ML20206G396

From kanterella
Jump to navigation Jump to search
SER Supporting Util Investigation of Employee Concerns as Described in Element Rept 308.03
ML20206G396
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 11/04/1988
From:
NRC OFFICE OF SPECIAL PROJECTS
To:
Shared Package
ML20206G037 List: ... further results
References
NUDOCS 8811220261
Download: ML20206G396 (3)


Text

_ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _

e.

p# Aq'c.

UNITED STATES s

[ ' '.c. 'i NUCLEAR REGULATORY COMMISSION I

W ASHINGTON, D. C,20S$6

,?'t h,,~/

y~

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

Subca tegory:

Maintenance i

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

(

f SUMARY OF ISSUES 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 original heaters required post weld heat treatment.

4 1

2.

The dimensions of the replacement heaters were different f ron the original heaters and cold-springing of the pipe nay have occurred j

when the replacement heaters were installed.

[

Ill.

EVAL L'ATION The main feedwater heaters are not safety-related equipment.

However, this f

item was reviewed for overall code compliance, 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-fitter foreman who oversaw the wora revealed no evidence of excessive force j

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.

)

I b0 o 27 P

PDC

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

l b

l 5

l i

l I

J l

o i

i l.

xf:

?

I Ef;CLOSUPE 3 l

+

S AFETY EVAL'.".TIONS OF '.NE I

TENNESSEE VALLEY AUTM*' TTY Ef@LOYEE C0ftCEPNS SPECI AL PROGRAM ELEFENT REPORTS f

i TOP THE SEQUOYAH NUCLEAR PLANT L

[

r t

I i

i i

t i

I I

+

I h

i i

e t

-.