Information Notice 1995-11, Failure of Condensate Piping Because of Erosion/Corrosion at Flow-Straightening Device

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Failure of Condensate Piping Because of Erosion/Corrosion at Flow-Straightening Device
ML031060332
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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane  
Issue date: 02/24/1995
From: Grimes B
Office of Nuclear Reactor Regulation
To:
References
IN-95-011, NUDOCS 9502210050
Download: ML031060332 (9)


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, -- --

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555

February 24, 1995

NRC INFORMATION NOTICE 95-11:

FAILURE OF CONDENSATE PIPING BECAUSE OF

EROSION/CORROSION AT A FLOW-STRAIGHTENING

DEVICE

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 possible piping failures caused by flow

disturbances that are not accounted for in erosion/corrosion programs.

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

On November 29, 1994, the Sequoyah Unit 1 reactor tripped from 100-percent

power. Approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after the plant trip, Tennessee Valley Authority

(TVA, the licensee) observed water pouring from a 16 inch nominal size

diameter condensate line between the 1B4 and 1B3 feedwater heaters. A

licensee investigation found , 180 degree circumferential crack in the reduced

section of a nominal 14 inch pipe. This pipe section was part of a

Westinghouse flow-metering device that had been installed during the first

refueling cycle to test turbine performance.

The metering device consisted of three flanged sections of pipe: the first

section reduced the pipe diameter from 16 inch to 14 inch; the last section

expanded the diameter back to 16 inch; and the middle section contained a

flow-straightening device, a nozzle, and flow taps. The flow straightener

device consisted of three 0.95 cm [0.375 inch] thick, circular plates with

drilled flow holes. The plates were spaced about 0.3 meter [1 foot] apart and

held together by four 1.27 cm [0.5 inch] rods.

The first circular plate fit

the pipe flange face and held the fixture in place.

The other two plates fit

the machined, inside surface of the 14 inch diameter pipe section.

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February 24, 1995 Discussion

TVA found that the pipe failure occurred at the interface of the edge of the

middle plate and the inner surface of the pipe wall.

The failure resulted

from bypass flow around the edge of the plate, which caused very localized

erosion along a narrow band, approximately 1.27 cm [0.5 in] wide and

360 degrees around the pipe wall. A 7.6 cm [3 inch] wide, 0.32 cm

[0.125 inch] deep machined surface, 360 degrees, on the outer surface of the

pipe in the same area of the internal erosion may have contributed to the pipe

failure.

This surface had been machined to serve as a reference surface and

the inner surface was machined to ensure a snug fit of the flow straightener

inside the pipe. At the failure area, erosion had further thinned the pipe

wall to approximately 0.127 cm [0.05 inch].

The condensate line containing the flow-metering device was in the

erosion/corrosion program and modeled with CHECMATE, but it was modeled as a

straight 16 inch pipe section without any diameter or thickness change.

CHECMATE is a program used by a majority of licensees that predicts

erosion/corrosion rates in piping components, ranks the components in order of

damage potential, and calculates the time remaining before reaching a user

defined acceptable wall thickness. The licensee personnel responsible for

operations and engineering were aware that the flow-metering device was

installed; however, ambiguities in drawings prompted the personnel responsible

for the erosion/corrosion program to assume that these sections had been

removed. The pipe configuration had not been visually inspected and it had

been modelled as a straight section.

After the pipe failure, the CHECMATE model, including the condensate line with

the flow-metering devices, was re-analyzed. The CHECMATE program did not

include a model for the flow straightener; the closest model for this device

was a straight pipe section. The CHECMATE model would have indicated a high

rank for erosion downstream of the nozzle, which would have been modelled as

an orifice.

Therefore, knowledge that the metering device was installed still

may not have prompted an inspection of the area of piping that failed (the

area of the flow straightener).

Even if the area had been inspected, the band

of erosion was so localized that it could have been missed since only grid

intersections are inspected.

The licensee determined that the parallel condensate lines still had the

temporary metering devices installed and replaced those sections with straight

16 inch sections of pipe.

