Information Notice 2017-06, Battery and Battery Charger Short Circuit Current Contributions to a Fault on the DC Distribution System: Difference between revisions

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NUCLEAR REGULATORY COMMISSION
NUCLEAR REGULATORY COMMISSION


OFFICE OF NUCLEAR REACTOR REGULATION OFFICE OF NEW REACTORS
OFFICE OF NUCLEAR REACTOR REGULATION


WASHINGTON, DC 20555-0001 September 26, 2017  
OFFICE OF NEW REACTORS
 
WASHINGTON, DC 20555-0001  
 
September 26, 2017  


NRC INFORMATION NOTICE 2017-06: BATTERY AND BATTERY CHARGER
NRC INFORMATION NOTICE 2017-06: BATTERY AND BATTERY CHARGER
Line 33: Line 37:
All holders of an operating license or construction permit for a nuclear power reactor under
All holders of an operating license or construction permit for a nuclear power reactor under


Title 10 of the
Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Domestic Licensing of
 
Code of Federal Regulations (10 CFR) Part 50, "Domestic Licensing of


Production and Utilization Facilities," except t
Production and Utilization Facilities, except those who have permanently ceased operations
 
hose who have permanently ceased operations


and have certified that fuel has been permanently removed from the reactor vessel.
and have certified that fuel has been permanently removed from the reactor vessel.
Line 45: Line 45:
All holders of and applicants for a power reactor early site permit, combined license, standard
All holders of and applicants for a power reactor early site permit, combined license, standard


design approval, or manufacturing license under 10 CFR Part 52, "Licenses, Certifications, and
design approval, or manufacturing license under 10 CFR Part 52, Licenses, Certifications, and


Approvals for Nuclear Power Plants." All applicants for a standard design certification, including
Approvals for Nuclear Power Plants.  All applicants for a standard design certification, including


such applicants after initial issuance of a design certification rule.
such applicants after initial issuance of a design certification rule.
Line 58: Line 58:
evaluated the magnitude of direct current (DC) fault current contributions from batteries and
evaluated the magnitude of direct current (DC) fault current contributions from batteries and


battery chargers to a downstream short-circuit
battery chargers to a downstream short-circuit fault on the DC distribution system.  The detailed


fault on the DC distribution system.  The detailed
test results, conclusions, and recommendations are provided in NUREG/CR-7229, Testing to
 
test results, conclusions, and recommendations are provided in NUREG/CR-7229, "Testing to


Evaluate Battery and Battery Charger Short-Circuit Current Contributions to a Fault on the DC
Evaluate Battery and Battery Charger Short-Circuit Current Contributions to a Fault on the DC


Distribution System" (Agencywide Docum
Distribution System (Agencywide Documents Access and Management System (ADAMS)  
 
ents Access and Management System (ADAMS)  
Accession No. ML17039A869).  The NRC expects that recipients of this IN will review the
Accession No. ML17039A869).  The NRC expects that recipients of this IN will review the


Line 78: Line 74:


==DESCRIPTION OF CIRCUMSTANCES==
==DESCRIPTION OF CIRCUMSTANCES==
On September 6, 2013, the NRC issued IN 2013-17, "Significant Plant Transient Induced by
On September 6, 2013, the NRC issued IN 2013-17, Significant Plant Transient Induced by


Safety-Related Direct Current Bus Maintenance at Power" (ADAMS Accession Number
Safety-Related Direct Current Bus Maintenance at Power (ADAMS Accession Number


ML13193A009).  It informed addressees of an event involving the loss of one train of the DC
ML13193A009).  It informed addressees of an event involving the loss of one train of the DC


distribution system in a nuclear power plant.
distribution system in a nuclear power plant. Specifically, both the battery and the battery
 
Specifically, both the battery and the battery


charger on one DC Class 1E power division tripped on overcurrent when a fault occurred in a
charger on one DC Class 1E power division tripped on overcurrent when a fault occurred in a
Line 92: Line 86:
downstream DC panel.
downstream DC panel.


