Information Notice 1988-59, Main Steam Isolation Valve Guide Rail Failure at Waterford Unit 3

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Main Steam Isolation Valve Guide Rail Failure at Waterford Unit 3
ML031150013
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, 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, Crane
Issue date: 08/09/1988
From: Rossi C
Office of Nuclear Reactor Regulation
To:
References
IN-88-059, NUDOCS 8808030112
Download: ML031150013 (8)


UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C.

20555

August 9, 1988

NRC INFORMATION NOTICE NO. 88-59:

MAIN STEAM ISOLATION VALVE GUIDE RAIL

FAILURE AT WATERFORD UNIT 3

Addressees

All holders of operating licenses or construction permits for nuclear power

reactors.

Purpose

This information notice discusses a main steam isolation valve (MSIV) guide

rail failure at Waterford 3 and its possible generic implications. The MSIV

is a D-2 Power Seal type, manufactured by ACF Industries, WKM Valve Division.

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 do not

constitute NRC requirements; therefore, no specific action or written response

is required.

Description of Circumstances

On April 11,

1988, during a routine inspection at Waterford 3, MSIV debris was

found in the strainer for the main turbine throttle valve. The disassembly and

inspection of the two MSIVs at the plant revealed that the downstream guide

rails in one of the valves (see attached drawing) had become completely dis- lodged, and several bolt heads on the still-attached upstream rails in the same

valve had been completely severed. The other MSIV had several separated bolt

heads on both upstream and downstream rails, but the guide rails were in place.

There were also galling marks on the chamfer of the guide rail and on the shoe

attached to the lever lock arm.

Discussion:

An analysis by the licensee indicates that the guide rail failure was caused by

the force of the lever lock arm assembly contacting the rail.

The valve, however, passed the inservice test requirements.

The analysis concludes that

even without the rails the valve could still perform its function, albeit at a

closure time that is slower by about a second, under the worst-case condition.

However, there is a possibility that a detached rail could jam the MSIV in a

partially open position. The failure of one MSIV is accounted for in the

utility's Safety Analysis Report.

8808030112 ZA

IN 88-59 August 9, 1988 After the failure at Waterford 3, a fiberscope examination of the WKM power

seal MSIVs at San Onofre Unit 3 revealed a broken bolt lying in the bottom

section of the body of one MSIV. Disassembly and inspection of this valve

revealed three failed bolts, galling marks on the shoe and the chamfer, and

an upstream rail slightly detached from the skirt plate.

At the same plant, a shutdown cooling isolation valve of a similar design was also damaged.

How- ever, the licensee believes that this damage occurred during maintenance. The

damage was similar to that found on the MSIVs, that is, galling marks, failed

bolts, and detached rails, but, in addition, the skirt plate was fractured and

the shoe was wedged into the lever arm pivot slot.

The NRC believes this type of failure could be generic to other plants.

Valves

of this type are also reported to be in use at San Onofre 2, South Texas 1 and 2, and Washington Nuclear Power Unit 2. Valves of similar design could exist at

other plants.

The preliminary indications suggest that the failures are

attributable to deficiencies in fabrication, engineering, and materials. The

corrective actions considered at Waterford and San Onofre 3 include

(1) stelliting the shoes and the chamfer on the rails

(2) verifying the bolt alignments

_doingnondestructive examinations of all new bolts

__ _ _ _-1--

'

.

t

-.-------

-

-. ,

__ ._

__ ___ __

(4) changing the angles of the rails and of the shoes

(5) increasing the valve closure time (within system performance constraints)

(6) periodically making fiberscope examinations of the valve internals

to detect excessive galling, severed guide rail bolts, and separated

guide ra'ls

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 Contact:

Kenneth Dempsey, NRR

(301) 492-0918 Attachments:

1. Figure of Valve

2. List of Recently Issued NRC Information Notices

Attachment

IN 88-59 August 9, Page I of

1988

GATE S SEGMENT

ASSEMBLY

GUIDE RAIL BOLT

LOCATIONS (9 PER

GUIDE RAIL).

