ML20003C323

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Forwards BAW-1628 Reactor Vessel Brittle Fracture Analyses During Small Break LOCA Events W/Extended Loss of Feedwater & Revised B&W Operator Guidelines,In Response to NUREG-0737,Item II.K.2.13 & NRC
ML20003C323
Person / Time
Site: Crane Constellation icon.png
Issue date: 02/23/1981
From: Hukill H
METROPOLITAN EDISON CO.
To: Ross D
Office of Nuclear Reactor Regulation
Shared Package
ML20003C324 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.2.13, TASK-TM L1L-022, L1L-22, LIL-22, NUDOCS 8102270717
Download: ML20003C323 (1)


Text

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Post Of fice Box 480 Middletown Pennsylvania 17057 717 944-4041 Writer s Orrect Otat Number February 23, 1981 Li 022 Office of Nuclear Reactor Regulation Attn: Denwood F. Ross, Director U. S. Nuclear Regulatory Commission Washington, D.C.

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Dear Sir:

Three Mile Island Nuclear Station, Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Reactor Vessel Thermal Shock Report Enclosed please find a copy of the B&W generic topical report " Reactor Vessel Brittle Fracture Analyses During Small Break LOCA Events with Extended Loss of Feedwater (BAW-1628)" and the B&W operator guidelines which have been revised to address reactor vessel thermal shock. These enclosures form the basis of our response to NUREG 0737 Item II.K.2.13 and your subject letter to J. H. Taylor (B&W) of July 12, 1979.

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