NRC-90-0034, Forwards, 1989 Annual Operating Rept for Fermi 2 & Main Steam Piping Dynamic Response Test Results

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Forwards, 1989 Annual Operating Rept for Fermi 2 & Main Steam Piping Dynamic Response Test Results
ML20012B014
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 02/26/1990
From: Sylvia B
DETROIT EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20012B015 List:
References
CON-NRC-90-0034, CON-NRC-90-34 NUDOCS 9003130264
Download: ML20012B014 (1)


Text

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B. Ralph Sylc

, Seneot %ce Pre.ioent

, 6430 North ointe Nghmay Nemport Wohigan 48166 l (313 LB&4150 February 26, 1990 NRC-90-0034 7 U. S. Nuclear Regulatory Commission Attn Document Control Desk Washington. D. C. 20555

Reference:

Fermi 2 NRC Docket No. 50-341 NRC 1.icense No. NPF-43 Subject 1989 Annual Operating Report for Fermi 2 In accordance with Fermi 2 Technical Specification 6.9.1.4 and NRC Regulatory Guide 1.16. the Detroit Edison Company is submitting the Annual Operating Report for the Fermi 2 Nuclear Power Plant for the period of January 1.1989 through December 31,1989 (see Enclosure 1).

The 1989 Fermi 2 Annual Operating Report satisfies the reporting requirements of 10CFR20.407. (Personnel Monitoring Report). Technical Specification 6.9.1.5.a (Annual Exposure Report by Function).

Technical Specification 6.9.1.5.b (Safety / Relief Valve Challenges).

Technical Specification 6.9.1.5.c (Emergency Core Cooling System Outages), and Technical Specification 6.9.1.5.d (Specific Activity Analysis of the Primary Coolant). The 1989 Annual Operating Report also includes a section on service life of the main steam bypass line. This satisfies the commitment stated in Detroit Edison letter VP-86-0154 to the Nuclear Regulatory Commission dated November 7,1986.

In addition. as committed in the Detroit Edison letter NRC-88-0302 dated December 21. 1988, the main steam piping dynamic response test results are enclosed herewith (see Enclosure 2). This test had been deferred from the Startup Test Program to the first subsequent inadvertent turbine trip.

If you have any questions or comments regarding this report, please contact Mr. Girija Shukla at (313) 586-4270.

Sincerely. 3 4/f/

Enclosures (2) cci A. B. Davis R. W. Def ayette W. G. Rogers gf 900313o264 S q g J#

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