TYPICAI

OF 4 GUIDE RAILS

1-'

Atti

nt

2 in 88-59

August 9. 1988

Page 1 of I

LIST oF RECEaIMT ISSUED

NRC INFOidATION NOTICES

_AA---

n-.-

rreson"At1nr

iaiWowb

Notice No.

88-57 de-Sd

88-55

88-54

88-52 SubJect

Potential Problems with

AScA 8rown toverl ITE-s1L

Time-Overcurrent Relays

Potential Loss of Safe

Shutdown Equipment Due to

Preesture Silicon Controlled

Rectifier Failure

Potential Problems with

Silicone Foas Fire Barrier

Penetration Seals

Potential Problem Caused

by Single Failure of an

Engineered Safety Feature

Swing tus

Failure of Circuit Breaker

Following Installation of

Amptector Direct Trip

AttacJment

Licensee Violations of NRC

Regulations, Which Led to

ledical Diagnostic

Misadvinistrations

Failure of Intrauterine

Tandem of Fletcher

Applicator Irachytherapy

Deuces During Patient

Treatment

UtU UT

Issuance

8/8/88

8/3/88

8/4/88 WM/8

7/28/88

7/28/88

7/27/88 Issued to

All holders of uLs

or CPs for nuclear

power reactors.

All holders of OLs

or CPs for nuclear

power reactors.

All holders of OLs

or CPs for nuclear

power reactors.

All holders of OLs

or CPS for nuclear

power reactors.

All holders of OLs

or CPS for nuclear

power reactors.

All manufacture

and

distributors of radio- pharmaceuticals for

hum use. nuclear

pharmacies, and

medical licensees.

Medical licensees.

81-46. --

ticense- Report of

-

Supplement 1

Cefective Refurbished

Circuit Breakers

- 7/26/88-

-

All hol40dsof-Ls

or CPs for nuclear

power reactors.

OL

  • Op rating License

CP

  • Construction Permit

UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D.C. 20555

OFFICIAL BUSINESS

PENALTY FOR PRIVATE USE. $300

FIRST CLSSMAIL1

IPOSTAGE & FEES PAIDI

IUSNRCI

IN 88-59 August 9, 1988 After the failure at Waterford 3, a fiberscope examination of the WKM power

seal MSIVs at San Onofre Unit 3 revealed a broken bolt lying in the bottom

section of the body of one MSIV. Disassembly and inspection of this valve

revealed three failed bolts, galling marks on the shoe and the chamfer, and

an upstream rail slightly detached from the skirt plate. At the same plant, a shutdown cooling isolation valve of a similar design was also damaged.

How- ever, the licensee believes that this damage occurred during maintenance. The

damage was similar to that found on the MSIVs, that is, galling marks, failed

bolts, and detached rails, but, in addition, the skirt plate was fractured and

the shoe was wedged into the lever arm pivot slot.

The NRC believes this type of failure could be generic to other plants.

Valves

of this type are also reported to be in use at San Onofre 2, South Texas 1 and 2, and Washington Nuclear Power Unit 2. Valves of similar design could exist at

other plants. The preliminary indications suggest that the failures are

attributable to deficiencies in fabrication, engineering, and materials. The

corrective actions considered at Waterford and San Onofre 3 include

(1) stelliting the shoes and the chamfer on the rails

(2) verifying the bolt alignments

(3) doing nondestructive examinations of all new bolts

(4) changing the angles of the rails and of the shoes

(5) increasing the valve closure time (within system performance constraints)

(6) periodically making fiberscope examinations of the valve internals

to detect excessive galling, severed guide rail bolts, and separated

guide rails

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 Contact:

Kenneth Dempsey, NRR

(301) 492-0918 Attachments:

