ML19321B310: Difference between revisions

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   .b AlaD:ma Power C;mpany g
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* 600 North 18th street Fost Offica Box 2641 Birm.ngnam. Alacama 35291 Teleonone 205 323-5341 L k hbcW17%?,,                                                            Alabama Power July 25, 1980 Docket No. 50-364 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commissicn Washington, D. C.          20555 Attention: Mr. A. Schwencer JOSEPH M. FARLEY NUCLEAR PLANT - UNIT 2 INSERVICE INSPECTION PROGRAM FOR ASME CODE CLASS 1, 2, AND 3 CCMPONENTS Gentlemen:
AlaD:ma Power C;mpany g
* 600 North 18th street Fost Offica Box 2641 Birm.ngnam. Alacama 35291 Teleonone 205 323-5341 L k hbcW17%?,,                                                            Alabama Power
                                                                            **""
July 25, 1980 Docket No. 50-364 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commissicn Washington, D. C.          20555 Attention: Mr. A. Schwencer JOSEPH M. FARLEY NUCLEAR PLANT - UNIT 2 INSERVICE INSPECTION PROGRAM FOR ASME CODE CLASS 1, 2, AND 3 CCMPONENTS Gentlemen:
The provisions of 10CFR50.55a(g), " Inservice Inspection Requirements,"
The provisions of 10CFR50.55a(g), " Inservice Inspection Requirements,"
stipulates that an inservice inspection program for ASME Code Class 1, 2, and 3 components for the initial 120-month interval of plant commercial operation shall be prepared and submitted to the NRC for review and approval . The regulation states that the program shall be in accordance with the requirements of Section XI of the ASME Code and Addenda incor-porated by reference in paragraph (b) of 10CFR50.55a on the date 12 months prior to the date of the issuance of the operating license, except where specific written relief has been granted by the Commission pursuant to 10CFR50, Section 50.55a(g)(6)(i).
stipulates that an inservice inspection program for ASME Code Class 1, 2, and 3 components for the initial 120-month interval of plant commercial operation shall be prepared and submitted to the NRC for review and approval . The regulation states that the program shall be in accordance with the requirements of Section XI of the ASME Code and Addenda incor-porated by reference in paragraph (b) of 10CFR50.55a on the date 12 months prior to the date of the issuance of the operating license, except where specific written relief has been granted by the Commission pursuant to 10CFR50, Section 50.55a(g)(6)(i).
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                                                                                                 @b fuel load date (date of hsuance of the Operating License) is September 1, 1980. Relief from the inspection requirements of Section XI is requested where full compliance with the requirements of the code is not practical.
                                                                                                 @b fuel load date (date of hsuance of the Operating License) is September 1, 1980. Relief from the inspection requirements of Section XI is requested where full compliance with the requirements of the code is not practical.
In such cases, specific information is provided which identifies the applicable code requirements, justification for the relief request, and the testing method to be used as an alternative.                                          g It is hereby reqJested that the subject program be approved and the          2 ASME Section XI code relief requested be granted pursuant to Section 50.55a (g)(6)(i) of 10CFR50.
In such cases, specific information is provided which identifies the applicable code requirements, justification for the relief request, and the testing method to be used as an alternative.                                          g It is hereby reqJested that the subject program be approved and the          2 ASME Section XI code relief requested be granted pursuant to Section 50.55a (g)(6)(i) of 10CFR50.
                                                                                              ,
                                                                                              '
Yours very,truly,      ,
Yours very,truly,      ,
e  ,
e  ,
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                                                   .,m  W 3 A &<~          ''
                                                   .,m  W 3 A &<~          ''
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O c'
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T0: Mr. A. Schwencer                            July 25, 1980
T0: Mr. A. Schwencer                            July 25, 1980

Latest revision as of 04:26, 1 February 2020

Forwards Inservice Insp Program for Class 1,2 & 3 Components.
ML19321B310
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 07/25/1980
From: Clayton F
ALABAMA POWER CO.
To: Schwencer R
Office of Nuclear Reactor Regulation
Shared Package
ML19321B311 List:
References
TAC-51033, TAC-51062, NUDOCS 8007310330
Download: ML19321B310 (2)


Text

_

- ~

.b AlaD:ma Power C;mpany g

  • 600 North 18th street Fost Offica Box 2641 Birm.ngnam. Alacama 35291 Teleonone 205 323-5341 L k hbcW17%?,, Alabama Power July 25, 1980 Docket No. 50-364 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commissicn Washington, D. C. 20555 Attention: Mr. A. Schwencer JOSEPH M. FARLEY NUCLEAR PLANT - UNIT 2 INSERVICE INSPECTION PROGRAM FOR ASME CODE CLASS 1, 2, AND 3 CCMPONENTS Gentlemen:

The provisions of 10CFR50.55a(g), " Inservice Inspection Requirements,"

stipulates that an inservice inspection program for ASME Code Class 1, 2, and 3 components for the initial 120-month interval of plant commercial operation shall be prepared and submitted to the NRC for review and approval . The regulation states that the program shall be in accordance with the requirements of Section XI of the ASME Code and Addenda incor-porated by reference in paragraph (b) of 10CFR50.55a on the date 12 months prior to the date of the issuance of the operating license, except where specific written relief has been granted by the Commission pursuant to 10CFR50, Section 50.55a(g)(6)(i).

In accordance with these regulations and in response to your letter of February 4,1980, Alabama Power Company hereby submits to the NRC seven (7) copies cf the report entitled " Joseph M. Farley Nuclear Plant -

Unit No. 2 Inservice Inspection Program." The information contained in this report is based on the guidance provided in your February 4, 1980, letter. The program was prepared in accordance with ASME Section XI, 1974 Edition and Addens through Summer 1975, since our current projected

@b fuel load date (date of hsuance of the Operating License) is September 1, 1980. Relief from the inspection requirements of Section XI is requested where full compliance with the requirements of the code is not practical.

In such cases, specific information is provided which identifies the applicable code requirements, justification for the relief request, and the testing method to be used as an alternative. g It is hereby reqJested that the subject program be approved and the 2 ASME Section XI code relief requested be granted pursuant to Section 50.55a (g)(6)(i) of 10CFR50.

Yours very,truly, ,

e ,

.~s -.t @

.,m W 3 A &<~

F. t. Clayton, Jr. -

g FLCj r/JGS:rt 6 l

'7 '

8007310330 I J

._ ~ -

O c'

T0: Mr. A. Schwencer July 25, 1980

Enclosures:

(7) Copies of " Joseph M. Farlye Nuclear Plant -

Unit No. 2 Inservice Inspection Program" cc: Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. W. H. Bradford

.