Information Notice 1992-09, Overloading and Subsequent Lock Out of Electrical Buses During Accident Conditions: Difference between revisions

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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 =  
Line 14: Line 14:
| page count = 3
| page count = 3
}}
}}
{{#Wiki_filter:UNITED STATES NUCLEAR REGULArORY
{{#Wiki_filter:UNITED STATES


COMMISSION
NUCLEAR REGULArORY COMMISSION


===OFFICE OF NUCLEAR REACTOR REGULATION===
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 January 30, 1992 NRC INFORMATION


NOTICE 92-09: OVERLOADING
WASHINGTON, D.C. 20555 January 30, 1992 NRC INFORMATION NOTICE 92-09:     OVERLOADING AND SUBSEQUENT LOCK OUT OF


AND SUBSEQUENT
ELECTRICAL BUSES DURING ACCIDENT CONDITIONS
 
LOCK OUT OF ELECTRICAL
 
===BUSES DURING ACCIDENT CONDITIONS===


==Addressees==
==Addressees==
All holders of operating
permits for nuclear power


licenses 6toJMnstruett0n
===All holders of operating licenses 6toJMnstruett0n===
reactors.


permits for nuclear power reactors.92 FEa 13 A8:49  
92 FEa 13 A8:49


==Purpose==
==Purpose==
The U.S. Nuclear Regulatory
The U.S. Nuclear Regulatory Comnission   (NRC) is issuing this information notice
 
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
identified by a licensee whereby


to restore non-essential
to alert addressees to a particular scenario accident      conditions, deenergized, electrical buses could be overloaded during      expected that recipients will


loads to the buses if offsite power is not lost. The procedure
and prevented from being reenergized. Ittoistheir      facilities and consider


would result in both emergency
review the Information for applicability problems. However, suggestions


and non-emergency
actions, as appropriate, to avoid similarnot NRC requirements; therefore, no


loads being powered concurrently
contained in this information notice is are


from the same bus. The licensee's
specific action  or written response    required.


recent calculations
==Description of Circumstances==
On November 21, 1991, the Power Authority for Unitthe State of New York, the


reveal that performing
3, reported that the vital


this procedure
licensee for Indian Point Nuclear Generating                              (LOCA) as a


could have overloaded
buses could bWcome overloaded during a loss-of-coolant-accident


buses. The resulting
directing    operators    to  restore non- result of emergency operating procedures power    is  not  lost.   The   procedure would


overcurrent
essential loads to the buses if offsite        loads  being  powered    concurrently


condition could lock out a bus (i.e., deenergize
result inboth emergency and non-emergency calculations reveal that performing


the bus and prevent it from being reenergized
from the same bus. The licensee's recent        The resulting overcurrent condition


from any source including
this procedure could have overloaded buses.


the associated
the bus and prevent it from being


emergency
could lock out a bus (i.e., deenergize the  associated emergency diesel generator).


diesel generator).
reenergized from any source including


Discussion
Discussion


A LOCA is generally
condition in power demand for


analyzed as the most limiting condition
A LOCA is generally analyzed as the most limiting   loads are added to the power


in power demand for onsite electrical
onsite electrical systems. When non-essential  electrical buses and breakers could


systems. When non-essential
system under this most demanding condition,system    recognizes such an overloaded


loads are added to the power system under this most demanding
be overloaded. The electrical protection    and  locks  out the bus. The dc-powered


condition, electrical
condition as an electrical fault on  a bus


buses and breakers could be overloaded.
breaker controls retain the faulted condition,      and the emergency diesel generator


The electrical
relays are manually


protection
will not be able to energize the bus until protective            trains of safety-related


system recognizes
reset. The scenario could result in disabling redundant


such an overloaded
equipment.


condition
9201240235      p


as an electrical
*                          WI''


fault on a bus and locks out the bus. The dc-powered
IN 92-09 January 30, 1992 This information notice requires no specific action or written response. If


breaker controls retain the faulted condition, and the emergency
you have any questions about the information in this notice, please contact


diesel generator will not be able to energize the bus until protective
the technical contact listed below or the appropriate Office of Nuclear


relays are manually reset. The scenario could result in disabling
Reactor Regulation (NRR) project manager.


redundant
o      &Dbec


trains of safety-related
Division of Operational Events Assessment


equipment.
office of Nuclear Reactor Regulation
 
9201240235 p* WI''
IN 92-09 January 30, 1992 This information
 
notice requires no specific action or written response.


