ML20002D395
| ML20002D395 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, LaSalle  |
| Issue date: | 01/06/1981 |
| From: | Kausch T, Rausch T COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 9425A, IEB-80-21, NUDOCS 8101200528 | |
| Download: ML20002D395 (2) | |
Text
g f[Q 6:
m
/
n Commonwealth Edison b;
\\
One First Natenal Plata Chicago. Cinois
{
Tja Addr'ss Reply 11 Post Othc2 Box 767 W,
U s(j Chicago, lihnois 60690
[(ji}
cj sa
=
S oo
~S o
E G
- p
~4 January 6, 1981 Mr. James G. Keppler, Director Directorate of Inspection and Enforcement - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Subj e ct :
LaSalle County Station Units 1 and 2 Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Response to IE Bulletin 80-21
" Valve Yokes Suppliec by Malcolm Foundry Ccmpany, In c. "
NRC Do cket Nos. 50-373/374, 50-454/455, and 50-456/457 Reference (a):
J. G. Keppler letter to C. Reed dated November 6, 1980.
Dear Mr. Keppler:
Reference (a) transmitted IE Bulletin 80-21 requesting a response concerning potentially faulty valve parts cast by Malcolm Foundry Company, Incorporated.
Commonwealth Edison has determined, by contacting the manufacturers of our safety-related valves, that no valve yokes manufactured by Malcolm Foundry are in use, or planned for use at Byron or Braidwood Stations.
It has been discovered that LaSalle County Station contains 138 safety-relateo valves with yokes cast by Malcolm Founory, In co rp ora t ed.
The valves were manufactured by the Anchor Darling Valve Company.
This information was reported to NRC Region III in accordance with 10CFR50.55(e) on De cember 18, 1980.
An engineering evaluation has revealed that no adequate nondestructive testing methodology exists to determine the mechanical properties of these components.
It was subsequently decided that all of the potentially faulty yokes would be replaced.
Affected Unit I valves, valves common to both units, and Unit 2 valves necessary for Unit I startup will be given priority status such that replacement of these yokes can be completed before Unit 1 fuel load (now s cheduled for June,1981).
The remaini.)g af fe cted yokes will be replaced prior to Unit 2 fuel load.
i jgu'O T 8UI i
61010.20 N Q
p-Due to the discovery of problems with Anchor-Darling valves, additional verification of the results of our manufacturer's survFy will be undertaken for LaSalle County Station.
The NRC will be netified should any valve be found to contain the potentially faulty material.
Please address any questions you may have concerning this matter to this office.
Very truly yours,
$A~./K m Thomas J. Rausch Nuclear Licensing Administrator Special Projects cc:
NRC Of fice of Inspection and Enforcement Division of Reactor Construction Inspection d
Washington, DC 20555 RIII Inspector - LaSalle 9425A