Cracked Insulators in Asl Dry Type Transformers Manufactured by Westinghouse Electric CorporationML031200032 |
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: |
08/26/1992 |
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From: |
Rossi C Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-92-063, NUDOCS 9208200177 |
Download: ML031200032 (5) |
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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>. |
lv
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 August 26, 1992 NRC INFORMATION NOTICE 92-63: CRACKED INSULATORS IN ASL DRY TYPE
TRANSFORMERS MANUFACTURED BY: WESTINGHOUSE I
ELECTRIC CORPORATION
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 the cracking of
ceramic insulators on ASL Dry Type Power Center 4160/480 volt (V) 3-phase
transformers manufactured by the Westinghouse Electric Corporation
(Westinghouse). It is expected that recipients will review the information
for applicability to their facilities and consider actions, as appropriate, to
avoid similar problems. However, suggestions contained in this information
notice are not NRC requirements; therefore, no specific action or written
response is required.
Description of Circumstances
On May 13, 1991, the Washington Public Power Supply System (WPPSS), the
construction permit holder for the Washington Nuclear Project, Unit 3, (WNP-3)
reported to the NRC that cracks were observed on ceramic insulators that
support the high voltage coils in certain Class 1E and Non-Class 1E 4160/480 V
transformers rated at 1000 and 1500 kVA.
The Pacific Gas and Electric Company (PG&E), the licensee for the Diablo
Canyon Nuclear Power Plant, Units 1 and 2,-found a hairline crack on an
insulator in one of the 4160/480V, 1000 KVA rated transformers in Unit 2. In
a letter of August 30, 1991, Westinghouse, the supplier of the transformer, recommended that PG&E replace the cracked insulator as soon as possible. On
September 19, 1991, PG&E evaluated the operability to justify continued
operation with the hairline crack on one of its insulators.
Discussion
The design of these transformers typically'-includes a magnetic.iron core, three high voltage coil assemblies and a steel frame.' The high voltage coil
assemblies are held in position and are electrically separated from the ground
plane of the transformer by a set of insulators uniformly spaced around the
top and bottom periphery of each coil assembly. In turn, the insulators are
9208200177 AtE
o- // C- It Icc
IN 92-63 August 26, 1992 held in place by pressure rings. A compressive force is applied to the top of
each pressure ring by four jack bolts. The assembly is designed to maintain
the spatial relationship of the coils, insulators, and the pressure ring
during normal operation, a seismic event, or an electrical fault condition.
The 1000 kVA transformer has six insulators at the top and bottom of each high
voltage coil assembly while the 1500 kVA transformer has eight. The
insulators are 4 3/8 inches long and 1 inch in diameter. The center portion
of each insulator has a series of annular indentations that form five rings or
skirts. Typically, the cracks were found in these indentations.
At WNP-3, both the WPPSS and NRC staff observed that some of the cracked
insulators in the affected transformers were installed off-center and were not
perpendicular to the pressure ring. The cracks were on insulators located at
the top or bottom of the high voltage coils and at least one hairline crack
was observed along the smallest cross section in the upper half of each
affected insulator.
On November 14, 1991, Westinghouse informed the NRC (Attachment 1) that it had
sent a customer notification letter to all utilities that may have received
Westinghouse safety-related ASL Dry Type transformers. Westinghouse stated
that it had received information from the ABB Power Transmission and
Distribution Company, Incorporated, that the cracking of the insulators could
have a catastrophic effect on the structural integrity of the transformer.
This information notice requires no specific action or written response. If
you have any questions about the information in this-notice, please contact
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
~Kha'rs` CE.Rossi, Directof
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contact: K. R. Naidu, NRR
(301) 504-2980
Attachments:
1. Westinghouse, letter ET-NRC-91-3638
2. List of Recently Issued NRC Information Notices
a ; A , - - . t. ..............................................................
. ,
Attachment 1 IN 92-63 August 26, 1992 -Nuclear and Alvancea
Westinghouse Energy Systems Tennciogy Division
Electric Corporation Box vii
B0x s3 *.
3ttsturgn Pennsylvania 1523C 3i:
ET-NRC-9 1-3638 November 14, 1991 Doc=en~t Contro! Desk
US Nuclear Regulatory Commission
Washington, DC 20555 Attention: Dr. Thomas E. Murley, Director
Office of Nuclear Reactor Regulation
Dear Dr. Murley:
Attached is a generic version of the customer notification letter, issued by Westinghouse to all utilities, both domestic and international which may have been supplied with safety related ASL Dry Tpe
Transformers. This letter was prepared to document Westinghouse's evaluation, of the ASL Dry Type
Transformer issue, pursuant to the requirements of 1OCFR Part 21.