===The event demonstrated that the fault impact on t===
The event demonstrated that the fault impact on the DC distribution system at a nuclear power
he DC distribution system at a nuclear power


plant can have a significant impact, as described in IN 2013-17.  While the cause of the battery trip was well understood by the NRC staff, the cause of the battery charger trip was not clear.
plant can have a significant impact, as described in IN 2013-17.  While the cause of the battery trip was well understood by the NRC staff, the cause of the battery charger trip was not clear.
Line 101: Line 94:
the initial higher fault current contribution by the battery charger to the downstream fault, whether connected in parallel with the battery or not.  However, this configuration was
the initial higher fault current contribution by the battery charger to the downstream fault, whether connected in parallel with the battery or not.  However, this configuration was


inconsistent with the language provided in the Institute of Electrical and Electronics Engineers'
inconsistent with the language provided in the Institute of Electrical and Electronics Engineers
(IEEE) Standard (Std) 946-2004, "IEEE Recommended Practice for the Design of DC Auxiliary


Power Systems for Generating Stations," Subclause 7.9.2, which states, "When the battery
(IEEE) Standard (Std) 946-2004, IEEE Recommended Practice for the Design of DC Auxiliary


charger is connected in parallel with the battery , the battery capacitance will prevent the battery
Power Systems for Generating Stations, Subclause 7.9.2, which states, When the battery
 
charger is connected in parallel with the battery, the battery capacitance will prevent the battery


charger contribution from rising instantaneously.  Therefore, the maximum current that a
charger contribution from rising instantaneously.  Therefore, the maximum current that a


charger will deliver on short circuit will not typi
charger will deliver on short circuit will not typically exceed 150 [percent] of the charger full load
 
cally exceed 150 [percent] of the charger full load


ampere rating.  Instantaneous battery charger current rise should only become a concern during
ampere rating.  Instantaneous battery charger current rise should only become a concern during


periods when the battery is disconnected." Therefore, the Office of Nuclear Regulatory
periods when the battery is disconnected.  Therefore, the Office of Nuclear Regulatory


Research (RES) collaborated from 2014 through 2016 in a battery testing program with
Research (RES) collaborated from 2014 through 2016 in a battery testing program with
Line 134: Line 126:
contributions is described in IEEE Std 946-2004.  The use of this standard neglects the initial
contributions is described in IEEE Std 946-2004.  The use of this standard neglects the initial


fault current contribution from the charger.  The
fault current contribution from the charger.  The DC system overcurrent protective device sizing
 
DC system overcurrent protective device sizing


selection and/or coordination setting could result in a fault not being isolated as intended.  This
selection and/or coordination setting could result in a fault not being isolated as intended.  This
Line 143: Line 133:


==BACKGROUND==
==BACKGROUND==
 
The DC power system provides power for Class 1E equipment such as breaker control, plant
===The DC power system provides power for Class 1E===
equipment such as breaker control, plant


instrumentation and control, monitoring, lighting (main control room and remote shutdown area),  
instrumentation and control, monitoring, lighting (main control room and remote shutdown area),  
Line 152: Line 140:
charger or associated preferred alternating current source fail.
charger or associated preferred alternating current source fail.


Criterion 21, "Protection System Reliability and Testability," of Appendix A, "General Design
Criterion 21, Protection System Reliability and Testability, of Appendix A, General Design


Criteria for Nuclear Power Plants," to 10 CFR 50, "Domestic Licensing of Production and
Criteria for Nuclear Power Plants, to 10 CFR 50, Domestic Licensing of Production and


Utilization Facilities," states, "The protection system shall be designed for high functional
Utilization Facilities, states, The protection system shall be designed for high functional


reliability and inservice testability commensurate with the safety functions to be performed.
reliability and inservice testability commensurate with the safety functions to be performed.


