ML20214N815
| ML20214N815 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/25/1986 |
| From: | Williams J TOLEDO EDISON CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| 1323, NUDOCS 8612030756 | |
| Download: ML20214N815 (2) | |
Text
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TOLEDO EDISON Docket No. 50-346 (Oy 31LUA (419) 24sr 2330 License No. NPF-3 F" W "* "33 Serial No. 1323 November 25, 1986 Director of Nuclear Reactor Regulation Attention:
Mr. John F. Stolz PWR Project Directorate No. 6 Division of PWR Licensing-B United States Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Stolz:
During a telephone conversation with Mr. A. W. DeAgazio of your staff on November 14, 1986, Toledo Edison provided information concerning testing of the Davis-Besse Nuclear Power Station Auxiliary Feedwater System, including steam supply lines and steam admission valves to the Auxiliary Feedwater Pump Turbines. This information was in regards to the extensive testing of the Auxiliary Feedwater System during power escalation, and the demonstration of operability for this system.
Specifically, Technical Specification 3.7.1.2 requires the Auxiliary Feedwater System to be operable in Modes 1, 2, and 3.
In accordance with Technical Specification 4.7.1.2a, Mode 3 entry is acceptable for completing operability testing for the Auxiliary Feedwater System.
Testing of steam admission valves and auxiliary feedwater pump turbine has been performed utilizing steam from the oil-fired auxiliary boiler at about 235 psig. The results of this testing were used to benchmark analyses used to predict the expected startup transient behavior of the l
turbines at full steam pressure, which has been determined to be accept-able. However, Mode 3 operation is necessary for attaining full steam l
pressure and flow for final operability testing of these turbines. This testing will be performed as part of a one-time functional test required by Plant Procedure PP 1102.05, " Controlling Procedure for Power Escalation Testing."
Mr. DeAgazio indicated that this approach to testing was reasonable and
(
did not constitute a departure from Technical Specifications.
Further l
conversation with Mr. Paul Byron, Senior Resident Inspector, on November 14, 1986, provided the same conclusion in that this testing is within the approved power escalation program.
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8612030756 861125 PDR ADOCK 05000346 i
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1HE TOLEDO EDISON COWMNY
[DSON PLAZA 300 MADISON ARNUE TOLE DO. UKO N l
E Bocket No. 50-346 License No. NPF-3 Serial No. 1323 November 25, 1986 Page 2 This letter serves to document the aforementioned conversations and our intent to proceed with testing of the aspects of the Auxiliary Feedwater System in accordance with Plant Procedure PP 1102.05 with no Technical Specification requirement being' impacted.
Very truly yours, t
W:RMC:pif V
cc: DB-1 NRC Resident Inspector I
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