Systems Interaction Event Resulting in Reactor System Safety Relief Valve Opening Following a Fire-Protection Deluge System MalfunctionML031180210 |
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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill |
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Issue date: |
10/31/1985 |
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From: |
Jordan E NRC/IE |
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To: |
|
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References |
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IN-85-085, NUDOCS 8510290039 |
Download: ML031180210 (4) |
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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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill |
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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 [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] </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 [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] </code>. |
SSINS No.: 6835 IN 85-85 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C. 20555 October 31, 1985 IE INFORMATION NOTICE 85-85: SYSTEMS INTERACTION EVENT RESULTING IN REACTOR
SYSTEM SAFETY RELIEF VALVE OPENING FOLLOWING
A FIRE-PROTECTION DELUGE SYSTEM MALFUNCTION
Addressees
All nuclear power reactor facilities holding an operating license (OL) or a
construction permit (CP).
Purpose
This notice is provided to alert licensees of a serious systems interaction
event involving the fire-protection deluge system located in the control room
ventilation charcoal filter housing. Following inadvertent actuation of this
system, an analog transient trip system (ATTS) panel was sprayed with water
causing malfunctions in certain safety system components.
It is expected that recipients will review this notice 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 requirements; therefore, no specific action or written
response is required.
Description of Circumstances
On May 15, 1985, at Georgia Power Company's Hatch Unit 1, personnel manually
scrammed the reactor from 75% power because of a stuck open low-low-set safety
relief valve (LLS-SRV). Shorting of one of the two redundant power supplies
and/or possibly intermittent shorting of logic system contacts in the ATTS
panel is believed to have caused the stuck open LLS-SRV. The panel is one of
two redundant panels located in the control room. The cause of the electrical
shorts in the affected panel was water intrusion into the panel.
The event began about 8:35 p.m. when an instrument water supply vent valve was
damaged, apparently by dragging of a crane hook along the line. The instru- ment water supply line eventually depressurized causing a portion of the fire- protection deluge system to actuate. The water supply line is located above
the control building and the deluge system is located in the control room
charcoal filter housing.
Following actuation of the deluge system, approximately 15 to 25 gal of water
backed up into the ventilation header before the system could be secured. The
8510290039
IN 85-85 October 31, 1985 backup was caused by plugged drains in the charcoal filter housing. Water
eventually leaked through a hole in the ventilation piping that was located
above the ATTS panel in the control room. Whenthe water sprayed onto the panel, one of two redundant panel power supplies apparently shorted because of water
intrusion into the panel. As a result, a LLS-SRV valve began to cycle open and
closed. The SRV cycled three times and then opened and remained open. The
operator manually scrammed the reactor from 75% power. A false turbine high
exhaust pressure trip signal also was generated, temporarily disabling the high
pressure core injection (HPCI) system. The reactor core isolation cooling
(RCIC) system was inoperable at the time, so neither HPCI nor RCIC was imme- diately available for use. Fortunately, neither system was needed during the
event. This is because the water level was restored and maintained by the
reactor feedwater system until the MSIVs were shut. Subsequent to MSIV closure, water level was maintained by the control rod drive (CRD) system with the
excess water being dumped to the condenser via the reactor-water cleanup-system.
The LLS-SRV closed without operator action at 9:52 pm.
Discussion:
The event is of considerable concern because of the potential for multiple
safety system failures through unanalyzed systems interactions. In this event, the water from the fire-suppression deluge system in the control room caused
opening of a safety relief valve and loss of primary system inventory. The
event could have been seriously aggravated by the spurious HPCI turbine high
exhaust pressure-trip-that-wasreceived-also apparently as a result of the
water intrusion. Because the RCIC system was inoperable at-the time of the
event, no safety-related high pressure injection system'would have been imme- diately available to restore water level should that have been necessary.
The HPCI turbine trip signal was reset shortly after it occurred, however, and
the system was returned to operability.
