05000361/LER-2006-003, Regarding Potential Emergency Diesel Generator Trip After a Seismic Event Due to an Electrical Ground Fault in a Non-Seismic Circuit

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Regarding Potential Emergency Diesel Generator Trip After a Seismic Event Due to an Electrical Ground Fault in a Non-Seismic Circuit
ML062710386
Person / Time
Site: San Onofre 
Issue date: 09/18/2006
From: Breig D
Southern California Edison Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 06-003-00
Download: ML062710386 (5)


LER-2006-003, Regarding Potential Emergency Diesel Generator Trip After a Seismic Event Due to an Electrical Ground Fault in a Non-Seismic Circuit
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)

10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
3612006003R00 - NRC Website

text

DT SOUTHERN CALIFORNIA Li EDISON An EDISON INTERNATIONAL% Company Daniel P. Breig, P.E.

Station Manager San Onofre September 18, 2006 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001

Subject:

Docket No. 50-361 Licensee Event Report No. 2006-003 San Onofre Nuclear Generating Station, Unit 2

Dear Sir or Madam:

This submittal provides Licensee Event Report (LER) 2006-003 for a potential Emergency Diesel Generator trip after a seismic event due to an electrical ground fault in a non-seismic load. This event did not affect the health and safety of either plant personnel or the public.

If you require any additional information, please contact me.

Sincerely, Unit 2 LER No. 2006-003 cc:

B. S. Mallett, NRC Regional Administrator, Region IV C. C. Osterholtz, NRC Senior Resident Inspector, San Onofre Units 2 & 3 P.O. Box 128 San Clemente, CA 92674-0128 949-368-9263/PAX 89263 Fax 949-368-6183 breigdp@songs.sce.com 7ýCC2ý__

Abstract

In January 2005, SCE recognized that a ground fault on a non-I E 4 kV circuit on the primary side of a non-1 E transformer would not trip the 1 E breaker to isolate the non-I E circuit from the emergency diesel generator (EDG). This could have resulted in the "A" train EDG tripping after an event that resulted in a ground fault on the non-1 E circuit. At that time, SCE focused on the potential for fire to cause a ground on the non-I E circuitry and did not fully consider seismically-induced faults.

In July 2006, the NRC questioned if a seismic event could also have caused a fault in the non-1 E circuitry.

SCE's reevaluation concluded that if a seismic event had occurred followed by a loss of offsite power and a ground fault on the primary side of the non-1 E transformer, the "A" train EDG could have been tripped. If this occurred during an EDG "B" train outage, both EDG trains would have been unavailable. At times in the past and as allowed by the Technical Specifications, SCE has removed "B" train EDGs from service.

Therefore, SCE is reporting this past condition under 1 OCFR50.73(a)(2)(b)(A) and (B).

A modification installed in 2005 corrected this condition. The safety significance of this occurrence is minimal because the affected circuit is bypassed during SIAS-related events and SONGS is able to crosstie the EDGs between Units 2 and 3 to access the available "B" train EDG.U.S. NUCLEAR REGULATORY COMMISSION (7-2001)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION

6. LER NUMBER PAGE (3)

YEAR SEQUENTIAL REV NO INUMBER I

2 of San Onofre Nuclear Generating Station (SONGS) Unit 2 06000361 100

- 003BE RE NO2f 1

2006

- 003 -

00 Plant:

San Onofre Nuclear Generating Station (SONGS) Unit 2 Discovery Date:

July 20, 2006 Reactor Vendor:

Combustion Engineering Mode:

Mode I - Power Operation Power:

99 percent

Description of Event

San Onofre Units 2 and 3 each have two emergency diesel generators (EDGs) [EK] to provide emergency AC power if preferred (offsite) AC power is unavailable. The "A" train EDGs provide standby power directly to safety related (1 E) and one non-safety related (non-I E) 4 kV transformer; whereas, the "B" train EDGs supply standby power directly only to 1 E-4kV loads. Consistent with NRC Regulatory Guide (RG) 1.75, "Physical Independence of Electric Systems," the "A" train EDGs are protected by a 1 E isolation breaker [BKR] and a non-1 E transformer [XFMR]. The 1 E breaker isolates the non-1 E loads from the EDG if there is a phase-to-phase fault in the non-1 E circuitry.

The non-1 E transformer isolates the non-i E loads from the EDG if there is a ground fault on the secondary side of the transformer. See the attached drawing.

In addition, each EDG is protected by a high impedance stator ground detection relay, which will trip the EDG if a ground fault occurs in a connected load. The ground fault protective trip is blocked during postulated accidents that result in a Safety Injection Actuation Signal (SIAS) but not blocked for non-SIAS (e.g. seismic) events.

