ML20235K421: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 14: Line 14:
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| page count = 5
| page count = 5
| project = TAC:64435, TAC:64436
| stage = Approval
}}
}}


Line 30: Line 32:
for Steam Generator Nozzle Inside Radiused Sections -
for Steam Generator Nozzle Inside Radiused Sections -
Joseph M. Farley Nuclear Plant, Units 1 and 2 (TACS 64435/64436)
Joseph M. Farley Nuclear Plant, Units 1 and 2 (TACS 64435/64436)
By letter dated January 13, 1987, you requested additional relief from the                  ,
By {{letter dated|date=January 13, 1987|text=letter dated January 13, 1987}}, you requested additional relief from the                  ,
volumetric examination requirements of ASME Code Class 1, 2 and 3 components.              l The specific relief requested is from the volumetric examination of the steam              l generator primary side nozzle inside radiused sections (Item No. B3.2,                      l Category B-D).                                                                              I We previously granted certain reliefs for Unit 1 and 2 requirements, which you requested pursuant to 10 CFR 50.55a(g) in our letters dated December 7, 1979, August 24, 1983, February 10, and March 30, 1984 (one-time relief),
volumetric examination requirements of ASME Code Class 1, 2 and 3 components.              l The specific relief requested is from the volumetric examination of the steam              l generator primary side nozzle inside radiused sections (Item No. B3.2,                      l Category B-D).                                                                              I We previously granted certain reliefs for Unit 1 and 2 requirements, which you requested pursuant to 10 CFR 50.55a(g) in our letters dated December 7, 1979, August 24, 1983, February 10, and March 30, 1984 (one-time relief),
January 10, and December 27, 1985, June 19, and November 17, 1986.
January 10, and December 27, 1985, June 19, and November 17, 1986.
Line 66: Line 68:
Relief from ASME Section XI Volumetric Examination Requirements for Steam Generator Nozzle Inside Radiused Sections -
Relief from ASME Section XI Volumetric Examination Requirements for Steam Generator Nozzle Inside Radiused Sections -
Joseph M. Farley Nuclear Plant, Units 1 and 2 (TACS 64435/64436)
Joseph M. Farley Nuclear Plant, Units 1 and 2 (TACS 64435/64436)
By letter dated January 13, 1987, you requested additional relief from the volumetric examination requirements of ASME Code Class 1, 2 and 3 components.      ,
By {{letter dated|date=January 13, 1987|text=letter dated January 13, 1987}}, you requested additional relief from the volumetric examination requirements of ASME Code Class 1, 2 and 3 components.      ,
The specific relief requested is from the volumetric examination of the steam      l generator primary side nozzle inside radiused sections (Item No. B3.2, Category B-D).
The specific relief requested is from the volumetric examination of the steam      l generator primary side nozzle inside radiused sections (Item No. B3.2, Category B-D).
We previously granted certain reliefs for Unit 1 and 2 requirements, which you requested pursuant to 10 CFR 50.55a(g) in our letters dated December 7, 1979, August 24, 1983, February 10, and March 30, 1984 (one-time relief),          ,
We previously granted certain reliefs for Unit 1 and 2 requirements, which you requested pursuant to 10 CFR 50.55a(g) in our letters dated December 7, 1979, August 24, 1983, February 10, and March 30, 1984 (one-time relief),          ,

Latest revision as of 15:19, 20 March 2021

Forwards Safety Evaluation Granting Relief from ASME Section XI Volumetric Exam Requirements for Steam Generator Nozzle Inside Radiused Sections.Requirements Impractical & Alternative Methods Acceptable
ML20235K421
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 07/08/1987
From: Adensam E
Office of Nuclear Reactor Regulation
To: Mcdonald R
ALABAMA POWER CO.
Shared Package
ML20235K423 List:
References
TAC-64435, TAC-64436, NUDOCS 8707160309
Download: ML20235K421 (5)


Text

E .

"M 0 3 1987 Docket Nos. 50-348 DISTRIBUTION:

and 50-364 Docket File E. Jordan NRC & Local PDRs J. Partlow Mr. R. P. Mcdonald PD21 r/f ACRS (10)

Senior Vice President S. Varga G. Johnson Alabama Power Company G. Lainas ARM /LFMB 1 Post Office Box 2641 E. Adensam GPA/PA j Birmingham, Alabama 35291-0400 P. Anderson T. Barnhart (4) i T. Murley/

Dear Mr. Mcdonald:

E. Reeves (L)

OGC-B J. Sniezek F. Miraglia  ;

Subject:

Relief from ASME Section XI Volumetric Examination Requirements '

for Steam Generator Nozzle Inside Radiused Sections -

Joseph M. Farley Nuclear Plant, Units 1 and 2 (TACS 64435/64436)

By letter dated January 13, 1987, you requested additional relief from the ,

volumetric examination requirements of ASME Code Class 1, 2 and 3 components. l The specific relief requested is from the volumetric examination of the steam l generator primary side nozzle inside radiused sections (Item No. B3.2, l Category B-D). I We previously granted certain reliefs for Unit 1 and 2 requirements, which you requested pursuant to 10 CFR 50.55a(g) in our letters dated December 7, 1979, August 24, 1983, February 10, and March 30, 1984 (one-time relief),

January 10, and December 27, 1985, June 19, and November 17, 1986.

