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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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 ŽW
"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 Unexpected Degradation 04/20/95 All holders of OLs or CPs
of Lead Storage Batteries for nuclear power reactors.
94-64, Reactivity Insertion 04/06/95 All holders of OLs or CPs
Supp. 1 Transient and Accident for nuclear power reactors
Limits for High Burnup
Fuel
95-18, Potential Pressure-Locking 03/31/95 All holders of OLs or CPs
Supp. 1 of Safety-Related Power- for nuclear power reactors.
Operated Gate Valves
95-20 Failures in Rosemount 03/22/95 All holders of OLs or CPs
Pressure Transmitters for nuclear power reactors.
due to Hydrogen Per- meation into the Sensor
Cell
95-19 Failure of Reactor Trip 03/22/95 All holders of OLs or CPs
Breaker to Open Because for nuclear power reactors.
of Cutoff Switch Material
Lodged in the Trip Latch
Mechanism
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 for boiling water reactors.
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.
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 15, 1994 and previous concurrence pages.
DOCUMENT NAME: 95-22.IN
TO- ,-.IV - ---- at thL A....t I*.Alt. In tkhe bnx: 'C -CODY without enclosures "E" - CoDy with enclosures ENS = No copy
[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 EE 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 LD-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 ID:DOPSl
NAME SMitra* CBerlinger* RKiesel AChatff-W BKGrimesa-
- DATE 09/22/94 l 10/26/94 03/ 95 E 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 15, 1994 and previous concurrence pages.
DOCUMENT NAME: BKRGRSE.SDA
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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 SC;§IRDOTS DTN I Do:DOT§fIIRI
NAME SAlexander v BCalure* Gftfi 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 kIdiintm In
M this .kndoummAnt- 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
1 AChaffee BKGrimes
NAME BWSheron* RGallo RLSpessard
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 15, 1994 and previous concurrence pages. DOCUMENT NAME: NRCIN.471 As h *A.-m'n -4. dfj Un o
thA hnV C' - COnY without enclosures 'EW - 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 *Tech Ed *EELB/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 *Tech Ed *EELB/NRR *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: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 *Tech Ed *EELB/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 7Biheron 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.
you have any questions abo the information in this notice, please contactIf
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 dated June 15, 1994 and Drevious concurrence nBaan
OFFICE J* II
I
- Region III *Region III *Region III
NAME TTella RMendez GEGrant EGGreenman
DATE I 9/ 7/94 6/10/94 6/10/94 1 6/13/94 .
= I I__
OFFICE I
- OGCB/NRR *Tarh Fkl cro i nonnD
I
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________________
NAME RJKlessel
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JM,- qrIMi t"M ML&ILnge uVrMI - ---
-- ruD^-1 DATE 9/ 7/94 9/12/94 9/2_t194 9/ /94 OFFICE
NAME
D:DE/NRR
BWSheron
C:OGCB/NRR [ D:DORS/NRR
ELDoolittle BKGrimes _
DATE I 9/ /94 9/ /94 94_ _ _ I_9_
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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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