Information Notice 1989-15, Second Reactor Coolant Pump Shaft Failure at Crystal River

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Second Reactor Coolant Pump Shaft Failure at Crystal River
ML031180526
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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant
Issue date: 02/16/1989
From: Rossi C
Office of Nuclear Reactor Regulation
To:
References
IN-89-015, NUDOCS 8902100265
Download: ML031180526 (9)
v • d • e


UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555 February 16, 1989 INFORMATION NOTICE NO. 89-15: SECOND REACTOR COOLANT PUMP SHAFT FAILURE AT

CRYSTAL RIVER

Addressees

All holders of operating licenses or construction permits for nuclear power

reactors.

purpose:

This information notice is being provided to alert addressees to indications of

potential sudden failure of a reactor coolant pump (RCP) shaft. It is expected

that recipients will review the information for applicability to their facil- ities and consider actions, as appropriate, to avoid similar problems. However,,

suggestions contained in this information notice do not constitute NRC require- ments; therefore, no specific action or written response is required.

Description of Circumstances

On January 18, 1989, the Crystal River Unit 3 plant experienced a loop 'Al low

coolant flow alarm and an automatic power runback from 75 percent of full power

to 64 percent of full power. Operators noted a drop in the "A" reactor coolant

pump motor current from 90 percent to 25 percent.

A preliminary review of the vibration and other coastdown data suggests that

the pump shaft and the impeller have decoupled. This may be due either to

fracture of the shaft itself or to failure of the cap screws and drive pins

which hold the impeller to the shaft. The root cause of the failure will be

more fully known when the pump is disassembled. The pump was manufactured by

Byron Jackson.

Both the low flow alarm and motor current decreases were also symptomatic of

the previous pump shaft failure in 1986.* During the 1986 event, pump vibration

remained high after the shaft break, indicating interference to motor spin at

the fracture interface, and after the pump was tripped, the pump motor rotation

stopped within a few seconds. The licensee believes that the lack of pump vi- bration and the longer post trip motor coastdown after the recent pump failure

indicate a lack of interference at the fracture interface.

Pump Shaft-Fe1-1urewat Crystal River."

(< 8902100265 Z# J if-i/C-

.

IN 89-15 February 16, 1989 Following the 1986 pump shaft failure, the licensee replaced the shafts in

all four coolant pumps. Two of the reactor coolant pumps received new shafts

of a different material (Alloy A-479 XM-19) and a different design. The

new

design did not contain the groove that was determined to be the crack initiation

location for the 1986 fracture. One pump was fitted with a new shaft of the

same material as that of the shaft that failed (Alloy A-286), but the licensee

believes the new shaft did not contain a groove. The "A" pump was fitted

a new shaft of the same design and material as that of the shaft that had with

previously. failed

In addition, following the 1986 failure, the licensee refurbished and improved

the vibration monitoring equipment on each coolant pump and located vibration

monitor alarms on the main control panel. The reactor coolant pump vibration

is continuously monitored by the Bently-Nevada Dynamic Data Manager System.

This system monitors the motor casing accelerometer inputs along with the

pump shaft proximity probes (X & Y, Keyphasor) on all four reactor coolant

pumps.

Increased vibration on the HA" RCP was noted in November 1988. A

the vibration monitoring data revealed a loss of rotor'stiffness.' review

The

of

vibration monitor vendor (Bently-Nevada) believed that the pump'shaft had

cracked. The licensee examined the "A" RCP shaft with ultrasonic testing

equipment and concluded that the shaft had not cracked. Cracks In the lower

motor housing support were identified and corrected. After repair of the

lower motor housingsupport, the licensee reported normalpump vibration.

However, pump vibrations of varying magnitudes were again noted shortly

thereafter.

The ultimate objective of the vibration monitoring system is to correlate

vibration data with crack growth and to provide an early' warning such that the

a

shaft break can be avoided. The program depends on an early detection of shifts

in steady state values of maximum shaft displacement, first-and second harmonics

and corresponding phase angles. Since shifts in the second harmonic and its

phase angle are sensitive indicators of changes in shaft stiffness and crack

growth, particular attention to these parameters is important.

Additional RCP shaft failures are discussed in Information Notice 85-03,

'Separation of Primary Reactor Coolant Pump Shaft and Impeller," and its

supplement.

IN 89-15 February 16, 1989 No specific action or written response is required by this information notice.

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

contacts 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 Contacts: Jai Rajan, NRR

(301) 492-0917 Walton Jensen, NRR

(301) 492-1190

Attachment: List of Recently Issued NRC Information Notices

Attachment

II 89-15 February 16. 1989 Page 1 of I

LIST OFRECENTLY ISSUED

NRC INFORUATION NOTICES

Infoeuatlon Date of

Notice No. Subject Issuance Issued to

89-14 -Inadequate Dedication 2/16/89 All holders of OLs

Process for Comeercial or CPs for nuclear

grade Cimponents Which power reactors.

Could Lead to Comon Node

Failure of a Safety System

89-I3 Alternative waste Management 2/6/89 All holders of PRC

Procedures ln Case of Denial specific licenses.

of Access to Low-Level Waste

Disposal Sites

89-12 Dose Calibrator Quality 2/9/39 All NRCmedical

Control licensees.

89-11 Failure of DCMotor-Operated 2/2/89 All holders of OLs

Valves to Develop Rated or CPs for nuclear

Torque Because of Improper power reactors.

Cable Sizing

89-10 Undetected Installation 1/27/89 All holders of OLs

Errors In Main Steam Line or CPs for BWRs.

Pipe Tunnel Differential

Temperature-Sensing Elements

at Boiling Water Reactors.

89-09 Credit for Control Rods 1/26/89 All holders of OLs

Without Scram Capability or CPs for test and

in the Calculation of the research reactors.