In January 2005, SCE recognized that a ground fault on the non-i E 4 kV circuit on the primary side of the non-I E transformer would not trip the 1 E isolation breaker to isolate the non-I E circuit from the emergency diesel generator (EDG). Therefore, if there was a loss of offsite power with no SIAS and a coincidental or resulting ground in the non-1 E circuitry on the primary side of the transformer, the "A" train EDGs could be tripped by the ground detection device before the 1 E isolation breaker could isolate the EDG from the faulted non-I E circuit.

Upon discovering this condition in 2005, SCE focused on the potential for fire to cause a ground on the non-I E circuitry on the primary side of the transformer. SCE's evaluation determined that the fire scenario would not prevent the EDG from performing its safety function. Because this condition represented a degradation of measures taken to minimize the potential for and effects of fires, SCE completed a design modification (in April 2005 for Unit 2 and May 2005 for Unit 3), to ensure that the ground protection device would not trip the EDG prior to the I E isolation breaker operating if there was a fault on the non-I E circuit.

In 2005, SCE determined this condition was not reportable because the EDG was found capable of performing its safety function.

In July 2006, during a NRC Component Design Basis Inspection (CDBI), the NRC questioned if SCE had evaluated whether a seismic event could also cause a fault in the same non-i E circuitry and, if so, if that condition would require a report to the NRC. SCE determined that the 2005 EDG design modifications would prevent the "A" train EDG from tripping on a seismically-induced ground fault on the non-1 E circuit. However, the operability evaluation performed in 2005 did not document an analysis of seismic events that could have prevented the "A" train EDG from performing its function prior to installation of the design modifications.U.S. NUCLEAR REGULATORY COMMISSION (7-2001)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION

1. FACIUTY NAME
2. DOCKET NUMBER
6. LER NUMBER PAGE (3)

YEAR SEQUENTIAL 1 REV NO 003 NUMBER 3

San Onofre Nuclear Generating Station (SONGS) Unit 2 05000361 2006

- 003I-00 If a seismic event had occurred followed by a loss of offsite power and a ground fault on the primary side of the non-I E transformer, it is possible the "A" train EDG could have been tripped. If this had occurred during an EDG "B" train outage, both EDG trains would have been unavailable to perform their required safety function. At times in the past, a "B" train EDG has been taken out of service for planned work as allowed by the Technical Specifications. Based on the guidance provided in NRC NUREG-1 022, on July 20, 2006 (discovery date), SCE concluded this past condition is reportable in accordance with 10CFR50.73(a)(2)(v)(A) and (B), as an event or condition that could have prevented fulfillment of a safety function required to maintain the reactor in a safe shutdown condition and to remove residual heat.

Cause of Event

In 1983, SCE modified the original design to attach a non-i E circuit to a 1 E bus. At that time the 1 E isolation breaker was installed consistent with RG 1.75 requirements. However, it was not realized that the ground fault protective trip on the EDG was faster than the I E isolation breaker. Due to the passage of time, it is not clear why this design did not preclude this condition.

Corrective Actions

In 2005, the EDG stator ground protection scheme was modified to immediately isolate the non-I E circuit when a line-to-ground fault is detected and to add a 5-second delay to the EDG ground fault protective trip. If the fault is cleared within 5 seconds of isolation of the non-iE circuit, the stator ground relay will reset and the EDG will not trip. If the fault has not cleared after 5 seconds, the EDG will trip. This change provides sufficient time for the existing non-i E circuit to separate from the I E bus without affecting the EDG.

A cause evaluation is in progress to determine why a seismic event evaluation was not formally documented when evaluating the potential causes of a fault in the non-1 E circuits. Additional corrective actions may be identified and implemented.

Safety Significance

The safety significance of this past condition is minimal. The Train "B" EDGs were unaffected by this condition. The EDGs are required to function following SIAS and non-SIAS events.

1. Following SIAS events, the EDGs are required to start and load within 10 seconds. A SIAS blocks the protective EDG trip and disconnects non-I E loads from the safety-related buses.

Therefore, even before the 2005 design modifications, a fire or seismically induced ground fault on the non-I E circuit would not have prevented the "A" train EDGs from performing their required safety functions. For SIAS events, there is no safety significance to this condition.

2. Following a non-SIAS event, it is possible that if a seismic event had occurred followed by a loss of offsite power and a ground fault on the primary side of the non-i E transformer, the "A" train EDGs could have been tripped. SCE performed a probabilistic risk assessment and demonstrated that the safety significance of this condition is minimal (increase in core damage frequency of 1 E-7/year and increase in large early release frequency of less than 1 E-8/year) due to the low probability of this scenario, the robustness of the non-1 E cable and windings on the primary side of the transformer, and the capability of using the crosstie between Units 2 and 3 to access the available "B" train EDG.U.S. NUCLEAR REGULATORY COMMISSION (7-2001)

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6. LER NUMBER YE I

SEQUEBNETIAL San Onofre Nuclear Generating Station (SONGS) Unit 2 05000361 YEEU ENUIA

Additional Information

SCE previously reported instances of inadequate separation of 1 E and non-1 E circuits in LERs 2000-002 and 1999-005.

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