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| {{#Wiki_filter:UNITED STATESNUCLEAR REGULArORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555January 30, 1992NRC INFORMATION NOTICE 92-09: OVERLOADING AND SUBSEQUENT LOCK OUT OFELECTRICAL BUSES DURING ACCIDENT CONDITIONS | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULArORY |
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| | COMMISSION |
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| | ===OFFICE OF NUCLEAR REACTOR REGULATION=== |
| | WASHINGTON, D.C. 20555 January 30, 1992 NRC INFORMATION |
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| | NOTICE 92-09: OVERLOADING |
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| | AND SUBSEQUENT |
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| | LOCK OUT OF ELECTRICAL |
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| | ===BUSES DURING ACCIDENT CONDITIONS=== |
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| |
|
| ==Addressees== | | ==Addressees== |
| All holders of operating licenses 6toJMnstruett0n permits for nuclear powerreactors.92 FEa 13 A8:49 | | All holders of operating |
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| | licenses 6toJMnstruett0n |
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| | permits for nuclear power reactors.92 FEa 13 A8:49 |
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| |
|
| ==Purpose== | | ==Purpose== |
| The U.S. Nuclear Regulatory Comnission (NRC) is issuing this information noticeto alert addressees to a particular scenario identified by a licensee wherebyelectrical buses could be overloaded during accident conditions, deenergized,and prevented from being reenergized. It is expected that recipients willreview the Information for applicability to their facilities and consideractions, as appropriate, to avoid similar problems. However, suggestionscontained in this information notice are not NRC requirements; therefore, nospecific action or written response is required. | | The U.S. Nuclear Regulatory |
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| | Comnission (NRC) is issuing this information |
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| | notice to alert addressees |
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| | to a particular |
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| | scenario identified |
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| | by a licensee whereby electrical |
| | |
| | buses could be overloaded |
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| | during accident conditions, deenergized, and prevented |
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| | from being reenergized. |
| | |
| | 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 |
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| | On November 21, 1991, the Power Authority |
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| | for the State of New York, the licensee for Indian Point Nuclear Generating |
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| | Unit 3, reported that the vital buses could bWcome overloaded |
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| | during a loss-of-coolant-accident (LOCA) as a result of emergency |
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| | operating |
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| | procedures |
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| | directing |
| | |
| | operators |
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| | to restore non-essential |
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| | loads to the buses if offsite power is not lost. The procedure |
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| | would result in both emergency |
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| | and non-emergency |
| | |
| | loads being powered concurrently |
| | |
| | from the same bus. The licensee's |
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| | recent calculations |
| | |
| | reveal that performing |
| | |
| | this procedure |
| | |
| | could have overloaded |
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| | buses. The resulting |
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| | overcurrent |
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| | condition could lock out a bus (i.e., deenergize |
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| | the bus and prevent it from being reenergized |
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| | from any source including |
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| | the associated |
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| | emergency |
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| | diesel generator). |
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| | Discussion |
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| | A LOCA is generally |
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| | analyzed as the most limiting condition |
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| | in power demand for onsite electrical |
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| | systems. When non-essential |
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| | loads are added to the power system under this most demanding |
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| | condition, electrical |
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| | buses and breakers could be overloaded. |
| | |
| | The electrical |
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| | protection |
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| | system recognizes |
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| | such an overloaded |
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| | condition |
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| | as an electrical |
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| | fault on a bus and locks out the bus. The dc-powered |
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| | breaker controls retain the faulted condition, and the emergency |
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| | diesel generator will not be able to energize the bus until protective |
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| | relays are manually reset. The scenario could result in disabling |
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| | redundant |
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| | trains of safety-related |
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| | equipment. |
| | |
| | 9201240235 p* WI'' |
