ML20040B682

Interim Deficiency Rept Re Welding Performed on Nuclear Safety Class Piping Sys W/O ASME Authorization & W/O Proper Heat Treatments,Originally Reported on 820108.New Piping Installed.Final Rept Will Be Submitted by 820630

ML20040B682
Person / Time
Site:	Waterford
Issue date:	01/18/1982
From:	Mclendon G LOUISIANA POWER & LIGHT CO.
To:	Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
10CFR-050.55E, 10CFR-50.55E, NUDOCS 8201260313
Download: ML20040B682 (4)

Text

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< g g \\ January 18, 1982 a - G D. McLENDON 9;

E J AN 2 51982* $ Senior Vice President r* QRMMWC C ~

.. msa m M1" W3K-82-0026 Q-3-A35.07.41 4 to Mr. Joh . 1 .>, !:egional Adminis tra tor , Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas /6012

SUBJECT:

Waterford SES Unit No. 3 Docket No. 50-382 Interim Report of Significant Construction Deficiency No. 41

" Unapproved Welding"

Reference:

Telcon - L. L. Bass (LP&L) to L. Martin (NRC) on January 8,1982

Dear Mr. Collins:

In accordance with the requirements of 10CFR50.55(e), we are hereby providing two copies of the Interim Report of Significant Construction Deficiency No. 41, " Unapproved Welding."

If you have any questions, please advise.

Very truly yours,

. d. nt '

GDMcL:LLB:grf Attachment ec: 1) Director Of fice of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 (with 15 copies of report) h

2) Director Office of Management

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Information and Program Control g/l U. S. Nuclear Regulatory Commission Washington, D. C. 20555 (with I copy of report) 8201260313 820118 PDR ADOCK 05000382 g PDR

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LOUISIANA POWER & LIGHT COMPANY l

j WATERFORD SES UNIT No. 3 i

Interim Report of Significant Construction Deficiency No. 41 i

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Unapproved Welding Reviewed by ' g [<'Ic v /[M [ D R. J. Milhi'ser - Site Manager Date

, Reviewed by / /[ //

J/ L.' Wills - Project Superintendent ' /

Date l

Reviewed by f/. [(< hM 4/ Hart - Project)/icensing Engineer ~ '

/-/P(( 'Date Reviewed by D' e / ! / 2/9 7

] J[ eB rt it. - ESS Project Engineer [ Date

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Reviewed by a,_ ((/[M /- / h[8--

Jgutierrez-Q.A. e Supervisor Date l

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j January 12, 1982 i

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INTERIM REPORT OF SIGNIFICANT CONSTRUCTION DEFICIENCY NO. 41

" UNAPPROVED WELDING" INTRODUCTION This report is submitted pursuant to 10CFR50.55(e). It describes a deficiency regarding welding performed on nuclear safety class piping systems without the appropriate ASME authorization and without applying proper heat treatments.

This problem is considered reportable under the requirements of 10CFR50.55(e). -

To the best of our knowledge, this problem has not been identified to the j Nuclear Regulatory Commission pursuant to 10CFR21.

DESCRIPTION OF PROBLEM l

Field welds on Component Cooling Spool Pieces 3CC-71A-6 and 3CC-71B-3 Type "D" sleeves were made by Ebasco start-up pipe fitters without proper authoriza-tion to weld to safety class piping. This nonconformance is documented on Non-conforman e Report W3-2971, Revision 1, issued on November 12, 1981.

Welding was performed on Main Stean Line 2MS40-5A-1 on a 1-3/8 inch wall thickness SA 234 WP B-V (SA 516 Gr70; material without employing the 200 F minimum preheat imposed by the ASME ' ode Section III Subsection NC. This weld was also made to a Class 2 spool piece without proper inspection. This nonconformance is documented on Nonconformance Report W3-3202, issued on November 18, 1981.

