ML20004C631

Final Deficiency Rept Re Bergen-Paterson Support Strut Assembly Design Interference Initially Reported on 810213. Design Changes Examined by Bechtel & Confirmed to Be Free of Interference.Stronger Insp & Mfg Controls Implemented

ML20004C631
Person / Time
Site:	Wolf Creek, Callaway
Issue date:	06/01/1981
From:	Seiken S STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM
To:	James Keppler, Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
10CFR-050.55E, 10CFR-50.55E, BLQA-81-42, SLNRC-81-37, NUDOCS 8106040355
Download: ML20004C631 (13)

Text

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SNUPPS Standardised Nusseer Unit Power Ptent System s chok. ch.rrv Ro.d June ', 1981 Rodivelle, Maryland 20060 mu sase0 SLNRC 81-37 FILE: 0491.10.2/M-218A SUBJ: Final Report on Bergen Paterson Support Strut Assembly Design Interference: Report No. 81-1 Mr. James G. Keppler Director, Region III Office of Inspection and Enforcement gx U.S. Nuclear Regulatory Comission 799 'loosevelt Road D b( $3h Glen Ellyn, Illinois 60137 s 7 y Ji., I h "5res,S$iEIv a 2 M 0 5 5816 U.S. Nuclear Regulatory Commission hu.s, Suite 1000, Parkway Central Plaza ,A 7

D 611 Ryan Plaza Arlington, Texas 76012 ,

$'Dg e .

Gentlemen:

On March 17, 1981, an interim report covering d. sign interferences in the Bergen Faterson furnished pipe support strut assemblies for Callaway No. I and Wolf Creek units was forwarded to the NRC Region III and IV, by SNUPPS letter SLNRC 81-015. The transmittal to the NRC indicated that a final report was anticipated by June 1, 1981.

Enclosed with this letter is the final report of the Bergen Paterson pipe support strut assembly cesign interferences. This report is furnished pursuant to requirements under 10CFR50.55(e) and is to be treated as a generic report applicable to Callaway I and Wolf Creek Units. The report defines the scope of the design interference proolem, addresses safety implications and identifies follow-up corrective actions which have either been taken or else are anticipated. These actions should effectively prevent recurrence of these design interferences.

If you have any further questions concerning this matter, please contact the undersigned.

i Very truly yours,

[

l 8106040355 g S. a. Seiken, Manager Quality Assurance

cl SJS

dck:8a3 Enclosure bI }

cc: G. L. Koester, KGE J. Konklin, NRC Region III l D. T. McPhee, KCPL T. E. Vandel, NRC/W.C.

l J. K. Bryan, UE Victor Stello, Jr., Director, Office W. A. Hansen, NRC/Callaway of I&E, USNRC, Washington, D.C.

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' FINAL REPORT 10CFR50.55(e) on POTENTIAL PIPE CLAMP - BRACKET INTERFERENCE

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'BERCEN - PATERSON PIPE SUPPORT STRUT ASSEMBLY with i

MECHANICAL SHOCK ARRESTOR SUPPLIED by .

PACIFIC SCIENTIFIC:

to SNUPPS UNITS r

a Bechtel Power Corporation

- Gaithersburg, Maryland May 26, 1981 l

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ENCLOSURE T0.BLQA-81/42 - 5/20/81' t

SL7DtARY OF CONTENTS 1.0 Introduction 2.0 Description of Reportable Deficiency 3.0 Analysis of Safety Implications

' 4.0 Corrective Action Attachment #1 - Summary of 'PSCo Forward Bracket "Take Out" Dimensions Attachment #2 - Forward Bracket Drawings l

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. ;c - .i ENCLOSURE TO BLQA-81/42 - 5/20/81

. ll 1 SERGEN'- PATERSON '7 10CFR50.55(e) - Final Report it

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INTRODUCTION In accordance with the t.quirements of .10CFR50.55(e). this report is -

preparea to provide a summary of a generic deficiency related to pipe' f clamp:to bracket interference which could hinder.the full _ function l of- Bergen-Paterson pipe support strut assemblies containing Pacific Sc;entific mechanical shock arrestors. Presently, the pipe support. ,

assemblies are designed to provide 'a 12' cone of movement- to

' accommodate thermal and seismic loads.

. In January.1977, Pacific' Ceientific (PSCo) . revised forward brackets (PSCo parts 1801599-03 and 1801597-03)_which reduced the available

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dimensions between the bracket face and .the bearing hole center.

' (see AttacFaent #1). This revision was not identified in the PSCo

- Snobber Design Book issued to Bergen-Paterson and other users until ,

- late February 1981 (See January 1981. Revision, Attachment #2)-  ;

This ' reduced "Take-Out" dimension, when maximum tolerances are used creates an interference between Bergen-Paterson parts 2640 and 2541 ,

. sizes 6 and 15 pipe clamps and the PSCo brackets. Under these circumstances the 12' cone of _ movement may not be achievable, and could. .in some instances, result in overstressing _ of the piping t i! component. , r p . .This deficiency was verbally reported to the NRC Region 1 Office of

-Inspection and Enforcement by SNUPPS on February 13, 1981. The Region I Office agreed to notify 343ffas III.and IV of this problem.