Shutdown Margin

89-08 Pump Damage Caused by 1/26/89 All holders of OLs

Low-Flow Operation or CPs for nuclear

power reactors.

89-07 Failures of Small-Diameter 1/25/89 All holders of OLs

Tubing in Control Air, Fuel or CPs for nuclear

Oil. and Lube Oil Systems power reactors.

Which Render Emergency Diesel

Generators Inoperable

Operating License

Construction Permit

IN 89-15 February 16, 1989 No specific action or written response is required by this information notice.

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

contacts 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 Contacts: Jai Rajan, NRR

(301) 492-0917 Walton Jensen, NRR

(301) 492-1190

Attachment: List of Recently Issued NRC Information Notices

  • SEE PREVIOUS PAGE FOR CONCURRENCE
  • EAB: NRR *EAB:NRR *TECH: ED *NRR:EMEB *NRR:EMEB NRR:DEST

WJensen:Db RLobel JRajan TMarsh LShao

2/2/89 2/2/89 2/3/89 2/3/89 2/3/89 2/ /89 C:EAB:NRR *C:OGCB:NRR

WDLanning CHBer1inger

2/ /89 2/8/89 2116Y89

IN 89-xx

February , 1989 Page 3 of

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

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

contacts 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 Contacts: Jai Rajan, NRR

(301) 492-0917 Walton Jensen, NRR

(301) 492-1190

Attachment: List of Recently Issued NRC Information Notices

  • SEE PREVIOUS PAGE FOR CONCURRENCE
  • EAB:NRR *EAB:NRR I'TECH:ED *NRR:EMEB *NRR:EMEB ' NRR:DEST

WJensen:Db RLobel JRajan TMarsh LShao

2/2/89 x2/3/89 2/3/89 2/3/89 2/6 /89

  • C:OGCB:NRR D:DOEA:NRR

CHBerlinger CERossi

2/8/89 2/ /89

IN 86-19, Supplement 1 February , 1989 Page 3 of

The ultimate objective of the vibration monitoring system is to correlate the

vibration data with crack growth and to provide an early warning such that a

shaft break can be avoided. The program depends on an early detection of shifts

in steady state values of maximum shaft displacement, 1X, 2X harmonics and

corresponding phase angles. Of the above parameters, particular attention

should be given to any shifts in the 2X harmonic and its phase angle. These

parameters are most sensitive to changes in the shaft stiffness and crack growth.

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

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

contacts 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 Contacts: Jai Rajan, NRR

(301) 492-0917 Walton Jensen, NRR

(301) 492-1190

Attachment: List of Recently Issued NRC Information Notices

  • SEE PREVIOUS PAGE FOR CONCURRENCE
  • EAB:NRR *EAB:NRR *TECH:ED *NRR:EMEB *NRR:EMEB NRR:DEST

WJensen:Db RLobel JRajan TMarsh LShao

2/2/89 '/3189

2/2/aS 2/3/89 2/3/89 2/ /89 C:EAB:NRR C:OGCB:NRR D:DOEA:hRR

WDLanning CHBerlinger CERossi

2/ /89 2/8S/89 2/ /89

IN 86-19, Supplement 1 February , 1989 Page 3 of

The ultimate objective of the vibration monitoring system is to correlate the

vibration data with crack growth and to provide an early warning such that a

shaft break can be avoided. The program depends on an early detection of shifts

in steady state valves of maximum shaft displacement, 1X, 2X harmonics and

corresponding phase angles. Of the above parameters, particular attention

should be given to any shifts in the 2X harmonic and its phase angle. These

parameters are most sensitive to changes in the shaft stiffness and crack growth.

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

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

contacts 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 Contacts: Jai Rajan, NRR

(301) 492-0917 Walton Jensen, NRR

(301) 492-1190

Attachment: List of Recently Issued NRC Information Notices

  • SEE PREVIOUS PAGE FOR CONCURRENCE
  • EAB: NRR *EAB:NRR 1"TECH:ED *NRR:EMEB *NRR:EMEB R:DEST

WJensen:Db RLobel JRaJan TMarsh (7 LSho

2/2/89 2/3/89 2/3/89 2/3/89 1 2/6/89 C:EA! SR C:OGCB:NRR D:DOEA:NRR

WDLanning CHBerlinger CERossi

2/1/89 2/ /89 2/ /89

IN 86-19, Supplement 1 February ., 1989 No specific action or written response is required by this information notice.

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

contacts 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 Contacts: Jai Rajan, NRR

(301) 492-0917 Walton Jensen, NRR

(301) 492-1190

Attachment: List of Recently Issued NRC Information Notices

-y- EAB:NRR EAB:NRR 1'ECM:ED NRRR EW NRR:EMEB NRR:DEST

WJensen:Db RLobel JRajax TMarsh LShao

/ /89 / /89 / /89  ;/ 3/89 2/3 /89 / /89 C:EAB:NRR C:OGCB:NRR D:DOEA:NRR

WDLanning CHBerlinger CERossi

/ /89 / /89 / /89

5 e (> (dOirCg U r trf LP

I

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 Contacts: Jai Rajan, NRR

(301) 492-0917 Walton Jensen, NRR

(301) 492-1190

Attachment: List of Recently Issued NRC Information Notices

EAB: R

t-,N R TECH:ED NRR:EMEB NRR: EMEB NRR:DEST

s ~en :Db RLHo e / I U V JRajan TMarsh LShao

2 /2 /89 Z-/L,/89 -A/3/89 / /89 / /89 / /89 C:EAB:NRR C:OGCB:NRR D:DOEA:NRR

WDLanning CHBerlinger CERossi

/ /89 / /89 / /89


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