Improper Electrical Grounding Results in Simultaneous Fires in the Control Room and the Safe-Shutdown Equipment RoomML031050393 |
Person / Time |
---|
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 |
---|
Issue date: |
01/08/1997 |
---|
From: |
Martin T Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
References |
---|
IN-97-001, NUDOCS 9701030090 |
Download: ML031050393 (10) |
|
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 |
---|
Category:NRC Information Notice
MONTHYEARInformation Notice 2020-02, Flex Diesel Generator Operational Challenges2020-09-15015 September 2020 Flex Diesel Generator Operational Challenges ML20225A0322020-09-0303 September 2020 NRC Choice Letter to NAC International with Attached Safety Inspection Report, IR 0721015/2020201, February 24-27, 2020 and July 22, 2020, Inspection of NAC International in Norcross, Georgia Information Notice 2012-09, PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs.2019-11-30030 November 2019 PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs. Information Notice 2011-20, NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011)2019-07-24024 July 2019 NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011) ML19196A2452019-07-15015 July 2019 Public Notice - Sequoyah Nuclear Plant, Unit 2 - Exigent Amendment to Facility Operating License Information Notice 2019-01, Inadequate Evaluation of Temporary Alterations2019-03-12012 March 2019 Inadequate Evaluation of Temporary Alterations ML16028A3082016-04-27027 April 2016 NRC Information Notice; IN 2016-05: Operating Experience Regarding Complications From a Loss of Instrumentation Air Information Notice 2015-05, Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps Information Notice 2015-05, Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps Information Notice 2013-20, OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-20, Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-11, OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2013-11, Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Contain2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Con2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notic2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2012-13, Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool Information Notice 2012-13, Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool Information Notice 2012-11, Age Related Capacitor Degradation2012-07-23023 July 2012 Age Related Capacitor Degradation ML12031A0132012-02-0606 February 2012 U.S. Nuclear Regulatory Commission Investigation Report No. 2-2010-058, Cpn International, Inc Information Notice 2011-19, Licensee Event Reports Containing Information Pertaining to Defects to Basic Components2011-09-26026 September 2011 Licensee Event Reports Containing Information Pertaining to Defects to Basic Components Information Notice 2011-15, Steel Containment Degradation and Associated License Renewal Aging Management Issues2011-08-0101 August 2011 Steel Containment Degradation and Associated License Renewal Aging Management Issues Information Notice 2011-17, Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping2011-07-26026 July 2011 Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping Information Notice 2011-13, Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-13, Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13)2011-06-29029 June 2011 Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13) Information Notice 2011-13, OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-04, IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-262010-12-21021 December 2010 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 ML13066A1872009-12-16016 December 2009 Draft NRC Information Notice 2009-xx - Underestimate of Dam Failure Frequency Used in Probabilistic Risk Assessments ML1007804482009-11-23023 November 2009 Email from Peter Bamford, NRR to Pamela Cowan, Exelon on TMI Contamination Control Event Information Notice 2009-11, NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-112009-07-0707 July 2009 NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-11 Information Notice 2009-10, Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10)2009-07-0707 July 2009 Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10) Information Notice 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify2009-06-19019 June 2009 Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify Information Notice 2008-12, Reactor Trip Due to Off-Site Power Fluctuation2008-07-0707 July 2008 Reactor Trip Due to Off-Site Power Fluctuation Information Notice 2008-11, Service Water System Degradation at Brunswicksteam Electric Plant Unit 12008-06-18018 June 2008 Service Water System Degradation at Brunswicksteam Electric Plant Unit 1 Information Notice 2008-04, Counterfeit Parts Supplied to Nuclear Power Plants2008-04-0707 April 2008 Counterfeit Parts Supplied to Nuclear Power Plants Information Notice 1991-09, Counterfeiting of Crane Valves2007-09-25025 September 2007 