Proper fault current calculations and protective device setttings on the DC system are important
Proper fault current calculations and protective device setttings on the DC system are important
Line 169: Line 157:
Reliability of the Class 1E DC power system is important in a nuclear power plant.  The DC
Reliability of the Class 1E DC power system is important in a nuclear power plant.  The DC


power system is designed so that no single failu
power system is designed so that no single failure of an electrical panel, battery, or battery
 
re of an electrical panel, battery, or battery


charger will result in a condition that will prevent the safe shutdown of the plant.
charger will result in a condition that will prevent the safe shutdown of the plant.
Line 181: Line 167:
controlled ferroresonant (CF) transformer-type, connected individually and in parallel with three
controlled ferroresonant (CF) transformer-type, connected individually and in parallel with three


Class 1E vented lead-acid batteries from different vendors.  The three nuclear-qualified batteries from three different vendors are repres
Class 1E vented lead-acid batteries from different vendors.  The three nuclear-qualified batteries from three different vendors are representative of battery models used in more than 75 percent of the nuclear power plants currently in the United States.  The SCR and CF battery
 
entative of battery models used in more than 75 percent of the nuclear power plants currently in the United States.  The SCR and CF battery


chargers represent about 90 percent of the battery charger designs used in nuclear power
chargers represent about 90 percent of the battery charger designs used in nuclear power
Line 191: Line 175:
The testing validated that the initial fault current contribution to a downstream fault from a
The testing validated that the initial fault current contribution to a downstream fault from a


battery charger (specifically the SCR-type chargers vs. the CF-type) is much higher-in the
battery charger (specifically the SCR-type chargers vs. the CF-type) is much higherin the


range of 7 to 10 times the charger full load ampere rating-during the first 100 milliseconds than
range of 7 to 10 times the charger full load ampere ratingduring the first 100 milliseconds than


what is currently stated as 150 percent in IEEE Std 946-2004.  The test results indicated that
what is currently stated as 150 percent in IEEE Std 946-2004.  The test results indicated that
Line 207: Line 191:
settings on the battery charger and downstream devices.  If IEEE Std 946-2004 was utilized to
settings on the battery charger and downstream devices.  If IEEE Std 946-2004 was utilized to


estimate short circuit current contributions in
estimate short circuit current contributions in DC distribution systems, licensees should consider
 
DC distribution systems, licensees should consider


performing a comprehensive review of the entire DC system protection coordination and
performing a comprehensive review of the entire DC system protection coordination and
Line 223: Line 205:
Additionally, there are efforts currently underway by the IEEE 946 Working Group to consider
Additionally, there are efforts currently underway by the IEEE 946 Working Group to consider


appropriate revisions to the standard.  The NRC staff that are involved in IEEE Standard 946  
appropriate revisions to the standard.  The NRC staff that are involved in IEEE Standard 946 have communicated to the working group the test results, conclusions, and recommendations
 
have communicated to the working group the test results, conclusions, and recommendations


provided in NUREG/CR 7229.
provided in NUREG/CR 7229.


==CONTACT==
==CONTACT==
S Please direct any questions about this matter to the technical contact(s) listed below or the
S
 
Please direct any questions about this matter to the technical contact(s) listed below or the


appropriate RES or Office of Nuclear Reactor Regulation (NRR) project manager.
appropriate RES or Office of Nuclear Reactor Regulation (NRR) project manager.


/ra/ (Gregory T. Bowman for)   /ra/ (Paul G. Krohn for)  
/ra/ (Gregory T. Bowman for)  
Louise Lund, Director     Timothy J. McGinty, Director Division of Policy and Rulemaking   Division of Construction Inspection
 
/ra/ (Paul G. Krohn for)  
 
Louise Lund, Director
 
Timothy J. McGinty, Director
 
Division of Policy and Rulemaking
 
Division of Construction Inspection
 
Office of Nuclear Reactor Regulation


Office of Nuclear Reactor Regulation    and Operational Programs
and Operational Programs


Office of New Reactors
Office of New Reactors
Line 244: Line 237:
Liliana Ramadan, RES/DE
Liliana Ramadan, RES/DE


301-415-2463 E-mail:   
301-415-2463  
Liliana.Ramadan@nrc.gov
 
E-mail:  Liliana.Ramadan@nrc.gov


Vijay Goel, NRR/DE
Vijay Goel, NRR/DE


301-415-3730  
301-415-3730  
  E-mail:
Vijay.Goel@nrc.gov


Note:  NRC generic communications may be found on the NRC public Web site, https://www.nrc.gov , under "NRC Library," "Document Collections."
E-mail: Vijay.Goel@nrc.gov
 
Note:  NRC generic communications may be found on the NRC public Web site, https://www.nrc.gov, under NRC Library, Document Collections.
 
