Hardened or Contaminated Lubricant Cause Metal-Clad Circuit Breaker FailuresML031060206 |
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: |
04/21/1995 |
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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-95-022, NUDOCS 9504180073 |
Download: ML031060206 (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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Category:NRC Information Notice
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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>. |
UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 April 21, 1995 NRC INFORMATION
NOTICE 95-22: HARDENED OR CONTAMINATED
LUBRICANTS
CAUSE METAL-CLAD
CIRCUIT BREAKER FAILURES
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 that could result from failing to periodically
check the condition
of lubricants
that may become hardened or contain contaminants
used in HK series (4-kV and 6.9-kV) and K-Line (600-V)circuit breakers manufactured
by Asea Brown Boveri (ABB, formerly ITE) and DB-50 (480-V) breakers manufactured
by Westinghouse.
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
Hardened Grease in Breaker Operating
Mechanisms
On October 4, 1988, during surveillance
testing of the low-pressure
core spray pump at River Bend, Unit 1, the safety-related
ABB HK 4-kV circuit breaker failed to close after the closing circuit was energized
from the control room.The failure was attributed
to breaker linkage grease that had solidified
with age, thus causing the closing mechanism
to bind.On February 8, 1989, during post maintenance
testing at D.C. Cook, Unit 1, an ABB HK 4-kV breaker failed to close after the closing circuit was energized.
On February 27, 1989, another HK breaker failed to close during a test. Both failures were attributed
to hardened grease that caused the operating mechanism
to bind. Seven additional
HK series breakers used in safety-related
and balance-of-plant
applications
also failed in this manner. The breakers were 17 years old and had been inspected
and serviced several times. However, the revision of the vendor manual in use and, consequently, licensee procedures
did not state the need to disassemble, clean or relubricate
the operating
mechanism
on a periodic basis, except when grease is found to be"contaminated" or when parts are replaced (see NRC Inspection
Report 50-315/89031 for additional
information).
RDiR :j4E JS en ce. SSOQ2S 95(YjS/9504180073 dr<F0S At0
IN 95-22 April 21, 1995 During an October 1992 surveillance
test at LaSalle, Unit 1, an ABB HK 4-kY reactor recirculation
pump breaker failed to trip. The failure was attributed
to hardened grease in the operating
mechanism.
In October 1993, during a Unit 2 refueling
outage, a nonsafety-related
ABB HK 4-kY pump breaker failed to close. This failure also was attributed
to hardened operating
mechanism grease. The licensee breaker maintenance
procedures
did not require inspection (other than visual), disassembly, or relubrication
of the breaker operating
mechanism
on a periodic basis (see NRC Inspection
Report 50-373/93031 for additional
information).
Contamination
of Grease on Sliding Electrical
Parts On November 5, 1989, during surveillance
testing at D.C. Cook, a Westinghouse
DB-50 480-V "B" train reactor trip bypass breaker failed to close electrically
because of high resistance
in the auxiliary
contacts that were part of the closing circuit. The high resistance
may have resulted from contamination
of the conductive
graphite grease prescribed
by the vendor manual. The revision of the Westinghouse
instruction
manual in use at D.C. Cook did not contain a recommendation
for periodically
replacing
the graphite grease or checking its condition (e.g., by measuring
contact resistance).
However, recent guidance issued by the vendor provided for such checking and replacement, as required.Discussion
The ABB HK breakers failed because lubricating
grease solidified
with age in the breaker operating
mechanisms.
As the grease hardened, friction increased in the metal-to-metal
contact areas. The additional
metal friction, as well as some interference
from hardened grease deposits, caused the mechanism
to become increasingly
difficult
to operate freely, eventually
resulting
in failures of the breakers to open or close. The circuit breakers discussed above had been routinely
inspected
on numerous occasions.
However, while the licensees
adequately
verified cleanliness
in the visual inspections, they failed to identify lubricant
that was solidified
or contaminated.
Preventive
maintenance
activities
did not include periodic cleaning or disassembly
of the operating
mechanism
to determine
if the operating
mechanism
should be relubricated.
