Failure of Reactor Trip Breaker to Open Because of Cutoff Switch Material Lodged in the Trip Latch MechanismML031060244 |
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 |
---|
Issue date: |
03/22/1995 |
---|
From: |
Grimes B K Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
References |
---|
IN-95-019, NUDOCS 9503160374 |
Download: ML031060244 (12) |
|
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>. |
-e UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 March 22, 1995 NRC INFORMATION
NOTICE 95-19: FAILURE OF REACTOR TRIP BREAKER TO OPEN BECAUSE OF CUTOFF SWITCH MATERIAL LODGED IN THE TRIP LATCH MECHANISM
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 the possible failure of a circuit breaker to open because of obstruction
by material from a subcomponent
switch. It is expected that recipients
will review this 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 July 14, 1994, during the monthly testing of the logic matrix of the reactor protection
system at St. Lucie, Unit 2, a General Electric (GE)Model AK 2-25 circuit breaker failed to open after operating
correctly
on three previous steps of the surveillance
procedure.
This circuit breaker is one of eight reactor trip circuit breakers in a one-out-of-two
taken twice reactor trip coincidence
logic. Several unsuccessful
attempts were made to open the breaker both electrically
and mechanically
before the licensee isolated the breaker as required by the Technical
Specifications
and shut down the Unit 2 reactor.The investigation
of the problem revealed that a 6-mm-square
[1/4-inch-square]
piece of phenolic material had jammed the circuit breaker trip latch mechanism, preventing
its operation.
This piece of phenolic material had broken off from the breaker cutoff switch (p/n 622 C 505 GI), which is part of the breaker antipump circuitry.
The cutoff switch is mounted in the breaker assembly above the trip latch mechanism (Figure 1). A screw holding the cutoff switch had come loose, allowing two halves of the switch to separate, become misaligned, and break during the previous circuit breaker operation.
The licensee inspected
the remaining
Unit 2 trip circuit breakers as well as the similar motor generator
set output breakers.
No additional
loose screws were found on the cutoff switch mountings.
The licensee has incorporated
the inspection
of the cutoff switch phenolic block and screw into the maintenance
procedures
for Units I and 2. a o ' 6s b 9503160374 PAQ T*tE bo s(A, qf-(otqS I ) 3H at44 I~ C fl
-V., IN 95-19 March 22, 1995 Discussion
On April 6, 1989, GE Switchgear
Operation
issued service advisory letter (SAL)303.0, which dealt with the possibility
that the cutoff switch actuator could crack and break and lead to breaker coil burnout. The text of SAL 303.0 is shown in Attachment
2. Although these cutoff switches had a different failure mode and were installed
on different
breaker models (Models AKR(U) 30s and AK(U) 25-1), the cutoff switch in question was the same part (p/n 622 C 505 GI) as the one that caused the AK2-25 breaker failure at St. Lucie, Unit 2.The majority of the reactor trip breaker failures at power reactors have been caused by problems with relatively
small electrical
subcomponents
in the breaker assembly, rather that the malfunction
of the main breaker mechanism itself. The failure of the cutoff switch in the trip breaker at St Lucie is another example of a subcomponent
failure resulting
in the failure of a trip breaker. The frequency
of reactor trip breaker failures could be reduced if these small component
problems were made less likely by appropriate
inspection
and maintenance.
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 (NRP) project manager.Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation
Technical
contacts:
S. Rudisail, Region II S. K. Mitra, NRR (404) 331-5582 (301) 415-2783 M. B. Shymlock, Region II (404) 331-5596 Attachments:
1. Figure 1 2. GE SAL 303.0 3. List of Recently Issued NRC Information
Notices
KJi Attachment
1 IN 95-19 March 22, 1995 FIGURE 1 AK-2 BREAKER FRONT VIEW f CUTOFF SWITCH TX
CONTACT
OR>
PIECE OF CUTOFF SWITCH DROPPED DOWN TO BOlTOM OF THE TRIP LATCH PREVENTING
THE LATCH FROM ACTUATING (CUTOFF SWITCH PIN 622 C 505 Gl)
vJ Attachment
2 IN 95-19 March 22, 1995 SWITCHGEAR
OPERATION SERVICE ADVICE SUBJECT ELECTRICALLY
OPERATED AKR 30S AND AKRU 30S BREAKERS AK 25-1 AND AKU 25-1 BREAKERS CUT OF SWITCH BREAKAGE-- I Ce MAn jnIV n TAB uIjsu SWGR OPER O.ba A1U .JUJ .U_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ I _ _ _ _ _ _ _ _ _ _ _ _ _ I _ _ _ _ _ _ _ _ _Backqround
The function of closing coil when the the Cut Off Switch is to interrupt
the breaker is closed.Problem On electrically
operated AKR(U) 30S and AK(U) 25-1 breakers manufactured
between July 1986 and November 1987 there is a possibility
that the cut off switch actuator may crack and break.If this occurs, the closing coil may be overheated
and burn up when the breaker is closed.Recommended
Action GE recommends
that the cut off switch actuator on all affected breakers be visually checked for cracks at the next regular breaker maintenance
/ inspection.
