ML20235W112
| ML20235W112 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/09/1987 |
| From: | Shelton D TOLEDO EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20235W116 | List: |
| References | |
| 1430, TAC-66377, NUDOCS 8710160010 | |
| Download: ML20235W112 (2) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _. _ _ _ _ _. _
l TOLEDO I
EDISON DONALD C. SHELTON Vra Prinsdent-Nucieer (419] P49?399 Docket No. 50-146 License No. NPF-3 Serial No. 1430 October 9, 1987 United States Nuclear Regulatory Commission Document Control Desk Washington, D. C.
20555 J
Subject:
License Amendment Application for One-Time Extension of the 18 Month Emergency Diesel Generator Surveillance Interval Gentlemen:
The enclosed application requests that the Davis-Besse Nuclear Power Station, Unit No. 1 Operating License, Appendix A, Technical Specifications be revised to reflect the changes attached. The proposed changes involve Section 3/4.8.1, Electrical Power Systems, A.C. Sources, Specifications 4.8.1.1.2d.1, 4.8.1.1.2d.3, and 4.8.1.1.2d.3.(c).
In addition, Specification 4.8.1.2 references Specification 4.6.1.1.2 J
requirements for Modes 5 and 6 operation.
The proposed changes would revise the Technical Specifications to allow a one-time extension in the 18 month surveillance interval for inspection and operability testing of the Emergency Diesel Generators (EDGs) and correction of s typographical error. This extension is necessary to avoid shutdown of the plant to perform this inspection and testing. The last inspection and operability test, for which the interval extension is requested, was performed prior to the eight month extension of the 1986 outage (extended due to the unscheduled Reactor Coolant Pump (RCP) shaft replacement).
Performance of the inspection and operability test requires approximately two weeks tc complete for each EDG.
In order to complete these tests, the plant must be in a shutdown condition (Mode 5 or 6) for either a four week outage er two separate two-week outages. This is based on Technical Specification 4.8.1.2 which requires one EDG to be operable in Modes 5 or 6.
L hb h,k i
d i
THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43652
l l.
Docket No. 50-346 License No. NPF-3 j
Serial No. 1430.
Page 2-s Since restart from the 1986 outage, there has only been one outage of sufficient duration to perform the 18 month inspection and operability test on the EDG. This outage, caused by Reactor Coolant leakage, was initially. scheduled to last only 10 days, which would not have been of sufficient duration to perform the tests. However, during startup, other problems occurred and the unit was shut down, extending the outage to 37 j
days. The 18 month EDG tests were not scheduled at this time due to the
.{
initial projected outage length and the uncertainty of the length of the j
extended outage.
4 The 18 month inspection and operability test for the EDGs, including the 25 percent extension per Technical Specification 4.0.2a, is due by January 3, 1988 fer EDG 1-1 and December 10, 1987 for EDG 1-2.
Based on these dates, a plant shutdown would be required prior to the fifth
)
refueling cutage, presently scheduled to commence February 1, 1988. The i
inspection and testing of both EDGs is proposed to be completed prior to Cycle 6 operation and no later than March 31, 1988 for EDG 1-1 and March 20, 1988 for EDG 1-2, or appropriate Technical Specification Action Statements will be followed. This one-time interval extension would allow performance of the surveillance in a rational and orderly manner during the upcoming fifth refueling outage.
The combined performance of both EDGs, based on the past 100 starts, is 0.99/ demand (which surpasses the industry average of 0.98/ demand). On
'l September 6, 1987, a Davis-Besse plant trip challenged EDG 1-1, which started on loss of essential bus power and operated as required.
1 Toledo Edison requests an expeditious NRC Staff review and that this amendment be issued prior to December 10, 1987 to avoid shutdown of the Davis-Besse Nuclear Power Station.
Enclosed is a check for $150 as required by 10CFR170.12(c) for a License Amendment Application.
Very tru.
- yours, j
W JSL:dem Enclosures cc: DB-1 NRC Resident Inspector 4
A. B. Davis, Regional Administrator (2 copies)
A. W. DeAgazio, NRC/NRR Davis-Besse Project Manager State of Ohio
.79
__ _. _ _ _ _ _ _ _ _ __ _ _ _ _ _ _. _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _