Information Notice 2014-10, Unfused DC Ammeter Circuits and Potential for Fire Events

Unfused DC Ammeter Circuits and Potential for Fire Events

ML14169A264
Person / Time
Issue date:	09/16/2014
From:	Michael Cheok, Kokajko L Division of Construction Inspection and Operational Programs, Division of Policy and Rulemaking
To:
References
TAC MF4189 IN-14-010
Download: ML14169A264 (5)

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

OFFICE OF NEW REACTORS

WASHINGTON, DC 20555-0001 September 16, 2014 NRC INFORMATION NOTICE 2014-10: POTENTIAL CIRCUIT FAILURE-INDUCED

SECONDARY FIRES OR EQUIPMENT DAMAGE

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 that 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 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 recent operating experience related to a potential for circuit failure-induced

secondary fire events or equipment damage. The NRC expects that recipients will review the

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

contained in this IN are not NRC requirements; therefore, no specific action or written response

is required.

DESCRIPTION OF CIRCUMSTANCES

This section describes events caused by a possible unanalyzed condition involving a potential

for circuit failure-induced secondary fire events or equipment damage. This unanalyzed

condition has been reported in event notifications (ENs) and licensee event reports (LERs) to

the NRC. Three examples are discussed below.

Browns Ferry Nuclear Plant

On October 15, 2011, the Browns Ferry Nuclear (BFN) Plant reported this issue via EN 47374 and subsequently on December 27, 2011, per BFN LER 2011-010 DC Ammeter Cables Not

Adequately Isolated (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML12003A256). The LER documents that during reviews to transition to the

National Fire Protection Association (NFPA) Standard 805, "Performance-Based Standard for

ML14169A264 Fire Protection for Light-Water Reactor Electric Generating Plants" (NFPA 805), the licensee

identified that the ammeters located in the main control room (MCR) for Battery Boards 1, 2, and 3 were electrically connected to the safety-related 250-volt dc bus at the battery boards

without electrical isolation. This condition may have the potential to cause secondary fires if two

ungrounded common power supply circuit faults occur during a fire that impacts the ammeter.

This condition impacted all three nuclear units, as the electrical isolation requirements for the

MCR ammeters were not maintained. This constituted a fire protection program deficiency that

could adversely affect the ability to achieve and maintain safe shutdown of the plant in the

unlikely event of a MCR fire. At the time of discovery, fire watches were already in place and

will remain in place until the identified condition is resolved. Corrective actions included the

addition of fuses to the ammeter circuits.

Clinton Power Station

During a Clinton Power Station (CPS) review of the event notification at the BFN Plant (EN 47374), CPS determined that the original plant design for the station battery ammeter circuits

contains a shunt in the current flow from each station battery. Attached to the shunt bar are two

leads to an ammeter in the MCR. The ammeter circuits attached to the shunt does not have

fuses, and if one of the ammeter circuits shorts to ground due to a fire at the same time another

dc circuit from the opposite polarity on the same battery also shorts to ground, a ground loop

through the unfused ammeter circuit could occur. The circuit was bounded by testing showing

that self-ignition of a secondary fire was not possible. However, the potential exists that

overloaded ammeter circuit could result in thermal damage to safe shutdown circuits in direct

physical contact with the ammeter circuit, resulting in a loss of the associated safe shutdown

function or capability. CPS reported this information to the NRC on January 27, 2012, in LER

2011-007-00 (ADAMS Accession No. ML12053A099).

Nine Mile Point Nuclear Station, Unit 1

During a review of industry operating experience regarding the potential for secondary fires

being caused by dc motor control circuits, Nine Mile Point Nuclear Station determined that the

described condition could be applicable to Nine Mile Point, Unit 1. This resulted in a potentially

unanalyzed condition with respect to 10 CFR Part 50, Appendix R analysis requirements. The

original plant design and configuration for a containment isolation valve included only over

current protection for the power circuits. There was no separate, properly-sized fuse protection

for the control circuits. The only protection for the control circuits was provided by the power

circuit fuses.

