Information Notice 1979-37, Cracking in Low Pressure Turbine Discs

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Cracking in Low Pressure Turbine Discs
ML031180211
Person / Time
Site: 05000000
Issue date: 12/28/1979
From:
NRC/OI
To:
References
IN-79-037, NUDOCS 7910250525
Download: ML031180211 (7)


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UNITED STATES

ISINS NO.:

6870

NUCLEAR REGULATORY COMMISSION

Accession No.:

OFFICE OF INSPECTION AND ENFORCEMENT

7910250525 WASHINGTON, D.C.

20555

December 28, 1979

IE Information Notice No. 79-37

CRACKING IN LOW PRESSURE TURBINE DISCS

Description of Circumstances

An anonvmous letter was received by the Director of the Office of Inspection and

Enforcement, on November 17, 1979 which alleged possible violation of Part 10 CFR

50.55e and/or 10 CFR 21 Requlations concerning reportability of recently discovered

stress corrosion cracking in Westinghouse 1800 rpm low pressure turbine discs.

Westinghouse had made a presentation on the turbine disc cracking to electric

utility executives on October 30, 1979.

Telephone discussions between the NRC staff and Westinohouse's Turbine Division

on November 20, 1979 established that crackinq, attributed to stress corrosion

phenomena, had been found in the keyway areas of several LP turbine discs at

operating plants and that inservice inspection techniques (i.e., in situ ultra- sonic examination) for crack detection have been developed and are beinq imple- mented in the field. The Office of Inspection and Enforcement was also notified

on November 20, 1979 that during the current overhaul of Commonwealth Edison's

Zion Unit 1 LP turbine, ultrasonic examination revealed embedded cracks located

on the inlet side on the disc bore area where no cracks had been previously

observed. Ultrasonic measurements indicate this disc bore cracking is of qreater

depth than the keyway cracks found to date.

According to Westinqhouse, these

bore cracks have been metallurgically examined and preliminary findinqs show them

not to be typical of classical stress corrosion cracking observed in the keyways.

The probable cracking mechanism and impact on disc integrity is being further

evaluated by Westinghouse.

A meetino was held on December 17, 1979 between the NRC staff, Westinghouse

and utility representatives to discuss the disc cracking problem, repair alter- natives, turbine missile evaluation, inspection techniques and plant inspection

priorities. In response to the staffs' request, Westinghouse provided the

staff an updated report on December 21, 1979 regarding the current field inspection

oroaram that included a list of nuclear power plants already inspected, recom- mended inspection schedules and pertinent information related to LP turbines

where cracks have been observed.

Inspections to date have identified turbine

disc cracks at Surry Unit 2, Point Beach Unit 2, Palisades, Indian Point Unit 3 and Zion Unit 1. All units except Point Beach Unit 2 will make repairs before

the plants return to power.

Point Beach returned to power on December 23, 1979

with a small crack in the No. 2 disc of LP Turbine No. 2. An analysis by

Westinghouse indicated that the observed crack will not attain critical dimensions

durinq 28 additional months of turbine operation. The NRC staff is evaluating

the turbine inspection results and analysis by Westinahouse.

IE Information Notice No. 79-37

December 28, 1979

Pace 2 of 2 Westinqhouse also notified the staff that extrapolation of information obtained

from Indian Point Unit 3 inspection and analysis indicates that disc crackina

could be significant at Indian Point Unit 2 and the turbines should be inspected

sooner than the spring outace of 1980. The NRC staff is currently reviewing

Consolidated Edison's plans for prompt evaluation of this potential problem

at this unit.

Enclosure 1 lists the PWR plants having Westinghouse 1500/1800 rpm turbines.

The AA cateaory represents those turbines which appear to have the earliest

need for inspection. With the exception of Yankee Rowe, Westinghouse has

recommended to utilities that Inspection of these machines be comDleted by

the Spring 1980 outage period. The Rowe unit is uninspectable by the present

ultrasonic techniques due to its design. Westinghouse has recommended the

remaining machines of the Cateqory A plants be inspected as their service

periods aooroach five years or in the event significant corrosion problems become

evident during this time. The NRC staff is currently reviewing the need for

inspection of those PWR plants having other interfacing turbine desions shown

in Enclosure 2. Changes to the forementioned inspection schedules proposed by

Westinghouse may be necessary as new technical information becomes available.

From the information available to the NRC staff at this time it appears that

crackinq may be more generically widespread in turbine discs (e.g., keyways and

bore areas) than previously observed. It is important to note that the UT

inspections performed by Westinahouse thus far were essentially limited to

the keyways (disc outlet) of selected discs whereas the Zion Unit 1 inspection

results indicate that examination of the disc bore section must be taken into

account.

Also, Westinghouse is currently re-evaluating their previously estimated

turbine missile energies based on recent missile test results from model symmetric

and non-symmetric missile impact tests. Their preliminary findinas, although

subject to chance, now indicate possible higher missile exit energies in some

cases than previously expected.

This Information Notice is provided as an early notification of a possibly

sianificant matter, the allegations and the generic safety implications of which

are currently undergoing review by the NRC staff.

It is expected that recipients

will review the information applicable to their facilities. If NRC evaluations

so indicate, further licensee actions may be requested or required.

Embedded

crackino in keyways and disc bore areas have been observed only in Westinghouse

LP turbines thus far.

However, the NRC staff. believes that turbines of other

manufacturers should be included in consideration of this problem.

No written response to this Information Notice is required. If you have any

questions recardinn this matter, please contact the Director of the appropriate

NRC Regional Office.

