Isolation Transfer Switches and Post-Fire Shutdown Capability| ML031180654 |
| Person / Time |
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| Site: |
Beaver Valley, Millstone, Hatch, 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, 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, 05000000, 05000262, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill, Crane |
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| Issue date: |
01/31/1985 |
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| From: |
Jordan E NRC/IE |
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| To: |
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| References |
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| IN-85-009, NUDOCS 8501300138 |
| Download: ML031180654 (3) |
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Similar Documents at Beaver Valley, Millstone, Hatch, 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, 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, 05000000, 05000262, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill, Crane |
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Category:NRC Information Notice
[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 [[: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 [[: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 [[:05000000]] OR [[:05000262]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] OR [[:Crane]] </code>. |
SSINS No.: 6835 IN 85-09
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C.
20555
January 31, 1985
IE INFORMATION NOTICE NO. 85-09:
ISOLATION TRANSFER SWITCHES AND POST-FIRE
SHUTDOWN CAPABILITY
Addressees
All nuclear power reactor facilities holding an operating license (OL) or a
construction permit (CP).
Purpose
This information notice is to alert recipients of potential deficiencies in the
electrical design of isolation transfer switches installed outside the control
room at many nuclear power plants. The transfer switches provide electrical
isolation of certain shutdown circuits from the control room and other essen- tial fire areas during post-fire accident conditions. It is expected that
recipients will review the information for applicability to their facilities
and consider actions, if appropriate, to preclude a similar problem occurring
at their facilities.
However, suggestions contained in this notice do not
constitute NRC requirements; therefore, no specific action or written response
is required.
Description of Circumstances
During a recent NRC fire protection inspection at the Wolf Creek facility, it
was discovered that a fire in the control room could disable the operation of
the plant's alternate shutdown system.
Isolation transfer switches of certain
hot shutdown systems would have to be transferred to the alternate or isolated
position before fire damage occurred to the control power circuits of several
essential pumps and motor-operated valves at this facility. If the fire damage
occurred before the switchover, fuses might blow at the motor control centers
or local panels and require replacements to make the affected systems/components
operable. This situation existed because the transfer scheme depended on the
existing set of fuses in the affected circuit and did not include redundant
fuses in all of the alternate shutdown system circuits. For most of the trans- fer switches, the situation would not cause a problem because the desired
effect after isolation is the deenergization of power.
In instances where the
system/component has to be operable or where operation might be required to
override a spurious actuation of a component (such as a motor-operated valve),
replacement of fuses may have become necessary. In such cases, troubleshooting/
repair would be required to achieve or maintain hot shutdown.
8501300138
IN 85-09 January 31, 1985 Discussion:
At the Wolf Creek facility, where the concern was discovered, the transfer
switches at the remote shutdown panel had redundant fusing. The only transfer
switches identified as a concern were those at other local stations that mainly
involve support systems operability or correction of spurious operations.-The
facility is either modifying existing switches or installing new switches for
certain components so that redundant fusing will exist with a new (different)
set of fuses switched into the circuit when the switch is placed in the isolat- ed mode.
Alternate shutdown procedures also are being revised so that shutdown
could be achieved under fire conditions which result in immediate evacuation of
the control room and control room circuit damage that causes maloperation of
equipment prior to isolation outside the control room.
This situation may exist at other facilities and may involve the shutdown panel
and other local stations that are needed for alternate shutdown capability.
This could include the switches and other circuits on the alternate/remote
shutdown panel.
Operability of the hot shutdown systems, including the ability
to overcome a fire or fire suppresant induced maloperation of hot shutdown
equipment and the plant's power distribution system, must exist without re- pairs, including replacement of fuses.Section III.G.1 of Appendix R to 10 CFR
50 addresses fire protection of safe shutdown capability. Meeting this
requirement for the affected circuits will ensure that redundant fuses are part
of the transfer schemes.
_
No specific action or written response is required by this information notice.
