ML20154H179
| ML20154H179 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/08/1988 |
| From: | Shelton D TOLEDO EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20154H182 | List: |
| References | |
| 1582, TAC-69084, NUDOCS 8809210206 | |
| Download: ML20154H179 (12) | |
Text
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TOLEDO
% EDISON DONALD C. SHELTON n.w-w Docket No. 50-346 H**""
License No. NPF-3 Serial No. 1582 September 8, 1988 United States Nuclear Regulatory Commission Document Control Desk Vashington, D. C.
20555
Subject:
Notification of Plans to Use Instrumented Inspection Techniques at the Davis-Besse Nuclear Power Station Gentlemen:
Toledo Edison's letter of April 11, 1988 tSerial No. 1486), notified the NRC of the specific cases where Toledo Edison intended to use Instrumented Inspection Technique (IIT) testing methodology (previously approved by the NRC) during the present refueling outage. The purpose of this letter is to inform the NRC of one additional case for which Toledo Edison intends to utilize IIT during the outage.
This case involves a modificatien to the Auxiliary Feedvater System (AFV).
As discussed with NRC on June 9, 1988, the modification installs flow control valves and cavitating venturis in the AFV pump discharge piping. The IIT methodology for this system was discussed in a telephone conversation with NRC staff members (A. DeAgazio and G. Johnson) on August 26, 1988. The test vill utilize the IIT methodology that was employed and approved by NRC letter dated February 29, 1988 (Serial No. 1486, Reference 1).
In addition to the modification, AFV valve AF3869 vill be replaced due to maintenance problems.
j This valve is within the test boundary of the modifiestion and vill be tested during this IIT test. Any valve repair or replacement vill also be inspected by the applicable Non-Destructive E9 amination per Code requirements prior to OftheIITtest.
O Justification for use of IIT in lieu of conventional hydrostatic testing is identified in the Topical Report HAFA 135 (P-A) under 8
main steam line testing where it eliminates the need to remove valve internals hj CU and bonnets in order to install isolation plugs to prevent pressurizing gg against the check valves. Additionally, use of IIT vill eliminate the
, [th go potential to over pressurize lover pressure rated components due to Q
unidentified intersystem leakage. Attached is a color coded piping and p
instrument diagram identifying the valves and venturis being installed, g4nI O$
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- l 20.0 THE TOLLDO EOSON COYPANY EDSON PLAZA 300 MACSON AVENUE TOLEDO, OHO 43652
o Docket No. 50-346 License No. NPF-3 Serial No. 1582 l
Page 2 If'there are any further questions, please contact Mr. R. V. Schrauder, Nuclear I.icensing Manager, at (419) 249-2366.
Very trul yours,
.L-CSK/ tit Attachment cc A. B. Davis, NRC Regional Administrator A. V. DeAgatio, NRC/NRR DB-1 Project Manager DB-1 Resident Inspector G. Johnson, NRC/NRR D. Jaggar, State of Ohio L. Dykstra, Hartford Insurance l
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