Information Notice 1987-36, Significant Unexpected Erosion of Feedwater Lines

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Significant Unexpected Erosion of Feedwater Lines
ML031130521
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, Skagit, Marble Hill, Crane
Issue date: 08/04/1987
From: Rossi C
Office of Nuclear Reactor Regulation
To:
References
IN-87-036, NUDOCS 8707290264
Download: ML031130521 (8)


SSINS No.:

6835 IN 87-36

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, DC 20555

August 4, 1987

NRC INFORMATION NOTICE NO. 87-36: SIGNIFICANT UNEXPECTED EROSION OF

FEEDVATER LINES

Addressees

All nuclear power reactor facilities holding an operating license or a con- struction permit.

Purpose

This information notice is provided to alert recipients to a potentially

generic problem pertaining to significant unexpected erosion which resulted

in pipe wall thinning in the safety-related portions of feedwater lines and

other related problems. It is expected that recipients will review the Infor- mation for applicability to their facilities and consider actions, if appro- priate, to preclude a similar problem. However, suggestions contained in this

notice do not constitute NRC redpuirements; therefore no specific action or

written response is required.

Description of Circumstances

At the Trojan Nuclear Plant it was discovered that at least two areas of the

straight sections of the main feedwater piping system experienced wall thinning

to an extent that the pipe wall thickness would have reached the minimum thick- ness required by the design code (ANSI B31.7, "Nuclear Power Piping") during

the next refueling cycle. These areas are in safety-related portions of ASME

Boiler and Pressure Vessel Code (ASME Code) Class 2 piping inside containment.

The pipe wall had thinned in both horizontal and vertical runs that were at

least seven pipe diameters downstream of elbows or other devices that can cause

flow turbulence. Criteria developed by the Electric Power Research Institute

(EPRI Users Manual NSAC-112, "CHEC [Chexal-Horowitz-Erosion-CorrosionJ,I dated

June 1987) would not have required that the pipe wall in these straight sec- tions be examined.

Although the straight sections of eroded 14-inch pipe were slightly thicker

than the minimum required thickness, it was projected that the pipe wall

thickness would erode below the minimum required thickness before the next

major outage. Consequently, the licensee plans to replace this piping before

restart.

02W64'

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8707290264 Ul

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IN 87-36 August 4, 1987 The Trojan plant is conducting a failure analysis on the degraded components to

determine the causes and mechanisms involved in the observed wall thinning

event. The NRC is evaluating the data available to determine any generic

implication of the event.

Related Generic Communications:

IE Information Notice 82-22, "Failure in Turbine Exhaust Lines," dated July 9,

1982 provides additional information pertaining to erosion/corrosion in wet

steam piping. Other erosion/corrosion events pertaining specifically to the

feedwater systems (including emergency and auxiliary feedwater) have occurred

in feedwater pump minimum-flow lines, J-tubes in steam generator feedwater

rings, and emergency feedwater supply to a helium circulator.

IE Information Notice 86-106, "Feedwater Line Break," was issued December 16,

1986. It described the then-known details of the December 9,, 1986 failure of

the suction line to a main feedwater pump at Surry Power Station Unit 2.

Supplement 1 to this information notice, which was issued February 13, 1987, provided additional detail on the failure mechanism. Supplement 2, which was

issued on March 10, 1987, discussed the effects of the system interactions that

resulted from the line break.

NRC Bulletin 87-01, "Thinning of Pipe Wall in Nuclear Power Plants," issued on

Juty-9;-987, requested that iTcensees submit information concernffng-thirlf

programs for monitoring the thickness of pipe walls in high-energy single-phase

and two-phase carbon steel piping systems.

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

If you have any questions about this matter, please contact the Regional

Administrator of the appropriate NRC regional office or this office.

rle

E.RostDirector

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

Paul C. Wu, NRR

(301) 492-8987 Attachment: List of Recently Issued NPC Information Notices

IN 87-36 August 4, 1987 The licensee believes that the high flow velocity of 22.6 ft/sec, in combina- tion with other operating factors, may be the cause of the thinning.