Welding was performed on 20-inch 900# Valve 2FW-V823A (SA 216 WCB material) in the Feedwater System without proper inspection and without employing the 200 F minimum preheat imposed by the ASME Code Section III Subsection NC.

This nonconformance is documented on Nonconformance Report W3-3206, issued on November 18, 1981.

SAFETY IFTLICATIONS Nonconformance Report W3-2971, Revision 1: If the welds should fail, the capa-bility of the CCW Surge Tank to provide pressure head to the CCW pumps would be lost. Without the CCW pumps, the ability to ensure continuous operation or safe shutdown is jeopardized. Therefore, these welds could adversely affect the safety of the plant.

Nonconformance Report W3-3202: Failure to use the proper preheat without sub-sequent postwel? heat treatment could cause unacceptably hardened areas to ex-ist in the base material heat affected zones adjacent to the weld metal. These areas if left uncorrected might exhibit low fracture toughness properties which would not provide adequate resistance to rapidly propagating fracture. Such fracture might originate during operation in weld defects which were not de-tected because of improper inspection. Failure would cause an increase in energy removal by the steam generator from the reactor coolant system. This causes an increase in core reactivity, which would present a safety hazard.

An additional concern is that steam system piping failures have the potential to release significant amounts of radioactive material. This release in radio-active material, caused by primary-secondary leakage, presents a safety hazard.

Nonconformance Report W3-3206: The same potential problem described in Non-conformance Report W3-3202 exists in this case. Failure could reduce feed-water flow to the steam generator, causing a reactor coolant system heatup.

This RCS heatup has the potential to cause core damage. Therefore, if the i defective welds are not removed, the safety of the plant could be adversely I affected.

CORRECTIVE ACTION The following controls and actions have been taken to preclude recurrence:

(1) Ebasco supervision responsible for coordinating the welding activity i has been directed and instructed on the proper procedure to follow in l order to obtain authorization to perform welding within the scope of Ebasco's Force Account work.

(2) Administrative Site Procedure ASP-IV-48 has been revised to include the Special Processes Group's review of service forms which authorize weld-ing on permanent plant equipment.

Corrective action for the problem description on Nonconformance Report W3-2971, Revision 1, entailed removing a four-foot section of line number 3CC-71A-6 along with the nonconforming welds; and a new section of pipe was installed. This change is documented on Field Change Request CH-1248, Revision

1. Corrective action has been completed and has been verified by Ebasco Quality. Assurance.

Corrective action for the problem descriptions on Nonconformance Reports W3-3202 and W3-3206 involves removing the temporary welds, stress relieving the base material to eliminate any unacceptable hardened areas, and examining the surface by the Magnetic Particle Test Method to ensure that an acceptable surface preparation is achieved. Corrective action is estimated to be com-pleted and a Final Report submitted to the USNRC on or before June 30, 1982.

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LOUISIANA POWER & LIGHT COMPANY j WATERFORD SES UNIT NO. 3 i

-i

Interim Report of i

Significant Construction Deficiency No. 41 J

l Unapproved Welding i

Reviewed by I$ [d R. J. Milhiber - Site Manager

////// L Date Reviewed by r / /[/ //

j J/ L." Wills - Project Superintendent '

Date i

Reviewed by _

_ Mf/. [( h r M'~ /-/('((

4/ Hart - froject)/icensing Engineer ~ / 'Date f /

j Reviewed by '

M Ae / ! / r./9 7 J/ eBruin - E Project Engineer

[ /' Date Reviewed by M M2 /- / b[8--

J[utierrez-Q.A. e Supervisor Date i

d January 12, 1982 l

1 i

i 1

l I

INTERIM REPORT OF SIGNIFICANT CONSTRUCTION DEFICIENCY NO. 41

" UNAPPROVED WELDING" INTRODUCTION This report is submitted pursuant to 10CFR50.55(e). It describes a deficiency regarding welding performed on nuclear safety class piping systems without the appropriate ASME authorization and without applying proper heat treatments. )

This problem is considered reportable under the requirements of 10CFR50.55(e).