The licensee also determined that the heater drain

system had two of these temporary metering sections but decided to leave the

lines in service because the flow straighteners had been removed in an outage

and present thickness measurements indicated no unacceptable erosion.

The root cause of the failure was the bypass flow around the middle plate of

the flow straightener. This bypass flow was not anticipated and the NRC staff

is not aware of any previous industry experience that would have demonstrated

a need to have the CHECMATE program indicate a high rank for flow

straighteners. This example is an indication of how flow disturbances not

accounted for by modelling tools can affect the reliability of licensee

erosion/corrosion programs.

IN 95-11

February 24, 1995 Related Generic Communications

In NRC Bulletin 87-01, "Thinning of Pipe Walls in Nuclear Power Plants,"

July 9, 1987, the staff requested licensees and applicants to inform NRC about

their programs for monitoring the wall thickness of carbon steel piping.

By NRC Generic

Thinning," May

implement long

Letter (GL) 89-08, "Erosion/Corrosion-Induced Pipe Wall

2, 1989, the staff requested licensees and applicants to

term erosion/corrosion monitoring programs.

The NRC also issued several information notices on erosion and corrosion.

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.

1

.ran

. Grimes, Director

Division of Project Support

Office of Nuclear Reactor Regulation

Technical contacts:

B. R. Crowley, RII

(404) 331-5579

N. Economos, RII

(404) 331-5580

K. I. Parczewski,

(301) 415-2705 NRR

Attachment:

List of Recently Issued NRC Information Notices

'-Attachment

IN 95-11

February 24, 1995 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information

Date of

Notice No.

Subject

Issuance

Issued to

95-10

Supp. 1

95-10

95-09

95-08

95-07

95-06

Potential for Loss of

Automatic Engineered

Safety Features

Actuation

Potential for Loss of

Automatic Engineered

Safety Features

Actuation

Use of Inappropriate

Guidelines and Criteria

for Nuclear Piping and

Pipe Support Evaluation

and Design

Inaccurate Data Obtained

with Clamp-On Ultrasonic

Flow Measurement Instruments

Radiopharmaceutical Vial

Breakage during Preparation

Potential Blockage of

Safety-Related Strainers

by Material Brought Inside

Containment

02/10/95

02/03/95

01/31/95

01/30/95

01/27/95

01/25/95

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 USNRC medical licensees

authorized to use byproduct

material for diagnostic

procedures.

All holders of OLs or CPs

for nuclear power reactors.

95-05

95-04

Undervoltage Protection

Relay Settings Out of

Tolerance Due to Test

Equipment Harmonics

Excessive Cooldown and

Depressurization of the

Reactor Coolant System

Following a Loss of

Offsite Power

01/20/95

01/19/95 All holders

Permits for

reactors.

of Construction

nuclear power

All holders of OLs or CPs

for nuclear power reactors.

OL = Operating License

CP -

Construction Permit

IN 95-11 February 24, 1995 In NRC Bulletin 87-01, "Thinning of Pipe Walls in Nuclear Power Plants,"

July 9, 1987, the staff requested licensees and applicants to inform NRC about

their programs for monitoring the wall thickness of carbon steel piping.

By NRC Generic Letter (GL) 89-08, "Erosion/Corrosion-Induced Pipe Wall

Thinning," May 2, 1989, the staff requested licensees and applicants to

implement long term erosion/corrosion monitoring programs.

The NRC also issued several information notices on erosion and corrosion.

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.

Original signed by

Brian K. Grimes

Brian K. Grimes, Director

-

Division of Project Support

Office of Nuclear Reactor Regulation

Technical contacts: B. R. Crowley, RII

(404) 331-5579

N. Economos, RII

(404) 331-5580

K. I. Parczewski, NRR

(301) 415-2705 Attachment:

List of Recently Issued NRC Information Notices

DOCUMENT NAME: 95-11.IN

  • See previous concurrence

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DATE

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12/19/94

12/19/94

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DATE

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01/17/95

01/19/95

02/2, //95

OFFICIAL RECORD COPY

IN 95-XX

January XX, 1995 In NRC Bulletin 87-01, "Thinning of Pipe Walls in Nuclear Power Plants,"

July 9, 1987, the staff requested licensees and applicants to inform NRC about

their programs for monitoring the wall thickness of carbon steel piping.