This thinning was discovered when the steam piping inspection program at the

Trojan plant was expanded to include single-phase piping. Trojan personnel

inspected essentially all safety-related high energy carbon steel piping

inside containment.

In addition, the licensee discovered approximately 30 additional areas of the

main feedwater piping system where the pipe wall had thinned so the thickness

of the pipe wall was either less than the minimum thickness required by the

design code or would have eroded to the minimum required thickness during the

next operating cycle. Of these areas, 10 were in the safety-related portions

of the system, while the rest were in non-safety-related portions. All of

these thirty additional areas were in regions that the EPRI criteria would have

indicated as 'needing examination.

Discussion:

The feedwater system inside containment consists of four lines.

are mirror images, as are Lines C and D. The parameters of the

2 portion of the piping system are as listed below.

Lines A and B

ASME Code Class

Design Temperature

^

Operating Temperature

Design Pressure

Operating Pressure

Piping Material

Diameter

Wall Thickness Nominal

Wall Thickness Minimal (ANSI B31.7)

Oxygen Content

pH

Flow Velocity

4450F

4450F

1125 psi

920 psi

A-106 GRB

14-in. OD

0.593 in.

0.510 in.

4 ppb

9.0

22.6 ft/sec @ 100% power

The thinning of the straight sections occurred in Lines A and D.

A number of 45- and 90-degree elbows and

The thickness of the remaining pipe wall

0.46 in. The minimum required thickness

ness at time of installation was 0.593 ir

two 60-degree elbows were also replaced.

in these areas ranged from 0.43 to

is 0.499 in., and nominal wall thick- In the non-safety-related portions of the feedwater lines, a total of 20 pieces

of 14-in. pipe were replaced. This total included elbows as well as some

straight pieces down stream of the elbows or other discontinuities. The

thinning in these segments is very similar to that in the ASME Code Class 2 portion except that the minimum required thickness was 0.44 in.

Trojan personnel also replaced a segment of 30-in. header pipe after identify- ing a localized portion of header pipe that had eroded to 1.018-in. wall.

thickness (a minimum thickness of 1.63 in. was required).

\\'

Attachment

IN 87-36

August 4, 1987

LIST OF RECENTLY ISSUED

INFORMATION NOTICES 1987

InTornation

Notice No.

87-35

87-34

87-33

87-3?

87-31

87-30

87-29

87-28 Dare or

Subject

Issuance

Reactor Trip Breaker,

7/30/87 Westinghouse Model DS-416,

Failed to Open on Manual

Initiation from the Cortrol

PooP

Single Failures in AuxIliary 7/24/87

Feedwater Systems

Applicability of 10 CFR

Part 21 to Nonlicensees

Deficiencies In the Testing

of Nuclear-Grade kctivated

Charcoal.

8locking. Bracing, and

Securing of Radioactive

Materials Packages in

Transportation.

Cracking of Surge Ring

Brackets in Large General

Electric Company Electric

Motors.

Recent Safety-Related

Incidents at Larqe

Irradiators.

Air Systems Problems at

U.S. Light Water Reactors.

7/24/87

7/10/87

7/10/87

7/2/87 Issued to

All nuclear power

reactor facilities

holding an OL or

CP employing W DS-J'6 reactor trip 6reakers.

All holders of an

OL or a CP for

pressurized water

reactor facilities.

All NRC licensees.

All nuclear power

reactor facilities

holding an OL or CP.

All NRC licensees.

All nuclear power

reactor facilities

holding an AL or CP.

6/26/87

All NRC licensees

authorized to possess

and use sealed sources

in large irradiators.

6/27/87

All nuclear power

reactor facilities

holding an OL or CP.