However, if you have any questions regarding this notice, please contact the
Regional Administrator of the appropriate NRC regional office or the technical
contact listed below.
w A L
anD rector
Divisi
of Emergency Preparedness
and Engineering Response
Office of Inspection and Enforcement
Technical Contact:
W. T. LeFave, NRR
(301)492-9470
V. D. Thomas, IE
(301)492-4755 Attachment: List of Recently Issued IE Information.Notices
Attachment
IN 85-09
January 31, 1985
LIST OF RECENTLY ISSUED
IE INFORMATION NOTICES
Information
Date of
Notice No.
Subject
Issue
Issued to
85-08
85-07
85-06
Industry Experience On
Certain Materials Used In
Safety-Related Equipment
Contaminated Radiography
Source Shipments
Contamination of Breathing
Air Systems
Pipe Whip Restraints
Inadequate Management Of
Security Response Drills
1/30/85
1/29/85
1/23/85
1/23/85
1/17/85
All power reactor
facilities holding
an OL or CP
All NRC licensees
authorized to
possess industrial
radiography sources
All power reactor
facilities holding
an OL or CP
All power reactor
facilities holding
an OL or CP
85-05
85-04
85-03 Separation Of Primary Reactor 1/15/85
Coolant Pump Shaft And
Impeller
All power reactor
facilities ,holding
an OL or CP, & fuel
fabrication & pro- cessing facilities
All pressurized water
power reactor
facilities holding an
OL or CP
All power reactor
facilities holding
an OL or CP
All material licensees
possessing irradiators
that are not self- shielded and contain
more than 10,000
curies of radioactive
material
85-02
Improper Installation And
Testing Of Differential
Pressure Transmitters
Continuous Supervision Of
Irradiators
1/15/85
1/10/85
85-01 OL = Operating License
CP = Construction Permit
|
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|
| list | - Information Notice 1985-01, Continuous Supervision of Irradiators (10 January 1985)
- Information Notice 1985-02, Improper Installation and Testing of Differential Pressure Transmitters (11 January 1985)
- Information Notice 1985-03, Separation of Primary Reactor Coolant Pump Shaft and Impeller (15 January 1985)
- Information Notice 1985-04, Inadequate Management of Security Response Drills (17 January 1985)
- Information Notice 1985-05, Pipe Whip Restraints (23 January 1985)
- Information Notice 1985-06, Contamination of Breathing Air Systems (23 January 1985, Topic: Spent fuel rack)
- Information Notice 1985-07, Contaminated Radiography Source Shipments (29 January 1985)
- Information Notice 1985-08, Industry Experience on Certain Materials Used in Safety-Related Equipment (30 January 1985)
- Information Notice 1985-09, Isolation Transfer Switches and Post-Fire Shutdown Capability (31 January 1985, Topic: Safe Shutdown)
- Information Notice 1985-10, Posttensioned Containment Tendon Anchor Head Failure (6 February 1985, Topic: Stress corrosion cracking)
- Information Notice 1985-11, Licensee Programs for Inspection of Electrical Raceway and Cable Installations (11 February 1985)
- Information Notice 1985-12, Recent Fuel Handling Events (11 February 1985, Topic: Eddy Current Testing)
- Information Notice 1985-13, Consequences of Using Soluble Dams (21 February 1985, Topic: Hydrostatic)
- Information Notice 1985-14, Failure of a Heavy Control Rod (B4C) Drive Assembly to Insert on a Trip Signal (22 February 1985)
- Information Notice 1985-15, Nonconforming Structural Steel for Safety-Related Use (22 February 1985)
- Information Notice 1985-16, Time/Current Trip Curve Discrepancy of ITE/Siemens-Allis Molded Case Circuit Breaker (27 February 1985)
- Information Notice 1985-17, Possible Sticking of Asco Solenoid Valves (1 March 1985)
- Information Notice 1985-18, Failures of Undervoltage Output Circuit Boards in the Westinghouse-Designed Sold State Protection System (7 March 1985)
- Information Notice 1985-19, Alleged Falsification of Certifications and Alteration of Markings on Piping, Valves, and Fittings (11 March 1985)
- Information Notice 1985-20, Motor-Operated Valve Failures Due to Hampering Effect (12 March 1985)
