ML20113B557

Requests Approval to Use ASME Code Cases N-524 - Alternative Exam Requirements for Longitudinal Welds in Class 1 & 2 Piping, as Alternative to ASME Section XI Code Requirements in Effect at All Entergy Nuclear Stations

ML20113B557
Person / Time
Site:	Grand Gulf, Arkansas Nuclear, River Bend, Waterford
Issue date:	06/20/1996
From:	Hutchinson C ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-96-00072, GNRO-96-72, NUDOCS 9606270207
Download: ML20113B557 (5)

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ENTERGY Entsrgy Opst tions,lnc.

eo so 7so Pcyt G bson. MS 39150 Tel 601437 2600 C. R. Hutchinson vre F+eemt (Teofor6 Gram Gulf Nix 4w Swm June 20, 1996 Docement Control Desk U.S. Nuclear Regulatory Commission Mail Station Pl-37 Washington, D.C. 20555

Subject:

Use of ASME Code Cases N-524 " Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping" Arkansas Nuclear One- Units 1 and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29 River Bend Station Docket No. 50-458 License No. NPF-47 Waterford 3 Steam Electric Station Docket No. 50-382.

License No. NPF-38 GNRO-96/00072 Gentlemen:

The purpose of this submittal is to request approval pursuant to 10CFR50. 55a (a) (3) , for the use of American Society of Mechanical Engineers  ;

(ASME) Code Case N-524 as an alternative to existing ASME Sr.ction XI Code i requirements currently in ef fect at all Entergy's nuclear s:6tions, i.e.,

Arkansas Nuclear 1 and 2, Grand Gulf, Waterford 3 and River Bend.

Code Case N-524 is contained in the 1995 Edition of Nuclear Code Cases but has not been included in Regulatory Guide 1.147, " Inservice Inspection Code Cases Acceptability - ASME Section XI Division 1."

9606270207 960620 PDR ADOCK 05000313 P PDR 270029 Of m-Y h"*.

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June 20, 1996 GNRO-96/ 00072 Page 2 of 5 Code Case N-524 provides alternative examination volumes of longitudinal piping weldr that eliminates insulation and support removal which is currently required while performing these examinations. The alternative examination volumes are those of longitudinal welds that are most susceptible to service induced degradation which ensures that the existing levels of safety provided by current examinations will not be reduced.

Approval for the use of this code case is requested by August 31, 1996.

Approval of this code case will allow its usage in this and future intervals at each respective facility.

Should you have any questions regarding this request, please contact Riley Ruffin at Grand G f Nuclear Stati n 601-437-2167

/7 Yours ly, <~'

./ f r

r R attachment: Code Case N-524 cc: Mr. R. B. McGehee (w/a)

Mr. N. S. Reynolds (w/a)

Mr. H. L. Thomas (w/o)

Mr. J. W. Yelverton (w/a)

Mr. L. J. Callan (w/a)

Regional Aid nistrator U.S. Nuclear hequlatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 Mr. J. N. Donohew, Project Manager (w/2)

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C. 20555 NRC Senior Resident Inspector (w/a)

Grand Gulf Nuclear Station P. O. Box 756 Bald Hill Road Port Gibson, MS 39150

4 June 20 1996 GNRO-96 /, 00072 Page 3 of 5 cc: NRC Senior Resident Inspector ( w/,a )

Arkansas Nuclear One 1448 S. R. 333 Russellville, AR 72801 NRC Resident Inspector (w/a)

Waterford 3 Steam Electric Station Trailer 426 P. O. Box B Killona, LA 70066 NRC Resident Inspector (w/a)

River Bend Station P. O. Box 1051 St. Francisville, LA 70775 Mr. George Kalman, Project Manager (w/a)

Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Region IV/ANO-1 Mail Stop 13H3 Washington, D.C. 20555 Mr. T. W. Alexion, Project Manager (w/a)

Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Region IV/ANO-2 Mail Stop 13H3 I Washington, D.C. 20555 Mr. C. P. Patel, Project Manager (w/a)

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Region IV/W3 Mail Stop 13H3 Washington, D.C. 20555 Mr. David Wiggington, Project Manager (w/a)

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Region IV/RB Mail Stop 13H3 Washington, D.C. 20555

i June 20, 1996 GNRO-96/ 00072 Page 4 of 5 cc: (cont ' d) Mr. Eugene Imbro (w/a)

CBLA Task Force U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Mail Stop 9Al Washington, D.C. 20555 i

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N-524 CMES OFASME BOH.H MD MSSUM MSEI. CODE AMwevel Date: Ampust 9,1993 1 See NumencelIndex for expiredon l

• and any reemrmeaan denee. ,

Case N 524 Alternative R*==lantion Requirements for Iangitudinal Welds la Class 1 and 2 Piping Section XI, Division 1 Inquiry: What alternative requirements m'ay be ap-plied to the surface and volumetric ernmination of l longitudinal piping welds specified in Table IWB-2500-1, Framiantion Category BJ, Table IWC-2500 1, Examination Categories C-F-1 and C-F-2 (Exam-ination Category C-F prior to Winter 1983 Adden-da), and Table IWC 2520, Framination Category C.

G (1974 Edition, Summer 1975 Addenda)?

Raply: It is the opinion of the Committee that the following shall apply:'

(a) When only a surface mmination is required, i

examination of longitudinal pip,ing welds is not re-  !

quired beyond those portions of the welds within the mmination boundaries of intersecting circumfer-ential welds.

(b) When both surface and volumetric mminn-tions are required, mmination of longitudinal piping

- l welds is not r'equired beyond those portions of the l

welds within the mmination boundaries of inter-  !

secting circumferential welds provided the; following l

requirements are met.

(1) Where longitudinal weMs are specifk d and {

I locations are known, mmmation requirements shall be' met for both transverse and parallel flaws at the intersection of the welds and for that length of '.on-gitudinal weld within the circumferential weld ex-amination volume; (2) Where longitudinal welds are specified but locations are unknown, or the existence of longitu-dinal welds is uncertain, the mmination require-ments shall be met for both transverse-and parallel flaws within the entire mmination volume of inter-secting circumferential welds.

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