ML20009E811

Revised Interim Rept of Significant Const Deficiency 29 Re Inadequate Clearance Between Process Piping Sys & box-type Pipe Supports/Restraints,Initially Discovered on 810423. As-built Gaps Will Be Measured & Analyzed & Mods Performed

ML20009E811
Person / Time
Site:	Waterford
Issue date:	07/14/1981
From:	Aswell D, Milhiser M, Milhiser R, Wills J LOUISIANA POWER & LIGHT CO.
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
10CFR-050.55E, 10CFR-50.55E, W3K81-0257, W3K81-257, NUDOCS 8107280462
Download: ML20009E811 (4)

Text

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LOUISIANA ua OuAnONOE Srnm P O W E F1 & L 1 G H T P O BOX 6008

• NEW OnLCANS. LOUISIANA 70174 * (504) 366-2345 EuS$SysE D L ASWELL July 14, 1981 y,c,p..., %,,

W3K81-0257 Q-3-A35.07.29 Q-3-A35.0.Q1

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Mr. K. V. Seyfrit, Director, Region IV y

,y Office of Inspection and Enforcement

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U. S. Nuclear Regulatory Commission g.

611 Ryan Plaza Drive, Suite 1000 C

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Arlington, Texas 76012 B1 9 5-c O))

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SUBJECT:

Waterford SES Unit 3

's Revised Interim Report of m

Significant Construction Deficiency No. 29

" Inadequate Clearance Between Process Piping Systems and Box-Type Pipe Supports / Restraints"

Reference:

Telecon, L. L. Bass to L. Martin on June 1, 1981

Dear Mr. Seyfrit:

In the above referenced telecon, LP&L committed to revise the interim report on SCD #29. Attached is the revised report which more clearly describes the problem.

Please replace the original report with this revised report.

I If you have any questions, please let us know.

Very truly yours, D. L. Aswell LLB:grf cc:

1) Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 (with 15 copies of report) ep/

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2) Direc tor Office of Management Information and Program Control I

U. S. Nuclear Regulatory Commission

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Washington, D. C. 20555 (with 1 copy of report) 8107280462 810714 PDR ADOCK 05000382 PDR S

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s LOUISIANA POWER & LIGHT COMPANY WATERFORD SES UNIT No. 3 Interim Report of Significant Construction Deficiency No. 29 Inadequate Clearance Between Process Piping Systems And Box-Type Pipe Supports / Restraints W

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l Reviewed by

~ Da't e' R. J. }filhiser, Site Manager

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Reviewed by J/ Ir/ Wills, Project Superintendent Date Revicued,by

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~/5'Yl g/q' J.,Har t, Project Licensing Engineer Date Reviewed by

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R. A.11a'rtnett, Q. A. Site Supervisor Date July 9, 1981 L

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INTERIM REPORT OF SIGNIFICANT CONSTRUCTION DEFICIENCY NO. 29 3

l INADEQUATE CLEARANCE BETWEEN PROCESS PIPING SYSTEMS AND BOX-TYPE PIPE SUPPORTS / RESTRAINTS INTRODUCTION This report is submitted pursuant to 10CFR50.55(e).

It describes deficiencies relative to clearance between process piping systems and box-type supports /

restraints.

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

This problem has not been reported under 10CFR21.

I DESCRIPTION 4

On April 23, 1981, it was estab]

3d that a problem existed with the box-type restraints for process piping beit.g installed by Tompkins-Beckwith, Inc.

The elements of the problem are:

a) Confusing and in some cases incorrect restraint design drawings protice3 by Bergen-Patterson.

b)

Tomptins-Beckwith's Contract. conflicts with the design drawings as to i

the required and allowable gap befwden the pipe and restraint structure.

The criteria entered in Tompkins-Beckwith, Inc. 's contract was 1/16" maximum and 0" minimum, i

c)

Incorrect installation by Tompkins-Beckwith, Inc.

The significant problem which resulted from the above defined problem elements is that the as-built installation has insufficient clearance to allow pipe thermal movement as required.

This problem exists in the following piping systems: Fuel Pool, Containment Spray, Component Cooling Water, Safety Injectfon, Boron Management, Waste Management, Turbine Cooling Water, Nitrogen Gas, Chemical Volume Control, Blowdown, Emergency Generator, Extraction Steam, Condensate, Reactor Cooling, Main Steam, Heater Drain, Air Evacuation and Auxiliary Steam.

The total number of restraints affected is estimated at 1,900.

Of this number, it is estimated that approximately 450 supports will require some form of modification (shim, trim lugs or add gap) in order to make them acceptable.

3 SAFETY IMPLICATIONS If these' deficiencies were lef t uncorrected, possible degradation of safety i

systems could occur.

Such degradation could occur through the exceeding of ASME Code allowable stresses creating the possibility that systems would be overstressed in some way not analyzed in the FSAR. Additionally, these deficiencies present the potential ^for common mode failures within/between systems.

Such failures are not analyzed in the FSAR.

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1 CORRECTIVE ACTION The corrective action plan being undertaken to correct the deficiencies is i

delineated as follows:

j A.

Evaluation 1)

Ebasco Site Support Engineering (ESSE) Hanger Group will measure all as-built gaps.

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2) Analysis of as-built gaps versus calculated thermal movements and maximum expected radial expansion of pipe will be conducted by Ebasco to determine acceptability of the as-built installation.

3) Bergen-Patterson will be requested to comment on technique and logic of Ebasco analysis.

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B.

Corrective Action Implementation 1)

Restraints which require modifications will be remeasured by Tompkins-Beckwith, Inc., after modifications are completed.

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2) Nonconformance Report W3-2644 will be the vehicle used by Tompkins-Beckwith, Inc., to implement corrective action (modifications) and docu-ment as-built gaps of restraints which are modified.

For those restraints not installed to date, the gap criteria has been redefined and distributed through issue of field sketches Series M694 These requirements have been incorporated into the respective Tompkins-Beckwith program procedures'.

Corrective Action will be completed on or before June 30, 1982, at which time the Final Report will be submitted.

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