In the postulated event, a fire in the reactor building at the dc motor operated valve could cause

one of the control circuits to short and potentially over heat since the current draw from the short

circuit would not be large enough to open the power circuit fuse, creating the potential for a

secondary fire in a different fire zone. The secondary fire could adversely affect safe shutdown

equipment and potentially affect the ability to achieve safe shutdown as required by 10 CFR

Part 50, Appendix R. This event was entered into the Nine Mile Point corrective action program and reported via EN 50098 and subsequently on July 8, 2014, in LER 2014-002-00 Unanalyzed Condition Due to

Unfused Motor Operated Valve Control Circuit (ADAMS Accession No. ML14205A279).

DISCUSSION

In the course of licensees performing self-assessments of their fire protection programs, several

facilities have reported issues involving a potential for circuit failure-induced secondary fire

events or thermal damage to equipment. In many cases, the issue is related to a lack of circuit

isolation on ammeter circuits and, therefore, these circuits present a potential fire source in

equipment if the ammeter circuit becomes grounded coincident with another circuit fault. In

some other cases, the issue is related to a lack of circuit isolation for power and control circuits

that can result in overheated cabling due to an electrical short and cause a secondary fire or

thermal damage. In some cases, safety-related equipment could be impacted due to thermal

damage. Note that there have been no fires reported to the NRC related to these issues.

However, licensees are reporting the potential for this to occur and impact associated safe

shutdown functions or capabilities.

Based on additional industry operating experience reviews, licensees have determined that

unanalyzed conditions may exist with respect to their existing deterministic fire protection

program requirements and analysis requirements involving dc ammeter circuits. Postulated

events could cause an unfused dc ammeter circuit to be grounded. If the event also causes

another dc circuit of the opposite polarity on the same component to become grounded, a

ground loop through the unfused dc ammeter circuit could then exist. This ground loop could

draw excessive current and the electrical conductor could overheat and damage adjacent

cables, or may result in a secondary fire or damage depending on the cable size, insulation, and

whether the type of cable would support self-ignition. NRC guidance contained in Generic

Letter (GL) 81-12 - Fire Protection Rule (45 FR 76602, 11/19/80) concerning associated circuits

of common enclosures, aims to prevent secondary fires and equipment damage from adversely

affecting safe shutdown. Licensee responses to GL 81-12 typically indicate that all circuits are

provided with appropriately-sized circuit protection devices.

As noted in the LERs, compensatory measures (i.e., fire watches or other appropriate

compensatory measures) for this type of issue were instituted for the affected areas of the plant.

Some licensees have reported taking corrective actions for the circuits that might be susceptible

to this unanalyzed condition in order to remove the possibility of grounded fault-induced damage

in these circuits. At least one licensees corrective actions included planned modifications to

install fusing in the susceptible circuits to eliminate the potential for such events or damage.

Licensees are encouraged to review the information provided through this IN and review similar

industry internal operating experience, as appropriate. Lessons learned during NFPA 805 transition evaluations may also be useful for other sites to consider. Licensee extent of

condition reviews may be appropriate for other similar potential hot short concerns to help

ensure plant safety.

CONTACT

This IN requires no specific action or written response. Please direct any questions about this

matter to one of the technical contacts listed below or to the appropriate Office of Nuclear

Reactor Regulation or Office of New Reactors project manager.

/RA/ /RA/

Michael C. Cheok, Director Lawrence E. Kokajko, Director

Division of Construction Inspection Division of Policy and Rulemaking

and Operational Programs Office of Nuclear Reactor Regulation

Brian Metzger, NRR

301-415-3972 E-mail: brian.metzger@nrc.gov

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

ML14169A264

• via e-mail TAC MF4189 OFFICE NRR/DRA/AFPB Tech Editor QTE NRR/DRA NRR/DRA BC: RES/FRB

NAME Metzger JDougherty * DFrumkin AKlein MSalley*

DATE 06 / 26 /14 06 / 23 /14 08 / 14 /14 08 / 19 /14 08 / 18 /14 OFFICE NRO/DSRA/BPFP NRO/DSRA BC: LA:PGCB:NRR PM:PGCB:NRR BC:PGCB:NRR

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DATE 9 / 5 /14 9 / 9 / 14 9 / 16 / 14