ML20155D613
| ML20155D613 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 05/27/1988 |
| From: | Wigginton D Office of Nuclear Reactor Regulation |
| To: | Dewease J LOUISIANA POWER & LIGHT CO. |
| Shared Package | |
| ML20155D618 | List: |
| References | |
| TAC-67977, NUDOCS 8806150277 | |
| Download: ML20155D613 (4) | |
Text
.
- cuo jog UNITED STATES NUCLEAR REGULATORY COMMISSION o
g t
WASHING TON, D. C. 20655
/
May 27,1988 Docket No. 50-382 Mr. J. G. Dewease Senior Vice President - Nuclear Operations Louisiana Pcwer and Light Company 317 Baronne Street, Mail Unit 17 New Orleans, Louisiana 70112
Dear Mr. Dewease:
SUBJECT:
APPROVAL 0F FRACTURE MECHANICS ANALYSIS OF REACTOR VESSEL FLAK! INDICATIONS IN HOT LEG N0ZZLE TO SHELL WELD - WATERFORD STEAM ELECTRIC STATION, UNIT 3 (TAC NO. 67977)
By letter dated May 16, 1988, the Louisiana Power and Light Ccepany provided results of a recent Inservice Inspection (ISI) examination of v!aterford 3.
Durirg the second refueling outage, ISI examinations of certain reactor vessel welds and ligaments were perfomed in accordance with the ASME Code,Section XI. The examinations were cenpleted on May 9, 1988.
During the scheduled ISI of the reactor vessel, three flaw indications were detected in the nozzle located at 0 degrees that exceeded or approached the acceptance standards of ASME Code,Section XI. To provide enhanced character-ization and sizing of these indications, the Ultrasonic Data Recording and Processing System (UDRPS) was used.
The UDRPS data revealed three indications in the hot leg nozzle to shell weld within the weld at or near the weld / nozzle forging fusion line. The UDRPS examination determined that the three flaws exceed the standards of ASME Code,Section XI. Therefore, the component would be unacceptable for service unless flavs are removed or repaired.
However, as allowed by ASME Code, a fracture mechanics evaluation, needed to demonstrate acceptance for service by evaluation and reexamination, was provided for our approval. We have completed our review.
Our enclosed safety evaluation concludes the following:
1.
The fracture mechanics analysis demonstrates that the three flaw indications in the hot leg nozzle-to-shell weld will not grow during the life of the i
plant to a size that will affect the integrity of the reactor vessel.
8806150277 800527 PDR ADOCK 05000382 P
i 2.
These flaw indications are conditionally acceptable for service and, therefore, recuire augmented inservice inspection during the next three inspecticn periods pursuant to ASME Section XI paragraph Ik'B-2420(b).
Please contact us should you have any questions.
Sin erely, s
)Y
(,
David nton, Project Manager
~
Project Directerate - IV Division cf Peactor Projects - III, IV, V and Special Projects
Enclosure:
Safety Evaluation cc w/ enclosure:
See next page 1
Mr. Jerrold G. Dewease Waterford 3 Louisiana Power & Light Cor.pany cc:
W. Malcolm Stevenson, Esq.
Regional Administrator, Region IV Monroe & Leman U.S. Nuclear Regulatory Commission 1432 Whitney Building Office of Executive Director for New Orleans, Louisiana 70103 Operations 611 Ryan Plaza Drive, Suite 1000 Mr. E. Blake Arlington, Texas 76011 Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW Mr. William H. Spell, Administrator Washington, D.C.
20037 Nuclear Energy Division Office of Environmental Affairs Resident Inspector /Waterford NPS Post Office Box 14690 Post Office Box 822 Baton Rouge, Louisiana 70898 Killona, Louisiana 70066 Mr. Ralph T. Lally President, Police Jury Manager of Quality Assurance St. Charles Parish Middle South Services, Inc.
Hahnville, Louisiana 70057 Post Office Box 61000 New Orleans, Louisiana 70161 Chairman William A. Cross Louisiana Public Service Commission Bethesda Licensing Office One American Place, Suite 1630 3 Metro Center Baton Rouge, Louisiana 70825-1697 Suite 610 Bethesda, Maryland 20814 Mr. R. F. Burski, Acting Nuclear Safety ar.d Pegulatory Affairs Manager Louisiana Power & Light Company 317 Baronne Street New Orleans, Louisiana 70112 1
l s
- 2.
These flaw indications are cenditionally acceptable for service and, therefore, reouire augmented inservice inspection during the next three inspection periods pursuant to ASME Section XI paragraph IWB-2420(b).
Please contact us should you have any questions.
Sincerely, Isf David L. Wigginton, Project Manager Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects
Enclosure:
Safety Evaluation cc w/ enclosure:
See next page 4
DISTRIBUTION Docket File-NRC PDR Local PDR PD4 Reading L. Rubenstein J. Calvo P. Noonan D. Wigginton 0GC-Rockville E. Jordan J. Partlow ACRS (10)
PD4 Plant File 1
PD4/LAI[pt N
PD4/P PD4/D h PNoonan DWigg<nton:sr JCalvo 05/.p/88 05 88 05/1//88