Until 1991, all the revisions
to the ITE/ABB HK and K-Line vendor manuals stated that breaker operating
mechanisms
were factory lubricated
and should not require additional
lubrication
during breaker service life. However, as early as 1972, ABB manuals, such as ITE HK Switchgear
Instruction
Book IB-8.2.7-1, and medium-voltage
switchgear
maintenance
and surveillance
manuals MS 3.2.1.9-IB (for HK) and MS 3.1.1.9-2B (for K-Line), did call for cleaning and relubrication
of the mechanism
with ANDEROL 757 grease (or NO-OX-ID grease for mating surfaces of moving, current-carrying
joints) should any lubricant be found contaminated
or when parts are replaced.In response to a 1989 10 CFR Part 21 report from D.C. Cook of mechanism binding due to hardened grease, ABB sent a letter to the NRC and all known affected licensees
or purchasers
of HK and K-Line breakers that described
the
K> ' IN 95-22 April 21, 1995 problem and recommended
solutions.
LaSalle, for example, had received this letter, yet had not updated procedures
to prevent the 1992 and 1993 failures.Other plants with the affected breakers included Perry, Comanche Peak, and Fermi. Comanche Peak had taken action to prevent these failures.In 1991, ABB issued revisions
to the HK and K-Line manuals that called for periodic (10-year)
cleaning and relubrication
of the operating
mechanism
with ANDEROL 757 and the mating surfaces of moving, current-carrying
joints with the NO-OX-ID, although mechanical
failures to operate have only been attributed
to hardened mechanism
lubricant.
In September
29 and October 3, 1994, letters to the NRC, ABB stated, on the basis of recent refurbishments, that the condition
of the mechanism
lubricant
cannot be determined
without complete disassembly
of the mechanism.
The October letter also cited failures of K3000 breakers as a result of hardened mechanism
lubricant, but stated that although failures of smaller K-Line breakers attributable
to hardened mechanism
grease had not been reported, some had operated sluggishly.
Repor-tedly, most of these breakers also have not been periodically
disassembled, cleaned, or relubricated
in service. In performing
post maintenance
testing, licensees
found no evidence of impending
breaker failures due to hardened grease because the tests were performed
primarily
to determine
whether the breaker tripped or closed.Unusual service conditions
such as high ambient temperatures, very dirty atmosphere
during construction
or outages or mixing of incompatible
greases were not specifically
identified
in the instances
cited. However, such conditions
accelerate
hardening
of mechanism
lubricants
and are conducive
to dirt or chemical contamination
and increased
electrical
resistance
of electrical
part lubricants.
Note that ESSO/Humble (now EXXON) NEBULA EP5F grease was used for these breakers prior to March 1972. After this date, new breaker mechanisms
were factory-lubricated
with ANDEROL 757. Manufacturers
have warned that old (or unidentified)
grease should be completely
removed before relubricating.
Although referring
to a different
type of circuit breaker, NRC IN 93-26,"Grease Solidification
Causes Molded-Case
Circuit Breaker Failure to Close," issued April 7, 1993, and its supplement
issued January 31, 1994, described
a similar problem. In addition, addressees
are reminded of commitments
made in response to the staff position in Generic Letter 90-03 and its Supplement
1, to maintain contact with certain key vendors (which include Class IE switchgear
vendors), in order to ensure that manuals (and equipment)
are kept up to date and the latest technical
information (including
10 CFR Part 21 reports and related correspondence)
is promptly obtained, evaluated
for applicability, and acted on, as appropriate.
Recommendations
for switchgear
maintenance
can also be found in owners group documents (e.g., the Westinghouse
Owners Group guidelines
on DB and DS breaker maintenance)
and industry guidance such as National Electrical
Manufacturers
Association (NEMA)publications, American National Standards
Institute/Institute
of Electrical
and Electronic
Engineers (ANSI/IEEE)
standards, and various Electric Power Research Institute (EPRI) reports such as NP-7410, "Breaker Maintenance."
