W3P88-0095, Forwards Handbook on Flaw Evaluation,Waterford Unit 3 Reactor Vessel Outlet Nozzle to Shell Welds. NRC Approval of Acceptable Disposition of Ref Three Indications Requested,Per Section XI,IWB-3610(b).Fee Paid

Forwards Handbook on Flaw Evaluation,Waterford Unit 3 Reactor Vessel Outlet Nozzle to Shell Welds. NRC Approval of Acceptable Disposition of Ref Three Indications Requested,Per Section XI,IWB-3610(b).Fee Paid

ML20154D602
Person / Time
Site:	Waterford
Issue date:	05/16/1988
From:	Burski R LOUISIANA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20154D605	List: ML20154D628 W3P88-0095, Forwards Handbook on Flaw Evaluation,Waterford Unit 3 Reactor Vessel Outlet Nozzle to Shell Welds. NRC Approval of Acceptable Disposition of Ref Three Indications Requested,Per Section XI,IWB-3610(b).Fee Paid
References
W3P88-0095, W3P88-95, NUDOCS 8805190259
Download: ML20154D602 (3)

Text

1 6 e P. O. sox eo340 LOUISI POWER AN A

& LlGHT / ai7NEW BAnoNNs SineEr OPLEANS, LOUISIANA 701e0. * (504) 595 3100 NiNSYsN May 16, 1988 W3P88-0095 A4.05 QA Attachment U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Sub;'et: Waterford 3 SES Docket No. 50-382 License No. NPF-38 Evaluation of Indications from Reactor Vessel Inservice Inspection During the Waterford 3 second refueling outage, an ultrasonic examination was performed on the reactor vessel welds and flange ligaments in accordance with the Waterford 3 Ten Year Inservice Inspection Program and Section XI of the ASME Code. The scope of the work included one hundred percent (100%) examination of the two (2) hotleg (outlet) nozzle-to-shell welds, fifty percent (50%) of the flange-to-shell weld, and fifty percent (50%) of the flange ligaments. The examinations were performed in accordance with the 1980 Edition through Winter 1981 Addenda of ASME Section XI. The examinations were completed on May 9, 1988.

During the inservice ultrasonic examination of the hot leg nozzle to shell weld located at 0 degree vessel axis three recordable indications were noted. Two (2) of the indications were detected with a 0 degree, 2.25 mHz longitudinal wave examination from the nozzle bore, and the remaining indication was detected with a 20 degree, 2.25 mHz longitudinal wave examination from the nozzle bore. These indications are clearly located within the weld at or near the weld / nozzle forging fusion line. The 0 degree longitudinal wave indications were determined to meet the i acceptance standards in Table IWB-3512-1 of the ASME Code Section XI, 1980 l Edition through the 1981 Addenda, while the 20 degree longitudinal wave l indication exceeded the allowable limits of Table IWB-3512-1. l In an effort to further characterize these indications, particularly the 20 degree longitudinal wave indication, supplemental examinations were  ;

performed using the Dynacon Ultrasonic Data Recording and Processing System i (UDRPS).

[ON 8805190259 880516 PJR ADOCK 05000382 I ,,

W DCD y [1ec G lSO l "AN EQUAL OPPORTUNITY EMPLOYER" goS-p"68 . 1

d Page 2 W3P88-0095 The UDRPS system is a known automated data recording and processing system '

which has the capability of recording, storing, processing, and imaging ultrasonic test data. UDRPS allows for more extensive recording of data, better visualization of examination data through the use of color-coded images, more flexible manipulation of data, and more consistent examination quality and archival retrieval of past examinations for comparison purposes. With UDRPS, the indications appeared to be rounded, volumetric-type reflectors, most probably deposited during the fabrication process. The indications were evaluated using the six-(6) d0 amplitude drop sizing rather than the fifty percent (50%) DAC sizing. These indications were determined to exceed the acceptance standards in Table IWB-3512-1 of the ASME Section XI, 1980 Edition through the 1981 Winter Addenda.

Accordingly, a fracture mechanics analysis, using the rules of IWB-3600 and the guidelines of Appendix A,Section XI, 1980 Edition through Winter 1981 Addenda, was performed for the three (3) indications. The three (3) l indications identified by both the conventional ultrasonic examinations and .

the UDRPS examinations have been determined to be acceptable by fracture  !

mechanics analysis using the rules of IWB-3600. In accordance with  !

IWB-2420(h), the indications will be re-examined during the next three (3)  !

inspection periods.

Provided with this letter is Enclosure 1, titled, "Handbook on Flaw Evaluation Waterford Unit 3 Reactor Vessel Outlet Nozzle to Shell Welds."

This enclosure provides a detailed discussion of the fracture mechanics ,

analysis including code acceptance criteria, fracture and fatigue growth i analysis methodology and evaluation of transients, including Pressurized l Thermal Shock and Low Temperature Over-pressure Protection. Appendix A of l the enclosure provides a detailed discussion of the fabrication j radiographs, the results of the baseline ultrasonic examination, I supplemental information about UDRPS examinations, a graphical l representation of the indications and acceptance criteria based on the 4

results of the fracture mechanics analysis and applicable figures.

Louisiana Power and Light herewitn submits, pursuant to Section XI, I IWB-3125(b), Enclosure 1, documenting the acceptability of the three (3) indications. Louisiana Power and Light furthermore requests that the NRC approve the acceptable disposition of these three (3) indications based on this evaluation analysis as required by Section XI, IWB-3610(b).

t The current schedule for Modes 1 and 2 is May 29 and 27, 1988 respectively.

5 Louisiana Power and Light respectfully requests that approval be granted 4

expeditiously so as to preclude extension of the outage beyond the current schedule.

4 i

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l

Page 3 W3P88-0095 Pursuant to 10CFR170.21, the required application fee of $150.00 is enclosed. Please contact me or N.S. Carns should there be any questions concerning this submittal. l Very truly yours,

<s4 R.F. Burski Manager - i Nuclear Safety & Regulatory Affairs I l

RFB:RJM:ssf Attachment cc: R.D. Martin, NRC Region IV J.A. Calvo, NRC-NRR 4

D.L. Wigginton, NRC-NRR h1C Resident Inspectors Office E.L. Blake W.M. Stevenson

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CLASS 3 CUSTOMER DES 10NATE3 DISTRIBUTION HANDBOOK ON FLAW EVALUATION WATERFORD UNIT 3 REACTOR VESSEL OUTLET N0ZZLE TO SHELL WELOS Mr.y, 1988 W. H. Bamford R. D. Rishel Y. S. Lee D. Kurek K. R. Balkey G. Wendell Verified By 0# I '

C. B. Bond '

Approved By 4 /< ~ 7 /s w 5:' 5. 'Palusamy, 44anager Structural Materials Engineering Although information contained in this report is non proprietary, no distribution shall be made outside Westinghouse or its licensees without the ,

customer's approval. O K 70 Dt srRt60TE PEG D, Wmpf wroN \

cou vessA77W W/vnt WESTINGHOUSE ELECTRIC CORPORATION ,

POWER SYSTEMS l 4

P.O. BOX 355 PITTSBURGH, PA 15230 4

• • • • 8805190270 880516 PDR ADOCK 05000392 .

$ DCD