ML17228A473; *concurred via email      TAC No. MG0062 OFFICE
 
TECH EDITOR*
RES/DE/ICEEB/TL*
RES/DE/ICEEB/TL*
RES/DE/ICEEB/BC*
NRR/DE/EEOB/BC*
NAME
 
JDougherty
 
LRamadan
 
KMiller
 
TKoshy
 
JQuichocho
 
(w/comments)
DATE
 
9/07/17
9/07/17
9/07/17
9/8/17
9/10/17 OFFICE
 
NRR/DE/EENB/BC
 
(Acting)*
NRO/DCIP/QVIB1/BC*
NRR/DE/D*
RES/DE/D*
NRR/DPR/PGCB/PM
 
NAME
 
TMartinez-Navedo
 
(w/comments)
TJackson
 
JLubinski
 
(w/comment)
BThomas
 
TMensah
 
DATE
 
9/11/17
9/07/17
9/18/17
9/15/17
9/19/17 OFFICE
 
NRR/DPR/PGCB/LA*
NRR/DPR/PGCB/BC
 
(Acting)*
NRO/DCIP/D
 
NRR/DPR/D
 
NAME
 
ELee
 
AGarmoe


ML17228A473; *concurred via email      TAC No. MG0062 OFFICE TECH EDITOR* RES/DE/ICEEB/TL* RES/DE/ICEEB/TL* RES/DE/ICEEB/BC* NRR/DE/EEOB/BC* NAME JDougherty LRamadan KMiller TKoshy
TMcGinty (PKrohn


JQuichocho (w/comments) DATE 9/07/17
for)  
9/07/17 9/07/17
LLund (GBowman
9/8/17 9/10/17 OFFICE NRR/DE/EENB/BC (Acting)*
NRO/DCIP/QVIB1/BC* NRR/DE/D*
RES/DE/D* NRR/DPR/PGCB/PM


NAME TMartinez-Navedo (w/comments) TJackson JLubinski (w/comment) BThomas TMensah DATE 9/11/17 9/07/17
for)  
9/18/17 9/15/
17 9/19/17 OFFICE NRR/DPR/PGCB/LA*
NRR/DPR/PGCB/BC (Acting)* NRO/DCIP/D NRR/DPR/D  NAME ELee AGarmoe TMcGinty (PKrohn


for) LLund (GBowman
DATE


for)  DATE 9/20/17  
9/20/17  
9/20/17 9/21/
9/20/17  
17 9/26/17}}
9/21/17
9/26/17}}


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

Latest revision as of 13:47, 8 January 2025

Battery and Battery Charger Short Circuit Current Contributions to a Fault on the DC Distribution System
ML17228A473
Person / Time
Issue date: 09/26/2017
From: Louise Lund, Mcginty T
Division of Construction Inspection and Operational Programs, Division of Policy and Rulemaking
To:
Mensah, T.M., NRR/DPR 415-3610
References
IN-17-006
Download: ML17228A473 (4)


ML17228A473 UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

OFFICE OF NEW REACTORS

WASHINGTON, DC 20555-0001

September 26, 2017

NRC INFORMATION NOTICE 2017-06: BATTERY AND BATTERY CHARGER

SHORT-CIRCUIT CURRENT CONTRIBUTIONS

TO A FAULT ON THE DIRECT CURRENT

DISTRIBUTION SYSTEM

ADDRESSEES

All holders of an operating license or construction permit for a nuclear power reactor under

Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Domestic Licensing of

Production and Utilization Facilities, except those who have permanently ceased operations

and have certified that fuel has been permanently removed from the reactor vessel.

