ML20198D548

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Forwards Insp Rept 50-341/98-15 on 980922-1109.Noncited Violation Re Failure to Follow Operating Procedure & Deenergizing of Engineered Safety Features Bus Was Identified
ML20198D548
Person / Time
Site: Fermi 
Issue date: 12/07/1998
From: Anton Vegel
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Gipson D
DETROIT EDISON CO.
Shared Package
ML20198D551 List:
References
50-341-98-15, NUDOCS 9812230118
Download: ML20198D548 (3)


See also: IR 05000341/1998015

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UNITED STATES

NUCLEAR REGULATORY COMMISSION

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801 WARRENvlLLE ROAD

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LISLE, ILLINOIS 60532-4351

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December 7, 1998

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Mr. D. R. Gipson

Senior Vice President

Nuclear Generation

The Detroit Edison Company

6400 North Dixie Highway

Newport, MI 48166

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SUBJECT:

FERMI INSPECTION REPORT 50-341/98015(DRP)

Dear Mr. Gipson:

On November 9,1998, the NRC completed an inspection at your Fermi 2 reactor facility. The

enclosed report presents the results of that inspection. During the 7-week period covered by

this inspection period, your conduct of activities was generally characterized by

safety-conscious operations, sound engineering, and good maintenance practices.

During the inspection, a number of personnel errors occurred during the refueling outage.

Consequently, the station error free clock was reset 11 times during the outage due to -

personnel errors. An example of a personnel error resulted in the issuance of a non-cited

violation for the failure to follow an operating procedure and the deenergizing of an engineored

safety features bus. The inspection also identified a concern regarding the failure to correctly

schedule a surveillance test on the primary containment radiation monitoring system. Your

identification of a failure to perform the surveillance test within the surveillance interval was

determined to be a non-cited violation of the Technical Specifications for the failure to adhere to

the Offsite Dose Calculation Manual requirements. Finally, concerns were identified regarding

the quality of the ma'atenance procedures for the high pressure turbine control valves.

Although these are nasafety-related pieces of equipment, insufficient torque applied to

. portions of the valve linkage resulted in unanticipated cycling of the valve internals during valve

manipulation. The valve cycling caused significant fluctuations in reactor power level and

caused operators to insert manual scrams on two occasions. These concerns indicate that

continued attention is needed to reduce personnel errors and to control maintenance activities.

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9812230118 981207

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ADOCK 05000341

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D.'. Gipson

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In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, the

enclosure, and your response will be placed in the NRC Public Document Room.

Sincerely,

/s/ C. Phillips for

Anton Vogel, Chief

Reactor Projects Branch 6

Docket No.: 50-341

License No.: NPF-43

Enclosure:

Inspection Report 50-341/98015(DRP)

cc w/ encl:

N. Peterson, Director, Nuclear Licensing

P. Marquardt, Corporate Legal Department

R. Gaston, Compliance Supervisor

R. Whale, Michigan Public Service Commission

Michigan Department of Environmental Quality

Monroe County, Emergency Management Division

Emergency Management Division, Ml Department

of State Police

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Document Name: G:\\FERM\\FER98015.DRP

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DATE

12/1/98

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12/1/98

12M/98 I

OFFICIAL RECORD COPY

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D. Gipson

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Distribution:

CAC (E Mail)

RPC (E-Mail)

Project Mgr., NRR w/enci

J. Caldwell, Rill w/enci

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C. Pederson, Ril' w/enci

B. Clayton, Rill w/ encl

SRI Fermi w/enct

DRP w/ encl

TSS w/enci

DRS (2) w/enci

Rlli PRR w/enct

PUBLIC IE-01 w/enci

Docket File w/ encl

GREENS

LEO (E-Mail)

DOCDESK (E-Mail)

210102

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