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| | issue date = 01/30/1992 | | | issue date = 01/30/1992 |
| | title = Overloading and Subsequent Lock Out of Electrical Buses During Accident Conditions | | | title = Overloading and Subsequent Lock Out of Electrical Buses During Accident Conditions |
| | author name = Rossi C E | | | author name = Rossi C |
| | author affiliation = NRC/NRR | | | author affiliation = NRC/NRR |
| | addressee name = | | | addressee name = |
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| | page count = 3 | | | page count = 3 |
| }} | | }} |
| {{#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 |
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| | NUCLEAR REGULArORY COMMISSION |
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| | OFFICE OF NUCLEAR REACTOR REGULATION |
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| | WASHINGTON, D.C. 20555 January 30, 1992 NRC INFORMATION NOTICE 92-09: OVERLOADING AND SUBSEQUENT LOCK OUT OF |
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| | ELECTRICAL 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 | | permits for nuclear power |
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| | ===All holders of operating licenses 6toJMnstruett0n=== |
| | reactors. |
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| | 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 Comnission (NRC) is issuing this information notice |
| | |
| | identified by a licensee whereby |
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| | to alert addressees to a particular scenario accident conditions, deenergized, electrical buses could be overloaded during expected that recipients will |
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| | and prevented from being reenergized. Ittoistheir facilities and consider |
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| | review the Information for applicability problems. However, suggestions |
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| | actions, as appropriate, to avoid similarnot NRC requirements; therefore, no |
| | |
| | contained in this information notice is are |
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| | specific action or written response required. |
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| ==Description of Circumstances== | | ==Description of Circumstances== |
| 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'' | | On November 21, 1991, the Power Authority for Unitthe State of New York, the |
| 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 | | |
| | 3, reported that the vital |
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| | licensee for Indian Point Nuclear Generating (LOCA) as a |
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| | buses could bWcome overloaded during a loss-of-coolant-accident |
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| | directing operators to restore non- result of emergency operating procedures power is not lost. The procedure would |
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| | essential loads to the buses if offsite loads being powered concurrently |
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| | result inboth emergency and non-emergency calculations reveal that performing |
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| | from the same bus. The licensee's recent The resulting overcurrent condition |
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| | this procedure could have overloaded buses. |
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| | the bus and prevent it from being |
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| | could lock out a bus (i.e., deenergize the associated emergency diesel generator). |
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| | reenergized from any source including |
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| | Discussion |
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| | condition in power demand for |
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| | A LOCA is generally analyzed as the most limiting loads are added to the power |
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| | onsite electrical systems. When non-essential electrical buses and breakers could |
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| | system under this most demanding condition,system recognizes such an overloaded |
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| | be overloaded. The electrical protection and locks out the bus. The dc-powered |
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| | condition as an electrical fault on a bus |
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| | breaker controls retain the faulted condition, and the emergency diesel generator |
| | |
| | relays are manually |
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| | will not be able to energize the bus until protective trains of safety-related |
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| | reset. The scenario could result in disabling redundant |
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| | equipment. |
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| | 9201240235 p |
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| | * WI'' |
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| | 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 |
| | |
| | ------ ____ 11 - |
| | 9 r |
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| | Attachment |
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| | IN 92-09 January 30, 1992 LIST OF RECENTLY ISSUED |
| | |
| | NRC INFORMATION NOTICES |
| | |
| | Information Date of |
| | |
| | Notice No. Subject Issuance Issued to |
| | |
| | 92-08 Revised Protective Action 01/23/92 All fuel cycle and materi- Guidance for Nuclear Inci- als licensees authorized |
| | |
| | dents to possess large quanti- ties of radioactive materi- ial. |
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| | 92-07 Rapid Flow-Induced Erosion/ 01/09/92 All holders of OLs or CPs |
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| | Corrosion of Feedwater Piping for pressurized water |
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| | reactors. |
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| | 92-06 Reliability of ATWS Mitiga- 01/15/92 All holders of OLs or CPs |
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| | tion System and Other NRC for nuclear power reactors. |
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| | Required Equipment Not |
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| | Controlled by Plant Tech- nical Specifications |
| | |
| | 42-05 Potential Coil Insulation 01/08/92 All holders of OLs or CPs |
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| | Breakdcwn in ABB RXMH2 Relays for nuclear power reactors. |
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| | 92-04 Potter & Brumfield Model 01/06/92 All holders of OLs or CPs |
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| | MDR Rotary Relay Failures for nuclear power reactors. |
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| | 92-03 Remote Trip Function 01/06/92 All holders of OLs or CPs |
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| | Failures in General Electric for nuclear power reactors. |
| | |
| | F-Frame Molded-Case Circuit |
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| | Breakers |
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| | 92-02 RelapS/Mod3 Computer Code 01/03/92 All holders of OLs or CPs |
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| | Error Associated with the for nuclear power reactors. |
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| | Conservation of Energy |
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| | Equation |
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| | 92-01 Cable Damage Caused by 01/03/92 All holders of OLs or CPs |
| | |
| | Inadequate Cable Installa- for nuclear power reactors. |
|
| |
|
| ------ ____-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
| | tion Procedures and Controls |
|
| |
|
| }} | | 91-87 Hydrogen Etbrittlement of 12/27/91 All holders of OLs or CPs |
| | |
| | Raychem Cryofit Couplings for nuclear power reactors. |
| | |
| | L a Operating License |
| | |
| | P a Construction Permit}} |
|
| |
|
| {{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 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 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 [[: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
permits for nuclear power
All holders of operating licenses 6toJMnstruett0n
reactors.