Bergen-Paterson filed a 10CFR Part 21 report with the NRC on March 6,1981 7

and has urged Pacific Scientific to inform their customers of potential interferences resulting from these dimensional changes. As far as is known, Pacific Scientific has filed no reports.

l A list of identification numbers of the assemblies containing the

i. potential interference shipped to the SNUPPS sites was compiled and

sent to both jobsites. Assemblies have been returned to Bergen- ,

h Paterson from Wolf Creek._ Similar arrangements are being made for >

the return of" assemblies from Call ~ -". Bergen-Paterson drawings

, for pipe clamps af fected *oy the P& .ic Scientific changes have been revised and all new manuf acture is being confirmed as free of

. interference.

p 2.0 ' DESCRIPTION OF REPORTABLE DEFICIENCY The Bergen-Paterson snubber assemblies being supplied to the SNUPPS j sites employ a Bergen-Paterson 2640 pipe clamp in combination with a

' Pacific Scientific end bracket assembly. Many of these snubber assemblies are' employed in safety-related piping systems.

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l' 10CPR50.55(e).. Final Report ENCLOSURE TO'BLQA-81/42 -'5/20/81

-BERGEN-PATERSON I '

continued.

The part 2541 anubber assemblies in question contain an interference between the pipe clamp and end bracket assembly which did not . ,

' permit the required thermal.and' seismic movement of supported pipe l sections.

' 3.0 ANALYSIS OF SAFETY' IMPLICATIONS

. t Snubbers that are 'amployed in seismically' designed piping systems must

,  ; permit the pipe to move thermally in the direction of the support ,

. and provide a rigid restraint during a seismic event.. The snubber

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must also permit motion of the piping transversely perpendicular to, i 'the end brackets. This is acheived by allowing a.12' cone of travel-o -at'both ends of the snubber, utilizing ball bushings.

! .The snubbers in question permitted less'than the full 12* cone'- .

specified in Bergen-Paterson's Load Capacity Data Sheets.:- Tee re-striction of pipe movement could have overstressed the pipe. The action of the clamp locking up with the snubber body could have also l~ ~overstressed the snubber during piping movement.

i 4.0 CORRECTIVE ACTION I

The interferences in these snubber assemblies resulted from:

1. PSCo's failure.to notify users when dimensions of its forward

' brackets were revised. '

2. Bergen-Paterson's. failure to identify this revision during the

• i incorporation of the brackets into assemblies.

! All assemblies in the affected sizes supplied to the SNUPPS sites

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after March 4, 1981. include the modified clamp to e iniste the potential for any interference with the PSCo bracket. echtel has 4

been informed that these changes.are also being incorporated into non- i

! SNUPPS' assemblies.

Bergen-Paterson clamps -ffectad by this interference problem which have been released to the sites will be returned to the supplier for modification in 'accordance with .the revised design drawings and

, shipped to the sites.- The design changes have been independently l examined by Bechtel and confirmed to be free of interference.

! Bergen-Paterson Management met with Bechtel and SNUPPS on March 23, F 1981 and committed to a progrra to strengthen and upgrade the control

over design, manufacturing, and subvendor activities. These include

. improved control over PSCo manufacturing; implementation of detailed

. Receiving Inspection of PSco products and auditing and examination of PSCo components placed in storage prior to the identification of l

the interference problem. Bechtel has reviewed the supplie 's up-graded program, observed it in operation and finds it to be satisf actory.

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10CFR50.55(e) Final Report BERGEN-PATERSON. ENCLOSURE TO BLQA-81/42 - 5/20/81 I continued Bergen-Paterson also committed _to perform a final assembly inter-ference check for compliance with the 12' cone of movement require-ment in assembled pipe support strut assemblies. Bechtel has reviewed the supplist's procedur.s for this check and has monitored its implementation and found both to be satisfactory. These chechs will continue for remaining shipments for Callaway 1 and Wolf Creek.

In addition Bechtel visited Bergen-Paterson to confirm the adequacy of the supplier's translation of specification requirements into their design documents. The supplier provided a complate' review of their preduct line to Bechtel for evaluation. Action to strengthen Bergen-Patersori manufacturing and inspection controls have also been implemented to assure that the modified designs are sucessfully inspected.

Based upon the actions taken:and as well as those proposed, this problem is considered to be resolved.

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ENC 1,0SURE TO BLQA - 81/42 - 5/20/81 ATTACHMENT #1 7'

SUMMARY

OF PSCo FOREWARD BRACKET "TAKE-0UT" DIMENSIONS ,

PART #1801597-03

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M  : 1.65" take-out c 1.50" take-out 1/77 and 4/80 revisions 1/81 revision PART #1301599-03

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+ c 1.56" take-out + c 1.30" take-out l

8/76 and 4/80 revisions 1/81 revision NOTE: All dimensions extracted from PSCo drawing information (see attachment #4)

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1801561 .-Q INSTHUC10N MT fCfp, .

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C ELECTRO PLATED ZINC 1 ALL DIMENSIONS ARE hOMINAL EXCEPI THOSE WITH LIMITS Lame--

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INDICATED.

. FORWARD _BRA CKET NOTES m esAs 1801599-03

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