This includes all AKR(U) 30S breakers with a Breaker Code Date less than P747+ and all AK(U) 25-1 breakers with a Breaker Date Code P548+ through P747+. The Breaker Code Date is on the control voltage nameplate located to the right of the escutcheon
on the breaker frame.Corrective
Action If a broken or cracked cut off switch is found, contact Customer Service for a no-charge
replacement
cut off switch [Part No. 622C505G1]
at: Mary Hockett Customer Service General Electric PO Box 488 Burlington, IA 52601 Phone: (319) 753-8475 8*673-6475 Telecopier:
(319) 753-5479 8*673-6479 Please have Breaker Serial Numbers and Date Codes when you contact us.I_ ,_ _ _ ...z p x PREPARED BY GARY SCHULE II II I I ISSUED BY DON LESNET II II II DATE I bUFtURtULb
IISSUE DATED 4-06-89 0 (NEW)IIOF 1 Attachment
3 IN 95-19 March 22, 1995 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 95-18 95-17 95-16 95-15 95-14 Potential
Pressure-Locking
of Safety-Related
Power-Operated Gate Valves Reactor Vessel Top Guide and Core Plate Cracking Vibration
Caused by Increased
Recirculation
Flow in a Boiling Water Reactor Inadequate
Logic Testing of Safety-Related
Circuits Susceptibility
of Con-tainment Sump Recircula- tion Gate Valves to Pressure Locking Potential
for Data Collection
Equipment
to Affect Protection
System Performance
Potentially
Nonconforming
Fasteners
Supplied by A&G Engineering
II, Inc.Failure of Condensate
Piping Because of Erosion/Corrosion
at a Flow-Straightening
Device Potential
for Loss of Automatic
Engineered
Safety Features Actuation 03/15/95 03/10/95 03/09/95 03/07/95 02/28/95 02/24/95 02/21/95 02/24/95 02/10/95 All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs All holders of OLs or CPs for boiling water reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.95-13 95-12 95-11 95-10 Supp. 1 OL = Operating
License CP = Construction
Permit
IN 95-19 March 22, 1995 Discussion
On April 6, 1989, GE Switchgear
Operation
issued service advisory letter (SAL)303.0, which dealt with the possibility
that the cutoff switch actuator could crack and break and lead to breaker coil burnout. The text of SAL 303.0 is shown in Attachment
2. Although these cutoff switches had a different failure mode and were installed
on different
breaker models (Models AKR(U) 30s and AK(U) 25-1), the cutoff switch in question was the same part (p/n 622 C 505 Gi) as the one that caused the AK2-25 breaker failure at St. Lucie, Unit 2.The majority of the reactor trip breaker failures at power reactors have been caused by problems with relatively
small electrical
subcomponents
in the breaker assembly, rather that the malfunction
of the main breaker mechanism itself. The failure of the cutoff switch in the trip breaker at St Lucie is another example of a subcomponent
failure resulting
in the failure of a trip breaker. The frequency
of reactor trip breaker failures could be reduced if these small component
problems were made less likely by appropriate
inspection
and maintenance.