Enclosures:

As stated

Enclosure 1 CATEGORY AA

STATION

UTIL ITY

UNIT

Florida, P&L

Consolidated ED.

PASNY

Arkansas P&L

VEPCO

Carolina PPbL

So. Calif. Ed.

Yankee A.P.

Wisc. Mich. Pwr.

Consumers Pwr.

Commonwealth Ed.

Commonwealth Ed.

Florida P&L

Nebraska PPD

Wisc. Mich. Pwr.

Maine Yankee

Rochester G&E

Northern States

Wisc. P.S.

Turkey Point

Indian Point

Indian Point

Russeliville

Surry

Robinson

San Onofre

Rowe

Point Beach

Palisades

Zion 1 Zion 2

Turkey Point

Cooper

Point Beach

Bailey Point

Ginna

Prairie Island

Kewaunee

3

2

3

1

1

2

1

1

1

1

1

2

4

1

2

1

1

1

1

Enclosure 1 (Continued) CATEGORY A

UTILITY

Alabama Power

Alabama Power

Baltimore G&L

Carolina P&L

Carolina P&L

Carolina P&L

Carolina P&L

Cincinnati G&E

Commonwealth Ed.

Commonwealth Ed.

Commonwealth Ed.

Commonwealth Ed.

Connecticut Yankee

Duke Power

Duke Power

Duquesne Lt.

Duquesne Lt.

Duquesne Lt.

Flordia Power Coro.

Flordia Power & Lt.

Flordia Power & Lt.

Houston L&P

Houston L&P

Louisiana P&L

Metropolitan Ed.

Northern States Pwr.

Pub. Service E&G

Pub. Service E&G

Pacific G&E

Pacific i&E

STATION

Fa rley

Farl ey

Calvert Cliffs

Harris

Harris

Harris

Harris

Zimmer

Byron

Byron

Braidwood

Braidwood

Haddam Neck

McGuire

McGui re

Shippinqport

Beaver Valley

Beaver Valley

Crystal River

St. Lucie

St. Lucie

So. Texas

So. Texas

Waterford

Three Mile Island

Prairie Island

Salem

Salem

Diablo Canyon

Diablo Canvon

UNIT

1

2

2

1

2

3

4

1

1

2

1

2

1

1

2

1

1

2

3

1

2

1

2

3

2

2

1

2

1

2

Enclosure 1 (Continued)

CATEGORY A

STATION UTILITY

UNIT

P.S. Indiana

P.S. Indiana

Puget Sound P&L

SMUD.

TVA

TVA

TVA

TVA

Marble Hill

Marble Hill

Skaqit

Rancho Seco

Sequoyah

Sequoyah

Watts Bar

Watts Bar

2

1

1

1

2

1

2

1

2

3

4

2 VEPCO

VEPCO

VEPCO

VEPCO

VEPCO

North

North

North

North

North

Anna

Anna

Anna

Anna

Anna

WPPSS

WPPSS

WPPSS

WPPSS

WPPSS

Hanford

WNPS

WNPS

WNPS

WNPS

2

1

3

4

5

Enclosure 2 UTILITY

Duke Power Co.

Duke Power Co.

Duke Power Co.

OPPD

Baltimore Electric

& Gas

Metropolitan Edison

Indiana & Michigan

Electric

Indiana & Michican

Electric

Northeast Utilities

Portland General

Electric

Toledo Edison

Arkansas Power &

Light

WPPSS

STATION

Oconee

Oconee

Oconee

Ft. Calhoun

Calvert Cliffs

Three Mile Island

D.C. Cook

D.C. Cook

Millstone

Trojan

Davis Besse

Arkansas Nuclear One

Hanford

UNIT

1

2

3

1

11

1

22

11

2

1

IE Information Notice No. 79-37

December 28, 1979

Enclosure

RECENTLY ISSUED

IE INFORMATION NOTICES

Information

Notice No.

Subject

Date

Issued

Issued To

79-36

79-35

79-34

79-33

79-32

79-31

Computer Code Defect In

Stress Analysis of Piping

Elbow

Control of Maintenance

and Essential Equipment

Inadequate Desiqn of

Safety-Related Heat

Exchanaers

Improper Closure of

Primary Containment

Access Hatches

Separation of Electrical

Cables for HPCI and ADS

Use of Incorrect Amplified

Response Spectra (ARS)

Reportinq of Defects and

Noncompliance, 10 CFR Part 21.

Loss of NonSafety-Related

Reactor Coolant System

Instrumentation During

Operation

12/31/79

All holders of power reactor

OLs and CPs

12/31/79

All power reactor facilities

with an OL or CP

12/27/79

All holders of power reactor

OLs and CPs

12/21/79

All power reactor facilities

holding OLs and CPs

12/21/79

All power reactor facilities

holding OLs and CPs

12/13/79

All holders of power reactor

OLs and CPs

79-30

79-29

12/6/79

All power reactor facilities

holding OLs and CPs and

vendors inspected by LCVIP

11/16/79

All power reactor facilities

holdino OLs or CPs

79-28

Overloading of Structural

Elements Due to Pipe Support

Loads

11/16/79

All power reactor

with an OL or CP

facilities

79-27

Steam Generator Tube

Ruotures At Two PWR

Facilities

Attemoted Damaqe To New

Fuel Assemblies

11/16/79

All power reactor facilities

holdina OLs and CPs

11/9/79 All Fuel Facilities, research reactors, and

oower reactors with an

OL or CP

79-12A