If you have any questions
Technical contact:  Thomas Koshy


about the information
(301) 504-1176 Attachment:  List of Recently Issued NRC Information Notices


in this notice, please contact the technical
------ ____  11          -
9 r


contact listed below or the appropriate
Attachment


Office of Nuclear Reactor Regulation (NRR) project manager.o &Dbec Division of Operational
IN 92-09 January 30, 1992 LIST OF RECENTLY ISSUED


===Events Assessment===
NRC INFORMATION NOTICES
office of Nuclear Reactor Regulation


Technical
Information                                      Date of


contact: Thomas Koshy (301) 504-1176 Attachment:
Notice No.        Subject                        Issuance  Issued to
List of Recently Issued NRC Information


Notices
92-08      Revised Protective Action            01/23/92  All fuel cycle and materi- Guidance for Nuclear Inci-                      als licensees authorized


------ ____-9 r Attachment
dents                                          to possess large quanti- ties of radioactive materi- ial.


IN 92-09 January 30, 1992 LIST OF RECENTLY ISSUED NRC INFORMATION
92-07      Rapid Flow-Induced Erosion/          01/09/92  All holders of OLs or CPs


NOTICES Information
Corrosion of Feedwater Piping                  for pressurized water


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
reactors.


Action Guidance for Nuclear Inci-dents Rapid Flow-Induced
92-06      Reliability of ATWS Mitiga-         01/15/92  All holders of OLs or CPs


Erosion/Corrosion
tion System and Other NRC                      for nuclear power reactors.


of Feedwater
Required Equipment Not


Piping Reliability
Controlled by Plant Tech- nical Specifications


of ATWS Mitiga-tion System and Other NRC Required Equipment
42-05      Potential Coil Insulation          01/08/92  All holders of OLs or CPs


Not Controlled
Breakdcwn in ABB RXMH2 Relays                  for nuclear power reactors.


by Plant Tech-nical Specifications
92-04        Potter & Brumfield Model            01/06/92  All holders of OLs or CPs


Potential
MDR Rotary Relay Failures                      for nuclear power reactors.


===Coil Insulation===
92-03      Remote Trip Function                01/06/92  All holders of OLs or CPs
Breakdcwn


in ABB RXMH2 Relays Potter & Brumfield
Failures in General Electric                    for nuclear power reactors.


Model MDR Rotary Relay Failures Remote Trip Function Failures in General Electric F-Frame Molded-Case
F-Frame Molded-Case Circuit


Circuit Breakers RelapS/Mod3 Computer Code Error Associated
Breakers


with the Conservation
92-02      RelapS/Mod3 Computer Code            01/03/92  All holders of OLs or CPs


of Energy Equation Cable Damage Caused by Inadequate
Error Associated with the                      for nuclear power reactors.


Cable Installa-tion Procedures
Conservation of Energy


and Controls Hydrogen Etbrittlement
Equation


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
92-01       Cable Damage Caused by              01/03/92   All holders of OLs or CPs


authorized
Inadequate Cable Installa-                    for nuclear power reactors.


to possess large quanti-ties of radioactive
tion Procedures and Controls


materi-ial.All holders of OLs or CPs for pressurized
91-87      Hydrogen Etbrittlement of            12/27/91  All holders of OLs or CPs


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
Raychem Cryofit Couplings                      for nuclear power reactors.


License P a Construction
L a Operating License


Permit}}
P a Construction Permit}}


{{Information notice-Nav}}
{{Information notice-Nav}}

Latest revision as of 03:18, 24 November 2019

Overloading and Subsequent Lock Out of Electrical Buses During Accident Conditions
ML031200714
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  Entergy icon.png
Issue date: 01/30/1992
From: Rossi C
Office of Nuclear Reactor Regulation
To:
References
IN-92-009, NUDOCS 9201240235
Download: ML031200714 (3)


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

  • 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


____ 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