1. Figure of Valve

2. List of Recently Issued NRC Information Notices

  • SEE PREVIOUS CONCURRENCES
  • C/OGCB:DOEA:NRR *RPB:ARM

Rossi i

CHBerlinger

TechEd

08/3 /88

08/01/88

07/27/88

  • OGCB:DOEA:NRR *EMEB:DEST:NRR *C/EMEB:DEST:NRR
  • EAD/DEST:NRR
  • D/DEST:NRR

DCKirkpatrick KDempsey

LBMarsh

JRichardson

LCShao

07/26/88

07/28/88

07/29/88

07/29/88

07/29/88

IN 88-XX

July xx, 1988 After the failure at Waterford 3, a fiberscope examination of the WKM power

seal MSIVs at San Onofre Unit 3 revealed a broken bolt lying in the bottom

section of the body of one MSIV. Disassembly and inspection of this valve

revealed three failed bolts, galling marks on the shoe and the chamfer, and an

upstream rail slightly detached from the skirt plate.

At the same plant, a

shutdown cooling isolation valve of a similar design was also damaged.

How- ever, the licensee believes that this damage occurred during maintenance.

The

damage was similar to that found on the MSIVs, that is, galling marks, failed

bolts, and detached rails, but, in addition, the skirt plate was fractured and

the shoe was wedged into the lever arm pivot slot.

NRC believes this type of failure to be generic to other plants.

Valves of

this type are also reported to be in use at San Onofre 2, South Texas 1 and 2, and Washington Nuclear Power Unit 2. Valves of similar design could exist at

other plants. The preliminary indications suggest that the failures are

attributable to deficiencies in fabrication, engineering, and materials.

The

corrective actions considered at Waterford and San Onofre 3 include

(1) stelliting the shoes and the chamfer on the rails

(2) verifying the bolt alignments

(3) doing nondestructive examinations of all new bolts

(4) changing the angles of the rails and of the shoes

(5) increasing the valve closure time (within system constraints)

(6) periodically making fiberscope examinations of the valve internals to

detect excessive galling, severed guide rail bolts, and separated

guide rails

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 Contact:

Kenneth Dempsey, NRR

(301) 492-0918 Attachments:

1. Figure

2. List of Recently Issued NRC Information Notices

  • SEE PREVIOUS CONCURRENCES

C021 D/DOEA:NRR

C/OGCB:DOEA:NRR

  • RPB:ARM

CERossi

CVBerlinger

TechEd

07/ /88

0 6) /88

07/27/fM'tA

  • OGCB:DOEA:NRR EMEB4REST:NRR C/EMEB:DEST:NRR

EAD/DEST:

D/DES

h

DCKirkpatrick KD f y

LBMarsh

JRichards nr/zn LCShao

07/26/88

07/..2/88 v j

7/88

07/J '/88

07, /88

IN 88-XX

July xx, 1988 Subsequent-to the failure at Waterford 3, a fiberscope examination of the WKM

h

power seal MSIVsit

-an

Onofre9Jnit 3 revealed a roken bolt lying in the

bottom section of the body of one MSIV. 4umiang/i assembly and inspection of

-was-foUlU-te-hes

e three failed bt5, galling marks on the shoe

and the c imfer, and an upstream rail slightly detached from the skirt plate.

At the same plant, a shutdown cooltng isolation valve of a similar design was

also fewnd-te-be9damaged. However, the licensee believes that this damage

J

c ncurred during maintenance. The damage was similar to that found on the

/

MSI1iV4%e4_galling marks, failed bolts, and detached rails, but, in addition,

,Ythe skirt plate was fractured and the shoe was wedged into the lever arm pivot

S g slot. t

a PL

Cjhis type of failure

44-be+eved to be generic to other plants. Valves-of

n

this type are also eported to be in use at San Onofre 2, South Texas 1 and 2,

7iand-0.SL Valve similar

'nkdesign

could exist at other plants. The pr~imi- cat ons

that the failures are attributable to deficien

sn

t fabricaton, en I eering, and materials. The corrective actions

t-have-ten"er

considered at Waterford and San Onofre 3 includeiL,/

qQS8x;A F-J(1,V Xtelliting the shoes and the chamfer on the rai

,-r

,*

~ (2,)

.erifying

the bolt alignmentsa--

=LT73-) 4Voing nondestructive examinations of all ne bolts,-

u(4j)

4hanglng the angles of the rails and of t

shoes,.