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. Gri fbyiatlI K. rmes Division of Project Support Office of Nuclear Reactor Regulation
Technical
contacts:
S. Rudisail, Region II S. K. Mitra, NRR (404) 331-5582 (301) 415-2783 M. B. Shymlock, Region II (404) 331-5596 Attachments:
1. Figure 1 2. GE SAL 303.0 3. List of Recently Issued NRC Information
Notices DOCUMENT NAME: S:\DOPS SEC\95-19.IN
OECB:DOPS:NRR*
RPB:ADM EELB:DE C/EELB:DE DCKirkpatrick
l BCalure, Tech Ed* SKMitra* CEBerlinger*
12/22/94 l 12/28/94 01/23/95 01/23/95 RII (via e-mail) RII (via e-mail) SC/OECB:DOPS:NRR
OECB:DOPS:NRR
SRudisail*
MBShymlok*
EFGoodwin*
RJKiessel*
01/25/95 01/25/95 Z 01/26/95 02/01/95 C/OECB:DOPS:NRR
D/J4* 7 =AEChaffee*
03/11/95 03// /95 OFFICIAL RECORD COPY
v~~IN 95-XX March xx, 1995 Discussion
On April 6, 1989, GE Switchgear
Operation
issued service advisory letter (SAL)303.0, which dealt with the possibility
that the cutoff switch actuator could crack and break and lead to breaker coil burnout. The text of SAL 303.0 is shown in Attachment
2. Although these cutoff switches had a different failure mode and were installed
on different
breaker models (Models AKR(U) 30s and AK(U) 25-1), the cutoff switch in question was the same part (p/n 622 C 505 Gl) as the one that caused the AK2-25 breaker failure at St. Lucie, Unit 2.The majority of the reactor trip breaker failures at power reactors have been caused by problems with relatively
small electrical
subcomponents
in the breaker assembly, rather that the malfunction
of the main breaker mechanism itself. The failure of the cutoff switch in the trip breaker at St Lucie is another example of a subcomponent
failure resulting
in the failure of a trip breaker. It follows that the frequency
of reactor trip breaker failures could be significantly
reduced if these small component
problems could be eliminated
by careful inspection
and maintenance.
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 Project Support Office of Nuclear Reactor Regulation
Technical
contacts: S. Rudisail, Region II (404) 331-5582 S. K. Mitra, NRR (301) 504-2783 M. B. Shymlock, Region II (404) 331-5596 Attachments:
1. Figure 1 2. GE SAL 303.0 3. List of Recently Issued NRC Information
Notices DOCUMENT NAMF: s!\nlfPS SFC\RRFAKER
- See nrev'ious concurrence
OECB:DOPS:NRR*
RPB:ADM EELB:DE C/EELB:DE DCKirkpatrick
BCalure, Tech Ed* SKMitra* CEBerlinger*
12/22/94 12/28/94 01/23/95 01/23/95 RII (via e-mail) RII (via e-mail) SC/OECB:DOPS:NRR
OECB:DOPS:NRR
SRudisail*
MBShymlok*
EFGoodwin*
RJKiessel*
01/25/95 01/25/95 01/26/95 02/01/95 C/OECB:DOPS:NRR
D/DOPS:NRR
AEChaffee*
BKGrimes 03/11/95 0 / j95_OFF IC IAL RECORD COPY
IN 95-xx March xx, 1995 Discussion
On April 6, 1989, GE Switchgear
Operation
issued service advisory letter (SAL)303.0, which dealt with the possibility
that the cutoff switch actuator could crack and break and lead to breaker coil burnout. The text of SAL 303.0 is shown in Attachment
2. Although these cutoff switches had a different failure mode and were installed
on different
breaker models (Models AKR(U) 30s and AK(U) 25-1), the cutoff switch in question was the same part (p/n 622 C 505 GI) as the one that caused the AK2-25 breaker failure at St. Lucie, Unit 2.The majority of the reactor trip breaker failures at power reactors have been caused by problems with relatively
small electrical
subcomponents
in the breaker assembly, rather that the malfunction
of the main breaker mechanism itself. The failure of the cutoff switch in the trip breaker at St Lucie is another example of a subcomponent
failure resulting
in the failure of a trip breaker. It follows that the frequency
of reactor trip breaker failures could be significantly
reduced if these small component
problems could be eliminated
by careful inspection
and maintenance.
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 Project Support Office of Nuclear Reactor Regulation
Technical
contacts: S. Rudisail, Region II (404) 331-5582 S. K. Mitra, NRR (301) 504-2783 M. B. Shymlock, Region II (404) 331-5596 Attachments:
1. Figure 1 2. GE SAL 303.0 3. List of Recently Issued NRC nnrlMFrNT
NAME- n-\nN\RRFAKFR
Information
Notices*See nrevious concurrence
vvVl r L. v \ --__ ._ .. ____.~. -.._........