This request, also pursuant to 10 CFR 50.55a(g), is for relief from ASME Code Section XI, as noted above. The enclosed Safety Evaluation delineates the relief, which we hereby grant to allow use of an alternate examination. l The staff has determined that where stated the ASME Code requirements are l impractical, the alternative methods to be performed will provide adequate assurance of the structural integrity of the components evaluated, and pur- ,

suant to 10 CFR 50.55a(a)(3) and 10 CFR 50.55a(g)(6)(i) the grariting of this I relief is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest. In l making this determination, we have given due consideration of tie burden that could result if these requirements were imposed on your facility.

The request for relief complies with the standards and regulations of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules l

l l

8707160309 070703 0 PDR ADOCK 0500 P

Mr. R.P. Mcdonald and regulations. The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I.

A copy of our Safety Evaluation for granting of the relief is enclosed.

Sincerely, Original Signed By Ober G.iide;s m Elinor G. Adensam, Director Project Directorate II-1 Division of Reactor Projects I/II

Enclosure:

As stated cc: w/ enclosure:

See next page

)h .

'$il

  • Prie pusly ncurre hllN)/ ,,

j LA./ :D PI y M: 1:DRPR *0GC *D:P DRPR PAnderson EReev.es/ds f RFonner EAdensam 87 6/29/87 7/01/87

/Q/87

i

.l03 E7 e Docket Nos. 50-348 DISTRIBUTION:

and 50-364 Docket File E. Jordan NRC & Local PDRs J. Partlow Mr. R. P. Mcdonald PD21 r/f ACRS (10)

Senior Vice President S. Varga G. Johnson Alabama Power Company G. Lainas ARM /LFMB Post Office Box 2641 E. Adensam GPA/PA Birmingham, Alabama 35291-0400 P. Anderson T. Barnhart (4)

T. Murley/

Dear Mr. Mcdonald:

E. Reeves (2-)

OGC-B J. Sniezek F. Miraglia

Subject:

Relief from ASME Section XI Volumetric Examination Requirements for Steam Generator Nozzle Inside Radiused Sections -

Joseph M. Farley Nuclear Plant, Units 1 and 2 (TACS 64435/64436)

By letter dated January 13, 1987, you requested additional relief from the volumetric examination requirements of ASME Code Class 1, 2 and 3 components. ,

The specific relief requested is from the volumetric examination of the steam l generator primary side nozzle inside radiused sections (Item No. B3.2, Category B-D).

We previously granted certain reliefs for Unit 1 and 2 requirements, which you requested pursuant to 10 CFR 50.55a(g) in our letters dated December 7, 1979, August 24, 1983, February 10, and March 30, 1984 (one-time relief), ,

January 10, and December 27, 1985, June 19, and November 17, 1986. l This request, also pursuant to 10 CFR 50.55a(g), is for relief from ASME Code l'Section XI, as noted above. The enclosed Safety Evaluation delineates the relief, which we hereby grant to allow use of an alternate examination. -

The staff has determined that where stated the ASME Code requirements are impractical, the alternative methods to be performed will provide adequate assurance of the structural integrity of the components evaluated, and pur-suant to 10 CFR 50.55a(a)(3) and 10 CFR 50.55a(g)(6)(1) the granting of this relief is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest. In  ;

making this determination, we have given due consideration of the burden that i could result if these requirements were imposed on your facility.

The request for relief complies with the standards and regulations of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules I I

. Mr. R.P. Mcdonald and regulations. The Comission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I.

A copy of our Safety Evaluation for granting of the relief is enclosed.

Sincerely,

$, N . WW Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects I/II

Enclosure:

As stated cc: w/ enclosure:

See next page

  • l Mr. R. P. Mcdonald Alabama Power Company Joseph M. Farley Nuclear Plant cc:

Mr. W. O. Whitt D. Biard MacGuineas, Esquire Executive Vice President Volpe, Boskey and Lyons Alabama Power Company 918 16th Street, N.W.

Post Office Box 2641 Washington, DC 20006 Birmingham, Alabama 35291-0400 Charles R. Lowman Mr. Louis B. Long, General Manager Alabama Electric Corporation Southern Company Services, Inc. Post Office Box 550 Post Office Box 2625 Andalusia, Alabama 36420 Birmingham, Alabama 35202 Chai rman Regional Administrator, Region II Houston County Commission U.S. Nuclear Regulatory Commission Dothan, Alabama 36301 101 Marietta Street, Suite 2900 Atlanta, Georgia 30303 Ernest L. Blake, Jr., Esquire Shaw, Pittman, Potts and Trowbridge Claude Earl Fox, M.D.

2300 N Street, N.W. State Health Officer Washington, DC 20037 State Department of Public Health l State Office Building Montgomery, Alabama 36130 Robert A. Buettner, Esquire i l

Balch, Bingham, Baker, Hawthorne, Mr. J. D. Woodard l Williams and Ward , General Manager - Nuclear Plant i Post Office Box 306 Post Office Box 470 l Birmingham, Alabama 35201 Ashford, Alabama 36312 Resident Inspector U.S. Nuclear Regulatory Commission Post Office Box 24 - Route 2 Columbia, Alabama 36319 I

l l