Counterfeiting of Crane Valves Information Notice 2007-28, Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls2007-09-19019 September 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls Information Notice 2007-29, Temporary Scaffolding Affects Operability of Safety-Related Equipment2007-09-17017 September 2007 Temporary Scaffolding Affects Operability of Safety-Related Equipment Information Notice 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station2007-03-30030 March 2007 Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station Information Notice 2007-06, Potential Common Cause Vulnerabilities in Essential Service Water Systems2007-02-0909 February 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Information Notice 2007-05, Vertical Deep Draft Pump Shaft and Coupling Failures2007-02-0909 February 2007 Vertical Deep Draft Pump Shaft and Coupling Failures Information Notice 2006-31, Inadequate Fault Interrupting Rating of Breakers2006-12-26026 December 2006 Inadequate Fault Interrupting Rating of Breakers Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear Information Notice 2006-13, E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. 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. 20555-0001
SIMULTANEOUS FIRES IN THE CONTROL ROOM
AND THE SAFE-SHUTDOWN EQUIPMENT ROOM
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 potential component grounding problems that could result in simultaneous
fires. 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
At approximately 5:00 p.m. on April 4, 1996, during a refueling outage, a licensee firewatch
detected smoke in the back panel area of the control room at the Palo Verde Nuclear
Generating Station, Unit 2. Licensee operators observed smoke emanating from the Train B
emergency lighting uninterruptible power supply (ELUPS) panel in the control room.
The fire in the control room resulted in loss of power to Train B control room emergency
lighting circuits, some general plant essential lighting and plant fire detection and alarm
system panels. Lighting powered by the unaffected Train A lighting system was sufficient to
operate the unit. The circuit breaker supplying power to the ELUPS panel tripped open when
wiring insulation in the conduit supplying the power supply panel melted and caused various
conductors to short circuit. The circuit breaker trip also deenergized power to the fire
detection and alarm panels in the auxiliary building. When operators checked the control
room fire alarm annunciator monitor, they noted that a large number of fire detector trouble
alarms were alarming and that the alarms were scrolling on the monitor screen as a result of
the deenergized fire detection and alarm panels.
The control room staff dispatched auxiliary operators to inspect their assigned areas to check I
for possible fire conditions and additional problems. An auxiliary operator discovered smoke
and fire in the Train B dc equipment room on the 100-foot level of the auxiliary building. The
fire was located in the 480/120-volt essential lighting isolation transformer. The trouble
alarms resulting from the lost power supply masked the actual fire alarm in the Train B dc
equipment room. J t-
9701030090 LA Ad pi
Ps E o48c. St .Ol r
IN 97-01 January 8, 1997 The licensee's onsite fire department responded and all fires were extinguished within a short
period of time. The licensee established the required compensatory firewatches in areas with
disabled fire detectors. Actual equipment damage was limited to the components involved in
the fires.
Discussion
The licensee's root-cause investigation indicated that the core of the regulating isolation
transformer (located in the Train B dc equipment room) failed and made contact with the
transformer coils, causing a short circuit fault to station ground through the transformer's
panel ground. The purpose of the subject transformer is to isolate nonsafety-related portions
of the circuit from the safety-related function of the circuit. The investigation also determined
that the neutral leg of the transformer had not been grounded. An alternate source of power
for the essential lighting uninterruptible power supply panel is provided by an inverter. The
system had been designed with ground connections on the neutral leg of the inverter instead
of grounding the neutral leg of the power supply (regulating transformer) in accordance with
industry practice. The neutral wiring conductors within the inverter and from the inverter to
the essential lighting distribution panel became the return fault path to the regulating
transformer. These conductors were not designed to handle the high fault currents to which
they were subjected. As a result, these wires ignited under these high fault currents. These
components are depicted in Figure 1. The licensee also determined that the fires were
related and were caused by a design error in the electrical grounding, which dated back to
plant construction. The licensee found similar grounding arrangements in the other two
Palo Verde units.