By NRC Generic Letter (GL) 89-08, "Erosion/Corrosion-Induced Pipe Wall

Thinning," May 2, 1989, the staff requested licensees and applicants to

implement long term erosion/corrosion monitoring programs.

The NRC also issued several information notices on erosion and corrosion.

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 Project Support

Office of Nuclear Reactor Regulation

Technical contacts: B. R. Crowley, RII

(404) 331-5579

N. Economos, RII

(404) 331-5580

K. I. Parczewski, NRR

(301) 415-2705 Attachment:

List of Recently Issued NRC Information Notices

DOCUMENT NAME: S:\\DOPSSEC\\SEQUOYAH.IN

  • See previous concurrence

OFC

l OECB:DOPS

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SC/OECB:DOPS

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DATE 1 12/14/94

12/19/94

12/19/94

12/21/94 OFC

C/EMCB:DE

OECB:DOPS

C/OECB:DOPS

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DATE

12/21/94

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01/17/95

01/19/95

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/95

___-OFFICIAL

RECORD COPY

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IN 95-XX

January XX, 1995 NRC Generic Letter (GL) 89-08, "Erosion/Corrosion-Induced Pipe Wall Thinning,'

May 2, 1989. The staff requested licensees and applicants to implement long

term erosion/corrosion monitoring programs.

The NRC also issued several information notices on erosion and corrosion.

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 Project Support

Office of Nuclear Reactor Regulation

Technical contacts:

B. R. Crowley, RII

(404) 331-5579

N. Economos, RII

(404) 331-5580

K. I.

(301)

Parczewski, NRR

504-2705 Attachment:

List of Recently Issued NRC Information Notices

DOCUMENT NAME:

G:\\SSK2\\SEQUOYAH.IN

  • See previous concurrence

OFC l OECB:DOPS

TECH ED

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12/19/94

12/19/94

12/21/94 OFC

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C/OECB:DOPS

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NAME

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BGrimes V98 DATE

12/21/94

01/17/95

01/19/95

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/95 1

OFFICIAL RECORD COPY

' -ok

IN 95-XX

January XX, 1995

NRC Generic Letter (GL) 89-08, "Erosion/Corrosion-Induced Pipe Wall Thinning,"

May 2, 1989. The staff requested licensees and applicants to implement long

term erosion/corrosion monitoring programs.

8 The NRC also issued several information notices on erosion and corrosion.

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 Project Support

Office of Nuclear Reactor Regulation

Technical contacts:

B. R. Crowley, RII

(404) 331-5579

N. Economos, RII

(404) 331-5580

K. I. Parczewski, NRR

(301) 504-2705 Attachment:

List of Recently Issued NRC Information Notices

DOCUMENT NAME: G:\\SSK2\\SEQUOYAH.IN

  • See previous concurrence

OFC

OECB:DOPS

TECH ED

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NAME

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EGoodwin*

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DATE 1 12/14/94

12/19/94

12/19/94

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OFFICIAL RECORD COPY

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IN 95-XX

January XX, 1995 NRC Generic Letter (GL) 89-08, "Erosion/Corrosion-Induced Pipe Wall Thinning,"

May 2, 1989.

The staff requested licensees and applicants to implement long

term erosion/corrosion monitoring programs.

8 The NRC also issued several information notices on erosion and corrosion.

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:

B. R. Crowley, RII/DRS

(404) 331-5579 N. Economos, RII/DRS

(404) 331-5580

K. I. Parczewski, NRR/DE

(301) 504-2705 Attachment:

List of Recently Issued NRC Information Notices

OFC }

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DOCUMENT NAME: G:\\SSK2\\SEQUOYAH.IN