__OECB:DOPS:NRR*
RPB:ADM* EELB:DE* C/EELB:DE*
DCKirkpatrick
BCalure, Tech Ed SKMitra CEBerlinger
12/22/94 12/28/94 01/23/95 01/23/95 RII* (via e-mail) RII* (via e-mail) SC/OECB:DOPS:NRR*
SRudisail
MBShymlok
EFGoodwin 01/25/95 01/25/95 01/26/95 OECB:DOPS:NRR*
C BD N D/DOPS:NRR
RJKiessel
AEChlree P BKGrimes 02/01/95 /11 /95 01/ /95 OFFICIAL RECORD COPY
IN 95-xx January xx, 1995 Discussion
On April 6, 1989, GE Switchgear
Operation
issued service advisory letter (SAL)303.0, which dealt with the possibility
that the cutoff switch actuator could crack and break and lead to breaker coil burnout. A copy of SAL 303.0 is attached.
Although these cutoff switches had a different
failure mode and were installed
on different
breaker models (Models AKR(U) 30s and AK(U) 25-1), the cutoff switch in question was the same part (p/n 622 C 505 GI) as the one that caused the AK2-25 breaker failure at St. Lucie, Unit 2.The majority of the reactor trip breaker failures at power reactors have been caused by problems with relatively
small electrical
subcomponents
in the breaker assembly, rather that the malfunction
of the main breaker mechanism itself. The failure of the cutoff switch in the trip breaker at St Lucie is another example of a subcomponent
failure resulting
in the failure of a trip breaker. It follows that the frequency
of reactor trip breaker failures could be significantly
reduced if these small component
problems could be eliminated
by careful inspection
and maintenance.
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 Project Support Office of Nuclear Reactor Regulation
Technical
contacts: S. Rudisail, Region II (404) 331-5582 S. K.(301)Mitra, NRR 504-2783 M. B. Shymlock, Region II (404) 331-5596 Attachments:
1. Figure 1 2. GE SAL 303.0 3. List of Recently Issued NRC nfnrilMrKT
IAMEM. r- \n N\RnFAVFR Information
Notices*SeP nrevious concurrence
UV%111L-1%
I 111ru-19- U. vuvuW-Xl ---re OECB:DOPS:NRR*
RPB:ADM* EELB:DE* C/EELB:DE*
DCKirkpatrick
BCalure, Tech Ed SKMitra CEBerlinger
12/22/94 J 12/28/94 01/23/95 _ 01/23/95 RII* (via e-mail) RII* (via e-mail) SC/OECB:DOPS:NRR*
SRudisail
MBShymlok
EFGoodwin 01/25/95 01/25/95 01/26/95 OECB:DOPS:NRR
C/OECB:DOPS:NRR
D/DOPS:NRR
=RJKiesse AEChaffee
BKGrimes*y /95 01/ /95 01/ /95 OFFICIAL RECORD COPY
IN 95-xx January xx, 1995 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 Project Support Office of Nuclear Reactor Regulation
Technical
contacts: S. Rudisail, Region II (404) 331-5582 M. B. Shymlock, Region II (404) 331-5596 S. K. Mitra, NRR (301) 504-2783 Attachments:
1. Figure 1 2. GE SAL 303.0 3. List of Recently MV tf la Issued NRC Information
Notices OECB:DOPS:NRR*
l RPB:ADM* EELB:DE C/EELB:DE
>DCKirkpatrick
BCalure ,Tech Ed SKMitra CEBerlinger
'l 12/22/94 12/28/94 1/Z3/95 1/Z/95lREG II I i^ REG II SC/OECB:DOPS:NRR
lSRudisail
MBShymlok~
-IEFGoodwin
0OIi1/95 J 01f)/95 01_ 9_5 OECB:DOPS:NRR
C/OECB:DOPS:NRR
D/DOPS:NRR
RJKiessel
AEChaffee
BKGrimes* 01/ /95 01/ /95 pc/ /95*See previous concurrences
From: Donald C. Kirkpatrick (DCK1)To: SBR Date: Wednesday, January 25, 1995 10:43 am Subject: CONCURNCE
W IN:FAILURE
OF RX TRIP BREAKR Steve: The attached file contains your proposed IN on the failure of the reactor trip breaker due to foreign material in the latch. Brian Grimes decided that it should be issued after all. We added some history on previous problems with the cutoff switch that was the source of the jamming material.Please review it, concur if possible and pass it on to Shymlock.
