ML19347A865: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
Line 2: Line 2:
| number = ML19347A865
| number = ML19347A865
| issue date = 09/26/1980
| issue date = 09/26/1980
| title = Forwards Interim Technical Evaluation Rept, Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports.
| title = Forwards Interim Technical Evaluation Rept, Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports
| author name = Carfagno S
| author name = Carfagno S
| author affiliation = FRANKLIN INSTITUTE
| author affiliation = FRANKLIN INSTITUTE
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:.     .        -
{{#Wiki_filter:.
1
*/
  */                                                                                                         l
-r-u 2 4
                                                                                          -r- u 2 4
. Franklin Research Center A Division of The Franklin Institute September 26, 1980 United States Nuclear Regulatory Commission Washington, D.C.
      ..    . Franklin Research Center A Division of The Franklin Institute September 26, 1980 United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention:     Mr. Edward J. Butcher, Jr.
20555 Attention:
Mr. Edward J. Butcher, Jr.
Project Officer
Project Officer


Line 32: Line 33:


==Dear Mr. Butcher:==
==Dear Mr. Butcher:==
Enclosed is an Interim Technical Evaluation Report leading to a temporary classification of the above referenced plant as Croup I for fracture-toughness adequacy of S/G and RCP supports.
Enclosed is an Interim Technical Evaluation Report leading to a temporary classification of the above referenced plant as Croup 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 the NRC with a request of the Licensee to inform the NRC when their response will be made.
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 the NRC with a request of the Licensee to inform the NRC when their response will be made.
Very truly yours, i
Very truly yours, i
S. P. Carfa no Project Manager SPC/TCS/cm Enclosure cc: J. R. Fair (also reproducible copy)
S. P. Carfa no Project Manager SPC/TCS/cm Enclosure cc: J. R. Fair (also reproducible copy)
K. R. Wichman                                                                           g A. F. Glagola (letter only)                                                             g s% r
K. R. Wichman g
                                                                                                              \
A. F. Glagola (letter only) g s% r
l 8009300440                                                                                         l The Benjamin Franklin Parkway, Philadelphia. Pa.19103 (215)448-1000 TWX-710 6701889}}
\\
l 8009300440 The Benjamin Franklin Parkway, Philadelphia. Pa.19103 (215)448-1000 TWX-710 6701889}}

Latest revision as of 06:41, 24 December 2024

Forwards Interim Technical Evaluation Rept, Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports
ML19347A865
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 09/26/1980
From: Carfagno S
FRANKLIN INSTITUTE
To: Butcher E
Office of Nuclear Reactor Regulation
Shared Package
ML19347A866 List:
References
CON-NRC-03-79-118, CON-NRC-3-79-118 NUDOCS 8009300440
Download: ML19347A865 (1)


Text

.

  • /

-r-u 2 4

. Franklin Research Center A Division of The Franklin Institute September 26, 1980 United States Nuclear Regulatory Commission Washington, D.C.

20555 Attention:

Mr. Edward J. Butcher, Jr.

Project Officer

Reference:

FRC Project C5257 NRC Contract NRC-03-79-ll8 NRC TAC No.12066 FRC Task No. 160

Title:

FRC Interim TER: Fracture Toughnes.s of Steam Generator and Reactor Coolant Pump Supports - Arkansas Nuclear One Unit 2

Dear Mr. Butcher:

Enclosed is an Interim Technical Evaluation Report leading to a temporary classification of the above referenced plant as Croup 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 the NRC with a request of the Licensee to inform the NRC when their response will be made.

Very truly yours, i

S. P. Carfa no Project Manager SPC/TCS/cm Enclosure cc: J. R. Fair (also reproducible copy)

K. R. Wichman g

A. F. Glagola (letter only) g s% r

\\

l 8009300440 The Benjamin Franklin Parkway, Philadelphia. Pa.19103 (215)448-1000 TWX-710 6701889