ML20203D942
| ML20203D942 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/12/1998 |
| From: | Gundrum L NRC (Affiliation Not Assigned) |
| To: | Grigg R WISCONSIN ELECTRIC POWER CO. |
| References | |
| TAC-M99664, NUDOCS 9802260211 | |
| Download: ML20203D942 (5) | |
Text
O February 12, 1998 Mr. Rich:rd R. Grigg Chbf Nuclear Officer Wisconsin Electric Power Company 231 West Michigan Street, Room P379 Milwaukee, WI 53201
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING THE POINT BEACH NUCLEAR PLANT, UNIT 2 THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN REQUEST FOR RELIEF NO. RR-2 23
)
(TAC NO. M99664) 1
Dear Mr. Grigg:
We have reviewed Wisconsin Electric Power Company's October 16,1996, submittal as l
supplemented on November 25,1997, and January 27,1998, for relief request RR-2-23. This request is for relief for Unit 2 from Section XI of the American Society of Mechanical Engineers (ASi.iE) Boiler and Pressure Vessel Code, " Rules for Inservice Examination of Nuclear Power Plant Components," 1986 edition. During the review, the staff determined that additional information was required. Enclosed is the request for additionalinformation (RAl). Please provide your response to these questions by April 10,1998, in addition, to expedite the review process, please send a copy of your RAI response to NRC's contractor, Idaho National l
Engineering and Environmental Laboratory (INEEL), at the following address:
MichaelT, Anderson INEEL Research Center 2151 North Boulevard PO Box 1625 Idaho Falls, Idaho 83415-2209 if you have any questions, please contact me at (301) 415-1380.
Sincerely, Original signed by Linda L. Gundrum, Project Manager Project Directorate 111-1 Division of Reactor Projects -Ill/IV j
i Office of Nuclear Reactor Regulation
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Docket No. 50-301
Enclosure:
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- 2 WASHINoToN, D.C. 30666 4001 February 12, 1998 Mr. Richard R. Grigg Chief Nuclear Officer Wisconsin Electric Power Company 231 West Michigan Street, Room P379 Milwaukee,WI 53201
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING THE POINT BEACH NUCLEAR PLANT, UNIT 2 THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN REQUEST FOR RELIEF NO. RR-2-23 (TAC NO. M99664)
Dear Mr. Grigg:
We have reviewed Wisconsin Electric Power Company's October 16,1996, submittal as supplemented on November 25,1997, and January 27,1998, for relief resquest RR 2-23. This request is for relief for Unit 2 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. During the review, the staff determined that additional information was required. Enclosed is the request for additionalinformation (RAl). Please provide your response to these questions by April 10,1998. In addition, to expedite the review l
process, please send a copy of your RAI response to NRC's contractor, Idaho National Engineering and Environmental Laboratory (INEEL), at the following address:
l Michael T. Anderson INEEL Research Center 2151 North Boulevard PO Box 1625 Idaho Falls, Idaho 83415-2209 If you have any questions, please contact me at (301) 415-1380.
Sincerely, Linda L. Gundrum, Project Manager Project Directorate Ill-1 Division of Reactor Projects -lil/lV Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301
Enclosure:
RAI cc w/ encl:
See next page
Mr. Richard R. Grigg Point Be:ch Nuclerr Plint Wisconsin Electric Power Company Unit Nos.1 and 2 cc:
Emest L. Blake, Jr.
MichaelT. Anderson Shaw, Pittman, Potts & Trowbridge INEEL Research Center 2300 N Street, N.W.
2151 North Boulevard Washington, DC 20037 PO Box 1625.
Idaho Falls, Idaho 83415-2209 Mr. Scott A. Patulski Vice President Point Beach Nuclear Plant Wisconsin Electric Power Company 6610 Nuciear Road Two Rivers, Wisconsin 54241 Mr. Ken Duveneck Town Chairman Town of Two Creeks 13017 State Highway 42 Mishicot, Wisconsin 54228 l
Chairman Public Service Commission of Wisconsin P.O. Box 7854 Madison, Wisconsin 53707-7854 Regional Administrator, Region til U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Resident inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, Wisconsin 54241 Ms. Sarah Jenkins Electric Division Public Service Commission of Wisconsin.
P.O. Box 7854 Madison, Wisconsin 53707-7854
REQUEST FOR ADDITIONAL INFORMATION THIRD 10-YEAR INTERVAL INSERVICE INSPECTION (ISli REQUEST FOR REllEF RR-2-23
- 1. Scone / Status of Review
- Throughout the service life of a water-cooled nuclear power facility,10 CFR 50.55a(g)(4) requires that components (including supports) that are classified as American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Class 1, Class 2, and Class 3 meet the requirements, except design and access provisions and preservice examination requirements, set forth in the ASME Code Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components", to the extent practical within the limitations of design, geometry, and materials of construction of the components. This section of the regulations also requires that inservice examinations of components and system pressure tests conducted during a 120-month inspection interval comply with the requirements in the latest edition and addenda of the Code incorporated by reference in 10 CFR 50.55a(b) on the date 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The components (including supports) may meet requirements set forth in subsequent editions and addenda of the Code that are incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and '
modifications listed therein and subject to Nuclear Regulatory Commission (NRC) approval.
The Code of record for the Point Beach Nuclear Plant, Unit 2, third 10-year ISI interval is the 1986 Edition of the ASME Section XI Code By letter dated October 16,1996, as supplemented on November 25,1997, and January 27,1998, the licensee submitted Request for Relief RR 23 from the requirements of the Code. The available information provided by the licensee has been reviewed by the NRC staff.
2, AdditionalInformation Reauired Based on the above review, the staff has concluded that the following information and/or clarification is required to complete the review of RR-2-23:
A.
Pursuant to 10 CFA 50.55a(g)(5)(iii), the licensee has requested relief from the Code -
coverage requirements for steam generator nozzle-to-safe end welds and associated safe end-to-pipe welds, in general,100% volumetric coverage was obtained from the safe end side, but the examinations were limited from the nozzle / elbow side by the geometric configuration. The licensee has addressed coverage in terms of "one-directional" or "two-directionar axial coverage for reflectors parallel to the weld seam, but has not addressed circumferential coverage for reflectors transverse to the weld seare. In accordance with Section Xl, Appendix lll, Supplement 4 - Austenitic and Dissimilar Metal Welds, angle beam examination for reflectors transverse to the weld shall be performed in two directions covering the minimum area from %-inch from one side of the weld crown to %-inch from the other side of the weld crown, including the crown. Confirm that the circumferential scans were performed on the subject welds to the extent required by the Code.
2-B.
Based on the discussion provided in the November 25,1997, letter, it is not clear if Request for Relief RR 2 23 is for preservice or inservice examinations. The licensee stated:
" Alternative components could not be substituted for examination because this is a preservice examination requirement for the replacement steam generators. The welds were volumetrically examined utilizing radiographic techniques."
Paragraph IWB 2200, Preservice Examination, states, in part, that shop and fold examinations may serve in lieu of the on-site preservice examinations provided that such examinations are conducted under conditions and with equipment and techniques equivalent to those that are expected to be employed for subsequent inservice examinations. It appears that radiographic techniques were used to satisfy the preservice examination requirements for the replacement welds. Provide a discussion regarding the preservice and inservice examinations of these welds and clarify the intent of this request.
The schedule for timely completion of this review requires that the licensee provide, by the requested date, the above requested information and/or clarifications regarding Point Beach Nuclear Plant, Unit 2, Request for Relief No. RR-2 23.
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