ML20138F905
| ML20138F905 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/18/1985 |
| From: | Williams J TOLEDO EDISON CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| 1199, TAC-60053, TAC-69084, NUDOCS 8510250371 | |
| Download: ML20138F905 (11) | |
Text
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TOLEDO
%ss EDISON Docket No. 50-346 JOE Witu,ws. JR sm,va %.m e -
License No. NCF-3 7,$%ll$
Serial No. 1199 October 18, 1985 Director of Nuclear Reactor Regulation Attention:
Mr. John F. Stolz Operating Reactor Branch No. 4 Division of Licensing United States Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Stolz:
The purpose of this letter is to request Nuclear Regulatory Commission (NRC) approval to use an alternative inspection technique at the Davis-Besse Nuclear Power Station Unit 1 to satisfy the Inservice Pressure Testing requirements of the ASME Code,Section XI, as permitted by 10CFR50.55a(a)(3).
The details of this alternative inspection technique, Instrumented Inspection Technique (IIT), are the subject of a H.A.F.A. International, Inc., Topical Report HAFA 135(P)(A). This topical report is currently under NRC review, and based on a meeting with NRC staff personnel on September 24, 1985, it is our understanding that the topical report will be approved in the near future.
The plant systems identified below have been evaluated in accordance with Section IV of the topical report. Based on these evaluations, it has been determined that the IIT can be implemented on the appropriate portions of the following systems:
Main Steam Auxiliary Feedwater Decay Heat / Low Pressure Injection High Pressure Injection Containment Spray Core Flood Component Cooling Water Service Water Station Drain Steam Gene rator Sampling and Blowdown Main Feedsster Reactor Coolant 8510250371 851018 PDR ADOCK 05000346 0T7 THE TOLEDO EDISON COMPANY EOISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43052 l
Docket No. 50-346 License No. NPF-3 Serial No. 1199 October 18, 1985 Page 2 For the current Davis-Besse Unit 1 outage, we intend to implement the IIT on portions of the Core Flood, Decay Heat, Auxiliary Feedwater and liigh Pressure Injection systems. Although we have chosen to conduct the ASME Section XI Code " System Hydrostatic Test" of IWA-5211(d) on the NSSS portion of the Reactor Coolant System, the IIT may also be implemented selectively within that boundary.
Because we would like to implement the IIT on some of the above systems during the current outage, we request your approval by October 30, 1985.
We are available at your convenience, if needed, to discuss this matter further.
It should be noted that Toledo Edison recognizes the capability of the IIT method to determine intersystem leakage, and therefore, may opt to take credit for this method to satisfy the Inservice Testing Program and Technical Specification requirements where appropriate.
Very truly yours, Q,,s.$ h 2 = e JW/JDE/SGW/bj s cc: DB-1 NRC Resident Inspector