To the best of our knowledge, this problem has not been identified to the Nuclear Regulatory Commission pursuant to 10CFR21.

i DESCRIPTION OF PROBLEM Field welds on Component Cooling Spool Pieces 3CC-71A-6 and 3CC-71B-3 Type "D" sleeves were made by Ebasco start-up pipe fitters without proper authoriza-tion to weld to safety class piping. This nonconformance is documented on Non-conformance Report W3-2971, Revision 1, issued on November 12, 1981.

Welding was performed on Main Steam Line 2MS40-5A-1 on a 1-3/8 inch wall thickness SA 234 WP B-W (SA 516 Gr70) material without employing the 200 F minimum preheat imposed by the ASME Code Section III Subsection NC. This weld was also made to a Class 2 spool piece without proper inspection. This nonconformance is documented on Nonconformance Report W3-3202, issued on November 18, 1981.

Welding was performed on 20-inch 900# Valve 2FW-V823A (SA 216 WCB material) in the Fr.edwater System without proper inspection and without employing the 200 F minimum preheat imposed by the ASME Code Section III Subsection NC.

This nonconformance is documented on Nonconformance Report W3-3206, issued on November 18, 1981.

SAFETY IFTLICATIONS Nonconformance Report W3-2971, Revision 1: If the welds should fail, the capa-bility of the CCW Surge Tank to provide pressure head to the CCW pumps would be lost. Without the CCW pumps, the ability to ensure continuous operation or safe shutdown is jeopardized. Therefore, these welds could adversely affect the safety of the plant.

Nonconformance Report W3-3202: Failure to use the proper preheat without sub-sequent postweld heat treatment could cause unacceptably hardened areas to ex-ist in the base material heat affected zones adjacent to the weld metal. These areas if left uncorrected might exhibit low fracture toughness properties which would not provide adequate resistance to rapidly propagating fracture. Such fracture might originate during operation in weld defects which were not de-tected beer.u e of improper inspection. Failure would cause an increase in energy rems val by the steam generator from the reactor coolant system. This causes an increase in core reactivity, which would present a safety hazard.

r __ ____________________________ __ ._

An additional concern is that steam system piping failures have the potential to release significant amounts of radioactive material. This release in radio-active material, caused by primary-secondary leakage, presents a safety hazard.

Nonconformance Report W3-3206: The same potential problem described in Non-conforennee Report W3-3202 exists in this case. Failure could reduce feed-water flaw to the steam generator, causing a reactor coolant system heatup.

Thb: RCS heatup has the potential to cause core damage. Therefore, if the defective welds are not removed, the safety of the plant could be adversely ufrected.

CORRECTIVE ACTION The following controls and actions have been taken to preclude recurrence:

I (1) Ebasco supervision responsible for coordinating the welding activity has been directed and instructed on the proper procedure to follow in order to obtain authorization to perform welding within the scope of Ebasco's Force Account work.

(2) Adminictrative Site Procedure ASP-IV-48 has been revised to include the Special Processes Group's review of service forms which authorize weld-ing on permanent plant equipment. '

Corrective action for the problem description on Nonconformance Report W3-2971, Revision 1, entailed removing a four-foot section of line number 3CC-71A-6 along with the nonconforming welds; and a new section of pipe was installed. This change is documented on Field Change Request CH-1248, Revision

1. Corrective action has been compl.eted and has been verified by Ebasco Quality Assurance.

Corrective action for the problem descriptions on Nonconformance Reports W3-3202 and W3-3206 involves removing the temporary welds, stress relieving the base material to eliminate any unacceptable hardened areas, and examining the surface by the Magnetic Particle Test Method to ensure that an acceptable surface preparation is achieved. Corrective action is estimated to be com-pleted and a Final Report submitted to the USNRC on or before June 30, 1982.

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