//It"

fl

75i) .ncreasing the valve closure time (withi system constraints),.->

i !U..'6)Ieriodically

making fiberscope examina ions of the valve internals to

J,

e- detect excessive galling, severed gu e rail bolts, and separated

'3/4.

8 Sguide

rails.---

i

by

No specific action or written response sequired by thia/i nformation notice.

-

If you have any questions about this mat er, please ci&fiet-the technical

contact listed below or the,,,egional

inistrator of the appropriate regional

office.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

Kenne

Dempsey, NRR

(30

492-0918 Attachments:

1. Figure

2. List of Recentl Issued NRC Information Notices

D/DOEA:NRR

C/OGCB:DOEA:NRR

RFA':

CERossi

CHBerlinger

WchO1fW/88

07/ /88

07/ /88

07/o77/88 OGCB:DOEA:NRR EM BDB T:NRR C/EMEB:DEST:NRR

EAD/DEST:NRR

D/DEST:NRR

DCKirkpatjjjl

KDipb6j'

LBMarsh

JRichardson

LCShao

07/g;/88 AJW# 07/ 7~f88

07/ /88

07/ /88

07/ /88

IN 88-XX

July xx,

1988 Subsequent to the failure at Waterford 3, a fiberscope examination of the WKM

power seal MSIVs at San Onofre'Unit 3 revealed a broken bolt lying in the

bottom section of the body of one MSIV. During disassembly and inspection of

this valve, it was found to have three failed bolts, galling marks on the shoe

and the chamfer, and an upstream rail slightly detached from the skirt plate.

At the same plant, a shutdown cooling isolation valve of a similar design was

also found to be damaged.

However, the licensee believes that this damage

occurred during maintenance.

The damage was similar to that found on the

MSIVs, i.e., galling marks, failed bolts, and detached rails, but, in addition, the skirt plate was fractured and the shoe was wedged into the lever arm pivot

slot.

This type of failure is believed to be generic to other plants.

Valves of

this type are also reported to be in use at San Onofre 2, South Texas 1 and 2, and WPPS. Valves similar in design could exist at other plants. The prelimi- nary indications are that the failures are attributable to deficiencies in

fabrication, engineering, and materials.

The corrective actions that have been

considered at Waterford and San Onofre 3 include:

1. Stelliting the shoes and the chamfer on the rails,

2. Verifying the bolt alignments,

3. Doing nondestructive examinations of all new bolts,

4. Changing the angles of the rails and of the shoes,

5.

Increasing the valve closure time (within system cons raints),

6. Periodically making fiberscope examinations of the alve internals to

detect excessive galling, severed guide rail bolt, and separated

guide rails.

No specific action or written response is required by

is information notice.

If you have any questions about this matter, please ontact the technical

contact listed below or the Regional Administrator f the appropriate regional

office.

Charl

E. Rossi, Director

Div ion of Operational Events Assessment

Of ce of Nuclear Reactor Regulation

Technical Contact:

Kenneth Dempse

NRR

(301) 492-09 Attachments:

1. Figure

2. List of Recently Issue NRC Information Notices

D/DOEA:NRR

C/OGCB:DOEA:NRR

RPB:ARM

CERossi

CHBerlinger

TechEd

OGCB:DOEA:NRR

DCKirkpaty4gI

07/;I$/88 AJw

EMEBL:DIST:NRR

KDOW%~y

07D-8/88

07/ /88 C/EMEB:DEST:NRR

LBMarsh

07/ /88

07/

/88 EAD/DEST:NRR

JRichardson

07/ /88

07/ /88 D/DEST:NRR

LCShao

07/ /88