OL u Operating License

CP

  • Construction Permit

UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D.C. 20555

OFFICIAL BUSINESS

PENALTY FOR PRIVATE USE, $300

FlRST CLASS MAIL

POSTAGE

  • FEES PAID

USNRC

WASH. D.C.

PERMIT No.

a4j

IN 87-36 August 4, 1987 The Trojan plant is conducting a failure analysis on the degraded components to

determine the causes and mechanisms involved in the observed wall thinning

event. The NRC is evaluating the data available to determine any generic

implication of the event.

Related Generic Communications:

IE Information Notice 82-22, "Failure in Turbine Exhaust Lines," dated July 9,

1982 provides additional information pertaining to erosion/corrosion in wet

steam piping. Other erosion/corrosion events pertaining specifically to the

feedwater systems (including emergency and auxiliary feedwater) have occurred

in feedwater pump minimum-flow lines, J-tubes in steam generator feedwater

rings, and emergency feedwater supply to a helium circulator.

FE Info mation Notice 86-106, "Feedwater Line Break," was issued December 16,

1986. It described the then-known details of the December 9, 1986 failure of

the suction line to a main feedwater pump at Surry Power Station Unit 2.

Supplement 1 to this information notice, which was issued February 13, 1987, provided additional detail on the failure mechanism. Supplement 2, which was

issued on March 10, 1987, discussed the effects of the system interactions that

resulted from the line break.

NRC Bulletin 87-01, "Thinning of Pipe Wall in Nuclear Power Plants," issued on

July 9, 1987, requested that licensees submit information concerning their

programs for monitoring the thickness of pipe walls in high-energy single-phase

and two-phase carbon steel piping systems.

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

If you have any questions about this matter, please contact the Regional

Administrator of the appropriate NRC regional office or this office.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

Paul C. Wu, NRR

(301) 492-8987 Attachment: List of Recently Issued NRC Information Notices

  • SEE PREVIOUS CONCURRENCES
  • C/OGCB:DOEA:NRR
  • PPMB:ARM

CHBerlinger

TechEd

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07/28/87

07/28/87

  • OGCB.DOEA:NRR
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07/16/87

07/16/87

07/16/87

07/16/87

IN 87-XX

July xx, 1987 The Trojan plant is conducting a failure analysis on the degraded

determine the causes and mechanisms involved in the observed wall

event. The NRC is evaluating the data available and has formed a

determine any generic implication of the event.

components to

thinning

task force to

Related Generic Communications:

IE Information Notice 82-22, "Failure in Turbine Exhaust Lines," dated July 9,

1982 provides additional information pertaining to erosion/corrosion in wet

steam piping. Other erosion/corrosion events pertaining specifically to the

feedwater systems (including emergency and auxiliary feedwater) have occurred

in feedwater pump minimum-flow lines, J-tubes in steam generator feedwater

rings, and emergency feedwater supply to a helium circulator.

IE Information Notice 86-106, "Feedwater Line Break," was issued December 16,

1986. It described the then-known details of the December 9, 1986 failure of

the suction line to the main feedwater pump at Surry Power Station Unit 2.

Supplement 1 to this information notice, which was issued February 13, 1987, provided additional detail on the failure mechanism. Supplement 2, which was

issued on March 10, 1987, discussed the effects of the system interactions that

resulted from the line break.

NRC Bulletin 87-01, "Thinning of Pipe Wall in

July 9, 1987, requested that licensees submit

programs for monitoring the thickness of pipe

and two-phase carbon steel piping systems.

Nuclear Power Plants," issued on

information concerning their

walls in high-energy single-phase

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

If you have any questions about this matter, please contact the Regional

Administrator of the appropriate NRC regional office or this office.

