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

@ One First National Plaza. Chicago. Ilknojs Commonwealth Edison 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'

/

. ~. :. 9 (

-v,

L. O. DelGeorge '

Nuclear Licesning Administrator Bool S6

///

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