All holders of and applicants for a power reactor early site permit, combined license, standard

design approval, or manufacturing license under 10 CFR Part 52, Licenses, Certifications, and

Approvals for Nuclear Power Plants. All applicants for a standard design certification, including

such applicants after initial issuance of a design certification rule.

PURPOSE

The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice (IN) to inform

addressees of the results of a recent NRC-led battery testing program. The testing program

evaluated the magnitude of direct current (DC) fault current contributions from batteries and

battery chargers to a downstream short-circuit fault on the DC distribution system. The detailed

test results, conclusions, and recommendations are provided in NUREG/CR-7229, Testing to

Evaluate Battery and Battery Charger Short-Circuit Current Contributions to a Fault on the DC

Distribution System (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML17039A869). The NRC expects that recipients of this IN will review the

information for applicability to their facilities and consider actions, as appropriate, for potential

impacts on DC fault studies and other related calculations. The suggestions in this IN are not

NRC requirements; therefore, the NRC requires no specific action or written response.

DESCRIPTION OF CIRCUMSTANCES

On September 6, 2013, the NRC issued IN 2013-17, Significant Plant Transient Induced by

Safety-Related Direct Current Bus Maintenance at Power (ADAMS Accession Number

ML13193A009). It informed addressees of an event involving the loss of one train of the DC

distribution system in a nuclear power plant. Specifically, both the battery and the battery

charger on one DC Class 1E power division tripped on overcurrent when a fault occurred in a

downstream DC panel.

The event demonstrated that the fault impact on the DC distribution system at a nuclear power

plant can have a significant impact, as described in IN 2013-17. While the cause of the battery trip was well understood by the NRC staff, the cause of the battery charger trip was not clear.

The NRC staff assumed that the cause of the battery charger trip could have been because of

the initial higher fault current contribution by the battery charger to the downstream fault, whether connected in parallel with the battery or not. However, this configuration was

inconsistent with the language provided in the Institute of Electrical and Electronics Engineers

(IEEE) Standard (Std) 946-2004, IEEE Recommended Practice for the Design of DC Auxiliary

Power Systems for Generating Stations, Subclause 7.9.2, which states, When the battery

charger is connected in parallel with the battery, the battery capacitance will prevent the battery

charger contribution from rising instantaneously. Therefore, the maximum current that a

charger will deliver on short circuit will not typically exceed 150 [percent] of the charger full load

ampere rating. Instantaneous battery charger current rise should only become a concern during

periods when the battery is disconnected. Therefore, the Office of Nuclear Regulatory

Research (RES) collaborated from 2014 through 2016 in a battery testing program with

Brookhaven National Laboratory (BNL) to validate the assumptions. The purpose of the testing

program was to determine if the battery and battery charger current contributions to the fault on

the DC distribution circuit would be different when connected individually or when connected in

parallel, which could impact the DC system device coordination.

In February 2017, the testing results were documented and published in NUREG/CR-7229.

One of the methods potentially used at nuclear power plants to estimate the short-circuit current

contributions is described in IEEE Std 946-2004. The use of this standard neglects the initial

fault current contribution from the charger. The DC system overcurrent protective device sizing

selection and/or coordination setting could result in a fault not being isolated as intended. This

can lead to undesirable system responses to a fault on the DC distribution system.

BACKGROUND

The DC power system provides power for Class 1E equipment such as breaker control, plant

instrumentation and control, monitoring, lighting (main control room and remote shutdown area),

and other functions. The battery supplies the load without interruption should the battery

charger or associated preferred alternating current source fail.

Criterion 21, Protection System Reliability and Testability, of Appendix A, General Design

Criteria for Nuclear Power Plants, to 10 CFR 50, Domestic Licensing of Production and

Utilization Facilities, states, The protection system shall be designed for high functional

reliability and inservice testability commensurate with the safety functions to be performed.

Proper fault current calculations and protective device setttings on the DC system are important

so that a fault can be isolated as close to the location of the fault as possible, thereby

minimizing the impact on plant operations and safety.

DISCUSSION

Reliability of the Class 1E DC power system is important in a nuclear power plant. The DC

power system is designed so that no single failure of an electrical panel, battery, or battery

charger will result in a condition that will prevent the safe shutdown of the plant.