Charles E. Rossi, Director

Division of Operational Event Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

Paul C. Wu, NRR

(301) 492-8987 Attachment: List of Recently Issued IE Information Notices

  • SEE PREVIOUS CONCURRENCES

D/DOEA:NRR

CERossi

07/ /87

  • OGCB:DOEA:NRR
  • ECEB:DEST:NRR

RJKiessel

PCWu

07/16/87

07/16/87 C/OGCB:DOEAiNRR

CHBerling ' if

07/~t/87

  • AC/ECEB:DEST:NRR

CEMcCracken

07/16/87

  • PPMB:ARM

TechEd

07/28/87

  • EAD:DEST:NRR

JRichardson

07/16/87

IN 87-XX

July xx, 1987 The Trojan Power Station is conducting a failure analysis on the degraded

components to determine the causes and mechanisms involved in the observed wall

thinning event. The NRC is evaluating the data available and has formed a task

force to determine any generic implication of the event.

Related Generic Communications:

TE Information Notice 82-22, "Failure in Turbine Exhaust Lines," dated July 9,

1982 provides additional information pertaining to erosion/corrosion in wet

steam piping. Other erosion/corrosion events pertaining specifically to the

feedwater systems (including emergency and auxiliary feedwater) have occurred

in feedwater pump minimum flow lines, J-tubes in steam generator feedwater

rings, and emergency feedwater supply to a helium circulator.

Information Notice 86-106, "Feedwater Line Break," was issued December 16,

1986. It described the, then known, details of the December 9, 1986, failure

of the suction line to the main feedwater pump at Surry Power Station Unit 2.

Supplement 1 to this information notice, which was issued February 13, 1987, provided additional detail on the failure mechanism. Supplement 2, which was

issued on March 10, 1987, discussed the effects of the system interactions

which resulted from the line break.

NRC Bulletin 87-01, "Thinning of Pipe Wall in Nuclear Power Plants," issued on

July 9, 1987, requested that licensees submit information concerning their

programs for monitoring the thickness of pipe walls in high-energy single-phase

and two-phase carbon steel piping systems.

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

If you have any questions about this matter, please contact the Regional

Administrator of the appropriate NRC regional office or this office.

Charles E. Rossi, Director

Division of Operational Event Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

Paul C. Wu, NRR

(301) 492-8987 Attachment: List of Recently Issued IE Information Notices

  • SEE PREVIOUS CONCURRENCES

D/DOEA:NRR

C/OGCB:DOEA:NRR

PPMB:ARJ4 CERossi

CHBerlinger

TechEd

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07/

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07/

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07/1V/87

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07/16/87

07/16/87

07/16/87

07/16/87

.

.

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IN 87-XX

July xx, 1987 Related Generic Communications:

IE Information Notice 82-22, "Failure in Turbine Exhaust Lines," dated July 9,

1982 provides additional information pertaining to erosion/corrosion in wet

steam piping.

Other erosion/corrosion events pertaining specifically to the

feedwater systems (including emergency and auxiliary feedwater) have occurred

in feedwater pump minimum flow lines, J-tubes in steam generator feedwater

rings, and emergency feedwater supply to a helium circulator.

Information Notice 86-106, "Feedwater Line Break," was issued December 16,

1986.

It described the, then known, details of the December 9, 1986, failure

of the suction line to the main feedwater pump at Surry Power Station Unit 2.

Supplement 1 to this information notice, which was issued February 13, 1987, provided additional detail on the failure mechanism. Supplement 2, which was

issued on March 10, 1987, discussed the effects of the system interactions

which resulted from the line break.

NRC Bulletin 87-01, "Thinning of Pipe Wall in

July 9, 1987, requested that licensees submit

programs for monitoring the thickness of pipe

and two-phase carbon steel piping systems.

Nuclear Power Plants," issued on

information concerning their

walls in high-energy single-phase

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

If you have any questions about this matter, please contact the Regional

Administrator of the appropriate NRC regional office or this office.

Charles E. Rossi, Director

Division of Operational Event Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

Paul C. Wu, NRR

(301) 492-8987 Attachment: List of Recently Issued IE Information Notices

OGCB:DOEA:NRR

RJKiessel

07/1)/87 D/DOEA:NRR

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