ML20132F894

From kanterella
Jump to navigation Jump to search
Responds to Re Info Notice 85-59, Valve Stem Corrosion Failures. No Attempt Made to Single Out Specific Manufacturer.Since Cracks Occurred Prior to Hot Functional Testing,Valves Possibly Defective When Installed
ML20132F894
Person / Time
Issue date: 09/27/1985
From: Jordan E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To: Velan A
VELAN VALVE CO.
References
IEIN-85-059, IEIN-85-59, NUDOCS 8510010429
Download: ML20132F894 (5)


Text

_.

SD 2 71985

&J l c

1 I

Mr. A. K. Velan President Velan Valve Corporation j

Avenue "C" 4

Griswold Industrial Park Williston, Vermont 05495

Dear Mr. Velan:

SUBJECT:

INFORMATION NOTICE 85-59, VALVE STEM CORR 0SION FAILURES I'm responding to your letter, dated August 9,1985, regarding the subject information notice. The message of Information Notice 85-59 was that safety systems may become inoperable through the sudden failure of' components that are not normally inspected. The components were valve stems and shafts made from 410 stainless steel.

There were four instances where the components had similar failures and each involved a different licensee and a different manufacturer, each of whom was identified in the information notice.

In each instance, the valves that failed had a higher hardness than specified by the manufacturer. The events were described in chronological order and Velan was the first manufacturer men-tioned. There was not any attempt to single out any. manufacturer.

The information about the leakage at Oconee was obtained. from our inquiri.es and a paper presented at an American Nuclear Society conference.

In addition to the valve stems that were cracked the entire length and more than half the stem diameter in depth, there were several valves with the seat hardfacing cracked.

]

The seat material was not 410 stainless steel. The cracks were discovered after the valves were exposed to cold (approximately room temperature) water at Oconee. Water at this temperature is not particularly corrosive to 410 stain-less steel or the seat material.

Since the cracks occurred prior to hot functional testing or nuclear service it appears possible that the valves were defective when installed.

1 We trust that this information is responsive to your concerns.

{

Sincerely, Drigind Siga.d tw L L heden 8510010429 B M 7 PDR In PDR Misc Edward L. Jordan, Director Division of Emergency Preparedness and Engineering Response Office of Inspection and Enforcement DISTRIBUTION RHVollmer ELJordan SASchwartz RLBaer AWDromerick PCortland JGPartlow -

BKGrimes GGZech DCSSJ DEPER R/F EGCB R/F PCortland R/F PDR

  • See previous concurrences Mh c
  • DEPER:IE
  • DEPER:IE EPER:IE
  • DEPER:IE DEPER:IE PCortland AWDromerick RLBaer SASchwartz ELJ dan 8/ /85 9/ /85 9/ /85 9/ /85 9//85 l.

~

Mr. A. K. Velan President Velan Valve Corporation Avenue "C" Griswold Industrial Park Williston, Vermont 05495

Dear Mr. Velan:

SUBJECT:

INFORMATION NOTICE 85-59, VALVE STEM CORR 0SION FAILURES l

I'm responding to your letter, dated August 9,1985, regarding the subject infonnation notice.

Information notices are written to inform recipients about potentially_ significant problems. The message of Information Notice 85-59 was that safety systems may become inoperable throu'gh the sudden failure of compo-2 nents that are not normally. inspected. The components were valve stems and shafts made from 410 stainless steel.

L There were four instances where the components had similar failures and each involved a different licensee and a different manufacturer.

In each instance, 4

the valves that failed had a higher hardness than specified by the manufactur-er. The events were described in chronological order and Velan was the first manufacturer mentioned. There was not any attempt to single out any manufacturer.

The infonnation about the leakage at Oconee was obtained from our inquiries and a paper presented at an American Nuclear Society conference.

In addition to the valve stems that were cracked the entire length and more than half the stem diameter in depth, there were several valves with cracked seats. The cracks were discovered after the valves were exposed to cold (approximately room temperature) water at Oconee. Water at this temperature is not.particularly corrosive to 410 stainless steel. The cracks occurred prior to hot functional testing or nuclear service.

~

We trust that this information is responsive to your concerns.

Sincerely, l

Edward L. Jordan, Director Division of Emergency Preparedness and Engineering Response Office of Inspection and Enforcement i

i DISTRIBUTION RHVollmer ELJordan SASchwartz RLBaer AWDromerick PCortland JGPartlow BKGrimes GGZech 90C507 _

DEPER R/F EGCB R/F PCortland R/F i

PDR

  • See previous concurrences
  • DEPER:IE
  • DEPER:IE
  • DEPER:IE
IE DEPER:IE i

PCortland AWDromerick RLBaer hwartz ELJordan l

8/ /85 9/ /85 9/' /85 9/l /85

)

9/ /85 1

i Mr. A. K. Velan President Velan Valve Corporation Avenue "C" Griswold Industrial' Park Williston, Vermont 05495

Dear Mr. Velan:

Subject:

Information Notice 85-59, Valve Stem Corrosion Failures I'm responding to your letter, dated August 9,1985, regarding the subject information notice.

Information notices are written to inform recipients about potentially significant problems. The message of Information Notice 85-59 was that safety systems may become inoperable through_the sudden failure of compo-nents that are not normally inspected. The components were valve stems and shafts made from 410 stainless steel.