S. R. Tritch, Manager
Engineering Technology Department
LRH/sa
Attachment
cc: ABB Power T&D Company Inc.
651 Holiday Drive
Pittsburgh, PA 15220
Attn: P. J. Pillitteri, Field Service Manager Integrated Logistics Support
LrrfuwkEr.NzsC4-3632 F ElR AlDOCK 0301)0397
Attachment 1 IN 92-63 August 26, 1992 --
Subject: Westinghouse ASL Dry Type Transformers
To: Utility
On June 10, 199i the Washington Public Power Supply System (WPPSS)
notified the NRC of a potential deficiency regarding ASL Power Center Dry
Type Transformers. In September 1987, an insulator that supports the
C-phase coil of a Westinghouse supplied dry type air ventilated 2000KVA
Non Class IE transformer was discovered to be cracked at WNP-3. In
January 1990, three additional cracked insulators were discovered in
another Non Class IE transformer purchased under the same contract.
Due to the above, WNP-3 engineering personnel inspected the plant's six
Class IE power center transformers purchased under the same contract.
These transformers, which have not yet been energized, were inspected in
November 1990. This inspection revealed cracked insulators in two of the
six transformers.
Westinghouse sold the.transformer product lines, including the ASL Dry
Type Power Center Transformers, to ABB Power Transmission and Distribution
Company Inc. Consequently, Westinghouse does not have the necessary
technical information or expertise available to identify all of the
potentially affected plants, the cause, nor the ultimate solution.
Westinghouse has been informed by ABB that the cracking of the insulators
could have catastrophic effect on the structural integrity of the
transformer. If your plant was supplied or utilizes the ASL Power Center
Dry TyDe Transformer, Westinghouse recommends that you pursue this matter
directly with ABB. Westinghouse has provided a copy of this generic
notification to ABB and the NRC and has concluded its evaluation of this
issue pursuant to the requirements of 1OCFR Part 21.
Project Manager
/sa
- -S
Attachment 2 IN 92-63 August 26, 1992 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
92-62 Emergency Response 08/24/92 All U.S. Nuclear Regulatory
Information Require- Commission licensees.
ments for Radioactive
Material Shipments
92-61 Loss of High Head 08/20/92 All holders of OLs or CPs
Safety Injection for nuclear power reactors.
92-60 Valve Stem Failure 08/20/92 All holders of OLs or CPs
Caused by Embrittlement for pressurized water
reactors (PWRs).
92-59 Horizontally-Installed 08/18/92 All holders of OLs or CPs
Motor-Operated Gate for nuclear power reactors.
Valves
-58 Uranium Hexafluoride 08/12/92 All Fuel Cycle Licensees.
Cylinders - Deviations
in Coupling Welds
92-57 Radial Cracking of 08/11/92 All holders of OLs or CPs
Shroud Support Access for boiling water reactors
Hole Cover Welds (BWRs).
92-56 Counterfeit Valves in 08/06/92 All holders of OLs or CPs
the Commercial Grade for nuclear power reactors.
Supply System
92-55 Current Fire Endurance 07/27/92 All holders of OLs or CPs
Test Results for for nuclear power reactors.
Thermo-Lag Fire Barrier
Material
92-54 Level Instrumentation 07/24/92 All holders of OLs or CPs
Inaccuracies Caused by for nuclear power reactors.
Rapid Depressurization
92-53 Potential Failure of 07/29/92 All holders of OLs or CPs
Emergency Diesel Gen- for nuclear power reactors.
