ML20129A386
| ML20129A386 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/16/1996 |
| From: | Patulski S WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| PBL-96-0218, PBL-96-218, NUDOCS 9610220132 | |
| Download: ML20129A386 (3) | |
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' Electnc POWER COMPANY Point Becch Nuclear Plant 6610 Nuclear ed.Two Rivers.WI 54241
. PBL 96-0218 October 16,1996 Document Control Desk U. S. NUCLEAR REGULATORY COMMISSION Mail Station PI-137 Washington,DC 20555 Gentlemen:
DOCKET 50-301 ASME SECTION XI RELIEF REOUEST RR-2-23 POINT BEACH NUCLEAR PLANT. UNIT 2 In accordance with 10 CFR 50.55a(g)(5)(iv), Wisconsin Electric Power Company requests relief from Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,
" Rules for Inservice Examination of Nuclear Power Plant Components," 1986, edition, no addenda. Tiie
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requirements for which reliefis requested apply to the third inservice inspection interval for Point Beach Nuclear Plant, Unit 2. The third interval began in December 1992 for Unit 2.
The attached relief request, RR-2-23, provides the information needed for the NRC to complete a review and approval as required. If you have any questions or require additional information, please contact us.
Sincerely, I
Scott Patuiski '
General Manager - Nuclear Operations caw A'ITACIIMENT l
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RR-2-23 COMPONENT
- Steam Generators A and B EXAM AREA RC-34-MRCl-Al-05 Safe End to A SG Inlet Nonle RC-36-MRCL-All-01 A A SG Outlet Nonle to Safe End RC 34 MRCL BI-05
. Safe End to B SG Inlet Nonic RC-36-MRCL-Bil-01 A B SG Outlet Nozzle to Safe End ISOMETRIC ISI PRI 2120 ISI PRI-2121 ASME SECTION XI CATEGORY BF ASME SECTION XI ITEM NUMBER B5.70 ASME SECTION XI REOUIREMENT Volumetric and Surface, Figure IWB-2500-8 ASME Code Case N-460 ALTERNATE REOUIREMENT The required surface examinations will be completed. The required volumetric examination will be completed to the extent practical.
REASON FOR PROPOSED ALTERNATE REOUIREMENT PBNP Unit 2 will be replacing both the A and B Steam Generators during the U2R22 outage (Fall 1996). The examination of the components above have been completed to the extent practical as required by the Code. Refracted longitudinal waves were used to perform the examination because of the acoustic properties of the materials involved. The use of refracted longitudinal waves prevents the use of beam reflection to increase the examination volume. Due to geometrical changes in the nonle configuration, complete coverage of the examination volume from the nozzle side could not be obtained.
Coverage obtained was approximately 44% from the nozzle side. Complete coverage from the safe end side was obtained.
Therefore,44% of the weld volume received two-directional coverage and 100% of the weld received one-directional coverage.
t Alternative components could not be substituted for examination because this is a preservice examination requirement for the replacement steam generators.
The attachment details a plot of the coverage obtained. This plot is representative of all four nozzle-to-safe end welds.
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WESTINGHOUSE NUCLEAR SERVICE DMSION NSPECTION SERVICES WELD PROFILE FtANT PONT BEACH UNIT 2
SKETCH 12173 SYSTJCOMP.
SAFE END TO NOZZLE IDENTIFACTION U&V PROCEDURE WIS-ISI-211 REV. O F.C.1 DATE 5-29-96 EXAMINER z
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66% OF REQUIRED EXAMINATION VOL I
NOT EXAMINED
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