Perhaps more serious is the potential effect the water could have had on
numerous other safety systems. The ATTS panels have permissive and arming
logic and trip, logic for various safety systems, as well as water level inputs
to the HPCI, RCIC, core spray (CS)., automatic depressurization system (ADS),
residual heat removal (RHR) system, and diesel activation logic. It is hard to
predict the anomalous behavior that could occur if both power supplies had been
lost, or if other portions of the logic had been shorted; but quite possibly, several safety systems could have malfunctioned, seriously handicapping the
operators during their efforts to stabilize the unit.
Prior to this event, no procedures were in place at Hatch Unit 1 for adequately
cleaning the ventilation plenums or drains in the charcoal filter units. Had
these procedures been prepared and implemented, the drain's would have functioned
as designed with no serious adverse effects. In response to this event, the
licensee cleaned and inspected drains in the remaining filter units and is
preparing cleanout and inspection procedures to be added to the maintenance
schedules.
IN 85-85 October 31, 1985 Another example of a design feature which could cause potential adverse system
interactions was recently found at Unit 1 of the South Texas Project. A non- seismic, non-category I potable water line> was found to pass through the control
room envelope via a relay room next to the> control room. This could subject the
solid-state protection system cabinets ancI the Westinghouse 7300 process control
system located nearby to water damage foll owing a seismic event. Although this
unit is under construction, it does point out that these problems can occur.
Also, IE Information Notice 83-41, "Actuation of Fire Suppression System
Causing Inoperability of Safety Related Equipment," was issued on June 22, 1983.
That notice identified a number of instances in which automatic actuation of
fire suppression systems degraded or jeopardized the operability of safety- related equipment.
No specific action or written response is required by this information notice.
If you have any questions regarding this matter, please contact the Regional
Administrator of the appropriate NRC regional office or the technical contact
listed below.
w4ar . Jordan, Director
Divis n of Emergency Preparedness
and Engineering Response
Office of Inspection and Enforcement
Technical Contact:
David R. Powell, IE
(301) 492-8373 Attachment: List of Recently Issued IE Information Notices
Attachment 1 IN 85-85 October 31, 1985 LIST OF RECENTLY ISSUED
IE INFORMATION NOTICES
Information Date of
Notice No. Subject Issue Issued to
85-84 Inadequate Inservice Testing 10/30/85 All power reactor
Of Main Steam Isolation Valves facilities holding
an OL or CP
85-83 Potential Failures Of General 10/30/85 All power reactor
Electric PK-2 Test Blocks facilities holding
an OL or CP
85-82 Diesel Generator Differen- 10/18/85 All power reactor
tial Protection Relay Not facilities holding
Seismically Qualified an OL or CP
85-81 Problems Resulting In 10/17/85 All power reactor
Erroneously High Reading facilities holding
With Panasonic 800 Series an OL or CP and
Thermoluminescent Dosimeters certain material
and fuel cycle
licensees
85-80 Timely Declaration Of An 10/15/85 All power reactor
Emergency Class Implemienta- facilities holding
tion Of An Emergency Plan, an OL or CP
And Emergency Notifications
85-17 Possible Sticking Of ASCO 10/1/85 All power reactor
Sup. 1 Solenoid Valves facilities holding
an OL or CP
85-79 Inadequate Communications 9/30/85 All power reactor
Between Maintenance, facilities holding
Operations, And Security an OL or CP; research
Personnel and nonpower reactor
facilities; fuel
fabrication and
processing facilities
85-78 Event Notification 9/23/85 All power reactor
facilities holding
an OL or CP
OL = Operating License
CP = Construction Permit
|
---|
|
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)
- 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)
- 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)
- 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)
- 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)
- Information Notice 1985-35, Failure of Air Check Valves To Seat (30 April 1985)
- Information Notice 1985-37, Chemical Cleaning of Steam Generators at Millstone 2 (14 May 1985)
- 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)
- 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)
- 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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