The final safety analysis report for the facility documented that grounding was accomplished
in accordance with Institute of Electrical and Electronics Engineers (IEEE)
Standard 142-1982, "Grounding of Industrial and Commercial Power Systems." The
transformer and equipment supplied by the transformer was designed as a grounded system.
IEEE 142-1982 defined a grounded system as a system of conductors in which at least one
conductor or point (usually the middle wire or neutral point of the transformer or the
generator windings) is intentionally grounded. The licensee also indicated that the grounding
design for Palo Verde was in accordance with Bechtel Drawing 13-E-ZVG-007, "Grounding
Notes, Symbols, and Details," Revision 20. The document did not require grounding of the
transformer's neutral leg.
The licensee's corrective actions included grounding the neutral leg of the isolation
transformer and fusing the output of the transformer to limit fault propagation. The licensee
also removed the ground from the control room ELUPS panel. These modifications did not
impact the isolation function of the transformer.
The event was of concern because a single electrical fault caused simultaneous fires in the
control room and the Train B dc equipment room which supports alternative post-fire safe
shutdown capability in the event of a control room fire. This electrical design error is
important because it created a fire vulnerability in two separate areas of the plant. The fire
could have resulted in operational challenges which are outside of the plant's design basis
IN 97-01 January 8, 1997 and the scope of the NRC fire protection regulations (10 CFR 50.48). This vulnerability was
caused by the inadequate design of the grounding circuitry from the electrical power supplies, which have been in service since the original construction.
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 project manager.
f Thomas T. Martin, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Chris Vandenburgh, Region IV
(817) 860-8161 E-mail: cavenrc.gov
Phil Qualls, Walnut Creek Field Office
(510) 975-0245 E-mail: pmqenrc.gov
Ronaldo Jenkins, NRR
(301) 415-2985 E-mail: rvjenrc.gov
Attachments:
1. Figure 1
2. List of Recently Issued NRC Inforation Nices
AIW J 7 tsn
Control Building Elevation 140' F 2E-QBN-D84 I Essential Ughting I
I Distribution Panel I Control Room
I 1-2/C #10 Emergency Ughts
(InConduit)
I 1-2/C #10 (InCondult)
- -
- -
-- - - 1
1213 1415s i
It- -i
_ _- _ _ _ -_= -
I I Le~I
I-f - -I
I I I I
I
I I
I I I
I
I I i
I I _ _- -
- - - - - - - - -
i
I 2E-QDN-N02 Control Room Emergency
I Routed hIcaot and tay (FO1) Lighting Uninterruptable,
2E-QBB-V02 Power Supply (
Asolation Transformer
a- --- - -
I
-1-2/C #2 I-- 4.. _
- I #8 Unit 2 Control Room Fire Event
I
_
M3217 I _
'7,
. _
Electricazl Schematic,- I-
_l
@; Ignited/&wlged by short circuit - <
ko 5 MCC 2E-PHB-M32 03
°c _ (D
Control Building Elevation 100'
Figure 1 t0
Attachment 2 IN 97-01 January 8, 1997 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
96-72 Undetected Failure that 12/24/96 All teletherapy
May Occur During Patient licensees
Treatments with Teletherapy
Devices
96-71 Licensee Response to Indi- 12/27/96 All holders of OLs
cations of Tampering, Van- or CPs for nuclear
dalism, or Malicious Mis- power reactors
chief
96-70 Year 2000 Effect on Computer 12/24/96 All U.S. Nuclear
System Software Regulatory Commission
licensees, certificate
holders, and registrants
96-69 Operator Actions Affecting 12/20/96 All holders of OLs
Reactivity or CPs for nuclear
power reactors
96-68 Incorrect Effective Diaphragm 12/19/96 All holders of OLs
Area Values in Vendor Manual or CPs for nuclear
Result in Potential Failure power reactors
of Pneumatic Diaphragm
Actuators
96-67 Vulnerability of Emergency 12/19/96 All holders of OLs
Diesel Generators to Fuel or CPs for nuclear
Oil/Lubricating Oil Incom- power reactors
patibility
OL = Operating License
CP = Construction Permit
IN 97-01 January 8, 1997 and the scope of the NRC fire protection regulations (10 CFR 50.48). This vulnerability was
caused by the inadequate design of the grounding circuitry from the electrical power supplies, which have been in service since the original construction.
