ML20034C945

Forwards Insp Rept 50-285/90-13 on 900301-0414 & Notice of Violation.Violations Involve Failure to Take Adequate Corrective Actions to Control Use of Danger Tags

ML20034C945
Person / Time
Site:	Fort Calhoun
Issue date:	05/24/1990
From:	Collins S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	Powers W OMAHA PUBLIC POWER DISTRICT
Shared Package
ML20034C946	List: IR 05000285/1990013 ML20034C945 ML20034C947
References
NUDOCS 9006040054
Download: ML20034C945 (3)

See also: IR 05000285/1990013

Text

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MAY 241990

In Reply Refer To:

Docket:

50-285/90-13

Omaha Public Power District

.

ATTN:

W. G. Gates, Division Manager

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Nuclear Operations

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444 South 16th Street Mall

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Omaha, Nebraska 68102-2247

Gentlemen:

.

This refers to the inspection conducted by Messrs. P. Harrell, R. Mullikin,

and T. Reis of this office during the period March 1 through April 14, 1990,

of activities authorized by NRC Operating License DPR-40 for the Fort Calhoun

Station, and to the discussion of our findings with you and other members of

your staff at the conclusion of the inspection.

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Areas examined during the inspection included licensee event report followup;

operational safety verification; monthly maintenance, surveillance, security,

and radiological protection observations; in-office review of reports; onsite

followup of events; and installation and testing of modifications. Within

,

these. areas, the inspection. consisted of selective examination of procedures

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and representative records, interviews with personnel, and observations by the

inspectors. The inspection findings are documented in the enclosed inspection

report.

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During this inspection, it was found that certain of your activities were in

violation of NRC requirements. Consequently, you are required to respond to

these violations, in writing, in accordance with the provisions of

Section 2.201 of the NRC's " Rules of Practice," Part 2, Title 10, Code of

Federal Regulations.

Your response should be based on the specifics contained

in the Notice of Violation enclosed with this letter.

The-violations documented in the enclosed inspection-report involve:

The failure to meet the separation criteria of Appendix R of

10 CFR Part 50 for the installation of three of four safety-related

inverters.

This violation was cited because it did not appear that the

licensee performed an adequate analysis, at the time this problem was

identified by the licensee, as to the capability of placing the plant in

a hot shutdown condition in the event that a fire caused the loss of

three of four safety-related inverters.

The failure to take adequate corrective actions to control the use of

danger tags.

This issue had been previously brought to your attention by

the NRC and, more recently, by your quality assurance organization.

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The failure to follow an established procedure that addressed

safety-related activities that resulted in the improper handling of

radiologically-contaminated air filters. This violation was issued based

on the potential for inadvertent radiological exposure of onsite personnel

in the event that the filters were ignited.

It is our understanding that, prior to exceeding a reactor coolant system

temperature of 300*F during restart from the current refueling outage, you

will install a fuse in the cabling located in the east switchgear room to

protect Inverter C output from the effects of a postulated fire in the west

switchgear room. This commitment is discussed in paragraph 5.a of the

enclosed report.

It is also our understanding that you have made the

following commitments, related to plant conditions identified by your design

-basis reconstitution program, to be completed prior to startup from the

current refueling outage:

(1) resolving the overstressed conditions related to

thermal anchor motion stresses in-the main steam, auxiliary feedwater, steam

generator blowdown, and safety injection systems; (2) resolution of the dead

weight loading concerns with the main feedwater and main steam systems; and (3)

resolution of the potential for overpressurizing the auxiliary feedwater lines

between the containment isolation valves.

Should your understanding of these

commitments differ from ours, please contact me immediately.

We have also examined actions you have taken with regard to previously

identified inspection findings. The status of these items is identified in

paragraph 3 of the enclosed report.

The responses directed by this letter and the accompanying Notices are not

subject to the clearance procedures of the Office of Management and Budget as

required by the Paperwork Reduction Act of 1980, PL 96-511.

Should you have any questions concerning this inspection, we will be pleased

to discuss them with you.

Sincerely,

/S

Samuel J. Collins, Director

Division of Reactor Projects

Enclosures:

1.

Appendix A - Notice of Violation

2.

Appendix B - NRC Inspection Report

50-285/90-13

cc w/ enclosures:

LeBoeuf, Lamb, Leiby & MacRae

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ATTN: Harry H. Voigt, Esq.

1333 New Hampshire Avenue, NW

Washington, D.C.

20036

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Omaha Public Power District

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Washington County Board

of Supervisors

ATTN: . Jack.Jensen, Chairman

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Blair, Nebraska 68008

Combustion Engineering, Inc.

ATTN:

Charles B. Brinkman, Manager

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Washington Nuclear Operations

12300 Twinbrook Parkway, Suite 330'

Rockville, Maryland 20852

.

Department of Health

. ATTN: Harold Borchert, Director

Division of Radiological Health

301' Centennial Mall, South

P.O. Box 95007

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Lincoln, Nebraska 68509

Fort Calhoun Station

ATTN:

G. R. Peterson, Manager

P.O : Box 399

' Fort Calhoun, tiebraska 68023

U.S. Nuclear Regulatory Commission

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. ATTN:

Resident Inspector

P.O.' Box 309

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Fort Calhoun, Nebraska- 68023

~ U.S. Nuclear Regulatory Commission

ATTN: -Regional Administrator, Region IV

611 Ryan Plaza Drive, Suite 1000

. Arlington, Texas 76011

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• Project Engineer (DRP/C)

Lisa Shea, RM/ALF

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