Information Notice 1993-96, Improper Reset Causes Emergency Diesel Generator Failures

Improper Reset Causes Emergency Diesel Generator Failures

ML031060602
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
Issue date:	12/14/1993
From:	Grimes B Office of Nuclear Reactor Regulation
To:
References
IN-93-096, NUDOCS 9312080261
Download: ML031060602 (12)

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UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555 December 14, 1993 NRC INFORMATION NOTICE 93-96: IMPROPER RESET CAUSES EMERGENCY DIESEL

GENERATOR FAILURES

Addressees

All holders of operating licenses or construction permits for nuclear power

reactors.

-

Purpose

The U.S. Nuclear Regulatory Commission (NRC) is issuing this information

notice to alert addressees to the potential for an emergency diesel generator

(EDG) to fail to start on demand or to trip during operation due to improper

execution of the reset operation at the conclusion of the previous run. 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

H.B. Robinson

In August of 1987 at the H.B. Robinson plant, startup trips occurred on the

KA" EDG. With the assistance of a vendor representative, several steps were

taken in an effort to preclude such trips, including replacement of the

governor, replacement of the governor oil, replacement of sticky fuel

injection pumps, checking of injection pump timing, and rebalancing fuel rack

settings. In February of 1988, startup trips were again experienced. It was

concluded, after detailed inspection of the latch mechanism parts, that there

was a possibility of wear on the tip of the latch, which may have been a

contributing factor to the trips. These parts were replaced with new parts.

On June 3, 1992, during the performance of a test activity, the TAw EDG

tripped on mechanical overspeed after the engine had been operating

approximately one half hour. After detailed consideration of possible

scenarios for the trips and considering prior actions taken, it was determined

that the most probable cause was a failure to properly reset the trip

mechanism after the previous run. It was concluded that operations personnel

apparently were unaware of the importance of moving the reset lever through

its full travel. In addition, resettirg was difficult for shorter individuals

due to the location of the reset lever, which is positioned over the exhaust

9312080261 PbR ZtE N o cq; q 1s (tat

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<-N 93-96 December 14, 1993 manifold. Operations personnel were subsequently trained on the proper method

for actuating the reset lever. Also, a step was provided to permit easier

access to the lever.

Duane Arnold

On June 11, 1993, while the Duane Arnold plant was operating at 85 percent of

full power, the 'A" EDG tripped approximately 3 seconds after the initial

start signal during an operability surveillance test. An evaluation was

conducted by the licensee of possible EDG trip causes, including occurrence of

an actual overspeed condition, failure of the overspeed mechanism, actuation

of the emergency stop pushbutton, failure of the emergency stop pushbutton, latch assembly not fully latched, latch assembly failure, mechanical trip

mechanism failure, and annunciator circuit or trip lever microswitch failure.

It was concluded that the most probable cause of the trip was that the latch

--assembly was not fully engaged from the previous reset operation and engine

startup vibration unlatched the trip mechanism. Less than complete engagement

of the latch assembly could be caused by an inadequate reset operation.

Corrective actions adopted by the licensee included procedure revisions to

ensure a more positive latching operation, improved physical access to the

reset lever, and operator training.

The procedure revision directs operators to perform the reset operation a

second time following the initial resetting of the trip. The second reset is

somewhat easier to perform and should ensure that the latch is fully engaged

in the event that the initial latching sequence resulted in a partially

latched condition. Verification that the latch is fully seated is

accomplished by checking that the reset lever subsequently moves freely.

Discussion

In response to experience with previous trips during fast starts, the diesel

manufacturer for both plants, (Coltec/Fairbanks Morse Engine Division), had

previously issued a service information letter (SIL, Volume A, Issue 25, dated

August 1, 1991) addressing a revised overspeed trip adjustment. The SIL

recommended that the overspeed trip setting be raised from the range of 112 to

115 percent to the range of 115 to 117 percent. In light of events that

occurred at H.B. Robinson and Duane Arnold, the manufacturer has now advised

these licensees that proper resetting of the trip mechanism would be enhanced

by slowly moving the reset lever fully to the reset position and back, twice.

The inadvertent partial reset latching operations described above may also

occur on other units having similar mechanical trip mechanisms.

- IN 93-96 December 14, 1993 This notice requires no specific action or written response. If you have any

questions about the information in this notice, please contact one of the

technical contacts listed below or the appropriate Office of Nuclear Reactor

Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: Larry Garner, RII

(404) 331-4663 Chris G. Miller, RIII

(319) 851-5111 Walter P. Haass, NRR

(301) 504-3219 Attachment:

List of Recently Issued NRC Information Notices

Att'achment

IN 93-96 December 14, 1993 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

Storm-Related Loss of 12/13/93 All holders of OLs or CPs

Offsite Power Events for nuclear power reactors

due to Salt Buildup located close to a large

on Switchyard Insulators body of salt water.