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 project manager.
original signed by D.B. Matthews
fA homas T. Martin, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Attachments:
1. Figure 1
2. List of Recently Issued NRC Information Notices
Technical contacts: Chris Vandenburgh, Region IV
(817) 860-8161 E-mail: cav~nrc.gov
Phil Qualls, Walnut Creek Field Office
(510) 975-0245 E-mail: pmqenrc.gov
Ronaldo Jenkins, NRR
(301) 415-2985 E-mail: rvj@nrc.gov
DOCUMENT NAME: 97-01lN
Tech Editor reviewed 10/11/96 To receive a copy of this document, hIdicate In the box: ACE = Copy w/o
attachment/enclosure 'E - Copy wlattachmentlenclosure 'N' - No copy
OFFICE TECH CONTS IC/PECB:DRPM lIID/DRPMA II,
NAME PQualls* AChaffee* TMarti'
CVandenburgh*
____ ___ R ienki ns* _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _
DATE 12/09/96 12/26/96 01/';/97 M
OFFIC1AL RECORD COPY
v-vIN 96-xx
December xx, 1996 The event was of concern because a single electrical fault caused simultaneous fires in the
control room and the Train B dc equipment room which supports alternative post-fire safe
shutdown capability in the event of a control room fire. This electrical design error is
important because it created a fire vulnerability in two separate areas of the plant. e fire
could have resulted in operational challenges which are outside of the plant's d gn basis
and the scope of the NRC fire protection regulations (10 CFR 50.48). This nerability was
caused by the inadequate design of the grounding circuitry from the ele I power supplies, which have been in service since the original construction.
This information notice requires no specific action or written res nse. If you have any
questions about the information in this notice, please conta ne of the technical contacts
listed below or the appropriate Office of Nuclear Reactor gulation project manager.
Tho s T. Martin, Director
Di i on of Reactor Program Management
ice of Nuclear Reactor Regulation
Technical contacts: Chris Vandenbu, Region IV
(817) 860-81 Email: cay nrc.gov
Phil ua s, Walnut Creek Field Office
(5 ) 975-0245 ail: pmq@nrc.gov
Ronaldo Jenkins, NRR
(301) 415-2985 EMail: rvjinrc.gov
Attachme s:
1. Figur 1
2. Lis cf Recently Issued NRC Information Notices
DOCUMENT NAME: G:URTRPALOIN.DFT
Tech Editor reviewed 10/11 To receive a copy of this document, indicate in the box: "C" = Copy without
attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy
OFFICE
CONTACT
S IC/EELB:DE C/SRXB:DSSAL C/PECB:DRPM D/DRPM
NAME PQualls* JCalvo* LMarsh* AChaftee TMartin
CVandenburgh*
RJenkins*
DATE 12 /09/96 12/09/96 12/12/96 12P__96 121 /96 OFFICIALtta REODCP', A90===11
-IN 96-xx
December xx, 1996 The event was of concern because a single electrical fault caused simultaneous
fires in the control room and the Train B dc equipment room which supports
alternative post-fire safe shutdown capability in the event of a control room
fire. This electrical design error is important because it created a fire
vulnerability in two separate areas of the plant. The fire ould have
resulted in operational challenges which are outside of t plant's design
basis and the scope of the NRC fire protection regulations (10 CFR 50.48).
This vulnerability was caused by the inadequate desigf of the grounding
circuitry from the electrical power supplies, whic ave been in service since
the original construction.