| | IN 92-09 January 30, 1992 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.o &Dbec Division of Operational |
| | |
| | ===Events Assessment=== |
| | office of Nuclear Reactor Regulation |
| | |
| | Technical |
| | |
| | contact: Thomas Koshy (301) 504-1176 Attachment: |
| | List of Recently Issued NRC Information |
| | |
| | Notices |
| | |
| | ------ ____-9 r Attachment |
| | |
| | IN 92-09 January 30, 1992 LIST OF RECENTLY ISSUED NRC INFORMATION |
| | |
| | NOTICES Information |
| | |
| | Date of Notice No. Subject Issuance Issued to 92-08 92-07 92-06 42-05 92-04 92-03 92-02 92-01 91-87 Revised Protective |
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| | Action Guidance for Nuclear Inci-dents Rapid Flow-Induced |
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| | Erosion/Corrosion |
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| | of Feedwater |
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| | Piping Reliability |
| | |
| | of ATWS Mitiga-tion System and Other NRC Required Equipment |
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| | Not Controlled |
| | |
| | by Plant Tech-nical Specifications |
| | |
| | Potential |
| | |
| | ===Coil Insulation=== |
| | Breakdcwn |
| | |
| | in ABB RXMH2 Relays Potter & Brumfield |
| | |
| | Model MDR Rotary Relay Failures Remote Trip Function Failures in General Electric F-Frame Molded-Case |
| | |
| | Circuit Breakers RelapS/Mod3 Computer Code Error Associated |
| | |
| | with the Conservation |
| | |
| | of Energy Equation Cable Damage Caused by Inadequate |
| | |
| | Cable Installa-tion Procedures |
| | |
| | and Controls Hydrogen Etbrittlement |
| | |
| | of Raychem Cryofit Couplings 01/23/92 01/09/92 01/15/92 01/08/92 01/06/92 01/06/92 01/03/92 01/03/92 12/27/91 All fuel cycle and materi-als licensees |
| | |
| | authorized |
| | |
| | to possess large quanti-ties of radioactive |
| | |
| | materi-ial.All holders of OLs or CPs for pressurized |
|
| |
|
| ==Description of Circumstances==
| | water reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.L a Operating |
| On November 21, 1991, the Power Authority for the State of New York, thelicensee for Indian Point Nuclear Generating Unit 3, reported that the vitalbuses could bWcome overloaded during a loss-of-coolant-accident (LOCA) as aresult of emergency operating procedures directing operators to restore non-essential loads to the buses if offsite power is not lost. The procedure wouldresult in both emergency and non-emergency loads being powered concurrentlyfrom the same bus. The licensee's recent calculations reveal that performingthis procedure could have overloaded buses. The resulting overcurrent conditioncould lock out a bus (i.e., deenergize the bus and prevent it from beingreenergized from any source including the associated emergency diesel generator).DiscussionA LOCA is generally analyzed as the most limiting condition in power demand foronsite electrical systems. When non-essential loads are added to the powersystem under this most demanding condition, electrical buses and breakers couldbe overloaded. The electrical protection system recognizes such an overloadedcondition as an electrical fault on a bus and locks out the bus. The dc-poweredbreaker controls retain the faulted condition, and the emergency diesel generatorwill not be able to energize the bus until protective relays are manuallyreset. The scenario could result in disabling redundant trains of safety-relatedequipment.9201240235 p* WI''
| |
| IN 92-09January 30, 1992 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.o &DbecDivision of Operational Events Assessmentoffice of Nuclear Reactor RegulationTechnical contact: Thomas Koshy(301) 504-1176Attachment: List of Recently Issued NRC Information Notices
| |
|
| |
|
| ------ ____-9 rAttachmentIN 92-09January 30, 1992 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to92-0892-0792-0642-0592-0492-0392-0292-0191-87Revised Protective ActionGuidance for Nuclear Inci-dentsRapid Flow-Induced Erosion/Corrosion of Feedwater PipingReliability of ATWS Mitiga-tion System and Other NRCRequired Equipment NotControlled by Plant Tech-nical SpecificationsPotential Coil InsulationBreakdcwn in ABB RXMH2 RelaysPotter & Brumfield ModelMDR Rotary Relay FailuresRemote Trip FunctionFailures in General ElectricF-Frame Molded-Case CircuitBreakersRelapS/Mod3 Computer CodeError Associated with theConservation of EnergyEquationCable Damage Caused byInadequate Cable Installa-tion Procedures and ControlsHydrogen Etbrittlement ofRaychem Cryofit Couplings01/23/9201/09/9201/15/9201/08/9201/06/9201/06/9201/03/9201/03/9212/27/91All fuel cycle and materi-als licensees authorizedto possess large quanti-ties of radioactive materi-ial.All holders of OLs or CPsfor pressurized waterreactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.L a Operating LicenseP a Construction Permit
| | License P a Construction |
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| }} | | Permit}} |
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| {{Information notice-Nav}} | | {{Information notice-Nav}} |
Overloading and Subsequent Lock Out of Electrical Buses During Accident ConditionsML031200714 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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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Issue date: |
01/30/1992 |
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From: |
Rossi C E Office of Nuclear Reactor Regulation |
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To: |
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References |
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IN-92-009, NUDOCS 9201240235 |
Download: ML031200714 (3) |
|
Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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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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 [[: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 [[: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 REGULArORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 January 30, 1992 NRC INFORMATION
NOTICE 92-09: OVERLOADING
AND SUBSEQUENT
LOCK OUT OF ELECTRICAL
BUSES DURING ACCIDENT CONDITIONS
Addressees
All holders of operating
licenses 6toJMnstruett0n
permits for nuclear power reactors.92 FEa 13 A8:49
Purpose
The U.S. Nuclear Regulatory
Comnission (NRC) is issuing this information
notice to alert addressees
to a particular
scenario identified
by a licensee whereby electrical
buses could be overloaded
during accident conditions, deenergized, and prevented
from being reenergized.
