | |||
Operated Flexible Wedge | |||
for nuclear power reactors. | for nuclear power reactors. | ||
Gate Valves | |||
92-25 Potential Weakness in | |||
03/31/92 | |||
Licensee Procedures for A | ===All holders of OLs or CPs=== | ||
Licensee Procedures for A | |||
for nuclear power reactors. | |||
===Loss of the Refueling=== | |||
Cavity Water | Cavity Water | ||
92-24 | 92-24 Distributor Modification to | ||
03/30/92 | |||
===All holders of OLs or CPs=== | |||
Certain Coemercial-Grade | |||
for nuclear power reactors. | |||
===Agastat Electrical Relays=== | |||
92-23 Results of Validation Test- | |||
03/27/92 | |||
===All holders of OLs or CPs=== | |||
ing of Motor-Operated Valve | |||
for nuclear power reactors | |||
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 Coeuercial- | |||
===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- | 92-19 Misapplication of Potter 5 | ||
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 | during A Control Room Fire | ||
OL - Operating License | |||
CP - Construction Permit | |||
( | |||
. X | . X | ||
X | |||
I> | |||
a | |||
a | |||
0 | |||
I5 | |||
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IN 92-27 April 3, 1992 This information notice requires no specific action or written response. If | IN 92-27 April 3, 1992 This information notice requires no specific action or written response. If | ||
| Line 267: | Line 347: | ||
Reactor Regulation (NRR) project manager. | Reactor Regulation (NRR) project manager. | ||
Charles E. Rossi, Director | ===Charles E. Rossi, Director=== | ||
Division of Operational Events Assessment | Division of Operational Events Assessment | ||
Office of Nuclear Reactor Regulation | ===Office of Nuclear Reactor Regulation=== | ||
Technical contacts: | |||
===N. Fields, NRR=== | |||
(301) 504-1173 | |||
(301) 504-1173 | |||
===K. Naidu, NRR=== | |||
(301) 504-2980 | (301) 504-2980 | ||
(301) 492-8609 Attachment: | ===R. Spence, AEOD=== | ||
(301) 492-8609 Attachment: | |||
===List of Recently Issued NRC Information Notices=== | |||
*SEE PREVIOUS CONCURRENCE | *SEE PREVIOUS CONCURRENCE | ||
OFC | OFC | ||
NAME :NFields* | |||
DATE :03/04/92 | :DOEA:OEAB | ||
_____ _______ | |||
:AEOD:ROAB | |||
NAME :AChaffee* | :DRIS:RVIB | ||
DATE :03/11/92 | |||
:ADM:RPB | |||
:RI | |||
:SC:DOEA:OEAB: | |||
NAME :NFields* | |||
:RSpence* | |||
:KNaidu* | |||
:JMain* | |||
:RBarkley* | |||
:DFischer* | |||
: | |||
DATE :03/04/92 | |||
:03/04/92 | |||
:03/09/92 | |||
:01/23/92 | |||
:03/05/92 | |||
:03/11/92 OFC :C:DOEA:OEAB :C:DOEA:OGCB :D:DOEA | |||
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_____ _______ | |||
___----------:- | |||
A | |||
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:------------ | |||
:------------:------------ | |||
:--------- | |||
NAME :AChaffee* | |||
:CBerlinger* : | |||
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DATE :03/11/92 | |||
:03/18/92 | |||
:03/2;792 | |||
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===OFFICIAL RECORD COPY=== | |||
Document Name: | |||
===IN DRAFT MILLSTONE=== | |||
IN 92-XX | IN 92-XX | ||
| Line 306: | Line 428: | ||
Reactor Regulation (NRR) project manager. | Reactor Regulation (NRR) project manager. | ||
Charles E. Rossi, Director | ===Charles E. Rossi, Director=== | ||
Division of Operational Events Assessment | Division of Operational Events Assessment | ||
Office of Nuclear Reactor Regulation | ===Office of Nuclear Reactor Regulation=== | ||
Technical contacts: N. Fields, NRR | |||
Technical contacts: | |||
(301) 504-1173 | (301) 504-1173 | ||
===K. Naidu, NRR=== | |||
(301) 504-2980 | (301) 504-2980 | ||
(301) 492-8609 Attachment: | ===R. Spence, AEOD=== | ||
(301) 492-8609 Attachment: List of Recently Issued NRC Information Notices | |||
*SEE PREVIOUS CONCURRENCE | *SEE PREVIOUS CONCURRENCE | ||
OFC | OFC | ||
NAME :NFields* | |||
DATE :03/04/92 | :DOEA:OEAB | ||
:AEOD:ROAB | |||
:DRIS:RVIB | |||
:ADM:RPB | |||
:RI | |||
:SC:DOEA:OEAB: | |||
NAME :NFields* | |||
:RSpence* | |||
:KNaidu* | |||
:JMain* | |||
:RBarkley* | |||
:DFischer* | |||
: | |||
DATE :03/04/92 | |||
:03/04/92 | |||
:03/09/92 | |||
:01/23/92 | |||
:03/05/92 | |||
:03/11/92 OFC :C:DOEA:OEAB :C:D0E 9yt | |||
D:DOEA | |||
Document Name: IN DRAFT MILLSTONE | : | ||