There were four instances where the components had similar failures-and each involved a different licensee and a different manufacturer.

In each instance, the valves that failed had a higher hardness than specified by the manufactur-er. The events were described in chronological order and Velan was the first manufacturer mentioned. There was not any attempt to single out any manufacturer.

The information about the leakage at Oconee was obtained from our inquiries and a paper presented at an~American Nuclear Society conference.

In addition to the valve stems that were cracked the entire length and more than half the stem diameter in depth, there were several valves with cracked seats. The cracks were discovered after the valves were exposed to cold (approximately room

~

i temperature) water at Oconee.- Water at this temperature is not particularly 4

corrosive to 410 stainless steel. The cracks occurred prior to hot functional testing or nuclear service.

We trust that this information is responsive to your concerns.

i 4

Edward L. Jordan, Director Division of Emergency Preparedness and Engineering Response i

Office of Inspection and Enforcement i

DISTRIBUTION JMTaylor RHVollmer ELJordan SASchwartz-RLBaer AWDromerick PCortland JGPartlow BKGrimes GGZech DCS-DEPER R/F 4

EGCB R/F PCortland R/F

  • See previous concurrences

/k02

  • DEPER:IE
  • DEPER:IE D PER:IE DEPER:IE DEPER:!E PCortland

'AWDromerick RLBaer SASchwartz ELJordan 8/ /85 9/ /85 9/g/85-9/ /85 9/ /85

W

~

Mr. A. K. Velan Prcsident Velan Valve Corporation Avenue "C" Griswold Industrial Park Williston, Vermont 05495

Dear Mr. Velan:

Subject:

Information Notice 85-59, Valve Stem Corrosion Failures i

Reference:

four letter, dated August 9,1985, same subject 1

Information notices are written to inform recipients about potentially signifi-cant problems. The message of Information Notice 85-59 was that safety systems may become inoperable through the sudden failure of components that are not i

normally inspected. The components were valve stems and shafts made from 410 stainless steel.

There were four instances where the conponents had similar failures and each involved a different licensee and a different manufacturer.

In each instance, the valves that failed had a higher hardness than specified by the manufactur-er. The events were described in chronological order and Velan was.the first manufacturer mentioned. There was not any attempt to single out any-manufacturer.

4 The information about the leakage at Oconee-was obtained from our inquiries and a paper presented at an American Nuclear Society conference.

In addition to the valve stems that were cracked the entire length and more than half the stem j

diameter in depth, there were several valves with cracked seats.

A review of the plant's history showed that the valves leaked fcur. months prior to hot functional testing and never saw nuclear service.

We trust that this information is responsive to your concerns.

Edward L. Jordan, Director Division of Emergency Preparedness and Engineering Response Office of Inspection and Enforcement I

DISTRIBUTION JMTaylor RHVollmer ELJordan SASchwartz RLBaer AWDromerick PCortland JGPartlow BKGrimes GGZech DCS.

DEPER R/F j

EGCB R/F PCortland R/F l

  • See previous concurrences
  • DEPER:IE QEPE - "4 DEPER:IE DEPER:IE DEPER:IE i

Mlfick RLBaer SASchwartz ELJordan g/jt/85 PCortland 8/ /85 9

9/ /85 9/. /85 9/ /85

. _ = - -

=

. - _ _ _ _ =

6 i

Mr. A. K. Velan President Velan Valve Corporation Avenue "C" Griswold Industrial Park Williston, Vermont 05495 i

Dear Mr. Velan:

i

Subject:

Information Notice 85-59, Valve Stem Corrosion Failures

Reference:

Your letter to me, dated August 9,1985, same subject t

Information notices are written to inform recipients about potentially signifi-l 4

cant problems. The message of Information Notice 85-59 was that safety systems may become inoperable through the sudden failure of components that are not normally inspected. The components were valve stems and shafts made from 410 stainless steel.

There were four instances where the components had similar failures and each

~

involved a different licensee and a different manufacturer.

In each instance, the valves that failed had a higher hardness than specified by the manufactur-er. The events were described in chronological order and Velan was the first manufacturer mentioned. There was not any attempt to single out any j

manufacturer.

1 j

The information about the leakage at Oconee was obtained from an informal paper presented by a Duke Power Company management official.

In addition to the 4

valve stems that were cracked the entire length and more than half the stem j

diameter in depth, there were several valves with cracked seats.

A review of the plant's history showed that the valves leaked four months prior to hot functional testing. The corrosion rate should be lower in warm water, than in nuclear service.

1 We trust that this information is responsive to your concerns.

4 i

Edward L. Jordan,-Director Division of Emergency Preparedness i

and Engineering Response Office of Inspection and Enforcement DISTRIBUTION JMTaylor RHVollmer ELJordan SASchwartz RLBaer AWDromerick l

PCortland JGPartlow

}

BKGrimes GGZech i

DCS DEPER R/F l

EGCB R/F PCortland R/F l

DEP

I DEPER:IE DEPER:IE DEPER:IE DEPER:IE PC rt and AWDromerick RLBaer SASchwartz ELJordan i

g/gs/85 9/ /85 9/ /85 9/ /85-9/ /85

-