erators due to Ex- cessive Rate of Loading
OL = Operating License
CP = Construction Permit
|
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|
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- Information Notice 1992-06, Reliability of ATWS Mitigation System and Other NRC Required Equipment Not Controlled by Plant Technical Specifications (15 January 1992)
- Information Notice 1992-06, Reliability of ATWS Mitigation System and Other NRC Required Equipment not Controlled by Plant Technical Specifications (15 January 1992)
- Information Notice 1992-07, Rapid Flow-induced Erosion/Corrosion of Feedwater Piping (9 January 1992)
- Information Notice 1992-08, Revised Protective Action Guidance for Nuclear Incidents (23 January 1992)
- Information Notice 1992-09, Overloading and Subsequent Lock Out of Electrical Buses During Accident Conditions (30 January 1992)
- Information Notice 1992-10, Brachytherapy Incidents Involving Iridium-192 Wire Used in Endobronchial Treatments (31 January 1992, Topic: Brachytherapy)
- Information Notice 1992-10, Brachytherapy Incidents Involving Iridium-192 Wire used in Endobronchial Treatments (31 January 1992, Topic: Brachytherapy)
- Information Notice 1992-11, Soil and Water Contamination at Fuel Cycle Facilities (5 February 1992, Topic: Brachytherapy)
- Information Notice 1992-12, Effects of Cable Leakage Currents on Instrument Settings and Indications (10 February 1992, Topic: Brachytherapy)
- Information Notice 1992-13, Inadequate Control Over Vehicular Traffic at Nuclear Power Plant Sites (18 February 1992, Topic: Brachytherapy)
- Information Notice 1992-14, Uranium Oxide Fires at Fuel Cycle Facilities (21 February 1992, Topic: Brachytherapy)
- Information Notice 1992-15, Failure of Primary Systems Compression Fitting (24 February 1992)
- Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown (25 February 1992, Topic: Reactor Vessel Water Level, Temporary Modification, Brachytherapy)
- Information Notice 1992-17, NRC Inspections of Programs Being Developed at Nuclear Power Plants in Response to Generic Letter 89-10 (26 February 1992, Topic: Stroke time)
- Information Notice 1992-18, Potential for Loss of Remote Shutdown Capability During a Control Room Fire (28 February 1992, Topic: Hot Short, Safe Shutdown)
- Information Notice 1992-19, Misapplication of Potter and Brumfield Mdr Rotary Relays (2 March 1992)
- Information Notice 1992-19, Misapplication of Potter and Brumfield MDR Rotary Relays (2 March 1992)
- Information Notice 1992-20, Inadequate Local Leak Rate Testing (3 March 1992)
- Information Notice 1992-21, Spent Fuel Pool Reactivity Calculations (24 March 1992)
- Information Notice 1992-23, Results of Validation Testing of Motor-Operated Valve Diagnostic Equipment (27 March 1992)
- Information Notice 1992-24, Distributor Modification to Certain Commercial-Grade Agastat Electrical Relays (30 March 1992)
- Information Notice 1992-25, Pressure Locking of Motor-Operated Flexible Wedge Gate Valves (2 April 1992, Topic: Stroke time, Hydrostatic)
- Information Notice 1992-27, Thermally Induced Accelerated Aging and Failure of ITE/Gould A.C. Relays used in Safety-Related Applications (3 April 1992)
- Information Notice 1992-27, Thermally Induced Accelerated Aging and Failure of Ite/Gould A.C. Relays Used in Safety-Related Applications (3 April 1992)
- Information Notice 1992-28, Inadequate Fire Suppression System Testing (8 April 1992, Topic: Safe Shutdown)
- Information Notice 1992-29, Potential Breaker Miscoordination Caused by Instantaneous Trip Circuitry (17 April 1992)
- Information Notice 1992-30, Falsification of Plant Records (23 April 1992)
- Information Notice 1992-31, Electrical Connection Problem in Johnson Yokogawa Corporation YS-80 Programmable Indicating Controllers (27 April 1992)
- Information Notice 1992-32, Problems Identified with Emergency Ventilation Systems for Near-Site (Within 10 Miles) Emergency Operations Facilities and Technical Support Centers (29 April 1992)
- Information Notice 1992-32, Problems Identified with Emergency Ventilation Systems for Near-Site (within 10 Miles) Emergency Operations Facilities and Technical Support Centers (29 April 1992)
- Information Notice 1992-33, Increased Instrument Response Time When Pressure Dampening Devices Are Installed (30 April 1992)
- Information Notice 1992-33, Increased Instrument Response Time When Pressure Dampening Devices are Installed (30 April 1992)
- Information Notice 1992-34, New Exposure Limits for Airborne Uranium and Thorium (6 May 1992)
- Information Notice 1992-35, Higher than Predicted Erosion/Corrosion in Unisolable Reactor Coolant Pressure Boundary Piping Inside Containment at a Boiling Water Reactor (6 May 1992)
- Information Notice 1992-35, Higher than Predicted Erosion/Corrosion in Unisolable Reactor Coolant Pressure Boundary Piping inside Containment at a Boiling Water Reactor (6 May 1992)
- Information Notice 1992-36, Intersystem LOCA Outside Containment (7 May 1992)
- Information Notice 1992-37, Implementation of the Deliberate Misconduct Rule (8 May 1992)
- Information Notice 1992-38, Implementation Date for the Revision to the EPA Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (26 May 1992, Topic: Brachytherapy)
- Information Notice 1992-39, Unplanned Return to Criticality During Reactor Shutdown (13 May 1992, Topic: Fuel cladding)
- Information Notice 1992-40, Inadequate Testing of Emergency Bus Undervoltage Logic Circuitry (27 May 1992)
- Information Notice 1992-41, Consideration of Stem Rejection Load In Calculation of Required Valve Thrust (29 May 1992, Topic: Anchor Darling)
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