During the battery testing program, BNL performed various short-circuit tests that simulated fault

conditions on a DC distribution system typical within a nuclear power plant. More specifically, two types of battery chargers were considered, a silicon controlled rectifier (SCR)-type and a

controlled ferroresonant (CF) transformer-type, connected individually and in parallel with three

Class 1E vented lead-acid batteries from different vendors. The three nuclear-qualified batteries from three different vendors are representative of battery models used in more than 75 percent of the nuclear power plants currently in the United States. The SCR and CF battery

chargers represent about 90 percent of the battery charger designs used in nuclear power

plants currently in the United States.

The testing validated that the initial fault current contribution to a downstream fault from a

battery charger (specifically the SCR-type chargers vs. the CF-type) is much higherin the

range of 7 to 10 times the charger full load ampere ratingduring the first 100 milliseconds than

what is currently stated as 150 percent in IEEE Std 946-2004. The test results indicated that

the initial short circuit contribution from the charger is not limited when connected in parallel with

the battery. The SCR-type charger contributed more to the fault current due to the longer

response time of its current limiting circuit than the CF-type. The initial higher short circuit

current contribution from the battery charger could impact the coordination of protective device

settings on the battery charger and downstream devices. If IEEE Std 946-2004 was utilized to

estimate short circuit current contributions in DC distribution systems, licensees should consider

performing a comprehensive review of the entire DC system protection coordination and

assumptions of battery and charger short circuit currents that were used to select their

protection fault interruption ratings and setpoints. Specifically, licensees are encouraged to

review their fault current calculations, make any necessary revision to size, and coordinate the

protective device settings based on the new information documented in NUREG/CR-7229.

Additionally, there are efforts currently underway by the IEEE 946 Working Group to consider

appropriate revisions to the standard. The NRC staff that are involved in IEEE Standard 946 have communicated to the working group the test results, conclusions, and recommendations

provided in NUREG/CR 7229.

CONTACT

S

Please direct any questions about this matter to the technical contact(s) listed below or the

appropriate RES or Office of Nuclear Reactor Regulation (NRR) project manager.

/ra/ (Gregory T. Bowman for)

/ra/ (Paul G. Krohn for)

Louise Lund, Director

Timothy J. McGinty, Director

Division of Policy and Rulemaking

Division of Construction Inspection

Office of Nuclear Reactor Regulation

and Operational Programs

Office of New Reactors

Technical Contact:

Liliana Ramadan, RES/DE

301-415-2463

E-mail: Liliana.Ramadan@nrc.gov

Vijay Goel, NRR/DE

301-415-3730

E-mail: Vijay.Goel@nrc.gov

Note: NRC generic communications may be found on the NRC public Web site, https://www.nrc.gov, under NRC Library, Document Collections.

ML17228A473; *concurred via email TAC No. MG0062 OFFICE

TECH EDITOR*

RES/DE/ICEEB/TL*

RES/DE/ICEEB/TL*

RES/DE/ICEEB/BC*

NRR/DE/EEOB/BC*

NAME

JDougherty

LRamadan

KMiller

TKoshy

JQuichocho

(w/comments)

DATE

9/07/17

9/07/17

9/07/17

9/8/17

9/10/17 OFFICE

NRR/DE/EENB/BC

(Acting)*

NRO/DCIP/QVIB1/BC*

NRR/DE/D*

RES/DE/D*

NRR/DPR/PGCB/PM

NAME

TMartinez-Navedo

(w/comments)

TJackson

JLubinski

(w/comment)

BThomas

TMensah

DATE

9/11/17

9/07/17

9/18/17

9/15/17

9/19/17 OFFICE

NRR/DPR/PGCB/LA*

NRR/DPR/PGCB/BC

(Acting)*

NRO/DCIP/D

NRR/DPR/D

NAME

ELee

AGarmoe

TMcGinty (PKrohn

for)

LLund (GBowman

for)

DATE

9/20/17

9/20/17

9/21/17

9/26/17