ML20078K231
| ML20078K231 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/27/1995 |
| From: | Maxfield G WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| PBL-95-0031, PBL-95-31, NUDOCS 9502090130 | |
| Download: ML20078K231 (3) | |
Text
s 3
f Wisconsin Electnc i
POWER COMPANY I
Point Beoch Nuclear Plant 6610 Nuclear Rd..Two Rivers WI 54241 (414) 755-2321 j
l PBL 95-0031 January 27, 1995 Document Control Desk U.
S. NUCLEAR REGULATORY COMMISSION Main Station P1-137 Washington, DC 20555 Gentlemen:
DOCKET 50-301 ASME SECTION XI RELIEF REOUEST RR-2-20 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.
The requirements for which relief is 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-2-20, provides the information needed for the NRC to complete a review and approval as required.
Sincerely, Greg Ma field Plant Manager Srm f
Attachnent cc:
NRC Regional Administrator NRC Resident Inspector i e *. n o r m 9502090130 950127 0-PDR ADOCK 05000301 P
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ASME SECTION XI RELIEF REOUEST RR-2-20 POINT BEACH NUCLEAR PLANT, UNIT 2 COMPONENT RPV-17-683 LOWER SHELL TO LOWER HEAD RING EXAM AREA Figure IWB-2500-3 ISOMETRICS i
ISI-PRI-2101
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A.SME SECTION XI CATEGORY B-A ASME SECTION XI ITEM NUMBER Bl.21 ASME SECTION XI REOUIREMENT ASME SECTION XI 1986 EDITION, NO ADDENDA TABLE IWB-2500-1 ITEM NUMBER: Bl.21 Examination Method: Volumetric Extent and Frequency: Accessible length of one weld.
NOTE 2: Includes essentially 100% of the weld length.
FEDERAL REGISTER VOLUME 57 - NO. 152 DATED AUG.
6, 1992 REQUIRES USE OF ASME SECTION XI 1989 EDITION, NO ADDENDA TABLE IWB-2500-1 ITEM NUMBER: Bl.21 Examination Method: Volumetric Extent and Frequency: Accessible length of all welds.
NOTE 2: Includes essentially 100% of the weld length.
ALTERNATE REOUIREMENT PBNP proposes that the percentage requirement of Note 2 be waived for weld RPV-17-683.
RPV-17-683 will be examined to the extent practical taking into account known limitations.
REASON FOR PROPOSED ALTERNATE REOUIREMENT During the Unit 2,
Second 10 Year Interval, reactor vessel examination in 1989, PBNP adopted the selection requirements of ASME Section XI 1989 Edition for Category B-A welds.
PBNP
a e
performed examinations of all of the Category B-A welds during.
the 1989' reactor vessel examination even though this was not a mandated requirement at the time.
Essentially 100% of all welds were examined with the exception of weld RPV-17-683.
Approximately 75% of the weld volume was examined due to-limitations.
Parallel and transverse examinations were limited above the weld by interference from - the four Core Barrel Antirotation Lugs. Transverse examinations are limited because of search unit bridging on the shell to head I
transition.
l 4
In order to achieve the requirements of Note 2
the-1 antirotation lugs would require removal and subsequent reinstallation.
This is not practical and would be very.
detrimental to the reactor vessel.
Prior. to the end of the Second Interval, Federal Register Vol.
57, No. 152, dated August 6, 1992 mandated the use of ASME Section XI 1989 Edition for Category B-A welds.
Based on the reactor vessel examination performed during 1989, PBNP met the requirements for the second 10 year interval.
During the reactor vessel examination scheduled for the Third 10 Year Interval the same physical limitations will exist-which will prevent essentially 100% of the weld volume ~from being examined.
It is expected that approximately 75% of the weld will be examined.
A