ML20206G396

SER Supporting Util Investigation of Employee Concerns as Described in Element Rept 308.03

ML20206G396
Person / Time
Site:	Sequoyah
Issue date:	11/04/1988
From:	NRC OFFICE OF SPECIAL PROJECTS
To:
Shared Package
ML20206G037	List: ML20206G034 ML20206G298 ML20206G302 ML20206G306 ML20206G315 ML20206G319 ML20206G325 ML20206G330 ML20206G337 ML20206G344 ML20206G348 ML20206G352 ML20206G358 ML20206G363 ML20206G366 ML20206G370 ML20206G374 ML20206G380 ML20206G385 ML20206G392 ML20206G396 ML20206G404 ML20206G408 ML20206G410 ML20206G416 ML20206G419 ML20206G426 ML20206G429 ML20206G435 ML20206G438 ML20206G447 ML20206G453 ML20206G457 ML20206G459 ML20206G462 ML20206G466 ML20206G472 ML20206G480 ML20206G486 ML20206G497 ML20206G502 ML20206G509 ML20206G519 ML20206G524 ML20206G529 ML20206G534 ML20206G539 ML20206G543 ML20206G550 ML20206G559 ... further results
References
NUDOCS 8811220261
Download: ML20206G396 (3)

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s UNITED STATES

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[,?' NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C,20S$6 ty~h , ,~/

..... t SAFETY EVALUATION BY THE OFFICE OF SpECIAl. PROJECTS FOR EFPLOYEE CONCERNS SEQUQYAH NUCLEAR PLANT, UNITS 1 AND 2 EPPLOYEE CONCERNS XX-85-017-003. AND -004 DOCKET N05. 50-237. AND 50-238 l

1. SUBJECT Categcry: Operations l i

Subca tegory: Maintenance Element: Corrective haintenance  !

Cer.cerns : xx-05-071-003: The replacerent rain feedwater heaters f were instdlled without postweld teat treatment, as required. [

XX-ES-971-004: The replacement main feedwater heaters  !

were installed such that cold-springing of connected j piping had occurred. t

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!!. SUMARY OF ISSUES f t

f 1. The replacement riain feedwater heaters were installed to the connected pipir.g without post weld beat treatment and this was incorrect as the ,

4 original heaters required post weld heat treatment.

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! 2. The dimensions of the replacement heaters were different f ron  !

j the original heaters and cold-springing of the pipe nay have occurred when the replacement heaters were installed. [

, Ill. EVAL L'ATION The main feedwater heaters are not safety-related equipment. However, this item was reviewed for overall code compliance, f f

hot all of the piping connections to the main feedwater heaters were post weld f heat treated, but those that would be recuired to be so treated by the appli-catie fiele f abrication code, USAS B31.7-1969 as des,-ibed in the FSAR, tecause i

of wall thickness limits, were post weld heat treated as evicenced in the TVA

work plan .'ackages for the installation of the re;1acement heaters. TVA inter-  !

' views with the two engineers who approved this portion of the work and a pipe-  !

j fitter foreman who oversaw the wora revealed no evidence of excessive force having been applied to the piping. The applicable field fabricatior, code,  ;

R 1.7, c;es accress cold sprin;ing, ard states " Cold springirg provides a j l

teneficial effect ir. Assisting a system to attain its ecst favorable position  !

j :ccrer". Cold springing is ar'alyzed cr.ly when it it used to reduce piping  !

j rtaction forces in design.

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O e IV. @ N!!SION The IEC .taff believes that the TVA investigation Of ine employee cer.cerns aas adequate, ar.d their resolution of the suocerns as described in Elemnt heport 308.03 is acceptable.

Principal Centributor: D. E. Smith I

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Ef@LOYEE C0ftCEPNS SPECI AL PROGRAM ELEFENT REPORTS f i

TOP THE SEQUOYAH NUCLEAR PLANT L

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