Pleace call me at (301) 504-1849 if you need anything else on this.Thanks, Don Kirkpatrick, OECB Files: G:\DON\BREAKER
From: Steven B. Rudisail (SBR)To: AT1:HMS1:HMS2:WN4:DCK1 Date: Wednesday, January 25, 1995 3:03 pm Subject: CONCURNCE
W IN:FAILURE
OF RX TRIP BREAKR Milton Shymlock and I have reviewed the draft notice and we both concur.CC: MBS
1. Contents of GE Service Advisory Letter 303.0 2. List of Recently Issued NRC Information
Notices OECB:DOPS:NRR
RPB:ADM EELB:DE C/EELB:DE DCKirkpatric
k , ' 4 9,4 Tech Ed SKMitra CEBerlinger
12/2/94 12b??/94 01/ 95 REG II REG II SC/OECB:DOPS
- NRR SRudisail
MBShymlok
EFGoodwin 01/ /95 01/ /95 01/ /95 OECB:DOPS:NRR
C/OECB:DOPS:NRR
D/DOPS:NRR
RJKiessel
AEChaffee
BKGrimes 01/ /95 01/ /95 01/ /95 2Z
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list | - Information Notice 1995-01, DOT Safety Advisory: High Pressure Aluminum Seamless and Aluminum Composite Hoop-Wrapped Cylinders (4 January 1995, Topic: Brachytherapy)
- Information Notice 1995-02, Problems With General Electric CR2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems With General Electric Cr2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems with General Electric CR2940 Contact Blocks in Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-03, Loss of Reactor Coolant Inventory and Potential Loss of Emergency Mitigation Functions While in a Shutdown Condition (18 January 1995, Topic: Packing leak, Water hammer)
- Information Notice 1995-04, Excessive Cooldown and Depressurization of the Reactor Coolant System Following Loss of Offsite Power (11 October 1996, Topic: Safe Shutdown, Shutdown Margin, Probabilistic Risk Assessment, Troxler)
- Information Notice 1995-05, Undervoltage Protection Relay Settings Out of Tolerance Due to Test Equipment Harmonics (20 January 1985)
- Information Notice 1995-06, Potential Blockage of Safety-Related Strainers by Material Brought Inside Containment (25 January 1995, Topic: Foreign Material Exclusion)
- Information Notice 1995-07, Radiopharmaceutical Vial Breakage During Preparation (27 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained with Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained With Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-09, Use of Inappropriate Guidelines and Criteria for Nuclear Piping and Pipe Support Evaluation and Design (31 January 1995, Topic: Operability Determination)
- Information Notice 1995-10, Potential for Loss of Automatic Engineered Safety Features Actuation (3 February 1995, Topic: High Energy Line Break)
- Information Notice 1995-11, Failure of Condensate Piping Because of Erosion/Corrosion at Flow-Straightening Device (24 February 1995, Topic: Feedwater Heater)
- Information Notice 1995-12, Potentially Nonconforming Fasteners Supplied by A&G Engineering II, Inc (21 February 1995)
- Information Notice 1995-13, Potential for Data Collection Equipment to Affect Protection System Performance (24 February 1995)
- Information Notice 1995-14, Susceptibility of Containment Sump Recirculation Gate Valves to Pressure Locking (28 February 1995)
- Information Notice 1995-15, Inadequate Logic Testing of Safety-Related Circuits (7 March 1995)
- Information Notice 1995-16, Vibration Caused by Increased Recirculation Flow in a Boiling Water Reactor (9 March 1995)
- Information Notice 1995-17, Reactor Vessel Top Guide and Core Plate Cracking (10 March 1995, Topic: Safe Shutdown, Intergranular Stress Corrosion Cracking, Stress corrosion cracking)
- Information Notice 1995-18, Potential Pressure-Locking of Safety-Related Power-Operated Gate Valves (15 March 1995)
- Information Notice 1995-19, Failure of Reactor Trip Breaker to Open Because of Cutoff Switch Material Lodged in the Trip Latch Mechanism (22 March 1995)
- Information Notice 1995-20, Failures in Rosemount Pressure Transmitters Due to Hydrogen Permeation Into Sensor Cell (22 March 1995)
- Information Notice 1995-21, Unexpected Degradation of Lead Storage Batteries (20 April 1995)
- Information Notice 1995-22, Hardened or Contaminated Lubricant Cause Metal-Clad Circuit Breaker Failures (21 April 1995, Topic: Hardened grease)