92 FEa 13 A8:49
Purpose
The U.S. Nuclear Regulatory Comnission (NRC) is issuing this information notice
identified by a licensee whereby
to alert addressees to a particular scenario accident conditions, deenergized, electrical buses could be overloaded during expected that recipients will
and prevented from being reenergized. Ittoistheir facilities and consider
review the Information for applicability problems. However, suggestions
actions, as appropriate, to avoid similarnot NRC requirements; therefore, no
contained in this information notice is are
specific action or written response required.
Description of Circumstances
On November 21, 1991, the Power Authority for Unitthe State of New York, the
3, reported that the vital
licensee for Indian Point Nuclear Generating (LOCA) as a
buses could bWcome overloaded during a loss-of-coolant-accident
directing operators to restore non- result of emergency operating procedures power is not lost. The procedure would
essential loads to the buses if offsite loads being powered concurrently
result inboth emergency and non-emergency calculations reveal that performing
from the same bus. The licensee's recent The resulting overcurrent condition
this procedure could have overloaded buses.
the bus and prevent it from being
could lock out a bus (i.e., deenergize the associated emergency diesel generator).
reenergized from any source including
Discussion
condition in power demand for
A LOCA is generally analyzed as the most limiting loads are added to the power
onsite electrical systems. When non-essential electrical buses and breakers could
system under this most demanding condition,system recognizes such an overloaded
be overloaded. The electrical protection and locks out the bus. The dc-powered
condition as an electrical fault on a bus
breaker controls retain the faulted condition, and the emergency diesel generator
relays are manually
will not be able to energize the bus until protective trains of safety-related
reset. The scenario could result in disabling redundant
equipment.
9201240235 p
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
____ 11 -
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 Revised Protective Action 01/23/92 All fuel cycle and materi- Guidance for Nuclear Inci- als licensees authorized
dents to possess large quanti- ties of radioactive materi- ial.
92-07 Rapid Flow-Induced Erosion/ 01/09/92 All holders of OLs or CPs
Corrosion of Feedwater Piping for pressurized water
reactors.
92-06 Reliability of ATWS Mitiga- 01/15/92 All holders of OLs or CPs
tion System and Other NRC for nuclear power reactors.
Required Equipment Not
Controlled by Plant Tech- nical Specifications
42-05 Potential Coil Insulation 01/08/92 All holders of OLs or CPs
Breakdcwn in ABB RXMH2 Relays for nuclear power reactors.
92-04 Potter & Brumfield Model 01/06/92 All holders of OLs or CPs
MDR Rotary Relay Failures for nuclear power reactors.
92-03 Remote Trip Function 01/06/92 All holders of OLs or CPs
Failures in General Electric for nuclear power reactors.
F-Frame Molded-Case Circuit
Breakers
92-02 RelapS/Mod3 Computer Code 01/03/92 All holders of OLs or CPs
Error Associated with the for nuclear power reactors.
Conservation of Energy
Equation
92-01 Cable Damage Caused by 01/03/92 All holders of OLs or CPs
Inadequate Cable Installa- for nuclear power reactors.
tion Procedures and Controls
91-87 Hydrogen Etbrittlement of 12/27/91 All holders of OLs or CPs
Raychem Cryofit Couplings for nuclear power reactors.
L a Operating License
P a Construction Permit
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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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