Information Notice 1986-81, Broken Inner-External Closure Springs on Atwood & Morrill Main Steam Isolation Valves

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Broken Inner-External Closure Springs on Atwood & Morrill Main Steam Isolation Valves
ML031250220
Person / Time
Issue date: 09/15/1986
From: Jordan E
NRC/IE
To:
References
IN-86-081, NUDOCS 8607110318
Download: ML031250220 (6)


LIS

tIN

86-81

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT

WASHINGTON, D.C.

20555

September 15, 1986

IE INFORMATION NOTICE NO. 86-81:

BROKEN INNER-EXTERNAL CLOSURE SPRINGS ON

ATWOOD & MORRILL MAIN STEAM ISOLATION VALVES

Addressees

All nuclear power reactor facilities holding an operating license or a construc- tion permit.

Purpose

This notice is provided to inform recipients of a potentially significant safety

problem that could result from broken inner-external closure springs on main

steam isolation valves (MSIVs) manufactured by Atwood & Morrill Co., Inc.

The

springs that failed were manufactured by Duer Spring and Manufacturing Co.

Quench cracks, which apparently developed during the manufacturing process, caused the springs to fail.

It is expected that the recipients review the information for applicability

to their facilities and consider actions, if appropriate, to preclude a similar

problem from occurring at their facilities.

However, suggestions contained in

this information notice do not constitute NRC requirements; therefore, no

specific action or written response is required.

Description of Circumstances

During an inspection of MSIVs following low-pressure seat leakage tests at

Enrico Fermi Unit 2 in May 1986, the licensee observed that four inner-external

closure springs were broken into two-to-seven pieces.

The licensee analyzed two

of the broken springs and determined the failure to be quench cracking caused by

the heat treatment process during manufacturing.

There are eight MSIVs with

eight inner-external and eight outer-external closure springs per valve.

All

outer-external closure springs were found intact and undamaged.

All 64 external

springs were from the same heat number (#8067703).

The external closure-spring

assemblies (inner and outer) perform a safety function to close the MSIVs.

Discussion:

Springs from Duer Spring and Manufacturing Co. were supplied to PWR and BWR

nuclear power plants on MSIVs manufactured by Atwood & Morrill.

The external

closing springs that failed at Fermi 2 were the inner springs around the valve

yoke rods.

The following effects on valve operation could occur with one or

more springs failing:

8607110318

IN 86-81 September 12, 1986 1.

Slower closing time with steam in the normal forward flow direction.

For

BWRs, General Electric estimates the closure time would increase from the

Technical Specification requirements of 3 to 5 seconds but will remain

under 10 seconds.

2.

Increased difficulty in meeting low-pressure seat leakage test requirements

in BWR units.

3.

Valve closure with steam in the reverse flow direction in PWR units could

be adversely affected since the springs provide the only external closing

assistance.

Internal closing assistance is provided by the use of a pilot

poppet design in these valves.

The spring manufacturer also performed laboratory metallographic examination of

the failed springs and verified that the failure was the result of quench

cracking.

Atwood & Morrill and Duer Spring have recommended that at the first

available opportunity all the external closing springs on all MSIVs be cleaned

and magnetic particle testing be performed.

Duer has provided an inspection

procedure.

Atwood & Morrill is issuing a letter to all affected customers concerning this

event which recommends that the above actions be taken.

The Atwood & Morrill

list of affected units is attached.

In addition, General Electric has issued

a service information letter, SIL No. 442 dated July 18, 1986, to owners of

affected BWRs recommending a visual inspection and, in some cases, load tests.

The NRC has reviewed the two procedures and has determined that either

recommendation is adequate for BWRs.

For PWRs, only the Atwood & Morrill

recommendations are appropriate.

However, consideration should be given to

visual inspections of the springs following any cycling of the valve until

completion of the Atwood & Morrill recommended inspection.

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

If you have any questions about this matter, please contact the Regional Admini- strator of the appropriate regional office or this office.

.dwardt

Jordan, Director

Divisi

of Emergency Preparedness

and Engineering Response

Office of Inspection and Enforcement

Technical Contact:

J. C. Stone, IE

(301) 492-9044 Attachments:

1.

List of affected plants as identified by Atwood & Morrill

2.

List of Recently Issued IE Information Notices

Attachment 1

IN 86-81 September 15, 1986 ATWOOD & MORRILL CO., INC.

Main Steam Isolation Valves

Furnished With External Closing Springs

Manufactured by Duer Spring & Manuf. Co.