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 November 21, 1991, the Power Authority
for the State of New York, the licensee for Indian Point Nuclear Generating
Unit 3, reported that the vital buses could bWcome overloaded
during a loss-of-coolant-accident (LOCA) as a result of emergency
operating
procedures
directing
operators
to restore non-essential
loads to the buses if offsite power is not lost. The procedure
would result in both emergency
and non-emergency
loads being powered concurrently
from the same bus. The licensee's
recent calculations
reveal that performing
this procedure
could have overloaded
buses. The resulting
overcurrent
condition could lock out a bus (i.e., deenergize
the bus and prevent it from being reenergized
from any source including
the associated
emergency
diesel generator).
Discussion
A LOCA is generally
analyzed as the most limiting condition
in power demand for onsite electrical
systems. When non-essential
loads are added to the power system under this most demanding
condition, electrical
buses and breakers could be overloaded.
The electrical
protection
system recognizes
such an overloaded
condition
as an electrical
fault on a bus and locks out the bus. The dc-powered
breaker controls retain the faulted condition, and the emergency
diesel generator will not be able to energize the bus until protective
relays are manually reset. The scenario could result in disabling
redundant
trains of safety-related
equipment.
9201240235 p* WI
IN 92-09 January 30, 1992 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.o &Dbec Division of Operational
Events Assessment
office of Nuclear Reactor Regulation
Technical
contact: Thomas Koshy (301) 504-1176 Attachment:
List of Recently Issued NRC Information
Notices
____-9 r Attachment
IN 92-09 January 30, 1992 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 92-08 92-07 92-06 42-05 92-04 92-03 92-02 92-01 91-87 Revised Protective
Action Guidance for Nuclear Inci-dents Rapid Flow-Induced
Erosion/Corrosion
of Feedwater
Piping Reliability
of ATWS Mitiga-tion System and Other NRC Required Equipment
Not Controlled
by Plant Tech-nical Specifications
Potential
Coil Insulation
Breakdcwn
in ABB RXMH2 Relays Potter & Brumfield
Model MDR Rotary Relay Failures Remote Trip Function Failures in General Electric F-Frame Molded-Case
Circuit Breakers RelapS/Mod3 Computer Code Error Associated
with the Conservation
of Energy Equation Cable Damage Caused by Inadequate
Cable Installa-tion Procedures
and Controls Hydrogen Etbrittlement
of Raychem Cryofit Couplings 01/23/92 01/09/92 01/15/92 01/08/92 01/06/92 01/06/92 01/03/92 01/03/92 12/27/91 All fuel cycle and materi-als licensees
authorized
to possess large quanti-ties of radioactive
materi-ial.All holders of OLs or CPs for pressurized
water reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.L a Operating
License P a Construction
Permit
|
---|
|
list | - Information Notice 1992-01, Cable Damage Caused by Inadequate Cable Installation Procedures and Controls (3 January 1992, Topic: Overspeed trip)
- Information Notice 1992-02, Relap5/MOD3 Computer Code Error Associated with the Conservation of Energy Equation (3 January 1992, Topic: Overspeed trip)
- Information Notice 1992-02, Relap5/Mod3 Computer Code Error Associated with the Conservation of Energy Equation (3 January 1992)
- Information Notice 1992-03, Remote Trip Function Failures in General Electric F-Frame Molded-Case Circuit Breakers (6 January 1992, Topic: Overspeed trip)
- Information Notice 1992-04, Potter and Brumfield Model Mdr Rotary Relay Failures (6 January 1992, Topic: Probabilistic Risk Assessment, Commercial Grade, Overspeed trip)
- Information Notice 1992-04, Potter and Brumfield Model MDR Rotary Relay Failures (6 January 1992, Topic: Probabilistic Risk Assessment, Commercial Grade)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs RXMH2 Relays (8 January 1992, Topic: Commercial Grade, Overspeed trip)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs Rxmh2 Relays (8 January 1992, Topic: Commercial Grade)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in ABS RXMH2 Relays (8 January 1992, Topic: Commercial Grade)
- 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, Topic: Unidentified leakage)
- 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, Topic: Local Leak Rate Testing)
- 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, Topic: Commercial Grade)
- 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)
... further results |
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