: | |||
________---------:----1--- | |||
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NAME :AChaffee* | |||
:CBer | |||
:CRossi | |||
DATE :03/11/92 | |||
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===OFFICIAL RECORD COPY=== | |||
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===IN DRAFT MILLSTONE=== | |||
*SEE PREVIOUS CONCURRENCE | *SEE PREVIOUS CONCURRENCE | ||
OFC | OFC | ||
:DOEA:OEAB | |||
:AEOD:ROAB | |||
:DRIS:RVIB | |||
:ADM:RPB | |||
:RI | |||
:S | |||
OEA:OEAB: | |||
NAME :NFields* | |||
:RSpence* | |||
:KNaidu* | |||
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:RBarkley* | |||
:DF scner | |||
: | |||
DATE :03/04/92 | |||
:03/04/92 | |||
:03/09/92 | |||
:01/23/92 | |||
:03/05/92 | |||
: 3/gi/92 OFC :C:DOEA:OEAB :C:DOEA:OGCB :D:DOEA | |||
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===OFFICIAL RECORD COPY=== | |||
Document Name: IN DRAFT MILLSTONE | Document Name: IN DRAFT MILLSTONE | ||
*SEE PREVIOUS CONCURRENCE | *SEE PREVIOUS CONCURRENCE | ||
OFC | OFC | ||
:DOEA:OEAB | |||
:AEOD:ROAB | |||
:DRIS:RVIB | |||
:ADM:RPB | |||
:RI | |||
:SC:DOEA:OEAB: | |||
NAME :NFields* | |||
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:JMain* | |||
:RBarkley* | |||
:DFischer | |||
DATE :03/04/92 | |||
:03/04/92 | |||
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/92 OFC :C:DOEA:OEAB :C:DOEA:OGCB :D:DOEA | |||
Document Name: IN DRAFT MILLSTONE | NAME :AChaffee | ||
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===IN DRAFT MILLSTONE=== | |||
*SEE PREVIOUS CONCURRENCE | *SEE PREVIOUS CONCURRENCE | ||
OFC | OFC :DOEA:OEAB | ||
:AEOD:ROAB | |||
:DRIS:RYIB | |||
:ADM:RPB | |||
:RI | |||
:SC:DOEA:OEAB: | |||
NAME :NFields* | |||
:RSpence* | |||
:KNaidu | |||
:JMain* | |||
:RBark1e! | |||
:DFischer | |||
: | |||
-------- | |||
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DATE :03/04/92 | |||
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OFC :C:DOEA:OEAB :C:DOEA:OGCB :D:DOEA | |||
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DATE ://92 | DATE ://92 | ||
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Document Name: IN DRAFT MILLSTONE}} | ===OFFICIAL RECORD COPY=== | ||
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IN DRAFT MILLSTONE}} | |||
{{Information notice-Nav}} | {{Information notice-Nav}} | ||
Latest revision as of 10:14, 16 January 2025
P.
.
I3
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C.
20555
April 3, 1992
NRC INFORMATION NOTICE 92-27: THERMALLY INDUCED ACCELERATED AGING AND
FAILURE OF ITE/GOULD A.C. RELAYS USED
IN SAFETY-RELATED APPLICATIONS
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 problems resulting from the accelerated aging and
failure of 120Y ac relays manufactured by the ITE/Gould Manufacturing Company
(currently Telemecanique).
The relay failures rendered portions of the associ- ated safety-related systems inoperable. 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
On November 23, 1991, while performing an eighteen month engineered safety
features operability test, the licensee for the Millstone Nuclear Power
Station, Unit 3, noted that control power was interrupted to three safety- related motor operated valves (MOYs). The valves were located in the charging, component cooling water, and steam generator atmospheric dump systems.
The
licensee inspected the valves' control power circuitry and determined that
three normally energized auxiliary relays had failed.
These relays provided
control power alarms and thermal overload protection for the MOYs. The relay
failures rendered each valve inoperable.
The relays, which had been in service for about seven years, were class J10
relays with J20M magnet block assemblies and standard G1OJA126, 120V, 60 cycle
coil assemblies manufactured by the ITE/Gould Manufacturing Company.
Inspection
of the relays revealed that the movable plastic armature carrier, which surrounds
the core and coil, and the retainer for the magnet yoke assembly were discolored, brittle and severely cracked.
Insulation degradation was severe, allowing
electrical shorts to develop within the coils. The licensee concluded that the
failures resulted from the thermal aging of the coil assemblies and plastic
parts near the coil assemblies.
