ML19259C179
| ML19259C179 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 05/07/1979 |
| From: | Reed C COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 7906140253 | |
| Download: ML19259C179 (3) | |
Text
Commonwealth Edison Tb One First National Plaza. Chicago. tilinois Address Reply to: Post Office BE767 F
Chicago. lilinois 60690 May 7, 1979
{$d Mr. James G. Keppler, Director Directorate of Inspection and Enforcement - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Subject:
Zion Station Units 1 and 2 Additional response to IE Bulletin 79-04 NRC Docket Nos. 50-295 and 50-304 References (a):
J. G.
Keppler letter to B. Lee, Jr.
dated March 30, 1979 (b):
C. Reed letter to J. G. Keppler dated May 1, 1979
Dear Mr. Keppler:
As indicated in Reference (b), the following is our response for Zion Station Units 1 and 2 as requested by Reference (a) concerning check valves manufactured by Velan Engineering Corporation.
We have identified the following Velan check valves in the safety systems listed below and have reviewed them for incorrect weights:
Safety Iniection System Valve No.
Size Velan Dwg. No.
SI-9032 3"
78409 SI-8922A 4"
78501 2278 331 SI-8922B 4"
78501 SI-8905A 4"
78501 SI-8905B 4"
78501 IO 1979 79061402.63:( j
Commonwealth Edison NRC Docket Nos. 50-295/304 Mr. James G. Keppler May 7, 1979 Chemical Volume and Control System Valve No.
Size Velan Dwg. No.
VC-8246 3"
78409 VC-8352A 3"
78409 VC-8352B 3"
78409 VC-8379A 3"
78409 VC-8379B 3"
78409 VC-8401 3"
78409 VC-8481A 4"
78501 VC-8481B 4"
78501 Component Cooling System Valve No.
Size Velan Dwg. No.
CC-9486 6"
73908-3 CC-9508 6"
73908-3 CC-9500 3"
73908-1 In each case, the incorrect valve weight (as given by Velan),
was used in the original piping analysis.
The original weight and thermal analysis, for piping systems greater than 2" in diameter, was performed on the computer Program "MEL-21."
The seismic analysis, for piping systems 8" and smaller, was evaluated using simplified seismic curves that detailed a conservative method for spacing seismic supports.
2278 j32
Commonwealth Edison NRC Docket Nos. 50-295/304 Mr. James G. Keppler May 7, 1979 We have reviewed the existing supports for the additional weights imposed (i.e., 25 lbs. additional for 3" valves, 35 lbs. for 4" valves, and 290 lbs. for 6" valves), and have concluded that the additional weights for the 3" and 4" valves have an insignificant effect on the support design and stress levels.
We have reviewed, in detail, the additional weight imposed by the 6" valves on the piping supports and have verified that the support designs are acceptable.
Please address any additional questions you may have concerning this matter to this office.
Very truly yours,
/t.?
Cordell Ree Assistant Vice-President cc:
Director, Division of Reactor Operations Inspection 2278 333