Failure of Reactor Trip Breaker to Open Because of Cutoff Switch Material Lodged in the Trip Latch MechanismML031060244 |
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 ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
03/22/1995 |
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From: |
Grimes B Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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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 ' 6sb
o
9503160374 PAQ T*tE bo qf-(otqS
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)
at44 I~
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-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
(CUTOFF SWITCH PIN 622 C 505 Gl) DROPPED DOWN TO BOlTOM OF
THE TRIP LATCH PREVENTING
THE LATCH FROM ACTUATING
vJ
Attachment 2 IN 95-19 March 22, 1995 SUBJECT ELECTRICALLY OPERATED
SWITCHGEAR AKR 30S AND AKRU 30S BREAKERS
OPERATION AK 25-1 AND AKU 25-1 BREAKERS
SERVICE ADVICE CUT OF SWITCH BREAKAGE
-- I Ce MAn jnIV n
TAB uIjsu ba A1U . JUJ . U
SWGR OPER O.
_ _ _ _ I _ _ _ _ _ _ _ _ _ _ _ _ _ I _ _ _ _ _ _ _ _ _
_ __ _ __ _ _ _ _ _ _
Backqround
The function of the Cut Off Switch is to interrupt the
closing coil when 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 Phone: (319) 753-8475 Customer Service 8*673-6475 General Electric Telecopier: (319) 753-5479 PO Box 488 8*673-6479 Burlington, IA 52601 Please have Breaker Serial Numbers and Date Codes when
you contact us.
,
I
PREPARED BY
_ _ _ _ .
.
II ISSUED BY
. z p x
II DATE I bUFtURtULb 1 II II IISSUE DATED IIOF
GARY SCHULE II DON LESNET II 4-06-89 0 (NEW)
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 Potential Pressure-Locking 03/15/95 All holders of OLs or CPs
of Safety-Related Power- for nuclear power reactors.
Operated Gate Valves
95-17 Reactor Vessel Top Guide 03/10/95 All holders of OLs or CPs
and Core Plate Cracking
95-16 Vibration Caused by 03/09/95 All holders of OLs or CPs
Increased Recirculation for boiling water reactors.
Flow in a Boiling Water
Reactor
95-15 Inadequate Logic Testing 03/07/95 All holders of OLs or CPs
of Safety-Related Circuits for nuclear power reactors.
95-14 Susceptibility of Con- 02/28/95 All holders of OLs or CPs
tainment Sump Recircula- for nuclear power reactors.
tion Gate Valves to
Pressure Locking
95-13 Potential for Data 02/24/95 All holders of OLs or CPs
Collection Equipment to for nuclear power reactors.
Affect Protection System
Performance
95-12 Potentially Nonconforming 02/21/95 All holders of OLs or CPs
Fasteners Supplied by for nuclear power reactors.
A&G Engineering II, Inc.
95-11 Failure of Condensate 02/24/95 All holders of OLs or CPs
Piping Because of Erosion/ for nuclear power reactors.
Corrosion at a Flow- Straightening Device
95-10 Potential for Loss of 02/10/95 All holders of OLs or CPs
Supp. 1 Automatic Engineered for nuclear power reactors.
Safety Features
Actuation
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 *See previous concurrence
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 S. K. Mitra, NRR
(404) 331-5582 (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 ICIAL 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 S. K. Mitra, NRR
(404) 331-5582 (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
nnrlMFrNT NAME- n-\nN\RRFAKFR
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 S. K. Mitra, NRR
(404) 331-5582 (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
nfnrilMrKT
UV%111L-1% I
IAMEM. r-
111ru-19- U.
N\RnFAVFR
\nvuvuW-Xl *SeP
---
nrevious
re
concurrence
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 Issued NRC Information Notices
MVtfla
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/95 lREG III i^
lSRudisail
0OIi1/95 REG II
MBShymlok~
J01f)*/95
- IEFGoodwin SC/OECB:DOPS:NRR
01_ 9_5 OECB:DOPS:NRR C/OECB:DOPS:NRR D/DOPS:NRR
RJKiessel AEChaffee BKGrimes
/95 01/ /95 /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)
- 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 Moisture Density Gauge)
- 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)
- Information Notice 1995-10, Potential for Loss of Automatic Engineered Safety Features Actuation (3 February 1995)
- Information Notice 1995-11, Failure of Condensate Piping Because of Erosion/Corrosion at Flow-Straightening Device (24 February 1995)
- 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)
- 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)
- 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)
- 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)
- Information Notice 1995-31, Motor-Operated Valve Failure Caused by Stem Protector Pipe Interference (9 August 1995)
- Information Notice 1995-32, Thermo-Lag 330-1 Flame Spread Test Results (10 August 1995, Topic: Fire Barrier)
- Information Notice 1995-33, Switchgear Fire and Partial Loss of Offsite Power at Waterford Generating Station, Unit 3 (23 August 1995)
- Information Notice 1995-34, Air Actuator and Supply Air Regulator Problems in Copes-Vulcan Pressurizer Power-Operated Relief Valves (25 August 1995)
- Information Notice 1995-35, Degraded Ability of Steam Generators to Remove Decay Heat by Natural Circulation (28 August 1995)
- Information Notice 1995-36, Potential Problems with Post-Fire Emergency Lighting (29 August 1995, Topic: Safe Shutdown, Emergency Lighting, Exemption Request)
- 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)
- 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: 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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