This information notice requires no specific ction or written response. If
you have any questions about the informatio in this notice, please contact
one of the technical contacts listed bel or the appropriate Office of
Nuclear Reactor Regulation project manaer.
Thomas T. Martin, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contacts: Chris ndenburgh. Region IV
(817) 60-8161 EMai : cav@nrc.gov
P il Qualls, Walnut Creek Field Office
510) 975-0245 EMail: pmq@nrc.gov
Ronaldo Jenkins, NRR
(301) 415-2985 EMail: rvj@nrc.gov
Attachment: 1. Figure 1
2. List of Recently Issued NRC Information Notices
DOCUM T NAME: G:\JRT\PALOIN.DFT
Tech Editor reviewed 10/11
[
To receive a copy of this document, indicate in the box: "C"= Copy without
attachment/enclosure
NAME PQualls*
CVandenburgh*
RJenkins*
"E"= Copy with attachment/enclosure "N" = No copy
OFFICE
CONTACT
S L C/EELB:DE [_ C/SRXB:DSSA L C/PECB:DRPM _D/DRPM
_
JCalvo* LMarsh* AChaffee TMartin
DATE 12 /09/96 12/09/96 12/12/96 12/ /96 ., 12/ /96 OFFICIAL RECORD COPY
4 IN 96-xx
December xx, 1996 vulnerability in two separate areas of the plant. The fire cowd have
resulted in operational challenges which are outside of thei ant's design
basis and the scope of the NRC fire protection regulation (10 CFR 50.48).
This vulnerability was caused by the inadequate design the grounding
circuitry from the electrical power supplies, which e been in service since
the original construction.
This information notice requires no specific ac *on or written response. If
you have any questions about the information i this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation project manager.
omas T. Martin, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contacts: Chris Vanonburgh, Region IV
(817) 8O -8161 EMail: cav@nrc.gov
Phi Qualls, Walnut Creek Field Office
CI0) 975-0245 ail: pmq@nrc.gov
Ronaldo Jenkins, NRR
(301) 415-2985 EMail: rvj@nrc.gov
Attachments: 1. Figure 1
2. List of Recently Issued NRC Information Notices
DOCUME NAME: G:\JRT\PALOIN.DFT
Tech ditor reviewed 10/11 To receive a copy of this document, indicate in the box: "C"= Copy without
attachment/enclosure "E"= Copy with attachment/enclosure "N"= No copy
OFFICE
CONTACT
S C/EELB: C/SRXB IC/PECB D/DRPM
Pr. DE L DSSA L_ :DRPM
NAME PQualls ul. JCalvo LMarshA AChaffee TMartin
CVandenb IM{
DATE R denkin_ _ _ _ _ _ _ _ _ _ _ _ _ _
DATE 12 /-/96 12/q/96 12/aE/96 12/ /96 12/ /96
,OFFICALRECORD COPY
0,119
4 t ' e
IN 96-xx
December xx, 1996 ,
potential to challenge the licensee's "Fire Protection Progr ' of 10 CFR
Part 50, Appendix R. This vulnerability was caused by th ?nadequate design
of the grounding circuitry from the electrical power supies, which have been
in service since the original construction.
