Information Notice 1993-90, Unisolatable Reactor Coolant System Leak Following Repeated Appeated Applications of Leak Sealant

Unisolatable Reactor Coolant System Leak Following Repeated Appeated Applications of Leak Sealant

ML031070175
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:	12/01/1993
From:	Grimes B Office of Nuclear Reactor Regulation
To:
References
IN-93-090, NUDOCS 9311190455
Download: ML031070175 (11)

Ie

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555

December 1, 1993

NRC INFORMATION NOTICE 93-90: UNISOLATABLE REACTOR COOLANT SYSTEM LEAK

Addressees

All holders of operating licenses or construction permits for nuclear power

reactors.

PurDose

The U.S. Nuclear Regulatory Commission (NRC) is issuing this information

notice to alert addressees to an application of an on-line leak sealing

process which substantially degraded the integrity of the reactor coolant

pressure boundary. 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 May 24, 1993, at the Millstone Nuclear Power Station, Unit 2, Northeast

Utilities (the licensee) identified a leak in a body-to-bonnet gasket on

valve 2-CH-442.

This valve is a Velan 2-inch gate valve which is used to

manually isolate the letdown portion of the chemical and volume control system

from the reactor coolant system for maintenance and local leak rate testing of

containment isolation valves. The valve is upstream of the automatic letdown

isolation valves, and itself cannot be isolated from the reactor coolant

system. Between June 4, and August 5, 1993, leak sealant was injected

approximately 30 times in an attempt to stop the leakage from the body-to- bonnet joint. Five sealant injections were performed by Leak Repairs, Inc.,

and the remainder were performed by Furmanite, Inc.; these activities were

performed under the direction of the licensee. The injections had marginal

results; after sealing, the valve would remain leak free for various periods

ranging up to 18 days in length and would then start to leak again.

On June 12, 1993, following the 7th leak-seal injection, technicians attempted

to install a body-to-bonnet peripheral clamp to provide a boundary for the

leak-sealant compound. The clamp could not be installed because of fit-up

problems with the irregularly shaped valve bonnet. The bonnet had been

installed 90 degrees away from its normal orientation, further complicating

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IN 93-90

December 1, 1993 the attempted clamp installation. Subsequent on-line attempts to seal the

leak included mechanical peening to prevent injection material from extruding

out of the gasket area. This peening closed the body-to-bonnet joint.

On August 5, 1993, leak sealant was injected to obtain the dry valve surfaces

required for welding a second (hybrid) clamp across the body-to-bonnet joint.

During the injection, technicians observed that the leakage increased

dramatically, from slight seepage to a 3.1-meter [10-foot] steam jet. The

technicians also reported that the valve bonnet appeared to lift and that one

body-to-bonnet stud moved. In response to the increased leakage, the Director

of Millstone, Unit 2, ordered a controlled normal shutdown. During the

shutdown, the maximum reactor coolant system leakage was 16.3 liters

[4.3 gallons] per minute.

Discussion

When valve 2-CH-442 was disassembled, it was discovered that one stud was

broken. Because the body of valve 2-CH-442 is an unisolatable reactor coolant

system pressure boundary, the broken stud changed the character of the

incident from a routine gasket-related failure to a significant structural

failure. An ABB-CE metallurgical study indicates that the stud broke in

response to loads applied as part of the on-line leak sealing process. The

most likely potential sources of loads were evaluated. These likely load

sources are: (1) drilling, tapping, and injection port installation,

(2)

peening, and (3) injecting. Subsequent testing performed for the licensee

at the ABB-CE facility indicated that stud loads produced by drilling, tapping, and injection port installation were moderate. However, when body- to-bonnet Joints are peened to the point that the edges contact, the adjacent

bolt can be loaded to failure due to the wedging action of the deformed metal.

Inspection revealed that two of the four studs had drill holes in them from

the injection port and clamp installation drilling processes. The broken stud

and one other stud each had 0.49 centimeter [0.19 inch] diameter holes that

penetrated 0.25 centimeter [0.10 inch] and 0.28 centimeter [0.11 inch] deep, respectively. The holes did not appear to contribute to the stud failure.

The licensee had intended to limit the injection port locations to low stress

zones. However, the injection ports had actually been drilled in restricted

high-stress zones located near the studs. Later analysis determined that the

drilling caused very little stress on the studs.