PWR UNITS

Utility

Duke Power Co.

Duke Power Co.

Duke Power Co.

Duke Power Co.

Houston Lighting

& Power

South Carolina

Elec & Gas

Station

Catawba 1 & 2 i

McGuire 1 & 2 Perkins 1, 2, & 3 Cherokee 1, 2, & 3 South Texas

Project 1 & 2

Virgil Summer 1

Quantity and Valve Size

8 34-inch

8 32-inch

12 32-inch Units Cancelled

12 32-inch Units Cancelled

8 32-inch

3 32-inch

TVA

TVA

TVA

Bellefonte 1 & 2 Sequoyah 1 & 2 Watts Bar 1 & 2

8 32-inch

8 32-inch

8 32-inch

Attachment 1

IN 86-81 September 15, 1986 ATWOOD & MORRILL CO., INC.

Main Steam Isolation Valves

Furnished With External Closing Springs

Manufactured by Duer Spring & Manuf. Co.

BWR UNITS

Utility

Boston Edison

Cleveland Elec.

Illuminating

Detroit Edison

Georgia Power

Gulf States Util.

Houston Lighting

& Power

Illinois Power

Jersey Central

Power & Light

Mississippi Power

& Light

Niagara Mohawk

Power Corp.

Northern States

Power Co.

Pennsylvania

Power & Light

Philadelphia

Electric

Philadelphia

Electric

Public Service

Elec & Gas

Station

Pilgrim 1!

Perry 1 &12

Enrico Fermi 2

Hatch 1

River Bend 1

Allens Creek 1 Clinton 1

Oyster Creek 1

Grand Gulf 1 & 2

Nine Mile Point 1

Monticello

Susquehanna 1 & 2 Limerick 1 & 2 Peach Bottom 2 & 3 Quantiy & Valve Size

8 20-inch

16 26-inch

8 26-inch

8 24-inch

8 24-inch

8 24-inch

Unit cancelled

8 24-inch

4 24-inch

16 28-inch

2 24-inch

8 18-inch

16 26-inch

16 26-inch

16 26-inch

16 26-inch Unit 2 cancelled

Hope Creek 1 & 2

Attachment 1

IN 86-81 September 15,

1986 ATWOOD & MORRILL CO., INC.

Main Steam Isolation Valves

Furnished With External Closing Springs

Manufactured by Duer Spring & Manuf. Co.

BWR UNITS

Utility

TVA

TVA

Station

Browns Ferryl1, 2,

& 3i

Hartsville AX, A2, B1 & B2

%

Quantiy & Valve Size

24 26-inch

32 26-inch Units B1 & B2 Cancelled

TVA

Phipps Bend 1 & 2

16 26-inch

Units cancelled

4 I%1-1

Attachment 2

IN 86-81

September 15, 1986

LIST OF RECENTLY ISSUED

IE INFORMATION NOTICES

Information

Date of

Notice No.

Subject

Issue

Issued to

86-80

86-79 Unit Startup With Degraded

9/12/86

High Pressure Safety Injection

System

Degradation Or Loss Of

Charging Systems At NWR

Nuclear Power Plants!Using

Swing-Pump Designs l

Scram Solenoid Pilot'Valve

(SSPV) Rebuild Kit Problems

9/2/86

9/2/86

86-78

86-77 Computer Program Error Report 8/28/86 Handling

86-76

86-75

86-74 Problems Noted In Control

8/28/86

Room Emergency Ventilation

Systems

Incorrect Maintenance

8/21/86

Procedure On Traversing

Incore Probe Lines

Reduction Of Reactor Coolant 8/20/86 Inventory Because Of Misalign- ment Of RHR Valves

Recent Emergency Diesel

8/20/86

Generator Problems

Failure 17-7 PH Stainless

8/19/86

Steel Springs In Valcor

Valves Due to Hydrogen

Embrittlement

All power reactor

facilities holding

an OL or CP

All power reactor

facilities holding

an OL or CP

All BWR facilities

holding an OL or CP

All power reactor

facilities holding

an OL or CP and

nuclear fuel man- ufacturing facilities

All power reactor

facilities holding

an OL or CP

All power reactor

facilities holding

an OL or CP

All BWR facilities

holding an OL or CP

All power reactor

facilities holding

an OL or CP

All power reactor

facilities holding

an OL or CP

86-73

86-72 OL = Operating License

CP = Construction Permit