ML20072J812
| ML20072J812 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 06/22/1983 |
| From: | Rybak B COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 6792N, NUDOCS 8306300237 | |
| Download: ML20072J812 (2) | |
Text
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Ch Commonwealth Edison
[O
) one First National Plazt, Chicago, Illinois i
J Address Reply 12: P:st Offica Box 767 (j Chicago, Illinois 60690 June 22, 1983 i
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory' Commission Washington, DC 20555
Subject:
Quad Cities Station Unit 1 Request for Extension of Mark I Containment Program Completion Date NRC Docket No. 50-254 Reference (a):
B. Rybak letter to H. R. Denton dated June 15, 1983.
Dear Mr. Denton:
The subject letter requested an extension be granted for the Mark I Containment Program for the following work at Quad Cities Unit 1:
1)
Stiffeners for the Safety Relief Valve Discharge (SRVD) line penetration of the vent pipe.
2)
Stiffeners for the ring girder and the ring girder web extension.
3)
Changes to the T-quencher guide plate bolts.
4)
Reinforcement of the SRVD line below the vent penetration.
5)
Redesign of the SRVD line rigid support in the vent pipe.
6)
Target Rock SRVD line shear lugs.
The attached report analysed the operability of these systems as they currently exist and found that they meet the appropriate operability criteria.
These operability stress limits are defined in Chapter 3.0 of the report.
A comparison of actual stresses *.ersus allowable stresses are found in Chapter 6 and summarized in Table 1.
Based on the comparison of calculated stresses and loads to the operability acceptance criteria contained in this report, the conservative definition of the loads as evidenced by in-plant tests, and the actual plant observations of the successful performance of all components, it is concluded that the containment internal structures and SRVDL piping will safely support the continued operation of the Unit until the next refueling outage.
b as 8306300237 830622 f
PDR ADOCK 05000254 yj P
L-j H. R.-Denton_ June-22, 1983 l
I It is expected'that these modifications will be complete at the next unit outage, currently scheduled for Spring, 1984.
If you have any questions concerning this matter, please contact this office.
.One (1) signed original and forty (40) copies of this letter are onclosed for your use.
Due to the nature of the report, only six (6)
. copies are enclosed.
Very truly yours, l
)
db I-B. Ryb Nuclear Licensing Administrator
~
1m cc::
R. Bevan'- NRR NRC Resident Inspector - Quad Cities 6792N
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