The leak-sealant injection procedure at Millstone permitted some peening

between the body and bonnet to prevent sealant extrusion (it did not allow

peening along the entire perimeter of the valve).

Inspection of valve

2-CH-442 revealed a significant amount of metal moved by the peening process.

Peening essentially obscured the body-to-bonnet interface, leaving a groove- like indentation along the split line, and metal was peened so that it was in

contact with all four bonnet studs. In addition, chisel-like marks were

IN 93-90

' _December 1, 1993 evident around the leak-sealant injection ports where hand peening was

performed. The licensee determined that the extensive peening was responsible

for the stud failure.

The licensee had made no provision to limit the amount of leak sealant

injected into the valve. As a result, a total of approximately 2.16 liters

[0.57 gallon] of leak sealant was injected into the body-to-bonnet joint.

The repeated attempts to seal the valve at Millstone Unit 2 indicated that an

adequate engineering evaluation was not performed. The licensee evaluation

did not adequately consider the effects of the sealing process and the borated

water on the fasteners. Also, the evaluation did not adequately consider the

amount or effect of sealant entering the system after repeated injections.

Further, the evaluation did not adequately consider the operational and safety

consequences of structural failure of the component or the fasteners during

and after the leak-seal attempts. In addition, management and quality

assurance oversight did not identify the failures to follow procedures, the

failures to adhere to engineering documents and the lack of weight given to

personnel safety considerations.

Events such as the one discussed above have the potential to cause a loss-of- coolant accident and to result in personnel injury or death. This event

illustrates the importance of properly performed engineering and safety

evaluations and the importance of considering occupational safety hazards in

support of on-line leak sealant use. When ASME Code Class 1 pressure boundary

components are involved, these considerations are especially important to

public safety.

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: Eric J. Benner, NRR

(301) 504-1171

Geoffrey P. Hornseth, NRR

(301) 504-2756

Charles G. Hammer, NRR

(301) 504-2791 Attachment:

List of Recently Issued NRC Information Notices

\\-

I

I ichment

rtr'93-90

December 1, 1993 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information

Date of

Notice No.

Subject

Issuance

Issued to

93-89

Potential Problems with

BWR Level Instrumentation

Backfill Modifications

11/26/93

All holders of OLs or CPs

for boiling water reactors.

93-88

93-86

93-85 Status of Motor-Operated

Valve Performance Pre- diction Program by the

Electric Power Research

Institute

Fuse Problems with

Westinghouse 7300

Printed Circuit Cards

Identification of Iso- topes in the Production

and Shipment of Byproduct

Material at Non-power

Reactors

Problems with X-Relays

in DB- and DHB-Type

Circuit Breakers Manu- factured by Westinghouse

Determination of Westing- house Reactor Coolant

Pump Seal Failure

11/30/93

11/04/93

10/29/93

10/20/93

10/20/93

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 test and research

reactors.

All holders of OLs or CPs

for nuclear power reactors.

All holders of OLs or CPs

for pressurized water

reactors (PWRs).

93-84

93-83

Potential Loss of Spent

Fuel Pool Cooling

Following A Loss of

Coolant Accident (LOCA)

10/07/93 All holders

for boiling

(BWRs).

of OLs or CPs

water reactors

93-82

Recent Fuel and Core

Performance Problems in

Operating Reactors

10/12/93

All holders of OLs or CPs

for nuclear power reactors

and all NRC-approved fuel

suppliers.

OL = Operating License

CP = Construction Permit

IN 93-90

K_,

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December 1, 1993 evident around the leak-sealant injection ports where hand peening was

performed. The licensee determined that the extensive peening was responsible

for the stud failure.

The licensee had made no provision to limit the amount of leak sealant

injected into the valve. As a result, a total of approximately 2.16 liters

[0.57 gallon] of leak sealant was injected into the body-to-bonnet joint.

The repeated attempts to seal the valve at Millstone Unit 2 indicated that an

adequate engineering evaluation was not performed. The licensee evaluation

did not adequately consider the effects of the sealing process and the borated

water on the fasteners.

Also, the evaluation did not adequately consider the

amount or effect of sealant entering the system after repeated injections.

