ML20134B134
| ML20134B134 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/22/1997 |
| From: | Grigg R WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| VPNPD-97-007, VPNPD-97-7, NUDOCS 9701290294 | |
| Download: ML20134B134 (2) | |
Text
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! h6Cff*fg RICHARD R. GRIGG/ PRESIDENT &
POWER COMPANY CHIEF OPERATING OFFICER CHIEF NUCLEAR OFFICER 231 W Mictugon, Po Box 2046. Mih. W 53201 (414) 221-2108 VPNPD 97-007 January 22,1997 Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mail Station PI-137 Washington, DC 20555 Gentlemen:
DOCKET 50-266 ASME SECTION XI RELIEF REOUESTS RR-1-02 AND RR-1-17 AND UNIT 1 REACTOR VESSEL EXAMINATION POINT BJ.ACH NUCLEAR PLANT UNIT 1 The purpose of this letter is to notify you of our intent to perform a demonstration of the inspection techniques the Wisconsin Electric Power Company (WE) will utilize in perfarmance of the subject relief requests and to inform you of our intent to perform a reactor vessel examination utilizing personnel and procedures qualified in accordance with the Performance Demonstration Initiative (PDI).
Relief requests RR-1-02 and RR-1-17 were submitted for examinations that will be completed in t.ccordance with 10 CFR 50.55a(a)(3)(i). Relief Request RR-1-02 was approved by your letter to WE dated August 27,1992. Relief Request RR-1-17 was submitted for your review by WE letter dated March 1,1996 and is pending your approval. The scope of these examinations is to perform ultrasonic examination of the nozzle-to-pipe we'ds from the inside diameter of the pipe to satisfy the surface examination requirement of Table IWB-2500 (ASME Section XI,1986 Edition, no addenda). The examination techniques used will substitute for the required surface examination and will be capable of detecting surface connected flaws. As specified in the subject relief requests, and committed to in a letter to the Nuclear Regulatory Commission dated October 16,1991, WE will demonstrate the capability of the ultrasonic testing instrumentation and procedures on cracks in a laboratory test block.
WE has contracted with Southwest Research Institute (SWRI) to perform the Point Beach Nuclear Plant, Unit I reactor vessel examination and the examinations specified in the subject relief requests. The reactor vessel examination is scheduled to be performed in the Spring of 1997 (currently scheduled in May 1997). This examination will be performed using procedures and personnel qualified to Supplements 4 and 6 of Appendix VIII (ASME Section XI 1989 Edition, 9701290294 970122
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o VPNPD 97-007 Page 2 January 22,1997 1989 addenda) in accordance with the Performance Demonst.ation Initiative (PDI) program. The i
examination will be performed to the 1986 Edition, no addenda utilizing the provisions in IWA-2240. SWRI will perform an IWA-2240 equivalency demonstration between the PDI 4
program inspection methods that will be used for the reactor vessel examination (already qualified by PDI) and the inspection methods of an examination in accordance with ASME Section XI 1986 Edition, no addenda, and Regulatory Guide 1.150.
The demonstration of the techniques used for the subject relief requests and the IWA-2240 equivalency demonstration are currently scheduled to be performed at the SWRI facility during the week ofMarch 10,1997. If you wish to send representatives to witness these J
demonstrations, please coordinate your attendance with Craig Prothero of WE at (414) 755-6515.
2 If you do not wish to attend the demonstration, the results of the demonstration will be made i
available for your review. If you require any adutional information, please contact us.
Sincerely //
t s
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i Richard R.
rigg President, Chief Operating Officer, and Chief Nuclear Officer i
CTP/rs cc:
NRC Regional Administrator NRC Resident Inspector
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