This information notice requires no specific actiofi 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 project manager. J
Thomas T. Martin, Director
,Division of Reactor Program Management
//Office of Nuclear Reactor Regulation
Technical Contacts: Chris Vandenburgh, Region IV
(817) 860,:8161 EMail: /av@nrc.gov
Phil/Qualls, Walnut Creek Field Office
(5i) 975-0245 EMail: pmq@nrc.gov
Ronaldo Jenkins, NRR
(301) 415-2985 EMail: rvj@nrc.gov
Attachments: 1. Figure 1
2. List of Recently Issued NRC Information Notices
DOCUM T NAME: G:\JRT\PALOIN.DFT
Tec Editor reviewed 10/11 Tg receive a copy of this document, indicate in the box: "C"= (Copy without
attachment/enclosure "E"= Copy with attachment/enclosure "N'
" = No copy
OFFICE
CONTACT
S l I B:/EELB:
[C/SRXI C/PECB D/DRPM
_- ] DSSA DE :DRPM J
NAME PQualls 7 LMarsh JCalvo AChaffee TMartin
CVandenb 0ig
7 RJenkin t 110l
DATE 12 iJI98J9W 12/ /96 12/ /96 12/ /96 12/ /96 OFFIC RECORD COPY
|
---|
|
list | - Information Notice 1997-01, Improper Electrical Grounding Results in Simultaneous Fires in the Control Room and the Safe-Shutdown Equipment Room (8 January 1997, Topic: Safe Shutdown, Emergency Lighting)
- Information Notice 1997-02, Cracks Found in Jet Pump Riser Assembly Elbows at Boiling Water Reactors (6 February 1997)
- Information Notice 1997-03, Defacing of Labels to Comply with 10 CFR 20.1904(b) (20 February 1997)
- Information Notice 1997-04, Implementation of a New Constraint on Radioactive Air Effluents (24 February 1997, Topic: Backfit)
- Information Notice 1997-05, Offsite Notification Capabilities (27 February 1997, Topic: Earthquake)
- Information Notice 1997-06, Weaknesses in Plant-Specific Emergency Operating Procedures for Refilling the Secondary Side of Dry Once-Through Steam Generators (4 March 1997)
- Information Notice 1997-07, Problems Identified During Generic Letter 89-10 Closeout Inspections (6 March 1997, Topic: Hot Short, Safe Shutdown, Weak link)
- Information Notice 1997-08, Potential Failures of General Electric Magne-Blast Circuit Breaker Subcomponents (12 March 1997, Topic: Coatings, Weak link)
- Information Notice 1997-09, Inadequate Main Steam Safety Valve (MSSV) Setpoints and Performance Issues Associated with Long MSSV Inlet Piping (12 March 1997)
- Information Notice 1997-10, Liner Plate Corrosion in Concrete Containments (13 March 1997)
- Information Notice 1997-11, Cement Erosion from Containment Subfoundations at Nuclear Power Plants (21 March 1997)
- Information Notice 1997-12, Potential Armature Binding in General Electric Type Hga Relays (24 March 1997)
- Information Notice 1997-13, Deficient Conditions Associated with Protective Coatings at Nuclear Power Plants (24 March 1997, Topic: Coatings)
- Information Notice 1997-14, Assessment of Spent Fuel Pool Cooling (28 March 1997, Topic: Time to boil, Coatings)
- Information Notice 1997-15, Reporting of Errors and Changes in Large-Break Loss-of-Coolant Accident Evaluation Models of Fuel Vendors and Compliance with 10 CFR 50. 46(a)(3) (4 April 1997, Topic: Coatings, Fuel cladding)
- Information Notice 1997-16, Preconditioning of Plant Structures, Systems, and Components Before ASME Code Inservice Testing or Technical Specification Surveillance Testing (4 April 1997, Topic: Stroke time, Coatings)
- Information Notice 1997-17, Cracking of Vertical Welds in the Core Shroud and Degraded Repair (4 April 1997, Topic: Coatings)
- Information Notice 1997-18, Problems Identified During Maintenance Rule Baseline Inspections (14 April 1997, Topic: Probabilistic Risk Assessment, Coatings, Emergency Lighting)
- Information Notice 1997-19, Safety Injection System Weld Flaw at Sequcyah Nuclear Power Plant, Unit 2 (18 April 1997, Topic: Boric Acid)
- Information Notice 1997-20, Identification of Certain Uranium Hexafluoride Cylinders That Do Not Comply with ANSI N14.1 Fabrication Standards (17 April 1997)