Further, the evaluation did not adequately consider the operational and safety

consequences of structural failure of the component or the fasteners during

and after the leak-seal attempts. In addition, management and quality

assurance oversight did not identify the failures to follow procedures, the

failures to adhere to engineering documents and the lack of weight given to

personnel safety considerations.

Events such as the one discussed above have the potential to cause a loss-of- coolant accident and to result in personnel injury or death. This event

illustrates the importance of considering occupational safety hazards as well

as the importance of properly performed engineering and safety evaluations in

support of on-line leak sealant use. When ASME Code Class 1 pressure boundary

components are involved, these considerations are especially important to

public safety.

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.

orig /s/'d by BKGrimes

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts:

Eric J. Benner, NRR

(301) 504-1171

Geoffrey P. Hornseth, NRR

(301) 504-2756

Charles G. Hammer, NRR

(301) 504-2791 Attachment:

List of Recently Issued NRC Information Notices

Resident Inspector (DAD) reviewed via E-mail on 10/22/93

• See attached page for previous concurrences

Concurrence page for"--rN 93-90

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11/23/93 P/4/93

[OFFICIAL RECORD LUPYJ

DOCUMENT NAME: 93-90.IN

IN 93-XX

November xx, 1993

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:

Eric J. Benner, NRR

(301) 504-1171

Geoffrey P. Hornseth, NRR

(301) 504-2756

Charles G. Hammer, NRR

(301) 504-2791 Attachment:

List of Recently Issued NRC Information Notices

Resident Inspector (DAD) reviewed via E-mail on 10/22/93

• See Previous Concurrence

OFC

OEAB:DORS

SC/OEAB:DORS

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DATE

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11/19/93

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[OFFICIAL RECORD COPY]

DOCUMENT NAME:MILLSTON.WEN

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IN 93-XX

November xx, 1993 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 Op

ating Reactor Support

Office of Nuc ear Reactor Regulation

Technical contacts: Eric J. Benner, NRR

(301) 504-1171 Geoffrey P. Hornset ,

RR

(301) 504-2756

Charles G. Hammer, RR

(301) 504-2791 Attachment: List of Recently Issu d NRC Informat n Notices

Resident Inspector (DAD) revie d via E-mail on 10/22/

• See Previous Concurrence

OFC

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DATE

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[OFFICIAL RECORD COPY]

DOCUMENT NAME:MILLSTON.WEN

'

IN 93-XX

November xx, 1993 At this time, the licensee is developing significant new information about the

effects of excessive peening. Ongoing laboratory experiments are showing that

when body-to-bonnet joints are peened to the point that the edges contact, the

adjacent bolt can be loaded to failure.

This is apparently due to the wedging

action of the deformed metal.

This information notice requires no specific actio For written response. If

you have any questions about the information in t is notice, please contact

the technical contact listed below or the approp iate Office of Nuclear

Reactor Regulation (NRR) project manager.

Brian

.

Grimes, Director

Divison of Operating Reactor Support

Off e of Nuclear Reactor Regulation

Technical contact: Eric J. Benner,

(301) 504-1171 Attachment: List of Recently Iss ed NRC

m

ormation Notices

Resident Inspector (DAD) eviewed via E-mail on 10/22/93

• See Previous Concurrence

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IN 93-XX

November xx, 1993 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

the technical contact listed below or the appropriate Office of Nuclear

Reactor Regulation (NRR) project manager.

Brian K. G me, Director

Division f Operating Reactor Support

Office

Nuclear Reactor Regulation

Technical co act: Eric J. Benner, NRR

(301) 504-1171 Attachment:

List

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Resident Inspector (DAD) r lewe via E-mail on 10/22/93

• See Previous Concurren

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IN 93-XX

November xx, 1993 This information notice requires no specific action or written response. If

yoU have any questions out the information in this notice, please contact

the technical contact 1 sted below or the appropriate Office of Nuclear

Reactor Regulation (NRR

roject manager.

Brian K.

imes, Director

Division 1 Operating Reactor Support

Office

Nuclear Reactor Regulation

Technical contact:

Eric J. enner, NRR

(301) 50 -1171 Attachment: List of Recently ssued

C Information Notices

Resident Inspector (DAD)

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