- Information Notice 1985-21, Main Steam Isolation Valve Closure Logic (18 March 1985)
- Information Notice 1985-22, Failure of Limitorque Motor-Operated Valves Resulting from Incorrect Installation of Pinion Gear (21 March 1985)
- Information Notice 1985-23, Inadequate Surveillance and Postmaintenance and Postmodification System Testing (22 March 1985)
- Information Notice 1985-24, Failures of Protective Coatings in Pipes and Heat Exchangers (26 March 1985, Topic: Ultimate heat sink, Coatings)
- Information Notice 1985-25, Consideration of Thermal Conditions in the Design and Installation of Supports for Diesel Generator Exhaust Silencers (2 April 1985, Topic: Coatings)
- Information Notice 1985-26, Vacuum Relief System for Boiling Water Reactor Mark I and Mark II Containments (2 April 1985, Topic: Coatings)
- Information Notice 1985-27, Notifications to the NRC Operations Center and Reporting Events in Licensee Event Reports (3 April 1985, Topic: Coatings)
- Information Notice 1985-28, Partial Loss of AC Power and Diesel Generator Degradation (9 April 1985, Topic: Coatings, Overspeed)
- Information Notice 1985-30, Microbiologically Induced Corrosion of Containment Service Water System (19 April 1985, Topic: Hydrostatic, Coatings, Biofouling)
- Information Notice 1985-31, Buildup of Enriched Uranium in Ventilation Ducts and Associated Effluent Treatment Systems (19 April 1985, Topic: Coatings)
- Information Notice 1985-32, Recent Engine Failures of Emergency Diesel Generators (22 April 1985, Topic: Coatings)
- Information Notice 1985-33, Undersized Nozzle-To-Shell Welded Joints in Tanks and Heat Exchangers Constructed Under the Rules of the ASME Boiler and Pressure Vessel Code (22 April 1985)
- Information Notice 1985-34, Heat Tracing Contributes to Corrosion Failure of Stainless Steel Piping (30 April 1985, Topic: Hydrostatic)
- Information Notice 1985-35, Failure of Air Check Valves to Seat (30 April 1985, Topic: Loss of Offsite Power)
- Information Notice 1985-35, Failure of Air Check Valves To Seat (30 April 1985, Topic: Loss of Offsite Power)
- Information Notice 1985-37, Chemical Cleaning of Steam Generators at Millstone 2 (14 May 1985, Topic: Feedwater Heater, Eddy Current Testing)
- Information Notice 1985-38, Loose Parts Obstruct Control Rod Drive Mechanism (21 May 1985)
- Information Notice 1985-39, Auditability of Electrical Equipment Qualification Records at Licensees Facilities (22 May 1985)
- Information Notice 1985-40, Deficiencies in Equipment Qualification Testing and Certification Process (22 May 1985)
- Information Notice 1985-43, Radiography Events at Power Reactors (30 May 1985, Topic: High Radiation Area, Scaffolding)
- Information Notice 1985-44, Emergency Communication System Monthly Test (30 May 1985, Topic: Health Physics Network)
- Information Notice 1985-46, Clarification of Several Aspects of Removable Radioactive Surface Contamination Limits for Transport Packages (10 June 1985)
- Information Notice 1985-47, Potential Effect of Line-Induced Vibration on Certain Target Rock Solenoid-Operated Valves (18 June 1985)
- Information Notice 1985-48, Respirator Users Notice: Defective Self Contained Breathing Apparatus Air Cylinders (19 June 1985, Topic: Hydrostatic)
- Information Notice 1985-49, Relay Calibration Problem (1 July 1985)
- Information Notice 1985-50, Complete Loss of Main and Auxiliary Feedwater at a PWR Designed by Babcock & Wilcox (8 July 1985, Topic: Overspeed trip, Overspeed)
- Information Notice 1985-51, Inadvertent Loss or Improper Actuation of Safety-Related Equipment (10 July 1985)
- Information Notice 1985-52, Errors in Dose Assessment Computer Codes and Reporting Requirements Under 10 CFR Part 21 (10 July 1985, Topic: Basic Component)
- Information Notice 1985-53, Performance of NRC-Licensed Individuals While on Duty (12 July 1985)
- Information Notice 1985-54, Teletherapy Unit Malfunction (15 July 1985)
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