ML100340719

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Forwards Interim Technical Evaluation Rept, Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports.
ML100340719
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 09/26/1980
From: Carfagno S
Franklin Institute
To: Butcher E
Office of Nuclear Reactor Regulation
Shared Package
ML100340720 List:
References
CON-NRC-03-79-118, CON-NRC-3-79-118 NUDOCS 8009300432
Download: ML100340719 (1)


Text

nu 7 nklin Research Center A Division of The Franklin Institute September 26, 1980 United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. Edward J.

Project Officer Butcher, Jr. /

Reference:

FRC Project C5257 NRC Contract NRC-03-79-118 NRC TAC No. 08776 FRC Task No. 169

Title:

FRC Interim TER: Fracture Toughness of Steam Generator and Reactor Coolant Pump Supports - Indian Point Unit 2

Dear Mr. Butcher:

Enclosed is an Interim Technical Evaluation Report leading to a temporary classification of the above referenced plant as Group I for fracture-toughness adequacy of S/G and RCP supports.

A final Technical Evaluation Report for this plant will be prepared upon receipt and review of the Licensee's response to a request-for-information )

letter which we understand has been issued by NRC on a 30-day request for response basis.

Very truly yours, S. P.carfa no Project Manager SPC/TCS/cm Enclosure cc: J. R. Fair (also reproducible copy)

K. R. Wichman A. F. Glagola (letter only)

T S,0 8009S00 432 The Benjamin Franklin Parkway, Philadelphia, Pa. 19103 (215) 448-1000 TWX-710 670 1889