-'~' IN 95-22 April 21, 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:
Rogelio Mendez, RIII (708) 829-9745 Stephen D. Alexander, NRR (301) 415-2995 Sikhindra
K. Mitra, NRR (301) 415-2783 Tirupataiah
Tella, RIII (708) 829-9749 Attachment:
List of Recently Issued NRC Information
Notices Le&la W
"Attachment
IN 95-22 April 21, 1995 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 95-21 94-64, Supp. 1 95-18, Supp. 1 95-20 95-19 95-18 Unexpected
Degradation
of Lead Storage Batteries Reactivity
Insertion Transient
and Accident Limits for High Burnup Fuel Potential
Pressure-Locking
of Safety-Related
Power-Operated Gate Valves Failures in Rosemount Pressure Transmitters
due to Hydrogen Per-meation into the Sensor Cell Failure of Reactor Trip Breaker to Open Because of Cutoff Switch Material Lodged in the Trip Latch Mechanism 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 04/20/95 04/06/95 03/31/95 03/22/95 03/22/95 03/15/95 03/10/95 03/09/95 03/07/95 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.All holders of OLs or CPs for boiling water reactors.All holders of OLs or CPs for boiling water reactors.All holders of OLs or CPs for nuclear power reactors.95-17 95-16 95-15 OL -Operating
License CP -Construction
Permit
I'~' IN 95-22 April 21, 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.orig /s/'d by CIGrimes Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation
Technical
contacts: Rogelio Mendez, RIII (708) 829-9745 Stephen D. Alexander, NRR (301) 415-2995 Sikhindra
K. Mitra, NRR (301) 415-2783 Tirupataiah
Tella, RIII (708) 829-9749 Attachment:
List of Recently Issued NRC Information
Notices* See EGGreenman
memorandum
to RLDennig dated June and previous concurrence
pages.DOCUMENT NAME: 95-22.IN----- at thL A....t I*.Alt. In tkhe bnx: 'C -CODY without enclosures "E" 15, 1994-CoDy with enclosures
ENS = No copy TO- ,-.IV[OFFICE Region III E Region III II E Region III E NAME TTella* RMendez* GGrant* EGGreenman*
DATE 09/07/94 06/10/94 06/10/94 06/13/94 OFFICE SIB/DOTS E TECH ED N SC:SIB DOTS E C:SIB/DOTS
E E D:DOTS:NRR
NAME SAlexander*
BCalure* GCwalina*
RGallo* RLSpessard*
DATE 01/03/95 12/29/94 01/03/95 101/06/95
101/06/95 OFFICE EELB/DE E C:EELB/DE
ECB:DOPS C:ECB/DOPS
L D-IDOPSI L NAME ISMitra* CBerlinger*
RKiessel AChaffee BKGrimeV)
I DATE 109/22/94
10/26/94 03/29/95 04/07/95 9 OFFICIAL RECORD COPY
IN 95-XX March 9, 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: Rogelio Mendez, Region III (708) 829-9745 Stephen D. Alexander, NRR (301) 415-2995 Sikhindra
K. Mitra, NRR (301) 415-2783 Tirupataiah
Tella, Region III (708) 829-9749 Attachment:
List of Recently Issued NRC Information
Notices* See EGGreenman
memorandum
to RLDennig dated June 15, 1994 and previous concurrence
pages.DOCUMENT NAME: BKRGRSE.SDA
To receive a conv of this document.
Indicate In the box: 'C" -Coov without enclosures
'E' = Copy with enclosures
'N" -No coDy OFFICE Region III E Region III E Region III E Regibn III I E NAME TTella* RMendez* GGrant* EGGreenman*
DATE 09/07/94 06/10/94 106/10/94
06/13/94 OFFICE SIB/DOTS E TECH ED N SC:SIB/DOTS
I E C:SIB/DOTS
E ]D:DOTS:NRRl
N NAME SAlexander*
BCalure* GCwalina*
IRGallo* RL pessard*DATE 01/03/95 12/29/94 101/03/95
101/06/95
101/06/95 OFFICE EELB/DE E C:EELB/DE
CB:DOPS ] C: ECUQP I D:DOPSl NAME SMitra* CBerlinger*
RKiesel AChatff-W
BKGrimesa-
- DATE 09/22/94 l 10/26/94 03/ E 95 1/J& 03/ /95 OFFICIAL RECORD COPY
IN 95-XX January 3, 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: Tirupataiah
Tella, Region III (708) 829-9749 Rogelio Mendez, Region III (708) 829-9745 Sikhindra
K. Mitra, NRR (301) 504-2783 Stephen D. Alexander, NRR (301) 504-2995 Attachment:
List of Recently Issued NRC Information
Notices* See EGGreenman
memorandum
to RLDennig dated June and previous concurrence
pages.DOCUMENT NAME: BKRGRSE.SDA
-- T -oa .&I .o xt-* l..At i., *ih. icy- ACEn CW withnoat Ancdloures
'F" 15, 1994' CoDY with enclosures
N -No copv o rU euvcive U cU Ps eB cge -Age. P --* -I-OFFICE Region III E Region III E Region III E Re ion III E ECB:DOPS NAME TTella* RMendez* GGrant* EGGreenman*
RKiesel DATE 09/07/94 06/10/94 06/10/94 06/13/94 01/ /95 OFFICE SIB/DOTS E TECH ED DTN SC;§IRDOTS
I Do:DOT§fIIRI
NAME SAlexander
v BCalure* Gftf i a R sard DATE 101/5/95 12/29/94 01/3 /95 6 '01/t' 95 OFFICE JEELB/DE I E C:EELB/DE
l Jj/RR C:ECB/DOPS
lI l D: NAME ISMitra CBerlinger
BWSheron AChaffee BKGrimes DATE J01/ /95 01/ /95 01/ /95 01/ /95 01/ /95 OFFICIAL RECORD COPY
IN 94-XX December 28, 1994 This informati
notice requires no specific action or written response.