- Information Notice 1997-21, Availability of Alternate AC Power Source Designed for Station Blackout Event (18 April 1997, Topic: Main transformer failure)
- Information Notice 1997-22, Failure of Welded-Steel Moment Resisting Frames During Northridge Earthquake (25 April 1997, Topic: Earthquake)
- Information Notice 1997-23, Evaluation and Reporting of Fires and Unplanned Chemical Reaction Events at Fuel Cycle Facilities (7 May 1997, Topic: Earthquake)
- Information Notice 1997-24, Failure of Packing Nuts on One-Inch Uranium Hexafluoride Cylinder Valves (8 May 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-25, Dynamic Range Uncertainties in the Reactor Vessel Level Instrumentation (9 May 1997, Topic: Earthquake)
- Information Notice 1997-26, Degradation in Small-Radius U-Bend Regions of Steam Generator Tubes (19 May 1997, Topic: Earthquake)
- Information Notice 1997-27, Effect of Incorrect Strainer Pressure Drop on Available Net Positive Suction Head (16 May 1997, Topic: Earthquake)
- Information Notice 1997-28, Elimination of Instrument Response Time Testing Under the Requirements of 10 CFR 50.59 (30 May 1997, Topic: Enforcement Discretion)
- Information Notice 1997-29, Containment Inspection Rule (30 May 1997)
- Information Notice 1997-30, Control of Licensed Material During Reorganizations, Employee-Management Disagreements, and Financial Crises (3 June 1997)
- Information Notice 1997-31, Failures of Reactor Coolant Pump Thermal Barriers and Check Valves in Foreign Plants (3 June 1997)
- Information Notice 1997-32, Defective Worm Shaft Clutch Gears in Limitorque Motor-Operated Valve Actuators (10 June 1997)
- Information Notice 1997-33, Unanticipated Effect of Ventilation System on Tank Level Indications and Engineering Safety Features Actuation System Setpoint (11 June 1997)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels in Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels In Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (Inc) IR100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (INC) Ir100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997)
- Information Notice 1997-36, Unplanned Intakes by Worker of Transuranic Airborne Radioactive Materials and External Exposure Due to Inadequate Control of Work (20 June 1997)
- Information Notice 1997-37, Main Transformer Fault with Ensuing Oil Spill Into Turbine Building (20 June 1997)
- Information Notice 1997-38, Level-Sensing System Initiates Common-Mode Faulure of High-Pressure-Injection Pumps (24 June 1997, Topic: Hydrostatic)
- Information Notice 1997-39, Inadequate 10 CFR 72.48 Safety Evaluations of Independent Spent Fuel Storage Installations (26 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-40, Potential Nitrogen Accumulation Resulting from Backleakage from Safety Injection Tanks (26 June 1997)
- Information Notice 1997-41, Revised - Potentially Undersized Emergency Diesel Generator (EDG) Oil Coolers (27 June 1997)
- Information Notice 1997-42, Management Weaknesses Resulting in Failure to Comply with Shipping Requirements for Special Nuclear Material (27 June 1997)
- Information Notice 1997-43, License Condition Compliance (1 July 1997, Topic: Ultimate heat sink)
- Information Notice 1997-44, Failures of Gamma Metrics Wide-Range Linear Neutron Flux Channels (1 July 1997)
- Information Notice 1997-45, Environmental Qualification Deficiency for Cables & Containment Penetration Pigtails (2 July 1997)
- Information Notice 1997-46, Unisolable Crack in High-Pressure Injection Piping (9 July 1997, Topic: Flow Induced Vibration)
- Information Notice 1997-47, Inadequate Puncture Tests for Type B Packages Under 10 CFR 71.73(c)(3) (27 June 1997)
- Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures (9 July 1997, Topic: Safe Shutdown, Unanalyzed Condition, Fire Barrier, Emergency Lighting, Continuous fire watch, Fire Protection Program, Fire Watch)
... further results |
---|