Unauthorized Forced 12/09/93 All holders of OLs or CPs

Entry into the Pro- for nuclear power reactors.

tected Area at Three

Mile Island Unit 1 on

February 7, 1993

93-93 Inadequate Control of 12/08/93 All holders of OLs or CPs

Reactor Coolant System for nuclear power reactors.

Conditions During Shutdown

93-92 Plant Improvements to 12/07/93 All holders of OLs or CPs

Mitigate Common Depend- for nuclear power reactors.

encies in Component

Cooling Water Systems

91-21, Inadequate Quality 12/07/93 All holders of OLs or CPs

Supp. 1 Assurance Program of for nuclear power reactors

Vendor Supplying and all recipients of

Safety-Related Equipment NUREG-0040, license Con- tractor and Vendor Inspec- tion Status Report' (White

Book).

89-77, Debris in Containment 12/03/93 All holders of OLs or CPs

Supp. 1 Emergency Sumps and for nuclear power reactors.

Incorrect Screen

Configurations

93-91 Misadjustment Between 12/03/93 All holders of OLs or CPs

General Electric 4.16-KV for nuclear power reactors.

Circuit Breakers and Their

Associated Cubicles

. OL = Operating License

CP - Construction Permit

IN 93-96 December 14, 1993 This notice requires no specific action or written response. If you have any

questions about the information in this notice, please contact one of the

technical contacts listed below or the appropriate Office of Nuclear Reactor

Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: Larry Garner, RII

(404) 331-4663 Chris G. Miller, RIII

(319) 851-5111 Walter P. Haass, NRR

(301) 504-3219 Attachment:

List of Recently Issued NRC Information Notices

• SEE PREVIOUS CONCURRENCE

OFFICE VIB/DRIL* lREGION III* REGION II* VIB/DRIL* VIB/DRIL*

NAME WHaass CHiller LGarner UPotapovs LNorrholm

DATE 09/09/93 09/09/93 08/30/93 09/10/93 09/15/93 TECH ED* DRIL/NRR* EEKB/NRR* OGCB/DORS* 1C:OGCB/DORS* D: N

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IN 93-XX

December xx, 1993 This notice requires no specific action or written response. If you have any

questions about the information in this notice, please contact one of the

technical contacts listed below or the appropriate Office of Nuclear Reactor

Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: Larry Garner, RII

(404) 331-4663 Chris G. Miller, RIII

(319) 851-5111 Walter P. Haass, NRR

(301) 504-3219 Attachment:

List of Recently Issued NRC Information Notices

• SEE PREVIOUS CONCURRENCE

OFFICE

NAME

DATE

VIB/DRIL*

WHaass

09/09/93 REGION III*

CMiller

09/09/93 REGION II*

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08/30/93 IVIB/DRIL*

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IN 93-XX

November xx, 1993 This notice requires no specific action or written response. If you have any

questions about the information in this notice, please contact one of the

technical contacts listed below or the appropriate Office of Nuclear Reactor

Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: Larry Garner, RII

(404) 331-4663 Chris G. Miller, RIII

(319) 851-5111 Walter P. Haass, NRR

(301) 504-3219 Attachment:

List of Recently Issued NRC Information Notices

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• SEE PREVIOUS CONCURRENCE .1, OFFICE VIB/DRIL* REGION I* REGION II* VIB/DRIL* VIB/DRIL*

NAME WHaass CMiller LGarner UPotapovs LNorrholm

DATE 09/09/93 109/09/93 08/30/93 09/10/93 9/15/93 TECH ED* DRIL/NRR* EEKB/NRR* OGCB/DORS* C:OGCB/DORS D:DORS/NRR

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IN 93-XX

October xx, 1993 This notice requires no specific action or written response. If you have any

questions about the information in this notice, please contact one of the

technical contacts listed below or the appropriate Office of Nuclear Reactor

Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: Larry Garner, R11

(404) 331-4663 Chris G. Miller, RIII

(319) 851-5111 Walter P. Haass, NRR

(301) 504-3219 Attachment:

