Information Notice 1989-21, Changes in Performance Characteristics of Molded-Case Circuit Breakers

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Changes in Performance Characteristics of Molded-Case Circuit Breakers
ML031180541
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, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane
Issue date: 02/27/1989
From: Rossi C
Office of Nuclear Reactor Regulation
To:
References
IN-89-021, NUDOCS 8902210564
Download: ML031180541 (7)


UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555

February 27, 1989 NRC INFORMATION NOTICE NO. 89-21: CHANGES IN PERFORMANCE CHARACTERISTICS

OF MOLDED-CASE CIRCUIT BREAKERS

Addressees

All holders of operating licenses or construction permits for nuclear power

reactors.

Purpose

This information notice is being provided to alert addressees to an observed

practice in which vendors make changes to the performance characteristics of

molded-case circuit breakers without making any corresponding revisions to

the breaker part number. 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 do not constitute NRC requirements; therefore, no

specific action or written response is required.

Description of Circumstances

During several inspections performed by the NRC, it was discovered that manu- facturers of molded case circuit breakers frequently altered the time-current

characteristic curves pertaining to a particular style or type of breaker.

These changes were made without changing the part number of the breaker and

often without any specific notification to the customer. The changes identi- fied during the NRC inspections ranged from very minor alterations to the

thermal portion of the curves to major alterations to the magnetic instanta- neous trip portion of the curves.

One change for ITE-type 100-amp breakers

involved the movement of the instantaneous band from 600-1000 amps to 1200-2000

amps. Although product literature usually contains the appropriate curves, the

curves are not routinely provided with the breakers.

Discussion:

As a result of these changes, many licensees who procure replacement breakers

by part number only are receiving breakers with performance characteristics

that may be different from those assumed in the original plant design. If the

breakers are not analyzed for performance characteristics, upon installation

these breakers potentially could degrade the electrical protection system

and/or cause premature tripping upon the energizing of vital safety-related

systems. Additionally, many perceived failures of circuit breakers detected

802

6

IN 89-21 February 27, 1989 during pre-installation or routine testing may actually be the result of un- known changes in time-current characteristic curves.

One way to ensure that

the breakers purchased conform to a particular curve would be to reference

the specific curve (including the applicable revision) as part of the purchase

requirements.

If the breaker was no longer manufactured to meet the specifi- cations of that specific curve, the new curve would have to be analyzed for

its effect on the overall system.

No specific action or written response is required by this information notice.

If you have any questions about this matter, please contact the technical

contact listed below or the Regional Administrator of the appropriate regional

office.

arl

.

si, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

J. B. Jacobson, NRR

(301) 492-0996 Attachment: List of Recently Issued NRC Information Notices

Attachment

IN 89-21 ;

February 27, 1989

Page 1 of I

LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

I nformati on

Date of

Notice No.

Subject

Issuance

Issued to

88-73,

Supplement 1

Direction-Dependent Leak

Characteristics of Contain- ment Purge Valves

2/27/89

All holders of OLs

or CPs for nuclear

power reactors.

89-20

89-19

89-18

89-17

89-16

89-15

89-14

Weld Failures in a Pump

of Byron-Jackson Design

Health Physics Network

2/24/89

2/23/89

2/22/89

Criminal Prosecution

Wrongdoing Committed

Suppliers of Nuclear

Products or Services

ofby

All holders of OLs

or CPs for nuclear

power reactors.

All holders of OLs

or CPs for nuclear

power reactors, and

the following fuel

facilities: Nuclear

Fuel Services of Erwin,

General Atomic, UNC

Montville, B&W LRC

Lynchburg, and B&W

Lynchburg.

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.

Contamination and Degra- dation of Safety-Related

Battery Cells

Excessive Voltage Drop

in dc Systems

Second Reactor Coolant Pump

Shaft Failure at Crystal

River

Inadequate Dedication

Process for Commercial

Grade Components Which

Could Lead to Common Mode

Failure of a Safety System

2/22/89

2/16/89

2/16/89

2/16/89 OL = Operating License

CP = Construction Permit

IN 89-21 February 27, 1989 during pre-installation or routine testing may actually be the result of un- known changes in time-current characteristic curves. One way to ensure that

the breakers purchased conform to a particular curve would be to reference

the specific curve (including the applicable revision) as part of the purchase

requirements. If the breaker was no longer manufactured to meet the specifi- cations of that specific curve, the new curve would have to be analyzed for

its effect on the overall system.

No specific action or written response is required by this information notice.