- Information Notice 1995-23, Control Room Staffing Below Minimum Regulatory Requirements (24 April 1995)
- Information Notice 1995-24, Summary of Licensed Operator Requalification Inspection Program Findings (25 April 1995, Topic: Job Performance Measure, License Renewal)
- Information Notice 1995-25, Valve Failure During Patient Treatment with Gamma Stereotactic Radiosurgery Unit (11 May 1995, Topic: Overdose)
- Information Notice 1995-26, Defect in Safety-Related Pump Parts Due to Inadequate Treatment (31 May 1995)
- Information Notice 1995-27, NRC Review of Nuclear Energy Institute, Thermo-Lag 330-1 Combustibility Evaluation Methodology Plant Screening Guide. (31 May 1995, Topic: Safe Shutdown, Fire Barrier, Exemption Request, Fire Protection Program)
- Information Notice 1995-28, Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites (5 June 1995, Topic: Safe Shutdown, Tornado Missile, Safe Shutdown Earthquake, Earthquake)
- Information Notice 1995-29, Oversight of Design and Fabrication Activities for Metal Components Used in Spent Fuel Dry Storage Systems (7 June 1995, Topic: Nondestructive Examination)
- Information Notice 1995-30, Susceptibility of Low-Pressure Coolant Injection Valves to Pressure Locking (3 August 1995, Topic: Hydrostatic, Power-Operated Valves, Overspeed trip)
- Information Notice 1995-31, Motor-Operated Valve Failure Caused by Stem Protector Pipe Interference (9 August 1995, Topic: Overspeed)
- Information Notice 1995-32, Thermo-Lag 330-1 Flame Spread Test Results (10 August 1995, Topic: Fire Barrier, Overspeed trip)
- Information Notice 1995-33, Switchgear Fire and Partial Loss of Offsite Power at Waterford Generating Station, Unit 3 (23 August 1995, Topic: Overspeed trip)
- Information Notice 1995-34, Air Actuator and Supply Air Regulator Problems in Copes-Vulcan Pressurizer Power-Operated Relief Valves (25 August 1995, Topic: Overspeed)
- Information Notice 1995-35, Degraded Ability of Steam Generators to Remove Decay Heat by Natural Circulation (28 August 1995, Topic: Overspeed)
- Information Notice 1995-36, Potential Problems with Post-Fire Emergency Lighting (29 August 1995, Topic: Safe Shutdown, Operator Manual Action, Emergency Lighting, Exemption Request, Overspeed)
- Information Notice 1995-37, Inadequate Offsite Power System Voltages During Design-Basis Events (7 September 1995)
- Information Notice 1995-38, Degradation of Boraflex Neutron Absorber in Spent Fuel Storage Racks (8 September 1995)
- Information Notice 1995-39, Brachytherapy Incidents Involving Treatment Planning Errors (19 September 1995, Topic: Brachytherapy, Underdose)
- Information Notice 1995-40, Supplemental Information to Generic Letter 95-03, Circumferential Cracking of Steam Generator Tubes. (20 September 1995, Topic: Hydrostatic, Nondestructive Examination, Brachytherapy)
- Information Notice 1995-41, Degradation of Ventilation System Charcoal Resulting from Chemical Cleaning of Steam Generators (22 September 1995, Topic: Brachytherapy)
- Information Notice 1995-42, Commission Decision on Resolution of Generic Issue 23, Reactor Coolant Pump Seal Failure. (22 September 1995, Topic: Brachytherapy)
- Information Notice 1995-43, Failure of Bolt-Locking Device on Reactor Coolant Pump Turning Vane (28 September 1995, Topic: Brachytherapy)
- Information Notice 1995-44, Ensuring Compatible Use of Drive Cables Incorporating Industrial Nuclear Company Ball-Type Male Connectors (26 September 1995, Topic: Brachytherapy)
- Information Notice 1995-45, American Power Service Falsification of American Society for Nondestructive Testing Certificates (4 October 1995, Topic: Commercial Grade, Brachytherapy)
- Information Notice 1995-46, Unplanned, Undetected Release of Radioactivity from the Exhaust Ventilation System of a Boiling Water Reactor (6 October 1995, Topic: Brachytherapy)
- Information Notice 1995-47, Unexpected Opening of a Safety/Relief Valve & Complications Involving Suppression Pool Cooling Strainer Blockage (30 November 1995)
... further results |
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