ML19296D396

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Forwards In-Plant Safety Relief Valve Test, Revision 2,in Response to Item Iib of NUREG-0478
ML19296D396
Person / Time
Site: LaSalle Constellation icon.png
Issue date: 02/28/1980
From: Delgeorge L
COMMONWEALTH EDISON CO.
To: Parr O
Office of Nuclear Reactor Regulation
Shared Package
ML19296D397 List:
References
RTR-NUREG-0478, RTR-NUREG-478 800208, NUDOCS 8003040521
Download: ML19296D396 (1)


Text

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Commonwealth Edison

@ One First National Plaza. Chicago. Ilknojs Acdress Reply to Post Office Box 767 ChlCago, libriors 60690 February 28, 1980 Mr. Olan D. Parr, Chief Light Water Reactors Branch No. 3 Division of Project Management U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

LaSalle County Station Unit 1 In-Plant SRV Test NRC Docket No. 50-373 Reference (a): D. L. Peoples letter to 0. D. Parr dated February 19, 1980

Dear Mr. Parr:

As is indicated in the Commonwealth Edison response to Item II.B of NUREG - 0478 contained in Section 3.4 of the LaSalle County Design Assessment Report (Reference (a)),

in-plant SRV tests will be run during the initial test program for LaSalle County Unit 1. Enclosed for your information are two (2) copies of the Test Plan, Revision 2 dated November 21, 1979.

If there are any questions on this test plan, please direct them to this office.

Very truly yours, v' / -

v , . ~ . :. 9 (

L. O. DelGeorge '

Nuclear Licesning Administrator Bool S6

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