If you have any que ions about the information
in this notice, please contact one of the technica contacts listed below or the appropriate
Office of Nuclear Reactor Regu tion (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contact(s):
Tirupataiah
Tell Region III (708) 829-9749 Rogelio Mendez, Region II (708) 829-9745 Sikhindra
K. Mitra, NRR (301) 504-2703 Stephen D. Alexander, NRR (301) 504-2995 Attachments:
1. List of Recently Issued NRC Information
Notices* See EGGreenman
memorandum
to RLDennig dated June 15, 1994 and previous concurrence
pages.DOCUMFNT NAME! BKRGRSE.SDA
T7 --Ih. M-U M this .kndoummAnt- kIdiintm In the hox: 'C -CoDv without enclosures
WE'-Copy with enclosures
END -No copy OFFICE Region III E [Recion III I E lRegion III I E Reio III E j NAME TTella* RMendez* IGGrant* EGGreenman*
DATE 09/07/94 06/10/94 106/10/94
106/13/94 OFFICE OGCB NRR E ED [ EELB/NRR E C:ECB/DOPS
_DOPS NAME RKiesel* A , SMitra* CBerlinger*
BKGrimes DATE 09/07/94 12/A0/94 09/22/94 10/26/94 12/ /94 OFFICE D:DE/NRR E C:SIB/DOTS
I D/DOTS I l C:ECB/DOPS
D:DOPS NAME BWSheron*
RGallo RLSpessard
1 AChaffee BKGrimes DATE 11/01/94 12/ /94 12/ /94 112/ /94 12/ /94 OFFICIAL RECORD COPY
IN 94-XX December 28, 1994 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contact(s):
Tirupataiah
Tella, Region III (708) 829-9749 Rogelio Mendez, Region III (708) 829-9745 Sikhindra
K. Mltra, NRR (301) 504-2703 Stephen D. Alexander, NRR (301) 504-2995 Attachments:
1. List of Recently Issued NRC Information
Notices* See EGGreenman
memorandum
to RLDennig dated June and previous concurrence
pages. DOCUMENT NAME: As h .-4 dfj *A.-m'n Un thA hnV o C' -COnY without enclosures
'EW 15, 1994 NRCIN.471-CoDy with enclosures
'N' = No copy OFFICE *Region III *Region III *Region III *Region III NAME TTella RMendez GEGrant EGGreenman
DATE 9/ 7/94 6/10/94 6/10/94 6/13/94 OFFICE *OGCB/NRR
I*C:EELB/NRR
NAME RJKiessel
JMain JM SKMitra CHBerlinger
DATE 9/ 7/94 9/12/94 9/22/94 10/26/94*D:DE/NRR
C:RVIIB/NRR
D:DOTS/NRR
C:OECB/NRR
D:DOPS/NRR
BWSheron RGallo RLSpessard
AEChaffee
BKGrimes 11/01/94 12/ /94 12/ /94 12/ /94 12/OFFICIAL RECORD COPY
IN 94-xx October xx, 1994 In doing post maintenance
testing, the licensees
did not find evidence of impending
breaker failures because the tests were done mainly to determine whether the breaker tripped or closed.Related Generic Communications
Although involving
a different
type of circuit breaker, NRC IN 93-26, "Grease Solidification
Causes Molded-Ca'e
Circuit Breaker Failure to Close," issued April 7, 1993, and its supplement
ssued January 31, 1994, described
a similar problem with grease solidification.
This information
notice requires no spe fic action or written response.
