ML20032B818
| ML20032B818 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 10/22/1981 |
| From: | Sargent C COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, 81-07, 81-7, NUDOCS 8111060393 | |
| Download: ML20032B818 (2) | |
Text
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i pi Commonwealth Edison One First National Plaza. Chicago. Illinois Address Reply to: Post Othce Box 767 Chicago, Illinois 60690 October 22, 1981 e
Mr. J.G. Keppler, Director Directorate of Inspections and Enforcement
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Region III
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Nuclear Regulatory Commission NOjgj, (~ph{.
799 Roosevelt Road Glen Ellyn, IL 60137
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Subject:
LaSalle County Station, Units 1 & 2 Excess Flow Check Valves, d2 Report No. 81-07
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, g,s k NRC Docket Nos. 50-373/374 Mr. Keppler:
Commonwealth Edison notified your of fice on September 22, 1981, Report No. 81-07, of a deficiency regarding the containment low-pressure instrument sensing line excess flow check valves.
That notification was made in accordance with Title 10 of the Code of the Federal Regulations Part 50.55e.
This letter fulfills the thirt" day reporting requirement of that regulation.
This deficiency was discovered during the containment integrated leak rate test at LaSalle County Station.
At that time it was recognized that these excess flow check valves, designed to be closed by the available differential pressure resulting from a sensing line areak immediately downstream of the valve in the event of a LLCA, would not be closed by the differential pressure avallasle should the sensing line break occur at the instrument rather than at a location immediately downstream of the excess flow check valve.
Dragon Valves Incorporated has designed a replacement spring and poppet assembly for these valves in accordance with the revised requirements of Sargent & Lundy's Valve Data Table DT-531, Revision 3.
Installation of these replacement springs and poppet assemblies will allow the excess flow check valves to close with the lower available differential pressure should the sensing line break occur at the instrument itself during a LOCA.
Shipment of the replacement assemblies for Unit 1 is anticipated by November 1, 1981.
We expect to install these assemblies prior to the fuel load of Unit 1; in any event, the assemblies will be installed prior to the requirement for primary containment being established during startup.
Unit 2 assemblies should be shipped by January 1, 1982.
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Mr. J.
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Keppler October 22, 1981 A
Any questions on this report should be directed to this office.
Very truly yours, e e Lcr C.
E.
Sargent Nuclear Licensing Administrator cc:
A. Bournia (NRR-DL)
NRC Resident Insp. - LSCS ECT/ji 0772L
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