ML20206G396
| ML20206G396 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah |
| Issue date: | 11/04/1988 |
| From: | NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20206G037 | List:
|
| 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
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
-.