1. List of Recently Issued Information Notices

• SEE PREVIOUS CONCURRENCE

OFFICE VIB/DRIL* REGIONX* REGION II* VIB/DRIL* VIB/DRIL*

NAME WHaass CMiller LGarner UPotapovs LNorrholm

DATE 09/09/93 09/09/93 08/30/93 09/10/93 09/15/93 TECH ED* DRIL/NRR* l EEKB/NRR* lOGCB/DORS C:OGCB/DORS D:DORS/NRR

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IN 93-XX

October xx, 1993 This notice requires no specific action or written response. If you have any

questions about the information in this notice, please contact one of the

technical contacts listed below or the appropriate Office of Nuclear Reactor

Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: Larry Garner, RII

(404) 331-4663 Chris G. Miller, RIII

(319) 851-5111 Walter P. Haass, NRR

(301) 504-3219 Attachment:

1. List of Recently Issued Information Notices

• SEE PREVIOUS CONCURRENCE

OFFICE VIB/DRIL* REGION I* REGION II* VIB/DRIL* VIB/DRIL*

NAME WHaass CMiller LGarner UPotapovs LNorrholm

DATE 09/09/93 09/09/93 08/30/93 1 09/10/93 09/15/93 TECH ED* DRIL/NRR* JEEKB/NROM OGCB/DORS C:OGCB/DORS D:DORS/NRR

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09/14/93 09/20/93 10/13/93 10/ /93 10/ /93 10/ /93

OFFICIAL RECORD COPY

DOCUMENT NAME: INEDGST.wen

IN 93-XX

October xx, 1993 Discussion

The staff is continuing its review of the above events with the manufacturer

of the diesel engines, Coltec/Fairbanks Morse Engine Division, to arrive at a

more detailed and consistent set of procedures to assure a positive latching

operation. In addition, it should be noted that other diesel engine

manufacturers may have similar mechanical trip mechanisms, and licensees

should be aware that potential inadvertent partial reset latching operations

may also occur on those units.

This notice requires no specific action or written response. If you have any

questions about the information in this notice, please contact one of the

technical contacts listed below or the appropriate Office of Nuclear Reactor

Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: Chris G. Miller, RI at Duane Arnold

(319) 851-5111 Larry Garner, R11

(404) 331-4663 Walter P. Haass, NRR

(301) 504-3219 Attachment:

1. List of Recently Issued Information Notices

• SEE PREVIOUS CONCURRENCE

OFFICE VIB/DRIL REGION I REGION II VIB/DRIL VI5/YOL

NAME WHaass CMiller LGarner UPotapovs 1; R holm

DATE 9 / 9/93* 9/9/93* 8/30/93* 9/10/93* l C//) /93 COPY YES NO YES NO YES NO YES NO 6 NO

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October xx, 1993 Page.4 of 3 Attachment:

1. List of Recently Issued Information Notices

• SEE PREVIOUS CONCURRENCE

OFFICE VIB/DRIL REGION I REGION II VIB/DRIL VIB/DRIL

NAME WHaass CMiller LGarner UPotapovs LNorrholm

DATE 9 / 9/93* 9/9/93* 8/30/93* 9/10/93* / /93 COPY YES NO YES NO YES NO YES NO YES NO

DOC

OFFICE TECH EDITOR DRIL/NRR OGCB/NRR EELB/NRR DORS/NRR

NAME a 44, CERossi GMarcus CBerlinger BGrimes

DATE 7 / 9 / /93 / /93 / /93 / /93 COPY YES NO YES NO YES NO YES NO YES NO

DOC

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OFFICIAL RECORD COPY Document Name: G:\INEDGST

IN 93-XX

October xx, 1993 Discussion

The staff is continuing its review of the above events with the manufacturer

of the diesel engines, Coltec/Fairbanks Morse Engine Division, to arrive at a

more detailed and consistent set of procedures to assure a positive latching

operation. In addition, it should be noted that other diesel engine

manufacturers may have similar mechanical trip mechanisms, and licensees

should be aware that potential inadvertent partial reset latching operations

may also occur on those units.

This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: Chris G. Miller, RI at Duane Arnold

(319) 851-5111 Larry Garner, RII

(404) 331-4663 Walter P. Haass, NRR

(301) 504-3219 a.?

Attachment:

1. List of Recently Issued Information Notices ' 1-eCL

OFFICE VIBDRIL E VIBD VIB/DRIL

NAME WHaass F 4It _f arneamfil r A UPot V LNorrholm

DATE 9/?9//93

9/93 93 / /93 93/ /93 COPY Y NO E NO Y NO YE NO YES NO

D o c_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

OFFICE DRIL/NRR OGCB/NRR EELB/NRR DORS/NRR

NAME CERossi GMarcus CBerlinger BGrimes

DATE I /93 I /93 I /93 I /93 COPY YES NO YES NO YES NO YES NO

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