9203270157 ;Z4-
IN 92-27 April 3, 1992 The failed relays were mounted shoulder to shoulder in a horizontal "ganged"
arrangement on a universal mounting strip supplied by the manufacturer. The
three relays that failed were each mounted in the middle of a ganged relay
cluster. The relays were originally qualified, individually, for the life of
the plant.
However, the qualification process did not account for the use of
the relays in the ganged arrangement. The licensee stated that the potential
heat induced degradation of "weak-link" materials such as the plastic armature
carrier was not considered in the qualification test report.
The licensee inspected relays in other safety and nonsafety systems and found
similar discoloration and embrittlement caused by overheating, but found no
additional failures. The Millstone licensee has replaced approximately 260
relays with identical components from spare motor control centers. Long term
corrective actions include periodic monitoring and replacement and/or physical
separation of ganged relays.
During the period April 1987 through August 1987, the licensee for the Seabrook
Generating Station experienced similar failures of ITE/Gould J-10 relays.
Following those failures, Telemecanique submitted a report to the NRC under
Title 10 of the Code of Federal Regulations (10 CFR), Part 21 (Part 21 report)
describing the Uailures at Seabrook. The report attributed the overheating
failures to the special low voltage coils in the J10 relays that were supplied
to the Seabrook Nuclear Station. Telemecanique stated that the relays supplied
to Seabrook were equipped with a non-standard magnet coil (identified as 816 with 50 ohms resistance) and, therefore, the failure mode would not be experi- enced at any other facility. The licensee for the Seabrook Station submitted a
Licensee Event Report (LER) to the NRC under 10 CFR Part 50.73 describing the
relay failures and their root cause analysis. The licensee stated in the LER
that, "...It was originally believed that excessive temperature resulted from
the close proximity of six normally energized relays...Subsequent investigation
led to the identification of relays not in close proximity with other energized
components that showed slight discoloration." However, the Seabrook licensee
accepted the Telemecanique Part 21 report conclusions that the failures were
due to the heat generated by the energized, non-standard coil.
The recent failures at Millstone suggest that the Seabrook licensee's original
conclusion may have been accurate. The gang mounting ("close proximity") of
these relays was likely a major contributor to the accelerated aging with
the condition being exacerbated by the additional heat generated by the contin- uously energized coil.
The J10 relay is one of a family of J-class relays currently manufactured by
Telemecanique as commercial grade items. Although the NRC staff is not aware
of the failure of any of the other J-class relays, these relays could be suscep- tible to similar heat induced degradation when gang mounted.
IN 92-27 April 3, 1992 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.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contacts: N. Fields, NRR
(301) 504-1173
K. Naidu, NRR
(301) 504-2980
R. Spence, AEOD
(301) 492-8609 Attachment: List of Recently Issued NRC Information Notices
m
CI
in W
11 I
2 I C0U-
%MM
- 0
a
Cl5
2 Attachment
April 3, 1992 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information
Date of
Notice No.
Subject
Issuance
Issued to
92-26 Pressure Locking of Motor-
04/02/92
All holders of OLs or CPs
Operated Flexible Wedge
for nuclear power reactors.
Gate Valves
92-25 Potential Weakness in
03/31/92
All holders of OLs or CPs
Licensee Procedures for A
for nuclear power reactors.
Loss of the Refueling
Cavity Water
92-24 Distributor Modification to
03/30/92
All holders of OLs or CPs
Certain Coemercial-Grade
for nuclear power reactors.
Agastat Electrical Relays
92-23 Results of Validation Test-
03/27/92
All holders of OLs or CPs
ing of Motor-Operated Valve
for nuclear power reactors
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 Coeuercial-
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 5
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
OL - Operating License
CP - Construction Permit
(
. X
X
I>
a
a
0
I5
IN 92-27 April 3, 1992 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.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contacts:
N. Fields, NRR
(301) 504-1173
K. Naidu, NRR
(301) 504-2980
R. Spence, AEOD
(301) 492-8609 Attachment:
List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCE
OFC
- DOEA:OEAB
- AEOD:ROAB
- DRIS:RVIB
- ADM:RPB
- RI
- SC:DOEA:OEAB:
NAME :NFields*
- RSpence*
- KNaidu*
- JMain*
- RBarkley*
- DFischer*
DATE :03/04/92
- 03/04/92
- 03/09/92
- 01/23/92
- 03/05/92
- 03/11/92 OFC :C:DOEA:OEAB :C:DOEA:OGCB :D:DOEA
_____ _______
___----------:-
A
- ------------
- ------------:------------
- ---------
NAME :AChaffee*
- CBerlinger* :
DATE :03/11/92
- 03/18/92
- 03/2;792
OFFICIAL RECORD COPY
Document Name:
IN DRAFT MILLSTONE
IN 92-XX
March xx, 1992 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.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contacts: N. Fields, NRR
(301) 504-1173
K. Naidu, NRR
(301) 504-2980
R. Spence, AEOD
(301) 492-8609 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCE
OFC
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DATE :03/04/92
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DATE :03/04/92
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