If you have any questions about this matter, please contact the technical

contact listed below or the Regional Administrator of the appropriate regional

office.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

J. B.

(301)

Jacobson, NRR

492-0996 Attachment:

List of Recently Issued NRC Information Notices

  • SEE PREVIOUS CONCURRENCES

D <

2/89

  • BC/AB:DRIS:NRR

EWBrach

02/07/89

  • C/OGCB:DOEA:NRR

CHBerlinger

02/09/89

  • BC/SELB:DEST:NRR

FRose

02/06/89

  • PPMB:ARM

TechEd

02/17/89

  • D/DRIS:NRR

BKGrimes

02/07/89

  • VIB:DRIS:NRR

JJacobson

01/30/89

  • SC/VIB:DRIS:NRR

UPotapovs

02/01/89

IN 89-XX

January XX, 1989 plant design. If unanalyzed, upon installation these breakers could

potenttally degrade the electrical protection system and/or cause premature

tripping upon energization of vital safety-related systems.

Additionally, many

perceived circuit breaker failures detected during pre-installation or routine

testing may actually be due to an unknown change in Time - Current

Characteristic Curves. One way to ensure that received breakers conform to a

particular curve would be to reference the specific curve (including revision

applicable) as part of the purchase requirements. If the breaker needed is no

longer manufactured to that specific curve, the new curve would need to be

analyzed for its effect on the overall system.

No specific action or written response is required by this information notice.

If you have any questions about this matter, please contact the technical

contact listed below or the Regional Administrator of the appropriate regional

office.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

J. B. Jacobson, NRR

(301) 492-0996

  • See previous concurrence.

OFC

VIB:DRIS
SC:VIB:DRIS
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NAME :JJacobson:nrp

UPotapovs*
EWBrach*
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BKGrimes*

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DATE :01/30/89*

02/01/89
02/07/89
02/06/89
02/07/89
02i1 /89 OFC
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IN 89-XX

January XX, 1989 plant design. If unanalyzed, upon installation these breakers could

potentially degrade the electrical protection system and/or cause premature

trip ing upon energization of vital safety related systems. Additionally, many

perce ed circuit breaker failures detected during pre-installation or routine

testing ay actually be due to an unknown change in Time - Current

Characterstic Curves. One way to ensure that received breakers conform to a

particular urve would be to reference the specific curve (including revision

applicable)

part of the purchase requirements. If the breaker need

is no

longer manufac ured to that specific curve, the new curve would need o be

analyzed for it effect on the overall system. No specific actio

r written

response is requi ed by this information notice. If you have a

questions

about this matter, lease contact the technical contact liste

below or the

Regional Administrat r of the appropriate regional office.

Charles E.

i, Director

Division

Operational Events Assessment

Office o Nuclear Reactor Regulation

Technical Contact:

J. B. Jacobson, RR

(301) 492-0996

DISTRIBUTION

Central Files

VIB R/F

DRIS R/F

BKGrimes

EWBrach

UPotapovs

JJacobson

  • See pr

ious concurrence.

IB:D I

SC: VIB- IS
BC: TORIS

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NAME

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DATE

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02/

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02/2 /89
02/

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02/

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02/

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IN 89-XX

January XX 1989

Page 2 of

plant design. If analyzed, upon installation these breakers cou d

potentially degrade

e electrical protection system and/or caus premature

tripping upon energiza on of vital safety related systems. Ad tionally, many

perceived circuit breake failures detected during pre-install ion or routine

testing may actually be du to an unknown change in Time - Cu rent

Characteristic Curves.

One

y to ensure that received brea ers conform to a

particular curve would be to reference the specific curve ( ncluding Revision

applicable) as part of the purc se requirements. If the reaker needed is no

longer manufactured to that spec ic curve, the new curve ould need to be

analyzed for its effect on the ove

11 system. No speci ic action or written

response is required by this informa ion notice. If yo have any questions

about this matter, please contact the echnical contac listed below or the

Regional Administrator of the appropria

regional of ice.

Charles E.

or

Divisi

o Op ational Events Assessment

Off' e of Nuclea Reactor Regulation

Technical Contact:

J. B. Jacobson, RR

(301) 492-0996

DISTRIBUTION

Central Files

VIB R/F

DRIS R/F

BKGrimes

EWBrach

UPotapovs

JJacobson

OFC

VIB:DRIS
9C: IB:DRIS
BC:VIB:DRIS

______-------

--

-

-

--

-

-

-

-

-

-

-



NAME

JJacob

.nrp1/ :UPotapovs

EWBrach

:1------

01/ /8--

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01/

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---_


DATE

01/0o/8
01/

/89

01/

/89