If you have any questions
about the informat n in this notice, please contact one of the technical
contacts listed below the appropriate
Office of Nuclear Reactor Regulation (NRR) project mana r.Brian K. Grim , Director Division of Ope0ating
Reactor Support Office of Nuclea Reactor Regulation
Technical
contact(s):
Tirupataiah
Tella, Region III (708) 829-9749 Rogelio Mendez, Region III (708) 829-9745 Sikhindra
K. Mitra, NRR (301) 504-2703 Attachments:
1. List of Recently Issued NRC Information
Notices* see EGGreenman
memorandum
to RLDennig dated June 15, 1994 and Drevious concurrence
pages I OFFICE *Region III *Region III *Region III *Region III NAME TTella RMendez GEGrant EGGreenman
DATE 9/ 7/94 6/10/94 6/10/94 6/13/94 OFFICE *OGCB/NRR
NAME RJKiessel
JMain JM SKMitra CHBerlinger
DATE 9/ 7/94 9/12/94 9/22/94 10/26/94*D:DE/NRR
C:RVIB/NRR
D:DOTS/NRR
C:OECB/NRR
D:DOPS/NRR
BWSheron RGalloj RLSpessard
AEChaffee
BKGrimes 11/01/94 11/ /94 11/ /94 11/ /94 11/ /94 DOCUMENT NAME: NRCIN.471 I.IN 94-xx October xx, 1994 In doing post maintenance
testing, the licensees
did not find evidence of impending
breaker failures because the tests were done mainly to determine whether the breaker trfpped or closed.Related Generic Communica'tions
Although involving
a different
type of circuit breaker, NRC IN 93-26, *Grease Solidification
Causes Molded-Ca
Circuit Breaker Failure to Close," issued April 7, 1993, and its supplement
issued January 31, 1994, described
a similar problem with grease solidification.
This information
notice requires no s cific action or written response.
If you have any questions
about the informa ion In this notice, please contact one of the technical
contacts listed belo or the appropriate
Office of Nuclear Reactor Regulation (NRR) project ma ager.Brian K. G mes, Director Division of erating Reactor Support Office of Nuc ar Reactor Regulation
Technical
contact(s):
Tirupataiah
Tella, Region III (708) 829-9749 Rogelio Mendez, Region III (708) 829-9745 Sikhindra
K. Mitra, NRR (301) 504-2703 Attachments:
1. List of Recently Issued NRC Information
Notices* see EGGreenman
memorandum
to RLDennig dated June 15, 1994 and previous concurrence
pages a_ _ _ _ _ _ _ L _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _OFFICE *Region III *Region III *Region III *Region III NAME TTella IRMendez GEGrant EGGreenman
DATE 9/ 7/94 6/10/94 6/10/94 6/13/94 OFFICE *OGCB/NRR
C gerL NAME RJKiessel
JMain JM SKMitra CH e nger DATE 9/ 7/94 l 9/12/94 9/22/94 10 /94 OFFICE p:E/NR C:OECB/NRR
l D:DOPS/NRR
NAME 7B iheron AEChaffee
BKGrimes DATE L/ I L/94 10/ /94 10/ /94 DOCUMENT NAME: NR5Ir\.471 IN 94-xx September
xx, 1994 In doing post ma tenance testing, the icensees did not find evidence of impending
breaker ilures because the were done mainly to determine
whether the breaker tripped closed. SW, This information
notice quires no specific action or written response.
If you have any questions
abo the information
in this notice, please contact one of the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation (NR project manager.1an K. Grimes, Director tvision of Operating
Reactor Support tkce of Nuclear Reactor Regulation
Technical
contact(s):
Tirupataiah
Tella, Rgion III (708) 829-9749 \Rogelio Mendez, Region Ilk (708) 829-9745 \Sikhindra
K. Mitra, NRR (301) 504-2703 Attachments:
1. List of Recently Issued NRC Information
Notices* see EGGreenman
memorandum
to RLDennig and Drevious concurrence
nBaan dated June 15, 1994 OFFICE J
- II *Region III *Region III *Region III NAME TTella RMendez GEGrant EGGreenman
I DATE I 9/ 7/94 6/10/94 6/10/94 1 6/13/94 .= I I__OFFICE*OGCB/NRR*Tarh Fkl cro i nonnD r_ .err n. Al-n0 I I. L.LL.U/ I CLDt% l LLLVIflKKDit21kih
f i ________________
NAME RJKlessel JMalin OM qrIMi t"M ML&ruD^-1 ----_AME RI esse_ _n JM,- -- uVrMI ILnge DATE 9/ 7/94 9/12/94 9/2_t194 9/ /94 OFFICE D:DE/NRR C:OGCB/NRR
[ D:DORS/NRR
NAME BWSheron ELDoolittle
BKGrimes _DATE I 9/ /94 9/ /94 I_9_ _ 94_ _)FOCUMFNT
M AMFP N JDJrT A71 11.-. , w -8u .III%% AM .'T 1 1
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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)
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